RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | 9 June 2022 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | |
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | 25 May 2022 | Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | |
RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | 21 June 2021 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | |
RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data | 7 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) | 24 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) | 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 |
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 | |
NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B | 14 December 2020 | 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B | |
RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask | 16 November 2020 | 10 CFR 71.95 Report on the 3-60B Cask | |
ML20309A505 | 3 November 2020 | Inspector Notes Cover Sheet | Commercial Grade Dedication |
RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 31 December 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence Affidavit |
RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 23 October 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Exclusive Use Affidavit Water rod |
RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | 15 August 2019 | Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | Hydrostatic Pressure and Temperature Limits Report License Renewal Power Uprate |
RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 2 July 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Stroke time Post Accident Monitoring Fuel cladding Affidavit |
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 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 Request | 29 May 2019 | Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request | Feedwater Controller Failure MELLLA Fuel cladding Power Uprate Affidavit |
RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 18 March 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin Affidavit Water rod |
RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 11 October 2018 | Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence Power Uprate Affidavit |
ML18249A159 | 13 August 2018 | Technical Requirements Manual, Revision 73 | Time of Discovery Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Functionality Assessment Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Pressure Boundary Leakage Offsite Circuit Operational leakage |
RA-18-0131, Technical Requirements Manual, Revision 66 | 13 August 2018 | Technical Requirements Manual, Revision 66 | Time of Discovery Reactor Vessel Water Level Ultimate heat sink Non-Destructive Examination Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Functionality Assessment Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Pressure Boundary Leakage Offsite Circuit Operational leakage |
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 Report | 29 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 | Pressure and Temperature Limits Report |
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 |
ML17024A036 | 31 December 2016 | Operating Data Report for 2016 | Temporary Modification Biofouling Power change Coast down |
ML16287A422 | 26 September 2016 | FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. | Anticipated operational occurrence Minimum Critical Power Ratio MELLLA |
ML16223A725 | 17 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) | FLEX Fukushima Dai-Ichi Earthquake Hardened vent |
ML18250A002 | 11 August 2016 | Technical Requirements Manual, Revision 70 | Time of Discovery Reactor Vessel Water Level High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Offsite Circuit Operational leakage |
ML18250A003 | 11 August 2016 | Technical Requirements Manual, Revision 63 | Time of Discovery Reactor Vessel Water Level High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Offsite Circuit Operational leakage |
ML16257A411 | 31 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. | Unanalyzed Condition Safety Limit Minimum Critical Power Ratio Ultimate heat sink Anticipated operational occurrence Probabilistic Risk Assessment Design basis earthquake Flow Accelerated Corrosion Feedwater Controller Failure Large early release frequency MELLLA Stress corrosion cracking Power Uprate Affidavit |
ML16041A435 | 1 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 | Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
ML16257A406 | 31 December 2015 | ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. | Stroke time MELLLA Fuel cladding Exclusive Use Affidavit |
ML15275A290 | 30 September 2015 | Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. | Shutdown Margin Anticipated operational occurrence |
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 |
ML16257A408 | 31 July 2015 | ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. | Stroke time MELLLA Fuel cladding Exclusive Use Affidavit |
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 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 |
ML14297A266 | 24 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 | GOTHIC |
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 14-0093, 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 |
ML14176A961 | 24 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 | Fire Barrier Coatings Foreign Material Exclusion |
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 |
ML13220A090 | 22 November 2013 | Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operator Manual Action Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Frazil ice Battery sizing Earthquake GOTHIC |
ML13317A592 | 20 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 | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operator Manual Action Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Frazil ice Battery sizing Earthquake |
ML13277A041 | 19 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 | Safe 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 |
ML16257A407 | 31 May 2013 | ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. | Shutdown Margin MELLLA Exclusive Use Affidavit Water rod |
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 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 |
ML13031A011 | 11 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 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 12-0133, 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 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 | |
ML12321A319 | 1 November 2012 | 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. | Stress corrosion cracking Flow Induced Vibration Power Uprate |