ML20210S928

Forwards Reactor Sys Branch SER Input Re Applicant Compliance w/10CFR50.55a, Seismic Classification & Sys Quality Group Classifications, of Fluid Containing Components of Reactor Coolant Pressure Boundary

ML20210S928
Person / Time
Site:	Satsop
Issue date:	06/20/1975
From:	Stello V Office of Nuclear Reactor Regulation
To:	Deyoung R Office of Nuclear Reactor Regulation
References
CON-WNP-1705 NUDOCS 8605290516
Download: ML20210S928 (5)

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Technical Review Branch Involved: 'Reacter Systems Breneh Requestad Ceepletion Date: June 16, 1973 l

l Description of Review: SER Review Status: Complete t

The FSAR submitted by the subject applicant hem been evaleeted by the '

Reactor Systems Branch. The SER teview is limited to oesuplianos by the applicant with the Codes and Standards Rule, section'50.55e of 10 CFR Part 50, Seismic Classification and System Quality Gesep' Classifications of those fluid containing campements whick are part of the reactor coolant pressure boundary and other fluid systeme important to safety. A final SER evaluation of the material within the scope of.regiaw of this branch

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Orfginal of.ad by D. F.Ross Victor Stelle, Jr..

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Divisie( of Technical Review Office of Noeleer Reactor Regulattes

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WASHINGTON K0 CLEAR PROJECT, UNITS 3 AND 5 DOCKET NOS. 50-508/509 211.0 Quality Group Classification, Reactor Systems Branch 211.1 Sefemic_Clansification (3.2.L)

Structurec, systems and components important to safety that are required to be designed to withstand the ef fects of.a Safe Shutdown Earthquake and remain functional have been propetly classified a? Seismic Category I items. These plant features are those necessary to assure (1) tha integrity of l

the reactot coulent pressure boundary. (2) the capability to shutdown the reactor and main'cain it in a safe shutdown condition, or (3) the tapability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10 Crk Part 100.

All other structures, systems and cpmponents that may be required for operation of the facility are designed to other than Seismic CateEory I requ? resents including those portions of Category I systems which are not required to perform a safety function. Structures, systema and components imimrtant i

to safaty that are designed to withstand the effects of a safe Shutdown Earthquale and remain functional have been identified in an acceptable manner in Table 3.2-1.

The basis for cur acceptance has been conformance of the applicant's designs, design criteria and design bases for structures, systems and componsnps important to cafety with the Commission's regulations as set forth in General Des 3gn Criterion 2, and to Regulatory Guide 1.29. MRC staff positions, and industry standards.

s Wa conclude that structures, systeas and components important to safety that are designed to withstand the effects of a i

Safe Shutdown Earthquake and remain functional have been properly classified as seismic C4tegory I ittas in conformance with the Commission's regulatioris, the applicable regulatocy

guide, NRC staff positions, and industry standt.rds and are acceptablu. Design of there items in accordance with i

seismic Catego,ry I requiroments provides resscnable assurance I

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that the plant will perform in a manner providing adequate safeguards to the health and safety of the public.

211.2 System Quality Group Classification (3.2.2)

Fluid system pressure-retaining components important to safety will be designed, fabricated, erected and tested to quality standards commensurate with the importance of the safety function to be performed. The applicant has applied the ANS classification system (Safety Classes 1, 2, 3 and NNS) in accordance with ANSI N18.2 and which corresponds to the Commission's Quality Groups A B, C and D in Regulatory Guide 1.26 to those fluid containing components which are part of the reactor coolant pressure boundary and other fluid systems important to safety where reliance is placed on these systems:

(1) to prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary, (2) to permit shutdown of the reactor and maintenance in the safe shutdown conditions, a.nd (3) to contain radio-active material. These fluid systems have been classified in an acceptable manner in Tables 3.2-1, 3.2-2 and 3.2-3 of the PSAR and on system Piping and Instrumentation Diagrams in the PSAR.

