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	Issue date	Title	Topic
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data	25 May 2022	Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data
RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data	7 June 2021	Cycle 24 Mellla+ Eigenvalue Tracking Data
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
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-19-0240, 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
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
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
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
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
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 13-0002, 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
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
ML12076A064	17 February 2012	Areva Document No. 51-9177315-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 11 to BSEP 12-0031	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA Operability Assessment Exclusive Use Affidavit
ML12076A085	17 February 2012	Areva Document No. 51-9177314-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology, Enclosure 14 to BSEP 12-0031	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA Exclusive Use Affidavit
ML12076A086	17 February 2012	Areva Document No. 51-9177316-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 17 to BSEP 12-0031	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA Operability Assessment Exclusive Use Affidavit
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
ML12100A087	31 May 2011	ANP-2989(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies.	Anticipated operational occurrence Exclusive Use Affidavit Water rod
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
ML111101020	24 March 2011	Reactor Pressure Vessel Flaw Evaluation	Power Uprate
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 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
ML101930549	20 January 2010	Impact of Tritium Leak on Public	Annual Radioactive Effluent Release Report
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
ML082190013	7 August 2008	Monthly Operating Reports Second Quarter 2008	Reserve Station Service Transformer Power change
ML090970248	31 July 2008	Enclosure 4 and 6 to BSEP 09-0034 - ANP-2729(NP), Rev. 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, and Areva Affidavit Withholding ANP-2727(P), Rev. 0 Form Public Disclosure	Anticipated operational occurrence Exclusive Use Affidavit Water rod
ML090970246	30 June 2008	Enclosure 7 and 9 to BSEP 09-0034 - ANP-2727(NP), Rev. 0, Brunswick, Unit 2, Cycle 19 Fuel Cycle Design, and Areva Affidavit Re Withholding ANP-2771(P), Rev. 0 from Public Disclosure	Shutdown Margin Exclusive Use Affidavit Water rod
ML072840219	30 September 2007	ANP-2642(NP), Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM-10 Fuel.
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

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