Pages that link to "ML16280A200"
Jump to navigation
Jump to search
The following pages link to ML16280A200:
Displayed 50 items.
- RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals (← 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)
- 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/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors (← links)
- 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 (← 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)
- 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)
- 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)
- 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/13-0134, 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/13-0079, 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/13-0073, 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/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)
- 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)
- 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 (← links)
- RNP-RA/06-0081, Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP (← links)
- RNP-RA/06-0062, Groundwater Protection - Data Collection Questionnaire (← links)
- RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure (← links)
- RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis. (← 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-05-0104, Transmittal of Core Operating Limits Report (← 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)
- ML050700408 (← links)
- ML041460246 (← links)
- ML032471632 (← links)
- 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 (← links)
- ML031700027 (← 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)
- RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504 (← links)
- ML031120705 (← links)
- RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent (← links)
- RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License (← links)
- RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 21 (← links)
- ML022110343 (← links)
- RNP-RA/02-0028, Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval (← 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)
- IR 05000261/2021005 (← 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)
- RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) (← links)