ML061780576
| ML061780576 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/27/2006 |
| From: | Joseph Sebrosky NRC/NMSS/SFPO |
| To: | Ridenoure R Omaha Public Power District |
| Sebrosky J, NRC/NMSS 301-415-1132 | |
| References | |
| TAC L23984 | |
| Download: ML061780576 (5) | |
Text
June 27, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FORT CALHOUN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
(TAC. NO. L23984)
Dear Mr. Ridenoure:
By letter dated June 9, 2006, Omaha Public Power District (OPPD) submitted a request for exemption from Certificate of Compliance (CoC) No. 1004 for the Fort Calhoun Station independent spent fuel storage installation (ISFSI). The exemption request includes exemptions from Technical Specifications (TSs) 1.2.1, 1.2.11, and 1.2.17a associated with CoC No. 1004 for the Standardized NUHOMS design. The exemption request also includes an exemption from 10 CFR 72.48(c)(2)(viii) to use a method of thermal analysis that is a departure from the methodology described in the Standardized NUHOMS updated final safety analysis report. In my letter to you dated June 14, 2006, I acknowledged receipt of your amendment request and provided a proposed schedule for our review.
In connection with the staffs review, we need the information identified in the enclosure to this letter. We request that you provide this information by July 3, 2006. Inform us at your earliest convenience, but no later than July 3, 2006, if you are not able to provide the information by that date. To assist us in re-scheduling your review, you should include a new proposed submittal date and the reasons for the delay.
Please reference Docket No. 72-54 and TAC No. L23984 in future correspondence related to this request. The staff is available to meet to discuss your proposed responses. If you have any questions regarding this matter, I may be contacted at (301) 415-1132.
Sincerely,
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos. 72-54, 50-285 cc: Mailing List
Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FORT CALHOUN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
(TAC. NO. L23984)
Dear Mr. Ridenoure:
By letter dated June 9, 2006, Omaha Public Power District (OPPD) submitted a request for exemption from Certificate of Compliance (CoC) No. 1004 for the Fort Calhoun Station independent spent fuel storage installation (ISFSI). The exemption request includes exemptions from Technical Specifications (TSs) 1.2.1, 1.2.11, and 1.2.17a associated with CoC No. 1004 for the Standardized NUHOMS design. The exemption request also includes an exemption from 10 CFR 72.48(c)(2)(viii) to use a method of thermal analysis that is a departure from the methodology described in the Standardized NUHOMS updated final safety analysis report. In my letter to you dated June 14, 2006, I acknowledged receipt of your amendment request and provided a proposed schedule for our review.
In connection with the staffs review, we need the information identified in the enclosure to this letter. We request that you provide this information by July 3, 2006. Inform us at your earliest convenience, but no later than July 3, 2006, if you are not able to provide the information by that date. To assist us in re-scheduling your review, you should include a new proposed submittal date and the reasons for the delay.
Please reference Docket No. 72-54 and TAC No. L23984 in future correspondence related to this request. The staff is available to meet to discuss your proposed responses. If you have any questions regarding this matter, I may be contacted at (301) 415-1132.
Sincerely,
/RA/
Joseph M. Sebrosky, Senior Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos. 72-54, 50-285 cc: Mailing List Distribution:
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SFPO SFPO SFPO SFPO NAME:
JSebrosky EZiegler SHelton LCampbell RShewmaker RNelson MRahimi for DATE:
6/27/06 6/26/06 6/26/06 6/26/06 6/27/06 6/26/06 OFFICIAL RECORD COPY
Ft. Calhoun Station, Unit 1 Service List cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1700 K Street, N.W.
Washington, DC 20006-3817 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FORT CALHOUN STATION DOCKET NUMBER 72-54 By letter dated June 9, 2006, Omaha Public Power District (OPPD) submitted a request for exemption from Certificate of Compliance (CoC) No. 1004 for the Fort Calhoun Station independent spent fuel storage installation (ISFSI). The exemption request includes exemptions from Technical Specifications (TSs) 1.2.1, 1.2.11, and 1.2.17a associated with CoC No. 1004 for the Standardized NUHOMS design. The exemption request also includes an exemption from 10 CFR 72.48(c)(2)(viii) to use a method of thermal analysis that is a departure from the methodology described in the Standardized NUHOMS updated final safety analysis report. This request for additional information (RAI) identifies additional information needed by the U.S. Nuclear Regulatory Commission (NRC) staff in connection with its review of the application.
Each individual RAI describes information needed by the staff for it to complete its review of the application and/or the safety analysis report (SAR) to determine whether the applicant has demonstrated compliance with the regulatory requirements.
RAI-1
State the minimum cooling time of the assemblies that will be loaded under this exemption request.
The summary of the key parameters for Fort Calhoun Stations CE 14x14 fuel, provided in Table 1 of Attachment 1 of the exemption request, lists a number of fuel parameters, excepting the minimum cooling time of the assemblies.
This information is necessary to ensure that the dose rates in TS 1.2.11 are not exceeded and to satisfy the requirements of 10 CFR 72.44(c)(1), 72.106, and 72.126.
RAI-2
Clarify whether the OS197L transfer cask (TC) surface dose rate, 13 rem/hr, given on Page 12 of Attachment 1 of the exemption request is the maximum or average surface dose rate.
Transnuclear, Inc. Calculation No. 1121-0505, which determines the radiation dose rates around the OS197L TC in support of the exemption request, states in Section 6.2 that 13 rem/hr is the maximum TC surface dose rate. However, Page 12 of Attachment 1 states that 13 rem/hr is the average TC surface dose rate.
This information is necessary to satisfy the requirements of 10 CFR 72.11 and 72.106.
RAI-3
Clarify whether the reference to Chapter 11 of the updated final safety analysis report (UFSAR) in the Accident Analysis section on page 18 of Attachment 1 of the exemption request is actually a reference to Chapter M.11 of the UFSAR.
The discussion in this section pertains to prior accident analyses performed for the OS197 and the OS197L TCs. Chapter 11 of the UFSAR pertains to quality assurance. Chapter M.11 of the UFSAR contains the accident analysis of the OS197.
This information is necessary to satisfy the requirements of 10 CFR 72.11.
RAI-4
OPPD should justify why the trailer shieldings impact on the structural response of the TC is not considered as creating the possibility for an accident of a different type than any previously evaluated in the UFSAR (10 CFR 72.48(c)(2)(v)).
OPPDs exemption request Attachment 2 page 95 section W.11.1.4 discusses the loss of neutron shield. This section evaluates, from a radiological perspective, the loss of the neutron shield and also postulates the loss of the trailer shielding. This evaluation does not include an evaluation of the structural impact the trailer shielding may have on the TC. For example, it is the staffs understanding that the 3 inch top shield is placed using a crane that is not single failure proof. OPPD does not evaluate the results dropping this shielding would have on the TC. In addition, TN does not evaluate the impact the additional transfer trailer shielding would have on the 80 inch accidental drop analysis discussed in Section W.11.1.3 of Attachment 2.
This information is necessary to satisfy the requirements of 10 CFR 72.48(c)(2)(v).