ML19210D781

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Requests Addl Info to Complete Review of WCAP-9157, Environ Qualification of Safety-Related Class IE Process Instrumentation. Info Needed Re Qualified Life of Resistance Temp Detectors & Remote Bellows Pressure Sensor
ML19210D781
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 11/16/1979
From: Baer R
Office of Nuclear Reactor Regulation
To: Parker W
DUKE POWER CO.
References
NUDOCS 7911280062
Download: ML19210D781 (5)


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          • g ggyIggyj Docket Nos. 50-369 and 50-370 Mr. William O. Parker, Jr.

Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Strer.

Charlotte, North Carolina 28242

Dear Mr. Parker:

SUBJECT:

ENVIRONMENTAL QUALIFICATION OF REACTOR COOLANT TEMPERATURE DETECTORS AND CONTAINMENT PRESSURE TRANSMITTERS (M:Guire Nuclear Station, Units 1 and 2)

The environmental qualification for certain Westinghouse-supplied instrumentation is described in WCAP-9157, " Environmental Qualification of Safety-Related Class IE Process Instrumentation." The regulatory staff has found that additional infomation is needed to complete its review of WCAP-9157. Westinghouse Electric Corporation has agreed to provide the requested information in a timely manner except for the qualified life of resistance temperature detectors (RTDs) to be used to measure the temperature of reactor coolant.

Your application for a license to operate the McGuire Plant references WCAP-9157 as a basis for the acceptance of the environmental qualification of the RTDS. Therefore, acceptable infomation to resolve this concern must be provided for our review and approval prior to the issuance of a license to operate your plant. We will require that resolutdon of the staff's concern as stated below be completed on your applica-tion.

The Westinghouse evaluation of the qualified life of the resistance temperature detectors (Section 2.2 of WCAP-9157) is unacceptable because the assumed post-accident fission product source term is too small and the assumed post-accident operating time is too short. Guidelines for calculating acceptable qualified life in a radiation environment follow.

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The total integrated exposure to be simulated in qualification tests should be the sum of the calculated integrated exposure during nomal plant operation and the calculated integrated exposure during post-accident plant operation.

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M'r. William 0. Parker, Jr. N0b I s g The fission product source term for calculating exposure during po'st-2.. -accident operation should correspond to loss-of-coolant-accident (LOCA) conditions with a release of 100". of the noble gases, 50% of the iodines,

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and 17. of the' remaining fission products generated in the equilibrium Core.

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Post-accident exposure for RTDs should be based on the~ higher of two exposures calculated by assuring (a) an instantaneous release of fission products from the fuel to the containment atmosphere, and (b) an instan-taneous release from the fuel to the reactor coolant without subsequent release to the containment.

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Post-accident operation time for the narrow-range resistance tempera-ture detectors should be the sum of the longest time required for reac-

, tor trip in any anticipated operational occurrence or design basis acci-dent plus a margin of one hour for uncertainties in predictins the time.

5.

Post-accident operation time fcP the wide-range resistance temperature detectons should consider the environmental conditions for an interval of 100 days following t'a accident,* unless a shorter time can be justi-fied. (Since the post-accident operation time used in qualification tests described in WCAP-9157 is less than 100 days, you should provide justification to show that. extending the test to 100 days would not significantly affect instrument performance or accuracy for this period).

In addition, since you do not reference WCAP-9157 as a basis for acceptance of the Barton Model 351 remote sensing bellows, additional information in the fom of test results and/or analyses are needed to demonstrate that this remote bel-lows pressure sensor, used in conjunction with the Barton Model 386A transmitter, is acceptable.

Plea" amend your application to provide the following additional information.

1.

Results of calculations using the guidelines in this letter to determine acceptable qualified life of resistance temperature detectors to be used to measure reactor coolant temperature.

2.

Results of tests or analyses to demonstrate acceptable environmental qualification of pressure transmitters to be used to measure containment pressure.

This infonnation is needed by' January 2,1980 in order to meet our schedule for review and approval of your application for an operating license.

If you cannot meet this date, please infom us within two weeks from the date of 1403

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Mr. William O. Parker, Jr.

3-50V18GD receipt of this letter of a date you will submit the requested infomation.

If you desire clarification of the technical infomation requested in this letter please call Tom Dunning on (301) 492-7387.

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Sincerely, M

I, hod Roberi.l. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management ces: See next pages 1403

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Mr.' William O. Parker, Jr.

$d Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 cc: Mr. W. L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. R. S. Howard Power Systems Division Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J..E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

Debevoise & Liberman 1200 Seventeenth Street, N. W.

Washington,, D. C.

20036 Robert M. Lazo, Esq., Chainnan Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Emmeth A. Luebke l 4 g j

'> g g Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. 0. Box 247 Bodega Bay, California 94923

Mr. William O. Parker, Jr.

NOV 16 g e

cc: Anthony Z. Roisman, Esq.

Natural Resources Defense Council W hin on, b55 Richard P. Wilson, Esq.

Assistant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 1403

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