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 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 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 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 | 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 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 |
IR 05000261/2021005 | 25 August 2021 | Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005) | Fitness for Duty Cyber Security Exemption Request COVID-19 |
ML022110343 | 31 January 2002 | Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System | Power Uprate Affidavit |
ML023040268 | 19 September 2002 | Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Power-Operated Valves |
ML030520269 | 15 February 2003 | Follow-up Report, Reference Event #39516 | |
ML030860823 | 26 March 2003 | Attachment Technical Letter Report | Weld Overlay |
ML031120705 | 18 April 2003 | Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001 | |
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 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 | |
ML050700408 | 20 February 2004 | EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version | Loop seal Exclusive Use Affidavit |