Pages that link to "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"
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The following pages link to 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:
Displayed 50 items.
- ML16315A272 (← links)
- ML16230A234 (← links)
- ML16158A006 (← links)
- ML16112A275 (← links)
- ML16063A103 (← links)
- RA-11-008, Progress Energy - Evidence of Guarantee of Payment of Deferred Premiums (← links)
- ML16280A200 (← links)
- RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations (← 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/18-0050, 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)
- RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.46 (← 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)
- RA-13-0051, License Amendment Request to Modify Technical Specification 3.8.1 Proposed Changes to Diesel Generator Testing Requirements (← links)
- RNP-RA/13-0072, Request for Site-Specific Information Related to Use of Gothic Be Withheld from Public Disclosure in Accordance with 10 CFR 2.390(a)(4) (← 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/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-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-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) (← 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-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses (← 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-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-16-0036, Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 0 (← links)
- RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation (← links)
- RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P (← links)
- RA-15-0058, Response to Second NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 (← 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-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted) (← links)
- RA-15-0037, Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 (← 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)