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RD EO (guiding documents of the operating organization), ST EO (standards of the operating organization) and STO (standards) of Energoatom Concern OJSC (Rosenergoatom Concern Federal State Unitary Enterprise)

RD EO 0001-93 Methodology for assessing the strength and residual life of general industrial pumps operated at nuclear power plants
RD EO 0003-93 (as amended 1 1998) Collection of methods for incoming and operational control of ion exchangers at nuclear power plants
+STO 1.1.1.002.05.0004-2012 (as amended on 1 2014, 2.3 2015) Water chemistry regime of the primary circuit of power units nuclear power plants with VVER-1000 reactors. Coolant quality standards and means of ensuring them (instead of STP EO 0004-00)
RD EO 0005-93 Regulations for the selection of conditions for sampling aqueous media at NPPs with RBMK and VVER (only for VVER)
+ RD EO 1.1.2.20.0005-2009 Typical instruction on the choice of conditions for the selection of aqueous media and sediments (only for RBMK)
STP EO 0006-02 Water-chemical regime of the secondary circuit of nuclear power plants with VVER-1000 reactors during commissioning of the power unit. Quality standards working environment and means of their provision
RD EO 1.1.2.09.0006-2008 (as amended 1 2010) Laboratory chemical analysis of deposits from heat exchange equipment of nuclear power plants with a high-power channel reactor. Methods for performing measurements (instead of RD EO 0006-93)
RD EO 0010-93 Methodology for determining the rational service rate (number) of NPP operational personnel
RD EO 0011-93 (as amended 1 1994) Verification, Maintenance and repair of systems important to safety and individual systems for the normal operation of NPP power units with an RBMK-1000 reactor. General technical requirements (standard regulations)
+ RD EO 1.1.2.01.0013-2014 (as amended 1 2017, 2 2018) Preparation and decommissioning of the nuclear power plant unit (replacing RD EO 0013-93)
+MU 1.2.4.10.006.0014-2007 Guidelines for testing with increased voltage and monitoring the technical condition of power cable lines at nuclear power plants
MU 1.3.2.06.027.0016-2007 Guidelines for the preparation of reports on the environmental activities of nuclear power plants
RD EO 0022-94 Temporary regulation on the procedure for exporting materials, documents and samples abroad (DSP)
+RD EO 0023-94 Regulations on the procedure for consideration, approval and approval of design, engineering and regulatory documentation in the operating organization Rosenergoatom Concern
RD EO 0028-94 Regulations on the procedure for the transfer of operational information on the operation of nuclear power plants to the Directorate of Operational and Emergency Planning of the Rosenergoatom Concern
RD EO 0029-94 Collection of standard job descriptions management personnel of nuclear power plants
RD EO 0032-94 List of regulatory and technical documents on labor protection in force at enterprises and organizations of the Rosenergoatom concern
STP EO 0035-2005 (as amended on 1 2010, 2.3 2015) Water chemistry regime of the secondary circuit of nuclear power plants with VVER-440 reactors. Working environment quality standards and means of ensuring them (instead of OST 34-37-769-85, STP EO-0035-95)
+ RD EO 1.1.2.19.0036-2008 (as amended 1 2015) Instructions for the investigation and accounting of fires at nuclear power plants (replacing RD EO 0036-95)
RD EO 1.1.2.01.0037-2007 Regulation on the procedure for visiting containment areas of RBMK-1000 reactors (replacing RD EO 0037-95)
RD EO 0038-95 Recommendations for the creation and maintenance of the fund normative documents and information support enterprises of the Rosenergoatom concern and their subdivisions
RD EO 0039-95 Regulatory and methodological requirements for managing the resource characteristics of NPP power unit elements
RD EO 0041-95 Regulations on the organization and implementation of control and inspection at nuclear power plants under construction, in supporting enterprises and organizations
RD EO 0047-04 Decontamination of equipment and pipelines of the multiple forced circulation circuit of nuclear power plants with large-capacity channel reactors. Sample program
RD EO 0048-96 Instructions on the procedure for preparing materials intended for open publication
RD EO 0049-2005 (as amended 1 2007) Model regulation on the labor protection department of a nuclear power plant
RD EO 0050-96 Regulations on checking the readiness of nuclear power plants for operation under conditions of autumn-winter maximum loads
RD EO 0059-96 Regulations on the procedure for issuing a submission to the operating organization for organizations to obtain special permits during the construction of nuclear and / or radiation hazardous facilities
RD EO 1.1.2.01.0061-2015 Metrological support of nuclear power plants. Calibration subsystem for nuclear power plants. Basic provisions (instead of RD EO 0061-97)
+RD EO 1.1.2.29.0062-2015 Metrological support of nuclear power plants. The procedure for assessing and confirming competence in performing calibration work (instead of RD EO 0062-97)
+RD EO 1.1.2.29.0063-2015 Metrological support of nuclear power plants. Calibration marks and hallmarks. Production, application, storage and extinguishing (instead of RD EO 0063-97)
+RD EO 1.1.2.29.0064-2015 Metrological support of nuclear power plants. The procedure for the implementation of inspection control over the activities for the performance of calibration work (instead of RD EO 0064-97)
+STO 1.1.1.01.0069-2017 (as amended 1 2017, 2-5 2018) Rules for the organization of maintenance and repair of systems and equipment of nuclear power plants (replacing RD EO 0069-97, RD 53.025.002-88, RD EO 0019 -92, RD 53.025.016-89)
RD EO 0074-97 Guidelines for the organization and implementation of measures for civil defense, prevention and elimination of emergencies at a nuclear power plant
+RD EO 1.1.2.01.0075-2015 (as amended on 1-2 2017, 3-5 2018) Insurance stock of equipment, assemblies and spare parts for unscheduled repair work at nuclear power plants. Regulation (instead of RD EO 1.1.2.01.0075-2009, RD EO 0075-2005) - chipboard
RD EO 0077-97 Temporary guidelines for calculating the operating capacity of power units of nuclear power plants
RD EO 0078-97 (as amended 1 2017) Instructions for the preparation and conduct of joint integrated emergency response exercises for nuclear power plants, the OPAS group, ATC, forces and means of interested ministries and departments
RD EO 0079-2005 Television control at nuclear power plants. General requirements
RD EO 0080-97 Television control equipment at nuclear power plants. Parameter measurement methods
RD EO 0081-97 Television control equipment at nuclear power plants. Test Methods
RD EO 0082-97 Television control equipment for nuclear power plants. Metrological certification methods
RD EO 1.1.2.12.0085-2014 (as amended 1 2015, 2 2017) Periodicity and standard duration of repair of nuclear power units (replacing RD EO 1.1.2.12.0085-2008, RD EO 0085-97)
+RD EO 1.1.2.01.0086-2014 (as amended 1.2 2017) Quality assurance in the repair of systems and equipment of nuclear power plants. Basic provisions (instead of RD EO 1.1.2.01.0086-2007, RD EO 0086-97)
RD EO 0089-98 Standard provision "On technical, production and operational-dispatching relations of NPPs and Rosenergoatom Concern with power systems, ODU, CDU of UES of Russia, RAO "UES of Russia"
RD EO 0091-98 Regulations on the procedure for reviewing the results of the production and economic activities of nuclear power plants that provide enterprises and organizations of the Rosenergoatom concern
+ RD EO 1.1.2.01.0094-2015 (as amended on 1-2 2016, 3 2017, 4 2018) Development and implementation of technical documents. Regulation (instead of RD EO 1.1.2.01.0094-2011, RD EO 0094-00)
+ RD EO 1.1.2.09.0095-2010 (as amended 1 2015) Guidelines for the analysis of the causes of events significant for safety and reliability, fires, accidents, damage to buildings and structures at nuclear power plants (replacing RD EO 0095-2004, RD EO 0095-98, RD EO 0131-98)
RD EO 0096-98 Standard regulation on resource characteristics management of NPP power unit elements
RD EO 1.1.2.01.0128-2015 (as amended 1 2016) Verification of the state of nuclear safety of a nuclear power plant by an internal commission. Standard provision (instead of RD EO 1.1.2.01.0128-2013, RD EO 0128-98)
RD EO 0129-98 (as amended in 1999, 2004, amended 1 2012) Requirements for the maintenance and repair of the containment prestressing system for NPPs with VVER-1000 and V-320 reactor plants
RD EO 0130-98 (as amended 1 2012) Requirements for the maintenance and repair of the containment prestressing system of NPPs with VVER-1000 and reactor units 302, 338, 187
STO 1.1.1.04.008.0134-2011 (as amended 1 2015) Technical documentation. Occupational safety management system (instead of RD EO 0134-01)
RD EO 1.1.2.01.0135-2012 (as amended 1 2017) Regulations on the procedure for submitting to the Crisis Center and centers technical support technological parameters of power units of nuclear power plants (instead of RD EO 0135-02)
RD EO 1.1.2.99.0136-2015 Nomenclature of operational neutronic calculations for NPPs with RBMK-1000 reactors (instead of RD EO 1.1.2.99.0136-2011, RD EO 0136-2005)
RD EO 1.1.2.09.137-2009 (as amended 1 2012, 2 2015) Integrated methodology for determining the physical and dynamic characteristics of RBMK-1000 reactors (replacing RD EO 0137-98)
+RD EO 0141-98 (as amended 1 2014) Typical technical requirements for methods for assessing the technical condition and residual life of NPP power unit elements
RD EO 0142-99* (2013) Method of ultrasonic testing of studs of flange connectors of NPP equipment (27.28.05.065-2012)
+STO 1.1.1.04.001.0143-2015 (as amended 1-3 2017, 4 2018) Regulations on annual reports on the assessment of the state of safe operation of nuclear power units (replacing ST EO 0143-2005)
+RD EO 1.1.2.29.0144-2013 Metrological support of nuclear power plants. The procedure for organizing and conducting certification of measurement techniques (methods) (instead of RD EO 0144-99)
+RD EO 1.1.2.29.0145-2013 Metrological support of nuclear power plants. The procedure for compiling, agreeing and approving the lists of measurement procedures (methods) used at nuclear power plants (instead of RD EO 0145-99)
RD EO 0147-99 (as amended 1 2017) Method of ultrasonic testing of metal of adapter bushings Du-250 and Du-500 VVER-440
RD EO 0148-99 Method of ultrasonic testing of the welded joint of the branch pipe for the outlet of the tubes of the level gauge and differential gauge with the VVER-440 casing
RD EO 1.1.2.01.0149-2015 (as amended 1 2016, 2.3 2017) Regulations on the central commission of Rosenergoatom Concern OJSC for knowledge testing (instead of RD EO 1.1.2.01.0149-2010, RD EO 0149-04 )
RD EO 0150-2004 Standard programs and methods for conducting physical experiments at power units of nuclear power plants with VVER-1000 reactors
RD EO 0151-2004 (as amended 1 2008) Method for calculating neutronic characteristics based on the data of physical experiments at power units of nuclear power plants with VVER-1000 reactors
+RD EO 1.1.2.01.0152-2013 (as amended 1 2016, 2 2017) Organization of an industry-specific information and analytical system for Rosenergoatom Concern OJSC based on the experience of operating nuclear power plants. Basic provisions (instead of RD EO 0152-2005)
RD EO 0154-99 Methodology for assessing the safety level of steam generators in operation at NPPs with VVER-1000 and VVER-440 reactors (M-01-98)
RD EO 1.1.2.09.0156-2011 Methodology for assessing the residual life of steam generators of nuclear power plants with a VVER-1000 reactor according to the criterion for achieving the maximum minimum value of the heat transfer surface (pipe system) (instead of RD EO 0156-99 (M-03-98))
+RD EO 1.1.2.16.0157-2009 (as amended 1 2013) Defect standards (killing criteria) for heat exchange tubes of steam generators of NPP reactor plants with VVER (instead of (N-04-98))
+RD EO 0159-99 Regulations on the laboratory for psychophysiological support of a nuclear facility (standard)
RD EO 0160-01 (as amended 1) Standard program for checking the state of radiation safety during the operation of nuclear power plants
+ RD EO 1.1.2.25.0161-2009 Requirements for the incoming and operational control of ion-exchange resins for nuclear power plants with pressurized water power reactor (instead of RD EO 0161-2004)
RD EO 1.1.2.01.0163-2016 (as amended 1 2017) Organization of investigation of events significant for safety and reliability at nuclear power plants of Rosenergoatom Concern JSC. Regulation (instead of RD EO 1.1.2.01.0163-2013, RD EO 0163-2005)
RD EO 0173-99 Basic provisions for organizing control over ensuring the safety of nuclear power plants of the Rosenergoatom concern (replacing RD EO 0024-94)
RD EO 1.1.2.08.0175-2007 (as amended 1 2011, 2 2014) Standard procedure for bringing the RBMK-1000 reactor to a critical state (replacing RD EO 0175-99)
STO 1.1.1.004.0179-2013 (as amended 1 2015, 2 2016, 3 2017) Regulations on licensed activities (replacing STO 1.1.1.03.004.0179-2009, RD EO 0179-04)
RD EO 0182-00 Regulations on the accounting and control of radioactive waste and radioactive waste of organizations of the Rosenergoatom concern
RD EO 0183-00 Regulations on the information and analytical system for accounting for radioactive waste and radioactive waste in the Rosenergoatom concern (IAS for radioactive waste and radioactive waste)
+ RD EO 1.1.2.01.0190-2010 (as amended on 1 2013, 2 2014, 3 2015, 4 2016) Regulations on the assessment of the technical condition and residual life of pipeline valves of nuclear power units (replacing RD EO 0190-00)
RD EO 0191-00 Method for mechanized eddy current testing of pin sockets M170 of the VVER-1000 reactor pressure vessel flange (I 45.00.01.VT-98)
RD EO 0192-00 Methodology for Radiation Control of Solid and Solidified Waste of Nuclear Power Plants (standard MVC)
RD EO 0193-00 Methodology for radiation monitoring of liquid radioactive waste from nuclear power plants (standard MVK)
RD EO 0194-00 (as amended 1 2001, amended 1 2008, 2 2011) Guidelines for the collection, processing and use of information on operating experience of nuclear power plants (collection of methodological materials)
RD EO 0195-00 Methodology for assessing the technical condition and residual life of NPP diesel generator sets
RD EO 0197-00 Instructions for office work in the concern "Rosenergoatom"
+RD EO 0198-00 (as amended 1 2002, 2 2004, 3 2007, 4 2008, 5 2012, 6 2013, 7 2014, 8 2017) Maintenance and repair of systems and equipment of nuclear power plants. Assembly of flange connections. General technical requirements
+RD EO 1.1.2.19.0199-2010 Determination of the content of the ferrite phase in the deposited metal of welding and surfacing materials, base metal, welded seams of austenitic stainless steels and anticorrosion surfacing of NPP equipment and pipelines. Instruction (instead of RD EO 0199-00)
+RD EO 1.1.2.29.0202-2013 Metrological support of nuclear power plants. The procedure for organizing and conducting primary calibration of measuring instruments (instead of RD EO 0202-00)
RD EO 1.1.2.29.0203-2014 Metrological support of nuclear power plants. The procedure for the formation and maintenance of an information fund to ensure the uniformity of measurements (instead of RD EO 0203-00)
RD EO 1.1.2.19.0204-2010 Instructions for testing the theoretical knowledge and practical skills of operational personnel of nuclear power plants when issuing Rostekhnadzor permits for the right to conduct work in the field of atomic energy use (replacing RD EO 0204-2006)
RD EO 0206-00 Standard procedure for the use of simulators and / or the use of workstations to test practical skills in conducting technological process(unit management) of nuclear power plants, checked at the examinations when issuing permits from the State Academy of Sciences of Russia for the right to conduct work in the field of using the use of atomic energy to operational personnel of nuclear power plants
+ RD EO 1.1.2.11.0210-2012 Consumption rates of ion exchangers for loading and refilling filters of water treatment plants for nuclear power plants with a high-power channel reactor (instead of RD EO 0210-02)
RD EO 0211-00 Method of ultrasonic testing of welded joints of the connecting pipeline of the pressure compensator of VVER-1000 reactor plant
RD EO 0212-01 Regulation on annual reports on self-assessment of the state of safety culture at nuclear power plants
RD EO 0213-00 Model regulation on the environmental service of a nuclear power plant
RD EO 0215-00 Quality system. Quality Management Program
RD EO 0216-01 Regulations on the procedure for the transfer of operational information on the operation of the NPP to the Department of Operational and Emergency Management of the Rosenergoatom Concern
RD EO 0224-00 A set of guidelines for operational diagnostic systems for NPPs with VVER reactors. Guidelines
RD EO 0226-00 Loose and loose object detection system. Typical operating instructions
RD EO 0228-00 System for vibronoise diagnostics of reactor plants with VVER. Typical operating instructions
RD EO 0230-00 Acoustic system for detecting leaks in the primary coolant of reactor plants with VVER. Typical operating instructions
RD EO 0231-00 Acoustic system for detecting primary coolant leaks. Method for diagnosing equipment of a reactor plant with VVER
RD EO 1.1.2.01.0233-2007 Regulations on the Quality Council of the Federal State Unitary Enterprise Concern "Rosenergoatom"
RD EO 0234-00 (as amended 1 2014) Method for assessing the technical condition and residual life of the metal structures of the RBMK-1000 reactor
RD EO 0235-00 Procedure for entering constants into the "Prisma" program for calculating the operational parameters of the cores of the RBMK-1000 reactors in the SCS "Skala" system
RD EO 1.1.2.03.0237-2016 (as amended on 1-2 2017, 3-6 2018) Repair campaign management. Rules (instead of RD EO 1.1.2.03.0237-2014, RD EO 0237-01)
STO 1.1.1.07.003.0252-2014 Laboratory chemical analysis of aqueous media of nuclear power plants with a high-power channel reactor. Measurement methods (instead of STO 1.1.1.07.003.0252-2009, RD EO 0252-02)
+RD EO 1.1.2.25.0274-2013 Metrological support of nuclear power plants. Verification laboratories of nuclear power plants. Technical requirements (instead of RD EO 0274-01)
RD EO 0276-01 (as amended 1) Regulations on the procedure for the transfer of operational information on the operation of a nuclear power plant to the Department of Operational and Emergency Management of the Rosenergoatom Concern
+STO 1.1.1.01.007.0281-2010 (as amended 1 2010, 2 2013, 3 2014, 4 2015, 5 2016, 6 2017, 7-8 2018) Management of resource characteristics of elements of power units of nuclear power plants (instead of RD EO 0281-01 )
RD EO 0282-2005 Instructions for metallographic monitoring of the condition of the metal of equipment and pipelines at nuclear power plants
+RD EO 1.1.2.25.0283-2016 Contents of programs for comprehensive inspection of nuclear facilities to extend their service life. Requirements (instead of RD EO 1.1.2.22.0283-2008, RD EO 0283-01)
RD EO 1.1.2.25.0286-2014 (as amended 1 2016, 2 2017) Nomenclature of groups of the same type of welded joints and surfacing of equipment and pipelines of NPP systems with RP VVER-440, VVER-1000 and RBMK-1000. Requirements (instead of RD EO 0286-01)
RD EO 0287-01 Guidelines. Monitoring of the technical condition and assessment of the residual service life of medium and low voltage power cables with polyethylene insulation. FSUE "NIIP"
RD EO 0288-01 Guidelines. Monitoring of the technical condition and assessment of the residual service life of medium and low voltage power cables with oil-paper insulation. FSUE "NIIP"
RD EO 0289-01 Methodology and program for assessing the technical condition and residual life of the equipment for the in-reactor control of energy release of the SVRK of NPP power units after the development of durability indicators
RD EO 0290-01 Methodology and program for assessing the technical condition and residual life of the neutron flux control equipment complex NFME
RD EO 1.1.2.05.0291-2016 (as amended 1 2017) Ensuring the quality of work when extending the service life of nuclear facilities. Requirements (instead of RD EO 1.1.2.22.0291-2008, RD EO 0291-01)
+ RD EO 1.1.2.25.0295-2011 (as amended 1 2014) Executive documents for repair work using welding. Types and requirements for content and design (instead of RD EO 0295-2004, RD 53.025.014-89)
RD EO 0296-01 (as amended 1 2002, 2 2005, 3 2008, amended 1 2004) Guidelines for compiling a technical report on the efficiency and thermal efficiency of a nuclear power plant
RD EO 0298-01 Methods for diagnosing the technical condition and evaluating the residual service life of cables with polyolefin insulation by measuring the induction period and the temperature of the onset of oxidation. FSUE "NIIP"
RD EO 0299-01 Method for diagnosing the technical condition and assessing the residual service life of cables and wires with polytetrafluoroethylene insulation by measurement specific heat melting. FSUE "NIIP"
RD EO 0301-01 Methodology and program for assessing the technical condition and residual life of blocks of the modernized unified complex of technical means (UKTS-M blocks)
RD EO 0303-01 Systems for operational diagnostics of equipment and pipelines of reactor plants with VVER. Basic provisions
RD EO 0304-01 Regulations on the procedure for access of rescuers from the Novovoronezh Emergency and Technical Center of the Rosenergoatom Concern to nuclear power plants and enterprises incorporating research reactors in an emergency mode for conducting radiation hazardous rescue operations
RD EO 0306-01 Methodology and program for assessing the technical condition and residual life of the electronic part of the automated control system for the turbine plant EC ASUT-1000-2
RD EO 0307-01 Method for measuring the amount of engagement in the telescopic connection of the upper paths (TST) of RBMK-1000 reactors
+RD EO 1.1.2.01.0308-2015 (as amended 1 2016, 2.3 2017) Procedure for collecting, processing, storing and transmitting information on failures and damages of nuclear power plant equipment. Regulation (instead of RD EO 1.1.2.01.0308-2012, RD EO 0308-02)
RD EO 1.1.2.99.0309-2014 Radiation monitoring equipment. Measuring channels of ambient dose equivalent rate. Verification procedure
RD EO 1.1.2.99.0310-2014 Radiation monitoring equipment. Measuring channels for the volumetric activity of gamma-emitting radionuclides in a liquid. Verification procedure
RD EO 1.1.2.99.0311-2014 Radiation monitoring equipment. Measuring channels of volumetric activity of beta-emitting radionuclides of inert gases. Verification procedure
RD EO 1.1.2.99.0312-2014 Radiation monitoring equipment. Measuring channels of volumetric activity of aerosol radionuclides. Verification procedure
RD EO 1.1.2.99.0313-2014 Radiation monitoring equipment. Measuring channels of volumetric activity of nuclides of vaporous iodine-131. Verification procedure
RD EO 0314-01 Program-methodology for carrying out work to determine and justify the residual life of the equipment of the fuel rods GII2-01, GII2-01-01 RP EGP-6 in order to extend the life of the Bilibino NPP power units
RD EO 0315-01 Program-method of carrying out work to determine and justify the residual life of the equipment of the SVRK VET-01, VET-02 RP EGP-6 in order to extend the life of the Bilibino NPP power units
RD EO 1.1.2.99.0316-2012 Standard instruction for maintaining the water-chemistry regime of the primary circuit of nuclear power plants with VVER-1000 reactors (replacing RD EO 0316-01)
+RD EO 1.1.2.01.0318-2014 Metrological support of nuclear power plants. Metrological support non-destructive testing and diagnostics. Basic provisions (instead of RD EO 0318-01)
RD EO 0322-02 Regulations for determining the technical condition and managing the aging of cables at nuclear power plants. FSUE "NIIP"
+RD EO 0324-2004 Regulations on the procedure for working with documents of the Technical Archive of Rosenergoatom Concern
+ STO 1.1.1.01.006.0327-2015 (as amended 1 2016, 2 2017) Extending the life of the nuclear power unit (replacing STO 1.1.1.01.006.0327-2008, RD EO 0327-01)
+RD EO 1.1.2.25.0329-2013 (as amended 1 2017) Organization of maintenance, operation and construction of dispatcher and process control facilities at nuclear power facilities. General technical requirements (instead of RD EO 0329-01)
+ RD EO 1.1.2.05.0330-2012 (as amended 1 2014, 2 2016) Guidelines for strength analysis of equipment and pipelines of RBMK, VVER, and PPG reactor plants at the operational stage, including operation beyond the design service life (instead of RD EO 0330-01)
RD EO 1.1.2.01.0331-2017 Transmission of operational information on the operation of nuclear power plants. Regulation (instead of RD EO 1.1.2.01.0331-2010, RD EO 0331-2006)
RD EO 0333-02 Methodology for Radiation Control of Primary Coolant Leakage into Water in Steam Generators at NPPs with VVER-1000 (Typical MVK)
RD EO 0334-02 Method for calculating the leakage of the primary coolant into the water of steam generators of NPPs with VVER-1000 (standard)
RD EO 0335-02 Software tool "CHECKMOD" (v.3.0.1000R) for calculating primary coolant leaks into the water of NPP steam generators with VVER-1000 (user manual)
RD EO 0336-02 Methodology for Radiation Monitoring of Primary Coolant Leakage into Water in Steam Generators at NPPs with VVER-440 (Typical MVK)
RD EO 0337-02 Method for calculating the leakage of the primary coolant into the water of steam generators of NPPs with VVER-440 (standard)
RD EO 0338-02 Software tool "CHECKMOD" for calculating the leakage of the primary coolant into the water of steam generators of NPPs with VVER-440 (v.3.0.440). User's Manual
RD EO 0339-02 Methodology for measuring the specific activity of reference radionuclides in the primary coolant and blowdown water during radiation monitoring of steam generator leaks at NPPs with VVER (typical MVI)
RD EO 0340-02 Landfills for disposal of NPP waste containing radionuclides within acceptable limits. Basic technical requirements for design
RD EO 0345-02 Method for semi-automatic ultrasonic testing of welded joints in pipelines Du300 and RGC of power units of the RBMK-1000 type
RD EO 0350-02 Method for Predicting the Temperature Dependence of Fracture Toughness of VVER-440 and VVER-1000 Reactor Pressure Vessel Materials
RD EO 0351-02 Guidelines for the calculation of the strength of VKU RP VVER-440
+RD EO 0352-02 Method for the reconstruction of specimens for impact and three-point static bending tests of VVER-type reactor vessel materials
RD EO 0353-02 Methodology for determining the service life of VVER nuclear reactor vessels during operation (MRK-SKhR-2000)
RD EO 1.1.2.29.0354-2012 Procedure for monitoring the neutron-physical characteristics of the RBMK-1000 passport (replacing RD EO 0354-2004)
RD EO 0355-02 Regulations on the organization of the work of the commission of the Rosenergoatom concern to investigate the causes of equipment malfunctions, accidents and uncontrolled combustion at nuclear power plants and supporting enterprises
RD EO 0356-02 Technical requirements for the design of storage facilities for packages of solid and solidified radioactive waste in reinforced concrete protective non-returnable containers of the NZK-150-1.5P type
RD EO 0357-02 Program and methodology for checking the state of the NPP physical protection system
RD EO 0358-02 Guidelines for the validation of symptom-oriented flowcharts emergency instructions and support procedures for NPP power units with RBMK-1000 reactor
RD EO 0359-04 Guidelines for the development and implementation of symptom-oriented emergency instructions and support procedures for NPP power units with RBMK-1000 reactor
RD EO 0360-02 Guidelines for the Form of Presentation of Flowcharts of Symptom-Oriented Emergency Instructions and Support Procedures for NPP Power Units with RBMK-1000 Reactor
RD EO 0361-02 Guidelines for Verification of Flow Diagrams of Symptom-Oriented Emergency Instructions and Support Procedures for NPP Power Units with RBMK-1000 Reactor
RD EO 0362-02 Methodology for assessing the technical condition and residual life of the graphite stack of the RBMK-1000 reactor
+RD EO 1.1.2.25.0363-2011 Digital (microprocessor) devices for relay protection and automation of electrical installations for auxiliary needs of normal operation, systems important for safety and emergency power supply of nuclear power plants. General technical requirements (instead of RD EO 0363-02) (OTT to TsURZA SN NPP)
RD EO 0364-02 Program-method of carrying out work to determine and justify the residual life of the drive of the AZ CPS of the EGP-6 reactor plant in order to extend the life of the Bilibino NPP power units
RD EO 0365-02 Program-method of carrying out work to determine and justify the residual life of the drive RS-AZ CPS RP EGP-6 in order to extend the life of the Bilibino NPP power units
RD EO 0366-02 Program-method of carrying out work to determine and justify the residual life of the drive of the AR CPS RP EGP-6 in order to extend the life of the Bilibino NPP power units
RD EO 0367-02 Program-method of carrying out work to determine and justify the residual life of the drive RR CPS RI EGP-6 in order to extend the life of the power units of the Bilibino NPP
+STO 1.1.1.07.003.0368-2017 Input and operational control of ion exchangers at nuclear power plants. Measurement methods (instead of STO 1.1.1.07.003.0368-2007, RD EO 0368-02)
RD EO 1.1.2.07.0386-2009 (as amended in 2009, 2012) Procedure for preparation, approval, signing, control and storage of contractual documentation in Energoatom Concern OJSC (instead of RD EO 1.1.2.07.0386-2007, RD EO 0386 -2004)
STO 1.1.1.07.003.0387-2009 Laboratory analysis of gaseous media of nuclear power plants with high-power channel reactor. Methods for performing measurements (instead of RD EO 0387-02)
RD EO 0407-02 Methodology and program for assessing the technical condition and residual life of 22BP36 power supplies used in AZ, PZ, SB systems of classes 2U, 3NU, 3N (important for safety)
RD EO 0408-02 Standard technological regulations. Preservation of equipment and pipelines of the secondary circuits of NPPs with VVER and the use of film-forming amines
RD EO 0417-02 Time limits for eddy current testing of 1000 heat exchange tubes of steam generators of operating nuclear power plants with power units of the VVER-1000, 440 type by the Intercontrol installation
RD EO 0419-02 (as amended 1) Guidelines for determining the technical condition of the water cooling channels of the stator windings of turbogenerators
RD EO 0420-02 Standard regulation on the diagnostic division of NPP (in terms of applicability)
RD EO 0421-02 Method for predicting the strength characteristics of the reactor pressure vessel material under additional irradiation
