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| | number = ML11102A048 | | | number = ML11102A048 |
| | issue date = 04/12/2011 | | | issue date = 04/12/2011 |
| | title = Brunswick Steam Electric Plant, Correction to Amendment No. 257 & 285 (TAC ME3856 & ME3857) | | | title = Correction to Amendment No. 257 & 285 (TAC ME3856 & ME3857) |
| | author name = Saba F E | | | author name = Saba F |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Annacone M J | | | addressee name = Annacone M |
| | addressee affiliation = Carolina Power & Light Co | | | addressee affiliation = Carolina Power & Light Co |
| | docket = 05000324, 05000325 | | | docket = 05000324, 05000325 |
| | license number = DPR-062, DPR-071 | | | license number = DPR-062, DPR-071 |
| | contact person = Saba F E | | | contact person = Saba F |
| | case reference number = TAC ME3856, TAC ME3857 | | | case reference number = TAC ME3856, TAC ME3857 |
| | document type = Letter, Safety Evaluation | | | document type = Letter, Safety Evaluation |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 SUB..BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 SUB..IECT: BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857) |
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| ==Dear Mr. Annacone:== | | ==Dear Mr. Annacone:== |
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| By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively. | | By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively. The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011. |
| The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011. The April 8, 2011 letter stated that the NRC staff's safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with the opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments. | | The April 8, 2011 letter stated that the NRC staff's safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with the opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments. Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments. |
| Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments. | | In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure 3. The corrected page is enclosed. |
| In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure | |
| : 3. The corrected page is enclosed.
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| We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447. | | We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447. |
| Sincerely, t:-t!;/1 c= Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc w/enclosure: | | Sincerely, t:-t!;/1 'L~ c= ~ c;~ ~t. |
| Distribution via ListServ OFFICIAL USE ONLY PROPRIETARY UNITED NUCLEAR REGULATORY WASHINGTON, D.C. | | Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc w/enclosure: Distribution via ListServ |
| SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 257 AND 285 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR*71 AND DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50*325 AND 50*324
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| ==1.0 INTRODUCTION==
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 257 AND 285 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR*71 AND DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50*325 AND 50*324 |
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| By application dated April 29. 2010 (Reference 1). as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18. and December 16, 2010, and April 6, 2011 (References 2 through 10, and Reference 39), Carolina Power & Light Company (CP&L, the licensee), requested license amendments to revise the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed license amendments will revise BSEP TS 5.6.5.b by adding the AREVA topical report, ANP-10298PA, "ACE/ATRIUM 10XM Critical Power Correlation," Revision 0, March 2010 (Reference 11), to the list of analytical methods that have been reviewed and approved by the Nuclear Regulatory Commission (NRC) for determining core operating limits. The proposed amendments would change the BSEP TSs to support transition to ATRIUM 10XM fuel and associated core design methodologies.
| | ==1.0 INTRODUCTION== |
| BSEP Units 1 and 2 are General Electric (GE) boiling water reactors (BWRs) BWR/4 design. Both BSEP units are currently operating at 120 percent of originally licensed thermal power at extended power uprate and maximum extended load line limit analysis conditions.
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| Each unit reactor core is composed of 560 fuel assemblies.
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| In each cycle. approximately 40 percent of the irradiated fuel assemblies are replaced with new fuel. On March 27. 2008, the NRC issued Amendments Nos. 246 and 274 for transition from GE fuel to ATRIUM*10 fuel for BSEP Units 1 and 2, respectively (Reference 12). The first transition from GE fuel to ATRIUM*10 fuel occurred in spring 2008 and spring 2009, when the licensee loaded 248 and 238 fresh ATRIUM 10 fuel assemblies in BSEP Units 1 and 2, respectively.
