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Issue date | Title | Topic | |
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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 |
ML051590333 | 31 May 2005 | Submittal of 10-Q Report | License Renewal Exemption Request |
ML052090202 | 28 July 2005 | Notification of Brunswick Ssdpc IR 05000325-05-07 and 05000324-05-07 | Probabilistic Risk Assessment Temporary Modification Maintenance Rule Program |
ML053530069 | 9 May 2005 | Operational Safety Review Team (Osart) Mission to Brunswick Nuclear Plant 9-25 May 2005 | 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 |
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 |
ML112411358 | 23 September 2011 | Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance | Significance Determination Process |
ML112411359 | 23 September 2011 | Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling | Fitness for Duty Arc flash Significance Determination Process Preliminary White Finding |
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 |
ML112800528 | 29 December 2010 | NRC 2011 Hb Robinson | |
ML12065A380 | 26 March 2012 | Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 | License Renewal |
ML12068A133 | 23 February 2012 | Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG | Overspeed trip |
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 |
ML121070716 | 17 May 2012 | Letter Report on the Evaluation of Cables from the HEAF Fire Event at the H.B. Robinson Steam Electric Plant | Arc flash |
ML12278A399 | 31 August 2012 | WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant | Operating Basis Earthquake Nondestructive Examination Functionality Assessment Aging Management Stress corrosion cracking Eddy Current Testing License Renewal EVT-1 |
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 |
ML12331A175 | 26 November 2012 | Draft Bypass Fiber Quantity Test Plan | |
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 |
ML13267A212 | 30 September 2013 | Enclosure 1, Transition Report - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition | Hot Short Safe Shutdown Boric Acid High winds Shutdown Margin Mission time Fire Barrier Time to boil Safe Shutdown Earthquake Enforcement Discretion Probabilistic Risk Assessment Coatings Fire impairment Operator Manual Action Multiple Spurious Operation Emergency Lighting B.5.b Significance Determination Process Thermoset Large early release frequency Exemption Request Earthquake Fire Protection Program Fire Watch Very Early Warning Fire Detection Manual Operator Action |
ML13270A176 | 24 September 2013 | Redacted - Office of Nuclear Reactor Regulation (NRR) Reactor Systems Branch (Srxb) Support of Region II Inspection of H. B. Robinson Treatment of Voids in Systems That Are Important to Safety | Stroke time Past operability Functionality Assessment Operability Determination GOTHIC Operability Assessment Affidavit |
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 |
ML13365A291 | 19 February 2014 | Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Job Performance Measure Frazil ice Earthquake GOTHIC |
ML14027A063 | 24 January 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for H. B. Robinson Steam Electric Plant, Unit 2, TAC No.: MF0720 | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Job Performance Measure Frazil ice Earthquake GOTHIC |
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 |
ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink Tornado Missile Fukushima Dai-Ichi Earthquake Generic Issues Program |
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 |
ML15280A199 | 19 October 2015 | 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 Review | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
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 |