Pages that link to "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"
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The following pages link to 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:
Displayed 50 items.
- RA-19-0428, Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension (← links)
- RA-12-041, Carolina Power & Light Company and Florida Power Corporation'S Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number (← links)
- RA-20-0050, Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0 (← links)
- RA-19-0468, Emergency Plan PLP-007, Revision 93 (← links)
- RA-04-0049, Independent Spent Fuel Storage Installation, Annual Report of Individual Exposure Monitoring for 2003 (← links)
- RA-20-0067, Emergency Plan PLP-007, Revision 94 (← 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-20-0157, Supplement to License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 (← links)
- RA-20-0177, Supplement to H.B. Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal - Site Actions (← links)
- RA-20-0374, Transmittal of Core Operating Limits Report for Cycle 33 (← links)
- RA-20-0323, Transmittal of Duke Energy Progress (DEP) Physical Security Plan, Revision 14 (← links)
- RA-20-0382, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model (← links)
- RA-20-0398, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) (← links)
- RA-20-0395, Emergency Action Levels Technical Basis CSD-EP-RNP-0101-02, Revision 1 and Emergency Action Level Wall Chart CSD-EP-RNP-0101-01, Revision 1 (← links)
- RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 (← links)
- RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan (← links)
- RA-19-0393, Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owner'S Activity Report (← links)
- RA-21-0095, Relief Requests for Inservice Testing Program Plan - Sixth Ten-Year Interval (← links)
- RA-21-0056, Refueling Outage 32 Steam Generator Tube Inspection Report (← links)
- JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments (← links)
- RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . (← links)
- JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments (← links)
- RA-20-0329, Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers (← 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)
- RA-21-0311, Response to Confirmatory Order EA-19-025 (← links)
- RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (← links)
- RA-21-0254, Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/ Temperature Limit Cooldown Curves (← links)
- RA-21-0076, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (← links)
- RA-22-0039, Delay of Planned End Date for Fifth 10-Year Inservice Testing (IST) Program Interval (← links)
- RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) (← 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-22-0179, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks (← links)
- RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility (← links)
- RA-22-0037, Emergency Plan Annex, Revision 1 and Emergency Plan Annex, Revision 1, Emergency Action Level (EAL) Wallchart, Revision 2, and EAL Technical Basis Document (← 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-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) (← links)
- RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (← links)
- RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. (← 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-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) (← links)
- RA-22-0347, Transmittal of Core Operating Limits Report (← links)
- RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 (← links)
- ML23011A015 (← links)
- RA-23-0015 (redirect page) (← links)
- ML23040A426 (redirect page) (← links)
- ML23129A001 (← links)
- ML23226A086 (← links)
- RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) (← links)
- RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube (← links)