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| The licensee plans to implement this amendment loading the ATRIUM 10XM fuel design in the BSEP Unit 2 during the spring 2011 refueling outage, beginning with Cycle 20. The BSEP Unit 1 amendment supporting transitioning to ATRIUM 10XM will be implemented during the spring 2012 refueling outage, beginning with Cycle 19. The supplements dated June 9, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011, provided additional information that clarified the application, did not expand the scope of the original Federal Register notice, did not change the OFFICIAL USE ONLY PROPRIETARY INFORMATION Enclosure 3
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| April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857)
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| ==Dear Mr. Annacone:==
| | By application dated April 29. 2010 (Reference 1). as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18. and December 16, 2010, and April 6, 2011 (References 2 through 10, and Reference 39), Carolina Power & Light Company (CP&L, the licensee), requested license amendments to revise the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. |
| | The proposed license amendments will revise BSEP TS 5.6.5.b by adding the AREVA topical report, ANP-10298PA, "ACE/ATRIUM 10XM Critical Power Correlation," Revision 0, March 2010 (Reference 11), to the list of analytical methods that have been reviewed and approved by the Nuclear Regulatory Commission (NRC) for determining core operating limits. The proposed amendments would change the BSEP TSs to support transition to ATRIUM 10XM fuel and associated core design methodologies. |
| | BSEP Units 1 and 2 are General Electric (GE) boiling water reactors (BWRs) BWR/4 design. |
| | Both BSEP units are currently operating at 120 percent of originally licensed thermal power at extended power uprate and maximum extended load line limit analysis conditions. Each unit reactor core is composed of 560 fuel assemblies. In each cycle. approximately 40 percent of the irradiated fuel assemblies are replaced with new fuel. On March 27. 2008, the NRC issued Amendments Nos. 246 and 274 for transition from GE fuel to ATRIUM*10 fuel for BSEP Units 1 and 2, respectively (Reference 12). The first transition from GE fuel to ATRIUM*10 fuel occurred in spring 2008 and spring 2009, when the licensee loaded 248 and 238 fresh ATRIUM 10 fuel assemblies in BSEP Units 1 and 2, respectively. |
| | The licensee plans to implement this amendment loading the ATRIUM 10XM fuel design in the BSEP Unit 2 during the spring 2011 refueling outage, beginning with Cycle 20. The BSEP Unit 1 amendment supporting transitioning to ATRIUM 10XM will be implemented during the spring 2012 refueling outage, beginning with Cycle 19. |
| | The supplements dated June 9, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011, provided additional information that clarified the application, did not expand the scope of the original Federal Register notice, did not change the OFFICIAL USE ONLY PROPRIETARY INFORMATION Enclosure 3 |
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| By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively.
| | ML11102A048 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC LPL2-2/PM NAME FSaba CSoia DBroaddus FSaba |
| The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011. The April 8, 2011 letter stated that the NRC staffs safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments.
| | ----------r-------------+-------------~------------~I 04/12/11 04/12/11 04/12/11}} |
| Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment.
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| Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments.
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| In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure
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| : 3. The corrected page is enclosed.
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| We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447.
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| Sincerely, IRA! Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: Distribution via ListServ DISTRIBUTION:
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| Public LPL2-2 rlt RidsNrrLACSola RidsNrrDorlLpl2-2 RidsNrrPMBrunswick RidsOgcMailCenter RidsAcrsAcnw_MailCTR RidsRgn2MailCenter ADAMS Accession No: ML 111 02A048 LPL2-2/PM LPL2-2/LA LPL2-2/BC OFFICE LPL2-2/PM NAME FSaba CSoia DBroaddus FSaba 04/12/11 04/12/11 04/12/11 OFFICIAL RECORD COPY}}
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Letter Sequence Other |
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Results
Other: BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20., BSEP 10-0126, ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126, BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 19, BSEP 13-0004, Operability Assessment (CR 2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation, ML102920551, ML103260315, ML103260322, ML11102A048
