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	Issue date	Title	Topic
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
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
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
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
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-18-0024, 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 12-0133, 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 12-0127, 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
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
ML12065A380	26 March 2012	Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2	License Renewal
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
ML12076A063	17 February 2012	Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA Exclusive Use Affidavit

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