ML20133A178

Forwards Request for Addl Info Re Application to Amend License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & Spent Fuel Storage Pool.Info Requested by 850815

ML20133A178
Person / Time
Site:	Grand Gulf
Issue date:	07/26/1985
From:	Adensam E Office of Nuclear Reactor Regulation
To:	Richard J MISSISSIPPI POWER & LIGHT CO.
References
TAC-57619, NUDOCS 8508050366
Download: ML20133A178 (3)

Text

'

{

July 26, 1985 DISTRIBUTION:

eDocket-Non 50-416.

NRC'PDR'i Docket No. 50-416 Local PDR PRC System LB #4 r/f Mr. Jackson B. Richard EAdensam Senior Vice President, Nuclear MDuncan Mississippi Power and Light Company 1.Kintner P.O. Box 23054 WBrooks Jackson, Mississippi 39205 Attorney, OELD JPartlow

Subject:

Grand Gulf Nuclear Station Unit 1-BGrimes High Density Spent Fuel Racks EJordan ACRS (16)

Dear Mr. Richard:

The NRC staff is reviewing the Mississippi Power and Light Company submittal dated May 6,1985, which requests an amendment to Grand Gulf Unit I license to allow installation of high density spent fuel racks in the upper containment pcol and in the spent fuel storage pool. The staff finds that the additional information described in the enclosure is needed to complete the review.

In order to meet the schedule for completion of this review, you are requested to provide the information described in the enclosure by August 15, 1985.

If you cannot meet this date you should advise the NRC Project Manager for Grand Gulf licensing actions, L. L. Kintner, within 7 days of receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Dar S. Hood Elin r G. Adensam, Chief nsing Branch No. 4 Division of Licensing

Enclosure:

As stated cc:

See next page

$#4 L

LA:p6kB#4 DL:LB #4 DL:L LKintner/hmc MDunbaii EAdensam 7/y85 7/p/85 7/ /85 K SN16 M

P pg

,6 Mr. Jackson B. Richard Mississippi Power & Light Company Grand Gulf Nuclear Staiton cc:

Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Mr. Oliver D. Kingsley, Jr.

and Reynolds Vice President, Nuclear Operations 1200 17th Street, N.W.

Mississippi Power & Light Company Washington, D. C.

20036 P.O. Box 23054 Jackson, Mississippi 39205 Mr. Ralph T. Lally Manager of Quality Assurance Office of the Governor Middle South Services, Inc.

State of Mississippi P.O. Box 61000 Jackson, Mississippi 39201 New Orleans, Louisiana 70161 Attorney General Mr. Larry F. Dale, Director Gartin Building Nuclear Licensing and Safety Jackson, Mississippi 39205 Mississippi Power & Light Company P.O. Box 23054 Mr. Jack McMillan, Director Jackson, Mississippi 39205 Solid Waste Mississippi State Board of Health Mr. R. W. Jackson, Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Maryland 20760 Alton B. Cobb, M.D.

State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Connission Jackson, Mississippi 39205 Route 2, Box 399 Port Gibson, Mississippi 39150 President Claiborne County Board of Supervisors Regional Administrator, Region II Port Gibson, Mississippi 39150 U.S. Nuclear Regulatory Connission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. J. E. Cross, General Manager Grand Gulf Nuclear Station Mississippi Power & Light Company P.O. Box 756 Port Gibson, Mississippi 39150 l

, y l

Enclosure REQUEST FOR ADDITIONAL INFORMATION -

GRAND GULF SPENT FUEL P0OL EXPANSION The proposed acceptance criterion for storage in the racks is that the K of a fuel assembly shall not be greater than 1.395 when calculated at the most reactive point in the assembly life in the core geometry at a temperature of 20 C.

This K. value is based on a calculations with a fresh 8 X 8-2 water rod assembly having uniform enrichment in the remaining rods. There are two sources of bias or uncertainty in this calculation which have not been treated. First is the effect on the rack K= of different assembly designs having the same value of K. as calculated for the core geometry. The second source (presumably a bias) arises from the fact that the values of K-assigned to the reload fuel will presumably be those provided by the fuel vendor (General Electric, e.g.) and calculated by their methods, which are different from the ones used to obtain the 1.395 value.

Please provide a discussion of these phenomena to address the magnitude of the uncertainties involved or to support a conclusion that the analyses provided are conservative.

1

__.