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MONTHYEARBSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report Project stage: Request BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report Project stage: Request ML1029205512010-10-12012 October 2010 Units, 1 and 2, Additional Information Supporting License Amendment Requests - Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Unit 2, Cycle 20 Project stage: Other BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20.2010-10-12012 October 2010 ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. Project stage: Other ML1029101672010-10-28028 October 2010 RAI Regarding License Amendment Requests for Addition of Analytical Methodology Topical Reports to TS 5.6.5, Core Operating Limits Report Project stage: RAI ML1032603222010-10-31031 October 2010 ANP-2948NP, Rev. 0, Mechanical Design Report for Brunswick Atrium 10XM Fuel Assemblies, Enclosure 3 to BSEP 10-0126 Project stage: Other BSEP 10-0126, ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-01262010-10-31031 October 2010 ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126 Project stage: Other ML1032603152010-11-0909 November 2010 Additional Information Supporting License Amendment Requests for Mechanical Design Report for Atrium 10XM Fuel Assemblies & Reload Safety Analysis Report for Unit 2 Cycle 20 Project stage: Other BSEP 10-0133, Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)2010-11-18018 November 2010 Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859) Project stage: Request BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars.2010-12-16016 December 2010 ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. Project stage: Response to RAI ML1036303342010-12-16016 December 2010 Response to Request for Additional Information Regarding License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859) Project stage: Response to RAI BSEP 11-0040, Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me...2011-04-0606 April 2011 Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me... Project stage: Request ML11102A0482011-04-12012 April 2011 Correction to Amendment No. 257 & 285 (TAC ME3856 & ME3857) Project stage: Other ML11091A0002011-04-14014 April 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML11097A0132011-04-15015 April 2011 Request for Withholding Information from Public Disclosure. Project stage: Withholding Request Acceptance ML11097A0162011-04-15015 April 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 192012-01-26026 January 2012 Submittal of Confirmatory Evaluation for Cycle 19 Project stage: Other BSEP 13-0004, Operability Assessment (CR 2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation2013-01-29029 January 2013 Operability Assessment (CR #2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation Project stage: Other 2010-04-29
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Category:Letter
MONTHYEARIR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 IR 05000324/20243012024-04-0303 April 2024 NRC Operator License Examination Report 05000325/2024301 and 05000324/2024301 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) 2024-09-04
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21343A2002021-12-20020 December 2021 Authorization and Safety Evaluation for Alternative from Certain Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code of Buried Service Water Piping (EPID L-2021-LLR-0014) (Non-Proprieta ML21281A1382021-12-14014 December 2021 Issuance of Amendment Nos. 306 and 334 to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21067A2242021-04-30030 April 2021 Issuance of Amendment Nos. 305 and 333 to Revise License Conditions to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20309A7842021-03-18018 March 2021 Issuance of Amendment Nos. 304 and 332 Revise Technical Specification 3.4.7 and 3.4.8 to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20253A3212021-01-26026 January 2021 Issuance of Amendment Nos. 302 and 330 Revise Technical Specification 3.6.3.1 to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20310A4102020-12-18018 December 2020 Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20269A3052020-09-29029 September 2020 Issuance of Amendment Nos. 301 and 329 to Revise Technical Specifications to Adopt TSTF-564 (EPID L-2020-LLA-0043) (Non-Proprietary) ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20073F1862020-03-0606 March 2020 Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2018-LLA-0273) (Redacted) ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals ML19316B0572020-01-0808 January 2020 Issuance of Amendment Nos. 297 and 325 to Modify Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.11 Safety Relief Valves ML19284C8332019-11-21021 November 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19281A3302019-11-21021 November 2019 Issuance of Amendment Nos. 296 and 324 to Adopt Technical Specification Task Force Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification ML19268A0542019-10-31031 October 2019 Units 1 and 2 - Issuance of Amendment Nos. 295 and 323 to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19254E0762019-10-25025 October 2019 Issuance of Amendment Nos. 294 and 322 to Revise Technical Specification 3.7.4 for Control Room Air Conditioning Subsystems ML19233A0732019-09-23023 September 2019 Issuance of Amendment Nos. 293 and 321 