ML20209G493

Discusses Review of Rev 1 to Technical Data Rept 571 Re Piping Insp Program for Cycle 11 Refueling Outage.Tech Specs on RCS Leakage Should Be Revised

ML20209G493
Person / Time
Site:	Oyster Creek
Issue date:	09/05/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
References
TAC-61967, NUDOCS 8609120489
Download: ML20209G493 (4)

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o UNITED STATES s [ g, NUCLEAR REGULATORY COMMISSION g g ;E WASHINGTON, D. C. 20555

%*****/ September 5,1986 Docket No. 50-219 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

SUBJECT:

REVISED PROGRAM FOR INSPECTION OF BWR STAINLESS STEEL PIPING i (TAC 619671 Re: Oyster Creek Nuclear Generating Station In your letter of July 8,1986, you provided the staff with Revision I to Technical Data Report (TDR) No. 571. This TDR discusses the pipina inspection program for the Cycle 11 Refueling (Cycle 11R) outane. This program provided the scope of inspections, examination criteria, repair methods, mitigatino actions, leak detection and leakage. The staff reviewed the original TOR No.

571 and concluded in its letter to you dated August 5,1985, that it met the guidelines in Generic Letter (GL) 84-11, Inspections of BWR Stainless Steel Piping, dated April 19, 1984. Therefore, the original TDR No. 571 was accept-able to the staff as a program for piping inspections in the Cycle 11R outage.

The staff has reviewed Revision 1 to TDR No. 571. We conclude after clarifying I discussions by phone with GPU Nuclear (the licensee) personnel that this revi-l sion to TDR No. 571 does not alter the conclusions made by the staff in its l letter dated August 5, 1985. The staff also concludes that the clarifying l discussions do not require any changes to the TDR. The pipiner inspection I program for the Cycle 11R outage described by Revision P to TDR 571 is accept-l able to the staff.

Based on our review of the above TDR, we also request that you revise the

! existing Technical Specifications (TS) on the reactor coolant system leak-l age. These revised TS are to have Section 3.3 and 4.3 of the Oyster Creek Appendix A TS in agreement with items B, C and E of Attachment I to GL 84-11.

These items are briefly (1) the maximum increase in unidentified leakage is 2 gom within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while operating, (2) the outage time for in-operable leakage measurement instruments associated with each sump,is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and (3) a visual examination for leakage of the reactor coolant piping is J

l 8609120489 860905 PDR ADOCK 05000219 O PDR l

P. B. Fiedler September 5, 1986 performed during each outage in which the containment is deinerted in accord-ance with ASME Section XI, IWA-5221, IWA-5241 and IWA-5242, respectively. You are requested to submit the proposed changes within 120 days or provide a justification for the existing TS being sufficiently restrictive. You may consider the staff's positions in the draf t Generic letter implementing draft report NUREG_0313, Revision 2, Technical Report on Material and Processing Guidelines for BWR Piping. This generic letter was issued for public comment in the Federal Register (51 FR 26196 to 2.9199) on July 21, 1986. It is the staff's position that these revised TS are needed to assure the timely discovery of unidentified leakage that may be caused by through wall cracks in austenitic stainless steel piping.

Sincerely, D.

QvVNM Jack N. Don w, Jr., Project Manager RWR Project Directorate #1 Division of BWR Licensing cc: See next page Distribution

Docket Filea NRC PDR Local PDR BWD1 Reading OGC-BETH (Info only)

R. Bernero E. Jordan B. Grimes J. Partlow ACRS (10)

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'DATE :8/21/86 :8/22/86 :8/22/86 :8/25/86 :8/25/86 :8/25/86  :

OFFICIAL RECORD COPY l

s-P. B. Fiedler _2_ September 5, 1986 performed durino each-outaae in which the containment is deinerted in accor -

ance with ASME Section XI, IWA_5221, IWA-5241 and IWA_5242, respectively. You are requested to submit the proposed changes within 120 days or provide justification for the existing TS being sufficiently restrictive. You ay consider the staff's positions in the draft Generic letter implementi g draft report NUREG-0313, Revision 2, Technical Report on Material and Pro ssing Guidelines for BWR Piping. This generic letter was issued for pub ic comment in the Federal Register (51 FR 26196 to 29199) on July 21, 1986. The staff believes that these revised TS are needed to assure the timely iscovery of unidentified leakage that may be caused by through wall crack in austenitic stainless steel piping.

Sincerely, ORIGINAr, SIGNE sy Jack N. Don ew, Jr., Project Manager RWR Proje . Directorate #1 Division f RWR Licensing cc: See next page Distribution Docket File NRC PDR Local PDR BWD1 Reading OGC-BETH (Info only)

R. Bernero E. Jordan B. Grimes J. Partlow ACRS (10)

J. Zwolinski J. Donohew C. Jamerson W. Koo R. Hermann B. D. Liaw G. Lainas G. Holahan OC file -

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_____:.________ _4:__ ____:.. _____:__ ____:__ . _

sp______:JZwolinski NAME :CJamers :J :WK

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DATE :8/ 2V 6 .________:____________:____________:____________:__7/86

8411/86 :8/11/86 :8/2./86 :8/J4/86 :8/ .

OFFICIAL RECORD COPY

Mr. P. B. Fiedler Oyster Creek Nuclear.

Dyster Creek Nuclear Generating Station Generating Station cc:

Mr. Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Rox 445 Washington, D.C. 20036 Forked River, New Jersey 08731

J.B. Liberman, Esauire Commissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1153 Aver.ue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David Scott, Acting Chief

! Regional Administrator, Region I Bureau of Nuclear Enoineering i U.S. Nuclear Regulato'.y Commission -Denartment of Environmental Ouality 631 Park Avenue 380 Scotch Road King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 BWR Licensing Manager

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GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General 4 State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey-Township 818 West Lacey Road Forked River, New Jersey 08731 Mr. D. G. Holland Licensino Manager Oyster Creek Nuclear Generatina Station ~ '

Post Office Box 388 Forked River, New Jersey 08731 A

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