ML20071K093

Tech Spec Change Request 113 to License DPR-50 Re Local Leakage Tests for Valves IC-VI6,VI8 & NS-VII in Type C Testing Program & Newly Installed Hydrogen Recombiner Valves

ML20071K093
Person / Time
Site:	Three Mile Island
Issue date:	04/21/1982
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20071K067	List: ML20071K064 ML20071K093 ML20071K114
References
NUDOCS 8204270460
Download: ML20071K093 (4)

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METROPOLITAN. EDISON COMPAh7 JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPAhT THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289

~ Technical Specification Change Request No. 113 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. ,

DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

GPU NUCLEAR CORPORATION By-Director, TMI-l t

Swcrn and subscribed to before me this )/ .

ay of

,/2A , 1982. ,

o 0? t' f _.~ '

Notary [/P lie FAMELA JOY LUEREChT, N3tary Public Dagh:n Canty, Pa.

Md&towri, My Corresmo Expiru Aagust 41963 1

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. 1 8204270460

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 i

GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No.113 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, 2ddressed as follows:

Mr. Donald Hoover, Chairman Mr. John E. Minnich, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION A

By Director, TMI-l Dated: April 21, 1982

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, I. TECHNICAL SPECIFICATION CHANGE REQUEST NO. 113

.The L1censee requests the attached changed pages replace the following pages of the existing' Technical Specifications:

Appendix A Replace pages 4-32, 4-33, 4-34b II. REASONS FOR CHANGE REQUEST j In NRC letter dated November 4, 1981, the Licensee was requested to l include Valves IC-VI6, VI8 and NS-VII in our type C testing program.

In our letter 82-022, dated January 26, 1982, we concurred and in

addition committed to include our newly installed hydrogen recombiner valves (HR-V2A, 2B, 4A, 4B, 22A, 22B, 23A, 23B) .

III. SAFETY ANALYSIS JUSTIFYING CHANGE i

All the above valves are either newly installed er were previously excluded from the Type C test as described in the November 4, 1981 i NRC letter. In conjuction with the hydrogen recombiner installation,

, leak rate test valves LR-V2 and LR-V3 have had blind flanges installed i downstream to act as containment isolation devices. k'e , therefore,

! request that these valves not be required to be type C tested. Valves 1

LR-V2 and V-3 remain within the test boundaries, but have as their

, function the throttling of building air flow during depressurization after Reactor Building Leak Rate Testing. Leak tests on penetrations

415 and 416 flanges will include any leakage from packing and bonnet gaskets on valves LR-V2 and V3.

i j Since it has been determined that our fluid blocking systems do not

meet the 10 CFR 50 Appendix J requirements for a seal system, all the valves in' Tech. Spec. 4.4.1.2.1 are either Type E or C tested in accordance with Appendix J, as appropriate. TMI-l has nrt taken l credit for these fluid block systems in lieu of actual trpe B and C

} tests since 1977. All discussion of these syst' ems are, there fore, being removed from the Technical Specifications. Valves have been listed in alphabetical order by tag number, and RS-Y2A tag number has been corrected.

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Conclusion i (1) .The probability or consequences of accidents previously evaluated

! have not increased.

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(2) No accidents, other than those previously censidered, will be introduced.

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(3) No safety margins have been reduced.

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t IV. AMENDMENT CLASSIFICATION (10 CFR 170.22)

This change request involves a single safety issue and is therefore considered a class III license amendment. A check in the amount of

$4,000.00 is enclosed.

V. IMPLEMENTATION 1

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We request'that the Amendment-be effective as of the date of issuance. ,

1 j VI. REFERENCES l 1. GPUN Letter 82-022 dated January 26, 1982 j 2. NRC Letter dated November 4, 1981

3. License Amendment No. 61 dated January 26, 1981

4. License Amendment No. 63 dated March 30, 1981 1,

'5. FSAR Section 5 i

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