ML20215M671

Summary of 860910 Meeting W/Util in Bethesda,Md Re Tech Spec Change Request 126 on Containment Integrated Leak Rate Test.Significant Items Discussed Listed.List of Meeting Attendees Encl

ML20215M671
Person / Time
Site:	Oyster Creek
Issue date:	10/22/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8611030153
Download: ML20215M671 (5)

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• ' [,Do UNITED STATES 8' Egn NUCLEAR REGULATORY COMMISSION h ,$ WASHINGTON. D. C. 20555 k.....,/ October 22, 1986 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

SEPTEMBER 10, 1986, MEETING WITH GPU NUCLEAR CORPORATION (GPUN)

TO DISCUSS TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) N0. 126 ON THE CONTAINMENT INTEGRATED LEAK RATE TESTS (ILRT)

On Wednesday, September 10, 1986, a meeting was held at NRC, Bethesda, Maryland with GPUN, the licensee, on the licensee's TSCR 126 which was submitted by letter dated July 25, 1986. The licensee had requested that the staff complete its review before September 15, 1986, in order for the licensee to support plant restart from the current Cycle 11 Refueling (Cycle 11R) outage. The staff reviewed the licensee's submittal and, by phone conference on August 20, 1986, the staff discussed the concerns it had with TSCR 126 with the licensee. These concerns would prevent approving the TSCR without additional information. The meeting of August 27, 1986, on the status of licensing actions on Oyster Creek, was requested by the licensee to discuss in more detail the concerns raised by the staff.

Attachment 1 is the list of participants that attended the meeting. The following is a sumary of the significant items discussed and the actions, if any, taken or proposed.

The review of TSCR 126 by the staff should not be considered complete because the review was stopped once it was determined that the TSCR could not be issued without additional information from the licensee and changes to the TSCR by the licensee. The staff, therefore, could not issue the TSCR as written by September 15, 1986.

The licensee first explained its philosophy of conducting an ILRT and why it proposed TSCR 126. This TSCR is a revision of an earlier submittal

! dated September 25, 1984, which was withdrawn later by the licensee. The TSCR the licensee stated, was due to the large increase in the Cycle 10R outage of the number of valves to be tested under Appendix J. The number of valves tested were doubled but the acceptance leak rate criteria was not changed. The TSCR proposes a change to these criteria.

Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, to 10 CFR Part 50 provides the requirements for the ILRT.

This includes the Type A, B and C tests listed in the TSCR. The staff 1 stated that revisions to Appendix J have been out for public comment and ,

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, m 2-that a final Appendix J is before the Comission and may be issued soon.

The licensee said that the TSCR included proposed changes to take into account some of the proposed Appendix J changes.

The licensee explained that its TSCR proposed a longer cycle for the Type A containment tests because the next refueling outage, after the current Cycle 11R outage, is expected in 1988, 17 months after the outage.

The licensee explained that deleting the 24-hour limit for the Type A containment ILRT had the effect of imposing the time limit in the ANSI /ANS standard. The staff stated that this was not entirely acceptable because it does not fully accept the standard and that it would provide guidance later relative to this item.

The staff also explained that the proposed TS 3.5.D.2 is more restrictive than the requirement in Appendix J and that the TSCR on the containment air lock testing requires, until the final revised Appendix J is issued, an exemption to Appendix J. The licensee's request for an exemption must include the information listed in 10 CFR 50.12.

The staff and the licensee discussed the details of testing the containment air locks. The licensee explained that these tests at Oyster Creek mean pressurizing the air space between the doors forming the air lock and not just pressurizing the seals of the air lock.

The staff requested that the licensee explain its ILRT philosophy and how it would implement the existing and revised Appendix J in its next submittal on TSCR 126. In particular, the proposed reduced testing should be addressed. The staff also requested that the licensee discuss the question of resilient seals, if any, in the existing containment purge and vent isolation valves in this submittal. The staff had requested this informa-tion in its Safety Evaluation (SE) on containment purging and venting during power operation, dated January 21, 1986. The licensee agreed to these requests and stated that its next submittal on TSCR 126 should be sent by November 24, 1986.

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/ Jack N. Donohew, Jr., 'oject Manager C BWR Project Directorate #1 Division of BWR Licensing

Attachment:

List of Attendees cc: R. Bernero G. Lainas G. Hulman J. Kudrick 0FC : BL:BWD1 :DB .: 1  : DBL  : DBL:BWD1  :  :  :

NAME:CJaik..____:__.}

on :Jt{jn ew :JKu :JZwolinski  :  :  :

DATE :10/ / :10/ 4 /86 :10'*8 /\ 6 :10/9/86  :  :  :

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............-w- ...

Oyster Creek Nuclear Generating Station cc: 1 Mr. Ernest L. Blake, Jr. Resident Inspector  !

Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Box 445 Washington, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering U.S. Nuclear Regulatory Commission Department of Environmental Protection 631 Park Avenue CN 411 King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08625 BWR Licensing Manager Mr. P. B. Fiedler GPU Nuclear Vice President & Director 100 Interpace Parkway Oyster Creek Nuclear Generating Parsippany, New Jersey 07054 Station Post Ofitce Box 388 Deputy Attorney General Forked River, New Jersey 08731 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 Licensing Manager Oyster Creek Nuclear Generating Station e' Mail Stop: Site Emergency Bldg.

P. O. Box 388 Forked River, New Jersey 08731 l

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.., l ATTACHMENT 1 MEETING WITH GPU NUCLEAR CORPORATION (GPUN)

To discuss TSCR 126 SUBMITTAL DATED JULY 25, 1986 SEPTEMBER 10, 1986 NAME ORGANIZATION J. Donohew NRC/NRR/ DBL J. Zwolinski NRC/NRR/ DBL J. Kudrick NRC/NRR/ DBL J. Kowalski GPUN J. Molnar GPUN B. Pitman GPUN K. Hutko GPUN J. Chung Region I R. Gallo Region I

- . I Distribution for Meeting Summary dated: October 22, 1986 Facility: ;0yster Creek Nuclear Generating Station

• Docket.Eilex /

NRCPDR Local PDR BWD1 Reading R. Bernerc J. Donohew J. Zwolinski C. Jamerson G. Lainas G. Hulman J. Kudrick OGC-BETH(InfoOnly')

E. Jordan.

B. Grimes ACRS (10) '. s.

Oyster Creek File ,

• Copies sent to persons on facility service list t

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