ML20247N790

Provides Addl Info to Clarify 890616 Integrated Leak Rate Test Rept & Informs of Completion of 10CFR50,App J,Type a Testing for Second 10-yr Interval of Plant

ML20247N790
Person / Time
Site:	Oyster Creek
Issue date:	07/27/1989
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908030164
Download: ML20247N790 (3)

Text

. -_ - _.

4.

I I

GPU Nuclear Corporation Nuclear

=31:r388 Forked River, New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Number:

July 27,1989 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137

' Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Ten Year Inservice Inspection Requirements; and Integrated Leak Rate Test Requirements

Reference:

1. Integrated Leak Rate Test Report, dated February 1,1988

2. Licensee Event Report 88-013, " Main Steam Isolation Valve (MSIV) Failure Caused by MSIV Poppet Vibration",

dated August 8,1988.

l

3. Oyster Creek License Amendment No.132, dated April 24, 1989.

4. Integrated Leak Rate Test Report, dated June 16, 1989.

5. NRC Safety Evaluation for ISI Exemption Requests, dated March 10,1989.

l l

This letter is being written for two purposes: 1) to provide additional l

information to clarify Reference 4, " Integrated Leak Rate Test Report" (ILRT) l dated June 16,1989; and,2) to inform the Nuclear Regulatory Commission of the l

completion of 10 CFR 50 Appendix J Type "A" testing for the second ten year interval of the Oyster Creek Nuclear Generating Station.

During the performance of a Main Steam Isolation Valve (MSIV) full closure surveillance on July 9,1988, anomalous results required the shutdown of the reactor. The discrepancies in the surveillance test data were attributed to a broken stem in a Main Steam Isolation Valve, NS03A. This occurrence was dor"mented in Reference 2 Licensee Event Report 88-013, Inspection Report 3

50-219/88-24, and numerous letters between GPU Nuclear and tie Nuclear Regulatory Commission since the event. As a consequence of the stem failure, as-found Local Leak Rate Test results could not be obtained in the summer 1988 timeframe. Reference 4, the June 1989 ILRT report, documented the results of c

as-found data taken during the type C testing performed in January 1989.

8908030164 890727 A "1 I

PDR ADOCK 05000219 W'

P PDC GPU Nuclear Corporation is a subsidiary of tne General Pubhc Utihties Corporation

1 W:5. Nuclear Regulatory Commission Page 2 It was concluded that since as-found data could not be obtained during the summer 1988 timeframe, and in light of the fact it was the stem that failed and not the seat, the as-found data from January 1989 would provide the most l

representative information for inclusion in the ILRT calculation. Although this was implied in a footnote on Page 28 of the June 1989 ILRT report, GPU Nuclear has provided this clarification of the intent of that footnote to preclude confusion.

The Oyster Creek Nuclear Generating Station is presently in its second Inservice Inspection (ISI) ten-year interval. That interval commenced in December 1979, and was scheduled to complete in December 1989.

Reference 5 documented the NRC approval of the GPUN request to extend the second 10-year ISI interval to October 14, 1991.

Separate from the ISI program, the 10 CFR 50 Appendix J type A testing requirements describe the frequency of performance for type A testing to coincide with the ISI intervals.

Oyster Creek Technical Specification 4.5.D requires that:

D.

Frequency 1.

Three Type "A" overall Integrated Containment Leakage Rate Tests shall be conducted at approximatEly 40 month intervals during scheduled shutdowns within each 10-year service period.

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

2.

If two consecutive periodic Type A tests fail to meet the acceptance criteria, the subsequent Type A test shall be performed at each shutdown for refueling or approximately every 18 months whichever occurs first. This schedule will remain in effect until two consecutive Type A tests meet the acceptance criteria, at which time the frequency of testing noted in D.1 above may be resumed.

These requirements were approved by Amendment No.132 (Reference 3).

During the present ten-year interval, six ILRTs have been performed. As documented by References 1 and 4, the two most recent ILRTs were completed successfully.

The Oyster Creek ISI Program does not utilize the " shutdown for the 10-year plant inservice inspection" methodology, but rather performs inspections which are distributed over the entire interval, thereby providing an ongoing evaluation.

Therefore, GPU Nuclear has determined that the requisite ILRTs for the second 10-year interval have been completed based on:

1.

The required three ILRTs have been completed.

S. Nucitar Regulatory Commission Page.3 1

2.

The most' recent ILRT was completed at the scheduled conclusion of the second 10-year interval.

3.

There is no " shutdown for the 10-year plant inservice inspection",

therefore the most recent refueling outage meets the intent of the requirement.

As the two most recent ILRTs have been completed successfully, the "approximately 40 month (s)" interval will be met by testing during refueling outage 14R, and will serve as the first ILRT in the third 10-year interval.

If you should require any further information, please call Mr. John Rogers, Oyster Creek Licensing Department at (609)971-4893.

Very truly yours, C2

(,

fd2[2 E. E. Fit patrick Vice President and Director Oyster Creek EEF/JJR/dmd (0796A) cc: Mr. W11112; T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/II Washington, DC 20555 NRC Resident Inspector Dyster Creek Nuclear Generating Station Forked River, NJ 08731 4

u_____.