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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 |