RD EO 1.1.2.11.0422-2012 (as amended 1.2 2013) Consumption rates of ion exchangers for loading and refilling filters of water treatment plants for nuclear power plants with pressurized water power reactor (replacing RD EO 0422-02)
RD EO 0423-02 Guidelines on the choice of initial data and parameters in the calculation of the radiation consequences of accidents at nuclear power plants
RD EO 0424-02 Method for automated television monitoring of the inner surface of VVER type reactor vessels
RD EO 0425-02 Methodology for automated television monitoring of internals of VVER type reactors
RD EO 0429-02 Guidelines. The procedure for transferring the measuring channels of the automated radiation monitoring system to the category of indicators
+ RD EO 1.1.2.29.0430-2011 (as amended 1 2014) The procedure for engaging contractors to perform work to monitor the condition of the metal of equipment and pipelines of nuclear power plants (replacing RD EO 0430-02)
RD EO 1.1.2.29.0431-2014 (as amended 1 2015) Metrological support of nuclear power plants. Certification of personnel of metrological services. Organization and procedure (instead of RD EO 0431-02)
RD EO 0432-02 Regulations on the internal system of export control of the concern "Rosenergoatom"
RD EO 0434-03 Instructions for the technical control of the corrosion state of equipment and pipelines of nuclear power plants with RBMK-1000 using indicator samples
RD EO 0435-02 Guidelines for the technical justification for the safety of storage of radioactive waste from nuclear power plants using a reinforced concrete protective non-returnable container of the type NZK-150-1.5P, NZK-150-1.5 (C)
RD EO 0438-02 Methodology for assessing the technical condition and residual life of ABP-1500
RD EO 0439-02 Procedure for assessing the resistance of elements of monitoring and control systems to electromagnetic effects during modernization and extension of operation at nuclear power plants
+ RD EO 1.1.2.01.0440-2013 (as amended 1 2017) Technical documentation. Regulations on internal expertise design and estimate documentation for modernization and reconstruction (instead of RD EO 1.1.2.01.0440-2007, RD EO 0440-02)
STO 1.1.1.01.004.0441-2016 Training programs for the position (profession) and maintaining the qualifications of employees of Rosenergoatom Concern JSC. Basic requirements of nuclear power plant personnel. Basic requirements (instead of RD EO 0441-03)
+ RD EO 1.1.2.01.0442-2013 Regulations on the procedure for the development and issuance of design and working documentation for modernization and reconstruction (instead of RD EO 1.1.2.01.0442-2007, RD EO 0442-03)
RD EO 0443-03 Temporary regulation on the procedure for monitoring the passport characteristics of the reactor plant with BN-600
+RD EO 1.1.2.05.0444-2016 Requirements for the operation, organization and testing of transformer and turbine oils at nuclear power plants (instead of RD EO 1.1.2.05.0444-2009, RD EO 0444-03)
RD EO 1.1.2.25.0445-2016 Requirements for the content of the album of neutronic characteristics of fuel loads of VVER-1000 and VVER-1200 reactors (replacing RD EO 0445-03)
RD EO 0446-03 Program-method for determining the technical condition and justification of the residual life of the metal structures of the EGP-6 reactor units of the power units of the Bilibino NPP
RD EO 1.1.2.01.0448-2012 Regulations on the certification of NPP personnel with RBMK-1000 and BN reactors performing operational neutron-physical calculations (replacing RD EO 0448-03)
RD EO 0449-03 Time limits for monitoring the integrity of the jumpers of one PGV-1000 collector using the VD-73 NCU device using the MD-2 VS manipulator at operating NPPs
RD EO 0451-03 Water coolant deaeration during the start-up of power units of nuclear power plants with RBMK-1000 reactors. Sample program
+ RD EO 1.1.2.99.0457-2011 Standard program for dosimetric monitoring of external exposure at nuclear power plants (replacing RD EO 0457-03)
RD EO 0458-03 Standard procedure for measuring the individual dose equivalent Нр(10) of neutron radiation using an individual dosimeter based on the albedo principle during individual dosimetric monitoring (IDC) of NPP personnel
+RD EO 1.1.2.99.0460-2013 Standard program for inspection of hydraulic structures of nuclear power plants
+ RD EO 1.1.2.01.0461-2013 (as amended 1 2015) Regulations on the sectoral system of supervision over the safety of hydraulic structures of nuclear power plants (replacing RD EO 1.1.2.01.0461-2008, RD EO 0461-03)
+RD EO 0462-03 (2015) Methodology for justifying the service life of building structures of buildings and structures of nuclear power plants
RD EO 0463-2005 Regulations on the organization of the operation and maintenance of the equipment of the satellite dispatch and technological communication system of the Rosenergoatom concern
RD EO 0464-03 (as amended 1 2007) Guidelines for performing measurements of nuclear materials at nuclear power plants of the Rosenergoatom concern for the purpose of accounting and control
+ STO 1.1.1.01.999.0466-2018 Basic rules for ensuring environmental protection at nuclear power plants (replacing STO 1.1.1.01.999.0466-2008, RD EO 0466-03 (EPEE AS-03))
RD EO 1.1.2.05.0468-2011 (as amended 1 2014) Ensuring the quality of work on the repair of nuclear power plant equipment using welding. Manual (instead of RD EO 0468-03)
+STO 1.1.1.01.004.0469-2008 (as amended 1, 2 2011) Preparation and conduct of emergency drills for nuclear power plant personnel. Basic requirements (instead of RD EO 0469-03)
RD EO 0472-03 Method of quantitative chemical analysis. Determination of nitrate ions by the potentiometric method on the pH-meter-ionomer "EKOTEST-120" in technological wastewater of nuclear power plants
RD EO 0473-03 Method of quantitative chemical analysis. Determination of chloride ions by the potentiometric method on a pH-meter-ionomer "EKOTEST-120" in process wastewater from nuclear power plants
RD EO 0474-03 Method of quantitative chemical analysis. Determination of sodium by the potentiometric method on the pH-meter-ionomer "EKOTEST-120" in process wastewater of nuclear power plants
RD EO 0475-03 Method of quantitative chemical analysis. Determination of potassium ions by the potentiometric method on a pH-meter-ionomer "EKOTEST-120" in technological wastewater of nuclear power plants
RD EO 0476-03 Methodology for assessing the technical condition and residual life of the channels of the control and protection system of the RBMK-1000 reactor
RD EO 0478-2003 Methodology for technical diagnostics and extension of the design service life of vessels and heat exchangers of systems important for the safety of Leningrad NPP power units with RBMK-1000 reactors
+ RD EO 0479-03 (as amended 1 2008, 2 2017) Standard action plan for personnel in the event of a radiation accident at a nuclear power plant of the Rosenergoatom concern
+ RD EO 1.1.2.01.0480-2009 Regulations on accreditation and audit of organizations for the performance of work, provision of services for the repair of nuclear power plants of Energoatom Concern OJSC (replacing RD EO 0480-03)
+STO 1.1.1.01.004.0484-2008 Training for the position and maintaining the qualifications of instructors for training nuclear power plant personnel. Basic requirements (instead of RD EO 0484-03)
RD EO 1.1.2.01.0485-2012 (as amended 1.2 2014, 3-5 2017) Regulations on Accounting and Control of Nuclear Materials (replacing RD EO 0485-03)
RD EO 1.1.1.2.025.0487-2015 (as amended 1 2017) Development of terms of reference, testing and conditions for the use of non-destructive testing tools and methods at nuclear power plants. Requirements (instead of RD EO 0487-05)
STO 1.1.1.01.004.0492-2008 (as amended 1 2013) Certification of educational and training divisions of nuclear power plants. Requirements for the organization and conduct (instead of RD EO 0492-03)
RD EO 0496-03 Guidelines for determining the condition and extending the service life of nuclear power plant cables, taking into account the impact on them of damaging factors of design basis accidents. FSUE "NIIP"
RD EO 0497-03 Method for measuring the mass concentration of anionic surfactants on the liquid analyzer "Fluorat-02-3M"
RD EO 0498-03 Methodology for measuring the mass concentration of cationic surfactants on the Fluorat-02-3M liquid analyzer
RD EO 1.1.2.25.0500-2015 (as amended 1.2 2016, 3 2017) Nomenclature of operational neutron-physical calculations and measurements for VVER-440 fuel loads. Requirements (instead of RD EO 1.1.2.25.0500-2008, RD EO 0500-03)
RD EO 1.1.2.25.0501-2015 (as amended 1.2 2016) Nomenclature of operational neutron-physical calculations and measurements for VVER-1000 fuel loads. Requirements (instead of RD EO 0501-03)
RD EO 0502-03 Standard program for testing and setting the main safety valves of power units with RBMK-1000 reactors
RD EO 0504-03 Guidelines for the search and localization of defects in the control cables of nuclear power plants. FSUE "NIIP"
+RD EO 0505-03 Instructions for metal steeloscopy
RD EO 1.1.2.09.0510-2010 Non-destructive testing. Adhesion of antifriction babbitt coating with steel base of bearing elements of nuclear power plant equipment. Ultrasonic method (instead of RD EO 0510-03)
RD EO 0511-03 (as amended 1, 2 2011) The program for monitoring the metal of the rotors of NPP turbine generators during operation
RD EO 0513-03 Application of the concept of "exclusion of gaps" for pipelines and collectors Du 300 KMPTS and SVB of NPP power units with RBMK-1000
+ RD EO 1.1.2.11.0515-2014 Accuracy standards for measurements of the main heat engineering quantities for nuclear power plants with water-cooled power reactors (instead of RD EO 0515-2004)
+ RD EO 1.1.2.01.0516-2016 Regulations on the metrological service of Rosenergoatom Concern JSC (instead of RD EO 1.1.2.01.0516-2011, RD EO 0516-2004)
+RD EO 0517-2004 General technical requirements for load limiters for overhead cranes of nuclear power plants
RD EO 1.1.2.10.0521-2008 (as amended 1 2011, 2 2017) Fuel assemblies for nuclear reactors of the VVER-1000 type. Typical procedure for checking the tightness of fuel element cladding (instead of RD EO 0521-2004)
RD EO 1.1.2.10.0522-2008 (as amended 1 2011, 2 2017) Fuel assemblies for nuclear reactors of the VVER-440 type. Typical method for checking the tightness of fuel element claddings (instead of RD EO 0522-2004)
RD EO 0524-2004 Guidelines for substantiating the safety concept "Leak before destruction" for pipelines of the primary circuit of VVER-440 of the first generation
+ RD EO 1.1.2.25.0526-2016 Contents of the program for preparing nuclear facilities for an additional service life (replacing RD EO 0526-2004)
RD EO 0527-2004 (as amended 1 2006, 2 2008) Technological instruction "Maintenance of NPP power units with RBMK reactors by high-temperature induction heat treatment unit for austenization of welded joints of the RGK bottom welding unit"
RD EO 0528-2004 Guidelines for the application of a systematic approach to the training of nuclear power plant personnel
RD EO 0529-2004 Methodology for measuring the degree of filling by the extraction-gravimetric method
RD EO 0530-2004 Methodology for performing humidity measurements by the gravimetric method
RD EO 0532-2004 (as amended 1) Fuel assemblies for nuclear reactors of the VVER type. Standard procedure for performing measurements in the control of tightness of fuel element claddings
RD EO 0535-2004 (as amended 1 2007) The procedure for certification of work on labor protection in the concern "Rosenergoatom"
RD EO 1.1.2.99.0538-2011 Methodology for assessing the technical condition and residual life of the containments of nuclear power plants with VVER-1000 (replacing RD EO 0538-2004)
+ STO 1.1.1.04.003.0542-2014 (as amended 1 2015, 2 2016, 3 2017, 4 2018) Procedure for organizing and carrying out the modernization of systems and equipment (instead of STO 1.1.1.04.003.0542-2012, ST EO 0542-2006)
RD EO 0543-2004 (as amended 1 2017) Method for automated ultrasonic testing of welded joints in pipelines Du 800 of the primary circuit of RBMK reactors using the AVGUR 5.2 system
RD EO 0544-2004 Method for automated ultrasonic testing of welded joints in pipelines DN 300 of RBMK reactors using the AVGUR 5.2 system
RD EO 1.1.2.09.0545-2010 Non-destructive testing. Adhesion of antifriction babbitt coating with steel base of bearing elements of nuclear power plant equipment. Capillary method (instead of RD EO 0545-2004)
RD EO 0546-2004 Technique for automated ultrasonic testing of the welded joint for welding the casing and the base metal of the extension of the upper tract of the TC of the RBMK-1000 reactor
RD EO 1.1.2.25.0549-2010 (as amended 1 2016) Educational materials to prepare for the position and maintain the qualifications of nuclear power plant personnel. Basic requirements (instead of RD EO 0549-2004)
RD EO 0550-2005 Thermal insulation of equipment and pipelines of the reactor plant of nuclear power plants with VVER-type reactors. General requirements
RD EO 0553-2004 Standard regulation on working with a reserve for filling managerial positions in the Rosenergoatom concern
RD EO 0558-2004 (as amended 1 2007) Quality Assurance Program for Confirmatory Measurements of Nuclear Materials at Nuclear Power Plants of the Rosenergoatom Concern
RD EO 0559-2004 Methodology for assessing the economic efficiency of extending the life of NPP power units
RD EO 0560-2004 Method for automated ultrasonic testing of a welded joint 10 of welding of a transition sleeve to a branch pipe of a VVER-440 reactor using the AVGUR 5.2 system
RD EO 0562-2004 Typical content of the action plan for the prevention and elimination of emergency situations of natural and man-made nature of the supply enterprise
RD EO 1.1.2.10.0565-2010 (as amended 1 2015) Fuel assemblies for nuclear reactors of the RBMK-1000 type. Standard procedure for radiation control of tightness of fuel element claddings based on an automated system
RD EO 0566-2004 Typical content of a civil defense plan for a nuclear power plant
RD EO 0567-2004 Technological instruction for the maintenance of NPP power units with RBMK reactors with an installation for induction heat treatment of welded joints in pipelines Du 300, which ensures the creation of compressive stresses in the root of the weld
+ RD EO 1.1.2.99.0570-2013 (as amended 1 2015) Instructions for the inspection of underwater parts of hydraulic structures of nuclear power plants (replacing RD EO 1.1.2.99.0570-2011, RD EO 0570-2004)
RD EO 1.1.2.11.0571-2015 (as amended 1 2017) Standards for permissible wall thicknesses of pipeline elements made of carbon steels during erosion-corrosion wear (instead of RD EO 1.1.2.11.0571-2010, RD EO 0571-2006)
RD EO 1.1.2.25.0572-2010 (as amended 1 2016) Evaluation of the organization and conduct of training for the position and maintaining the qualifications of nuclear power plant personnel. Basic requirements (instead of RD EO 0572-2004)
+ RD EO 1.1.2.01.0573-2019 Carrying out inspections of the implementation of quality assurance programs of Rosenergoatom Concern JSC and organizations performing work and providing services to the operating organization. Position
RD EO 0574-2004 Model regulation on the certification of managers and specialists of the Rosenergoatom concern
+RD EO 0577-2004 Typical enlarged standards for the number of personnel in the main activity (industrial and production personnel) of nuclear power plants with VVER, RBMK-1000 and BN-600 reactors
RD EO 0578-2005 Model regulation on the department of technical diagnostics, flaw detection and technical control nuclear power plants
+RD EO 1.1.2.03.0579-2011 (as amended 1 2014) Organization of work to maintain the serviceability of the means of the automated process control system of nuclear power plants, thermal automation and measurements. Rules (instead of RD EO 0579-2004)
RD EO 1.1.2.25.0582-2011 (as amended 1 2017) Database for the decommissioning of nuclear power plants. General requirements (instead of RD EO 0582-2005)
RD EO 0583-2004 Certification of personnel in the field of non-destructive and destructive testing of equipment and pipelines, elements and structures of nuclear power plants
+RD EO 0586-2004 Standards for the design of thermal insulation of equipment and pipelines of nuclear power plants
+RD EO 0588-2004 Guidelines. Storage and operation of current transformers of the TFRM type, voltage classes 330-750 kV
RD EO 0593-2004 Guidelines for the organization of work when handling hazardous NPP waste
+ RD EO 0597-2004 Guidelines for monitoring the condition of current transformers based on chromatographic analysis of dissolved gases (CHARG) in oil
RD EO 0599-2005 Standard regulation on the personnel department of the branch of the Rosenergoatom concern - a nuclear power plant
RD EO 0601-2005 Methodology for automated ultrasonic testing of NPP fasteners
RD EO 0602-2005 Methodology for automated eddy current testing of the nests of the main connector of the VVER-1000 reactor
RD EO 0603-2005 Methodology for assessing the technical condition and residual life of the technological channels of the RBMK-1000 reactor
+RD EO 0604-2005 Guidelines. Monitoring of environmental protection at nuclear power plants
RD EO 0606-2005 Methodology for calculating the resistance to brittle fracture of reactor vessels of NPPs with VVER during operation
RD EO 0608-2005 (as amended 1 2007, 4 2008) Guidelines for Accounting and Control of Nuclear Materials in the Hot Cell of the Novovoronezh Nuclear Power Plant Branch of Rosenergoatom Concern
RD EO 0609-2005 Method for automated ultrasonic testing of welded joints in austenitic pipelines DN 300 and measuring the geometric dimensions of identified discontinuities (MCRPN cracks)
RD EO 0610-2005 Method for manual ultrasonic testing of welded joints in austenitic pipelines DN 300 and measuring the geometric dimensions of identified discontinuities (MCRPN cracks)
RD EO 1.1.2.29.0612-2015 Procedure for putting into operation, use and modernization of software designed for neutron-physical calculations to ensure the operation of NPPs with RBMK-1000 reactors (replacing RD EO 0612-2005)
+RD EO 1.1.2.25.0614-2010 Educational premises of educational and training divisions of nuclear power plants. Equipment requirements (instead of RD EO 0614-2005)
RD EO 0615-2005 Guidelines for the detection of short circuits in steel sheets of the stator core by the electromagnetic method during the repair of turbogenerators
RD EO 0616-2005 (as amended 1 2007, 2 2008, 3 2011) The procedure for transferring data on nuclear materials from nuclear power plants to the information system for accounting and control of nuclear materials of the Rosenergoatom concern
RD EO 0619-2005 Program for managing the service life of electrical and electronic elements of nuclear power plants. Requirements for development and implementation. FSUE "NIIP"
RD EO 0620-2005 Standard operating instructions for special water treatment plants, including pre-wash filters, using pre-wash ion-exchange filtration technology
STO 1.1.1.02.005.0621-2007 Water-chemical regime of the primary circuit of VVER-440 power units without corrosion-resistant surfacing of the hull. Coolant quality standards and means of ensuring them (instead of ST EO 0621-2005)
ST EO 0622-2005 (as amended 1 2009, 2 2015) Water-chemistry regime of the primary circuit of power units of nuclear power plants with VVER-440 reactors with corrosion-resistant shell surfacing. Coolant quality standards and means of ensuring them
RD EO 1.1.2.01.0623-2015 (as amended 1.2 2017) Repair exchange fund of equipment, assemblies and spare parts. Regulation (instead of RD EO 1.1.2.01.0623-2009, RD EO 0623-2005)
+ RD EO 1.1.2.99.0624-2017 Monitoring of building structures of nuclear power plants (replacing RD EO 1.1.2.99.0624-2011, RD EO 0624-2005)
STO 1.1.1.04.006.0627-2008 (as amended 1 2009, 2 2011) On rationalization work in Energoatom Concern OJSC
RD EO 0629-2005 Guidelines for the detection of cracks on the inner surface of the shroud rings of rotors using the ultrasonic method without removing the shroud rings from the rotor during the repair of turbogenerators
+RD EO 0630-2005 Guidelines for the control of metal in order to extend the life of turbines of nuclear power plants beyond the designated period
RD EO 0631-2006 Fuel assemblies for nuclear reactors of the VVER type. Preparation and processing of initial data for the calculation of the WANO nuclear fuel tightness index
RD EO 0637-2006 (as amended 1 2008) Regulations for the interaction of personnel of nuclear power plants, Crisis Center, Technical Support Centers of FSUE Concern "Rosenergoatom" when transmitting data to OASKRO NPP
RD EO 0638-2005 Guidelines for the organization of local warning systems in areas where nuclear power plants are located
RD EO 0641-2006 (as amended 1 2008) Regulations for the interaction of personnel of nuclear power plants and the Crisis Center of the Federal State Unitary Enterprise Concern "Rosenergoatom" when transmitting data to AKRB AS
+STO 1.1.1.01.004.0644-2010 (as amended 1 2014) Regulations on the procedure for recruitment and advance training of personnel for nuclear power plants (replacing ST EO 0644-2005)
STO 1.1.1.01.002.0646-2012 (as amended 1 2014, 2.3 2016) Analysis and use of operating experience of nuclear power plants. Basic provisions
RD EO 0648-2005 Regulations on the technical diagnostics of electrically driven industrial pipeline valves at power units of nuclear power plants
RD EO 1.1.2.01.0654-2014 (as amended 1 2015, 2 2017) Regulations on the quality control of construction and installation works by the developer and technical customer during the construction of nuclear power plants (replacing RD EO 0654-2006)
RD EO 1.1.2.25.0655-2014 (as amended 1 2017) Requirements for the technical content of quality assurance programs for the construction of nuclear facilities (replacing RD EO 0655-2006)
+RD EO 0658-2006 (as amended 1 2009) Requirements for the conservation and maintenance of objects of work in progress in a state suitable for preservation
+ STO 1.1.1.01.003.0667-2016 Classification of technical documentation of Rosenergoatom Concern JSC
+ STO 1.1.1.01.003.0668-2013 (as amended 1 2016) Technical documentation. Rules for the construction, presentation, design and designation of regulatory documents
RD EO 0669-2006 (as amended 1 2013) Steels and alloys of pipelines and elements of nuclear power plant equipment. Definition chemical composition atomic emission method spectral analysis. Methodical instruction
+STO 1.1.1.01.003.0670-2015 (as amended 1 2018) Circulation of technical documentation of Rosenergoatom Concern JSC. General requirements
STO 1.1.1.02.001.0673-2017 (as amended 1 2018) Occupational safety rules for the operation of thermal mechanical equipment and heating networks of nuclear power plants of Rosenergoatom Concern JSC (replacing RD 34.03.201-97 for NPPs)
RD EO 0674-2006 (as amended 1 2007, 2 2008, 3 2011) Instructions for filling out reporting forms on nuclear materials at nuclear power plants of the Federal State Unitary Enterprise Concern "Rosenergoatom"
+ STO 1.1.1.07.001.0675-2017 Nuclear power plants. Equipment, devices, means of monitoring and control systems. General technical requirements
STO 1.1.01.002.0676-2015 (as amended 1 2017) Classification and documentation of work on the modernization of systems and equipment
+ STO 1.1.1.01.0678-2015 (as amended 1-6 2018, 7 2019) Basic rules for ensuring the operation of nuclear power plants (OPE AS) (replacing RD EO 0348-02)
STO 1.1.1.01.004.0680-2006 (as amended 1 2011, 2 2014) Teaching aids (instead of RD EO 0278-01, RD EO 0279-01)
RD EO 1.1.2.25.0682-2014 Requirements for the content of the album of neutronic characteristics of fuel loads of VVER-440 reactors
RD EO 1.1.2.01.0683-2006 Regulations on the procedure for certification of personnel of nuclear power plants with VVER reactors performing neutronic calculations of fuel loads
RD EO 1.1.2.01.0684-2009 Regulations on the organization of the operation and maintenance of the equipment of the integrated dispatch communication system of the security service of Rosenergoatom Concern OJSC and nuclear power plants
RD EO 1.1.2.13.0685-2009 The procedure for coordinating the use of installations, equipment and materials obtained by import for non-destructive testing of equipment and pipelines of nuclear power plants
RD EO 1.1.2.01.0686-2007 (as amended 1 2015, 2 2016) Regulations on the procedure for training managers and personnel of nuclear power plants in matters of civil defense and protection from emergencies
RD EO 1.1.2.09.0688-2006 Method for calculating the strength of the steam separator RBMK-1000 during service life extension
+STO 1.1.1.02.006.0689-2014 Water use at nuclear power plants. Classification of cooling water supply systems
+STO 1.1.1.03.003.0693-2006 Commissioning at nuclear power plants with VVER-type reactors. Standard provision on the State Acceptance Commission. Model regulation on the working commission. Standard regulation on working subcommittees (instead of OST 34-37-785-85, OST 34-37-787-85)
+RD EO 1.1.2.05.0697-2016 Reinforced concrete cooling towers for nuclear power plants. Construction and operation. Management
RD EO 1.1.2.01.0698-2016 Organization of interaction and development of corrective measures during safety and quality checks for the safety of Rosenergoatom Concern JSC by federal executive authorities and state corporation for Atomic Energy "Rosatom". Position
RD EO 1.1.2.19.0699-2006 Operation and maintenance of an uninterruptible power supply unit
RD EO 1.1.2.01.0700-2006 Regulations on the competition for the best research and development work
STO 1.1.1.01.004.0702-2006 Standard regulation on the training unit of a nuclear power plant (instead of RD EO 0133-98)
RD EO 1.1.2.01.0707-2015 Regulations on the procedure for issuing preliminary permits for planned increased exposure of nuclear power plant personnel
RD EO 1.1.2.20.0708-2006 Maintaining the water-chemistry regime of the primary circuit of nuclear power plants with VVER-440 reactors. Typical instruction
STO 1.1.1.01.003.0709-2013 (as amended 1 2014, 2 2015, 3 2016, 4 2017) General requirements for the procedure for maintaining documentation at the workplaces of operational personnel of nuclear power plants
RD EO 1.1.2.01.0712-2013 (as amended 1 2014, 2 2016, 3 2017) Regulations on accounting and control of radioactive substances and radioactive waste (replacing STO 1.1.1.04.007.0712-2007)
+RD EO 1.1.2.01.0713-2013 (as amended 1.2 2015, 3 2017) Regulation on conformity assessment in the form of acceptance and testing of products for nuclear power plants
RD EO 1.1.2.09.0714-2011 Method for calculating the strength of the main elements of fast reactor installations with sodium coolant
+STO 1.1.1.02.013.0715-2016 Water chemistry regime of the main process circuit and auxiliary systems of nuclear power plants with RBMK-1000 reactor. Working environment quality standards and means of ensuring them (instead of STP EO 0005-01)
RD EO 1.1.2.28.0717-2014 (as amended 1 2017) Assembly of gland seals. General technical requirements
+RD EO 1.1.2.19.0726-2007 Instructions for maintenance of brush-contact devices of turbogenerators
+STO 1.1.1.07.003.0727-2014 Laboratory chemical analysis of water from nuclear power plants with pressurized water power reactor. Measurement techniques
+ RD EO 1.1.2.10.0732-2007 (as amended 1 2008, amended 1 2017) Standard methodology for refueling planning at NPPs with RBMK-1000 reactors
RD EO 1.1.2.22.0733-2007 Standard programs and procedures for measuring the neutronic characteristics of VVER-440 reactors at nuclear power plants
RD EO 1.1.2.25.0734-2014 Information and analytical system "Center for Chemical Support of Nuclear Power Plants". Requirements for the structure, types of support and operation procedure
RD EO 1.1.2.09.0735-2007 Methods for calculating neutron-physical characteristics based on the data of physical experiments at power units of nuclear power plants with VVER-440 reactors
RD EO 1.1.2.28.0738-2007 Protective polymer coatings and compositions for nuclear power plants. General requirements
+RD EO 1.1.2.28.0739-2007 (as amended 1 2017) Decontamination formulations for nuclear power plants. General requirements
+ RD EO 1.1.2.20.0742-2008 (as amended 1 2009, 2 2010, 3 2011) Standard instructions for organizing work with precious metals, precious stones and inventory items containing them
RD EO 1.1.2.01.0743-2008 (as amended 1 2011) Regulation on the procedure for the development of circulars and information letters in FSUE Concern "Rosenergoatom"
+ STO 1.1.1.04.008.0744-2008 Professional standard of the organization "Specialist in the field of thermal power engineering"
+ STO 1.1.1.04.008.0745-2008 Professional standard of the Metrolog organization
STO 1.1.1.04.008.0746-2008 Professional standard of the organization "Specialist in the field of vocational training"
STO 1.1.1.04.008.0747-2008 Professional standard of the organization "Specialist in the management of radioactive waste and spent nuclear fuel"
+STO 1.1.1.04.008.0748-2008 Professional standard of the organization "Specialist in the development and maintenance of information systems software"
STO 1.1.1.04.008.0749-2008 Professional standard of the organization "Specialist in the field of nuclear safety"
STO 1.1.1.04.008.0750-2008 Professional standard of the organization "Accounting Specialist"
STO 1.1.1.04.008.0751-2008 Professional standard of the organization "Specialist in the field of economics"
STO 1.1.1.04.008.0752-2008 Professional standard of the organization "Chemist"
+STO 1.1.1.04.008.0753-2008 Professional standard of the organization "Specialist in the field of thermal automation and measurements"
+ STO 1.1.1.04.008.0754-2008 Professional standard of the organization "Specialist in the field of electric power industry"
STO 1.1.1.04.008.0755-2008 Professional standard of the organization "Manager in nuclear energy"
STO 1.1.1.04.008.0756-2008 Professional standard of the organization "Specialist in the maintenance and repair of mechanical equipment"
STO 1.1.1.04.008.0757-2008 Professional standard of the organization "Specialist in the field of nuclear power plant radiation safety"
STO 1.1.1.03.003.0759-2008 Readiness of systems, equipment and premises of power units of nuclear power plants with VVER-1000 reactors based on the V-320 project for the commissioning stages. Technical requirements
RD EO 1.1.2.28.0760-2015 (as amended 1 2016, 2 2017) Comprehensive measures to ensure the operational readiness of new power units of nuclear power plants. General requirements
+STO 1.1.1.01.003.0761-2017 Environmental management system of Rosenergoatom Concern JSC. General provisions, structure, requirements
STO 1.1.1.01.003.0762-2017 Environmental management system of Rosenergoatom Concern JSC. Internal audit
RD EO 1.1.2.10.0764-2008 (as amended 1 2013) Preparation of nuclear power plants of Energoatom Concern OJSC for OSART/PROSPER/IAEA missions. Reference Method
RD EO 1.1.2.01.0766-2008 Fuel assemblies for nuclear reactors of the VVER type. Regulations on the exchange of information based on the results of monitoring the tightness of fuel cladding and the reliability of nuclear fuel between the NPP and the industry information system based on operating experience
RD EO 1.1.2.28.0767-2008 (as amended 1 2011, 2 2017) Industry automated system for monitoring the radiation situation in the area of ​​nuclear power plants. General requirements for operation (instead of RD EO 0491-03, RD EO 0495-03)
RD EO 1.1.2.01.0768-2008 Regulations on a single telecom operator and the procedure for interaction with Energoatom Concern OJSC and its branches
RD EO 1.1.2.01.0769-2014 (as amended 1 2017) Organization of repair of nuclear power plant equipment according to technical condition. Basic provisions
RD EO 1.1.2.09.0770-2008 Methodology for assessing the technical condition and residual life of the unloading and loading machine RZM-488
+ STO 1.1.1.01.003.0771-2013 (as amended 1 2013, 2 2017) Technical documentation. General requirements for the withdrawal of documents from circulation
+ RD EO 1.1.2.09.0772-2012 (as amended 1 2014) Methodology for assessing the technical condition and resource characteristics of systems and means of fire protection of nuclear power units (replacing RD EO 1.1.2.09.0772-2008, RD EO 0585-2004)
RD EO 1.1.2.05.0773-2008 Guidelines for assessing the strength and residual life of elements of metal structures of RBMK-1000 reactors (replacing RD EO 0490-03)
STO 1.1.1.01.003.0776-2014 Technical documentation management system. General provisions
STO 1.1.1.01.003.0779-2014 (as amended 1 2015, 2 2016) Technical documentation. Operational documentation. The order of development and circulation. Documents for the maintenance of technological processes (operating instructions, diagrams, diagram albums)
RD EO 1.1.2.20.0782-2008 Water-chemical regime of the internal cooling circuit of diesel generators of nuclear power plants. Typical instruction
RD EO 1.1.2.28.0785-2009 Acoustic emission control of equipment and pipelines of nuclear power plants with RBMK-1000 reactors. General requirements
RD EO 1.1.2.01.0787-2017 Identification of hazardous production facilities. Position
RD EO 1.1.2.05.0788-2009 Guidelines for the calculation of the strength of standard components and parts made of graphite of the RBMK reactor of the first generation
RD EO 1.1.2.09.0789-2009 Method for determining the fracture toughness based on the test results of witness samples for calculating the strength and service life of VVER-1000 reactor pressure vessels
RD EO 1.1.2.01.0792-2009 Regulations on the Standard Process Regulations for Power Units of Nuclear Power Plants with a VVER Reactor
STO 1.1.1.03.004.0794-2009 (as amended 1 2017) Decontamination of personal protective equipment for nuclear power plant personnel. Quality criteria and means of decontamination
STO 1.1.1.03.004.0795-2009 (as amended 1 2017) Decontamination of equipment and premises of nuclear power plants. Quality criteria and means of decontamination
STO 1.1.2.07.003.0796-2015 Input control of reagents used at nuclear power plants with a high-power channel reactor. Measurement techniques
STO 1.1.1.04.005.0797-2012 (as amended 1 2014, 2-3 2015, 4-5 2017) Accounting, classification and analysis of minor events (low-level events)
+RD EO 1.1.2.01.0798-2017 Development, implementation and evaluation of the effectiveness of activities in the analysis and use of operating experience. Position
STO 1.1.1.07.003.0800-2009 (as amended 1 2015) Water chemistry of the secondary circuit of nuclear power plants with VVER-1000 reactors with morpholine dosing during commissioning of the power unit. Working environment quality standards and means of ensuring them
+STO 1.1.1.07.003.0801-2009 (as amended 1 2011, 2 2012) Laboratory analysis of gaseous media of nuclear power plants with pressurized water power reactor. Measurement techniques
+STO 1.1.1.04.001.0802-2015 (as amended 1 2016) Production control over compliance with industrial safety requirements at hazardous production facilities. Position
RD EO 1.1.2.01.0803-2015 (as amended 1.2 2016, 3 2017) Distribution of responsibilities when interacting with contractors during the repair of systems and equipment of nuclear power plants (replacing RD EO 1.1.2.01.0803-2009, RD EO 1.1.2.13.0843-2010)
+RD EO 1.1.2.11.0805-2010 Water-chemical regime in the cooling system of turbogenerator stator windings at nuclear power plants with VVER reactors. Working environment quality standards and means of ensuring them
STO 1.1.1.04.001.0806-2009 (as amended 1 2018) Safety assessment of disposal facilities for very low level waste
+RD EO 1.1.2.28.0807-2011 Devices for relay protection and electric automation of nuclear power plants. General technical requirements
RD EO 1.1.2.01.0808-2009 Regulations on the technical diagnostics of rotary equipment of nuclear power units based on the results of vibration measurements
RD EO 1.1.2.28.0809-2009 Stationary devices for monitoring radioactive contamination of nuclear power plant personnel. General technical requirements
+RD EO 1.1.2.28.0810-2009 Interlaboratory comparisons in the field of radiation measurements at nuclear power plants. General requirements
STO 1.1.1.04.001.0811-2010 (as amended 1 2014, 2 2015, 3 2016) Technical requirements for radiation monitoring subsystems of emissions in the radiation monitoring system of nuclear power plants
RD EO 1.1.2.28.0812-2009 Technical documentation. Modernization of monitoring and control systems for nuclear power plants with VVER reactors. General technical requirements
RD EO 1.1.2.13.0813-2009 Regulations for the work of expert groups on radiation safety in the event of an accident at a nuclear power plant
STO 1.1.1.04.007.0814-2009 (as amended 1 2011) Information collection and processing system of the complex of engineering and technical systems for the physical protection of nuclear power plants. Technical requirements
+RD EO 1.1.2.01.0816-2015 Regulations on the management of nonconformities in the construction of nuclear power plants
+RD EO 1.1.2.01.0817-2016 Industrial safety management system. Position
+STO 1.1.1.07.003.0818-2016 Water chemistry regimes of the secondary circuit of NPP with VVER-1000. Working environment quality standards and means of ensuring them (instead of RD EO 1.1.2.11.0720-2007, STP EO 0003-03)
RD EO 1.1.2.28.0819-2010 The procedure for archiving data of monitoring and control systems recorded on electronic media
RD EO 1.1.2.01.0820-2010 (as amended 1 2013, 2 2016) Regulations on the Centralized Reserve of Emergency Sets of Instruments, Materials, Medications, Personal Protective Equipment, Special Tools and Communication Equipment of Rosenergoatom Concern OJSC in Case of Radiation Accidents at the Nuclear Plant stations (chipboard)
+STO 1.1.1.02.011.0821-2013 Systems and equipment for internal operational communication of nuclear power plants. General technical requirements
RD EO 1.1.2.11.0822-2010 Water-chemistry regime of the third circuit of nuclear power plants with BN-800 reactor. Working environment quality standards and means of ensuring them
+STO 1.1.1.07.003.0823-2010 Accuracy standards for radiation measurements. Rationing the accuracy of dosimetric measurements
RD EO 1.1.2.09.0824-2010 (as amended 1 2013) Laboratory analysis of deposits from heat exchange equipment of nuclear power plants with pressurized water power reactor. Measurement techniques
RD EO 1.1.2.25.0825-2010 Operating organization requirements for composition and content project documentation in the part "Management (organization of management) of a nuclear power plant"
RD EO 1.1.2.25.0826-2010 Design documentation layout. Management (management organization) of a nuclear power plant
+RD EO 1.1.2.01.0827-2010 (as amended 1 2014, 2 2018) Regulations on the procedure for performing periodic safety assessment of nuclear power units
RD EO 1.1.2.11.0836-2010 Water-chemical regime of the third circuit of power unit 4 of the Beloyarsk nuclear power plant during commissioning of the power unit. Working environment quality standards and means of ensuring them
RD EO 1.1.2.25.0839-2010 Requirements for quality assurance programs for floating thermal power plants
RD EO 1.1.2.01.0840-2010 Regulations on the organization of the operation and maintenance of the equipment of the trunking radio communication system of the Berkut technical equipment complex of the security service of Rosenergoatom Concern OJSC and NPPs
+STO 1.1.1.01.005.0841-2010 (as amended 1 2013) General requirements for the scope of radiation monitoring in radiation monitoring systems of nuclear power plants
STO 1.1.1.01.003.0845-2016 (as amended 1 2017) Technical documentation. Terms and Definitions
RD EO 1.1.2.99.0846-2011 (as amended 1 2014, 2 2015) Procedure for the development of job descriptions for employees of branches of Rosenergoatom Concern OJSC
RD EO 1.1.2.99.0847-2011 (as amended 1 2014, 2 2015) The procedure for developing regulations on the structural subdivisions of the branches of Rosenergoatom Concern OJSC
RD EO 1.1.2.19.0848-2011 (as amended 1 2014) Instruction on the procedure for developing, agreeing, approving and amending the organizational and functional structures of the management of the branches of Rosenergoatom Concern OJSC
RD EO 1.1.2.25.0851-2011 Requirements for the physical protection of floating nuclear thermal power plants based on a floating power unit
RD EO 1.1.2.09.0852-2011 Laboratory chemical analysis of aqueous media of the Beloyarsk NPP. Measurement techniques
+STO 1.1.1.07.003.0853-2011 Accuracy standards for radiation measurements. Rationing the accuracy of spectrometric measurements
+ STO 1.1.1.06.003.0854-2011 Technical documentation. Terms and definitions for NPP operation
STO 1.1.1.02.006.0856-2011 (as amended 1 2016) Rules for the operation of hydraulic structures of nuclear power plants
STO 1.1.1.01.003.0859-2016 Management technical documentation. Requirements for the development, circulation and withdrawal from circulation of programs for the management and organizational activities of Rosenergoatom Concern JSC
+ STO 1.1.1.01.003.0860-2011 (as amended 1 2016) Technical documentation. Management technical documentation. General provisions
STO 1.1.1.01.003.0861-2011 Requirements for the composition of the kit and the content of the part "Organization of commissioning and commissioning of the facility" of the section "Construction organization project as part of the design documentation of nuclear power plants"
+STO 1.1.1.03.004.0862-2011 Installation of electrical equipment at an operating nuclear power plant. Quality assurance requirements
RD EO 1.1.2.03.0864-2011 (as amended 1 2015) Classifiers of information for the collection, processing and analysis of data on the reliability of nuclear power plant equipment
RD EO 1.1.2.99.0866-2012 Calculation substantiation of the strength of K-17 cassettes during long-term storage in cooling pools and during transport and technological operations. Methodology
+ RD EO 1.1.2.99.0867-2012 Methodology for assessing the technical condition and residual life of building structures of nuclear power plants (replacing RD EO 0447-03)
STO 1.1.1.03.0868-2012 Monitoring of seismological conditions in areas where nuclear power plants are located
RD EO 1.1.2.01.0869-2015 (as amended 1 2016, 2 2017) Regulations on non-compliance management during commissioning of new NPP power units
+STO 1.1.1.04.001.0870-2012 Fire safety requirements for the decommissioning of nuclear power units
RD EO 1.1.3.99.0871-2012 Methodology for calculating the resistance to brittle fracture of AKES reactor vessels with VVER-1000 when extending the service life to 60 years
RD EO 1.1.2.01.0872-2012 (as amended on 1 2013, 2 2014, 3.4 2016, 5 2017) Regulations on the final safety culture day at Rosenergoatom Concern OJSC
+STO 1.1.1.02.009.0873-2012 Ensuring safety in the operation of buildings and structures of nuclear power plants
+RD EO 1.1.2.29.0874-2012 Procedure for extending the designated service life (resource) of fire fighting equipment operated at nuclear power plants
+STO 1.1.1.01.001.0875-2013 Equipment for automated systems for monitoring the radiation situation in the area where nuclear power plants are located. Technical requirements of the operating organization
+STO 1.1.1.01.001.0876-2013 Equipment for automated systems for radiation monitoring of nuclear power plants. Technical requirements of the operating organization
STO 1.1.1.01.001.0877-2017 Automated system for individual dosimetric monitoring of a nuclear power plant. Technical requirements
+STO 1.1.1.01.001.0878-2013 Means of operational radiation monitoring for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.03.003.0879-2012 (as amended on 1 2015, 2-5 2017) Commissioning of nuclear power plant units with pressurized water power reactors. The procedure for the implementation and acceptance of commissioning work on technological systems and equipment (instead of STO 1.1.1.03.003.0692-2006, OST 34-37-782-85, OST 34-37-784-85)
+STO 1.1.1.03.003.0880-2017 Commissioning of units of nuclear power plants with pressurized water power reactors. Scope and sequence of commissioning works. General provisions (instead of STO 1.1.1.03.003.0880-2013, STO 1.1.1.03.003.0691-2006, OST 34-37-791-85)
STO 1.1.1.03.003.0881-2017 Commissioning of units of nuclear power plants with pressurized water power reactors. Terms and definitions (instead of STO 1.1.1.03.003.0881-2012, STO 1.1.1.03.003.0690-2006, OST 34-37-783-85)
+ STO 1.1.1.04.001.0882-2012 Fire safety management and assurance system
STO 1.1.1.03.002.0884-2012 (as amended 1 2018) Requirements for the design of radioactive waste management systems
+RD EO 1.1.2.25.0885-2012 Microprocessor devices for relay protection and automation. General delivery requirements
RD EO 1.1.2.01.0886-2012 Regulations on organizing the commissioning of a pilot floating power unit as part of a floating nuclear thermal power plant
RD EO 1.1.2.01.0887-2012 Regulation on the organization and provision of physical protection at floating nuclear thermal power plants
+STO 1.1.1.01.001.0888-2013 Piping and pipeline parts for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0889-2013 Heat exchange equipment for nuclear power plants (with internal structures). Technical requirements of the operating organization
+STO 1.1.1.01.001.0890-2013 Pipe fittings for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0891-2013 Instrumentation for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0893-2013 Pumping equipment for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0894-2013 Generators for nuclear power plants and their auxiliary equipment. Technical requirements of the operating organization
+STO 1.1.1.01.001.0895-2013 Equipment for chemical treatment and water treatment for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0896-2013 Vessels for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0897-2013 Compressors for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0899-2013 Climate control equipment for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0900-2013 Sealing devices (locks, doors) and penetrations for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0901-2013 Reinforcing sheath bundles for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0903-2013 Equipment for devices and fire extinguishing systems for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0904-2013 Thermal insulation for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.01.001.0905-2013 Equipment for radioactive waste management systems for nuclear power plants. Technical requirements of the operating organization
+STO 1.1.1.03.003.0906-2013 (as amended on 1 2015, 2-5 2017) Commissioning of nuclear power plant units with pressurized water power reactors. The procedure for the implementation and acceptance of commissioning work on electrical equipment (instead of STO 1.1.1.03.003.0692-2006, OST 34-37-782-85, OST 34-37-784-85)
STO 1.1.1.03.003.0907-2012 (as amended 1 2014, 2.3 2015, 4 2017) Commissioning of nuclear power plants. Reporting documentation (instead of OST 34-37-806-87, OST 34-37-807-85, OST 34-37-810-85, OST 34-37-916-86)
+ RD EO 1.1.2.03.0910-2012 (as amended 1 2016) Fire safety rules for construction and installation works at urban planning facilities of Rosenergoatom Concern OJSC
STO 1.1.1.03.003.0911-2012 Concrete for building structures and radiation protection of nuclear power plants
STO 1.1.1.03.002.0912-2012 (as amended 1 2013) Standards for the design of building structures for a sealed enclosure of the accident localization zone of nuclear power plants with a double containment
RD EO 1.1.2.29.0913-2012 (as amended 1 2016) Organization of work on accounting and forecasting the fluence of fast neutrons on the vessels of nuclear power plants with VVER
+STO 1.1.1.03.003.0914-2013 (as amended on 1 2014, 2 2015, 3.4 2017) Commissioning of nuclear power plant units with pressurized water power reactors. The procedure for the implementation and acceptance of commissioning work at the automated process control system (instead of STO 1.1.1.03.003.0692-2006)
STO 1.1.1.03.003.0916-2013 (as amended 1 2014, 2.3 2015, 4 2016, 5 2017) Rules for commissioning nuclear power units (replacing VSN AS-90)
+RD EO 1.1.2.99.0921-2014 (as amended 1 2017) Calculation of resistance to brittle fracture of perforated shells (elliptical reactor lid). Methodology
RD EO 1.1.2.25.0923-2013 Electrolysis plants for hydrogen production at nuclear power plants. Technical requirements
+RD EO 1.1.2.01.0924-2013 Metrological support of nuclear power plants. Metrological support of measuring systems during the construction and operation of nuclear power plants. Basic provisions
+RD EO 1.1.2.99.0925-2013 Metrological support of nuclear power plants. Indicators. Identification and maintenance procedure
RD EO 1.1.2.29.0926-2013 (as amended 1 2016, 2.3 2017) Procedure for consideration of draft documents in the field of atomic energy use
RD EO 1.1.2.01.0927-2013 (as amended 1 2013) Amplitude criterion for damping heat exchange tubes of steam generators of NPP reactor plants with VVER
+RD EO 1.1.2.05.0929-2013 (as amended 1 2014, 2 2015, 3 2017) Guidelines for acceptance inspections at manufacturing plants and incoming inspection at NPPs of equipment of safety classes 1, 2 and 3
+ RD EO 1.1.2.01.0930-2013 (as amended 1 2015, 2 2017, 3 2018) Regulations on the management of nonconformities in the manufacture and incoming inspection of products for nuclear power plants
+ RD EO 1.1.2.01.0931-2013 (as amended 1 2014, 2.3 2015, 4 2017) Basic provisions on the input control of products at nuclear power plants
+STO 1.1.1.03.003.0932-2013 Fire safety requirements for the construction of nuclear power plants
+RD EO 1.1.2.05.0935-2013 (as amended 1 2015) Guidelines for the organization of work when handling production and consumption waste
+RD EO 1.1.2.99.0936-2013 (as amended 1 2017) Methodology for assessing the service life of the welding unit of the heat carrier header to the PGV-1000 steam generator vessel (NPP with VVER-1000)
+RD EO 1.1.2.25.0937-2013 Non-destructive testing. Uniform requirements for the form and content of technological maps
RD EO 1.1.2.05.0939-2016 Safety concept "leak before destruction" for the coolant circuit of nuclear power plants. Manual (instead of RD 95 10547-99 (R-TPR-01-99))
+ RD EO 1.1.2.29.0940-2013 (as amended 1 2014) Procedure for evaluating the effectiveness of the implementation of quality assurance programs by nuclear power plants
RD EO 1.1.2.01.0942-2013 Regulations on the interaction between Rosenergoatom Concern OJSC and the Emergency and Technical Center of the Ministry of Atomic Energy of Russia (St. Petersburg)
+RD EO 1.1.2.25.0943-2013 Requirements for ensuring electromagnetic compatibility of monitoring and control systems of nuclear power plants
RD EO 1.1.2.99.0944-2012 Methodology for calculating the strength and residual life of VVER-1000 internals when the service life is extended to 60 years
STO 1.1.1.01.003.0946-2013 Instructions for Ensuring Radiation Safety during NPP Operation. General requirements for construction and content
STO 1.1.1.04.001.0947-2013 (as amended 1 2015) Regulation on the radiation safety management system
STO 1.1.1.04.001.0948-2013 Subsystem for monitoring liquid discharges in the radiation monitoring system of nuclear power plants. Technical requirements
STO 1.1.1.02.005.0950-2014 Water quality standards for the first and third circuits of nuclear power plants, cooling circuits and intermediate circuits for storage of spent fuel assemblies and solid radioactive waste from floating power units with pressurized water reactors. Technical requirements
RD EO 1.1.2.01.0951-2014 Regulation on emergency centers of a floating nuclear thermal power plant
+ RD EO 1.1.2.29.0952-2014 (as amended 1 2017) Production certification procedure
+RD EO 1.1.2.01.0953-2014 Regulation on checking the state of production at manufacturers of equipment for nuclear power plants
+RD EO 1.1.2.29.0954-2014 Procedure for analysis of documentation for equipment supplied to nuclear power plants
+RD EO 1.1.2.29.0955-2014 (as amended 1 2017, 2 2018) The procedure for control by the operating organization of the implementation of quality assurance programs in the design and manufacture of equipment for nuclear power plants
RD EO 1.1.2.01.0956-2014 (as amended 1 2017) Regulations on the assessment of compliance with safety requirements of organizational and technological documentation for construction and installation works during the construction of nuclear power plants
+RD EO 1.1.2.01.0958-2014 (as amended 1 2015) Coordination of technical requirements and Decisions on the use of imported products intended for use at nuclear power plants. Position
+ RD EO 1.1.2.29.0960-2015 (as amended 1 2016, 2 2017, 3 2018) Procedure for approval and approval of quality assurance programs and quality manuals
RD EO 1.1.2.25.0962-2014 (as amended 1 2017) Comprehensive survey of a nuclear power plant unit for preparation and decommissioning. General requirements
RD EO 1.1.2.99.0963-2014 (as amended 1 2016) Commissioning of nuclear power plants. Quality control of commissioning works at nuclear power plants of Rosenergoatom Concern OJSC
RD EO 1.1.2.25.0978-2014 Organization of the water-chemistry regime in liquid radioactive waste storage tanks. Technical requirements
+STO 1.1.1.03.004.0979-2014 Water-chemical regime of the secondary circuit of nuclear power plants of the AES-2006 project during commissioning of the power unit. Coolant quality standards and means of ensuring them
STO 1.1.1.03.004.0980-2014 (as amended on 1 2015, 2.3 2016) Primary circuit water chemistry regime during the commissioning of the power unit of the nuclear power plant of the AES-2006 project. Coolant quality standards and means of ensuring them
+ STO 1.1.1.04.001.0985-2014 Warning and evacuation control system for people in case of a fire at a nuclear power plant. Tests and commissioning
+STO 1.1.1.01.003.0995-2014 Organizational standards that establish technical requirements for the same type of equipment groups. Content and order of application. General provisions
+STO 1.1.1.03.002.0999-2014 Aggregate type water mist fire extinguishing installations for buildings, structures and premises of nuclear power plants. Design Requirements
RD EO 1.1.2.29.1000-2014 (as amended 1 2017) List of nuclear-hazardous activities at the unit of a nuclear power plant with VVER. Development order
STO 1.1.1.03.002.1003-2014 List of measures for civil defense, measures for the prevention of natural and man-made emergencies to section 12 of the design documentation of nuclear power plants. Requirements for the composition, content and design
+RD EO 1.1.2.99.1008-2015 Methodology for assessing the technical condition and residual life of non-replaceable elements of building structures for fastening nuclear power plant equipment
STO 1.1.1.03.002.1011-2015 Development of section 11 "Estimates for the construction of capital construction facilities" of design documentation for the construction of nuclear power facilities. General requirements
STO 1.1.1.03.002.1013-2015 Development of section 11 "Estimates for the construction of capital construction facilities" when adjusting the design documentation. General requirements
+RD EO 1.1.2.29.1019-2015 Organization of acceptance into operation of fire-fighting external and internal water supply systems. The procedure and methodology for testing for water loss of fire water supply systems of power units of nuclear power plants
RD EO 1.1.2.99.1022-2015 (as amended 1 2017) Measurement of the wall thickness of equipment and pipelines of nuclear power plants using EMA thickness gauges
RD EO 1.1.2.25.1033-2015 (as amended 1 2017) Repair of nuclear power plant equipment using cold curing polymer composite materials. General technical requirements
RD EO 1.1.2.29.1034-2015 (as amended 1 2017) Development of lists and work programs for nuclear hazardous work for units of nuclear power plants with RBMK, BN and EGP reactors. Order
RD EO 1.1.2.25.1041-2015 Laboratory Information Systems at nuclear power plants. Requirements for the structure, types of support and operation procedure
RD EO 1.1.2.01.1048-2015 Organization of engineering support for the operation of nuclear power plants
RD EO 1.1.2.29.1053-2015 Procedure for the issuance by the operating organization of a permit for exceeding the control level of the individual exposure dose of personnel and persons seconded to the nuclear power plant (instead of RD EO 0280-01, RD EO 0494-03)
RD EO 1.1.2.25.1063-2015 Monitoring and control systems, NPP automation equipment. Protection of information from unauthorized access and impact. Requirements information security during installation, commissioning and operation of automated process control systems
RD EO 1.1.2.29.1067-2015 Report on the safety analysis of the power unit of a nuclear power plant. The order of development and updating
+STO 1.1.1.03.002.1069-2015 Fire safety requirements for the design of nuclear power plants
+RD EO 1.1.2.01.1071-2015 Metrological support of nuclear power plants. Organization and carrying out metrological examination of documentation (instead of RD EO 0158-99)
+ STO 1.1.1.01.003.1073-2015 (as amended 1 2017) Repair documentation. Regulations for the maintenance and repair of systems and equipment of nuclear power plants. Rules for the construction, presentation, execution, approval, approval and registration (instead of RD EO 1.1.2.25.0705-2006)
+ STO 1.1.1.01.003.1074-2015 (as amended 1.2 2017) Repair documentation. Technological documentation for the repair of nuclear power plant equipment. Rules for the construction, presentation, execution, approval, approval and registration (instead of RD EO 0017-2004, RD EO 0017-92 (RD 95.028.001-92))
+ STO 1.1.1.01.003.1075-2015 Repair documentation. Specifications for the repair of nuclear power plant equipment. Rules for the construction, presentation, execution, approval, approval and registration (instead of RD EO 1.1.2.03.0857-2011)
RD EO 1.11.2.25.1077-2015 (as amended 1 2016, 2 2017) Requirements for the content and procedure for developing a general nuclear power plant quality assurance program
STO 1.1.1.02.004.1078-2015 Stationary installations for monitoring radioactive contamination of nuclear power plant personnel. General technical requirements, types and test methods
STO 1.1.1.01.003.1084-2015 Organizing, conducting and analyzing the results of self-assessment of the operational safety of nuclear power plants (instead of MR 1.2.1.14.0108-2012, AI 1.3.2.06.004.07/03-2009)
RD EO 1.1.2.01.1097-2015 (as amended 1 2017) Quality control of nuclear fuel manufacturing for nuclear power plants. Position
STO 1.1.1.03.004.1099-2016 (as amended 1 2017, 2 2018) Radioactive waste management at nuclear power plants of Rosenergoatom Concern JSC
+STO 1.1.1.04.004.1108-2017 (as amended 1, 2 2018) Integrated management system of Rosenergoatom Concern JSC. General provisions, structure, requirements
+STO 1.1.1.02.005.1116-2016 Chemical substances and materials affecting the operation of nuclear power plant equipment. Primary requirements
STO 1.1.1.03.004.1120-2016 Extending the life of nuclear facilities (except for units of nuclear power plants)
+STO 1.1.2.04.001.1142-2016 Software and hardware complex of the upper level of the radiation monitoring system. General technical requirements (instead of RD EO 1.1.2.28.0724-2007)
+STO 1.1.1.02.013.1153-2016 (as amended 1 2017, 2 2018) Nuclear fuel. Technical requirements
STO 1.1.1.03.004.1156-2016 Water chemistry of the primary circuit during the commissioning of a power unit of a nuclear power plant with a VVER-1000 reactor. Coolant quality standards and means of ensuring them (instead of STP EO 0009-03)
+STO 1.1.1.03.004.1179-2016 (as amended 1, 2 2018) Organization of work involving the opening of nuclear power plant equipment. Rules (instead of RD EO 1.1.2.03.0127-2013, RD EO 1.1.2.03.0127-2010, RD EO 0127-98, RD EO 1.1.2.29.0292-2011, RD EO 0292-01)
STO 1.1.1.06.1185-2016 Monitoring and control systems. APCS of nuclear power plants. Terms and Definitions
STO 1.1.1.06.1186-2016 Monitoring and control systems. Cybersecurity of process control systems for nuclear power plants. Terms and Definitions
RD EO 1.1.2.01.1217-2017 Commissioning, use and modification of software tools used at nuclear power plants of Rosenergoatom Concern JSC to calculate the neutronic characteristics of VVER-type reactors. Regulations (replacing RD EO 0499-03)
+ STO 1.1.1.01.004.1228-2017 Personnel management system. General provisions
+STO 1.1.1.04.003.1293-2017 (as amended 1, 2 2018) Integrated control system. General Quality Guidelines for the Operating Organization Rosenergoatom Concern JSC (instead of STO 1.1.1.04.004.0977-2014)
+ STO 1.1.1.01.003.1340-2017 Development, execution and accounting of solutions (technical solutions). General requirements (instead of RD EO 1.1.2.01.0740-2012, RD EO 0477-03, RD EO 1.1.2.01.0347-2006, RD EO 0347-02)
+STO 1.1.1.03.999.1354-2017 Assessment of the technical condition and residual life of pipelines, vessels and pumps of nuclear power plants -2009, RD EO 1.1.2.09.0774-2011)
STO 1.1.1.04.001.1384-2017 Radiation monitoring systems for nuclear power plants. General requirements
+STO 1.1.1.03.004.1405-2017 (as amended 1 2018) Organization of pre-operational and operational control of metal of equipment, pipelines and other elements of nuclear power plants
+STO 1.1.1.02.009.1407-2017 Operation of buildings and structures of nuclear power plants. Basic provisions (instead of RD EO 1.1.2.99.0007-2011, RD EO 0007-2005, TI-34-70-049-86)
+ STO 1.1.1.04.001.1500-2018 Fire safety rules for the operation of nuclear power plants (replacing PPB-AS-2011)
+RD EO 2728011.001-2007 Visual and measuring control, capillary control of stud sockets, studs, bolts, nuts and washers of NPP equipment flange connectors. Quality assessment standards
RD EO 27.28.05.049-2011 (as amended 1 2015, 2 2017) Method of ultrasonic testing of welded joints steel pipes with wall thickness 2-6 mm

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Appendix A. Typical scope of inspections during acceptance inspection and incoming control of pumping equipment 1 Appendix B. Typical scope of inspections during acceptance inspection and incoming inspection of elements and blocks of pipelines of 1-3 safety classes Appendix C (recommended). Typical scope of checks during acceptance inspection and incoming inspection of heat exchange equipment/pressure vessels of safety class 1-3 Appendix D (recommended). Typical scope of inspections during acceptance inspection and incoming inspection of pipeline fittings of 1-3 safety class Appendix D (recommended). Typical scope of inspections during acceptance inspection and incoming inspection of electrical equipment, instrumentation equipment, automation equipment, automated process control systems, IVS 1-3 safety class Appendix E (recommended). Typical scope of checks during acceptance inspection and incoming control of GPM 1-3 safety class Appendix G (recommended). Typical scope of checks during acceptance inspection and input control of power transformers Appendix I (recommended). Typical scope of inspections during acceptance inspection and incoming control of turbogenerators Appendix K (recommended). Typical scope of checks during acceptance inspection and incoming inspection of a steam turbine plant

Attachment 1

Guiding document of the operating organization RD EO 1.1.2.05.0929-2013
"Guidelines for conducting acceptance inspections at manufacturing enterprises and incoming control at nuclear power plants of equipment of 1, 2 and 3 safety classes"
(approved by order of Rosenergoatom Concern OJSC of June 17, 2013 N 9/557-P)

With changes and additions from:

Foreword

1 Developed by the Quality Department of Rosenergoatom Concern OJSC

2 Introduced by the Quality Department of Rosenergoatom Concern OJSC

4 First introduced

1 area of ​​use

1.1 This guidance document of the operating organization "Guidelines for acceptance inspections at manufacturing plants and incoming inspection at NPPs of equipment of safety classes 1, 2 and 3" (hereinafter referred to as the Guidelines) establishes requirements for standard scopes of acceptance inspections at manufacturing plants and incoming inspections at NPP sites, equipment of a number of main nomenclature groups intended for use as part of elements or as elements assigned to safety classes 1, 2 and 3 in accordance with NP-001, as well as power transformers of safety class 4, turbine generators of safety classes 3, 4 and steam turbine installations of the 4th safety class according to NP-001.

1.2 The requirements of the Guidelines must be taken into account by the branches of Rosenergoatom Concern OJSC (hereinafter referred to as the Concern), general contractors and authorized organizations when developing / adjusting their procedural documents that define the requirements for the organization, establishing responsibility and drawing up / participating in the preparation of reporting documents as part of acceptance inspections at manufacturing enterprises and incoming control of products at NPPs under construction and in operation.

1.3 The requirements of the Guidelines must be taken into account by the Concern's branches and general contractors when developing/adjusting the Lists of products subject to incoming inspection or standard programs for incoming inspection of products drawn up in accordance with the requirements of RD EO 1.1.2.01.0931-2013.

3.6 workpiece: An object of labor from which a part is made by changing the shape, size, surface properties and (or) material (GOST 3.1109).

3.7 spare part: A component of the product intended to replace the same part that was in operation in order to maintain or restore the serviceability or performance of the product (GOST 18322).

3.8 product: A unit of production, the quantity of which can be calculated in pieces, kilograms, meters.

3.9 accessory product: Subcontractor's products used as an integral part of the products manufactured by the manufacturer.

3.11 installation organization: an organization engaged on a contractual basis by the Concern (its branch) / general contractor for the installation of products at the NPP site and possessing the relevant permits in relation to this species activities.

3.12 non-compliance: Non-compliance with one or more requirements established by the ITT (TT) or TOR, RKD, PTD, regulatory legal acts of the Russian Federation, federal norms and rules in the field of atomic energy use and other regulatory documentation specified in the ITT (TT), TK, RKD , PDD, contracts for the manufacture and / or supply, and requirements (technical, quality) of the above contracts.

Note - non-conformities do not include those identified during conformity assessment in the form of acceptance (testing) during manufacture or during input control at the NPP site:

Errors in the accompanying documentation (with the exception of the discrepancy between the form of the passport (certificate of manufacture) for the products and the form specified in the federal norms and rules in the field of the use of atomic energy);

Deviations due to incompleteness of the accompanying documentation (with the exception of the absence of: a product quality document (quality certificate / form / passport / label / certificate of manufacture), Operation Manual, Installation Manual (in the absence of this section in the Operation Manual), Quality Plan and Decisions on the use of imported products);

Deviations from the requirements of ITT/TOR in the presence of the design documentation approved by the Concern (for NPPs under construction)/the Concern's branch (for operating NPPs);

Lack of design and working documentation for construction (the terms are applied in accordance with GOST R 21.1001) or deviations of product characteristics from the requirements of design and working documentation for construction.

