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

Semantic search

Query log

Navigation menu

	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 05-0018, Occupational Radiation Exposure Report for 2004	20 April 2005	Occupational Radiation Exposure Report for 2004
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 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors	31 August 2005	Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15	14 November 2005	Core Operating Limits Report, Revision 2, Cycle 15	Anticipated operational occurrence
BSEP 06-0075, Groundwater Questionnaire	28 July 2006	Groundwater Questionnaire	Offsite Dose Calculation Manual
BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes	24 August 2006	Report of 10 CFR 50.59 Evaluation and Commitment Changes	Offsite Dose Calculation Manual Excess Flow Check Valve Fire Watch Power change
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 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors	24 September 2008	Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	23 February 2009	Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
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 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes	18 August 2010	Report of 10 CFR 50.59 Evaluations and Commitment Changes	Shutdown Margin Temporary Modification
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 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report	8 April 2011	Renewed Facility Operating License and Cycle 20 Core Operating Limits Report	Safety Limit Minimum Critical Power Ratio
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 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident	27 November 2012	Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident	Safe Shutdown Unanalyzed Condition High Radiation Area Ultimate heat sink Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Scram Discharge Volume Earthquake Scaffolding Seismic Walkdown Report
BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	14 November 2012	Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
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 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events	28 February 2013	Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events	Safe Shutdown High winds Ultimate heat sink Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action FLEX Design basis earthquake Spent Fuel Pool Instrumentation Coast down
BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241)	8 September 2011	1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241)	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 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes	14 August 2014	Report of 10 CFR 50.59 Evaluations and Commitment Changes	Aging Management License Renewal Commercial Grade Control of Heavy Loads Through-Wall Leak
BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors	4 September 2014	Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident	18 December 2014	Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident	High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Earthquake Power-Operated Valves Power Operated Valves
BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)	13 January 2015	Enclosure 3 - Areva Operability Assessment. (CR #2014-7395)	Safety Limit Minimum Critical Power Ratio Operability Assessment
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
BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D	11 April 2018	Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D	Weld Overlay Dissimilar Metal Weld
IR 05000261/2021005	25 August 2021	Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005)	Fitness for Duty Cyber Security Exemption Request COVID-19
ML022110343	31 January 2002	Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System	Power Uprate Affidavit
ML023040268	19 September 2002	Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual	Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Power-Operated Valves