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 | |
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-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-23-0120, 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-23-0080, 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-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-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-22-0017, 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-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 |
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 |
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 | |
RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2) | 2 April 2018 | Report of Changes Pursuant to 10 CFR 50.59(d)(2) | Unanalyzed Condition Open Phase Condition Fire Watch Overspeed trip |
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) | |
ML16281A510 | 15 December 2016 | Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans | Aging Management Stress corrosion cracking License Renewal |
RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | 31 October 2016 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | Post Accident Monitoring |
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 |
RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | 5 October 2016 | Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | Post Accident Monitoring |
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 |
RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits | 14 September 2016 | Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits | Power Uprate |
RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 | 25 May 2016 | Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 | Hot Short Safe Shutdown High winds Mission time Fire Barrier Time to boil Enforcement Discretion Probabilistic Risk Assessment Fire impairment Operator Manual Action Multiple Spurious Operation Significance Determination Process Thermoset Large early release frequency Exemption Request Fire Protection Program Fire Watch Very Early Warning Fire Detection |
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 |
ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink Tornado Missile Fukushima Dai-Ichi Earthquake Generic Issues Program |
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 | |
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 |
RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04) | 19 August 2015 | Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04) | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Mission time Fire Barrier Tornado Missile Time to boil FLEX B.5.b Fukushima Dai-Ichi Severe Accident Management Guideline Time Critical Operator Action Earthquake Scaffolding Weak link GOTHIC Unidentified leakage |
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 |
RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel | 26 February 2015 | Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel | Post Accident Monitoring |
RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System | 8 April 2014 | Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System | |
RNP-RA/14-0012, Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3.... | 12 March 2014 | Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3.... | |
RNP-RA/14-0011, Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident | 27 February 2014 | Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident | Safe Shutdown Unanalyzed Condition Boric Acid High Radiation Area Ultimate heat sink Operating Basis Earthquake Finite Element Analysis Fukushima Dai-Ichi Design basis earthquake Earthquake Scaffolding Seismic Walkdown Report |
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 |
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 |
RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter | 21 August 2013 | Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter | Post Accident Monitoring |
RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication | 24 June 2013 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication | Post Accident Monitoring |
RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012 | 25 April 2013 | Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012 | |
ML12331A175 | 26 November 2012 | Draft Bypass Fiber Quantity Test Plan | |
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 |
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 |
ML12068A133 | 23 February 2012 | Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG | Overspeed trip |
RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System | 23 November 2011 | Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System | |
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 |
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 |
ML112800528 | 29 December 2010 | NRC 2011 Hb Robinson | |
ML101930417 | 6 May 2010 | Tritium Database Report | Offsite Dose Calculation Manual Hydrostatic |
RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. | 31 July 2009 | WCAP-17077-NP, Revision 0, 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 |
RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation | 19 June 2009 | Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation | Affidavit |
ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Feedwater Heater Power change Downpower Power Uprate Overspeed trip |