ML18086B234
| ML18086B234 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/22/1981 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM NUDOCS 8201060504 | |
| Download: ML18086B234 (2) | |
Text
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t PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Mailing Address:
P. o. Box 570, Newark, New Jersey 07101 December 22, 1981 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
THERMAL-MECHANICAL REPORT REVISED SMALL -
BREAK LOCA METHODS SALEM NUCLEAR GENERATING STATION NO. 1 UNIT DOCKET NO. 50-272 Item II.K.2.13. of NUREG-0737 requires that PSE&G submit a detailed analysis of the thermal-mechanical conditions in the reactor vessel during recovery from small breaks with an extended loss of all feedwater, no later than January 1, 1982.
This analysis is being prepared by Westinghouse for generic Westinghouse plant groupings and will be submitted to the NRC by the end of 1981.
This generic study is applicable to Salem 1 and PSE&G will submit, if necessary, additional plant specific analyses on this subject.
Item II.K.3.30. of NUREG-0737 requires that PSE&G comply with the requirements of NUREG-0737 regarding revision of methods used by NSSS vendors and/or fuel suppliers for small-break LOCA analysis for compliance with Appendix K to 10CFR50.
Westinghouse feels very strongly and PSE&G agrees that the small-break LOCA analysis model currently approved by the NRC for use on Salem 1 is conservative and in conformance with Appendix K to 10CFR50.
However, as documented in Westinghouse letter, NS-TMA-2318, dated September 26, 1980
--S~* D. G. Eisenhut, Westinghouse believes that the p 010605 -
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272 PDR The Energy People 95-0942
Dir. of Nucl. Reactor Reg. 12/22/81 improvement in realism of small-break calculations is a worthwhile effort and has committed to revise its small-break LOCA analysis model to address NRC concerns (e.g.,
NUREG-0611, 0623, etc.).
This revised Westinghouse model is currently scheduled for submittal to the NRC by April 1, 1982 as documented in Westinghouse letter NS-EPR-2524 dated November 25, 1981, to Mr. D. G. Eisenhut.
Should you have any questions in this regard, do not hesitate to contact us.
FM:mw Very truly yours,
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/E. A. Liden Manager -
Nuclear Licensing and Regulation CC:
Mr. Leif Norrholm Senior Resident Inspector Mr. Gary c. Meyer Licensing Project Manager AJ04 1/2