ML20009C904
| ML20009C904 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/21/1981 |
| From: | Mccaffrey B LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, TASK-2.D.1, TASK-TM SNRC-600, NUDOCS 8107220119 | |
| Download: ML20009C904 (2) | |
Text
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LONG ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD e WADING HIVER, N.Y.11792 July 21, 1981 SNRC-600 N
/
A Mr. Harold R. Denton CE Office of Nuclear Reactor Regulation
> E2 6$
d U.S. Nuclear Regulatory Commission 7 d Cj js Washington, D.C.
20555 w-C S "-i SH0REHAM NUCLEAR POWER SlATION - UNIT 1
~
Docket No. 50-322
SUBJECT:
PRELIMINARY SAFETY / RELIEF VALVE (S/RV) OPERABILITY TEST RESULTS fur SHOREHAM NUCLEAR POWER STATION
References:
- 1) Letter from T. J. Dente (BWR00) to D, G. Eisenhut (NRC),
" Transmittal of Preliminary Data from Generic BWR Safety / Relief Valve (S/RV) Test Program" dated July 1,1981.
- 2) Letter from D. B. Waters (BWROG) to D. G, Eisenhut (NRC),
" Responses to NRC Questions on the BWR S/RV Test Program" dated March 31, 1981 (Response to NRC Question No. 1)
Dear Mr. Denton:
In response to NUREG-0737, Item II.D.2, this letter prevides the results of a preliminary review of the generic BWR S/RV test p.ogram results (Reference 1) in order to confirm the adequacy of the S/RV's for Shoreham Station for the alternate shutdown cooling condition which is the only expected condition resulting in liquid or two-phase discharge through the S/RV's.
The Shorenam Station employs the Target-Rock 2-stage, 6R10 type of S/RV, Model No. 7567F. The test results for the Target-Rock, 2-stage, 6R13 Valve, Model No. 7567F000 are applicable to this plant's valves (Reference 2). A preliminary review of the generic BWR S/RV test program results demorstrates that the tested valve satisfies the acceptance criteria for operability.
Consequently, based on this preliminary review, the operational adequacy of the S/RV's for the Shoreham Station has been demonstrated.
T. OO l 5
iO 8107220119 810721 FDR ADOCK 05000322 A
PDR F C-893 s
. The operability of the S/RV's for steam dischar ge conditions is demonstrated by normal vendor productior testing of each of the in-plant S/RV's.
Please contact Mr. J. P. Morin if you have an3 questions concerning this transmittal.
Very truly yours,
//EW' B. R. McCaf dy Manager. Project Engineering Shoreham Nuclear Power Station Enclosures cc:
J. Higgins i
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