These deviations are comments and are subject to elimination by the general contractor/supplier/manufacturer without issuing a non-compliance registration document and decisions taken. For inconsistencies due to the incompleteness of the accompanying documentation (absence of: a document on product quality (quality certificate / form / passport / label / certificate of manufacture), Operation Manual, Installation Manual (in the absence of this section in the Operation Manual), Quality Plan and Decisions on the use of imported products) is not required to issue a document for registering nonconformities and decisions made.

3.13 equipment: A complex of interrelated products that has a given functional purpose and is intended to be used independently or as part of other equipment.

Note - Within the framework of this document, equipment refers to heat exchange equipment, steam and hot water boilers, pressure vessels, pipeline fittings, pumps, drives, electric motors, electric generators, steam turbines, components and elements of pipelines, electrical and electronic devices, cable products , equipment, instruments and blocks of electrical and electronic devices, dosimetric equipment and physical protection equipment, reloading machines, transport and technological equipment, control, management, measurement and diagnostics, equipment for storage and processing of radioactive waste, equipment for thermal and biological protection, devices fire extinguishers, sealing devices and penetrations.

3.14 passport: A document containing information certifying the manufacturer's guarantees, the values ​​of the main parameters and characteristics (properties) of the product, as well as information on the certification and disposal of the product.

3.15 semi-finished product: An object of labor subject to further processing at the consumer enterprise (GOST 3.1109).

Note - within the framework of this document: 1) consumer enterprises are the manufacturer and its subcontractors or the NPP site; 2) the following semi-finished products are considered: sheets, pipes, forgings (stampings), long and shaped steel, blanks, steel and iron castings.

3.16 supplier: A legal entity or an individual entrepreneur that supplies equipment to a general contractor or a branch of the Concern (NPP).

3.17 manufacturer: A legal entity or an individual entrepreneur producing / s products for subsequent delivery.

3.18 products: The result of activity, presented in material form and intended for further use for economic and other purposes.

Note - within the framework of this document, products include equipment, components, fasteners, spare parts, blanks, semi-finished products, welding (surfacing) materials.

3.19 procedure: A documented procedure for ensuring the performance of a certain work (process), as well as the procedure and methods for monitoring the results of their implementation.

3.20 production and technological documentation: technological instructions, technological process maps and other documents regulating the content and procedure for the implementation at the manufacturing enterprise (its subcontractors) of all technological and control operations in the manufacture of products.

3.21 quality plan: A document reflecting the results of the conformity assessment work in the form of acceptance and testing and containing records of the work performed at successive control points in accordance with the technological process for manufacturing products and the procedure for performing conformity assessment work.

3.22 working design documentation: Design documentation developed on the basis of TK (ITT, TT) and designed to ensure the manufacture, control, acceptance, delivery, operation and repair of the product.

3.23 repair organization: an organization engaged on a contractual basis by the Concern (its branch) / general contractor for the repair and reconstruction of products at the NPP site and possessing the relevant permits for this type of activity.

3.24 manual: A document containing information about the design, principle of operation, characteristics (properties) of the product, its components and instructions necessary for the correct and safe operation of the product (intended use, maintenance, current repair, storage and transportation) and assessments of its technical condition during determining the need to send it for repair, as well as information on the disposal of the product and its components

3.25 subcontractor: A legal entity or an individual entrepreneur involved / th on a contractual basis to perform part of the technological process of manufacturing products, including the manufacture of components purchased by the manufacturer of products.

Note - Subcontractors do not include laboratories (test centers) involved in non-destructive and/or destructive testing and/or testing.

3.26 welding (surfacing) materials: Welding wire, surfacing tape, fluxes, coated electrodes and shielding gases used in welding (surfacing) to ensure a given process and obtain a welded joint and surfacing.

3.27 technical task: The initial document for the development of a product and technical documentation for it, which establishes the main purpose and quality indicators of the product, technical, economic and special requirements presented to the developed product, volume, stages of development and composition of design documentation.

Notes

1. Subject to the development of technical specifications, the technical assignment does not apply to design documents.

2. For imported products, this document is issued in the form of technical requirements.

3. The specific content of the TOR is determined by the product developer on the basis of ITT (technical requirements of the supply agreement) of the general designer (branch of the Concern, enterprise - manufacturer of equipment - consumer of the component product). In case of initiative development, the specific content of the TK is determined by the product developer in accordance with its procedural documents.

3.28 authorized organization: A legal entity authorized in accordance with a joint decision of the State Corporation "Rosatom" and Federal Service on Environmental, Technological and Nuclear Supervision dated 25.06.2007 N 06-4421 (as amended by NN 1, 2, 3) "On the procedure and scope for conducting conformity assessments of equipment, products, components, materials and semi-finished products supplied to nuclear power plants" at performance of work on conformity assessment in the form of acceptance (testing) of products intended for use in the elements of the NF of the Russian Federation, assigned to 1, 2, 3 safety classes according to NP-001, or has entered into an agreement with the Concern to carry out work on conformity assessment in the form of acceptance ( tests) of products intended for use in NF elements Russian Federation, referred to the 4th safety class according to NP-001

3.29 form: A document containing information certifying the manufacturer's guarantees, the values ​​of the main parameters and characteristics (properties) of the product, information reflecting the technical condition of this product, information on certification and disposal of the product, as well as information that is entered during its operation (duration and operating conditions, maintenance, repairs and other data).

3.30 operating organization: An organization established in accordance with the legislation of the Russian Federation and recognized, in accordance with the procedure and under the conditions established by the Government of the Russian Federation, by the relevant body for managing the use of atomic energy, as suitable to operate a nuclear installation, radiation source or storage facility and to carry out, on its own or with the involvement of other organizations, activities for the placement , design, construction, operation and decommissioning of a nuclear installation, radiation source or storage facility, as well as activities for the handling of nuclear materials and radioactive substances (N 170-FZ of November 21, 1995).

3.31 NPP element: equipment, instruments, pipelines, cables, building structures and other products that ensure the performance of specified functions independently or as part of systems and are considered in the design as structural units when performing reliability and safety analyzes (NP-001).

3.32 label: A document containing the manufacturer's guarantees, the values ​​of the main parameters and characteristics (properties) of the product, information about the certification of the product.

4 Symbols and abbreviations

NPP (NPP) - nuclear power plant (Nuclear power plant);

APCS - automated process control system;

VIK - visual-measuring control;

GOST - state standard;

GPM - lifting mechanism;

GMO - leading materials science organization;

GI - hydraulic tests;

ZIP - spare parts, tools and accessories;

IVS - information-computing system;

IKI - imported components;

ITT - initial technical requirements;

KIP - instrumentation;

ICC - intergranular corrosion;

ND - normative documentation;

OIT - equipment, products and technologies for nuclear installations, radiation sources and storage facilities;

OPB - general provisions security;

OST - industry standard;

QCD - department of technical control;

MPC VK - permanent commission for input control;

PC - quality plan;

PKD - production control documentation;

PSI - acceptance tests;

PTD - production technological documentation;

RKD - working design documentation;

RF - Russian Federation;

RE - operation manual;

SB - assembly drawing;

CPS - control and protection system;

TB1 - base metal quality control table;

TB2 - table of quality control of welding consumables, welded joints and overlays;

TK - terms of reference;

TT - technical requirements;

THAT - specifications;

MA - authorized organization;

ED - operational documentation;

Ra - arithmetic mean deviation of the surface profile;

Rz - height of surface profile roughness by 10 points.

5 Responsibility of participants

5.1 Organizations participating in acceptance inspections at manufacturing enterprises of products intended for use as part of elements or as an element classified as 1, 2, 3 safety classes according to NP-001 are:

Customer (branch of the Concern (NPP or Directorate of the NPP under construction) - for products supplied directly to NPPs or a Russian manufacturer of equipment / product using this product as a semi-finished product or component);

Authorized organization;

Supplier of the Russian Federation - the holder of an agreement with a foreign manufacturer or a foreign supplier, if it is present in the supply chain;

Manufacturer.

5.2 Organizations participating in the input control at NPP sites of products intended for use as part of elements or as an element classified as 1, 2, 3 safety classes according to NP-001 are:

Branch of the Concern (NPP or Directorate of the NPP under construction) - the end consumer of the products;

General contractor (for NPPs under construction);

Authorized organization;

Assembly organization;

Repair organization;

Provider;

Manufacturer.

5.4 Organizations-participants are responsible for fulfilling the requirements of these Guidelines when organizing, conducting acceptance inspections at manufacturing enterprises and incoming inspections at NPP sites, as well as preparing/participating in the preparation of reporting documents based on their results.

6 Carrying out acceptance inspections and incoming control (general provisions)

6.1 Acceptance inspections are mandatory for products subject to conformity assessment in the form of acceptance in accordance with Decision N 06-4421 (am. 1-3) .

6.2 Acceptance inspection is the last stage of assessing the conformity of the manufacture of products with the requirements of the regulatory legal acts of the Russian Federation, ND, ITT (TT) or TK, RKD, PDD and supply contracts, the result of which is a decision on the suitability of products for delivery.

6.3 Products completed in accordance with the supply contract and accepted by the Quality Control Department of the manufacturer are presented for acceptance inspection. Technological and / or control operations present at the control point "Acceptance Inspection", before the start of the survey by the authorized organization and organizations - participants in the conformity assessment, must be controlled by the QCD / quality service of the manufacturer.

6.4 Acceptance inspection includes:

Checking the completeness of the accompanying documentation, including a set of technical documents for repairs (if there are requirements in the supply contract and / or TS / TK);

Checking the correctness of the design and content of the accompanying documentation, including quality documents;

Note - When checking the correctness of the execution of the accompanying documentation, the MA controls the availability of approval of a set of technical documents for repair with Rosenergoatom Concern JSC (Order of Rosenergoatom Concern OJSC dated 16.03.2015 N 9 / 276-P "On organizing the completion of technical documentation for the repair of equipment and new nuclear power plants).

Visual and measuring control of products;

Checking the conformity of the completeness and quantity of products and spare parts;

Checking the conformity of conservation, coloring, packaging and labeling of products;

Checking the conformity of the container.

6.5 In the Quality Plans, the acceptance inspection should be documented by one control point, completing the Quality Plan and including the control operations specified in clause 6.4.

6.6 If, according to the conditions of production, these operations are significantly separated in time (for example, it takes several days to complete the entire acceptance inspection complex) or are part of other control points with the status of "HP" for an authorized organization (for example, PSI), then it is allowed to register these operations to separate and as part of other control points, which should be agreed upon when developing and agreeing on the Quality Plan. At the same time, if these operations are not repeated, the remaining operations are indicated in the Quality Plan in accordance with clause 6.4.

6.7 Acceptance inspections of products are carried out by representatives of the authorized organization and organizations - participants in the conformity assessment with the participation of a responsible representative from the manufacturer, appointed by the management of this enterprise in the prescribed manner (by order) to participate in the acceptance inspection.

6.9 The presentation of products for acceptance inspection is carried out individually, or in batches of product units, or in a combination of several units or batches of products, which is reflected in the Notification of the acceptance inspection, drawn up in the manner adopted in RD EO 1.1.2.01.0713.

6.10 If, according to one Quality Plan, the manufacture of several units or batches of products is controlled, for which the manufacturer issues several quality documents and sets of accompanying documentation, verification of the completeness of the accompanying documentation and verification of the correctness of the execution and content of the accompanying documentation, including documents on quality, should be carried out for all sets.

6.11 Input control is carried out at the NPP site in order to prevent the use at NPP of products that do not meet the requirements of the regulatory legal acts of the Russian Federation, RD, ITT (TT) or TK, RKD and supply contracts.

6.12 All products received at the NPP site and intended for use as part of elements or as an element classified as 1, 2, 3, 4 safety classes according to NP-001 are subject to incoming control.

6.13 Prior to the incoming inspection, the branch of the Concern and the general contractor (for NPPs under construction) must accept the products delivered to the NPP site in terms of quantity (including checking the compliance of the products with the information specified in the transport documents and checking the absence of damage to the tare/packing) from the transport organization with compliance with the rules stipulated by the regulatory legal acts of the Russian Federation regulating the activities of transport.

6.14 Requirements for the procedure for the acceptance of products in terms of the quantity and execution of reporting documentation based on its results, the procedure for identifying non-compliance of products with the information specified in the transport documents, and / or damage to containers / packaging should be established in the procedural documents of the branches of the Concern and general contractors.

6.15 If the results of acceptance by quantity are positive, the incoming inspection of products must be started no later than 10 calendar days from the date of signing the waybill by the general contractor (for NPPs under construction) or a branch of the Concern (for operating NPPs), unless otherwise provided in the contract for supply of products.

6.16 Products, in respect of which a non-compliance was revealed during the input control, is considered not to have passed the input control and is not subject to further use at the NPP site until the identified non-conformities are eliminated.

6.17 The decision on the possibility of further use at the NPP site of products, in respect of which comments were revealed during the input control, is made by the members of the MPC VK, is indicated in the "Conclusion" section of the Input Control Report, which is approved by its chairman. This decision can only be made if there is letter of guarantee from the general contractor (for NPPs under construction) or the supplier (for NPPs in operation) on the elimination of comments within the time period agreed with the Concern's branch.

6.18 Input control is carried out according to the parameters (requirements) and methods established in the ITT (TT) or TOR, RKD (for imported products in the absence of TS, the requirements established in Technical requirements, drawn up and agreed in accordance with RD-03-36), ND and contracts for the supply of products.

If you are a user of the online version of the GARANT system, you can open this document right now or request hotline in system.

Document as of August 2014

Foreword

1 Developed by the Quality Department of Rosenergoatom Concern OJSC.

2 Introduced by the Quality Department of Rosenergoatom Concern OJSC.

1.2 The requirements of the Guidelines must be taken into account by the branches of Rosenergoatom Concern OJSC (hereinafter referred to as the Concern), general contractors and authorized organizations when developing / adjusting their procedural documents that define the requirements for the organization, establishing responsibility and drawing up / participating in the preparation of reporting documents as part of acceptance inspections at manufacturing enterprises and incoming control of products at NPPs under construction and in operation.

1.3 The requirements of the Guidelines must be taken into account by the Concern's branches and general contractors when developing/adjusting the Lists of products subject to incoming inspection or standard programs for incoming inspection of products drawn up in accordance with the requirements of RD EO 1.1.2.01.0931-2013.

2 Normative references

3.29 form: A document containing information certifying the manufacturer's guarantees, the values ​​of the main parameters and characteristics (properties) of the product, information reflecting the technical condition of this product, information on certification and disposal of the product, as well as information that is entered during its operation (duration and operating conditions, maintenance, repairs and other data).

3.30 operating organization: An organization established in accordance with the legislation of the Russian Federation and recognized, in accordance with the procedure and under the conditions established by the Government of the Russian Federation, by the relevant body for managing the use of atomic energy, as suitable to operate a nuclear installation, radiation source or storage facility and to carry out on its own or with the involvement of others organizations activities for the placement, design, construction, operation and decommissioning of a nuclear installation, radiation source or storage facility, as well as activities for the handling of nuclear materials and radioactive substances (N 170-FZ of November 21, 1995).

3.31 NPP element: Equipment, instruments, pipelines, cables, building structures and other products that ensure the performance of specified functions independently or as part of systems and are considered in the design as structural units when performing reliability and safety analyzes (NP-001) .

3.32 label: A document containing the manufacturer's guarantees, the values ​​of the main parameters and characteristics (properties) of the product, information about the certification of the product.

4 Symbols and abbreviations

NPP (NPP) - nuclear power plant (Nuclear power plant);

APCS - automated process control system;

VIK - visual-measuring control;

GOST - state standard;

GPM - lifting mechanism;

GMO - leading materials science organization;

GI - hydraulic tests;

ZIP - spare parts, tools and accessories;

IVS - information-computing system;

IKI - imported components;

ITT - initial technical requirements;

KIP - instrumentation;

ICC - intergranular corrosion;

ND - normative documentation;

OIT - equipment, products and technologies for nuclear installations, radiation sources and storage facilities;

OPB - general security provisions;

OST - industry standard;

QCD - department of technical control;

MPC VK - permanent commission for input control;

PC - quality plan;

PKD - production control documentation;

PSI - acceptance tests;

PTD - production technological documentation;

RKD - working design documentation;

RF - Russian Federation;

RE - operation manual;

SB - assembly drawing;

CPS - control and protection system;

TB1 - base metal quality control table;

TB2 - table of quality control of welding consumables, welded joints and overlays;

TK - terms of reference;

TT - technical requirements;

TU - technical conditions;

MA - authorized organization;

ED - operational documentation;

Ra - arithmetic mean deviation of the surface profile;

Rz - height of surface profile roughness by 10 points.

5 Responsibility of participants

5.1 Organizations participating in acceptance inspections at manufacturing enterprises of products intended for use as part of elements or as an element classified as 1, 2, 3 safety classes according to NP-001 are:

Customer (branch of the Concern (NPP or Directorate of the NPP under construction) - for products supplied directly to NPPs or a Russian manufacturer of equipment / product using this product as a semi-finished product or component);

Authorized organization;

Supplier of the Russian Federation - the holder of an agreement with a foreign manufacturer or a foreign supplier, if it is present in the supply chain;

Manufacturer.

5.2 Organizations participating in the input control at NPP sites of products intended for use as part of elements or as an element classified as 1, 2, 3 safety classes according to NP-001 are:

Branch of the Concern (NPP or Directorate of the NPP under construction) - the end consumer of the products;

General contractor (for NPPs under construction);

Authorized organization;

Assembly organization;

Repair organization;

Provider;

Manufacturer.

5.3 The procedure for the participation of the above organizations in carrying out acceptance inspections at manufacturing plants and/or as part of the MPC of VC at NPP sites is established by the Guiding Documents of the Concern.

5.4 Organizations-participants are responsible for fulfilling the requirements of these Guidelines when organizing, conducting acceptance inspections at manufacturing enterprises and incoming inspections at NPP sites, as well as preparing/participating in the preparation of reporting documents based on their results.

6 Carrying out acceptance inspections and incoming control (general provisions)

6.1 Acceptance inspections are mandatory for products subject to conformity assessment in the form of acceptance in accordance with decision N 06-4421 (amend. 1 - 3) .

6.2 Acceptance inspection is the last step in assessing the conformity / quality control of the manufacture of products with the requirements of the regulatory legal acts of the Russian Federation, RD, ITT (TT) or TK, RKD, PDD and supply contracts, the result of which is a decision on the suitability of products for delivery.

6.3 Products completed in accordance with the supply contract and accepted by the Quality Control Department of the manufacturer are presented for acceptance inspection.

6.4 Acceptance inspection includes:

Checking the completeness of the accompanying documentation;

Checking the correctness of the design and content of the accompanying documentation, including quality documents;

Visual and measuring control of products;

Checking the conformity of the completeness and quantity of products and spare parts;

Checking the conformity of conservation, coloring, packaging and labeling of products;

Checking the conformity of the container.

6.5 In the Quality Plans, the acceptance inspection should be documented by one control point, which ends the Quality Plan and includes the control operations specified in clause 6.4.

6.6 If, according to the conditions of production, these operations are significantly separated in time (for example, it takes several days to complete the entire acceptance inspection complex) or are part of other control points with the status of "HP" for an authorized organization (for example, PSI), then it is allowed to register these operations to separate and as part of other control points, which should be agreed upon when developing and agreeing on the Quality Plan. At the same time, if these operations are not repeated, the remaining operations are indicated in the Quality Plan in accordance with clause 6.4.

6.7 Acceptance inspections of products are carried out by representatives of an authorized organization with the participation of a responsible representative from the manufacturer, appointed by the management of this enterprise in the prescribed manner (by order) to participate in the acceptance inspection.

6.8 Customer (branch of the Concern (NPP or Directorate of NPP under construction) - for products supplied directly to NPPs or a Russian manufacturer of equipment / products using this product as a semi-finished product or component), general contractor (for NPPs under construction), RF supplier - holder contracts with a foreign manufacturer or a foreign supplier, if it is present in the supply chain, establish the need for their participation in the acceptance inspection by determining the status of "HP" at the control point "Acceptance inspection" of the Quality Plan for manufactured products.

6.9 Presentation of products for acceptance inspection is carried out individually or in batches of units of products, or in a combination of several units or batches of products, which is reflected in the Notification of Acceptance Inspection, drawn up in the manner adopted in the Guiding Documents of the Concern.

6.10 If, according to one Quality Plan, the manufacture of several units or batches of products is controlled, for which the manufacturer issues several quality documents and sets of accompanying documentation, verification of the completeness of the accompanying documentation and verification of the correctness of the execution and content of the accompanying documentation, including documents on quality, should be carried out for all sets.

6.11 Input control is carried out at the NPP site in order to prevent the use at NPP of products that do not meet the requirements of the regulatory legal acts of the Russian Federation, RD, ITT (TT) or TK, RKD and supply contracts.

6.12 All products received at the NPP site and intended for use as part of elements or as an element classified as 1, 2, 3, 4 safety classes according to NP-001 are subject to incoming control.

6.13 Prior to the input control, the branch of the Concern and the general contractor (for NPPs under construction) must accept the products delivered to the NPP site in terms of quantity (including checking the compliance of the products with the information specified in the transport documents and checking the absence of damage to the container / packaging) from the transport organization in compliance with the rules provided for by the regulatory legal acts of the Russian Federation regulating the activities of transport.

6.14 Requirements for the procedure for the acceptance of products in terms of the quantity and execution of reporting documentation based on its results, the procedure for identifying non-compliance of products with the information specified in the transport documents, and / or damage to containers / packaging should be established in the procedural documents of the branches of the Concern and general contractors.

6.15 If the results of acceptance by quantity are positive, the incoming inspection of products must be started no later than 10 calendar days from the date of signing the waybill by the general contractor (for NPPs under construction) or a branch of the Concern (for operating NPPs), unless otherwise provided in the contract for supply of products.

6.16 Products, in respect of which a non-compliance was revealed during the input control, is considered not to have passed the input control and is not subject to further use at the NPP site until the identified non-conformities are eliminated.

6.17 The decision on the possibility of further use at the NPP site of products, in respect of which comments were revealed during the input control, is made by the members of the MPC VK, is indicated in the "Conclusion" section of the Input Control Report, which is approved by its chairman. This decision can be made only if there is a letter of guarantee from the general contractor (for NPPs under construction) or the supplier (for NPPs in operation) on the elimination of comments within the time period agreed with the Concern's branch.

6.18 Input control is carried out according to the parameters (requirements) and methods established in the ITT (TT) or TK, RKD (for imported products in the absence of TS, the requirements established in the Technical Requirements, drawn up and agreed in accordance with RD-03-36), ND and contracts for the supply of products.

6.19 The scope of control during the acceptance inspection at the manufacturing plant and incoming inspection at the NPP site of the equipment included in the list of item groups given in Appendices A - E, as a whole, should correspond to the typical scopes given in these Appendices.

TYPICAL SCOPE OF INSPECTIONS DURING ACCEPTANCE INSPECTION AND ENTRANCE INSPECTION OF PUMPING EQUIPMENT OF SAFETY CLASS 1 - 3

Table A.1

1. Specifications or TK for the pump.

2. Drawing general view pump.

3. Assembly drawing of the pump.

4. Specification of the assembly drawing for the pump.

5. Drawings of parts and assembly units that are part of the pump (indicate the designation of the drawings).

6. Table of quality control of the base metal - TB-1.

7. Table of quality control of welding materials, welded joints and surfacing - TB-2.

8. Packing list.

9. Passport of the pump.

10. Operation manual for the pump.

13. Quality plan for the pump.

15. Calculation (extract from the calculation) for the strength and seismic resistance of the pump.

16. Statement of ED.

17. List of spare parts and accessories.

RD-03-36, approved by the Concern and approved by Rostekhnadzor (for pumps manufactured by foreign manufacturers).

RD-03-36, approved by the Concern and approved by Rostekhnadzor (if IKI is available, for pumps manufactured by manufacturers of the Russian Federation).

23. Additional documents in accordance with the TU / TOR and the contract for the manufacture / supply (indicate the name).

Controlled:

2. Correspondence of the dates of examination of control points indicated by the representatives of the manufacturer (its subcontractor / s), with the dates indicated in the documentation issued by the enterprise based on the results of the operations, and in the pump passport.

4. Presence on the List of Development and Approval of the Quality Plan of certifying signatures of all persons and/or outgoing numbers of approval letters of organizations participating in the approval process.

5. Compliance of the total quantity and nomenclature indicated on the Accounting Sheet with serial numbers and the corresponding product passports with the data of the order of the Concern (its branch) and the specification of the contract for manufacturing/supply.

2.2 Passport of the pump

Controlled:

Appendix 4 PNAE G-7-008.

2.2 Specified pump drawing number.

2.3 Specified brand of pump.

2.4 Specified serial number.

2.5 The indicated date of manufacture, the name of the manufacturer and his address.

2.6 Specified characteristics of the pump (the data must match the data in TS / TOR and SB):

Pump pressure;

Maximum and nominal head of the pump;

Inlet pressure;

Design temperature;

Working environment;

Rated feed;

Pressure and temperature of hydraulic tests of the pump housing (the data specified in the section must also comply with the GI protocol and section 5 of PNAE G-7-008);

service life;

Service life up to medium and overhaul(frequency of repair).

2.7 Correspondence of the specified information about the pump elements:

Note: in the case of the use of semi-finished products purchased from an unofficial dealer, the availability of the Certificate Data Confirmation Program agreed with GMOs is additionally controlled (the Program must include a list of tests for these semi-finished products), a Sampling Report with the participation of the Representative of the MA for these semi-finished products and Test Reports in accordance with the above Program ;

The brand of welding materials used corresponds to those indicated in Table. 1 - 9 PNAE G-7-009;

The scope of non-destructive testing complies with the requirements of TB-2 and PNAE G-7-010, table. 2 - 6 (for foreign manufacturers of pumps, the availability of the conclusion of the leading materials science organization on the compliance of the applied non-destructive testing methods and the requirements for certification of controllers with the requirements of PNAE G-7-010 and unified non-destructive testing methods is additionally controlled);

In the case of using semi-finished products from steels and / or welding consumables of foreign production - for Russian enterprises- pump manufacturers are additionally controlled for the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, for foreign enterprises - pump manufacturers, the presence of a conclusion of the leading materials science organization on the compliance of the characteristics of the applied steel grades and / or welding consumables with grades is controlled steels and / or welding consumables specified in PNAE G-7-008, PNAE G-7-009, TU / TK and control tables;

Fittings and instrumentation (the section must be completed in accordance with the supplied fittings with passports / certificates, while additionally for instrumentation, the presence of certificates of approval of the type of measuring instruments obtained from them in the Russian Federation is controlled (according to Federal Law N 102-FZ of June 26, 2008) );

Information about precious materials and non-ferrous metals and their alloys (hereinafter - non-ferrous metals) is indicated in accordance with GOST 2.608 "Procedure for recording information about precious materials in operational documents" for precious materials and GOST 1639 "Scrap and waste of non-ferrous metals and alloys. General specifications. Interstate Council for Standardization, Metrology and Certification" - for non-ferrous metals;

The total (calculated) mass of non-ferrous metals is indicated, as well as information about the locations of the components of the product that contain non-ferrous metals. The name of non-ferrous metals and the sequence of their recording - according to GOST 1639.

Controlled:

Controlled:

1. Compliance appearance products to the requirements of TU / TK, SB.

2. Compliance of overall dimensions with the requirements of TU / TK, SB.

3. Compliance with the connecting dimensions of the nozzles to the requirements of TU / TK, SB.

4. Compliance of cutting the edges of the pipes for welding (if any) with the requirements of the Security Council.

5. The absence of defects on the product: dents on the body, dents in the ends of the fittings, damage to the base metal in the form of burns, deep scratches, tearing of metal and other damage, linear dimensions which (depth / width / length) exceed those established in GOST / TU for metal (GOST, TU for metal are determined from TB1 and passport) and PNAE G-7-025 (section 4.4, if there are body parts made by casting).

Controlled:

2. Compliance with the displacement of edges in butt joints, the height (depth) of the recess between the beads, the scalyness of their surface, the concavity of the weld root, single surface inclusions of welded joints with the requirements of PNAE G-7-010 (section 11.2).

4. Availability and compliance of markings (brands) on welded joints (surfaced parts) with the requirements of section 10 PNAE G-7-009.

6. Compliance with the requirements of PNAE G-7-008 (clauses 2.4.3.3 and 2.4.3.4) that the distance between the edge of the butt weld of the equipment or pipeline and the center of the hole closest to it should be at least 0.9 of the diameter openings while simultaneously observing the following requirement: the distance between the edge of the fillet weld for welding a nozzle or other cylindrical hollow parts and the edge of the nearest butt weld of the equipment must be at the same time not less than three times the calculated height of the fillet weld h and three times the nominal wall thickness of the part to be welded.

These requirements must be specified in the design documentation for the product.

7. Compliance with the requirements of PNAE G-7-008 (clause 2.4.3.8) that the distance between the edges of the nearest fillet welds for welding branch pipes (fittings) to the equipment must be at least three calculated heights of the fillet weld or three nominal wall thicknesses of the welded branch pipes or pipes.

Note: for different values ​​of the indicated heights or thicknesses, their larger value should be taken. The requirements of this paragraph do not apply to the welding of pipes into tube sheets (grids) and collectors, tube sheets of technological channels, CPS channels and other channels.

Controlled:

3. Compliance of the completeness of the spare parts kit with the list of spare parts kits, TU / TK.

Controlled:

TYPICAL SCOPE OF INSPECTIONS DURING ACCEPTANCE INSPECTION AND INCOMING INSPECTION OF ELEMENTS AND PIPELINE UNITS OF SAFETY CLASS 1 - 3

Table B.1

Name of the check 1 Checking the completeness of the accompanying documentation

The presence of the following documents included in the delivery set is controlled:

1. General view drawings (if available for pipeline elements).

2. Assembly drawings (for pipeline blocks).

3. Specifications for assembly drawings (for piping blocks).

4. Drawings of parts and assembly units (for piping blocks, indicate the designation of the drawings).

5. Table of quality control of the base metal - TB-1.

6. Table of quality control of welding materials, welded joints and surfacing - TB-2.

7. Packing list.

8. Certificate of manufacture of parts and assembly units of the NPP pipeline.

9. Calculation (extract from the calculation) for strength.

10. Certificate of manufacture of parts and assembly units of the NPP pipeline (if available for parts and assembly units that are part of the pipeline unit).

11. Certificates for semi-finished products and welding consumables.

12. Quality plan for elements (blocks) of pipelines.

13. Quality plan for components (if available, for parts and assembly units included in the pipeline block, indicate the name, designation and safety class of the component).

14. Decision on application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (for elements (blocks) of pipelines manufactured by foreign manufacturers).

15. Decision on the use of IKI, drawn up in accordance with RD-03-36

16. OIT certificates for equipment and components (in case the products are subject to mandatory certification and are included in the "Unified List of Products Subject to Mandatory Certification", approved by Decree of the Government of the Russian Federation of December 1, 2009 N 982 (effective with appropriate changes)).

17. Additional documents, in accordance with the TU / TOR and the contract for the manufacture / supply (indicate the name).

2 Checking the correctness of the design and content of the accompanying documentation 2.1 Quality plan

Controlled:

1. The presence of signatures of persons participating in the control, and the dates of its implementation at each control point.

2. Compliance of the dates of examination of control points indicated by the representatives of the manufacturer (its subcontractor/s) with the dates indicated in the documentation issued by the enterprise based on the results of the operations, and in the certificate of manufacture of parts and assembly units of the NPP pipeline.

3. The presence on the Identification Sheet of marks on the performance of control, technological operations and quality control in the identification table of signatures with a description of the position and full name. all persons involved in quality control of production.

5. Compliance of the total quantity and nomenclature of the serial numbers indicated on the Accounting Sheet and the corresponding product passports with the data of the order of the Concern (its branch) and/or the manufacturing/supply contract.

2.2 Certificate of manufacture of parts and assembly units of the NPP pipeline

Controlled:

1. Compliance of the form of the Certificate with Appendix 5 PNAE G-7-008.

2. The presence of completed sections of the certificate of manufacture (taking into account the comments in PNAE G-7-008, Appendix 5) and the correctness of their content in terms of compliance:

2.1 The specified license number for manufacturing and the date of its issue, the name of the interregional territorial department of Rostekhnadzor that issued the license.

2.2 The specified name of the manufacturer and his address.

2.3 The specified name of the pipeline for its intended purpose.

2.4 Specified Order No.

2.5 of the indicated year of manufacture.

2.6 Specified working environment.

2.7 The specified design pressure, MPa (kgf / sq. cm).

2.8 Designated temperature, °C.

2.9 of the specified group.

3. Correspondence of the specified data on pipes:

The table is full;

The name of the elements corresponds to the RKD and / or submitted certificates;

Batch and heat numbers correspond to those indicated in the certificates;

Used semi-finished products correspond to table. P9.1 PNAE G-7-008.

Note: in the case of the use of semi-finished products purchased from an unofficial dealer, the presence of the Certificate Data Confirmation Program agreed with GMOs is additionally controlled (the Program must include a list of tests for these semi-finished products), a Sampling Report with the participation of the Representative of the MA for these semi-finished products and Test Reports, according to the above program;

In the case of the use of semi-finished products from steels and / or welding consumables of foreign production - for Russian enterprises - manufacturers of elements and blocks of pipelines, the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, is additionally controlled for foreign enterprises - manufacturers of elements and blocks of pipelines, the presence of the conclusion of the leading materials science organization on the compliance of the characteristics of the applied steel grades and / or welding consumables with the steel grades and / or welding consumables specified in PNAE G-7-008, PNAE G-7-009, drawings and tables of control ;

In the case of the use of semi-finished products from steels of foreign production - for Russian manufacturers, the presence of a Decision on the application, drawn up in accordance with RD-03-36, is additionally controlled

The certificates contain a record of the tests carried out at the ICC (for steels of the austenitic class). If the certificate does not contain data on the IWC, a factory test report must be submitted.

If the certificate does not contain the data required for confirmation in accordance with TB-1 according to the certificate data, the availability of relevant test reports is controlled.

Note: the batch and heat number is filled in for pipes made of austenitic steels with an outer diameter of 57 mm or more and for pipes made of steels of other structural classes with an outer diameter of 108 mm or more, operating under a pressure of 3.93 MPa (40 kgf / sq. cm) and more. For pipes of group B systems of the indicated standard sizes, the accompanying documentation must include metal quality control data (certificates) to the extent stipulated by the standards or specifications.

4. Compliance with the specified data on fittings (cast, welded, stamped, forged from a sheet):

The applied materials correspond to tab. P9.1 PNAE G-7-008.

Note: for pipes of group B systems made of austenitic steels with an outer diameter of 57 mm and above and from steels of other structural classes with an outer diameter of 108 mm and above, operating under a pressure of 3.93 MPa (40 kgf / sq. cm) and more, in the composition the accompanying documentation must include metal quality control data (certificates) to the extent stipulated by the technical documentation.

5. Compliance with the specified data on welded joints:

The table is filled (in the presence of fittings);

The name of the connected elements corresponds to the RKD;

RD-03-36

The designations (numbers) and dates of the documents (protocols, conclusions, etc.) drawn up based on the results of the control correspond to those presented;

The data on the heat treatment of pipes, fittings and welded joints are indicated.

6. Compliance of the indicated results of hydraulic tests with the Protocol of hydraulic tests, the requirements of the RKD and section 5 of the PNAE G-7-008.

7. The presence of a completed Conclusion, including the presence of signatures of the director or chief engineer of the enterprise, head of the Quality Control Department, the seal of the manufacturer and the date of issuance of the certificate.

2.3 Documents of registration of nonconformities and decisions taken

Controlled:

1. For Nonconformity Reports (nonconformities of class and type B-1, B-2, B-3):

The form of the Report complies with RD EO 1.1.2.01.0930;

All columns of the Non-Conformity Report are completed;

The type of nonconformity is determined correctly, according to the classification of nonconformities (RD EO 1.1.2.01.0930);

The non-compliance report was approved in accordance with the established procedure, in accordance with RD EO 1.1.2.01.0930.

2. For Decisions (non-compliance of class and type A and B-4):

The decision was agreed upon in the prescribed manner, in accordance with RD EO 1.1.2.01.0930;

The decision was approved by Rostekhnadzor or a letter from Rostekhnadzor was attached to it stating that in this case there were no violations of federal norms and rules in the field of the use of atomic energy (for class A non-compliances);

All measures for the Resolution have been completed.

Controlled:

1. Compliance of the appearance of the product with the requirements of the RKD and / or OST.

2. Compliance of overall dimensions with the requirements of RKD and/or OST.

3. Compliance of connecting dimensions of branch pipes with the requirements of RKD and/or OST.

4. Compliance with the cutting of the edges of the pipes for welding (if any) with the requirements of the RKD and / or OST.

5. Absence of external damage on the product: dents on the side surfaces, dents on the ends, damage to the base metal in the form of burns, deep scratches, tearing of metal and other damage, the linear dimensions of which (depth/width/length) exceed those established in GOST/TU for metal (GOST, TU for metal are determined from TB1 and manufacturing certificate).

6. With flange bolt plugs:

3.2 External inspection of welded joints (if there is welding)

Controlled:

1. The absence of defects in welded joints according to PNAE G-7-010 (Section 11.2), visible during visual inspection: surface cracks of all types and directions; exfoliation; influxes; splashes of metal; burns, fistulas, shrinkage shells; undercuts; lack of penetration; clusters and non-single inclusions.

3. Compliance with the shape and dimensions of the welds (width and height of reinforcement, leg value, concavity) with the requirements of PNAE G-7-009 and RKD.

4. Availability and compliance of markings (brands) on welded joints (surfaced parts) with the requirements of section 10 PNAE G-7-009. Compliance of the brand number on the product with the number specified in the section "Data on welded joints" of the Certificate of manufacture.

5. In case of presence of unmarked welded joints (surfacing), the description of this case in the design documentation and the presence in the accompanying documentation of sketches (diagrams) of the product indicating the location of non-marked welded joints and the brands of welders who performed welding (surfacing) are controlled.

Note: it should be taken into account that (in accordance with paragraph 10.4 of PNAE G-7-009) if all welded joints of the product are made by one welder, then branding (marking) of each welded joint may not be carried out. In this case, the welder's brand is placed near the nameplate or on another open area of ​​\u200b\u200bthe product (or welded assembly) and the place of branding is enclosed in a clearly visible frame applied with indelible paint (the latter does not apply to product surfaces washed with coolant).

The requirements of paragraphs 2.3.3 - 2.3.5, 2.4.2.5 for elbows/bends are met;

The requirements of clause 2.3.6 for the location of openings on pipelines have been met;

Butt welded joints (if any) are made with full penetration (clause 2.4.1.2);

Welded pipes are made of a maximum of 2 sectors (with an outer diameter of up to 920 mm) and a maximum of 3 sectors (with an outer diameter of more than 920 mm). The central angle of each sector is not less than 90° (clause 2.4.2.1);

There are no welds in the pipe sections to be bent (2.4.2.4);

If there are welded elbows within the curved section, there is no more than one transverse ring joint (clause 2.4.2.5);

In the case of sector bends made of welded pipes, the distance between the mates of the transverse annular seam of the bend with the longitudinal or spiral seams of the connected sectors or pipes must be at least 100 mm, while the indicated distance is measured between the junction points of the axes of the corresponding seams (clause 2.4. 2.6);

The lack of alignment of the axes of the longitudinal seams of two adjacent parts in transverse butt welded joints of parts (assembly units) with longitudinal welded joints. The axes of these seams must be offset relative to each other by a distance of at least three times the nominal thickness of the thicker-walled part of the parts to be joined, but not less than 100 mm (the latter condition does not apply to welded joints of parts with a nominal outer diameter of less than 100 mm) - p 2.4.3.1.

Note: for cylindrical parts (assembly units) with longitudinal seams made by automatic welding, it is allowed to reduce the specified distance (including the location of the longitudinal seams of the parts to be joined along one axis), subject to radiographic and ultrasonic, as well as capillary or magnetic particle control of mating or intersection areas longitudinal and transverse welded joints (ultrasonic testing of welded joints of parts made of austenitic steels is not mandatory);

Fulfillment of the requirements of paragraphs 2.4.3.3 and 2.4.3.4 that the distance between the edge of the butt weld of the equipment or pipeline and the center of the hole closest to it should be at least 0.9 of the hole diameter, while simultaneously observing the following requirement: the distance between the edge fillet weld welding of a fitting or other cylindrical hollow parts and the edge of the nearest butt weld of the equipment must be at the same time not less than three times the calculated height of the fillet weld h and three times the nominal wall thickness of the welded part.

Note: In accordance with paragraph 2.4.3.5 of PNAE G-7-008, it is allowed to reduce the distances specified in paragraphs 2.4.3.3 and 2.4.3.4 (including the location of holes in the butt weld) while simultaneously observing the following requirements:

Drilling holes must be carried out after heat treatment (if any) of the butt welded joint and its continuous non-destructive testing by methods provided for welded joints of the corresponding category; drilling of holes is allowed before heat treatment of the welded joint, if after welding of branch pipes (fittings) and performing heat treatment, boring (reaming) of the hole is performed with the removal of the root part of the weld; in this case, heat treatment of butt welded joints, in which holes for welding nozzles are made, may be combined with heat treatment (if any) of fillet welded joints for welding nozzles;

The yield strength of the weld metal of a butt welded joint at the design temperature must not be lower than the yield strength of the base metal (yield strengths are taken according to standards or specifications for materials and (or) tables of the Norms for calculating strength and PC; in the absence of such information in the specified documentation, it is allowed to use certificate data) this requirement is not mandatory in the case of welding branch pipes (fittings) and pipes without flaring, if the stresses in the butt welded joint of the equipment or pipeline do not exceed the yield strength of the weld metal and the base metal at the design temperature;

The inner surface of the holes must be subjected to capillary or magnetic particle testing.

The distance between the axes of adjacent transverse butt welds must be at least three times the nominal wall thickness of the welded parts (for the greater thickness), but not less than 100 mm for products having a nominal outer diameter of more than 100 mm in the zone of welded joints, and not less than the specified diameter when its value is up to 100 mm inclusive (clause 2.4.3.6);

The distance between the edges of the nearest fillet welds for welding branch pipes (fittings) to pipelines must be at least three calculated heights of the fillet weld or three nominal wall thicknesses of the welded branch pipes or pipes. For different values ​​of the indicated heights or thicknesses, their larger value should be taken (clause 2.4.3.8);

The distance from the edge of the nozzle weld to the edge of the nearest transverse pipe weld when welding nozzles to measuring orifice chambers shall simultaneously be equal to at least three wall thicknesses of the welded nozzle and three times the design height of the fillet weld (clause 2.4.3.7).

The distance from the edge of the butt weld to the beginning of the curved section of the bend on pipelines with a nominal outer diameter of 100 mm or more must be at least 100 mm, and for pipelines with a nominal outer diameter of up to 100 mm - not less than the nominal outer diameter of the pipe. For stamped, forged and stamp-welded elbows (bends), bent pipes of heat exchange surfaces and steeply bent elbows, it is allowed to reduce the straight section of the elbow (bend), as well as the location of the transverse weld at the border of the straight and curved sections (clause 2.4.3.13).

Note: when welding parts (assembly units) to pipelines, the straight sections of which have a limited length or are absent (tees, fittings, bent elbows, stamped and stamp-welded transitions, etc.), the requirements of paragraphs 2.4.3.1 - 2.4.3.13 PNAE G-7-008 are not mandatory, provided that local heat treatment and/or ultrasonic testing of welded joints is possible (clause 2.4.3.14);

When welding branch pipes (fittings) into pipelines from pipes with longitudinal or spiral seams, there should be no exit of pipe welds to the corner (upper and lower) points of intersection of the generatrix of the pipe and fitting. The minimum distance measured on the outer surface from the indicated points to the axes of the pipe welds must be at least 100 mm (clause 2.4.3.15).

4 Checking the compliance of the completeness and quantity of equipment and spare parts

Controlled:

1. Compliance of the completeness of the product with the packing list.

2. Compliance of the quantity of shipped products with the specification of the contract for manufacturing/supply and the Quality Plan.

5 Checking the conformity of conservation, coloring, packaging and labeling of products. Checking the conformity of containers

Controlled:

1. Compliance of product marking (volume of records) with the requirements of RKD/OST.

2. Compliance with factory N products, year of manufacture, brand of the manufacturer, records in the certificate of manufacture.

3. The nozzles of the product are plugged in accordance with the requirements of the RKD / OST and the instructions for packing.

4. Compliance of product coloring with the requirements of RKD/OST.

5. Compliance of packaging and preservation of the product with the requirements of RKD / OST and GOST 9.014.

6. Terms of temporary anticorrosive protection of products do not exceed those specified in GOST 9.014.

7. Compliance of containers with the requirements of the drawing, GOST 15150 and RKD/OST.

TYPICAL SCOPE OF INSPECTIONS DURING ACCEPTANCE INSPECTION AND ENTRANCE INSPECTION OF HEAT EXCHANGING EQUIPMENT/PRESSURE VESSELS 1 - 3 SAFETY CLASSES

Table B.1

Name of the check 1 Checking the completeness of the accompanying documentation

The presence of the following documents included in the delivery set is controlled:

1. General view drawing of heat exchange equipment/vessel.

2. Assembly drawing of heat exchange equipment/vessel.

3. Drawings of parts and assembly units included in the heat exchange equipment/vessel (indicate designation of drawings).

6. Specifications or TOR for heat exchange equipment/vessel.

7. Packing list.

8. Assembly drawing specification for heat exchange equipment/vessel.

9. Passport of heat exchange equipment/vessel.

10. Operation manual for heat exchange equipment/vessel.

11. Passport and instruction manual for components (if available, indicate the name, designation and safety class of the component).

12. Documents of registration of nonconformities and decisions made (if any).

13. Quality plan for heat exchange equipment/vessel.

14. Quality plan for components (if available, indicate the name, designation and safety class of the component).

15. Calculation (extract from the calculation) for the strength and seismic resistance of heat exchange equipment/vessel.

16. Statement of ED.

17. List of spare parts and accessories.

18. Specifications for repairs.

19. List of documents for repairs.

20. Application decision, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (for heat exchange equipment/vessel manufactured by foreign manufacturers).

21. Decision on the use of IKI, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (if IKI is available for heat exchange equipment / vessel manufactured by manufacturers of the Russian Federation).

22. OIT certificates for equipment and components (in the event that products are subject to mandatory certification and are included in the "Unified list of products subject to mandatory certification", approved by Decree of the Government of the Russian Federation of December 1, 2009 N 982 (effective with appropriate changes)).

2 Checking the correctness of the design and content of the accompanying documentation 2.1 Quality plan

1. Controlled:

2. The presence of signatures of persons participating in the control, and the dates of its implementation at each control point.

3. Compliance of the dates of examination of control points indicated by the representatives of the manufacturer (its subcontractor/s) with the dates indicated on the documentation issued by the enterprise based on the results of the operations, and in the passport of the heat exchange equipment.

4. The presence on the Identification Sheet of marks on the performance of control, technological operations and quality control in the table of identification of signatures with a breakdown of the position and full name. all persons involved in quality control of production.

