Pages that link to "ML16315A272"

The following pages link to ML16315A272:

Displayed 44 items.

• 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/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals ‎ (← links)
• RA-18-0261, Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints ‎ (← links)
• RA-18-0248, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change ‎ (← 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-17-0055, Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 ‎ (← links)
• RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) ‎ (← links)
• RA-17-0043, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 ‎ (← 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-16-0042, Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed ‎ (← links)
• RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P ‎ (← 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-19-0153, 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 .. ‎ (← links)
• ML18230B133 ‎ (← links)
• RA-19-0316, Response to Request for Additional Information Regarding License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from TS ‎ (← 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-19-0453, Response to Request for Additional Information Regarding License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ‎ (← links)
• HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete ‎ (← 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-20-0287, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protectiv ‎ (← links)
• RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple ‎ (← links)
• RA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . ‎ (← links)
• RA-21-0067, Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval ‎ (← links)
• RA-21-0203, Response to Request for Additional Information Regarding License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications ‎ (← 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-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ‎ (← links)
• RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ‎ (← links)
• RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ‎ (← links)
• RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 ‎ (← links)
• RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 ‎ (← links)
• RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific ‎ (← links)
• RA-24-0165, Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations ‎ (← links)
• RA-24-0172, Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications ‎ (← links)
• RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical. ‎ (← links)
• RA-24-0097, Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations ‎ (← links)
• RA-24-0033, Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals ‎ (← links)
• ML24033A059 ‎ (← links)