ML20247A138
| ML20247A138 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/04/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20246B820 | List: |
| References | |
| GL-83-28, NUDOCS 8905230052 | |
| Download: ML20247A138 (1) | |
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ENCLOSURE 1 SAFETY EVALUATION REPORT HILLSTONE NUCLEAR POWER STATION, UNIT 1 GENERIC LETTER 83-28, ITEM 4.5.2 REACTOR TRIP SYSTEM RELIABILITY - ON-LINE TESTING INTRODUCTION AND
SUMMARY
i Generic Letter 83-28 was issued by NRC on July 8, 1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salem ATWS events. Item 4.5 states a staff position which requires on-line functional testing of the reactor trip system, including independent testing of. the diverse trip features of the reactor trip breakers, for all plants.
Item 4.5.2 requires applicants and licensees with plants not currently designed to permit this periodic on-line testing to justify not making modifications to permit such testing. By letters dated November 8, 1983 and March 16, 1984, the licensee Northeast Nuclear Energy Company, responded to the staff position regarding Item 4.5.2 of Generic Letter 83-28. Our review of these responses finds them to be acceptable.
EVALUATION In their first submittal dated November 8, 1983, the licensee statee that the Millstone 1 Reactor Trip System was designed to permit on-line testing of the reactor trip system and that periodic on-line testing would be performed at intervals specified in the Technical Specifications.
It was not clear from this response that the plant would perform independent testing of the operability of the backup scram valves. However, in their last submittal they stated that the plant was implementing a procedure to fully test the nomal backup scram valves and the ATWS backup scram valves and that this testing would be perfomed at refueling outages.
CONCLUSION The staff concludes that this response is acceptable since the licensee's response meets the staff position.
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