ML19220B329
| ML19220B329 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/23/1975 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904250641 | |
| Download: ML19220B329 (6) | |
Text
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...a Voss A. Moore, Jr., Assistant Director for LUR's, Grouc 2, RL SAFETY EVALUATI0t! REP 03.T - THREE MILE ISLAND MUCLEAR STATICM, U' LIT 2 Plant.'iame: Three title Island Nuclear Station, Unit 2 Occket No.: 50-320 tiilestone No.: 24-21 Licensir.g Stage: Operating License Responsible Branch and Project Leader: LWR 2-2, H. Silver Tecnnical Review Branch Involved: Reactor Systems Granch Requested Completion Date: Sectember 5, 1975 Descriotion of Review: SER Review Status: Complete The FSAR subnitted by the subject acclicant has been eva'.uated by the Reactor Systems Branch. The SER review is liaited to corsliance by the apolicant with the Codes and Standards Rule, Section 50.55a of 10 CFR Part 50, Seisnic Classification and System Quality Group Classifications of those fluid containing cocoonents which are part of the reactor coolant oressure boundary and other fluid systems important to safety. A final SER evaluation of the
- naterial within the scope of review of this branch is enclosed.
brwaf signcaEsl Vic.or Stena /
Victor Stello, Jr., Assistant Director for Reactor Safety Divisicn of Technical Review Office of Nuclear Reactor Regulation
Enclosure:
SER cc:
S. Hanauer R. Heinecan R. Coyd W. Mcdonald V. Stello K. Kniel H. Silver T. Novak R. Kirkwood Docket Fil d NRR Reading RSB Reading TR:RS
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~HREE MILE ISLAND NUCLFAR STATION UM T 2 Docket No. S0-32_0_
211.0 REACTOR SYSTEMS BRANCH, Quality Group Classification (3.2.1)
Seismic Classification Structures, system.; and comocnents imoortant to safety that are required to be designed to withstand the effects of a Safe Shut-down Earthquake and remain functional have, in general, been croperly classified as seismic Category I items. These plant features are those necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shutdown the reactor and maintain it in a safe shutdcwn condition, or (3) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposares comparable to the guideline exposures of 10 CFR Part 100.
All ci.ner structures, systems and com;onents that may be re-qu1 red for operaticn of the facility have been designed to other than seismic Category I requirements including those portions of Category I systems which are not required to perform a safety function.
Structures, systems and components important to safety that have been designed to withstand the effects of a Safe Shutdown Earthquake and remain functional are identified in an acceptable manner in the FSAR.
The basis for our acceotance has been conformance of the applicant's designs, desigri criteria and design bases for structures, systems and ccmponents important to safety with the Comission's regulations as set forth in General Cesign Criterion 2 and industry standards.
We conclude that structures, systems and cocoonents important to safety that are designed to withstand the effects of a Safe Shutdown Earthquake and remain functional have, in general, been properly classified as seismic Category I items in confor-ance with the Comission's regulations and industry standards and are acceptable. Design of these items in accordance with seismic Category I requirements orovides reasonable assurance that the plant will perform in a manner providing adequate safeguards to the health and safety of the public.
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211-2 211.2 System Ouality Grouc Classification (3.2.2)
Fluid system pressure-retalning camconents important to safety have, in generai, been designed, fabricated, erected and tested to quality standards commensurate with the imcortance of the safety function to be performed. The applicant has identified those fluid-containinc ccmconents which are part of the reactor coolant pressure boundar7 and other fluid systems important to safety where relianci s placed on these systems:
(1) to prevent or mitigate the consequences of accidents and mal-functions originating within the reactor coolant pressure boundary, (2) to permit shutdown of the reactor and maintenance in the safe shutdown conditien, and (3) to contain radicactive material. These fluid systems have, in general, been classi-fied in an acceptable manner in Table 3.2-1 of the FSAR and on system Piping and Instrumentation Diagrams in the FSAR.
