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Category:Letter type:CNS
MONTHYEARCNS-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 Testing2018-07-19019 July 2018 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-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report 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 System2018-05-0808 May 2018 (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 Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 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 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days 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 Fukus2017-12-28028 December 2017 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 Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 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 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 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 Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask 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 Time2017-09-14014 September 2017 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-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask 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 Pump2017-08-14014 August 2017 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-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations 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 Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 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.2017-01-26026 January 2017 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-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure 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 Accident2016-12-0808 December 2016 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-16-066, 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..2016-10-20020 October 2016 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-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 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) an2016-08-0202 August 2016 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) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask 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/5000/00682016-07-13013 July 2016 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-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23146A0582023-04-24024 April 2023 Updated Final Safety Analysis Report (Revision 23) - Redacted (Public) Copy RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-21-0188, Submittal of Updated Final Safety Analysis Report (Revision 22), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, and 10 CFR 50.59 Evaluation Summary Report2021-10-28028 October 2021 Submittal of Updated Final Safety Analysis Report (Revision 22), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, and 10 CFR 50.59 Evaluation Summary Report ML20106E9182020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 7, Appendix 7B, Figures ML20106E9372020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 13, Figures ML20106E9192020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 7, Appendix 7A, Tables ML20106E9222020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 8, Appendix 8A, Tables ML20106E9232020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML20106E9252020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 9, Appendix 9A, Tables ML20106E9262020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML20106E9272020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 10, Figures ML20106E9282020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 10, Tables ML20106E9292020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20106E9322020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 11, Tables ML20106E9332020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20106E9352020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 12, Tables ML20106E9362020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20106E9392020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML20106E9162020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6A, Tables ML20106E9142020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant and Connected Systems ML20106E9132020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 5, Appendix 5A, Tables ML20106E9122020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 5, Appendix 5B, Figures ML20106E9112020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML20106E9102020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 4, Appendix 4A, Tables ML20106E9092020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 4, Appendix 4B, Figures ML20106E9082020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 3, Design Criteria - Structures, Components, Equipment and Systems ML20106E9072020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3A, Tables ML20106E9052020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics ML20106E9042020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2A, Tables ML20106E9022020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 1, Introduction & General Description of Station ML20106E9012020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 1, Appendix 1A, Tables ML20106E9002020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 1, Appendix 1B, Figures ML20106E8992020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, 2019 Revision 21 Loep - Redacted Version ML20106E8982020-04-0202 April 2020 Submittal of Revision 21 to Updated Final Safety Analysis Report ML20106E9402020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 14, Figures ML20106E9412020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 14, Tables ML20106E9422020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation ML20106E9432020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 15, Figures ML20106E9452020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 15, Tables ML20106E9472020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 16, Selected Licensee Commitments ML20106E9482020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20106E9492020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 18, Tables RA-19-0423, 1 to Updated Final Safety Analysis Report, Report of Information Removed from Revision 21 of the Catawba Nuclear Station, Units 1 and 2 FSAR2020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Report of Information Removed from Revision 21 of the Catawba Nuclear Station, Units 1 and 2 FSAR ML20106E9462020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML20106E9202020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML20106E9172020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML20106E9502020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities ML20106E9382020-04-0202 April 2020 1 to Updated Final Safety Analysis Report, Chapter 13, Tables ML21229A0192019-10-0909 October 2019 1 to Updated Final Safety Analysis Report, Chapter 8, Appendix 8B, Figures NRC (Redacted) RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes 2023-04-24
[Table view] |
Text
I ~-
Kelvin Henderson
((_-..DUKE Vice President
~JENERGYm Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.4251 f: 803.701.3221 CNS-16-050
July 12, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 and Unit 2 Docket Nos. 50-413 and 50-414 UFSAR/Selected Licensee Commitment Changes Pursuant to 10CFR 50. 71 (e), please find attached changes to the Catawba Nuclear Station Selected Licensee Commitments Manual. This document constitutes Chapter 16 of the Updated Final Safety Analysis Report (UFSAR).
Any questions regarding this information should be directed to Tolani Owusu, Regulatory Affairs, at (803) 701-5385.
I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to Chapter 16 of the UFSAR sinceJ previous submittal.
Kelvin Henderson Vice President, Catawba Nuclear Station Attachment
U.S. Nuclear Regulatory Commission July 12, 2016 Page 2 xc: Catherine Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Michael Orenak NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 0-8G9A 11555 Rockville Pike Rockville, MD 20852 J.D. Austin, Senior Resident Inspector Catawba Nuclear Station
Duke Energy
~~DUKE CN01VP I 4800 Concord Road
~ ENERGY~ York, SC 29745 July 12, 2016 Re: Catawba Nuclear Station Selected Licensee Commitments Manual Revision Date: 06/10/2016 Attached are revisions to the Catawba Nuclear Station Selected Licensee Commitments Manual. Please remove and replace the following pages:
REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE SECTIONS Pages 1 through 5 Pages 1 through 5 Revision 64 Revision 65 TAB 16.7-6 16.7-6-1 through 16.7-6-3 16.7-6-1through16.7-6-3 Revision 2 Revision 3
- 16. 7-13-1 through 16. 7-13-5 16.7-13-1through167-13-5 Revision 2 Revision 3 If you have any questions concerning the contents of this package update, contact Toni Lowery at (803)701-5 ~
~chr Regulatory Affairs Manager Attachment
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 15 05/10/16 16.1 1 08/27/08 16.2 2 08/21/09 16.3 1 08/21/09 16.5-1 3 08/19/15 16.5-2 Deleted 16.5-3 1 02/20/04 16.5-4 0 10/09/02 16.5-5 1 01/28/10 16.5-6 1 08/21/09 16.5-7 2 02/06/15 16.5-8 2 12/22/08 16.5-9 1 02/20/12 16.5-10 Deleted 16.6-1 0 10/09/02 16.6-2 Deleted 16.6-3 1 08/21/09 16.6-4 1 08/21/09 16.6-5 2 01/09/13 16.7-1 1 08/21/09 16.7-2 4 02/03/11 16.7-3 4 07/27/13 16.7-4 2 08/21/09 16.7-5 2 08/21/09 Catawba Units 1 and 2 Page 1
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 3 06/10/16 16.7-7 1 08/21/09 16.7-8 2 08/21/09 16.7-9 9 06/06/13 16.7-10 7 03/28/16 16.7-11 1 08/21/09 16.7-12 1 08/21/09 16.7-13 3 06/10/16 16.7-14 1 08/21/09 16.7-15 1 08/21/09 16.7-16 0 06/08/09 16.7-17 0 02/10/15 16.7-18 0 05/10/16 16.8-1 6 12/10/15 16.8-2 2 02/20/12 16.8-3 1 10/24/06 16.8-4 2 11/05/07 16.8-5 3 08/21/09 16.9-1 7 10/24/11 16.9-2 5 10/24/11 16.9-3 3 02/03/11 16.9-4 3 08/21/09 16.9-5 6 06/23/10 16.9-6 10 02/10/15
\ *. ,; . --=~r~Gatawba Units 1 and 2 ** .. ~:._, .. , Page 2
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.9-7 4 08/21/09 16.9-8 5 08/21/09 16.9-9 3 08/21/09 16.9-10 5 08/21/09 16.9-11 3 08/21/09 16.9-12 3 02/10/15 16.9-13 3 08/21/09 16.9-14 1 09/25/06 16.9.:.15 2 08/21/09 16.9-16 ' 2 08/21/09 16.9-17 0 10/09/02 16.9-18 0 10/09/02
'16.9-19 3 02/20/12 16.9-20 0 10/09/02 16.9-21 0 10/09/02 16.9-22 1 08/21/09 16.9-23 4 10/24/11 16.9-24 2 10/24/06 16.9-25 2 08/21/09 16.9-26 0 03/05/12 16.10-1 1 08/21/09 16.10-2 1 10/24/06 16.10-3 1 08/21/09 16.11-1 1 07/27/13
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.11-2 4 02/10/15 16.11-3 0 10/09/02 16.11-4 1 08/21/09 16.11-5 0 10/09/02 16.11-6 3 08/03/15 16.11-7 9 02/10/15 16.11-8 0 '10/09/02 16.11-9 0 10/09/02 16.11-10 1 08/21/09 16.11-11 1 03/20/03 16.11-12 0 10/09/02 16.11-13 1 07/27/13 16.11-14 0 10/09/02 16.11-15 0 10/09/02 16.11-16 1 10/24/11 16.11-17 0 10/09/02 16.11-18 1 08/21/09 16.11-19 0 10/09/02 16.11-20 2 ' 03/28/16 16.11-21 o* 10/09/02 16.12-1 0 10/09/02 16.13-1 0 10/09/02 16.13-2 Deleted 16.13-3 Deleted
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.13-4 0 10/09/02
RN Discharge Instrumentation 16.7-6 16.7 INSTRUMENTATION 16.7-6 RN Discharge Instrumentation COMMITMENT The following shall be FUNCTIONAL:
Instrument Components:
Loops:
