ML18092B560
| ML18092B560 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML18092B558 | List: |
| References | |
| GL-83-28, NUDOCS 8705080280 | |
| Download: ML18092B560 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT
- DOCKET NOS. 50-272/311 SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 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 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 positi.on which requires on-line functional testing of the reactor trip system, including independeni 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 letter dated July 22, 1983 and several previous submittals, the licensee, Public Service Electric and Gas Company, responde.d 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 licensee states that they perform on-line testing of the reactor trip breakers, including independent testing of the undervoltage and shunt trip attachments. Although the licensee does not specifically refer to the entire reactor trip system, the licensee's Technical Specifications require on-line testing of the remainder of the reactor trip system. Thus, we can conclude that the plant is designed to allow on-line testing of the reactor-trip system and independent testing of the undervoltage and shunt trip attachments of the reactor trip break@rs.
1 870 5080280- 870430 PDR 'ADOCK 05000272 p
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,, CONCLUSION
- The staff finds that t.he Salem Nuclear Generating Station, Units 1 and 2, is designed to pennit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers. Thus, the license! meets the staff position of Item 4.5.2 of Generic Letter 83-28.
PRINCIPAL CONTRIBUTOR:
A. Toalston I
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DOCKET FILES NRC PDR Local PDR PD I-3 Reading SVarga OGC E. Jordan B. Grimes J. Partlow DFischer M. Rushbrook ACRS (10)
INTERNAL DJSTRIBUTION