ML20212B478

SER Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing

ML20212B478
Person / Time
Site:	Sequoyah
Issue date:	08/01/1986
From:	NRC
To:
Shared Package
ML20212B475	List: ML20212B472 ML20212B478
References
GL-83-28, NUDOCS 8608060335
Download: ML20212B478 (4)

Text

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ENCLOSURE SAFETY EVALUATION REPORT GENERIC LE T TER 83-28. ITEMS 3.1.3 AND 3.2.3 FDST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)

SEQUOYAH NUCLEAR PLANT, UNITS 1,2 DOCKET NO.: 50-327/328 -

INTRODUCTION AND

SUMMARY

1 Generic Letter 83-28 describes 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 Tennessee Valley

_ Authority, the licensee for the Sequoyah Nuclear Plant, Units 1,2 for Items i 3.1.3 and 3.2.3 of the Generic Letter. 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.

REQUIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance I

test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test re-quirements, with supporting iustification, shall be submitted for staff i approval.

t 8608060335 860801 PDR ADOCK 05000327 P PDR

• EVALUATION .

The licensee for the Sequoyah Nuclear Plant, Units 1,2 responded to these re-quirements with submittals dated November 7, 19832 and March 20, 19863 ,

The licensee stated in these submittals that no post-maintenance testing re-quirements in Technical Specifications for either the reactor trip system or other safety-related components had been identified which degraded safety.

CONCLUSION Based on the licensee's statements that no post-maintenance test requirements

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were found in Technical Specifications tlat 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 Lic'enses, and Holders of Construction Permits,

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

2. Letter, L. M. Mills, Tennessee Valley Au.thority to E. Adensam, NRC,

" Response to Generic Letter 83-28 " Required Actions Based on Generic Implications of Salem ATWS Events," for Sequoyah Nuclear Plant, dated November 7, 1983.

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, REFERENCES (CONT.) ,

3. Letter, R. Gridley, Tennessee Valley Authority to B. J. Youngblood, NRC, Response to NRC Letter of December 19, 1985 requesting additional information on Generic Letter 83-28 Item 3.2.3, dated March 20, 1986.

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