5. Availability on the List of Development and Approval of the Quality Plan of certifying signatures of all persons and/or approval letters of organizations participating in the approval process.

6. Compliance of the total quantity and nomenclature of the serial numbers indicated on the Accounting Sheet and the corresponding product passports with the order of the Concern (its branch) and the specification of the contract for manufacturing/supply.

2.2 Vessel passport

Controlled:

1. Correspondence of the passport form with Appendix 3 PNAE G-7-008.

2. The presence of completed sections of the passport and the correctness of their content in terms of compliance:

2.1 The specified license number for manufacturing and the date of its issue, the name of the interregional territorial department of Rostechnadzor that issued the license.

2.2 The specified name of the heat exchange equipment/vessel.

2.3 The specified registration number (assigned by the interregional territorial department of Rostekhnadzor (when registering heat exchange equipment/vessel in this body) or by the owner enterprise (when registering heat exchange equipment/vessel at this enterprise)).

2.4 Specified:

Names and addresses of the supplier;

Factory number;

Year of manufacture;

Drawing designations;

Equipment groups.

2.5 Specified characteristics of the heat exchange equipment/vessel (the data must match the data in TS/TOR and SB):

design pressure;

Estimated wall temperature;

Hydraulic (pneumatic) test pressures, names of the test medium, test duration and test temperature (the data specified in the section must comply with the GI protocol, the requirements of TK / TU and SB, section 5 of PNAE G-7-008);

The minimum allowable wall temperature during hydraulic (pneumatic) tests after manufacture;

working environment;

internal volume;

Masses of equipment without working environment;

service life;

Service life before overhaul (repair frequency).

2.6 Correspondence of the specified data on the main elements of the heat exchange equipment/vessel and materials:

The table is full;

Certificate numbers correspond to those presented;

Grades of materials, types of blanks, numbers of melts and numbers of semi-finished products (batches) used in the manufacture of parts and assembly units of heat exchange equipment / vessel correspond to those indicated in the certificates;

Used semi-finished products correspond to table. P9.1 PNAE G-7-008;

In the case of the use of foreign-made steels, for Russian manufacturers, the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, is additionally controlled for Russian manufacturers, for foreign manufacturers, the presence of a conclusion of the head materials science organization on the compliance of the characteristics of the applied steel grades steel grades specified in PNAE G-7-008, drawings and control tables;

The certificates contain a record of the tests carried out at the ICC (for steels of the austenitic class). If the certificate does not contain data on the ICC, a factory test report must be submitted;

The specified volume of control of the base metal corresponds to TB-1.

Note: if the certificate does not contain the data required for confirmation in accordance with TB-1 according to the certificate data, the availability of relevant test reports is controlled. In the case of the use of semi-finished products purchased from an unofficial dealer, the availability of the Certificate Data Confirmation Program agreed with GMOs is additionally controlled (the Program must include a list of tests for these semi-finished products), a Sampling Report with the participation of the Representative of the MA for these semi-finished products and Test Reports, according to the above Program;

The table contains information about fasteners, or a link to the quality document for these parts, which is included in the accompanying documentation.

2.7 Correspondence of the specified data on welded joints and surfacing (the data must be indicated in the scope established by the quality control table for welding consumables, welded joints and surfacing - TB-2):

The table is full;

The name of the connected elements corresponds to TB-2;

The numbers of welded joints or overlays indicated in the table correspond to TB-2 and the scheme of welded joints;

The brand (designation) of the welder corresponds to the data specified in the certificates of welders and in orders for the appointment of brands;

The name and brand of the materials to be welded correspond to those specified in the section "Data on the main elements of the vessel and materials";

Applied welding materials correspond to table. 1 - 9 PNAE G-7-009;

The scope of non-destructive testing complies with the requirements of RKD and PNAE G-7-010 tab. 2 - 6 (for foreign manufacturers, the availability of the conclusion of the parent materials science organization on the compliance of the applied non-destructive testing methods and the requirements for certification of controllers with the requirements of PNAE G-7-010 and unified non-destructive testing methods is additionally controlled);

In the case of the use of foreign-made welding consumables, for Russian manufacturers, the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, is additionally controlled for Russian manufacturers, for foreign manufacturers, the presence of a conclusion of the head material science organization on compliance with the characteristics applied grades of welding consumables to grades of welding consumables specified in PNAE G-7-009 and control tables;

The designations (numbers) and dates of the documents (protocols, conclusions, etc.) drawn up based on the results of the control correspond to those presented.

2.8 Compliance of the specified data on the heat treatment of parts, assembly units of products:

The table is full;

The name of parts and assembly units corresponds to the RKD;

The heat treatment data correspond to the data given in the oven charts and heat treatment diagrams or quality documents (for purchased components).

2.9 Correspondence of the specified data on fittings and safety fittings:

The tables are full;

The data given in the tables correspond to the data given in the passports for fittings and the requirements of TU/TOR for heat exchange equipment/vessel;

Forms of passports for fittings comply with the requirements of NP-068;

Safety class and armature group corresponds to the safety class and group of heat exchange equipment/vessel.

2.10 The results of hydraulic (pneumatic) tests (correspond to the attached test report and the requirements of TU / TK section 3.2 of the Passport for valves, section 5 PNAE G-7-008).

2.11 Information about precious materials and non-ferrous metals and their alloys (hereinafter - non-ferrous metals) is indicated in accordance with GOST 2.608 "Procedure for recording information about precious materials in operational documents" for precious materials and GOST 1639 "Scrap and waste of non-ferrous metals and alloys. General specifications. Interstate Council for Standardization, Metrology and Certification" - for non-ferrous metals.

2.12 The total (calculated) mass of non-ferrous metals is indicated, as well as information about the locations of the components of the product that contain non-ferrous metals. The name of non-ferrous metals and the sequence of their recording - according to GOST 1639.

2.13 The presence of a completed Conclusion, including the presence of signatures of the director or chief engineer of the enterprise, the head of the QCD, the seal of the manufacturer and the date of issuance of the passport.

2.3 Documents of registration of nonconformities and decisions taken

Controlled:

1. For Nonconformity Reports (nonconformities of class and type B-1, B-2, B-3):

The form of the Report complies with RD EO 1.1.2.01.0930;

All columns of the Non-Conformity Report are completed;

The type of nonconformity is determined correctly, according to the classification of nonconformities (RD EO 1.1.2.01.0930);

The non-compliance report was approved in accordance with the established procedure, in accordance with RD EO 1.1.2.01.0930.

2. For Decisions (non-compliance of class and type A and B-4):

The decision was agreed upon in the prescribed manner, in accordance with RD EO 1.1.2.01.0930;

The decision was approved by Rostekhnadzor or a letter from Rostekhnadzor was attached to it stating that in this case there were no violations of federal norms and rules in the field of the use of atomic energy (for class A non-compliances);

All measures for the Resolution have been completed.

3. Visual and measurement control of products 3.1 External inspection of equipment in accessible places

Controlled:

3. The location of the branch pipes on the heat exchange equipment/vessel complies with the requirements of TU/TOR and SB.

4. Compliance with the connecting dimensions of the nozzles to the requirements of TU / TK and SB.

5. Compliance of cutting the edges of the pipes for welding (if any) with the requirements of the Security Council.

6. The absence of external damage on the product: dents on the side surfaces, dents in the ends of the fittings, the difference in surfaces (deplanation) of the bottom and cover does not exceed the base metal damage required in the drawings (if any) in the form of burns, deep scratches, tearing of metal and other damage , whose linear dimensions (depth / width / length) exceed those established in GOST / TU for metal (GOST, TU for metal are determined from TB-1 and passport).

7. In the presence of flanged bolted connections of the bottom and cover:

A gasket is installed in the flange connection (the material complies with the requirements of the RKD);

Fasteners are fully installed and comply with the product specification;

The ends of the bolts / studs protrude from the nuts by 2 - 3 turns.

3.2 External inspection of welded joints (if there is welding)

Controlled:

1. The absence of defects in welded joints according to PNAE G-7-010 (Section 11.2), visible during visual inspection: surface cracks of all types and directions; exfoliation; influxes; splashes of metal; burns, fistulas, shrinkage shells; undercuts; lack of penetration; clusters and non-single inclusions.

2. Compliance with the displacement of edges in butt joints, the height (depth) of the recess between the beads, the scalyness of their surface, the concavity of the weld root, single surface inclusions of welded joints with the requirements of PNAE G-7-010 (section 11.2).

3. Compliance with the shape and dimensions of the welds (width and height of reinforcement, leg value, concavity) with the requirements of PNAE G-7-009 and RKD.

5. In case of presence of unmarked welded joints (surfacing), the description of this case in the design documentation and the presence in the accompanying documentation of sketches (diagrams) of the product indicating the location of unmarked welded joints and the brands of welders who performed welding (surfacing) are controlled.

Note: it should be taken into account that (in accordance with paragraph 10.4 of PNAE G-7-009) if all welded joints of the product are made by one welder, then branding (marking) of each welded joint may not be carried out. In this case, the welder's brand is placed near the nameplate or on another open area of ​​\u200b\u200bthe product (or welded assembly) and the place of branding is enclosed in a clearly visible frame applied with indelible paint (the latter does not apply to product surfaces washed with coolant).

6. Compliance with the requirements of PNAE G-7-008 (requirements for the design and location of welds):

6.1 Butt welded joints (if any) are made with full penetration.

6.2 Shell:

6.2.1 The shell is made of a maximum of 2 sectors (with an outer diameter of up to 920 mm) and a maximum of 3 sectors (with an outer diameter of more than 920 mm). The central angle of each sector must be at least 90° (clause 2.4.2.1);

6.2.2 If there are longitudinal and transverse welds on the shell, the axes of the longitudinal welds are displaced relative to each other (clause 2.4.3.1):

If the outer diameter of the shell is more than 100 mm - by a distance of at least three times the nominal thickness of the thicker-walled of the parts to be joined, but not less than 100 mm;

With the outer diameter of the shell less than 100 mm - at a distance of at least three times the nominal thickness of the thicker of the parts to be joined.

Note: the specified requirement is not mandatory if the longitudinal seams are made by automatic welding and at the same time the control of the areas of interface or intersection of longitudinal and transverse welded joints is carried out:

radiographic;

Ultrasonic (for welded joints of parts made of austenitic steels, it is not mandatory);

Capillary or magnetic particle.

6.3 Bottoms, covers:

6.3.1 When welding bottoms or covers from several parts (sheets) with the location of welds along the chord, the distance from the outer edge of the weld to the diameter of the bottom or cover parallel to the chord is not less than 0.2 of the nominal inner diameter of the bottom or cover (clause 2.4.3.2) .

6.3.2 If there is a circumferential weld, the distance between the outer edge of the circumferential weld on bottoms and lids (except for spherical and dish-shaped ones) and the center of the bottom or lid is not more than 0.25 of the nominal internal diameter of the bottom or lid, and the minimum distance between the edges of two adjacent radial or meridional welds must be at least three nominal thicknesses of the bottom or cover, but not less than 100 mm (clause 2.4.3.2).

Note: the requirement for the location of the circular seam does not apply to the seams of welding of covers and bottoms to flanges and shells.

6.4 Welding and location of fittings, hatches:

6.4.1 Compliance with the requirements of paragraphs 2.4.3.3 and 2.4.3.4 that the distance between the edge of the butt weld of the equipment or pipeline and the center of the hole closest to it should be at least 0.9 of the hole diameter, while simultaneously observing the following requirement: the distance between the edge of the fillet weld for welding a nozzle or other cylindrical hollow parts and the edge of the nearest butt weld of the equipment must be at the same time not less than three times the calculated height of the fillet weld h and three times the nominal wall thickness of the part to be welded.

Note: in accordance with paragraph 2.4.3.5 of PNAE G-7-008, it is allowed to reduce the distances specified in paragraphs 2.4.3.3 and 2.4.3.4 (including the location of holes in the butt weld) while simultaneously observing the following requirements:

Drilling holes must be carried out after heat treatment (if any) of the butt welded joint and its continuous non-destructive testing by methods provided for welded joints of the corresponding category; drilling of holes is allowed before heat treatment of the welded joint, if after welding of branch pipes (fittings) and performing heat treatment, boring (reaming) of the hole is performed with the removal of the root part of the weld; in this case, heat treatment of butt welded joints, in which holes for welding nozzles are made, may be combined with heat treatment (if any) of fillet welded joints for welding nozzles;

The yield strength of the weld metal of a butt welded joint at the design temperature must not be lower than the yield strength of the base metal (yield strengths are taken according to the standards or specifications for materials and (or) tables of strength calculation standards and the Control Rules; in the absence of such information in the specified documentation, it is allowed use certificate data) this requirement is not mandatory in the case of welding branch pipes (fittings) and pipes without flaring, if the stresses in the butt welded joint of the equipment or pipeline do not exceed the yield strength of the weld metal and the base metal at the design temperature;

The inner surface of the holes must be subjected to capillary or magnetic particle testing.

These requirements must be specified in the design documentation for the product;

6.4.2 The distance between the axes of adjacent transverse butt welds on cylindrical and conical products must be at least three times the nominal wall thickness of the welded parts (over the greater thickness), but not less than 100 mm for products having a nominal outer diameter in the zone of welded joints over 100 mm, and not less than the specified diameter with its value up to 100 mm inclusive (clause 2.4.3.6).

Note: this requirement does not apply to welds for welding pipelines to branch pipes of equipment and fittings, if these branch pipes were subjected to heat treatment as part of equipment and fittings, as well as to welds for welding tube sheets and elements such as rings having a thickness of more than twice exceeding the thickness of the flanging for welding;

6.4.3 The distance between the edges of the nearest fillet welds for welding branch pipes (fittings) to pipelines shall be at least three design heights of the fillet weld or three nominal wall thicknesses of the welded branch pipes or pipes. For different values ​​of the indicated heights or thicknesses, their larger value should be taken (clause 2.4.3.8);

6.4.4 The distance from the edge of the nozzle weld to the edge of the nearest transverse pipe weld when welding nozzles to measuring orifice chambers shall simultaneously be at least three times the wall thickness of the welded nozzle and three times the design height of the fillet weld (clause 2.4.3.7).

Note: it is allowed to place fittings with an outer diameter of up to 30 mm in the heat-affected zone of the annular seams of measuring devices with nozzles and diaphragms;

6.4.5 The distance from the edge of the choke weld to the edge of the nearest transverse pipe weld when welding the choke to the chambers of the measuring diaphragms is simultaneously at least three times the wall thickness of the welded choke and three times the design height of the fillet weld (clause 2.4.3.7);

Note: it is allowed to place fittings with an outer diameter of up to 30 mm in the heat-affected zone of the annular seams of measuring devices with nozzles and diaphragms.

6.4.6 The distance between the edges of the nearest fillet welds for welding branch pipes (fittings) or pipes to equipment or pipelines is equal to at least three design heights of the fillet weld or three nominal wall thicknesses of the branch pipes or pipes to be welded. For different values ​​of the indicated heights or thicknesses, their larger value should be taken (clause 2.4.3.8).

Note: the requirements of this paragraph do not apply to the welding of pipes into tube sheets (grids) and collectors, tube sheets of technological channels, CPS channels and other channels;

6.4.7 When welding non-pressure flat parts to the surfaces of equipment and pipelines, the distance between the edge of the fillet weld of these parts and the edge of the nearest butt weld of the equipment or pipeline, as well as between the edges of the fillet welds of the nearest parts to be welded, is equal to at least three design (maximum) heights fillet welds (clause 2.4.3.9).

Note: when welding in-hull (out-of-hull) parts and devices, it is allowed to intersect the butt welds of equipment with fillet welds with a calculated height of not more than 0.5 of the nominal thickness of the shell wall, but not more than 10 mm;

6.4.8 The distance between the edge of the seam of the butt welded joint of the pipeline with the branch pipe (fitting) of the equipment and the edge of the seam of the nearest butt welded joint on the pipeline (i.e. the length of the branch pipe) is at least 100 mm for pipelines with a nominal outer diameter of more than 100 mm and not less than the nominal outer diameter for pipelines of smaller diameter (2.4.3.10).

Note: when welding parts (assembly units) to equipment or pipelines, the straight sections of which have a limited length or are absent (tees, fittings, bent elbows, stamped and stamp-welded transitions, etc.), the requirements of paragraph 2.4.3.1 - 2.4.3.13 are not mandatory provided local heat treatment and/or ultrasonic testing of welded joints has been carried out.

3.3 Internal inspection of the product

Controlled:

1. The absence of foreign objects, dirt, water inside the products.

2. No damage to the base metal in the form of burns, traces of foreign objects, defects machining.

4 Checking the compliance of the completeness of the quantity of equipment and spare parts

Controlled:

1. Compliance of the completeness of the product with the packing list and TU / TK.

2. Compliance of the quantity of shipped products with the specification of the contract for manufacturing/supply and the Quality Plan.

3. Correspondence of the completeness of the spare parts kit with the list of spare parts and accessories kits.

5 Checking the conformity of conservation, coloring, packaging and labeling of products. Checking the conformity of containers

Controlled:

1. Compliance of the product marking (volume of records) with the requirements of the OM, passport, TU / TK and PNAE G-7-008 (clause 1.2.13).

2. Compliance with factory N of the product, year of manufacture, brand of the manufacturer, entries in the passport.

3. The nozzles of the product are plugged in accordance with the requirements of TU / TOR and instructions for packing.

4. Compliance of the color of the product with the requirements of TU/TOR and RE (preservation section).

5. Compliance of the packaging and preservation of the product with the requirements of the RE, TU / TK and GOST 9.014.

6. Terms of temporary anticorrosive protection of products (according to the passport) do not exceed those specified in GOST 9.014.

7. Compliance of the container with the requirements of the drawing, GOST 15150 and TU / TK.

TYPICAL SCOPE OF CHECKS DURING ACCEPTANCE INSPECTION AND ENTRANCE INSPECTION OF PIPELINE FITTINGS 1 - 3 SAFETY CLASSES

Table D.1

Name of the check 1 Checking the completeness of the accompanying documentation

The presence of the following documents included in the delivery set is controlled:

1. General view drawing of pipeline fittings.

2. Assembly drawing of pipeline fittings.

3. Drawings of wear and body parts that are part of pipeline fittings (indicate the designation of the drawings).

4. Table of quality control of the base metal - TB-1.

5. Table of quality control of welding materials, welded joints and surfacing - TB-2.

6. Specifications or TK for pipeline fittings.

7. Packing list.

8. Specification of the assembly drawing for pipeline fittings.

9. Passport of pipeline fittings.

10. Operation manual for pipeline fittings.

11. Passport and instruction manual for components (if available, indicate the name, designation and safety class of the component).

12. Documents of registration of nonconformities and decisions made (if any).

13. Quality plan for pipeline fittings.

14. Quality plan for components (if available, indicate the name, designation and safety class of the component).

15. Calculation (extract from the calculation) for the strength and seismic resistance of pipeline fittings.

16. Statement of ED.

17. List of spare parts and accessories.

18. Specifications for repairs.

19. List of documents for repairs.

20. Decision on application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (for pipeline valves manufactured by foreign manufacturers).

21. Decision on the use of IKI, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (if IKI is available, for elements and blocks manufactured by manufacturers of the Russian Federation).

22. OIT certificates for equipment and components (in case the products are subject to mandatory certification and are included in the "Unified list of products subject to mandatory certification", approved by Decree of the Government of the Russian Federation of December 1, 2009 N 982 (effective with appropriate changes)).

23. Additional documents, in accordance with the TU / TOR and the contract for the manufacture / supply (indicate the name).

Notes:

1. The passport must be supplied with each fitting with DN > 150 and with each safety valve (with each main and each IR - for IPU) regardless of DN. For fittings DN< 150 допускается оформление одного паспорта на партию изделий в количестве до 50 шт.

2. Strength calculation and working drawings of body and wear parts of each standard size should be sent with the first product in one copy for a batch of products.

2 Checking the correctness of the design and content of the accompanying documentation 2.1 Quality plan

Controlled:

1. The presence of signatures of persons participating in the control, and the dates of its implementation at each control point.

2. Compliance of the dates of examination of control points indicated by the representatives of the manufacturer (its subcontractor / s) with the dates indicated on the documentation issued by the enterprise based on the results of the operations, and in the passport of pipeline valves.

3. The presence on the Identification Sheet of marks on the performance of control, technological operations and quality control in the identification table of signatures with a description of the position and full name. all persons involved in quality control of production.

4. Availability on the List of Development and Approval of the Quality Plan of certifying signatures of all persons and/or approval letters of organizations participating in the approval process.

5. Compliance of the total quantity and nomenclature of the serial numbers indicated on the Accounting Sheet and the corresponding product passports with the order of the Concern (its branch) and the specification of the contract for manufacturing/supply.

2.2 Passport for fittings

Controlled:

1. Compliance of the passport form with Annex 15 NP-068.

2. The presence of completed sections of the passport and the correctness of their content in terms of compliance:

2.1 The specified license number for manufacturing and the date of its issue, the name of the interregional territorial department of Rostechnadzor that issued the license.

2.2 Specified:

Product name;

Drawing designations;

Designations TU / TK;

Names and addresses of the manufacturer;

Safety class and armature group;

Classification designation;

Factory number;

Nominal diameter (DN);

Service life to medium and major repairs, or by cycles of opening and closing.

2.3 The specified characteristics of the reinforcement (the data must match the data in TS / TOR and SB):

Name of the working environment;

design pressure;

design temperature;

working pressure;

operating temperature;

service life;

Reinforcement speed (opening and closing time).

2.4 Specified characteristics of the actuator (for motorized valves, the data must match the passport of the actuator and the data indicated on its marking):

Type of drive;

Drawing designation;

Drive version;

Factory number;

Gear ratio;

Maximum torque.

Note: in the passport in the characteristics of the product:

For safety valves, in addition, the passport must indicate the response (opening) pressure, the reset pressure (from the spring), the gas (liquid) flow rates, the valve cross-sectional area, or the dependence of the throughput on the pressure difference is given;

For control valves, in addition, the passport must indicate the coefficient of conditional throughput, throughput characteristic.

2.5 The indicated results of hydraulic tests - comply with the attached test report and the requirements of TU / TK and section 5 of PNAE G-7-008.

2.6 The indicated results of the seal tightness tests - correspond to the attached test report, leaks comply with the requirements of TU / TK.

2.7 The specified information about the main and fasteners (including information about their overlays):

The table is full;

The name of parts and assembly units corresponds to the RKD;

Certificate numbers correspond to those presented;

Used semi-finished products correspond to table. P9.1 PNAE G-7-008 and applications 11 - 12 NP-068;

In the case of using foreign-made steels (with the exception of those specified in Appendices 11 - 12 NP-068) - for Russian manufacturing enterprises, the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, is additionally controlled for foreign manufacturing enterprises, the presence of the conclusion of the parent materials science organization on the compliance of the characteristics of the applied steel grades with the steel grades specified in PNAE G-7-008, drawings and control tables is controlled;

Applied welding materials correspond to table. 1 - 9 PNAE G-7-009;

The applied materials for surfacing sealing and guiding surfaces comply with Appendix 13 NP-068;

The scope of non-destructive testing complies with the requirements of RKD and PNAE G-7-010 tab. 2 - 6 (for foreign manufacturers, the availability of the conclusion of the parent materials science organization on the compliance of the applied non-destructive testing methods and the requirements for certification of controllers with the requirements of PNAE G-7-010 and unified non-destructive testing methods is additionally controlled);

In the case of the use of foreign-made welding consumables, for Russian manufacturers, the presence of a Decision on the application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor, is additionally controlled for Russian manufacturers, for foreign manufacturers, the presence of a conclusion of the head material science organization on compliance with the characteristics applied grades of welding consumables to the grades of welding consumables specified in PNAE G-7-009 and control tables.

