THE ORDER OF THE FEDERAL SERVICE OF THE RUSSIAN FEDERATION ON ECOLOGICAL, TECHNOLOGY AND ATOMIC SUPERVISION

of December 17, 2015 No. 521

About approval of Federal regulations and rules of use of atomic energy of "Rules for the Construction and Safe Operation of the equipment and pipelines of atomic power stations"

According to article 6 of the Federal Law of November 21, 1995 No. 170-FZ "About use of atomic energy" (The Russian Federation Code, 1995, No. 48, Art. 4552; 1997, No. 7, Art. 808; 2001, No. 29, Art. 2949; 2002, No. 1, Art. 2; No. 13, Art. 1180; 2003, No. 46, Art. 4436; 2004, No. 35, Art. 3607; 2006, No. 52, Art. 5498; 2007, No. 7, Art. 834; No. 49, Art. 6079; 2008, No. 29, Art. 3418; No. 30, Art. 3616; 2009, No. 1, Art. 17; No. 52, Art. 6450; 2011, No. 29, Art. 4281 No. 30, Art. 4590; Art. 4596; No. 45, Art. 6333; No. 48, Art. 6732; No. 49, Art. 7025; 2012 No. 26, Art. 3446; 2013, No. 27, the Art. 3451), subitem 5.2.2.1 of Item 5 of the Regulations on Federal Service for Environmental, Technological and Nuclear Supervision approved by the order of the Government of the Russian Federation of July 30, 2004 No. 401 (The Russian Federation Code, 2004, No. 32, Art. 3348; 2006, No. 5, Art. 544; No. 23, Art. 2527; No. 52, Art. 5587; 2008, No. 22, Art. 2581; No. 46, Art. 5337; 2009, No. 6, Art. 738; No. 33, Art. 4081; No. 49, Art. 5976; 2010, No. 9, Art. 960; No. 26, Art. 3350; No. 38, Art. 4835; 2011, No. 6, Art. 888; No. 14, Art. 1935; No. 41, Art. 5750; No. 50, Art. 7385; 2012, No. 29, Art. 4123; No. 42, Art. 5726; 2013, No. 12, Art. 1343; No. 45, Art. 5822; 2014, No. 2, Art. 108; No. 35, Art. 4773; 2015, No. 2, Art. 491; to No. 4, of the Art. 661), I order:

Approve the enclosed federal regulations and rules of use of atomic energy of "Rules for the Construction and Safe Operation of the equipment and pipelines of atomic power stations" (NP-089-15).

 

Approved by the Order of the Federal Service of the Russian Federation on ecological, technology and atomic supervision of December 17, 2015 No. 521

Federal regulations and rules of use of atomic energy of "Rules for the Construction and Safe Operation of the equipment and pipelines of atomic power stations" (NP-089-15)

I. Appointment and scope

1. These federal regulations and rules of use of atomic energy of "Rules for the Construction and Safe Operation of the equipment and pipelines of atomic power stations" (are developed by NP-089-15) (further - Rules) according to the Federal Law of November 21, 1995 No. 170-FZ "About use of atomic energy", the Regulations on development and approval of federal regulations and rules of use of atomic energy approved by the order of the Government of the Russian Federation of December 1, 1997 No. 1511 (The Russian Federation Code, 1997, No. 49, Art. 5600; 2012, No. 51, Art. 7203).

2. These rules establish requirements to the device, production, installation and operation working under the excessive, hydrostatic or vakuummetrichesky pressure of the equipment and pipelines of the atomic power stations (further - AEU) carried to the A, B and C groups according to items 4 - 6 these rules.

The used terms and determinations are given in appendix No. 1 to these rules.

