ML20137L202
| ML20137L202 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/06/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20137L192 | List: |
| References | |
| GL-83-28, NUDOCS 8601270333 | |
| Download: ML20137L202 (3) | |
Text
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ENCLOSURE i
SAFETY EVA EA*iTON REPORT GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)
LIMERICK GENERATING STATION, UNITS 1,2 DOCKET NOS. 50-352/353 INTRODUCTION AND
SUMMARY
1 Generic Letter 83-28 describes intermediate actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit ; of Salem Nuclear Power Plant.
This report is an evaluation of the responses submitted by Philadelphia Electric Company, the licensee for the Limerick Generating Station, Unit I and applicant for Limerick Generating Station, Unit 2 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.
l 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.
I REQUIREMENT 4
Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated I
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 Limerick Generating Station, Unit 1 and applicant for Limerick Generating Station, Unit 2 responded to these requirements with an original submittal dated November 10, 19832 and a supplement dated May 29, 19853 The licensee stated in the original submittal that preparation of the Technical Specifications were not complete.
The supplemental submittal stated that no post-maintenance testing requirements were identified in Technical Specifications during their preparation which degraded safety for either the reactor trip or other safety related components.
CONCLUSION Based on the licensee / applicant's statement that no post-maintenance test requirements were found in Technical Specifications that degraded safety, we find the licensee / applicant'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.
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i REFERENCES (CONT.)
2.
Letter, V. S. Boyer, Philadelphia Electric Company, to D. G. Eisenhut,
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NRC, November 10, 1983.
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3.
Letter, S. L. Daltroff, Philadelphia Electric Company, to A. Schwencer, l
NRC, May 29, 1985.
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