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 Issue dateTitleTopic
BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report8 April 2011Renewed Facility Operating License and Cycle 20 Core Operating Limits ReportSafety 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 12-003129 February 2012Areva 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 12-0031Safety 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 2011ANP-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 Accident27 November 2012Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi AccidentSafe 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 Instrumentation14 November 2012Special 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 12-013327 November 2012Document 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 Impact14 January 2013Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error ImpactFunctionality 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 Events28 February 2013Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External EventsSafe 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 20111707-01-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 A31 March 2014Seismic 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 AccidSafe 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 Changes14 August 2014Report of 10 CFR 50.59 Evaluations and Commitment ChangesAging 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 Errors4 September 2014Annual 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 Accident18 December 2014Expedited 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 AccidentHigh 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 2015Enclosure 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 2015ANP-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 N4D11 April 2018Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4DWeld Overlay
Dissimilar Metal Weld
HNP-04-083, Day Special Report, Steam Generator Tube Plugging27 May 2004Day Special Report, Steam Generator Tube PluggingEddy Current Testing
HNP-05-059, Emergency Response Data System (ERDS) Data Point Library Changes12 May 2005Emergency Response Data System (ERDS) Data Point Library ChangesReactor Vessel Water Level
Met Tower
HNP-05-067, Emergency Core Cooling System Evaluation Changes25 May 2005Emergency Core Cooling System Evaluation Changes
HNP-06-031, Notification of NPDES Permit Renewal Application10 February 2006Notification of NPDES Permit Renewal ApplicationBoric Acid
Grab sample
Hydrostatic
Biofouling
HNP-06-073, Day Special Report Steam Generator Tube Plugging During RFO-135 May 2006Day Special Report Steam Generator Tube Plugging During RFO-13
HNP-06-128, Engineering Report on: Evaluation of Charging-Safety Injection Pump Motor Bearing Temperatures at Progress Energy Harris Nuclear Plant12 October 2006Engineering Report on: Evaluation of Charging-Safety Injection Pump Motor Bearing Temperatures at Progress Energy Harris Nuclear Plant
HNP-07-068, Day Special Report of the Metal Impact Monitoring System14 May 2007Day Special Report of the Metal Impact Monitoring System
HNP-07-178, Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition10 January 2008Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 EditionSafe Shutdown
Boric Acid
Shutdown Margin
Enforcement Discretion
Probabilistic Risk Assessment
Operator Manual Action
Multiple Spurious Operation
Fire Protection Program
HNP-08-015, Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors28 February 2008Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water ReactorsLoop seal
Mission time
Safe Shutdown Earthquake
Hydrostatic
Coatings
Operating Basis Earthquake
Temporary Modification
Foreign Material Exclusion
Exemption Request
Earthquake
Maintenance Rule Program
Scaffolding
HNP-09-056, Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)22 May 2009Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)Safe Shutdown
Fire Barrier
Time to boil
Emergency Lighting
Hemyc
Exemption Request
Earthquake
Power Operated Valves
Fire Protection Program
Fire Watch
HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 November 2012Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentSafe Shutdown
Unanalyzed Condition
Boric Acid
Ultimate heat sink
Safe Shutdown Earthquake
Operating Basis Earthquake
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Earthquake
Seismic Walkdown Report
HNP-13-046, Report of Changes Pursuant to 10 CFR 50.5929 April 2013Report of Changes Pursuant to 10 CFR 50.59Safe Shutdown
Ultimate heat sink
Tornado Missile
Coatings
Tornado-Generated Missile
Tornado Generated Missile
HNP-13-083, Submittal of Summaries of 10 CFR 50.54(q) Evaluations1 August 2013Submittal of Summaries of 10 CFR 50.54(q) Evaluations
HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.327 March 2014Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
HNP-15-027, Flood Hazard Reevaluation Report, Revision 11 April 2015Flood Hazard Reevaluation Report, Revision 1Safe Shutdown
Ultimate heat sink
Hydrostatic
HNP-16-017, Transmittal of Summary of a 10 CFR 50.54(q) Evaluation29 February 2016Transmittal of Summary of a 10 CFR 50.54(q) Evaluation
HNP-16-083, Mitigating Strategies Assessment Report for Flooding Hazard Information21 December 2016Mitigating Strategies Assessment Report for Flooding Hazard InformationUltimate heat sink
Safe Shutdown Earthquake
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
HNP-17-006, Submittal of Cycle 20 Activity Report30 January 2017Submittal of Cycle 20 Activity ReportThrough Wall Leak
HNP-17-040, Snubber Program Plan1 June 2017Snubber Program PlanSafe Shutdown
Incorporated by reference
Earthquake
HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2 May 2018Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment ChangesFuel cladding
Overspeed trip
IR 05000261/202100525 August 2021Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005)Fitness for Duty
Cyber Security
Exemption Request
COVID-19
ML0206502434 March 2002Inspection / Activity Plan 03/01/2002 - 03/31/2003
ML02211034331 January 2002Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus SystemPower Uprate
Affidavit
ML02304026819 September 2002Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course ManualSafe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Power-Operated Valves
ML03007017225 October 2002Summary Report - Ncrs Initiated Since 10/18/2002
ML03007017423 September 2002Summary Report - Ncrs Initiated Since 09/16/2002
ML03007018011 September 2002Summary Report - Ncrs Initiated Since 09/10/2002
ML03007018523 August 2002Summary Report - Ncrs Initiated Since 08/17/2002
ML0300701882 March 2002Facility, Summary Report - Ncrs Initiated Since 05/27/2002
ML0300701946 June 2002Summary Report - Ncrs Initiated Since 05/30/2002
ML03007019630 May 2002Summary Report - Ncrs Initiated Since 05/23/2002
ML03007019820 May 2002Summary Report - Ncrs Initiated Since 05/13/2002
ML03007020013 May 2002Summary Report - Ncrs Initiated Since 05/06/2002
ML03007020415 April 2002Summary Report - Ncrs Initiated Since 04/08/2002