1RNFE7520 RN Pump A Discharge Flow Annubar 1RNLP7520 1RNFT7520 RN Pump A Discharge Flow 1RNP7520 RN Pump A Discharge Flow (Control Room Indication) 1RNFE7510 RN Pump B Discharge Flow Annubar 1RNLP7510 1RNFT7510 RN Pump B Discharge Flow 1RNP7510 RN Pump B Discharge Flow (Control Room Indication) 2RNFE7520 RN Pump A Discharge Flow Annubar 2RNLP7520 2RNFT7520 RN Pump A Discharge Flow 2RNP7520 RN Pump A Discharge Flow (Control Room Indication) 2RNFE7510 RN Pump B Discharge Flow Annubar 2RNLP7510 2RNFT7510 RN Pump B Discharge Flow 2RNP7510 RN Pump B Discharge Flow (Control Room Indication)
Annunicators:
1AD12-A/1 RN Pump A Flow Hi/Low 1AD12-A/4 RN Pump B Flow Hi/Low 2AD12-A/1 RN Pump A Flow Hi/Low 2AD12-A/4 RN Pump B Flow Hi/Low APPLICABILITY: Whenever the associated unit's RN train is required to be OPERABLE.
Catawba Units 1 and 2 16.7-6-1 Revision 3
RN Discharge Instrumentation 16.7-6 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more instrument A.1.1 Ensure associated RN Immediately loop(s) and/or pump(s) are not in service.
annunciator(s) non-functional. OR A.1.2 Align affected RN loop(s) Immediately discharge(s) to Standby Nuclear Service Water Pond (SNSWP).
AND A.2 Restore non-functional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> instrument loop(s) and/or annunciator(s) to FUNCTIONAL status.
B. Required Action and B.1 Contact Station Immediately associated Completion Management for additional Time for Condition A not guidance.
met.
TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-6-1 Perform CHANNEL CALIBRATION. 18 months BASES The basis for this SLC is stated in Reference 1, page 11, "Part of the licensing bases of the RN system included the ability for operators to manually change the discharge path for the RN system from the non-safety related Lake Wylie to the safety related SNSWP."
This SLC was developed to address the NRC concerns about actions to be taken in the event instrumentation/alarms were out of service which would impair the ability of operators to recognize loss of the non-safety discharge. This SLC shall ensure the proper actions are taken based on plant equipment conditions.
Catawba Units 1 and 2 16.7-6-2 Revision 3
RN Discharge Instrumentation 16.7-6 REFERENCES 1. NRC Inspection Report, 50-413, 414/94-17, September 9, 1994.
- 2. Catawba Nuclear Station PIP O-C94-1555.
Catawba Units 1 and 2 16.7-6-3 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 16.7 INSTRUMENTATION 16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply Piping Temperat~~/
Monitoring System ~
COMMITMENT a. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System, which is comprised of an Operator Aid Computer (OAC) temperature display graphic, shall be FUNCTIONAL, and
- b. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System high temperature alarm setpoints shall be set to ensure that the design temperature of the steam supply piping (600°F) is not exceeded, and
- c. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low average temperature alarm setpoint shall be set such that a low temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F), and
- d. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low temperature alarm setpoints shall be set such that a low temperature condition is identified prior to an individual piping section reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F).
APPLICABILITY: MODES 1, 2, and 3.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. OAC steam supply A.1 Verify that backup control Immediately piping temperature room steam supply piping monitoring function non- temperature monitoring functional. capability is available.
(continued)
Catawba Units 1 and 2 16.7-13-1 . Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action*to obtain Immediately associated Completion steam supply piping Time for Condition A not temperature using met. alternate means.
