ML20236G521

Requests NRC Approval by 880115 of Plant Schedule to Perform Future Containment Integrated Leak Rate Tests (ILRT) Under Normal ILRT Schedule,Per Tech Spec 4.4.1.1.5 & 10CFR50,App J.Update of Util 870209 Local Leak Rate Results Encl

ML20236G521
Person / Time
Site:	Three Mile Island
Issue date:	10/27/1987
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236G524	List: ML20236G521 ML20236H378
References
5211-87-2183, IEIN-85-071, IEIN-85-71, NUDOCS 8711030056
Download: ML20236G521 (2)

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floute 441 South Middletown, Pennsylvania 17057 o191 7F 944 7621 1

TELEX 84 2386 Writer's Direct Dial Number:

October 27, 1987 i i

5211-87-2183 j 1

i U.S. Nuclear Regulatory Commission Attn: Document Control Desk i

Washington, DC 20555

Dear Sir:

1 Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating L1 cense No. DPR-50 Docket No. 50-289 Containment Integrated Leak Rate Test (ILRT) Schedule 10 CFR 50, Appendix J The purpose of this letter is to request NRC approval of TMI-1's schedule to perform Future Containment Integrated Leak Rate Tests in accordance with the normal ILRT schedule per Technical Specification (T.S. ) 4.4.1.1.5 and 10 CFR 50, Appendix J ,Section III.D.l .a. NRC approval is required because the November,1986 as-found ILRT failed to meet the acceptance criteria. Also, attached to this letter is an update of our Local Leak Rate Test (LLRT) report which shows the results of tests that were not complete when the 1986 ILRT report was submitted.

Whenever any Type A test fails to meet the applicable acceptance criteria, review and approval of the schedule applicable to subsequent Type A tests is required by Appendix J,Section III. A(6)(a). Two consecutive test failures would result in the requirement to perform these tests at each plant shutdown for refueling until two consecutive tests meet the acceptance criteria. GPUN has evaluated the results of the 1984 ILRT with respect to the guidance given in NRC Information Notice 85-71, dated August 22, 1985 and we have verified that the 1984 ILRT passed the as-found test, even when corrected for local leakage repairs. Because the 1984 TMI-l ILRT results submitted on July 19, 1984 were favorable, the 1986 test failure was the first such failure since 1977.

In accordance with 10 CFR 50, Appendix J and TMI-l Technical Specification 4.4.1.1.8, the results of TMI-l's November,1986 ILRT was submitted to the NRC in a summary report entitled " Reactor Containment Building Integrated Leak Rate Test" on February 9,1987. Because the first (as-found) test had failed the acceptance criteria and the event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(ii), a License Event Report (LER) was submitted as LER 86-013-00 on December 8,1986.

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5211-87-2183 October 27, 1987 The November 1986 ILRT failure was largely due to leakage of the Penetration Pressurization check valves, PP-V101 and PP-Y102. It was determined that their contribution amounted to approximately 21% of the total observed Reactor Building leakage during the ILRT. Both valves were repaired during the l Cycle 6 refueling outage. Because Local Leak Rate Testing (LLRT) was not complete at the time of our February 9,1987 submittal, the test results for PP-V101 and PP-V102 were not included. Therefore, we are providing an update i to the LLRT section of our February 9,1987 submittal. This update reflects the results of LLRT through the end of the Cycle 6 refueling outage.

Subsequent to our February 9,1987 submittal, the purge valve LLRT procedure has been revised to incorporate the testing of PP-V101 and PP-V102 each refueling interval . These tests were performed prior to Cycle 6 operation ,

under a Temporary Change Notice (TCN), and the permanent change to this procedure has since been approved. Based on the scheduled performance of these tests each refueling outage and ILRT frequency as specified by 10CFR50 .

Appendix J and T.S. 4.4.1, we believe that the required integrity of PP-V101 j and PP-V102 and hence the integrity of the Reactor Building can be assured.

In order that we can firm up our plans for the Cycle 7 refueling outage, GPUN requests NRC approval by January 15, 1988 to perform the next ILRT in i accordance with the normal schedule requirements of Appendix J and TMI-1 l Technical Specifications. The next ILRT is currently scheduled for the Cycle 8 refueling outage.

1 Sincerely, W

H. D. Hukill Vice President & Director, TMI-l HDH/MRK/spb:0996A l Attachment cc: G. Edison W. Russell l R. Conte l J . Stol z

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