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	Issue date	Title	Topic
BSEP 02-0078, Occupational Radiation Exposure Report for 2001 from Carolina Power & Light Co	15 April 2002	Occupational Radiation Exposure Report for 2001 from Carolina Power & Light Co	High Radiation Area
BSEP 02-0151, Extended Power Uprate Implementation Test Report - Phase 1	4 September 2002	Extended Power Uprate Implementation Test Report - Phase 1	Shutdown Margin MELLLA Power Uprate
BSEP 02-0186, Response to Request for Additional Information, Proposed License Amendment to Revise Pressure - Temperature Curve Limits	22 November 2002	Response to Request for Additional Information, Proposed License Amendment to Revise Pressure - Temperature Curve Limits
BSEP 05-0079, Inservice Inspection Program for the Third Year Interval-Refueling Outage 16 Owner'S Activity Report	8 July 2005	Inservice Inspection Program for the Third Year Interval-Refueling Outage 16 Owner'S Activity Report	Through-Wall Leak
BSEP 05-0081, Extended Power Uprate, Phase 2 Implementation Test Report	17 June 2005	Extended Power Uprate, Phase 2 Implementation Test Report	Annual Radiological Environmental Operating Report MELLLA Power Uprate
BSEP 05-0103, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	12 August 2005	Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	Grab sample Offsite Dose Calculation Manual
BSEP 07-0067, BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007	30 June 2007	BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007	Stroke time Fuel cladding
BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6	31 July 2007	Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6	Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Power Uprate Water rod
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
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
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
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 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
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
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
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 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
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
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
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
ML030520269	15 February 2003	Follow-up Report, Reference Event #39516
ML030860823	26 March 2003	Attachment Technical Letter Report	Weld Overlay
ML040960086	29 February 2004	to 0000-0016-6502-SRLR, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant, Unit 1, Reload 14, Cycle 15.	Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Power Uprate
ML050910212	31 January 2005	0000-0028-0680-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17.	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Power Uprate Affidavit
ML052090202	28 July 2005	Notification of Brunswick Ssdpc IR 05000325-05-07 and 05000324-05-07	Probabilistic Risk Assessment Temporary Modification Maintenance Rule Program
ML062770227	19 October 2006	Essential Fish Habitat Assessment for License Renewal of Brunswick Steam Electric Plant, Units 1 and 2	License Renewal Biofouling Power Uprate
ML072070311	30 June 2007	BSEP 07-0067 Enclosure 3; Areva Report ANP-2646(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, Dated June 2007	Anticipated operational occurrence Water rod
ML072070318	30 June 2007	BSEP 07-0067 Enclosure 6; Areva Report ANP-2625(NP), Revision 0, Brunswick, Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM-10 Fuel, Dated June 2007
ML072180372	31 July 2007	Areva Report ANP-2658(NP), Revision 0, Brunswick Unit 1 Cycle 17 Fuel Cycle Design, Enclosure 3	Shutdown Margin 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.
ML082190013	7 August 2008	Monthly Operating Reports Second Quarter 2008	Reserve Station Service Transformer Power change
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
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
ML101930549	20 January 2010	Impact of Tritium Leak on Public	Annual Radioactive Effluent Release Report
ML111101020	24 March 2011	Reactor Pressure Vessel Flaw Evaluation	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
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
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
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
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
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
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
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
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
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
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

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