Pages that link to "RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report"
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The following pages link to RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report:
Displayed 50 items.
- ML16244A060 (← links)
- ML16230A006 (← links)
- ML16056A242 (← links)
- ML17349A157 (← links)
- ML15343A012 (← links)
- ML18191A564 (← links)
- ML16294A254 (← links)
- RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (← links)
- RA-17-0051, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating (← links)
- RA-16-0032, Duke Energy Regulatory Commitment Change Related to Loss of Coolant Accident Reanalysis to Address Fuel Pellet Thermal Conductivity Degradation (← links)
- RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations (← links)
- RA-14-0015, Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Catawba and McGuire Nuclear Stations (← links)
- RA-18-0114, License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (← links)
- RA-17-0049, Withdrawal of Application to Adopt ASME Code Case OMN-20 for Pump and Valve Inservice Testing (← links)
- RA-18-0184, Withdrawal of License Amendment Request to Revise Technical Specification (TS) 4.2.2, Control Rod Assemblies (← links)
- MNS-16-007, Relief Request 15-MN-003, Limited Weld Examinations, Response to Request for Additional Information (← links)
- MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System (← links)
- RA-18-0235, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments (← links)
- RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles (← links)
- MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles (← links)
- RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs (← links)
- MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies (← links)
- MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal (← links)
- RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers (← links)
- MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies (← links)
- RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers (← links)
- MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information (← links)
- MNS-15-066, Response to NRC June 18, 2015 and May 8, 2015 Requests for Additional Information Re License Amendment Request to Implement Risk-Informed Performance-Based Fire Protection Program (← links)
- MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension (← links)
- MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. (← links)
- MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) (← links)
- MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation (← links)
- MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension (← links)
- MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. (← links)
- MNS-15-073, Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension (← links)
- MNS-15-070, Response to August 18, 2015, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program (← links)
- MNS-15-062, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition (← links)
- MNS-15-052, Response to June 18, 2015, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program (← links)
- RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A (← links)
- RA-18-0273, End of Cycle 25 In-service Inspection Summary Report (← links)
- RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 (← links)
- RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 (← 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-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS (← links)
- RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. (← links)
- CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. (← links)
- MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications (← links)
- RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions (← links)
- RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding (← links)