3. Requirements of these rules do not extend on:

a) the fuel elements and assemblies, working bodies of management system and protection (further - SUZ) and other designs in the body of reactors, technology and other channels which are containing sharing, absorbing or slowing down materials;

b) the pipes and devices which are built in in the equipment or the pipeline which destruction does not lead to exit of working environment out of limits of this equipment or to leakage through the elements dividing different environments or environment with different parameters;

c) the mechanical and electric devices located in the equipment (for example mechanisms of reloading devices, executive mechanisms of SUZ, driving wheels of pumps);

d) the devices placed in the equipment or in pipelines for check of their working capacity;

e) internal metal facing of hermetic barrier, pools of overload and endurance, pools storages of spent nuclear fuel, concrete body of research reactors;

e) pipelines and the body of the equipment manufactured of nonmetallic materials;

g) the body of turbines, gate-type fittings of intermediate overheat of vapor, perepuskny pipelines within the turbine, pipelines of selection of vapor from the turbine to the first shutoff valves, and also elements and nodes of hydraulic system of regulation of the turbine plant;

h) support, suspension brackets, dampers, hydroshock-absorbers and limiters of movements of the equipment and pipelines;

i) the metalwork and casings pressurizing internal space of reactors of channel type, including the graphite laying concluded in casing and elements relating to it;

j) metalwork of reloading and obmyvochny boxes with the equipment which is in them (except the traffic jams pressurizing reloading channels of the reactor) for reactors with the zhidkometallichesky sodium heat carrier;

k) sealing elements;

l) the metalwork located in the equipment and not loaded in the project modes with heat carrier pressure;

m) the parts of the equipment which are not representing independent vessels (for example the condensers and heat exchangers which are built structurally in the equipment);

o) hydrolocks, pipelines of modulation of tanks, the vessels working under hydrostatic pressure;

o) the pipelines of measuring systems and diagnostics, sampling relating 3 classes of safety to elements with nominal internal diameter less than 15 mm;

p) the equipment and pipelines which are used only during the commissioning, maintenance and repair;

c) the body of the AEU reactor block with the reactor on bystry neutrons with the zhidkometallichesky lead heat carrier, intra case devices (including elements of active zone), the equipment and pipelines of contour of circulation of the lead heat carrier which are in contact with the lead heat carrier and (or) protective gas to the first gate-type armature and also the equipment and pipelines of the second steam-and-water contour from the steam generator to armature, the second from the steam generator (gate-type or the return).

Separate requirements and provisions of these rules can be applied by developer to the above-stated equipment and pipelines.

4. The group A turns on the equipment and pipelines carried to elements of 1 class of safety.

5. The group B turns on the equipment and pipelines carried to elements 2 classes of safety. Besides, the group B turns on the equipment and pipelines carried to elements 3 classes of safety:

a) failure or destruction of which brings to unremovable regular means of AEU to leakage of the heat carrier which is directly contacting to the fuel elements;

b) failure or destruction of which leads to failure to carry out by any security system of the functions;

c) being in contact with the zhidkometallichesky sodium heat carrier irrespective of effects of their failures or destructions.

6. The group C turns on the equipments and pipelines carried to elements 3 classes of safety, failure or destruction of which which did not enter into group B:

a) brings to removable regular means to leakage of the heat carrier which is directly contacting to the fuel elements;

b) requires enforcement of security systems;

c) leads to failure of one of channels of any security system;

d) leads to exceeding of the established values of maximum permissible emissions or admissible dumpings of radioactive materials, or admissible levels of radioactive pollution of working premises of AEU.

7. For the specific equipment and pipelines belonging to group is established by developers of projects of reactor installation (further - RU) and AEU.

8. Action of these rules, except for carrying out hydraulic, pneumatichydraulic and pneumatic testing (further - testing by pressure), extends to welded connections of the equipment and pipelines of the A, B and C groups with the details and (or) assembly units which are not working under pressure.

9. As borders between the equipment and the pipeline belonging to different groups (or between the pipelines belonging to different groups) serve welded or demountable connections. Boundary welded connections and fasteners shall be referred to the equipment (or to the pipeline) to which more high requirements for safety are imposed.

