ML20128F456

Forwards SE Accepting Rev to Inservice Testing Program Re Leakage Testing of Containment Isolation Valves

ML20128F456
Person / Time
Site:	Oyster Creek
Issue date:	10/01/1996
From:	Stolz J NRC (Affiliation Not Assigned)
To:	Roche M GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20128F460	List: ML20128F456 ML20128F479
References
TAC-M95142, NUDOCS 9610080081
Download: ML20128F456 (3)

Text

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October 1, 1996 l

Mr. Michael B. Roche

Vice President and Director

GPU Nuclear Corporation

i. Oyster Creek Nuclear Generating Station P.O. Box 388

Forked River, NJ 08731

SUBJECT:

SAFETY EVALUATION FOR THE OYSTER CREEK NUCLEAR GENERATING STATION j INSERVICE TESTING PROGRAM REQUEST (TAC NO. M95142) i .

By letter dated March 28, 1996, GPU Nuclear Corporation (GPU) submitted a j revision to the inservice. testing program for the Oyster Creek Nuclear

, Generating Station. The revisions relate to the. leakage testing requirements of the 1986 Edition of the American Society of Mechanical Engineers (ASME)

Boiler and. Pressure Vessel Code (the Code). The revisions allow GPU is use 3 certain portions of a later edition of the ASME Code for leakage testitj of i valves, including containment isolation valves. NRC approval of the revisions l will allow GPU to implement a recent amendment (Amendment 186) to the

, technical specifications related to leakage testing of containment isolation

' valves.

t The NRC staff has reviewed the proposal and determined that use of portions of i the later edition of the ASME Code is acceptable pursuant to 10 CFR

, 50.55s(f)(4)(iv), provided all related requirements are met, for the reasons

discussed in the enclosed safety evaluation. This completes staff action on l TAC Number M95142.

i l If you have any questions on th'is matter, please call Mr. Ron Eaton at (301) t 415-3041. ~

t

} ~ Sincerely, ,

1 l' Original signed by L.. Ol~s han for:

John F. Stolz, Director

[

Project Directorate I-2 Division'of Reactor Projects'- I/II

, Office of Nuclear Reactor Regulation Docket No. 50-219 ' Distribution

'DocketiE11e1 ACRS

Enclosure:

Safety Evaluation PUBLIC" ' " PEselgroth, RI PDI-3 Plant GHill (2) cc'w/ encl: See next page SVarga WDean JZwolinski OGC i DOCUMENT NAME: G:\EATON\M95142.IST  !

Ta ,eceive a copy of thig doewnnat,ladeate in the boa: 'C' = Copy without attachment / enclosure *E' = Copy with attachment /encloswo *N* = No copy j OFFICE PMfPI M2/ lE LA l hE, OGCJ44f Woe ptT#):PDI-2 l l NAME Reft ( n ~ CJamerson (W h N JStolz DATE 09/dl./96 09/ 50/96 / f9/ /' / /96' W pS/ i /96 0FFEIAL RECORD COPY lo n= ch nenn 9610080081 961001 NRC FILE CENTER COPY PDR ADOCK 05000219 l

- .-  ?- __ - . PDR ,_ _

i

.' p uc ug l g 4 UNITED STATES i = 'E NUCLEAR REGULATORY COMMISSION

. If WASHINGTON, D.C. 3066H001

% ,,,,, # October 1, 1996 Mr. Michael B. Roche Vice President and Director

! GPU Nuclear Corporation Oyster Creek Nuclear Generating Station P.O. Box 388 Forked River, NJ 08731

SUBJECT:

SAFETY EVALUATION FOR THE OYSTER CREEK NUCLEAR GENERATING STATION l INSERVICE TESTING PROGRAM REQUEST (TAC NO. M95142)

By letter dated March 28, 1996, GPU Nuclear Corporation (GPU) submitted a I revision to the inservice testing program for the Oyster Creek Nuclear Generating Station. The revisions relate to the leakage testing requirements i of the 1986 Edition of the American Society of Mechanical Engineers (ASME)  !

Boffer and Pressure Vessel Code (the Code). The revisions allow GPU to use certain portions of a later edition of the ASME Code for leakage testing of valves, including containment isolation valves. NRC approval of the revisions will allow GPU to implement a recent amendment (Amendment 186) to the technical specifications related to leakage testing of containment isolation valves. i The NRC staff has reviewed the proposal and determined that use of portions of the later edition of the ASME Code is acceptable pursuant to 10 CFR 50.55a(f)(4)(iv), provided all related requirements are met, for the reasons discussed in the enclosed safety evaluatior,. This completes staff action on TAC Number M95142.

If you have any questions on this matter, please call Mr. Ron Eaton at (301) 415-3041.

Sinc y, h w '/fL John F. Stolz, Director Project Directorate I-2 l Division of Reactor Projects - I/II '

Office of Nuclear Reactor Regulation Docket No. 50-219  :

Enclosure:

Safety Evaluation cc w/ encl: See next page

-M. Roche Oyster Creek Nuclear GPU Nuclear Corporation Generating Station cc:

Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

Washington, DC 20037 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, NJ 07054 l

Mayor Lacey Township 818 West Lacey Road Forked River, NJ 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P.O. Box 388 Forked River, NJ 08731 l

Rasident Inspector c/o U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Kent Tosch, Chief l New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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