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RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation16 November 2023RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 202226 April 2023Duke Energy Annual Radiological Environmental Operating Report - 2022
ML19233A07323 September 2019Issuance of Amendment Nos. 293 and 321 to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
RA-18-0131, Technical Requirements Manual, Revision 6613 August 2018Technical Requirements Manual, Revision 66
ML18249A15913 August 2018Technical Requirements Manual, Revision 73
BSEP 18-0051, Annual Radioactive Effluent Release Report - 201726 April 2018Annual Radioactive Effluent Release Report - 2017
ML17186A2196 September 2017Issuance of Amendments to Adopt TSTF-529, REV-4, Clarify Use and Application Rules (CAC Nos. MF8819-MF8820)
ML17066A37426 April 2017Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML17017A38527 January 2017Final SRO Written Exam - Delay Release 2 Years
BSEP 16-0082, Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.27 October 2016Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.
ML18250A00211 August 2016Technical Requirements Manual, Revision 70
ML18250A00311 August 2016Technical Requirements Manual, Revision 63
RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process23 June 2016Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process
RA-16-0001, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.18 January 2016Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.
IR 05000324/201500231 July 2015IR 05000325/2015002, 05000324/2015002; April 1, 2015, Through June 30, 2015; Duke Energy Progress, Inc., Brunswick Steam Electric Plant, Units 1 & 2, Fire Protection, Operability Determinations and Functionality Assessments, and Post-Mainte
ML14316A39112 November 2014Initial Exam 2014301 Final SRO Written Exam
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)
BSEP 14-0038, Radioactive Effluent Release Report for 201323 April 2014Radioactive Effluent Release Report for 2013
BSEP 13-0042, Off-Site Dose Calculation Manual, Revision 3629 April 2013Off-Site Dose Calculation Manual, Revision 36
ML12136A58415 November 2011Offsite Dose Calculation Manual Revision 35
ML11271003328 September 2011ROP Tabletop Examples and Results
ML11126A22231 December 2010Radioactive Effluent Release Report for January 1 Through December 31, 2010, Enclosure 1 to BSEP 11-0045
ML11126A22313 July 2010Offsite Dose Calculation Manual, Revision 34, Enclosure 2 to BSEP 11-0045
ML1015900783 May 2010Initial Exam 2010-301 Draft SRO Written Exam
IR 05000324/201000618 April 2010IR 05000325-10-006 and 05000324-10-006, on 03/15/2010 - 03/19/2010; Brunswick Steam Electric Plant, Unit 1; Supplemental Inspection for a White Finding
ML10124105218 December 2009Off-Site Dose Calculation Manual, Revision 33
BSEP 09-0045, Submittal of Radioactive Effluent Release Report for 200827 April 2009Submittal of Radioactive Effluent Release Report for 2008
IR 05000324/200801012 December 2008IR 05000325-08-010, 05000324-08-010, on 09/08/2008 - 11/13/2008 for Brunswick, Units 1 and 2
ML07124028530 January 2006Off-Site Dose Calculation Manual, Revision 29
ML05123009014 March 2005Off-Site Dose Calculation Manual (ODCM) Revision 28
BSEP 05-0020, Off-Site Dose Calculation Manual (ODCM) Revision 281 May 2004Off-Site Dose Calculation Manual (ODCM) Revision 28
ML04124033726 April 2004Unit Nos. I and 2, Radioactive Effluent Release Report for 2003
ML03360011519 December 2003Application for Technical Specification Change Re Mode Change Limitations Using Consolidated Line Item Improvement Process
BSEP 03-0164, 180-Day Response to Generic Letter 2003-01, Control Room Habitability9 December 2003180-Day Response to Generic Letter 2003-01, Control Room Habitability
BSEP-03-0003, Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H28 April 2003Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H
ML02239006026 August 2002Tech Spec Page for Amendment No. 224 Missed Surveillances
ML02239005726 August 2002Tech Spec Page for Amendment No. 249 Missed Surveillances
BSEP 02-0002, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process25 March 2002Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process
IR 05000324/199801021 December 1998Insp Repts 50-324/98-10 & 50-325/98-10 on 981011-1121. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Also Includes Results of Engineering & Health Physics Insp
IR 05000324/199800711 August 1998Insp Repts 50-324/98-07 & 50-325/98-07 on 980607-0718. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
ML20198Q3014 November 1997Proposed Tech Specs 3.0 & 4.0,revising Specific Terms in Proposed TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology
BSEP-97-0383, Responds to NRC Re Violations Noted in Insp Repts 50-324/97-08 & 50-325/97-08.Corrective Actions:Disciplined Individuals Involved,Conducted Stand Down W/Operations Personnel & Revised Procedure 0O1-01.08 Re Log Book Reviews2 September 1997Responds to NRC Re Violations Noted in Insp Repts 50-324/97-08 & 50-325/97-08.Corrective Actions:Disciplined Individuals Involved,Conducted Stand Down W/Operations Personnel & Revised Procedure 0O1-01.08 Re Log Book Reviews
IR 05000324/199700720 June 1997Integrated Insp Repts 50-324/97-07 & 50-325/97-07 on 970413-0524.No Violations Noted.Major Areas Inspected: Licensee Operations,Engineering,Maint & Plant Support
ML20137Y79414 April 1997Proposed Tech Specs 3.0 & 4.0 Re Applicability of LCO & Surveillance Requirements,Per GL 87-09
BSEP-97-0144, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-0914 April 1997Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-09
ML20137A48318 March 1997SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2
BSEP-97-0011, Responds to NRC Re Violations Noted in Insp Repts 50-324/96-15 & 50-325/96-15.Corrective Actions:Reactor Power Was Reduced & Feedwater Temperature Compensation Was Corrected13 January 1997Responds to NRC Re Violations Noted in Insp Repts 50-324/96-15 & 50-325/96-15.Corrective Actions:Reactor Power Was Reduced & Feedwater Temperature Compensation Was Corrected
Information Notice 1996-44, Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly5 August 1996Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly
ML20217B31211 February 1991Safety Insps 50-324/91-01 & 50-325/91-01 on 910101-31. Violation Noted.Major Areas Inspected:Maint & Surveillance Observation,Operational Safety Verification,Onsite Review Committee & Response to Events