ML17276A159

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Provides Final Test Results to Demonstrate Operational Adequacy of Safety Relief Valve for Facility,In Response to NUREG-0737,Item II.D.1.Submittal of NEDE-24988-P & Ltr Completes Item
ML17276A159
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/27/1981
From: Bouchey G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM GO2-81-421, NUDOCS 8111030151
Download: ML17276A159 (6)


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811027 81ii030151 05000397 PDR ADOCK A PDR L Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 October 27, 1981 G02-81-421 SS-L-02-PLP-81-034 Docket No. 50-397 Mr. D. G. Eisenhut, Director MySe HLICLtNl RltlltA'SCOT U. S, Nuclear Regulatory Commission COAIPI NON Division of Licensing Office of Nuclear Reactor Regulation Washington, D. C, 20555

Dear Mr. Eisenhut:

Subject:

TRANSMITTAL OF SAFETY/RELIEF VALVE (S/RV) OPERABILITY TEST REPORT FOR SUPPLY SYSTEM NUCLEAR PROJECT NO. 2

References:

1) Letter, T. Dente (BWR Owner's Group) to D.G. Eisenhut (NRC), "Transmittal of Valve Operability Test Report from Generic BWR Safety/

Relief Valve (S/RV) Test Program", dated September 25, 1981

2) Letter, G.D. Bouchey (WNP-2) to D,G, Eisenhut (NRC), "Supply System Nuclear Project No. 2 Preliminary Safety/Relief Valve (S/RV) Opera-bility Test Results", dated July 21, 1981 In response to NUREG 0737 Item II.D.l, this letter provides the final test results which demonstrate the operational adequacy of the S/RV's for WNP-2.

In addition, the adequacy of the S/RV discharge piping and supports has also been demonstrated. These final test results are contained in NEDE-24988-P, "Analysis of Generic BWR Safety/Relief Valve Operability Test Results", which was submitted to the NRC via Reference 1. WNP-2 is a participant in the BWR Owner's Group generic S/RV operability test program, WNP-2 employs the Crosby type of S/RV, The applicability of the generic test results to this plant's S/RV's has already been demonstrated in Re-ference 2. It should be noted that Reference 2 incorrectly stated that the tested Crosby 6210 Valve applicable to WNP-2 was Model No,, HB-65-.DF, The valve employed by WNP-2 is HB-65-BP.

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Mr. D. G. Eisenhut October 27, 1981 Page Two G02-81-421 A review of the test report shows that the operational adequacy of the S/RV's and the piping and supports for WNP-2 has been demonstrated for the conditions defined in Item II.D.1. The submittal of NEDE-24988-P and this letter satisfies the October, 1981 and January, 1982 submittal requirements of Item II.D.l and completes WNP-2 efforts on this item.

Very truly yours, G. D. Bouchey Deputy Director, Safety and Security GDB/PLP/jca cc: M.W. Hodges - NRC J.A. Olshinski - NRC D.M. Verrelli - NRC

'N".'S;7 Reyno.l.ds - DLL R. Auluck - NRC WNP-2 Files

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