to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19018A2062019-05-0606 May 2019 Issuance of Amendment Nos. 290 and 318 to Revise Note on Brunswick TS 3.8.3 for One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML19035A0062019-04-22022 April 2019 Issuance of Amendment Nos. 289 and 317 to Relocate the Pressure-Temperature Limits in the Technical Specifications to the Pressure-Temperature Limits Report ML18291B3222019-01-0909 January 2019 Issuance of Amendment Nos. 288 and 316 to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 ML18264A2602019-01-0707 January 2019 Issuance of Amendment Nos. 287 and 315 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML18243A2982018-09-27027 September 2018 Issuance of Amendment to Modify DC Sources Technical Specification Surveillance Requirement 3.8.4.5 ML18172A2582018-09-18018 September 2018 Non-Proprietary, Issuance of Amendment Regarding Core Flow Operating Range Expansion (Mellla+) ML18197A4302018-08-0909 August 2018 Relief Request ISI-10 to Regarding Alternate Repair of Feedwater Nozzle Dissimilar Metal Welds ML18106B1692018-07-0606 July 2018 Issuance of Amendment Nos. 284 and 312 Regarding Request to Allow Performance-Based Fire Protection Alternative for Thermal Insulation Material ML18124A3052018-05-0909 May 2018 Alternative for ISI-09 Regarding Reactor Pressure Vessel Shell Welds Fourth Ten-Year Inservice Inspection Interval ML18122A2032018-05-0707 May 2018 Relief from the Requirements of the ASME Code, Section XI, ISI-11 Regarding System Leakage Test of Class 1 Piping ML18117A1912018-05-0404 May 2018 Proposed Alternative to Defer Inspection of Reactor Vessel Instrumentation Nozzle 2B11-RPV-N11B Until the First Period in the 5th 10-Year ISI Interval ML18039A4442018-04-13013 April 2018 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control Revision 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads 2024-07-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 SUB..IECT: BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857)
Dear Mr. Annacone:
By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively. The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011.
The April 8, 2011 letter stated that the NRC staff's safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with the opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments. Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments.
In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure 3. The corrected page is enclosed.
We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447.
Sincerely, t:-t!;/1 'L~ c= ~ c;~ ~t.
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc w/enclosure: Distribution via ListServ
OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 257 AND 285 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR*71 AND DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50*325 AND 50*324
1.0 INTRODUCTION
By application dated April 29. 2010 (Reference 1). as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18. and December 16, 2010, and April 6, 2011 (References 2 through 10, and Reference 39), Carolina Power & Light Company (CP&L, the licensee), requested license amendments to revise the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.
The proposed license amendments will revise BSEP TS 5.6.5.b by adding the AREVA topical report, ANP-10298PA, "ACE/ATRIUM 10XM Critical Power Correlation," Revision 0, March 2010 (Reference 11), to the list of analytical methods that have been reviewed and approved by the Nuclear Regulatory Commission (NRC) for determining core operating limits. The proposed amendments would change the BSEP TSs to support transition to ATRIUM 10XM fuel and associated core design methodologies.
BSEP Units 1 and 2 are General Electric (GE) boiling water reactors (BWRs) BWR/4 design.
Both BSEP units are currently operating at 120 percent of originally licensed thermal power at extended power uprate and maximum extended load line limit analysis conditions. Each unit reactor core is composed of 560 fuel assemblies. In each cycle. approximately 40 percent of the irradiated fuel assemblies are replaced with new fuel. On March 27. 2008, the NRC issued Amendments Nos. 246 and 274 for transition from GE fuel to ATRIUM*10 fuel for BSEP Units 1 and 2, respectively (Reference 12). The first transition from GE fuel to ATRIUM*10 fuel occurred in spring 2008 and spring 2009, when the licensee loaded 248 and 238 fresh ATRIUM 10 fuel assemblies in BSEP Units 1 and 2, respectively.
The licensee plans to implement this amendment loading the ATRIUM 10XM fuel design in the BSEP Unit 2 during the spring 2011 refueling outage, beginning with Cycle 20. The BSEP Unit 1 amendment supporting transitioning to ATRIUM 10XM will be implemented during the spring 2012 refueling outage, beginning with Cycle 19.
The supplements dated June 9, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011, provided additional information that clarified the application, did not expand the scope of the original Federal Register notice, did not change the OFFICIAL USE ONLY PROPRIETARY INFORMATION Enclosure 3
ML11102A048 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC LPL2-2/PM NAME FSaba CSoia DBroaddus FSaba
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