Category:Letter type:CNS

C

• CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
• CNS-13-006, 10 CFR 21 Notification - Identification of Defect
• CNS-13-007, Response to Request for Additional Information Regarding the Seismic Hazard Walkdowns Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
• CNS-14-001, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage
• CNS-14-002, Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
• CNS-14-004, Response to Request for Additional Information Dated December 20, 2013, Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power Systems.
• CNS-14-015, Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding Update - Review of Available Physical Margin (APM) Assessments
• CNS-14-020, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
• CNS-14-021, Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds
• CNS-14-025, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
• CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.
• CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications
• CNS-14-035, Submittal of Post Accident Monitoring (PAM) Report
• CNS-14-045, Commitment Change Evaluation Report for 2013
• CNS-14-052, 2013 Annual Radioactive Effluent Release Report
• CNS-14-055, Technical Specification Bases Changes
• CNS-14-056, 301 General Correspondence
• CNS-14-063, 2013 Annual Radiological Environmental Operating Report
• CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate
• CNS-14-079, Technical Specification Bases Changes
• CNS-14-081, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology (Proprietary) Response to NRC Request for Additional Information (RAI)
• CNS-14-086, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
• CNS-14-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Cask
• CNS-14-093, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
• CNS-14-097, Request for Relief Number 14-CN-002, Continued Use of High Density Polyethylene (Hdpe) Material in Nuclear Safety Related Piping Application
• CNS-14-098, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate
• CNS-14-100, Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds
• CNS-14-101, ISFSI - Registration of Spent Fuel Storage Cask Identification Number CN-VCC-76
• CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage
• CNS-14-106, Independent Spent Fuel Storage Installation (ISFSI) - Registration of Spent Fuel Storage Cask
• CNS-14-114, Units 1 & 2 - License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters - Response to NRC Request for Additional Information
• CNS-14-125, Request for Relief Number 14-CN-002 Continued Use of High Density Polyethylene (Hdpe) Material in Nuclear Safety Related Piping Application
• CNS-14-127, Proposed Technical Specifications (TS) Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (Colr), License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measuremen
• CNS-14-128, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable.
• CNS-14-129, Transmittal of Industry High Density Polyethylene (Hdpe) Test Results
• CNS-14-130, Expedited Seismic Evaluation Process Report (CEUS Sites), 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 Fukushima Dai-ichi Accident
• CNS-14-132, Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
• CNS-14-133, Relief Request Serial Number 14-CN-003, Relief Request to Use Alternative Depth Sizing Criteria
• CNS-15-001, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 75-Day Response to NRC Request for Additional...
• CNS-15-002, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable.
• CNS-15-007, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate - Response to NRC Requests for Additional Information (Rals)
• CNS-15-008, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
• CNS-15-009, Errata Letter for 10 CFR 50.54(f) Submittal of Expedited Seismic Evaluation Process (Ese) Report, Revision 2
• CNS-15-013, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
• CNS-15-018, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 120-Day Response to NRC RAI
• CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.
• CNS-15-022, Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities
• CNS-15-027, License Amendment Request (LAR) to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
• CNS-15-031, Commitment Change Evaluation Report for 2014
• CNS-15-035, Catawba, Unit 2 - Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Order to Modify with
• CNS-15-035, Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Order to Modify with Regard.
• CNS-15-039, Letter from Christos S. Kamilaris Effective March 2, 2015, Cecil A. Fletcher II Assumed Responsibilities as the Manager of Nuclear Regulatory Affairs at Catawba Nuclear Station
• CNS-15-046, Request for Relief Number 14-CN-002 Continued Use of High Density Polyethylene (Hdpe) Material in Nuclear Safety Related Piping Application
• CNS-15-047, Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais)
• CNS-15-048, Transmittal of 2014 Annual Radiological Environmental Operating Report
• CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations
• CNS-15-053, Response to Request for Additional Information Regarding Expedited Seismic Evaluation Process Report
• CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.14
• CNS-15-058, Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
• CNS-15-061, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage
• CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)
• CNS-15-066, ISFSI - Registration of Spent Fuel Storage Cask Identification Number CN-VCC-78
• CNS-15-067, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Supplemental Response to NRC Request For..
• CNS-15-068, Response to NRC Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and ...
• CNS-15-070, Supplemental Response to NRC Request for License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
• CNS-15-071, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
• CNS-15-075, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start..
• CNS-15-079, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose -Submitted Pursuant to 10 Cer 50.55a(z)(2)
• CNS-15-080, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
• CNS-15-086, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start..
• CNS-15-098, Technical Specification Bases Changes
• CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
• CNS-15-105, Core Operating Limits Report (COLR) for Cycle 23 Reload Core - Revision 1
• CNS-16-001, License Amendment Request (LAR) to Revise Technical Specifications (TS) Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
• CNS-16-002, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plan, LAR Supplement to Transmit Entire Attachment.
• CNS-16-004, Catawba, Units 1 and 2 - Emergency Plan, Revision 146 Correction
• CNS-16-005, Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Order to Modify.
• CNS-16-012, Transmittal of Core Operating Limits Report (COLR) for Cycle 21 Reload Core - Revision 2
• CNS-16-014, License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And.
• CNS-16-015, Technical Specification Bases Changes
• CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001
• CNS-16-018, Docket Nos.: 50-413 and 50-414 - Commitment Change Evaluation Report for 2015
• CNS-16-020, Inservice Inspection Report for End of Cycle 22 Refueling Outage
• CNS-16-022, Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Et
• CNS-16-023, Independent Spent Fuel Storage Installation (ISFSI) - Re-Registration of Spent Fuel Storage Casks
• CNS-16-026, Transmittal of Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/024, OSC Activation Procedure
• CNS-16-030, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ...
• CNS-16-031, Technical Specification Bases Changes
• 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
• CNS-16-037, Ufsar/Selected Licensee Commitment Changes
• CNS-16-038, Emergency Plan Revision 16-1 Correction (Emergency Plan Manual, Revision 148)
• CNS-16-041, Units, 1 & 2, Independent Spent Fuel Storage Installation (ISFSI) - Registration of Spent Fuel Storage Cask
• CNS-16-042, Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval
• CNS-16-043, Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Forc
• CNS-16-044, Registration of Spent Fuel Storage Casks
• CNS-16-045, Unit 2, Ufsar/Selected Licensee Commitment Changes
• CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems
• CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask
• CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes
• CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an
• CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068
• CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 25
• CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24
• 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..
• CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions
• CNS-16-069, Submittal of Emergency Plan, Revision 16-2
• 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
• CNS-16-080, Submittal of Emergency Plan Implementing Procedure
• CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report
• CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
• CNS-17-008, Commitment Change Evaluation Report for 2016
• CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time
• CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report
• CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing
• CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days
• CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations
• CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report
• CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal
• CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core
• CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report
• CNS-17-033, Technical Specification Bases Changes
• CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report
• CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump
• CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump
• CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask
• CNS-17-042, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE
• CNS-17-044, Inservice Inspection Report for Unit 1 End of Cycle 23 Refueling Outage
• CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding
• CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122
• CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual
• CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask
• CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask
• CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement
• CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2
• CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2
• CNS-17-058, Catawba, 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
• 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
• CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information
• CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
• CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days
• CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing
• CNS-18-015, Commitment Change Evaluation Report for 2017
• CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2
• CNS-18-022, Submittal of Emergency Plan Implementing Procedure
• 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
• CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report
• CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report
• CNS-18-028, 2017 Annual Radiological Environmental Operating Report
• CNS-18-031, Notice of Enforcement Discretion (NOED) Request
• CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report