AND 8.2 Monitor steam supply ----------NOTE---------
piping temperature using The provisions of alternate means to ensure SLC 16.2.6 are not it is within established applicable.
limits. ---------------------------
' Once per 15 minute~
C. All steam supply piping C.1 Declare the turbine driven Immediately temperature monitoring AFW pump inoperable.
capability lost.
AND C.2 Enter applicable Conditions Immediately and Required Actions of Technical Specification 3.7.5, AFW System, for the inoperable turbine driven AFW pump.
AND C.3 Isolate steam supply to 15 minutes I turbine driven AFW pump.
AND C.4 De-energize turbine driven 15 minutes. I AFW pump steam supply piping heat trace.
(continued)
Catawba Units 1 and 2 16.7-13-2 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. OAC steam supply D.1 Initiate action to restore Immediately piping temperature . OAC steam supply piping monitoring function temperature monitoring alarm setpoints not set function alarm setpoints per COMMITMENT. per COMMITMENT.
D.2 Verify that backup control Immediately room steam supply temperature monitoring capability is available.
TESTING REQUIREMENTS TEST FREQUENCY TR 16. 7-13-1 ----------------------------------NOTE----..----------------------------
. Instrument calibration includes verification of OAC output and OAC alarm setpoints.
Perform calibration of applicable instrumentation and 18 months heat trace controllers.
TR 16. 7-13-2 Perform a visual and thermography inspection of the 18 months steam supply piping heat trace circuitry.
TR 16. 7-13-3 Perform a visual inspection of selected portions* of the Each refueling turbine driven AFW pump steam supply piping for high outage temperature damage.
BASES The turbine driven AFW pump steam supply piping is equipped with heat trace to minimize condensate generation during turbine startup operations.
The heat trace control system is designed to maintain the piping temperature within a narrow operating band. The heat trace is energized and deenergized to maintain the piping temperature within the band.
Catawba Units 1 and 2 16.7-13-3 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System
- 16. 7-13 BASES (continued)
The primary means of monitoring turbine driven AFW pump steam supply piping temperature is the OAC. The OAC data is obtained via piping thermocouples and a local chart recorder (EHCR002). Backup control room temperature monitoring capability is provided via a control room annunciator.
The annunciator is fed via a reflash panel, from the same local chart recorder as the OAC. Alternate means of monitoring turbine driven AFW pump steam supply piping temperature include: the chart recorder local temperature display, the heat trace controller local temperature display, or calibrated, hand-held temperature measuring instruments. It is only when all steam supply piping temperature monitoring capability (including any alternate means) is lost that Condition C is required to be entered. This indicates a condition where the actual temperature of the piping is unknown.
Failure of the heat trace to deenergize could result in the design temperature for the steam supply piping being exceeded. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of high steam supply piping temperatures. The OAC high temperature alarm setpoint is established to ensure that the design temperature of the steam supply piping of 600°F is not exceeded. Upon receipt of the OAC alarm due to high temperature on the steam supply piping, personnel are required to open the heat trace supply breaker for the appropriate high temperature section of piping within 15 minutes. The time limit prevents the possibility of the actual piping temperature reaching the piping design temperature of 600°F.
Low steam supply piping temperatures result in increased condensate formation during turbine driven AFW pump startup. A large volume of condensate in the steam supply piping could result in turbine damage, water hammer, or turbine overspeed trips. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System further ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of low steam supply piping temperatures. The OAC low average temperature alarm setpoints are set such that a low average system temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F). The OAC low temperature alarm setpoints for individual piping sections are set such that a low temperature condition is identified prior to the piping reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F). The 225°F limit is provided to prevent the accumulation of condensate in the piping during periods of standby readiness.
REFERENCES 1.. Problem Investigation Process (PIPs) C-97-0616 and C 1431.
Catawba Units 1 and 2 16.7-13-4 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REFERENCES (continued)
- 2. CNC-1223.43-02-0012, Calculation of Maximum Operator Response Time for SA System Heat Trace Failure to De-energize Scenario.
- 3. CNC-1223.43-02-0009, SA System TDAFWP Steam Supply Pipe Heat Tracing Operability Determination.
Catawba Units 1 and 2 16.7-13-5 Revision 3