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	Issue date	Title	Topic
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)	Boric Acid Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Fuel cladding Affidavit Water rod
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 Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Coast down Affidavit Manual Operator Action
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 Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit
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
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/15-0053, 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
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
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 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