Pages that link to "RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage"
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The following pages link to RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage:
Displayed 33 items.
- 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-18-0097, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System (← links)
- CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System (← links)
- CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus (← links)
- RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. (← links)
- CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← 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)
- NRC-18-0016, Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.. (← links)
- MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-003 (← links)
- CNS-16-035, License Amendment Request to Revise Technical Specifications Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Requests for Additional Information CAC Nos. MF7265 and MF7266 (← links)
- CNS-16-010, Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 (← links)
- RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 (← links)
- RA-19-0280, Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 (← links)
- CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding (← links)
- ML20052D936 (← links)
- RA-20-0002, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits (← links)
- CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 (← links)
- RA-20-0104, Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R23 (← links)
- RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period (← links)
- RA-21-0017 (redirect page) (← links)
- ML21029A265 (redirect page) (← links)
- ML21131A026 (← links)
- EPID:L-2020-LLA-0192 (← links)
- ML21131A026 (← links)
- RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 (← links)
- RA-21-0321, Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report (← links)
- RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative (← links)
- RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology (← links)
- RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle (← links)
- RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds (← links)
- RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) (← links)
- 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 (← links)