The basis for acceptance in the staff's review has been conformance of the applicant's designs, design criteria, and denign bases for pressure-retaining components such as pressure vessels, heat exchangers, storage tanks, pumps, piping and valves in fluid systems important to safety with the commission's Regulations as set forth in General Design Criterion 1, the requirements of the Codes specified in Section 50.55a of 10 CFR Part 50, and to Regulatory Guide 1.26, NRC staff positions and industry standards.

We conclude that fluid systems pressure-retaining components Laportant to safety that are designed, fabricated, erected and tested to quality standards in conformance with the Commission's regulations, the applicable Regulatory Guide NRC staff

' positions and industry standards are acceptable. Conformance with these requirements provides reasonable assurance that the plant j

will perform in a manner providing adequate safeguards to the health and safety of the public.

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i 211.3 Compliance with_10 CFR Part 50. Section 50.55a (5.2.1.3) Componento of the' reactor coolant pressure boundary as defined by the rules of 10 CFR Part 50, Section 50.53a have been properly identified and classified as ASME Section III, Code i

Class I components in Table 5.2-1 of the PSAR. These components

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within the reactor coolant pressure boundary will be constructed in accordance with the requirements of the applicable codes and addenda as specified by the rules of 10 CFR Part 50, Section 50.55a, Codes and Standards.

We conclude that construction of the components of the reactor coolant pressure boundary in conformance with the Commission's regulations provides reasonable assurance that the resulting

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quality standards are commensurate with the importance of the safety function of the reactor coolant pressure boundary and is acceptable.

211.4 Applicable Code Cases (5.2.1.4)

The ASME Code Cases specified in Table 5.2-6 whose requiremento will be applied in the construction of pressure-retaining

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ASME Section III, Code Class 1, components within the Reactpr Coolant Pressure Boundary (Quality Group Classification A), are in accordance with those code cases in Regulatory Guides 1.84 and 1.85 that are generally acceptable to the Commission. We conclude that compliance with the requirements of these Code Cases, in conformance with the Commission's regulations, is expected to result in a component quality level that is commensurate with the importance of the safety function of the reactor coolant pressure boundary and is acceptable.

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4 Bibliography General References 1.

10 CFR Part it Appendix A, General Design Criterion 1. " Quality Standards and Records."

2.

10 CFR Part 50, Appendix A, General Design Criterion 2, " Design Bases for Protection Against Natural Phenomena."

3.

10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants."

4.

10 CFR Part 100. Appendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants."

5.

Regulatory Guide 1.26 " Quality Group Classifications and Standards."

6.

Regulatory Guide 1.29, " Seismic Design Classification."

7.

Regulatory Guide 1.84, " Code Case Acceptability ASME Section III Design and Fabrication."

8.

Regulatory Guide 1.85, " Code Case Acceptability ASME Section III Materials."

9.

ANSI N18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1973).

10. ASME Boiler and Pressure Vessel Code, 1971 and 1974 Editions,Section III,

" Nuclear Power Plant Components," American Society of Mechanical Engineers.

11. ASME Boiler and Pressure Vessel Code, 1971 and 1974 Editions,Section VIII, Division 1, " Pressure Vessels," American Society of Mechanical Engineers.

12. ANSI B31.1-1973, " Power Piping," American National Standards Institute.

13. API Standard 620, Fourth ' Edition. February 1970, " Recommended Rules for Design 'and Construction of Large, Welded, Low-Pressure Storage Tanks,"

American Petroleum Institute.

14. API Standard 650. Third Edition, July 1966, " Welded Steel Tanks for 011 Storage," American Petroleum Institute.

15. AURA D100-67, "AWWA Standard for Steel Tanks-Standpipes, Reservoirs, and Flavated Tanks for Water Storage," American Water Works Association.

16. ANSI B96.1-1967, " Specification for Welded Aluminum-Alloy Field-Erected Storage Tanka," American National Standards Institute.

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