ML19312D545

Forwards Request for Addl Info Re OL Application.Info Needed Concerns RHR Sys.Commitment to Demonstrate Ability to Manually Operate Atmospheric Steam Dump Valves While Communicating W/Control Room Necessary

ML19312D545
Person / Time
Site:	North Anna
Issue date:	03/07/1980
From:	Parr O Office of Nuclear Reactor Regulation
To:	Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 8003240594
Download: ML19312D545 (5)

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NUCLEAR REGULATORY COMMISSION 3

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WASHINGTON, D. C. 20555 a

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Docket No. 50-339 MAR 0 71989 Mr. J. H. Ferguson Executive.Vice President - Power Operations Virginia Electric & Power Company P. O. Box 26666 Richmond, Virginia 23261

SUBJECT:

' REQUEST FOR ADDITIONAL INFORMATION To continue our review of your application for a license to operate the North Anna Power Station, Unit 2, additional information is required.

The information requested is described in the Enclosure.

Please infonn us after receipt of this letter of your schedule for providing the requested information.

Sincerely,

b. $w Olan

. Parr, Chief Light Water Reactors Branch flo. 3 Division of Project Management

Enclosure:

As Stated cc w/ enclosure:

See Next Page 1

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MAR 0 7 ggg i

Mr. J. H. Ferguson 2-cc: Mr. Anthony Gambaradella Clarence T. Kipps, Jr., Esq.

Office of the Attorney General 1700 Pennsylvania Avenue, N.W.

11 South 12th Street - Room 308 Washington, D. C.

20006 Richmond, Virginia :23219 Carroll J. Savage, Esq.

Richard M. Foster, Esq.

1700 Pennsylvania Avenue, N.W.

Musick, Williamson, Schwartz Washington, D. C.

20006 Leavenworth & Cope, P. C.

P. O. Box 4579 Mr. James C. Dunstan Boulder, Colorado 80306 State Corporation Comission Comonwealth of Virginia Michael W. Maupin, Esq.

Blandon Building Hunton, Williams, Gay & Gibson Richmond, Virginia 23209 P. O. Box 1535 Richmond, Virginia 23212 Alan S. Rosenthal, Esq.

Atomic Safety and Licensing Appeal Board

'Mrs. June Allen U.S. Nuclear Regulatory Commission 412 Owens Drive Washington, D. C.

20555 Huntsvil1e, Alabama 35801-1 Michael C. Farrar, Esq.

Mrs. James Torson Atomic Safety and Licensing Appeal Board 501 Leroy U.S. Nuclear Regulatory Comission Socorro, New Mexico 87801 Washington, D. C.

20555 Mrs. Margaret Dietrich Dr. John H. Buck Route 2, Box 568 Atomic Safety and Licensing Appeal Board P

Gordonsville, Virginia 22942 U.S. Nuclear Regulatory Comission Washington, D. C.

20555 William H. Rodgers, Jr., Esq.

Georgetown University Law Center Atomic Safety and Licensing Board Panel 600 New Jersey Avenue, N. W.

U.S. Nuclear Regulatory Comission Washington, D. C.

20001 Washington, D. C.

20555 Mr. Peter S. Hepp Mr. Michael S. Kidd Executive Vice President U.S. Nuclear Regulatory Comission Sun Shipping & Ory Dock Company P. O. Box 128 P. O. Box 540 Spots 1vania, Virginia 22553 Chester, Pennsylvania 19013 Dr. Paul W. Purdom Mr. R. B. Briggs-Department of Civil Engineering Associate Director Drexel University 110 Evans Lane Philadelphia, Pennsylvania 19104 Oak Ridge,. Tennessee 37830 l

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7 LMr. J. ' H. -- Ferguson '

MAR 0 7 gggg

cc:- Dr. Lawrence _R. Quarles Apartment No. 51.

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. Kendal-at-Longwood -

Kennett Square, Pennsylvania-19348

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3Mr.' Irwin B.'Kroot.

' Citizens Energy Forum P. 0.' Box 138

McLean, Virginia 22101

-James B. Dougherty, Esq.

. Potomac Alliance ~

1416 S Street, N.W.

Washington, D. C.

20009

.W. R. Cartwright, Station Manager P. O. Box 402 Hineral, Virginia 23117?

iW. L. Stewart, Manager P.:0.-Box-315-Surry, Virginia 23883 4

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.s Enclosure North Anna Power Station The Regulatory Requirements Review Committee, in a memorandum from E. Case, Committee Chairman, to L. Gossick, Ex eutive Director for i

Operations (dated February 16,1978), has appro. d a new staff position (BTP RSB 5-1) for the Residual Heat Removal Systec (RHR). The technical requirements for your plant are describa below. Flease respond to these l

requirements in sufficient detail to enable the staff to review your compliance j

in an expeditious fashion.

1.

Provide safety-grade steam generator dump valves, operators, air and power supplies which meet the single failure criteria.

' Provide a comitment to demonstrate the ability to manually operate the atmospheric steam dump valves and demonstrate the ability-to communicate with the control room while doing so.

2.

Provide the capability to cool down to the RHR cut-in point in less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> assuming the most limiting single failure and loss of offsite power or show that manual actions inside or outside containment or return to hot standby until the manual actions or maintenance can be performed to correct the failure provides an acceptable alternative.

3.

Provide the capability to depressurize the reactor coolant system with only safety-grade systems assuming a single failure and loss of offsite power or show that manual actions inside or outside containment or remaining at hot standby until manual actions or repairs are complete provides an acceptable alternative.

4.

Provide the capability for barating with only safety-grade systems assuming a single failure and loss of offsite power or show that manual actions inside or outside containment or remaining at hot standby until manual action or repairs are. completed provides an acceptable alternative.

5.

Provide a commitment to perform a natural circulation test (including the worst single failure) to demonstrate the ability to cooldown and depressurize the reactor coolant system and to demonstrate that boron mixing is sufficient under such circumstances. As an alternative to a test at North Anna pr6 vide justification of why the proposed Diablo Canyon natural circulation test is prototypic.of North Anna and is bounding. Any justification should include reasons why steam generator cooldown and upper head cooloff for North Anna will be accounted for in the Diablo Canyon test. Provide a commitment to run the natural circulation test at North Anna prior to startup following first refueling of Unit 2 if the Diablo Canyon test is not completed or does not provide satisfactory results during the first fuel cycle at North Anna Unit 2.

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C'ommit-td providing specific' procedures for cooling down using

' natural circulation and submit a summary of these procedures.

7.: Provide or require a seismic Category I AFW supply for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at Hot Shutdown plus cooldown to the DHR system cut-in based on the longest-time (for only onsite-or offsite power and assuming the worst single failure), or show that an adequate alternate seismic Category I source.will be available.

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Identify and discuss safety grade CVCS instrumentation needed for operator information during shutdown.

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