ML20210U333
| ML20210U333 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Cooper |
| Issue date: | 05/23/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20210U322 | List: |
| References | |
| GL-83-28, NUDOCS 8606020294 | |
| Download: ML20210U333 (3) | |
Text
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i ENCLOSURE SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)
COOPER NUCLEAR STATION DOCKET NO.: 50-298 INTRODUCTION AND
SUMMARY
Generic Letter 83-78 describes intermediate term actions to be taken by I
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 Nebraska Public Power District, the licensee for Cooper Nuclear Station for Items 3.1.3 and 3.2.3 of the Ganerir. 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 Because of this 3.2.3 applies them to all other safety-related components.
similarity, the responses to both items were evaluated together.
RE0VIREMENT Licensees and applicants 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,iustification, shall be submitted for staff approval.
8606020294 860523 PDR ADOCK 05000298 PDR P
i EVALUATION The licensee for the Cooper Nuclear Station responded to these requirements 2
3 with submittals dated November 4, 1983, and July 30, 1985.
The licensee stated in these submittals that there were no post-maintenance testing require-ments in Technical Specifications for either the reactor trip system or other
.I safety-related comoonents which degraded safety.
+
i 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 i
83-28.
i REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, i
" Required Actions Based on Generic Implications of Salem ATWS Events r
(Generic Letter 83-28)," July 8, 1983.
2.
Nebraska Public Power District letter, L. G. Kund to D. G. Eisenhut, i
Director, Division of Licensing, NRC, " Response to Generic Letter 83-28,
' Required Actions Based on Generic Implications of Salem ATWS Events.'
NRC Docket No. 50-298, DPR-46.", November 4, 1983.
i
, REFERENCES (CONT.)
1.
Nebraska Public Power District letter, J. M. Pilant to D. B. Vassallo, Nuclear Reactor Regulation, Division of Licensing, NRC Generic Letter 83-28, Item 3.1.3 " Post Maintecunce Testing" (Reactor Trip System Components) NRC Docket No. 50-298, DPR-46, July 30, 1985.
Principal Contributor:
W. Long Dated:
May 23, 1986 L