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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 25, 2012 David A. Heacock Dominion Energy Kewaunee, Inc. Innsbrook Technical Center 5000 Dominion Blvd. Glen Allen, VA 23060-6711 KEWAUNEE POWER STATION -CLOSEOUT OF INFORMATION REQUEST PURSUANT TO 50.54(f) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 25, 2012 David A. Heacock Dominion Energy Kewaunee, Inc. | ||
-FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION (TAC NO. ME8205) | Innsbrook Technical Center 5000 Dominion Blvd. | ||
Glen Allen, VA 23060-6711 | |||
==SUBJECT:== | |||
KEWAUNEE POWER STATION - CLOSEOUT OF INFORMATION REQUEST PURSUANT TO 50.54(f) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE - FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION (TAC NO. ME8205) | |||
==Dear Mr. Heacock:== | ==Dear Mr. Heacock:== | ||
By letter dated February 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120410195), the U.S. Nuclear Regulatory Commission (NRC) issued a letter in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(f). | |||
Pursuant to this regulation, the NRC staff requested that you provide further information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation, on peak cladding temperature in the Westinghouse-furnished realistic emergency core cooling system evaluation models. The requested information would enable the NRC staff to determine compliance with the Kewaunee Power Station (KPS) licensing basis, which includes the requirements of 10 CFR 50.46(a)(3)(ii), concerning the reporting of errors and changes to the emergency core cooling system evaluation model. Specifically, the subject letter required that you provide information within 30 days of February 16, 2012, to address the following issues: An estimation of the effect of the thermal conductivity degradation error on the peak fuel cladding temperature calculation for the emergency core cooling system evaluations at KPS. A description of the methodology and assumptions used to determine the estimates. | By letter dated February 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120410195), the U.S. Nuclear Regulatory Commission (NRC) issued a letter in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(f). Pursuant to this regulation, the NRC staff requested that you provide further information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation, on peak cladding temperature in the Westinghouse-furnished realistic emergency core cooling system evaluation models. The requested information would enable the NRC staff to determine compliance with the Kewaunee Power Station (KPS) licensing basis, which includes the requirements of 10 CFR 50.46(a)(3)(ii), | ||
This description shall include consideration of experimental data relevant to thermal conductivity degradation and specific information regarding any computer code model changes which were necessary to address these data. By letter dated March 15, 2012 (ADAMS Accession No. ML12079A287), you submitted a response to the 10 CFR 50.54(f) information request for KPS. The NRC staff has reviewed your submitted information and determined that for KPS your response provides the information required to be responsive to the issues discussed above. In addition, the NRC staff determined that your response, which included a report pursuant to 10 CFR 50.46(a)(3)(ii), demonstrates that your facility has complied with the applicable reporting requirements. | concerning the reporting of errors and changes to the emergency core cooling system evaluation model. | ||
Therefore, the action under 10 CFR 50.54(f) is closed. | Specifically, the subject letter required that you provide information within 30 days of February 16, 2012, to address the following issues: | ||
D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46. If you have any questions on this matter, please contact me at 301-415-3079. | (1) An estimation of the effect of the thermal conductivity degradation error on the peak fuel cladding temperature calculation for the emergency core cooling system evaluations at KPS. | ||
Sincerely, Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46. If you have any questions on this matter, please contact me at 301-415-3079. | (2) A description of the methodology and assumptions used to determine the estimates. | ||
Sincerely, IRA! Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ DISTRIBUTION: | This description shall include consideration of experimental data relevant to thermal conductivity degradation and specific information regarding any computer code model changes which were necessary to address these data. | ||
PUBLIC LPL3-1 R/F | By letter dated March 15, 2012 (ADAMS Accession No. ML12079A287), you submitted a response to the 10 CFR 50.54(f) information request for KPS. The NRC staff has reviewed your submitted information and determined that for KPS your response provides the information required to be responsive to the issues discussed above. In addition, the NRC staff determined that your response, which included a report pursuant to 10 CFR 50.46(a)(3)(ii), demonstrates that your facility has complied with the applicable reporting requirements. Therefore, the action under 10 CFR 50.54(f) is closed. | ||
.. OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC (A) NRR/LPL3-1/PM NAME KFeintuch BTully IFrankl KFeintuch DATE 04/20/12 04/20/12 04/23/12 04/25/12 OFFICAL RECORD}} | |||
D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46. | |||
If you have any questions on this matter, please contact me at 301-415-3079. | |||
Sincerely, Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ | |||
D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46. | |||
If you have any questions on this matter, please contact me at 301-415-3079. | |||
Sincerely, IRA! | |||
Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ DISTRIBUTION: | |||
PUBLIC LPL3-1 R/F RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrDorlDpr Resource RidsNrrPMKewaunee Resource JPaige, NRR BParks, NRR RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource AUlses, NRR REul, OE ADAMS Accession No'.. ML121080326 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC (A) NRR/LPL3-1/PM NAME KFeintuch BTully IFrankl KFeintuch DATE 04/20/12 04/20/12 04/23/12 04/25/12 OFFICAL RECORD COPY}} | |||
Latest revision as of 05:52, 12 November 2019
| ML121080326 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 04/25/2012 |
| From: | Feintuch K Plant Licensing Branch III |
| To: | Heacock D Dominion Energy Kewaunee |
| Feintuch K, NRR/DORL/LPL3-1, 415-3079 | |
| References | |
| TAC ME8205 | |
| Download: ML121080326 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 25, 2012 David A. Heacock Dominion Energy Kewaunee, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION - CLOSEOUT OF INFORMATION REQUEST PURSUANT TO 50.54(f) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE - FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION (TAC NO. ME8205)
Dear Mr. Heacock:
By letter dated February 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120410195), the U.S. Nuclear Regulatory Commission (NRC) issued a letter in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(f). Pursuant to this regulation, the NRC staff requested that you provide further information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation, on peak cladding temperature in the Westinghouse-furnished realistic emergency core cooling system evaluation models. The requested information would enable the NRC staff to determine compliance with the Kewaunee Power Station (KPS) licensing basis, which includes the requirements of 10 CFR 50.46(a)(3)(ii),
concerning the reporting of errors and changes to the emergency core cooling system evaluation model.
Specifically, the subject letter required that you provide information within 30 days of February 16, 2012, to address the following issues:
(1) An estimation of the effect of the thermal conductivity degradation error on the peak fuel cladding temperature calculation for the emergency core cooling system evaluations at KPS.
(2) A description of the methodology and assumptions used to determine the estimates.
This description shall include consideration of experimental data relevant to thermal conductivity degradation and specific information regarding any computer code model changes which were necessary to address these data.
By letter dated March 15, 2012 (ADAMS Accession No. ML12079A287), you submitted a response to the 10 CFR 50.54(f) information request for KPS. The NRC staff has reviewed your submitted information and determined that for KPS your response provides the information required to be responsive to the issues discussed above. In addition, the NRC staff determined that your response, which included a report pursuant to 10 CFR 50.46(a)(3)(ii), demonstrates that your facility has complied with the applicable reporting requirements. Therefore, the action under 10 CFR 50.54(f) is closed.
D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46.
If you have any questions on this matter, please contact me at 301-415-3079.
Sincerely, Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ
D. Heacock -2 After review of the 10 CFR 50.46(a)(3) report, the NRC staff has determined that additional information will be required to verify the adequacy of your emergency core cooling system evaluation model. Therefore, while the information provided pursuant to 10 CFR 50.54(f) enabled the staff to close this action, the staff has initiated separate actions to request for additional information under the auspices of 10 CFR 50.46.
If you have any questions on this matter, please contact me at 301-415-3079.
Sincerely, IRA!
Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrDorlDpr Resource RidsNrrPMKewaunee Resource JPaige, NRR BParks, NRR RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource AUlses, NRR REul, OE ADAMS Accession No'.. ML121080326 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC (A) NRR/LPL3-1/PM NAME KFeintuch BTully IFrankl KFeintuch DATE 04/20/12 04/20/12 04/23/12 04/25/12 OFFICAL RECORD COPY