Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Search Clear all entries

	Issue date	Title	Topic
ML061440487	18 May 2006	Submittal of 10-O Report for Quarterly Period Ending March 31, 2006
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
ML071100006	8 December 2006	Operational Safety Review Team (Osart) Mission and Follow-up Visit Report	Safe Shutdown Fitness for Duty Fire Barrier Water Inventory Control Coatings Temporary Modification Aging Management Foreign Material Exclusion Flow Accelerated Corrosion Large early release frequency Stress corrosion cracking Severe Accident Management Guideline License Renewal Earthquake Fire Watch Power change Siren Power Uprate Thermography
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
ML101270439	5 May 2010	Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML101930417	6 May 2010	Tritium Database Report	Offsite Dose Calculation Manual Hydrostatic
ML101930549	20 January 2010	Impact of Tritium Leak on Public	Annual Radioactive Effluent Release Report
ML101930553	14 December 2009	NEI 07-07 NEI Groundwater Protection Initiative NEI Peer Assessment Report for Brunswick
ML110871250	24 March 2011	BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages	Weld Overlay VT-2 Earthquake EVT-1 Dissimilar Metal Weld DM weld
ML111101020	24 March 2011	Reactor Pressure Vessel Flaw Evaluation	Power Uprate
ML112700069	26 September 2011	Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants	Shutdown Margin Anticipated operational occurrence Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Channel-control blade interference Scram Discharge Volume Earthquake
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
ML13277A041	19 September 2013	Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition	Safe Shutdown High winds Ultimate heat sink Non-Destructive Examination Mission time Fire Barrier Time to boil Safe Shutdown Earthquake Enforcement Discretion Probabilistic Risk Assessment Fire impairment Operator Manual Action Multiple Spurious Operation Emergency Lighting Significance Determination Process Scram Discharge Volume Large early release frequency Exemption Request Fire Protection Program Fire Watch Very Early Warning Fire Detection
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
ML14297A266	24 October 2014	Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14	GOTHIC
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
ML16041A435	1 March 2016	Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force	Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Earthquake
ML16223A725	17 August 2016	Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468)	FLEX Fukushima Dai-Ichi Earthquake Hardened vent
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
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
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
ML17024A036	31 December 2016	Operating Data Report for 2016	Temporary Modification Biofouling Power change Coast down
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
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
ML19204A161	31 March 1998	Technical Evaluation Report on the Submittal Only Review of the Individual Plant Examination of External Events at Brunswick Nuclear Plant, Units 1 and 2 - Final Report
ML19204A162	18 November 1998	Enclosure 1 - Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE) Submittal on Brunswick Steam Electric Plant (Bsep), Units 1 and 2
ML19204A209	30 June 1995	Individual Plant Examination for External Events Submittal - Final Report	Safe Shutdown High winds Shutdown Margin Ultimate heat sink Mission time Fire Barrier Safe Shutdown Earthquake Post Accident Monitoring Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Operating Basis Earthquake Emergency Lighting Finite Element Analysis Abnormal operational transient Seismically rugged Design basis earthquake Scram Discharge Volume Stress corrosion cracking Severe Accident Management Guideline Earthquake Turbine Missile Fuel cladding Liquid penetrant Fire Protection Program Fire Watch Weak link Manual Operator Action
ML20309A505	3 November 2020	Inspector Notes Cover Sheet	Commercial Grade Dedication
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
NRC Generic Letter 1979-45	25 September 1979	NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences	Boric Acid
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
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

Semantic search

Query log

Navigation menu