ML20234E049
| ML20234E049 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/26/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20234E002 | List: |
| References | |
| GL-83-28, NUDOCS 8709220269 | |
| Download: ML20234E049 (2) | |
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ENCLOSURE SAFETY EVALUATION REPORT GENERIC LETTER 83-?8, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)
RIVER REND STATION, UNIT 1 DOCKET NO.: 50-458 INTRODUCTION AND
SUMMARY
1 Generic Letter 83-?8 describes intermediate term actions to be taken bv 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 Gulf States Util-ities, the licensee for the River Rend Station, Unit i for Items 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 1
3.1.3 apolies these requirenants to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components.
Because of tnis similarity, the responses to both itens were evaluated together.
REQUIREMENT Licensees and apolicants shall identify, if applicable, any post-maintenance 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 justification, shall be submitted for staff approval.
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EVALUATION The licensee for the River Bend Station, Unit I responded to these requirements 3
with submittals dated August 3, 1984 and March 20, 1985.
The licensee stated in these subnittals that there were no post-maintenance testina requirements in Technical Specifications for either the reactor trip system or other safety-related componants 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 Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
2.
Letter, J. E. Booker, Gulf States Utilities Co, to D. G. Eisenhut, NRC, August 3, 1984.
i 3.
Letter, J. E. Booker, Gulf States Utilities Co, to H. R. Denton, l
NRC, March 20, 1985.
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