ML20209C357
| ML20209C357 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 01/23/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20209C322 | List: |
| References | |
| GL-83-28, NUDOCS 8702040252 | |
| Download: ML20209C357 (1) | |
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SAFETY EVALUATION REPORT DOCKET NOS. 50-454, 455, 456, 457 BYRON AND RRAIDWOOD STATIONS, UNITS 1 AND ?
GENERIC LETTER 83-28, ITEM 4.5.2 REACTOR TRIP SYSTEM RELIABILITY - ON-LINE TESTING INTRODUCTION AND
SUMMARY
Generic Letter 83-28 was issued by the 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 all plants to conduct testing of the reactor trip system, includino independent testing of the diverse trip features of the reactor trip breakers.
Item 4.5.2 requires applicants and licensees with plants not currently designed to permit this periodic on-line testing to justify not makino modifications to pemit such testino. By letter dated November 5,1983, the applicant, Commonwealth Edison 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 The applicant stated that the Ryron and Braidwood Stations would be designed to allow on-line testing of the Reactor Trip System. The capability for independent testing of the undervoltage and shunt trip attachments was a part of the reactor trip syste-modifications made in response to Item 4.3 and was approved by the staff in a.etter dated March 13, 1985.
CONCLUSION The staff finds that the Byron and Braidwood Stations have been designed to permit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers. Thus, your design meets the staff position of Item 4.5.2 Generic Letter 83-28.
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