ML20142A131

Safety Evaluation Supporting post-maint Testing Programs Required by Generic Ltr 83-28

ML20142A131
Person / Time
Site:	Yankee Rowe
Issue date:	03/13/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20142A127	List: ML20142A126 ML20142A131
References
GL-83-28, NUDOCS 8603190342
Download: ML20142A131 (3)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT10N RELATED TO THE OPERATION OF YANKEE NUCLEAR POWER STATION YANKEE ATOMIC ELECTRIC COMPANY POST MAINTENANCE TESTING DOCKET N0. 50-29 INTRODUCTION AND

SUMMARY

Generic Letter 83-281describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit 1 of Salem Nuclear Power Plant.

This report is an evaluation of the responses submitted by the Yankee Atomic Electric Company, the licensee for the Yankee Nuclear Power Station for Items 3.1.3 and 3.2.3 of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of this report.

The requirements for these two items are identical with the exception that Item 3.1.3 applies these requirements to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated together.

RE0UIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated 9603190342 860313 .

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to degrade rather than enhance safety. Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval.

EVALUATION The licensee for the Yankee Nuclear Power Station responded to these requirements with submittals dated November 5, 1983 2 and July 5, 19853 . The licensee stated in these submittals that there were no post-maintenance testing requirements in Technical Specifications for either the reactor trip system or other safety-related components which degraded safety.

CONCLUSION Based on the licensee's statement that no post-maintenance test requirements were found in Technical Specifications that degraded safety, we find the licensee's responses acceptable for Items 3.1.3 and 3.2.3 of Generic Letter 83-28.

REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,

" Required Actions Based on Generic lirplications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.

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2. Yankee Atomic Electric Company Letter, L. H. Heider to D. G. Eisenhut, Director, Office of Nuclear Reactor Regulation, NRC, " Response to Generic Letter 83-28", November 5, 1983, FYR 83-94.

3. Yankee Atomic Electric Company Letter, G. Papanic, Jr. to J. A.

Zwolinski, NRC, " Generic Letter 83-28, Request for Additional Information", July 9, 1985, FYR 85-75.

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