ML17342A285
| ML17342A285 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Turkey Point |
| Issue date: | 11/14/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17342A284 | List: |
| References | |
| GL-83-28, NUDOCS 8511220346 | |
| Download: ML17342A285 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST>>MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS TURKEY POINT UNIT NOS.
3 AND 4 DOCKET NOS. 50-250 AND 50-251 INTRODUCTION AND
SUMMARY
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 Florida Power and Light Company, the licensee for the Turkey Point Plant, Units 3,4 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 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.
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8511220346 851114 PDR ADOCN, 05000250 RE UIREMENT I
p PDR 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 justification, shall be submitted for staff appt oval.
='VALUATION The licensee for the Turkey Point Plant, Units 3,4 responded to these require-ments with a submittal dated November 8, 1983.
The licensee stated in this 2
submittal that there were no post-maintenance testing requirements in Technical Specifications for either reactor trip system or other safety-related com-ponents 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.
Dated:-'ovember 14, 1985 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.
R. Williams, Jr., Florida Power and Light Co. to D. G. Eisenhut, NRC, November 8, 1983.