10. Design, project and technology documentation on the equipment, and also on the details and assembly units of pipelines made before entry into force of these rules or which are in production at the time of their entry into force, is not subject to conversion.

11. The officials and specialists occupied with designing, designing, production, installation and operation of the equipment and pipelines shall undergo recurring inspection of knowledge of the corresponding Chapters of these rules according to the procedure and in the terms established by the organization performing the specified works, but at least once in five years.

12. The persons who had the corresponding training and allowed to independent work according to the procedure, established by the operating organization shall carry out maintenance and repair of the specific equipment and pipelines.

II. Designing and designing

General provisions

13. Durability and functional characteristics of the equipment and pipelines shall be proved in the AEU (RU) project for all service life of the equipment and pipelines.

14. Service life and resource characteristics of the equipment and pipelines are established by developer and shall be specified in project or design documentation.

15. The developer of the RU (AEU) project and developer of the equipment and pipelines shall provide possibility of their survey, maintenance, repair, diagnosing, carrying out testing by pressure and nondestructive control of metal after production, installation and in case of operation, and also replacements of the equipment and pipelines with service life of less project service life of AEU.

In case of possibility of carrying out ultrasonic control of metal preference shall be given not to the manual, and automated control.

16. For the equipment (except armature) and pipelines of the first contour of the pressurized water reactor content of cobalt in the main and naplavochny materials of the details and assembly units contacting to the heat carrier shall not exceed % 0,05.

17. For the equipment and pipelines contacting to radioactive circles the possibility of drainage of the heat carrier and removal of products of pollution, deactivations of surfaces and removal of the flushing and deactivating solutions shall be provided.

The equipment and pipelines contacting to the zhidkometallichesky sodium heat carrier or products of its allocations from which under the terms of engineering procedure complete removal of products of pollution is impossible shall be specified in the RU project.

18. In RU with pressurized water reactors and reactors with the zhidkometallichesky sodium heat carrier containers with reactor body metal samples witnesses for assessment of impact of temperature and neutron radiation shall be placed.

19. The quantity of sets of samples witnesses and containers with samples witnesses in sets, locations of containers and frequency of control of characteristics of metal of samples witnesses shall be proved in the RU project. Obraztsov witnesses there shall be enough for periodic confirmation of each controlled characteristic of metal during service life of AEU.

Design documentation shall include the Program of control of radiation embrittlement and thermal aging which contents shall meet federal standards and rules of use of atomic energy of "The rule of control of the main metal, welded connections and the built-up surfaces in case of operation of the equipment, pipelines and other EXPERTS elements" (NP-084-15) approved by the order of Federal Service for Environmental, Technological and Nuclear Supervision of December 7, 2015 No. 502 (it is registered by the Ministry of Justice of the Russian Federation on March 10, 2016, registration No. 41366) (further - NP-084-15).

20. Need of placement of samples witnesses for research reactors is determined by developers of the AEU projects.

21. Developer of the AEU project the possibility of carrying out separate testing shall be provided by pressure of the pipelines attached to the soaking-up and pressure head parts of pumps if the last are designed on different pressure.

22. In project and design documentation measures for protection of the equipment and pipelines from physical and chemical and physical impact of working environment shall be specified.

23. The equipment and pipelines with temperature of outside surface of walls is above 45 °C, located in the serviced rooms, and it is above 60 °C, located in rooms of limited access, shall be heat-insulated. Temperature of outside surface of heat insulation shall not exceed the above-stated values. On the main circulating pipelines on all their extent and on other pipelines in the places which are subject to nondestructive operational control, heat insulation shall be removable.

24. The space arrangement of pipelines, and also methods and conditions of fixing of the equipment and pipelines shall exclude their damage owing to mutual movements.

25. The possibility of removal of air when filling with working or test environment shall be provided in the equipment and pipelines, and also the condensate which is formed in the course of warming up or cooling. Handling capacity of devices for removal of air shall be confirmed with calculation.

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