ML18082B195
| ML18082B195 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/05/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009190192 | |
| Download: ML18082B195 (2) | |
Text
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PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 September 5, 1980 Director of Nuclear Reactor Regulation
- u. S. Nuclear Regulatory Commission Washington, D. c.
20555 Attention: Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:
II.D.l RELIEF AND SAFETY VALVE TEST REQUIREMENTS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 In response to your letter dated August 29, 1980, PSE&G submits the following with regard to the subject test requirements:
- 1.
PSE&G will monitor the EPRI program to provide assurance that:
(a)
It will be applicable to the Salem plant design, and (b)
It will provide sufficient information to qualify the Reactor Coolant System relief and safety valves and associated piping and supports under expected operating conditions for design basis transients and accidentse
- 2.
PSE&G will submit to the NRC, in a time frame compatible with the completion of the EPRI program, the following information with respect to Salem:
(a)
Evidence supported by test of safety and relief valve functionability for expected operating and accident (non-ATWS) conditions.
The testing will demonstrate that the valves will open and reclose under the expected flow conditions.
( b)
A correlation, or other evidence, to substantiate that the valves tested in the EPRI program demon-strate functionability of as-installed primary re-lief and safety valves.
The Energy People 8 0 0 9 1 g. 0 /9:i- *;
f 95-0942
Director of Nuclear Reactor Regulation 9/5/8 0 This correlation will show that the test conditions used are equivalent to expected operating and accident condi-tions as described in the FSAR.
The effect of as-built relief and safety valve discharge piping on valve op-erability will be accounted for, if it is different than the generic test loop piping.
(c) Test data, including criteria for success and failure of valves tested, will be provided for review and evalua-tion.
This test data will include data which would per-mit plant specific evaluation of discharge piping and supports which are not tested directly.
- 3.
PSE&G will submit in a time frame compatible with the EPRI program, by January 1, 1982, evidence supported by test to qualify the PORV block valves under expected op-erating conditions for design basis transients and accidents.
Should you have any questions, do not hesitate to call us.
CC: Mr. Leif Norrholm Salem Resident Inspector GO 06 1/2 9~:/y~2rs, 7' j J;;I( /!ff R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction