ML20206F562
| ML20206F562 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 06/11/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20206F553 | List: |
| References | |
| GL-83-28, NUDOCS 8606240521 | |
| Download: ML20206F562 (2) | |
Text
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ENCLOSURE SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 4.3 REACTOR TRIP SYSTEM RELIABILITY (AUTOMATIC ACTUATION OF 5 HUNT TRIP ATTACHMENT FOR WESTINGHOUSE AND B&W PLANTS)
WASHINGTON NUCLEAR PROJECT, UNIT 1 (WNP-1)
DOCKET NO. 50-460 INTRODUCTION AND
SUMMARY
1 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 Washington Public Power Supply System, the apF : ant for Washington Nuclear Project, Unit 1 for Item 4.3 of the Generic Letter. The actual document reviewed as part of this evaluation is listed in the references at the end of this report.
REQUIREMENT Westinghouse and B&W reactors shall be modified by providing automatic reactor trip system actuation of the breaker shunt trip attachments.
The shunt trip attachment shall be considered safety related (Class 1E).
Licensees and appli-cants should submit a report describing the modifications.
EVALUATION The applicant for Washington Nuclear Power 1 (WNP-1) provided a general re-2 sponse for Item 4.3 of Generic Letter 83-28 by letter dated March 30, 1984.
The letter noted that since WNP-1 was in an extended construction dclav, the modifications had not been completed. However, the applicant-committed to address the concerns of Item 4.3 three years prior to fuel load. We consider this acceptable.
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. CONCLUSION The required actions needed to resolve the concerns of Item 4.3 have been de-veloped by the industry and the NRC prior to fuel load for WNP-1. This, in combination with the applicant's commitment to submit a conceptual design of the reactor trip system that will have to meet these requirements three years prior to fuel load, is considered sufficient for close-out of these items.
REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28", July 8, 1983.
2.
Letter, G. C. Sorensen, Washington Public Power Supply System, to E. G. Adensam, NRC, March 30, 1984.
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