ML19248D647
| ML19248D647 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/30/1979 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7908170127 | |
| Download: ML19248D647 (4) | |
Text
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[ [,.,, ( (,'o, UNITED STATES j
NUCLEAR REGULATORY COMMISSION y
WASM NGTON, D. C. 20555
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s.,.sj JUL 3 01979 Docket No. 50-339 Mr. W. L. Proffitt Senior Vice President - Power Operations Virginia Electric & Power Company P. O. Box 26666 Richmond, Virginia 23261 Dear Mr. Proffitt
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 infomation is required.
The information requested is described in the Enclosure.
To maintain our licensing review schedule, we will need a completely adequate response to the enclosed request by August 10, 1979.
Please infom us after receipt of this letter of your confirmation of the above date or the date you will be able to meet.
Sincerely, D
Olan D. Parr., Chief Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
Request for Additional Information cc w/ enclosure:
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See next page 790817otA
- 3,
Mr. W. L. Proffitt JUL 3 01979 cc: Mr. Anthony Gambaradella Cl arence T. Ki pps, Jr., Esq.
[
Office of the Attorney General 1700 Pennsylvania /wenue, LW.
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.
211 Stribling Avenue Washington,D. C.
20006 Charlottesville, Virginia 22903 Mr. James C. Dunstan Michael W. Maupin, Esq.
State Corporation Comission Hunton, Williams, Gay & Gibson Comonwalth of Virginia P. O. Box 1535 Blandon Building Richmond, Virginia 23212 Richmond, Virginia 23209 Mrs. June Allen Alan S. Rosenthal, Esq.
412 Owens Drive Atomic Safety and Licensing Appeal Board Hantsville, Alabama 35801 U.S. Necicar Regulatory Comission Washington,V. C.
20555 W. James Torson 501 Leroy Michael C. Ferrar, Esq.
j Socorro, New Mexico 87801 Atomic Safety and Licensing Appeal Board g
U,5, Nuclear Regulatory Comission Mrs. Margaret Dietrich Lshington, D. C.
20555 l
Route 2, Box 568 i
Gordonsville, Virginia 22942 Dr. John H. Buck i
Atomic Safety and Licensing Appeal Board I
Willi am H. Rodgers, Jr., Esq.
U.S. Nuclear Regulatory Comission Georgetow. thiversity Law Center Washington, D. C.
20555
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600 New Jersey Avenue, N'.W.
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Washington,D. C.
20001 Atomic Safety and Licensing Board Panel i
U.S. Nuclear Regulatory Comission W. Peter S. Hepp Washington, D. C.
20555 f'
Executive Vice President Sun Shipping & Dry Dock Company Mr. Michael S. Xidd P. O. Box 540 U.S. Nuclear Regulatory Comission Chester, Pennsylvania 19013 P. O. Box 128
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Spotslvania, Vi rginia 22553 Associate Director Dr. Paul W. Purdom i
110 Evans Lane Department of Civil Engineering i
Oak Ridge, Tennessee 37830 Drexel University Philadel phia, Pennsylvania 19104 i
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Mr. W. L. Proffitt JUL 3 01979 cc:
Dr. Lawrence R. Quarles Apartment ho. 51 Kenoa l-a t-Longwood Kennett Square, Pennsylvania 19348 Mr. Irwin B. Kroot Citizens Energy Forum P. O. Box 138 McLean, Vi rginia 22101 James 8. Dougherty, Esq.
Potomac Alliance P. O. Box 9306 Washington, D. C.
20005 f
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e ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION NORTH ANNA POWER STATION, UNIT 2 DOCKET NO. 50-339 4.0 REACTOR 4.1 ',
The fission gas release n.odel in the approved Westinghouse fuel performance code (North Anna Unit 2 reference 5) has been found to underpredict gas release from fuel pellets at high burnup, >20,000 mwd /tU.
The effects of higher fission gas release on the safety analyses for North Anna 2 should be evaluated using either (li the approsed per formance code in combination with the NRC correction method or (2) a revised performance code which suitably models the increased fission gas release.
4.15 Westinghouse has documented in WCAP-8963 a change in the internal fuel rod gas pressure criteria. Will tiie fuel design criterion for North Anna Unit 2 incorporate this change for rod pressure? If so, provide the criterion as modified by NRC review, the above noted reference, and a reanalysis in the FSAR of affected evaluations.
4.16 During a recent refueling outage at a W plant (Salem 1), strap damage t
was observed on a number of the fuel spacer grids.
It is not known whether the damage occurred during the initial core loading or during the refueling withdrawal. What assurances can you provide that the same type of grid damage will not be experienced at North Anna Unit 2?
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