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 |
ML030520269 | 15 February 2003 | Follow-up Report, Reference Event #39516 | |
ML031120705 | 18 April 2003 | Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001 | |
ML031700027 | 6 June 2003 | Submittal of 10-O Report | Boric Acid Power Uprate |
ML031890936 | 10 July 2003 | Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys | Enforcement Discretion |
ML032471632 | 22 August 2003 | Submittal of 10-Q Report | Boric Acid |
ML041460246 | 19 May 2004 | Q Report for Period Ending 03/31/2004 | |
ML050700408 | 20 February 2004 | EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version | Loop seal Exclusive Use Affidavit |
ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Feedwater Heater Power change Downpower Power Uprate Overspeed trip |
ML101930417 | 6 May 2010 | Tritium Database Report | Offsite Dose Calculation Manual Hydrostatic |
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 Water hammer |
ML112800528 | 29 December 2010 | NRC 2011 Hb Robinson | |
ML12068A133 | 23 February 2012 | Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG | Overspeed trip |
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 Intergranular Stress Corrosion Cracking Stress corrosion cracking Eddy Current Testing License Renewal EVT-1 |
ML12331A175 | 26 November 2012 | Draft Bypass Fiber Quantity Test Plan | |
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 Water hammer |
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 |
ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink Tornado Missile Fukushima Dai-Ichi Earthquake Generic Issues Program |
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 |
ML16280A200 | 5 October 2016 | Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals | Aging Management Power change Power Uprate Affidavit |
ML16281A510 | 15 December 2016 | Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans | Aging Management Stress corrosion cracking License Renewal |
ML18288A369 | 31 October 1990 | ANF-88-054(NP)(A), PDC-3: Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2. | |
NRC Generic Letter 1979-45 | 25 September 1979 | NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences | Boric Acid |
RA-05-0104, Transmittal of Core Operating Limits Report | 10 October 2005 | Transmittal of Core Operating Limits Report | Shutdown Margin |
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. | 19 August 2015 | Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. | Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit |
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. | 19 November 2015 | Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. | Safe Shutdown Shutdown Margin Loop seal Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Feedwater Heater Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit Loss of condenser vacuum |
RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.46 | 17 November 2015 | Annual Report of Changes Pursuant to 10 CFR 50.46 | |
RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P | 4 May 2016 | Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P | Shutdown Margin Reactor Vessel Water Level Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit |
RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P | 3 October 2016 | Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P | Safe Shutdown Boric Acid Shutdown Margin Loop seal Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Feedwater Heater Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Coast down Affidavit Manual Operator Action Loss of condenser vacuum |
RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) | 15 August 2017 | Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) | |
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 May 2019 | Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | |
RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 22 November 2021 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | 6 January 2022 | Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | Stress corrosion cracking Eddy Current Testing |
RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | 9 August 2022 | Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | Post Accident Monitoring |
RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 1 November 2022 | Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | 5 April 2023 | Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | Nondestructive Examination |
RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | 31 May 2023 | Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | |
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | 12 July 2023 | Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | License Renewal Subsequent License Renewal |
RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | 14 December 2023 | Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | Finite Element Analysis Aging Management Stress corrosion cracking Affidavit |
RA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld | 28 June 2024 | Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld | |
RNP-RA/02-0028, Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval | 26 March 2002 | Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval | |
RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License | 6 November 2002 | Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License | |
RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 21 | 11 November 2002 | Steam Generator Tube Plugging During Refueling Outage 21 | |
RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent | 11 February 2003 | Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent | |