ML20136H180

Forwards Request for Addl Info Re 850506 Request for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & in Spent Storage Pool.Info Requested by 850826

ML20136H180
Person / Time
Site:	Grand Gulf
Issue date:	08/09/1985
From:	Adensam E Office of Nuclear Reactor Regulation
To:	Richard J MISSISSIPPI POWER & LIGHT CO.
References
TAC-57619, NUDOCS 8508200217
Download: ML20136H180 (4)

Text

DISTRIBUTION:

C Docket;No.._50-416 T P NRC PDR local PDR Docket No. 50-416 PRC System LB #4 r/f EAdensam Mr. Jackson B. Richard LKintner Senior Vice President, Nuclear

- MDuncan Mississippi Power and light Company JRidgely P.O. Box 23054 Attorney, OEl.D Jackson, Mississippi 39205 JPartlow BGrimes

Subject:

Grand Gulf Nuclear Station Unit 1 - EJordan High Density Spent Fuel Racks 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 pool 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 26, 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.

Origin [ Signed by

. Kintner E or G. Adensam, Chief licensing Branch No. 4 Division of licensing

Enclosure:

As stated cc: See next page DL:LB #4 1.A:g:h#4 DL:lB #4 1 1.Kintner/hmc M0uncan EAdensam i 8/P/85 8/}/85 h/f/85 8508200217 850009 PDR ADOCK 05000416 P PDR

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Mr. Jackson B. Richard Mississippi Power & Light Company Grand Gulf Nuclear Staiton i  !

l cc:

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

i Wise, Carter, Child, Steen and Caraway Attorney General l P.O. Box 651 Department of Justice l Jackson, Mississippi 39205 State of Louisiana l Baton Rouge, Louisiana 70804 L 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 ,

l Jackson, Mississippi 39205 j Mr. Ralph T. Lally Manager of Quality Assurance Office of the Governor Middle South Services, Inc. State of Mississippi 4

P.O. Box 61000 Jackson, Mississippi 39201 New Orleans, Louisiana 70161 Attorney General

Mr. Larry F. Dale, Director Gartin Building i 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 i Gaithersburg, Maryland 20760 Alton B. Cobb, M.D.

! State Health Officer j Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Commission Jackson, Mississippi 39205 j

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 Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323

- Mr. J. E. Cross, General Manager i Grand Gulf Nuclear Station i.- Mississippi Power & Light Company

! P.O. Box 756 l

Port Gibson, Mississippi 39150 i

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ENCLOSURE L REQUEST FOR ADDITIONAL INFORMATION GRAND GULF UNIT 1 l

SPENT FUEL POOL CAPACITY EXPANSION l l

1. Operating license condition 2.C.28 states, in part, that "No '

irradiated fuel may be stored in the Unit i spent fuel pool prior to completion of modifications to the standby service water (SSW). system and verification that the design flow can be achieved to all SSW system components. ... Until the SSW system is modified, the spent fuel pool cooler shall be isolated from the SSW ' system by locked closed valves. The position of these valves shall be verified every 31 days until the design flowrate for (the) SSW system is demonstrated." Provide a dis-cussion, PLIDs, and a schedule of completion for the modifica-tions to 1) satisfy license condition 2.C.28 and 2) remove the additional heat load imposed by the proposed Ancreased storage capacity of the spent fuel pool. Note: the increased heat loads used for sizing the SSW system should conform to the results of Question 2 below.

2. The calculated . spent fuel- decay heat loads identified in the submittal did not follow the guidelines of the Standard Review Plan (NUREG - 0800) Section 9.1.3 and Branch Technical Position ASB 9-2. The heats loads provided in the submittal are not conservative with respect to those calculated by using the afore-mentioned references and therefore the licensee's calculations are not acceptable. Provide the results of revised calculations which use the aforementioned references.

3. Specify the overall heat transfer rate (BTU /Hr-ft2 -F) for the L" spent fuel pool cooling system's heat exchanger. If the heat transfer rate. is similar to- that of'the RHR heat exchanger, then the spent fuel pool cooling-system should be re-evaluated to assure that the- spent fuel pool water temperature does not exceed ,140-F for- normal heat load conditions and the single -

failure of one spent fuel pool cooling system train. Reliance on the RHR system for normal refueling heat loads is not accept-able. .

4. Verify that FSAR Figure 9.1-26-(Amendment 52) is still applicable I. in that it shows two heat exchangers and pumps whereas Figure 5.1.1.of the May 6th submittal indicates one heat exchanger.

. 5. Section 5.1.1 of the submittal states that "The upper contain-

{, ment pool does not contain any fuel while the plant is operat-ing." Verify that this means that no spent fuel will be-in 1

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the upper . containment pool in any operating mode other than l

the refueling mode.

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6. With respect to a gate drop accident, it is not clear whether- l damage to any fuel bundles has been assumed. Since the fuel bundle handles extend above the top of the racks (Refer to sub- l mittal Figure 3.6), it should be assumed that the gate will l impact the top of the fuel bundles. Therefore, provide the l results of an analysis of the. consequences of damaging the I maximum number of fuel bundles that can be hit with the gate's l

" smallest cross-sectional dimension" and also those hit by the  ;

I gate rotating and landing on the side with the " largest cross-sectional dimension". ,

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