ML19242D680
| ML19242D680 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/28/1979 |
| From: | Goldberg S NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Deale V, Eva Hill, Stober Q LAWRENCE LIVERMORE NATIONAL LABORATORY, Atomic Safety and Licensing Board Panel, WASHINGTON, UNIV. OF, SEATTLE, WA |
| References | |
| NUDOCS 7908160068 | |
| Download: ML19242D680 (5) | |
Text
NRC PUBL!C DOCU2ENI ROOM
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NUCLEAR REGULATORY COMMISSION L/
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Valentine B. Deale, Esq., Chairman Dr. Quentin J. Stober
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Atomic Safety ar.d Licensing Board Fisheries Research Institute 1001 Connecticut Avenue, N.W.
University of Washingten Washington, D.C.
20036 Seattle, Washington 98195 Mr. Ernest Hill Lawrence Livermore Laboratory University of California P.O. Box 800, L-123 Livermore, California 94550 In the Matter of Virginia Electric and Power Company (North Anna Nuclear Power Station, Units 1 and 2)
Docket Nos. 50-338 SP & 50-339 SP (Proposed Amendment to Facility Operating License NPF-4 to Permit Storage Pool Modification)
Gentlemen:
Enclosed please find executed copies of the two affidavits of Jared S. Wermiel which accompanied the NRC Staff supplemental response to VEPCO's summary disposition motion.
Sincerely,
[fL /\\L Steven C. Goldberg Counsel for NRC Staff
Enclosure:
As stated cc w/ enclosure:
Michael W. Maupin, Esq.
Mr. Irwin B. Kroot James B. Dougherty, Esq.
Anthony J. Gambardella, Esq.
Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Board Panel Docketing and Service Section
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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Docket Nos. 50-338 SP i VIRGINIA ELECTRIC AND POWER COMPANY
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50-339 SP
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(Proposed Amendment to Facility (North Anna Nuclear Power Station,
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Operating License NPF-4 to Permit Units 1 and 2)
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Storage Pool Modification)
AFFIDAVIT OF JARED S. WERMIEL ON CONTENTION 2(a): RADI0 ACTIVE EMISSION (ACCIDENTS)
I, Jared S. Wermiel, being duly sworn, state:
Contention 2 (Radioactive Emission) states, in part:
In CEF's opinion, applicants' analysis of radiation released, and of possible releases, in the event of those accidents considered in [ Sections 9.1 and 9.2]
of the application, are superficial and insubstan-tial in the Summary of the Proposed Modifications.
I have reviewed paragraphs 87 through 90 of "VEPCO's Statement of Mater:al Facts as to Which There is no Genuine Issue to be Heard" (hereinafter re-ferred to in separate Staff affidavits as "VEPCO's Statement of Material Facts") attached to its May ll,1979 summary disposition motion, as rele-vant to Contention 2, and concur in the statements contained therein.
Loss of Spent Fuel Pool Cooling Capability and Fuel Pool Leakage (Summary, 659.1 and 9.2)
The proposed increase in the spent fuel storage capacity does not affect the potential for these accidents as cooling of the pool and the maintenance
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. of an adequate water level in the pool is presently a technical specification requirement for the North Anna operating license and will remain so under the proposed modification.
See also 52.4 of the NRC Staff Safety Evaluation.
i prepared in connection with the proposed modification.
The spent fuel pool cooling system is a seismic Category I system.
There-Fore, the complete failure of the spent fuel pool cooling system is considered to be a very unlikely event.
However, adequate pool makeup capability is provided from redundant sources to maintain pool cooling as discussed in the
" Affidavit of Paul H. Leech, Francis C. Kornegay and Jared S. Wermiel on Contention 1: Thermal Effects" which accompanied the "NRC Staff Response to VEPC0 Sumary Disposition Motion," dated June 5,1979. This affidavit also describes the protection available in the event of pool leakage.
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Jared S. Wermiel Subscribed and sworn to before me this 28th day n# June,1979 In k
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My Conmission expires: July 1,1982 oq ~
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UNITED STAiES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOAPD In the Matter of
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Docket Nos. 50-338 SP*
VIRGINIA ELECTRIC AND POWER COMPANY _ )
50-339 SP
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(Proposed Amendment to Facility (North Anna Nuclear Power Station,
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Operating License NPF-4 to Permit Units 1 and 2)
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Storage Pool Modification) a AFFIDAVIT OF JARED S. WERMIEL ON NEW CONTENTION CONCERNING
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SERVICE WATER COOLING SYSTEM I, Jared S. Wermiel, being duly sworn, state:
By Order, dated June 6,1979, the licensing board admitted the following new contention raised in the May 9 Motion of Intervenor Potomac Alliance:
Tae intervenor contends that the service water cooling system for the facility will be inadequate to support the component cooling system for the spent fuel pool if the proposed modification of the pool is permitted.
The licensee recently submitted the results of a performance test on the North Anna service water reservoir.
The results of this test indicated that the design maximum temperature for the service water system must be U
increased from 95 F to 110 F based on eventually supporting four unit opera-tion. Since the service water system cools the component cooling water system, this change will cause an increase in the design maximum component U
cooling water system temperature from 105 F to 113.2 F.
This change also will result in a corresponding increase in the spent fuel pool cooling water system design maximum temperature for both the normal and abnormal cooling 6/3 o
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, load requirements as this system is cooled by component cooling water.
In order to maintain the spent fuel pool temperature within the limits of 140 F U
for the normal case and 170 F for the abnormal case as defined in the Staff Safety Evaluation of January 29, 1979 for the proposed increased spen't fuel storage capability assuming the maximum service water system temperature, one fuel pool cooling pump and two heat exchangers are required to operate.
However, this mode of operation is needed for only a short period of time just after refueling when the spent fuel decay heat load is at its greatest level. Should only one cooler be available during this peak heat load U
period, the resulting pool water temperatures of 148 F for the normal case and 177 F for the abnormal case are only slightly above the previously established limits and will not result in unacceptable operating conditions nor will it adversely affect the health and safety of the public.
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U Jared S. Wermiel Subscribed and sworn to before me this 2Sth day of June,1979.
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Nota ry Jublic My Commission expires:
July 1, 1979 I
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