ML20236S938

Forwards Request for Addl Info Re Licensee 980224 Request for Amend to Callaway TSs to Support Mod to Increase Sf Pool Capacity at Callaway Plant

ML20236S938
Person / Time
Site:	Callaway
Issue date:	07/23/1998
From:	Lyon C NRC (Affiliation Not Assigned)
To:	Randolph G UNION ELECTRIC CO.
References
TAC-MA1113, NUDOCS 9807270333
Download: ML20236S938 (4)

Text

w July 23,1998 '

Mr. Garry L'. Randolph ' ,

Vice President and Chief Nuclear Officer .

Union Electric Company Post Office Box 620 Fulton, Missouri _S5251.-

SUBJECT:

. REQUEST FOR ADDITIONAL INFORMATION (RAl) ~- UNION ELECTRIC COMPANY - CALLAWAY PLANT, UNIT 1 (TAC NO. MA1113)

Dear Mr. Randolph:

The NRC staff has reviewed Union Electric Company's request for an amendment to the

Callaway technical specifications dated February 24,1998, and its supplement dated May 27, 1998, to support a modification to increase the spent fuel pool capacity at the Callaway Plant.

. As a result of the review, the staff has determined that additionalinformation is needed to' complete the review. The information needed is detailed in the enclosure.

To assist the NRC staff in meeting its review schedule, we request that you respond to the RAl'

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in writing within 30 days of receipt of this letter.

If you have any questions, please contact me at (301) 415-2296. .

1 Sincerely, Cc4F.

, Carl F. Lyon, roject Manager Project Directorate IV-2'-

. Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation i

l Docket No. 50-483 DISTRIBUTION:

l Docket File ACRS, TWFN

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I Mr. Garry L. Randolph July 23,1998 cc:

Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. President and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855 Post Office Box 411 Burlington, Kansas 6683g John O'Neill, Esq.

Shaw, Pittman, Potts & Trowbridge Mr. Dan 1. Bolef, President 2300 N. Street, N.W. Kay Drey, Representative Washington, D.C. 20037 Board of Directors Coalition for the Environment Mr. H. D. Bono 6267 Delmar Boulevard Supervising Engineer University City, Missouri 63130 Quality Assurance Regulatory Support Union Electric Company Mr. Lee Fritz Post Office Box 620 Presiding Commissioner Fulton, Missouri 65251 Callaway County Court House 10 East Fifth Street U.S. Nuclear Regulatory Commission Fulton, Missouri 65151 Resident inspector Office 8201 NRC Road Mr. Alan C. Passwater, Manager Steedman, Missouri 65077-1302 Licensing and Fuels Union Electric Company Mr. J. V. Laux, Manager Post Office Box 6614g Quality Assurance St. Louis, Missouri 63166-614g Union Electric Company Post Office Box 620 Fulton, Missouri 65251 Manager- Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission ,

Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-6064 Mr. Ronald A. Kucera, Deputy Director

, Department of Natural Resources P.O. Box 176 Jefferson City, Missourl 65102

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l1 REQUEST FOR ADDITIONAL INFORMATION UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 L DOCKET NO. 50-483 "1. The May 27,1998, submittal states that administrative controls will be implemented to ensure that dose rates extemal to the building will meet the limits for the general public.

It also stat - that additional controls will be implemented to ensure that interior building dose rates are maintained within the ranges of the specified zone designations.

Describe what additional controls you will take to ensure that the current radiation zone designations are not exceeded. In addition to administrative controls, discuss the use of any bridge movement interlocks that may be used to control the placement of fuel assemblies in the fuel racks.

2. Your submittal states that you will install three spent fuel pool (SFP) racks (with a combined capacity of 279 fuel assemblies) in the cask loading pit in a later campaign.

Discuss how the presence of spent fuel in these racks will affect the dose rates in accessible areas adjacent to the cask loading pit both during storage and movement of the spent fuel assemblies into and out of the pit.

3. Describe any sources of high radiation that may be in the Callaway Plant SFP during diving operations to remove the old SFP racks and install the new racks. Discuss what j precautions (such as use of TV monitoring, tethers, etc.) will be used to ensure that the divers will maintain a safe distance from any high radiation sources in the SFP.

Describe how you plan to monitor the doses received by the divers during the raracking i operation (e.g., use of dosimetry, alarming dosimeters, remote readout radiation detectors).

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4. Provide the calculated 30 day doses (thyroid and whole body) to the control room operator as a result of a fuel handling accident (occurring both in the fuel handling building and in containment). Describe the calculational method used to arrive at these l doses and include all assumptions. Describe any differences that may exist between control room isolation following a fuel handling accident and control room isolation following a LOCA and describe how these differences would affect operator 30 day accident doses.

L 5. Verify that all of the assumptions used in the Final Safety Analysis Report (FSAR) fuel handling accident analysis are still applicable. Also verify that the resulting postulated thyroid and whole body doses at the Exclusion Area Boundary and Low Population

. Zone as a result of a fuel handling accident are still valid.

6. Discuss the shipment and disposal of the old spent fuel rack modules.

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7. Discuss how the storage of the additional spent fuel assemblies in the Callaway Plant SFP will affect the releases of radioactive gases (specifically Kr-85,1-131 and tritium) from the SFP.

8. Discuss how the storage of the additional spent fuel assemblies will affect the releases of radioactive liquids from the plant.

9. Discuss your plans to use a vacuum to remove any crud or other debris from the floor of the SFP before and during the SFP reracking project. Also describe any radiation surveys that will be performed (from the pool rim or by divers in the pool) to map dose rates in the SFP.

10. Is full core off-load the general practice for planned refueling outages?

11. If full core off-load is the general practico, then the corresponding heat load is the one considered for normal operation. Table 5.8.1 states that for the postulated full core discharge, the maximum allowable haat load is 63.41 MBtu/hr, which corresponds to a maximum bulk SFP temperature of 170*F. This limit exceeds the American Concrete Institute (ACl) Standard 379, which states in part, "for normal operation or any other long term period, the [SFP) temperatures shall not exceed 150 degrees." If the planned refueling is generally a full core off-load, provide an evaluation on how long the SFP temperature would be above 150*F, and the justification for why the 170'F limit is acceptable to meet the intent of ACI-379.

12. Is there a procedure for performing the outage specific evaluation of heat load? What value is used for the maximum pool heat load?

13. Discuss sources and capacities of make-up water and the methods / systems (indicating

. seismic design category) used to provide make-up water, as well as the time needed to set up a path for make-up water to the SFP.

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14. The February 24,1998, subrnittal stated that additional racks will be placed within the cask loading pit during a later campaign. When do you anticipate installing these cask loading pit racks? Would newly off-loaded fuel be placed in the cask loading pit? If not, what controls would be in place to ensure that newly off-loaded fuel would not be placed in the cask loading pit? How do you ensure that sufficient cooling is provided to the fuel located in the cask loading pit?

15. With regard to the FLUENT 3D model, what are the model assumptions? Was a sensitivity study done with regard to the different physics and correlations options? Has the model been proven to be grid independent?

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