ML14192A717
| ML14192A717 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/18/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14192A716 | List: |
| References | |
| GL-83-28, NUDOCS 8512090513 | |
| Download: ML14192A717 (2) | |
Text
o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 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)
CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 INTRODUCTION AND
SUMMARY
Generic Letter 83-281 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 Carolina Power and Light Company, the licensee for the H. B. Robinson Plant, Unit No. 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.
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 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.
6512090513 851118 PDR ADOCA 05000261 P
-2 EVALUATION The licensee for the H. B. Robinson Plant, Unit No. 2 responded to these re quirements with a submittal dated November 7, 19832.
The licensee stated in this submittal that there were no post-maintenance testing requirements in Technical Specifications for either reactor trip system or other safety related components 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: November 18, 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, A. B. Cutter, Carolina Power and Light Co. to D. G. Eisenhut, NRC, November 7, 1983.