The basis for acceptance in the staff's review has been conformance of the applicant's designs, design criteria, and design bases for pressure-retaining ccmconents such as pressure vessels, heat exchangers, storage tanks, pumps, piping and valves in fluid systems important to safety with the Ccmmission'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 industry standards.
We concluced that fluid systems pressure-retaining comoonents important to safety that have been designed, fabricated, erected and tested to quality standards in conformance with the Commission's regulations and industry standards are acceptable.
Conformance with these requircments provide reasonable assurance that the plant will perform in a manner providing adequate safeguards to the health and safety of the public.
P.
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211-3 211.3 Comoliance with 10 CFR Part 50. Sectior ca.55a (5.2.1.3) Components of tne reactor ccoiant ores:ure ocundary as defined by the rules of 10 CFR Part 50, Section 50.55a have been properly identified and classified as ASME Section III, Cole Class A and AtiSI B31.7, Class 1 components in Table 5.2-1 of the FSAR. These comoonents within the reactor coolant press' re boundary have been constructed in accordance with the require-ments 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 quality standards are centensurate with the imoortance of the safety function of the reactor coolant pressure boundary and is acceptable.
211.4 Acolicable Code Cases (5.2.1.4) The ASME Code Cases specified in Table 5.2-2 whose requirements have been applied in the construction of prassure-retaining ASME Secticn III, Code Class A, components within the Reactor 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 acceotable to the Commission. We conclude that ccmoliance with the requirements of these code cases, in conformance with the Commission's regulations, is expected to result in a component quality level chat is commensurate with the importance of the safety function of the reactor coolant pressure boundary and is acceptable.
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O BIBLIOGRAPHY p neral Refereices 10 CFR Parc 50, Accendix A, General Design Criterion 1, "Quali'.y Standards ad Records."
2.
16 CFR Part 5), Appendix A, General Design Criterion 2, " Design Bases for o rotection 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, Accendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants."
5.
Regulatory Guide 1.25, " Quality Group Classificaticrs and Standards."
6.
Regulatory Guide 1.29, " Seismic Design Classification."
7.
Regulatory Guid' l.84, " Code Case Acceptabi ~ 4ty ASME Sectien III Design and Fabr cation."
8.
Regulatory Guide 1.85, " Code Case Acceptability ASME Section III Materials."
9.
ANSI N18.2, "Nunlear Safety Critaria for the Design o Stationary Pressurized Water Reactor Plants," American National itandards Institute (1973).
- 10. ASME Boiler ar.d Pressure '/essel Code,1965 Edition,Section III,
Nuclear '/essels," American Society of Mechanical Engineers.
- 11. ASME Boiler and Pressure 'lessel Code,1968 and 1971 Editions,Section III,
" Nuclear Power Plcnt Nmponents," American Society of Mechanical Engineers.
- 12. ANSI B31.7-1968 and 1969 Editions, " Nuclear Power Piping," American National Standards Instutute.
13.
Draft ASME Code for Pumps and '/alves for Nuclear Power, (Dated November 1968), American Society of echanical Engineers.
14.
ASME Boiler and Pressure '/essel Code,1968 and 1971 Editions, Section
'/III, Division 1, " Pressure '/essels," American Society of Muhanical Engineers.
- 15. ANSI 331.1.0-1967, "Pcwer Piping," Amrican National Standards Institute.
- 16. API Standard 620, Fourth Edition, February 1970, " Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storate Tanks,'
American Petroleum Institute.
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- 17. API Standard 650, Third Edition, July 1966, " Welded Steel Tanks for Oil Storage," American Petroleum Institute.
- 18. AWWA D100-67, "AWWA Standard for Steel Tanks-Standpipes, Peservoirs, and Elevated Tanks for '.later Storage,"American Water Works Association.
- 19. ANSI 896.1-1967, "Soecification for Welded Aluminum-Alloy Field-Erected Storage Tanks," American National Standards Institute.
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