BSEP 02-0078, Occupational Radiation Exposure Report for 2001 from Carolina Power & Light Co | 15 April 2002 | Occupational Radiation Exposure Report for 2001 from Carolina Power & Light Co | High Radiation Area |
BSEP 02-0151, Extended Power Uprate Implementation Test Report - Phase 1 | 4 September 2002 | Extended Power Uprate Implementation Test Report - Phase 1 | Shutdown Margin MELLLA Power Uprate |
BSEP 02-0186, Response to Request for Additional Information, Proposed License Amendment to Revise Pressure - Temperature Curve Limits | 22 November 2002 | Response to Request for Additional Information, Proposed License Amendment to Revise Pressure - Temperature Curve Limits | |
BSEP 05-0018, Occupational Radiation Exposure Report for 2004 | 20 April 2005 | Occupational Radiation Exposure Report for 2004 | |
BSEP 05-0079, Inservice Inspection Program for the Third Year Interval-Refueling Outage 16 Owner'S Activity Report | 8 July 2005 | Inservice Inspection Program for the Third Year Interval-Refueling Outage 16 Owner'S Activity Report | Through-Wall Leak |
BSEP 05-0081, Extended Power Uprate, Phase 2 Implementation Test Report | 17 June 2005 | Extended Power Uprate, Phase 2 Implementation Test Report | Annual Radiological Environmental Operating Report MELLLA Power Uprate |
BSEP 05-0103, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | 12 August 2005 | Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | Grab sample Offsite Dose Calculation Manual |
BSEP 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 31 August 2005 | Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15 | 14 November 2005 | Core Operating Limits Report, Revision 2, Cycle 15 | Anticipated operational occurrence |
BSEP 06-0075, Groundwater Questionnaire | 28 July 2006 | Groundwater Questionnaire | Offsite Dose Calculation Manual |
BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes | 24 August 2006 | Report of 10 CFR 50.59 Evaluation and Commitment Changes | Offsite Dose Calculation Manual Excess Flow Check Valve Fire Watch Power change |
BSEP 07-0067, BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007 | 30 June 2007 | BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007 | Stroke time Fuel cladding |
BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6 | 31 July 2007 | Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6 | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Power Uprate Water rod |
BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel. | 30 September 2007 | ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel. | Water rod |
BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 24 September 2008 | Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | 23 February 2009 | Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | |
BSEP 09-0034, Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 2009 | 31 January 2009 | Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 2009 | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Heater Feedwater Controller Failure MELLLA Coast down Overspeed trip |
BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes | 18 August 2010 | Report of 10 CFR 50.59 Evaluations and Commitment Changes | Shutdown Margin Temporary Modification |
BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. | 12 October 2010 | ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. | Anticipated operational occurrence |
BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. | 16 December 2010 | ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. | |
BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR | 31 March 2011 | Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR | Anticipated operational occurrence Fuel cladding |
BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report | 8 April 2011 | Renewed Facility Operating License and Cycle 20 Core Operating Limits Report | Safety Limit Minimum Critical Power Ratio |
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 12-0031 | 29 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 | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA Operability Assessment |
BSEP 12-0040, ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis. | 31 December 2011 | ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis. | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Heater Feedwater Controller Failure MELLLA |
BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident | 27 November 2012 | Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident | Safe Shutdown Unanalyzed Condition High Radiation Area Ultimate heat sink Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Scram Discharge Volume Earthquake Scaffolding Seismic Walkdown Report |
BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | 14 November 2012 | Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation | |
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 12-0133 | 27 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 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact | 14 January 2013 | Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact | Functionality Assessment Operability Determination Operability Assessment |
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 Events | 28 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 | Safe Shutdown High winds Ultimate heat sink Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action FLEX Design basis earthquake Integrated leak rate test Spent Fuel Pool Instrumentation Coast down |
BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241) | 8 September 2011 | 1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241) | Operability Assessment |
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 A | 31 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 | Safe Shutdown Unanalyzed Condition High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Seismically rugged Design basis earthquake Earthquake Weak link |
BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes | 14 August 2014 | Report of 10 CFR 50.59 Evaluations and Commitment Changes | High Energy Line Break Aging Management License Renewal Commercial Grade Control of Heavy Loads Through-Wall Leak |
BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 4 September 2014 | Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
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 Accident | 18 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 | High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Integrated leak rate test Earthquake Power-Operated Valves Power Operated Valves |
BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395) | 13 January 2015 | Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) | Safety Limit Minimum Critical Power Ratio Operability Assessment |
BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. | 31 July 2015 | ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence B.5.b MELLLA Power Uprate Exclusive Use Affidavit Water rod |
BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D | 11 April 2018 | Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D | Weld Overlay Dissimilar Metal Weld |
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User | 16 December 2020 | 10 CFR 71.95 Report for 3-60B Casks User | |
ML030520269 | 15 February 2003 | Follow-up Report, Reference Event #39516 | |
ML030860823 | 26 March 2003 | Attachment Technical Letter Report | Weld Overlay |
ML031700027 | 6 June 2003 | Submittal of 10-O Report | Boric Acid Power Uprate |
ML031890936 | 10 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 | Enforcement Discretion |
ML032471632 | 22 August 2003 | Submittal of 10-Q Report | Boric Acid |
ML040960086 | 29 February 2004 | to 0000-0016-6502-SRLR, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant, Unit 1, Reload 14, Cycle 15. | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Heater Feedwater Controller Failure MELLLA Power Uprate |
ML041460246 | 19 May 2004 | Q Report for Period Ending 03/31/2004 | |
ML043430133 | 30 November 2004 | Submital of 10-Q Report | |
ML050910212 | 31 January 2005 | 0000-0028-0680-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17. | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Power Uprate Affidavit |
ML051590333 | 31 May 2005 | Submittal of 10-Q Report | License Renewal Exemption Request |
ML052090202 | 28 July 2005 | Notification of Brunswick Ssdpc IR 05000325-05-07 and 05000324-05-07 | Probabilistic Risk Assessment Temporary Modification Maintenance Rule Program |
ML053530069 | 9 May 2005 | Operational Safety Review Team (Osart) Mission to Brunswick Nuclear Plant 9-25 May 2005 | Safe Shutdown Fitness for Duty Fire Barrier Water Inventory Control Coatings Temporary Modification Aging Management Foreign Material Exclusion Flow Accelerated Corrosion Intergranular Stress Corrosion Cracking Large early release frequency Stress corrosion cracking Severe Accident Management Guideline License Renewal Earthquake Fire Watch Power change Siren Power Uprate Thermography |