Notes:

1. For fittings with classification designation 1, 2, 3CIIIa, in addition to the indicated information, data on the mechanical characteristics and chemical composition of the metal in the amount provided for by RD or TS, as well as information on heat treatment, should be provided, while several tables are allowed. This requirement does not apply to instrumentation fittings.

2. When issuing a passport for a batch of products, it is allowed to indicate, instead of specific mechanical characteristics and chemical composition, the compliance of mechanical characteristics and chemical composition with the requirements of TS (or RD for metal) or indicate the minimum allowable parameters for TS (or RD for metal).

2.8 The specified information about the completeness - meets the requirements of TU / TK.

2.9 of the specified information on conservation and packaging - the conservation periods specified in the section have not expired. The section states that valves must withstand storage in undamaged original packaging for at least 36 months without re-preservation. After the expiration of the storage period and then every 12 months, a survey of the state of the container and storage conditions should be carried out.

2.10 Specified information about deviations from the technical documentation for their compliance with the documents of registration of nonconformities and the decisions made, included in the set of accompanying documentation.

2.11 of the specified information about the supplier's guarantees - the guaranteed period must be at least 36 months from the date of issuance of the confirmation of delivery (or from the day of transportation across the border - in case of import), including at least 24 months from the date of commissioning (subject to the rules of transportation , storage, installation and operation).

2.12 Specified information about the presence/absence of vibration- and seismic-resistant (seismic-resistant) design of reinforcement for their compliance with the requirements of TU/TOR.

2.13 Information about precious materials and non-ferrous metals and their alloys (hereinafter - non-ferrous metals) is indicated in accordance with GOST 2.608 "Procedure for recording information about precious materials in operational documents" for precious materials and GOST 1639 "Scrap and waste of non-ferrous metals and alloys. General specifications. Interstate Council for Standardization, Metrology and Certification" - for non-ferrous metals.

2.14 The total (calculated) mass of non-ferrous metals is indicated, as well as information about the locations of the components of the product that contain non-ferrous metals. The name of non-ferrous metals and the sequence of their recording - according to GOST 1639.

2.15 The presence of a completed Conclusion, including the presence of signatures of the director or chief engineer of the enterprise, the head of the Quality Control Department, the seal of the manufacturer and the date of issuance of the passport.

Note: the passport must contain general drawings and quality control tables TB-1 and TB-2.

2.3 Documents of registration of nonconformities and decisions taken

Controlled:

1. For Nonconformity Reports (nonconformities of class and type B-1, B-2, B-3):

The form of the Report complies with RD EO 1.1.2.01.0930;

All columns of the Non-Conformity Report are completed;

The type of nonconformity is determined correctly, according to the classification of nonconformities (RD EO 1.1.2.01.0930);

The non-compliance report was approved in accordance with the established procedure, in accordance with RD EO 1.1.2.01.0930.

2. For Decisions (non-compliance of class and type A and B-4):

The decision was agreed upon in the prescribed manner, in accordance with RD EO 1.1.2.01.0930;

The decision was approved by Rostekhnadzor or a letter from Rostekhnadzor was attached to it stating that in this case there were no violations of federal norms and rules in the field of the use of atomic energy (for class A non-compliances);

All measures for the Resolution have been completed.

3. Visual and measurement control of products 3.1 External inspection of equipment in accessible places

Controlled:

1. Compliance of the appearance of the product with the requirements of TU / TK and SB.

2. Compliance with the overall dimensions of the requirements of TU / TK and SB.

3. Compliance with the cutting of the edges of the pipes for welding with the requirements of TU / TK and SB.

4. Absence of external damage on the product: dents on the body, dents in the ends of fittings, damage to the base metal in the form of burns, deep scratches, tearing of metal and other damage, the linear dimensions of which (depth/width/length) exceed those established in GOST/TU for metal (GOST, specifications for metal are determined from TB-1 and passport) and PNAE G-7-025 (section 4.4, if there are body parts made by casting).

5. According to the results of mechanical processing of parts, there are no trimming of necks, sharp corners and edges (with the exception of cases specified in the design documentation).

6. For safety valves of classes 1A, 2BIIa, 2BIIc - the absence of stuffing box seals.

7. If there is a stuffing box packing, the height of the stuffing box packing after the final tightening of the stuffing box packing should be such that the stuffing box bushing enters the seat by at least 3 mm and not more than 30% of its height.

8. Knots and parts of fittings made of carbon steel are covered with protective coatings according to technological instructions manufacturer. The grade of the coating complies with the requirements of TU / TK.

9. Fittings with built-in electric or pneumatic drive and any fittings with DN > 50 have a place for its rigid fastening to building structures.

10. In the design of the flanges of fittings designed to work with a radioactive environment, elements (for example, "whiskers") are provided that make it possible to additionally seal the connection by welding at least three times during repairs.

3.2 External inspection of welded joints (if there is welding)

Controlled:

1. The absence of defects in welded joints according to PNAE G-7-010 (Section 11.2), visible during visual inspection: surface cracks of all types and directions; exfoliation; influxes; splashes of metal; burns, fistulas, shrinkage shells; undercuts; lack of penetration; clusters and non-single inclusions.

2. Compliance with the displacement of edges in butt joints, the height (depth) of the recess between the beads, the scalyness of their surface, the concavity of the weld root, single surface inclusions of welded joints with the requirements of PNAE G-7-010 (section 11.2).

3. Compliance with the shape and dimensions of the welds (width and height of reinforcement, leg value, concavity) with the requirements of PNAE G-7-009 and RKD.

4. Availability and compliance of markings (brands) on welded joints (surfaced parts) with the requirements of section 10 PNAE G-7-009. Compliance of the stamp numbers on the product with the numbers specified in TB-2, the scheme of welded joints and the section of the passport "Data on welded joints and surfacings".

5. In case of presence of non-marked welding joints of surfacing, the description of this case in the design documentation and the presence in the accompanying documentation of sketches (diagrams) of the product indicating the location of non-marked welded joints and the brands of welders who performed welding (surfacing) are controlled.

Note: it should be taken into account that (in accordance with paragraph 10.4 of PNAE G-7-009) if all welded joints of the product are made by one welder, then branding (marking) of each welded joint may not be carried out. In this case, the welder's brand is placed near the nameplate or on another open area of ​​\u200b\u200bthe product (or welded assembly) and the place of branding is enclosed in a clearly visible frame applied with indelible paint (the latter does not apply to product surfaces washed with coolant).

6. Mating flanges (nipples) supplied complete with fittings are butt welded.

7. Compliance with the requirements of PNAE G-7-008 (requirements for the design and location of welds).

8. Butt welded joints (if any) are made with full penetration.

9. The roughness of the outer surface of the reinforcement must be no more than Ra = 100 µm (Rz = 500 µm) or comply with the requirements of non-destructive testing.

4 Checking the compliance of the completeness and quantity of equipment and spare parts

Controlled:

1. Compliance of the completeness of the product with the packing list, TU / TK.

2. Compliance of the quantity of shipped products with the specification of the contract for manufacturing/supply and the Quality Plan.

3. Correspondence of the completeness of the spare parts kit with the list of spare parts and accessories kits.

Notes:

1. Electric actuator DN<= 300 поставляется с приводом, смонтированным на арматуре. Для электроприводной арматуры DN >300, it is allowed to supply valves with a removed electric drive (electric motor) in a single shipping container.

2. The delivery set must include electric sensors for remote signaling of the shutoff valve end positions, installed directly on the valves or packaged in accordance with the Technical Specifications/TOR for sensors or valves.

3. The delivery set must include a set of control rings of each standard size with one machined edge for welding control samples (the need to supply control rings, their number and dimensions must be specified in the supply contract).

4. High-speed pneumatic actuator is supplied complete with a pneumatic distributor and limit switches.

5. Fittings with classification designation 1A, 2BIIa, 2BIIIa, 3CIIIa in the presence of a cover-body connector must be equipped with devices that provide controlled tightening of the studs.

5 Checking the conformity of conservation, coloring, packaging and labeling of products. Checking the conformity of containers

Controlled:

1. Compliance of the marking on the valve body (volume of records) with the requirements of TU / TK and NP-068.

2. Compliance with marking data on fittings: name or trademark manufacturer, serial number, year of manufacture, design pressure (in the housing), design temperature (in the housing), nominal diameter DN, arrow indicating the direction of the medium flow (with one-way supply of the medium), type of working medium (liquid - "l", gas - "g", steam - "p"), valve classification designation (according to Table 1), safety class and valve group, product designation, steel grade and heat number (for bodies made of castings), requirements of TU / TK and entries in the passport.

Note: if there is no restriction on the type of medium, its designation is not marked.

3. Correspondence of marking data on the electric drive: name or trademark of the manufacturer, symbol electric drive, torque range, rotational speed, speed limit, rated power (on the motor plate), degree of protection, weight, serial number, year of manufacture, the requirements of TS / TOR for valves and entries in the passport for the electric drive.

4. The branch pipes of the product are plugged in accordance with the requirements of TU / TOR and instructions for packaging.

Notes:

Fasteners, rods and other non-paintable surfaces must be preserved with K-17 grease or other preservative as agreed with the operating organization;

The surfaces of reinforcement parts made of pearlitic steels, processed for welding during installation, are not painted at a width of 20 mm from the edge, but are preserved.

6. Compliance of packaging and preservation of the product with the requirements of TU / TK and GOST 9.014.

8. Compliance of the container with the requirements of the drawing, GOST 15150 and TU / TK.

TYPICAL SCOPE OF INSPECTIONS WHEN CARRYING OUT AN ACCEPTANCE INSPECTION AND INPUT INSPECTION OF ELECTRICAL EQUIPMENT, INSTRUMENTATION EQUIPMENT, AUTOMATIC EQUIPMENT, APCS, IVS 1 - 3 SAFETY CLASSES

Table E.1

Name of the check 1 Checking the completeness of the accompanying documentation

The presence of the following documents included in the delivery set is controlled:

1. Drawing of a general view of the equipment.

2. Assembly drawing of equipment.

3. Assembly drawing specification.

4. Schematic electrical circuit.

5. List of elements (in the absence of an electrical circuit in the circuit).

6. Electrical connection diagram or connection table.

7. Specifications or technical requirements for equipment.

8. Text and description of the program (if the software used is available).

9. Form for software according to GOST 19.501.

10. Packing list.

11. Passport / form / equipment label.

12. Equipment operation manual.

14. Certificate of approval of measuring instruments (for equipment that is a measuring instrument).

15. Documents of registration of nonconformities and decisions made (if any).

16. Quality plan for equipment.

17. Quality plan for components (if available, indicate the name, designation and safety class of the component).

18. Test reports for seismic resistance of equipment.

19. Statement of ED.

20. List of spare parts and accessories.

21. Specifications for repairs.

22. List of documents for repairs.

23. Decision on application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (for equipment manufactured by foreign manufacturers).

24. Decision on the use of IKI, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (if IKI is available, for elements and blocks manufactured by manufacturers of the Russian Federation).

25. Additional documents, in accordance with the TU / TOR and contracts for the manufacture / supply (indicate the name).

2 Checking the correctness of the design and content of the accompanying documentation 2.1 Quality plan

Controlled:

1. The presence of signatures of persons participating in the control, and the dates of its implementation at each control point.

2. Correspondence of the dates of examination of control points indicated by the representatives of the manufacturer (its subcontractor/s) with the dates indicated in the documentation issued by the enterprise based on the results of the operations, and in the passport/form/label of the equipment.

3. The presence on the Identification Sheet of marks on the performance of control, technological operations and quality control in the identification table of signatures with a description of the position and full name. all persons involved in quality control of production.

4. Availability on the List of Development and Approval of the Quality Plan of certifying signatures of all persons and/or approval letters of organizations participating in the approval process.

5. Compliance of the total quantity and nomenclature of the serial numbers indicated on the Accounting Sheet and the corresponding product passports with the order of the Concern (its branch) and the specification of the supply/manufacturing contract.

2.2 Passport for equipment

Controlled:

1. Compliance of the passport form with the requirements of TU / TK (if any).

2. Availability of completed sections of the passport and compliance of their content with the requirements of TS / TOR and available Test Reports (calculations) in terms of:

Names and designations of the product, safety class, climatic version, seismic resistance category, resistance to external mechanical influences, degree of protection by the shell in accordance with GOST 14254, degree of test severity and performance criteria for noise immunity tests, reliability indicators;

Requirements for completeness, conservation and shelf life, manufacturer's warranties.

3. Information about precious materials and non-ferrous metals and their alloys (hereinafter - non-ferrous metals) is indicated in accordance with GOST 2.608 "Procedure for recording information about precious materials in operational documents" for precious materials and GOST 1639 "Scrap and waste of non-ferrous metals and alloys . General specifications. Interstate Council for Standardization, Metrology and Certification" - for non-ferrous metals.

4. The total (calculated) mass of non-ferrous metals is indicated, as well as information about the locations of the components of the product that contain non-ferrous metals. The name of non-ferrous metals and the sequence of their recording - according to GOST 1639.

5. Availability of a completed section "certificate of packaging" with the mark of the packer and the date of packaging.

6. Availability of a completed section "certificate of acceptance" with the signature of the QCD inspector and the seal of the manufacturer.

7. The presence of a completed section containing the name, actual and legal address of the manufacturer and the license number of Rostekhnadzor for manufacturing.

2.3 Documents of registration of nonconformities and decisions taken

Controlled:

1. For Nonconformity Reports (nonconformities of class and type B-1, B-2, B-3):

The form of the Report complies with RD EO 1.1.2.01.0930;

All columns of the Non-Conformity Report are completed;

The type of nonconformity is determined correctly, according to the classification of nonconformities (RD EO 1.1.2.01.0930);

The non-compliance report was approved in accordance with the established procedure, in accordance with RD EO 1.1.2.01.0930.

2. For Decisions (non-compliance of class and type A and B-4):

The decision was agreed upon in the prescribed manner, in accordance with RD EO 1.1.2.01.0930;

The decision was approved by Rostekhnadzor or a letter from Rostekhnadzor was attached to it stating that in this case there were no violations of federal norms and rules in the field of the use of atomic energy (for class A non-compliances);

All measures for the Resolution have been completed.

2.4 Seismic test reports

Controlled:

1. According to the test results, the vibration resistance and vibration strength of the product are confirmed.

2. When carrying out tests, the loads are applied at the base of the fastening of products. The method of fixing the product on the stand plate should be similar to the method of fixing it during operation.

3. The combination of loads corresponds to the floor-by-floor accelerograms and floor-by-floor reaction spectra for the installation sites of the product at the NPP (should be given in TS / TOR) for the corresponding category of seismic resistance of the equipment (clause 6.7 of NP-031).

3 Visual and measurement inspection of products

Controlled:

1. Compliance of the names and designations of the used components (devices, devices and devices) with the requirements of the RKD and the Decision on the use of IKI, drawn up in accordance with RD-03-36 (if imported components are available).

2. No damage to protective and protective-decorative coatings (visually).

3. Availability of the possibility of removal and replacement of components (devices, instruments and devices).

4. The quality of the laying and connection of conductors (cables) - visually.

5. Availability and completeness of equipment parts intended for external connections.

6. No damage to components (devices, instruments and devices) - visually.

7. Availability, correctness and location of plates with functional inscriptions and reference designations.

8. Checking the overall and installation dimensions for compliance with the requirements of the Security Council.

4 Checking the compliance of the completeness of equipment and spare parts

Controlled:

1. Compliance of the completeness of the product with the packing list, TU / TK.

2. Compliance of the quantity of shipped products with the specification of the contract for manufacturing/supply and the Quality Plan.

3. Correspondence of the completeness of the spare parts kit with the list of spare parts and accessories kits.

5 Checking the conformity of conservation, coloring, packaging and labeling of products. Checking the conformity of containers

Controlled:

1. Compliance of the product labeling (volume of records) with the requirements of the RKD.

2. Compliance with factory N products, year of manufacture, brand of the manufacturer, entries in the passport.

3. Compliance of the color of the product with the requirements of the RKD.

4. Compliance of the packaging and preservation of the product with the requirements of the RKD and GOST 9.014.

5. Terms of temporary anticorrosive protection of products do not exceed those specified in GOST 9.014.

6. Compliance of the container with the requirements of the drawing, GOST 15150 and RKD for the product.

TYPICAL SCOPE OF INSPECTIONS DURING ACCEPTANCE INSPECTION AND ENTRANCE INSPECTION OF GLM 1 - 3 SAFETY CLASSES

Table E.1

Name of the check 1 Checking the completeness of the accompanying documentation

The presence of the following documents included in the delivery set is controlled:

1. Drawing of a general view of the GPM.

2. Assembly drawing of the GPM.

3. Specification of the assembly drawing for the GPM.

4. Drawings of wearing parts that are part of the GPM (indicate the designation of the drawings).

5. Wiring drawings.

6. Design and operation manual for the crane track.

7. Table of quality control of the base metal - TB-1.

8. Table of quality control of welding materials, welded joints and surfacing - TB-2.

9. Specifications or TK for GPM.

10. Packing list.

11. Passport for GPM.

12. Operation manual for GPM.

13. Passport and operating manual of components (if available, indicate the name, designation and safety class of the component).

14. Documents of registration of nonconformities and decisions made (if any).

15. Quality plan for GPM.

16. Quality plan for components (if available, indicate the name, designation and safety class of the component).

17. Calculation (extract from the calculation) for the strength and seismic resistance of the GPM.

18. Statement of ED.

19. List of spare parts and accessories.

20. Specifications for repairs.

21. List of documents for repairs.

22. Decision on application, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (for GPM manufactured by foreign manufacturers).

23. Decision on the use of IKI, drawn up in accordance with RD-03-36, approved by the Concern and approved by Rostekhnadzor (if IKI is available, for elements and blocks manufactured by manufacturers of the Russian Federation).

24. Additional documents, in accordance with the TU / TOR and the contract for the manufacture / supply (indicate the name).

2.2 Passport for GPM

Controlled:

1. Correspondence of the passport form with annexes 6 - 9 NP-043.

2. The presence of completed sections of the passport and the correctness of their content in terms of compliance:

2.1 The specified license number for manufacturing and the date of its issue, the name of the interregional territorial department of Rostechnadzor that issued the license.

2.2 Specified specifications GPM (including the characteristics of components) - the data must match the data in the TS / TOR, RKD and quality documents for components - additionally indicate which characteristics are controlled.

2.3 Compliance of the documentation included in the GPM passport with the requirements of appendices 6 - 9 of NP-043.

2.16 Information about precious materials and non-ferrous metals and their alloys (hereinafter - non-ferrous metals) is indicated in accordance with GOST 2.608 "Procedure for recording information about precious materials in operational documents" for precious materials and GOST 1639 "Scrap and waste of non-ferrous metals and alloys. General specifications. Interstate Council for Standardization, Metrology and Certification" - for non-ferrous metals.

2.17 The total (calculated) mass of non-ferrous metals is indicated, as well as information about the locations of the components of the product that contain non-ferrous metals. The name of non-ferrous metals and the sequence of their recording - according to GOST 1639.

2.4 Availability and correctness of filling in the "Certificate of Acceptance" section, including the signatures of the Technical Director / Chief Engineer of the enterprise, the head of the QCD, the seal of the manufacturer and the date of issuance of the passport.

2.3 Documents of registration of nonconformities and decisions taken

Controlled:

1. For Nonconformity Reports (nonconformities of class and type B-1, B-2, B-3):

The form of the Report complies with RD EO 1.1.2.01.0930;

All columns of the Non-Conformity Report are completed;

The type of nonconformity is determined correctly, according to the classification of nonconformities (RD EO 1.1.2.01.0930);

The non-compliance report was approved in accordance with the established procedure, in accordance with RD EO 1.1.2.01.0930.

2. For Decisions (class A and B-4 nonconformities):

The decision was agreed upon in the prescribed manner, in accordance with RD EO 1.1.2.01.0930;

The decision was approved by Rostekhnadzor or a letter from Rostekhnadzor was attached to it stating that in this case there were no violations of federal norms and rules in the field of the use of atomic energy (for class A non-compliances);

All measures for the Resolution have been completed.

2.4 Seismic design

Controlled:

1. The calculation method is approved by Rostekhnadzor.

2. Calculation substantiations of the seismic resistance of the GPM and its elements were carried out for the case of transportation of the maximum load indicated in its passport for normal operation.

Note: it is allowed to reduce the calculated value of the cargo in cases provided for by the calculation methods approved by Rostekhnadzor.

3 Visual and measurement inspection of products 3.1 Visual inspection of equipment in accessible places

Controlled:

1. Compliance of the appearance of the product with the requirements of TU / TK and SB.

2. Compliance of the overall dimensions of the elements of the GPM (for components, the compliance of their name, designation and technical characteristics is also checked) with the requirements of the design documentation for the GPM and passports (for components).

3. Absence of external damage on the product: dents, damage to the base metal in the form of burns, deep scratches, tearing of metal and other damage, the linear dimensions of which (depth / width / length) exceed those established in GOST / TU for metal (GOST, TU for metal determined from TB-1).

3.2 External inspection of welded joints (if there is welding)

Controlled (in accordance with RD 24.090.97):

1. Compliance of the shape and dimensions of welded joints with the requirements of the RKD.

2. Absence of defects in welded joints visible during visual inspection: surface cracks of all types and directions; local sags with a total length of more than 10 mm at a seam section of 1000 mm; undercuts with a depth of more than 0.5 mm with a thickness of the thinnest of the welded elements up to 20 mm inclusive; undercuts with a depth of more than 3% of the thickness of the thinnest of the welded elements, with its thickness over 20 mm; pores in the amount of more than 4 pieces at a seam length of 100 mm (in this case, the maximum pore size should not be more than 1 mm with a thickness of the welded elements up to 8 mm inclusive and more than 1.5 mm with a thickness of the welded elements over 8 mm up to 50 mm inclusive); accumulation of pores in an amount of more than 5 pieces per 1 sq. cm of the seam area (in this case, the maximum size of any of the pores should not be more than 1 mm); unsealed craters; burns and fistulas.

3. The difference in the height of the ridge and cavity of the surface of the butt welded joint in any of its sections along its length is not more than the allowance for the convexity of the weld.

4. The difference in the height of the scallop and the depression of the surface, measured along the thickness of the weld, of the fillet weld at any point in its length is not more than 0.7 of the tolerance for the leg of the fillet weld.

5. Availability and compliance of markings (brands) on welded joints (surfaced parts) with the requirements of the RKD. Correspondence of the hallmark numbers on the product with the numbers indicated in TB-2.

4 Checking the compliance of the completeness and quantity of equipment and spare parts

Controlled:

1. Compliance of the completeness of the product with the packing list, TU / TK.

2. Compliance of the quantity of shipped products with the specification of the contract for manufacturing/supply and the Quality Plan.

3. Correspondence of the completeness of the spare parts kit with the list of spare parts and accessories kits.

5 Checking the conformity of conservation, coloring, packaging and labeling of products. Checking the conformity of containers

Controlled:

1. Compliance of the product marking (volume of records) with the requirements of TU / TK.

2. Compliance with the marking of the head. N products, year of manufacture, brand of the manufacturer of the category of seismic resistance and safety class of the product, entries in the passport.

3. Presence of a marking on the GPM hook that meets the requirements of section 2.6 of PB 10-382.

Note: in cases where the plate hook is suspended from the traverse using a fork, the markings on the fork must be the same as on the hook.

4. Availability of markings on the wedge bushing and the GPM wedge corresponding to the requirements of the rope diameter.

5. Compliance of the color of the product with the requirements of the RKD.

6. Compliance of the packaging and preservation of the product with the requirements of the RKD and GOST 9.014.

7. Terms of temporary anticorrosive protection of products do not exceed those specified in GOST 9.014.

8. Compliance of containers with the requirements of the drawing, GOST 15150 and TU / TK for GPM.

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