ML20236T497
| ML20236T497 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/23/1998 |
| From: | Lyon C NRC (Affiliation Not Assigned) |
| To: | Maynard O WOLF CREEK NUCLEAR OPERATING CORP. |
| References | |
| TAC-MA1294, NUDOCS 9807280221 | |
| Download: ML20236T497 (4) | |
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A.i July;23, 1998 4
' Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 '
- Burlington, Kansas 66839
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI)- WOLF CREEK
' NUCLfSR OPERATING CORPORATION - WOLF CREEK NUCLEAR GENERATING STATION, UNIT 1 (TAC NO. MA1294)
Dear Mr. Maynard:
The NRC staff has reviewed Wolf Creek Nuclear Operating Corporation's request for an amendment to the Wolf Creek technical specifications dated March 20,1998, and its supplement dated May 28,1998, to support a modification to increase the spent fuel pool capacity at the Wolf Creek Nuclear Generating Station. As a result of the review, the staff has
, determined that additional information 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 RAI in writing within 30 days of receipt of this letter, a
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- If you have any questions,' please contact me at (301) 415-2296..
Sin Carl F. Lyon, Pfoject Manager Project Directorate IV-2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
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Docket No. 50-482 DISTRIBUTION:
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Enclosure:
Request for Additional-PUBlIC PDIV-2 Reading Information -
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Mr. Otto L. Maynard July 23,1998 1
I cc:
Jay Silberg, Esq.
Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the Govemor State of Kansas Topeka, Kansas 66612 Attomey General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building ?S3 Topeka, Kansas 66620 O
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REQUEST FOR ADDITIONAL INFORMATION WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK NUCLEAR GENERATING STATION. UNIT 1 DOCKET NO. 50-482 1.
The May 28,1998, 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 states that additional controls will be implemented to ensure that !nterior building dose rates are maintained within the ranges of the specifed 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 Wolf Creek Plant SFP during diving operations to remove the old SFP racks and install the new racks. Discuss what precautions (such as use of TV monitoring, tethers, etc.) will be used to ensure that the c'ivers will maintain a safe distance 1 rom any high radiation sources in the SFP.-
Describe how you plan to monitor me doses received by the divers during the reracking operation (e.g., use of dosimetry, alarming dosimeters, remote readout radiation detectors).
4.
Provide the calculated 30 day doses (thyroid and whole body) to the control room
. operator as a result of a fuel handling g.ccident (occurring both in the fuel handling building and in containment). Describe the calculational method used to arrive at these doses and include all assumptions. Dcscribe 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.
5.
Veriff that all of the assumptions used in the final Safety Analysis Report (FSAR) fuel handling accident analysis are still applicable. Also verify that the resultirsg postulated thyroid and whole body doses at the Exclusion Area Boundary and Low Population Zone f-as a res, ult of a fuel handling accident are still valid.
6.
Discuss the sh!pment and disposal cf the oxf spent fuel rack modules.
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Discuss how the storage of the additional spent fuel assemblies in the Wolf Creek Station 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 tne 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 raracking 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 practice, 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 heat load is 63.41 MBtu/hr, which corresponds to a j
maximum bulk SFP temperature of 170*F. This limit exceeds the American Concrete l
Institute (ACl) Standard 379, which states in part, "for normal operation or any other j
long term period, the [SFP) temperatures shall not exceed 150 degrees.". 4 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 ACl-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.
14.
The March 20,1998, submittal 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.
Wkh regard to the FLUENT 3D rnodel, 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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