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| | number = ML16294A226 | | | number = ML16294A226 |
| | issue date = 10/27/2016 | | | issue date = 10/27/2016 |
| | title = Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8363 and MF8364) | | | title = Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion |
| | author name = Hon A L | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Gideon W R | | | addressee name = Gideon W |
| | addressee affiliation = Duke Energy Progress, Inc | | | addressee affiliation = Duke Energy Progress, Inc |
| | docket = 05000324, 05000325 | | | docket = 05000324, 05000325 |
| | license number = DPR-062, DPR-071 | | | license number = DPR-062, DPR-071 |
| | contact person = Hon A L, NRR/DORL/LPL2-2, 415-8480 | | | contact person = Hon A, NRR/DORL/LPL2-2, 415-8480 |
| | case reference number = CAC MF8363, CAC MF8364 | | | case reference number = CAC MF8363, CAC MF8364 |
| | document type = Letter | | | document type = Letter |
| | page count = 4 | | | page count = 4 |
| | project = CAC:MF8363, CAC:MF8364 | | | project = CAC:MF8363, CAC:MF8364 |
| | stage = Other | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461 October 27, 2016 SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364) Dear Mr. Gideon: By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML 16271A187), Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 1 O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities associated with the W. Gideon -2 -application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016. In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data. If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov. Docket Nos. 50-325 and 50-324 Enclosure: Supplemental Information Needed cc w/encl: Distribution via Listserv Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+), the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800), and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information: 1. Appropriate disposition for Limitation and Condition (L&C) 9.5 -Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions. 2. Appropriate disposition for L&C 9.23 -MELLLA+ Eigenvalue Tracking. This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23. 3. Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval. 4. A TWS instability (A TWS-1) analysis with Unit No. 2 specific assumptions. (Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.) Enclosure W. Gideon -2 -application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016. In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data. If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov. Docket Nos. 50-325 and 50-324 Enclosure: Supplemental Information Needed cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-2 R/F RidsACRS_MailCTR Resource RidsNrr[DssSrxb Resource RidsNrrDorl Resource RidsNrrDorllpl2-2 Resource RidsNrrPMBrunswick Resource RidsNrrLABClayton Resource RidsRgn2MailCenter Resource ADAMS Accession No | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461 |
| * ML 16294A226 .. OFFICE NRR/DORL/LPL2-2/PM NAME A Hon DATE 10/27/2016 OFFICE NRR/DORL/LPL2-2/BC(A) NAME JDion DATE 10/27/2016 Sincerely, IRA/ Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation NRR/DORL/LPL2-2/LA N RR/DSS/SRXB/BC BClayton (LRonewicz for) EOesterle 10/27/2016 10/21/2016 NRR/DORL/LPL2-2/PM A Hon 10/27/2016 OFFICIAL RECORD COPY | | |
| }} | | ==SUBJECT:== |
| | BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 - |
| | SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364) |
| | |
| | ==Dear Mr. Gideon:== |
| | |
| | By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML16271A187), Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. |
| | The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| | Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| | The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the |
| | |
| | W. Gideon application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. |
| | The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016. |
| | In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data. |
| | If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov. |
| | Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 |
| | |
| | ==Enclosure:== |
| | |
| | Supplemental Information Needed cc w/encl: Distribution via Listserv |
| | |
| | SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+), the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800), and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information: |
| | : 1. Appropriate disposition for Limitation and Condition (L&C) 9.5 - Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions. |
| | : 2. Appropriate disposition for L&C 9.23 - MELLLA+ Eigenvalue Tracking. This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23. |
| | : 3. Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval. |
| | : 4. ATWS instability (ATWS-1) analysis with Unit No. 2 specific assumptions. (Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.) |
| | Enclosure |
| | * ML16294A226 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA N RR/DSS/SRXB/BC NAME A Hon BClayton (LRonewicz for) EOesterle DATE 10/27/2016 10/27/2016 10/21/2016 OFFICE NRR/DORL/LPL2-2/BC(A) NRR/DORL/LPL2-2/PM NAME JDion A Hon DATE 10/27/2016 10/27/2016}} |
Letter Sequence Acceptance Review |
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CAC:MF8363, Clarify Use and Application Rules (Approved, Closed) CAC:MF8364, Clarify Use and Application Rules (Approved, Closed) |
|
MONTHYEARML16294A2262016-10-27027 October 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Acceptance Review ML16330A5052016-11-0909 November 2016 Response to Request for Supplemental Information in Support of MELLLA + LAR, Non-Proprietary Information - Class I (Public) Project stage: Supplement BSEP 16-0101, Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion2016-11-0909 November 2016 Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion Project stage: Supplement ML16319A4232016-11-14014 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16319A4242016-11-14014 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16327A0232016-11-21021 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16342B6002016-12-0707 December 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Project stage: Approval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Request BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Request ML18010A8472018-04-0505 April 2018 Request for Withholding Information from Public Disclosure for Brunswick Steam Electric Plant, Units 1 and 2, Regarding Core Flow Operating Range Expansion (CAC No. MF8363 and MF8364; EPID L-2016-LLA-0009) Project stage: Withholding Request Acceptance 2016-11-09
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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 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 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
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 -
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364)
Dear Mr. Gideon:
By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML16271A187), Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the
W. Gideon application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016.
In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data.
If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov.
Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosure:
Supplemental Information Needed cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+), the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800), and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information:
- 1. Appropriate disposition for Limitation and Condition (L&C) 9.5 - Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions.
- 2. Appropriate disposition for L&C 9.23 - MELLLA+ Eigenvalue Tracking. This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23.
- 3. Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval.
- 4. ATWS instability (ATWS-1) analysis with Unit No. 2 specific assumptions. (Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.)
Enclosure
- ML16294A226 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA N RR/DSS/SRXB/BC NAME A Hon BClayton (LRonewicz for) EOesterle DATE 10/27/2016 10/27/2016 10/21/2016 OFFICE NRR/DORL/LPL2-2/BC(A) NRR/DORL/LPL2-2/PM NAME JDion A Hon DATE 10/27/2016 10/27/2016