Pages that link to "RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)"
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The following pages link to RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary):
Displayed 50 items.
- ML16281A510 (← links)
- ML15253A410 (← links)
- ML15280A199 (← links)
- ML14027A063 (← links)
- ML13365A291 (← links)
- ML13270A176 (← links)
- ML13267A212 (← links)
- ML12331A175 (← links)
- ML12278A399 (← links)
- ML121070716 (← links)
- ML12068A133 (← links)
- ML112411359 (← links)
- ML112411358 (← links)
- ML112800528 (← links)
- ML16280A200 (← links)
- RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. (← links)
- ML18288A369 (← links)
- RA-13-0022, Carolina Power and Light Company'S Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirement for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12 (← links)
- RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2) (← links)
- RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors (← links)
- RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits (← links)
- 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 (← links)
- RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.46 (← links)
- 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) (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- RA-13-0051, License Amendment Request to Modify Technical Specification 3.8.1 Proposed Changes to Diesel Generator Testing Requirements (← links)
- RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication (← links)
- 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 (← links)
- RA-11-012, Regarding Response to Request for Additional Information-Reactor Vessel Beltline Weld Relief Request (RR-23) (ME5407) (← links)
- RA-09-019, Request for Exemptions from Physical Security Requirements (← links)
- RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors (← links)
- RA-08-0116, Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System (← links)
- RA-18-0185, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report (← links)
- RA-19-0094, Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval (← links)
- RA-19-0090, Independent Spent Fuel Storage Installation - Report of Changes Pursuant to 10 CFR 72.48 (← links)
- RA-18-0265, Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding: Integrated Assessment Submittal (← links)
- RA-18-0193, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power .. (← links)
- RA-18-0194, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 3 (← links)
- RA-18-0048, Corrected Technical Specification Pages for TSTF-425 License Amendment Request (← links)
- 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) (← links)
- RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P (← links)
- RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P (← links)
- RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. (← links)
- 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. (← links)
- 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.... (← links)
- 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 (← links)
- RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012 (← links)
- 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 (← links)