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 Issue dateTitleTopic
RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 249 June 2022Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24
RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)22 November 2021Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)Post Accident Monitoring
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
RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2521 June 2021Inservice 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)24 February 2021Proposed 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)Fitness for Duty
Ultimate heat sink
Non-Destructive Examination
Safe Shutdown Earthquake
Coatings
Operating Basis Earthquake
Finite Element Analysis
Foreign Material Exclusion
Exemption Request
Affidavit
RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies31 December 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesAnticipated operational occurrence
Affidavit
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.4630 May 2019Annual 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 N4D11 April 2018Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4DWeld Overlay
Dissimilar Metal Weld
RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2 April 2018Report of Changes Pursuant to 10 CFR 50.59(d)(2)Unanalyzed Condition
Open Phase Condition
Fire Watch
Overspeed trip
ML17024A03631 December 2016Operating Data Report for 2016Temporary Modification
Biofouling
Power change
Coast down
ML16281A51015 December 2016Staff Assessment of the Reactor Vessel Internals Aging Management Program PlansAging Management
Stress corrosion cracking
License Renewal
RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors31 October 2016Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation MonitorsPost Accident Monitoring
RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors5 October 2016Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation MonitorsPost Accident Monitoring
RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P3 October 2016Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-PSafe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Coast down
Affidavit
Manual Operator Action
ML16223A72517 August 2016Interim 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)FLEX
Fukushima Dai-Ichi
Earthquake
Hardened vent
RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-17425 May 2016Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174Hot Short
Safe Shutdown
High winds
Mission time
Fire Barrier
Time to boil
Enforcement Discretion
Probabilistic Risk Assessment
Fire impairment
Operator Manual Action
Multiple Spurious Operation
Significance Determination Process
Thermoset
Large early release frequency
Exemption Request
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection
ML15253A41011 March 2016Enclosure 2 Screening Analysis ReportUltimate heat sink
Tornado Missile
Fukushima Dai-Ichi
Earthquake
Generic Issues Program
ML16041A4351 March 2016Staff 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 ForceSafe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake
RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.4617 November 2015Annual Report of Changes Pursuant to 10 CFR 50.46
ML15280A19919 October 2015Staff 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 ReviewSafe Shutdown Earthquake
Fukushima Dai-Ichi
Earthquake
RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)19 August 2015Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Mission time
Fire Barrier
Tornado Missile
Time to boil
FLEX
B.5.b
Fukushima Dai-Ichi
Severe Accident Management Guideline
Time Critical Operator Action
Earthquake
Scaffolding
Weak link
GOTHIC
Unidentified leakage
RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel26 February 2015Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux ChannelPost Accident Monitoring
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 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
ML14297A26624 October 2014Record 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), 10/24/14GOTHIC
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 14-0093, 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
RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System8 April 2014Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System
RNP-RA/14-0012, Flood Hazard Reevaluation Report, 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, 2.3 and 9.3....12 March 2014Flood Hazard Reevaluation Report, 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, 2.3 and 9.3....
ML13277A04119 September 2013Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 EditionSafe Shutdown
High winds
Ultimate heat sink
Non-Destructive Examination
Mission time
Fire Barrier
Time to boil
Safe Shutdown Earthquake
Enforcement Discretion
Probabilistic Risk Assessment
Fire impairment
Operator Manual Action
Multiple Spurious Operation
Emergency Lighting
Significance Determination Process
Scram Discharge Volume
Large early release frequency
Exemption Request
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection
RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter21 August 2013Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure TransmitterPost Accident Monitoring
RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication24 June 2013Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve IndicationPost Accident Monitoring
RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 201225 April 2013Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012
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 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
RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System23 November 2011Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System
ML11270006926 September 2011Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 PlantsShutdown Margin
Anticipated operational occurrence
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Channel-control blade interference
Scram Discharge Volume
Earthquake
ML11241135923 September 2011Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and CoolingFitness for Duty
Arc flash
Significance Determination Process
Preliminary White Finding
ML11241135823 September 2011Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and MaintenanceSignificance Determination Process
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 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
ML11087125024 March 2011BWR Vessel and Internals Inspection Summaries for Spring 2010 OutagesWeld Overlay
VT-2
Earthquake
EVT-1
Dissimilar Metal Weld
DM weld
ML11280052829 December 2010NRC 2011 Hb Robinson
BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes18 August 2010Report of 10 CFR 50.59 Evaluations and Commitment ChangesShutdown Margin
Temporary Modification
ML1019304176 May 2010Tritium Database ReportOffsite Dose Calculation Manual
Hydrostatic
ML1012704395 May 2010Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML10193055314 December 2009NEI 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 Instrumentation23 February 2009Special 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 Errors24 September 2008Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors