ML20035A174
| ML20035A174 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1993 |
| From: | Steven Bloom Office of Nuclear Reactor Regulation |
| To: | Tira Patterson OMAHA PUBLIC POWER DISTRICT |
| References | |
| TAC-M85116, NUDOCS 9303240223 | |
| Download: ML20035A174 (4) | |
Text
7 March 19, 1993 Docket No. S0-285 Mr. Terry L. Patterson Division Manager - Nuclear Operation Omaha Public Power District 444 South 16th Street Hall Mail Stop BE/EP 4 Omaha, Nebraska 68102-2247
Dear Mr. Patterson:
SUBJECT:
SPENT FUEL P0OL RERACK - REQUEST FOR ADDITIONAL INFORMATION (RAI)
FORT CALHOUN STATION, UNIT I (TAC NO. M85116)
By letter dated December 7,1992, you proposed revisions to amend Technical Specifications (TS) 2.8, 3.2 (Table 3-5), 4.4.2, 5.10.3, and Figure 2-10 of your TS. These changes will allow an increase in the number of spent fuel assemblies which may be stored in the spent fuel pool upon modification to the spent fuel pool storage racks. To continue our review we need additional information and a commitment from you. The commitment is to use Appendix A of Regulatory Guide DG-8006 if you use divers for the rerack. The enclosed t
questions and commitment were discussed by the NRC staff and your staff in a telecon on January 27, 1993.
As discussed during the telecon, we anticipate that your responses to our request for additional information (RAI) will be i
submitted within 4 weeks.
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If you have any questions abor + this matter, please do not hesitate to call me f
at (301) 504-1313. This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget review under Public Law 96-511.
Sincerely, ORIGINAL SIGNED BY:
Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
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c March 19, 1993 Docket No. 50-285 Mr. Terry L. Patterson Division Manager - Nuclear Operation Omaha Public Power District 444 South 16th Street Mall Mail Stop SE/EP 4 i
Omaha, Nebraska 68102-2247
Dear Mr. Patterson:
SUBJECT:
SPENT FUEL POOL RERACK - REQUEST FOR ADDITIONAL INFORMATION (RAI)
FORT CALHOUN STATION, UNIT 1 (TAC NO. M85116)
By letter dated December 7,1992, you proposed revisions to amend Technical Specifications (TS) 2.8, 3.2 (Table 3-5), 4.4.2, 5.10.3, and Figure 2-10 of your TS. These changes will allow an increase in the number of spent fuel assemblies which may be stored in the spent fuel pool upon modification to the spent fuel pool storage racks. To continue our review we need additional information and a commitment from you. The commitment is to use Appendix A of Regulatory Guide DG-8006 if you use divers for the rerack.
The enclosed questions and commitment were discussed by the NRC staff and your staff in a telecon on January 27, 1993. As discussed during the telecon, we anticipate that your responses to our request for additional information (RAI) will be submitted within 4 weeks.
i If you have any questions about this matter, please do not hesitate to call me at (301) 504-1313. This requirement affects fewer than 10 respondents and, i
therefore, is not subject to Office of Management and Budget review under Public Law 96-511.
7 Sincerely,
/l
-Q Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
RAI i
cc w/ enclosure:
See next page
'i Mr. Terry L. Patterson Omaha Public Power District fort Calhoun Station, Unit No. I CC:
Harry H. Voigt, Esg.
LeBoeuf, Lamb, Leiby & MacRae 1875 Connecticut Avenue, NW Washington, D.C.
20009-5728 Mr. Jack Jensen, Chairman r
Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Raymond P. Mullikin, Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 l
Rockville, MD 20852 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission i
611 Ryan Plaza Drive, Suite 1000 i
Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health 4
Nebraska Department of Health 301 Centennial Mall, South Post Office Box 95007 Liocoln, Nebraska 68509 Mr. James W. Chase, Manager Fort Calhoun Station Post Office Box 399 Fort Calhoun, Nebraska 68023 i
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ENCLOSURE i
1 QUESTIONS ON FORT CALHOUN RERACK 7
1.
The Holtec Licensing Report states that a moderator temperature of 4*C, i
corresponding to the maximum possible moderator density, was assumed for the criticality analysis to assure that the true reactivity will always be lower over the expected range of water temperatures. However, since the SCALE cross section library as used by NITAWL has scattering matrices only at 20 C and 277 C, explain how the reactivity at 4 C was obtained.
2.
The reactivity calculations for the use of control element assemblies (CEAs) inserted into fuel assemblies assumed that the CEA was depleted I
to 75% of its initial boron-10 loading for conservatism. What amount of depletion is anticipated for the cycle life of a typical CEA and what 1
amount of core insertion during CEA lifetime is this based on?
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3.
Proposed Technical Specification 2.8(12) requires a minimum boron concentration of 100 ppm in the spent fuel pool whenever storing unirradiated fuel in the pool. However, since credit is taken for soluble boron for accident conditions such as lateral motion of the rack modules under seismic conditions, should this technical specification require a minimum boron concentration in the spent fuel pool at all l
times?
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