ML15348A260
| ML15348A260 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire  |
| Issue date: | 12/17/2015 |
| From: | Geoffrey Miller Plant Licensing Branch II |
| To: | Zaremba A Duke Energy Carolinas |
| Miller G | |
| References | |
| TAC MF6480, TAC MF6481, TAC MF6482, TAC MF6483, TAC MF6484, TAC MF6485, TAC MF6486 | |
| Download: ML15348A260 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Arthur Zaremba Nuclear CFAM - Regulatory Affairs Duke Energy Carolinas, LLC Mail Code EC2ZF/P.O. Box 1006 Charlotte, NC 28201-1006 December 17, 2015
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2; MCGUIRE NUCLEAR STATION, UNITS 1 AND 2; AND OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO USE AN ALTERNATE FISSION GAS GAP RELEASE FRACTION (TAC NOS. MF6480, MF6481, MF6482, MF6483, MF6484, MF6485 AND MF6486)
Dear Mr. Zaremba:
By letter dated July 15, 2015 (Agencywide Documents Access and Management System Accession No. ML15196A093), Duke Energy Carolinas, LLC, license amendment requires to use a new set of fission gas gap release fractions for high burnup fuel rods that exceed the linear heat generation rate limit detailed in Regulatory Guide 1.183, Table 3, Footnote 11.
The U.S. Nuclear Regulatory Commission staff has reviewed the submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On December 10, 2015, you indicated that a response to the RAI would be provided by within 45 days from the date of this letter.
If you have any questions, please call me at 301-415-2481.
Sincerely, 1
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G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413, 50-414, 50-369, 50-370, 50-269, 50-270, and 50-287
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION CATAWBA NUCLEAR STATION, UNITS 1 AND 2 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 LICENSE AMENDMENT REQUEST ALTERNATE FISSION GAS GAP RELEASE FRACTIONS DOCKET NOS. 50-413 AND 50-414 DOCKET NOS. 50-369 AND 50-370 DOCKET NOS. 50-269, 50-270, AND 50-287 By letter dated July 15, 2015 (Agencywide Documents Access and Management System Accession No. ML15196A093), Duke Energy Carolinas, LLC, license amendment requires to
- use a new set of fission gas gap release fractions for high burnup fuel rods that exceed the linear heat generation rate limit detailed in Regulatory Guide 1.183, Table 3, Footnote 11. In order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review of the request, the following additional information is requested.
ARCB-RAl-1
\\_
For those changes to the current licensing basis (CLB) parameters used in the affected dose consequence analyses provide additional information describing, for each affected design basis accident, all the basic parameters used in the dose consequence analyses. For each parameter, please indicate; the CLB value, the revised value where applicable, the basis for any changes made to the CLB values, and the applicable reference location within either the Updated Final Safety Analysis Report or Technical Specifications. If possible, the NRC staff requests that this information be presented in separate tables for each accident evaluated.
ARCB-RAl-2 Appendix B of RG 1.183, Regulatory Position 1.1 states:
"The number of fuel rods damaged during the accident should be based on a conservative analysis that considers the most limiting case. This analysis should consider parameters such as the weight of the dropped heavy load or the weight of a dropped fuel assembly (plus any attached handling grapples), the height of the drop, and the compression, torsion, and shear stresses on the irradiated fuel rods. Damage to adjacent fuel assemblies, if applicable (e.g., events over the reactor vessel), should be considered."
Enclosure Please explain how the revised fuel handling accident analysis determines the most limiting case, and how it shows that the limiting case is not the drop of an object other than an irradiated fuel assembly.
ML15348A260 RidsNrrPMOconee Resource RidsNrrLASFigueroa Resource RidsRgn2MailCenter Resource
- via e-mail OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRO/DRA/ARCB/BC N RR/LPL2-1 /BC NAME GEMiller SFigueroa UShoop*
MMarkley DATE 12/15/15 12/15/15 11/25/15 12/17/15