Pages that link to "RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals"
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The following pages link to RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals:
Displayed 50 items.
- ML16230A234 (← links)
- ML16158A006 (← links)
- ML16063A103 (← links)
- ML16054A159 (redirect page) (← links)
- ML15009A284 (← links)
- ML14167A345 (← links)
- ML14115A440 (← links)
- ML14016A279 (← links)
- ML13266A240 (← links)
- ML13249A000 (← links)
- ML13240A499 (← links)
- ML13135A184 (← links)
- ML13079A293 (← links)
- ML12307A408 (← links)
- ML12278A399 (← links)
- TAC:ME9633 (← links)
- ML16280A200 (← links)
- RNP-RA/16-0011, H.B. Robinson Steam Electric Plant, Unit 2 - Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (TAC No. ME9633) (redirect page) (← links)
- RNP-RA/16-0011 (redirect page) (← links)
- RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change (← links)
- RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (← links)
- RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. (← 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)
- RNP-RA/16-0031, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits (← links)
- RNP-RA/16-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits (← links)
- RNP-RA/16-0017, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. (← links)
- RNP-RA/15-0117, Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits (← links)
- RNP-RA/15-0101, Response to NRC Request for Additional Information Regarding License Amendment Request to Change Emergency Action Levels (Eals) Scheme Based on NEI 99-01, Revision 6 (← links)
- RNP-RA/15-0071, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. (← links)
- RNP-RA/14-0028, Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/13-0053, Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... (← links)
- RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (← links)
- RNP-RA/14-0097, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← 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-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)
- RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/13-0134, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/13-0073, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/16-0072, Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 2 (← links)
- RA-19-0154, 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 (Sscs) for Nuclear Power Reactors (← links)
- RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 (← links)
- RA-19-0421, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145) (← links)
- RA-19-0460, Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (← links)
- RA-20-0048, Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections (← links)
- RA-19-0452, Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident (← links)
- RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)