ML20065N030
| ML20065N030 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/18/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 331A, NUDOCS 8210220011 | |
| Download: ML20065N030 (3) | |
Text
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VINGINIA ELECTRIC AND Powan CoxPANY RIcnnown, VIMUIMIA 20261 R.H.LeAssono October 18, 1982 Vace Pamespawr Neca. man ormeATsons Mr. Harold R. Denton, Director Serial No. 331A Office of Nuclear Reactor Regulation PSE&C/HSM:acm Attn:
Mr. Robert A. Clark, Chief Docket Nos. 50-338 Operating Reactors Franch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:
ADDITIONAL INFORMATION PROPOSED OPERATING LICENSE AMENDMENT NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 In our letter of July 13, 1982, Serial No. 331, Vepco requested an amendment to Operating Licenses NPF-4 and NPF-7 to allow the receipt and storage of 500 spent fuel assemblies from Surry Power Station Unit Nos. I and 2 in the North Anna Power Station Unit Nos. I and 2 spent fuel pool.
In support of this request, we forwarded the report, " Summary of Information in Support of the Storage of Surry Spent Fuel at North Anna Power Station Unit Nos. I and 2".
We have identified two items in this report which trust be corrected..
In our report, we identify the number of storage locations in the proposed Neutron Absorber Spent Fuel Storage Rack as 1748 storage locations.
This number has since been changed to 1737 storage locations during the refinement of the spent fuel rack design.
The other change is in Table 7-1 which is a tabulation of fuel pool temperatures for different heat load cases.
The actual temperature changes are minor. A new Table 7-1 is therefore attached.
Neither of the changes cause any change in the safety analysis or the conclusion of the safety analysis for the proposed Operating License-Amendments.
If further information is required on this matter, we would be pleased to meet with your staff at their convenience.
Very truly yours, R. H. Leasburg Aool i
B210220011 821018 PDR ADDCK 05000338 P
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l Vimoin A Es.scTaic Awo Powsm Courawv To Harold R. Denton i
Attachment:
j Table 7-1 " Spent Fuel Pool Cooling System Heat Load and Operating Temperatures with Storage of Surry Spent Fuel in the North Anna 1 and 2 Fuel Pool" l
cc:
Mr. James P. O'Reilly Regional Administrator Region II U. S. Nuclear Regulatory Commission Atlanta, Georgia 30303 F
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TABLE 7-1 (Rev. 1)
SPENT FUEL P0OL COOLING SYSTEM HEAT LOAD AND OPERATING TEMPERATURES WITH STORAGE OF SURRY SPENT FUEL i
Ih THE NORTH ANNA l AND 2 FUEL P0OL Fuel Pool Temperature, OF Decay Heat MRTU/HR 1P2C 2P2C No Surry Fuel High Density Racks (966)
Normal 19.4 13F.4 130.4 Abnormal 35.9 169.5 154-0 No Surry Fuel Neutron Absorber Racks (1737)
Normal 23.1 138.5 135.0 Abnormal 39.2 156.5 151.0 Surry Fuel (500)
High Density Racks (966)
Normal 20.5 136.0 132.5 Abnormal 36.3 153.0 147.5 Surry Fuel (500)
Neutron $hs>rberRacks(1737)
N No ial-
.24.1 140.0 136.0 Abnormal
- 40.0 160.0 148.5 1P2C - 1 Pump 2 Coolers 2P2C - 2 Pumps 2 Coolers y