ML12340A404
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| ML12340A404 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/14/2012 |
| From: | Pope A H Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 12-0128 | |
| Download: ML12340A404 (3) | |
Similar Documents at Brunswick | |
|---|---|
Category:Letter
MONTHYEARIR 05000324/20240022024-08-0505 August 2024
[Table view]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 ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick 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) ML22230D0692022-08-22022 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident IR 05000324/20220022022-08-0505 August 2022 Integrated Inspection Report 05000324/2022002 and 05000325/2022002 IR 05000324/20220102022-06-27027 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 2022010 2024-08-05 Category:Report MONTHYEARML24047A2092024-02-22022 February 2024
[Table view]Calendar Year 2023 Baseline Inspection Completion RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16041A4352016-03-0101 March 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 2024-02-22 Category:Miscellaneous MONTHYEARML24047A2092024-02-22022 February 2024
[Table view]Calendar Year 2023 Baseline Inspection Completion RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML16041A4352016-03-0101 March 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241)2011-09-0808 September 2011 1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241) BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report2011-04-0808 April 2011 Renewed Facility Operating License and Cycle 20 Core Operating Limits Report ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes2010-08-18018 August 2010 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1019305532009-12-14014 December 2009 NEI 07-07 NEI Groundwater Protection Initiative NEI Peer Assessment Report for Brunswick BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2009-02-23023 February 2009 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2008-09-24024 September 2008 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML0711000062006-12-0808 December 2006 Operational Safety Review Team (Osart) Mission and Follow-up Visit Report BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes2006-08-24024 August 2006 Report of 10 CFR 50.59 Evaluation and Commitment Changes BSEP 06-0075, Groundwater Questionnaire2006-07-28028 July 2006 Groundwater Questionnaire ML0614404872006-05-18018 May 2006 Submittal of 10-O Report for Quarterly Period Ending March 31, 2006 BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 152005-11-14014 November 2005 Core Operating Limits Report, Revision 2, Cycle 15 BSEP 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2005-08-31031 August 2005 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML0515903332005-05-31031 May 2005 Submittal of 10-Q Report ML0535300692005-05-0909 May 2005 Operational Safety Review Team (Osart) Mission to Brunswick Nuclear Plant 9-25 May 2005 BSEP 05-0018, Occupational Radiation Exposure Report for 20042005-04-20020 April 2005 Occupational Radiation Exposure Report for 2004 ML0434301332004-11-30030 November 2004 Submital of 10-Q Report ML0414602462004-05-19019 May 2004 Q Report for Period Ending 03/31/2004 ML0324716322003-08-22022 August 2003 Submittal of 10-Q Report ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys ML0317000272003-06-0606 June 2003 Submittal of 10-O Report ML19204A1621998-11-18018 November 1998 Enclosure 1 - Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE) Submittal on Brunswick Steam Electric Plant (Bsep), Units 1 and 2 2024-02-22 |
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