ML18089A177

Forwards Analysis of Valve/Operator Interface Hardware for Containment Pressure & Vacuum Relief Valves 1 & 2 VC 5, in Response to NRC 830519 Request

ML18089A177
Person / Time
Site:	Salem
Issue date:	06/07/1983
From:	LIDEN E A Public Service Enterprise Group
To:	VARGA S A Office of Nuclear Reactor Regulation
Shared Package
ML18089A178	List: ML18089A177 ML18089A179
References
NUDOCS 8306140059
Download: ML18089A177 (3)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department June 7, 1983 Director of Nuclear Reactor Regulation

u. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:

Gentlemen:

Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing COMPLETION OF VALVE OPERABILITY REVIEWS FOR 10" PRESSURE/VACUUM RELIEF VALVES USED FOR PURGE OR VENT OF CONTAINMENTS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Pursuant to 10 CFR50.54(f), we hereby provide the information requested in your letter dated May 19, 1983. We have assessed the operability of our 10" pressure/vacuum relief valves with respect to the concerns of Enclosure 1 of your letter. Attached are the results of a stress analysis for the valve-to-operator interfacing hardware under operating loads during a LOCA. The tabulation summarizing the results of this stress analysis demonstrates structural integrity using the recommendations of Section 4.4 of your Enclosure

1. Since this analysis demonstrates that the 10" pressure/vacuum relief valves (VC5 and VC6) will operate in the event of a DBA-LOCA, it is our intent to operate these valves in mance with our existing Technical Specifications which allow the valves, normally maintained shut in MODES 1, 2, 3, and 4, to be intermittently opened under administrative control for safety purposes during all applicable modes of operation.

8306140059 830607 PDR ADOCK 05000272 p i' PDR The Energy People ,,, 95-2168 (80 Mi 11-82 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 6/7/83 Should you have any further questions, we will be pleased to discuss them with you. Attachment CC: Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector Very truly yours, Manager -Nuclear Licensing and Regulation

.' ! .* . *,.._, .... .., ... J. Fitzgerald Public Service Electric & Gas Nuclear Dept. Building TB002 P.O. Box 236 Hancocks Bridge, New Jersey 08038 June 3, 1983 *

Subject:

10" Model 32200 Butterfly Valves Masoneilan S/N 05587-2 PSE & G Valve No. 1VC5, 2VC5, 1VC6 and 2VC6 Masoneilan Masoneilan Division iV1cGraw-Edison Co mp any Norwood, MA 02062, USA 617 762 4600 Teiex: 9244i0 Cable: MASON!CA A stress analysis has been performed to demonstrate the structual integrity of the valve to operator interfacing hardware.

The analysis is contained in the enclosed copy of CYGNA Report No. 81041-RN004.

As indicated in the report, all calculated stresses are within allowable limits. Very truly yours, c-1 Jl ..

{U -.7(.,CJ.,'YYV.____

Ernest W. Kramer Nuclear Engineer EWK:mk J. Haberlin -MN, Norwood J. Mascart -MN, Norwood J. Reed -MN, Norwood P. Ruest -MN, Norwood -....: