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	Issue date	Title	Topic
RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6	31 July 2003	Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6	Boric Acid Hydrostatic Stress corrosion cracking
RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.	31 March 2006	ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.	Coast down Exclusive Use Affidavit
RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure	17 July 2006	Request for Technical Specifications, Change Related to Containment Peak Pressure	Ultimate heat sink
RNP-RA/06-0062, Groundwater Protection - Data Collection Questionnaire	24 July 2006	Groundwater Protection - Data Collection Questionnaire
RNP-RA/06-0081, Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP	31 August 2006	Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP	Nondestructive Examination Finite Element Analysis Stress corrosion cracking Affidavit
RNP-RA/08-0026, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors	7 March 2008	Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors	Boric Acid High Radiation Area Fire Barrier Coatings Foreign Material Exclusion Stress corrosion cracking Exemption Request Scaffolding Manual Operator Action
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
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 Stress corrosion cracking Eddy Current Testing License Renewal EVT-1
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
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
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/13-0079, 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/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
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/14-0037, 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/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/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/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
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/16-0078, 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
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
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