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 Issue dateTitle
ML22230D06922 August 2022Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident
ML18172A25818 September 2018Non-Proprietary, Issuance of Amendment Regarding Core Flow Operating Range Expansion (Mellla+)
BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report4 April 2018Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
ML17298B13125 October 201705000325/2017-301 and 05000324/2017-301 Exam Draft Items
ML17017A38527 January 2017Final SRO Written Exam - Delay Release 2 Years
IR 05000324/201600211 August 2016NRC Integrated Inspection Report No. 05000325/2016002 and 05000324/2016002 and Exercise of Enforcement Discretion
ML16257A41131 July 2016DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus.
IR 05000324/20150041 February 2016NRC Integrated Inspection Report Nos. 05000325/2015004 and 05000324/2015004 and Notice of Enforcement Discretion
ML14310A80828 January 2015Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(C)
IR 05000324/20140086 November 2014IR 05000325/2014008 and 05000324/2014008, September 8-12, 2014 and September 22-26, 2014, Brunswick, NRC Triennial Fire Protection
BSEP 14-0092, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC ME9623 and ME9624)15 August 2014Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC ME9623 and ME9624)
ML14205A59224 July 2014Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (TAC Nos. ME9623 and ME9624)
ML14070A20421 April 2014Staff Assessment Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
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 A31 March 2014Seismic 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
BSEP 13-0071, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Supplement to Walkdown Report31 July 2013Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Supplement to Walkdown Report
ML13127A03814 May 2013Plan for the Regulatory Audit Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
IR 05000324/20120058 February 2013IR 05000325-12-005 & 05000324-12-005, 10/01/12 - 12/31/12, Brunswick Steam Electric Plant, Units 1 & 2, Post Maintenance Testing, Follow-up of Events, and Other Activities
BSEP 12-0126, Recommendation 2.3 Flooding Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 November 2012Recommendation 2.3 Flooding Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident27 November 2012Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12237A05314 August 2012Technical Specification Bases, Brunswick Steam Electric Plant, Unit 1 - Renewed Facility Operating License DPR-71, Revision 80
IR 05000324/201200330 July 2012IR 05000325-12-003, 05000324-12-003; 04/01/12 - 06/30/12; Brunswick Steam Electric Plant, Units 1 & 2; Follow-up of Events
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML08322046930 October 2008Renewed Facility Operating License, Technical Specification Bases, Revision 60
IR 05000324/200400528 January 2005IR 05000325-04-005, 05000324-04-005, on 09/19/2004 - 12/31/2004; Brunswick Steam Electric Plant, Units 1 and 2; Problem Identification and Resolution
BSEP 04-0160, Submittal of Technical Specification Bases Change10 December 2004Submittal of Technical Specification Bases Change
BSEP 04-0109, Report of 10CFR50.59 Evaluation and Commitment Changes27 August 2004Report of 10CFR50.59 Evaluation and Commitment Changes
ML04085049419 March 2004Comment (1) of Tony Groblewski Regarding Notice of Clarification of Steam Generator Tube Integrity Event Reporting Guideline in NUREG-1022
ML04236055923 February 2004E-mail, C. Ogle to Eng Branch, Fwd: Peer Review of Inspection Reports
ML05038036816 January 2004E-mail from C. Ogle to Eng. Branch - Peer Review of Inspection Reports
ML04238028416 January 2004E-mail, C. Ogle to Eng Branch, Peer Review of Inspection Reports
BSEP-03-0126, Submittal of TS Bases Changes for Revision 30 & 2920 August 2003Submittal of TS Bases Changes for Revision 30 & 29
BSEP 03-0062, Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 5029 May 2003Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50
BSEP 03-0023, LER 2002-02-00 from Brunswick, Unit 2 Regarding Remote Shutdown Panel Power Supply Inventer Design Deficiency14 February 2003LER 2002-02-00 from Brunswick, Unit 2 Regarding Remote Shutdown Panel Power Supply Inventer Design Deficiency
IR 05000325/20033019 September 2002February 50-325/2003-301 Exam Draft Simulator Scenarios
IR 05000324/19980066 July 1998Insp Repts 50-324/98-06 & 50-325/98-06 on 980426-0606. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
ML20199G75023 January 1998Insp Repts 50-324/97-13 & 50-325/97-13 on 971109-1227. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support.Includes Results of Maint, Engineering & FP Insps
BSEP-97-0454, Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time6 November 1997Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time
ML20199J56013 October 1997Rev 2 to 0AP-022, Bnp Outage Risk Mgt
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
BSEP-94-0231, Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.4.6,by Removing pressure-temperature Curves & Vessel Surveillance Capsule Withdrawal Schedule17 June 1994Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.4.6,by Removing pressure-temperature Curves & Vessel Surveillance Capsule Withdrawal Schedule
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
BSEP-92-0050, Annual Rept Per 10CFR50.59 for 1991. Rept Contains Tests & Experiments Conducted in 1991 But Not Described in Fsar31 December 1992Annual Rept Per 10CFR50.59 for 1991. Rept Contains Tests & Experiments Conducted in 1991 But Not Described in Fsar
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
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