ML20059L644

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Safety Evaluation Supporting 900302 & 0829 Requests for Exemption from Requirements of 10CFR50,App J Re one-time Extension of Interval Between Tests for Performance of Type B & Type C Tests
ML20059L644
Person / Time
Site: Oyster Creek
Issue date: 09/12/1990
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059L642 List:
References
NUDOCS 9009270208
Download: ML20059L644 (6)


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UNITED STATES lJ NUCLEAR REGULATORY COMMISSION W

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...al SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REWEST FOR TEST ItiTERVAL EXEMPTION RELATED TO 10 CFR PART 50, APPENDIX J TYPE B AND C TESTING GPU NUCLEAR CORPORATION AND' h

JERSEY. CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION p

LOCKET NO. 50-219 L[

1.0' INTRODUCTION I

By letters dated March 2, 1990 and August 29, 1990, GPU Nuclear Corporation (GPUN/ licensee) requested an exemption from certain requirements of 10 CFR 50, Appendix J, concerning a

+ime only request r v an extension of the interval 7

L between tests for the per

.nce of Type B te:,ts on penetrations and Type C tests on valves.. Enclos I and 11 list the specific penetrations and valves g'

and the date of-the most recent successful completion of each Local Leak Rate Test (LLRT).

2.0 EVALUATION Paragraphs III.D.2. and III.D.3 of 10 CFR 50, Appendix J require that LLRT of containment penetrations (Type B te;. ting) and valves (Type C testing) be performed at intervals no greater'than 2-years. Theilicensee has-. requested

.an enmption from this requirement in the form of a one-time only extension unti the next refuelic.g outage (13R) which.is presently' scheduled for no-later than February 15, 1991. This would extend the interval _between tests for 32 penetrations and 43 valves for.no more than.4-1/2 months of power operation.

Testing of ~ penetrations will be extended from October 7,1990, or later until' the 13R refueling outage and-testing of valves will be extended from October 1, 1990,'or later until the 13R refuelin9 outage. The exemption is based on a refueling outage starting date no later than February 15, 1991.

Thesepenetrationscannotbetestedduringpoweroperationbecause1)some Lpenetrations require access to the drywell in order to test, and 2) some

< penetrations require valve manipulations inside the drywell and some penetra-tions-are in high radiation levels. These valves cannot be tested during power operation, because the systems involved must be operating to allow

' continued operation of the plant.

In GPUN's letter of March 2,1990, the licensee states that meeting the 2-year testing interval for LLRT implementation would necessitate a reactor shutdown prior to the 13R refueling outage schedule date. This would result in an E.T 9009270209 900912 ~

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additional thermal cycle for the plant, as well as the potential environmental impact of a winter shutdown to meet 10 CFR 50, Appendix-J testing criteria.

Temporary deferment of these tests would allow the licensee to take the plant y-off-line consistent with system needs for power and the licensee's overall 1

program of power management.

3.0 CONCLUSION

GPUN has indicated that an attempt was made to test the 43 valves for which they are seeking an exemption.. They were unable to test the valves because in order to perform the test the plant would have to reduce power or shutdown.

If the plant is shutdown for an unscheduled outage, the valves that are part of the Appendix J program will be tested on a best efforts basis.

--The staff has reviewed the-licensee's request.and finds that the l'eakage characteri_stics of the penetrations and valves in question would not be expected to degrade significantly during the period of the requested extension, which is short in comparison with the 2 year interval specified in 10 CFR 50, Appendix J.

This is based on previous test experience at other nuclear plants.

Based on1the above the staff concludes that the requested extension of the start of tne 13R refueling outage to no later than February 15, 1991 ef the Type B and C. TEST for the 32 penetrations and 43 valves is acceptable.

Principal Contributor:

A. W. Dromerici Dated: September 12, 1990 l

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