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Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Manual
MONTHYEARML22299A0342022-10-20020 October 2022 Deletion of SLC 16.7-4, Table of Contents ML22242A0072022-08-17017 August 2022 SLC Revisions ML22200A0302022-07-0707 July 2022 SLC Manual Revision to Loes and 16.11-2 ML22174A0802022-06-0101 June 2022 Transmittal External Distribution Notification TR-NUC-CN-014344 - SLC Manual Revision to Loes and SLC 16.7-5 ML22153A0642022-05-0303 May 2022 SLC Manual Revision to 16.11-2 and 16.11-7 ML22095A0042022-03-29029 March 2022 Catawaba Nuclear Station, Units 1 and 2, SLC Manual Revision to 16.7-5 and Loes ML22034A5602022-01-26026 January 2022 Issue CNS SLC Revisions ML21281A2132021-10-0404 October 2021 SLC Manual, Revision to Lees and 16.13-4 ML21281A2082021-09-14014 September 2021 SLC Manual, Revision to Loes and 16.7-9 ML21161A0932021-05-13013 May 2021 SLC Manual Revision to Loes and 16.11-2 ML20066F4882020-02-27027 February 2020 SLC Manual Revision to Loes and 16.9-18 ML20014D6172019-12-19019 December 2019 SLC Manual Revision to Loes and 16.8:2 ML19337A4382019-11-21021 November 2019 SLC Manual Revision to Loes, 16.6-4, 16.7-3, and 16.11-20 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 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-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual ML17038A5262017-01-26026 January 2017 Replacement Pages for the Selected Licensee Commitments Manual ML16208A0712016-07-18018 July 2016 SLC Manual Revision to Loes, 16.7-6 and 16.7-13 ML16175A4272016-06-0707 June 2016 Submittal of Selected License Commitments Manual Change, Rev. 63 CNS-16-037, Ufsar/Selected Licensee Commitment Changes2016-05-26026 May 2016 Ufsar/Selected Licensee Commitment Changes ML13122A2612013-04-17017 April 2013 Meteorological Instrumentation ML13135A0322013-03-25025 March 2013 Offsite Dose Calculation Manual (Odcm), Revision 56 ML12311A5042012-10-18018 October 2012 Submittal of Selected Licensee Commitments Manual Revision 08/02/2012 ML12312A0692012-10-17017 October 2012 Table 16.8-1-2 Unit 2 Cpcopds ML12129A3172012-04-23023 April 2012 Selected Licensee Commitments Manual Revision Dates: 04/11/2012 ML12109A2852012-04-16016 April 2012 Unit 2, Ufsar/Selected Licensee Commitment Changes ML12135A6032012-03-31031 March 2012 Offsite Dose Calculation Manual (Odcm), Revision 55 ML12088A2912012-03-21021 March 2012 Selected Licensee Commitments Manual, Revision Dates: 10/24/2011, 02/20/2012, and 03/5/2012 ML1110103872011-04-0505 April 2011 Selected Licensee Commitments Manual, Revision Date: 02/03/11 ML11123A0492011-01-31031 January 2011 Revision 53 to Offsite Dose Calculation Manual (ODCM) ML1012703122010-04-29029 April 2010 Revision 52 to Offsite Dose Calculation Manual ML1007403712010-02-25025 February 2010 Selected Licensee Commitments Manual, Revision Date 11/23/09 ML0814207582008-01-31031 January 2008 Offsite Dose Calculation Manual (Odcm), 2008, Revision 50 ML0814304342008-01-30030 January 2008 Duke Energy - Radioactive Waste Process Control Program Manual, Revision 15 ML0814305382008-01-30030 January 2008 Duke Energy, Radioactive Waste Process Control Program Manual, Revision 15 ML12135A6022008-01-30030 January 2008 Radioactive Waste Process Control Program Manual, Revision 15 ML0814207702008-01-30030 January 2008 Duke Energy - Radioactive Waste Process Control Program Manual, Revision 15 ML1011900272008-01-30030 January 2008 Radioactive Process Control Program Manual ML11129A2932008-01-30030 January 2008 Corp PCP Nedl Sdqa C Radioactive Waste Process Control Program Manual, Revision 15 ML1012704362008-01-30030 January 2008 Revision 15 to Radioactive Waste Process Control Program Manual CNS-15-041, Radioactive Waste Process Control Program Manual, Revision 152008-01-28028 January 2008 Radioactive Waste Process Control Program Manual, Revision 15 ML0719100452007-01-31031 January 2007 Offsite Dose Calculation Manual (Ocdm), Revision 49 ML0714203312007-01-31031 January 2007 Revision 49 to Offsite Dose Calculation Manual ML0518006342005-06-0101 June 2005 Technical Specifications (TS) Manual ML0613702082005-01-31031 January 2005 Offsite Dose Calculation Manual (Odcm), Revision 47 ML0412800992004-01-31031 January 2004 ODCM Offsite Dose Calculation Manual. ML0412800922003-11-20020 November 2003 2003 Annual Radioactive Effluent Release Report, Nedl Sdqa C Corporate Process Control Program ML0412804342003-11-20020 November 2003 Radioactive Waste Process Control Program Manual, Revision 14 ML0512501142003-11-20020 November 2003 Radioactive Waste Process Control Program Manual ML0612104012003-11-20020 November 2003 Corporate Process Control Program, Revision No. 14 2022-08-17
[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
JAMES R. MORRIS Duke Vice President OEnergye Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax April 16, 2012 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 50.7.1(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 Larry Rudy, Regulatory Compliance, at (803) 701-3084.
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 since the previous submittal.
James R. Morris Attachment Accm www. duke-energy. com
U.S. Nuclear Regulatory Commission April 16, 2012 Page 2 xc: V. M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. H. Thompson NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G. A. Hutto, Senior Resident Inspector Catawba Nuclear Station I
U.S. Nuclear Regulatory Commission April 16, 2012 Page 3 bxc: w/o attachment NCMPA-1 NCEMC PMPA w/attachment Electronic Licensing Library EC050 RGC File CN01RC Master File CN-801.01 CN04DM
DueDUKE D k ENERGY CORPORATION Catawba Nuclear Station Energy 4800 Concord Rd.
York, SC 29745 April 16, 2012 Re: Catawba Nuclear Station Selected Licensee Commitments Manual Revision Dates: 04/11/2012 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 4 Pages 1 through 4 Revision 49 Revision 50 TAB 16.7 SLC 16.7-9 SLC 16.7-9 Revision 6 Revision 7 If you have any questions concerning the contents of this package update, contact Kristi Byers at (803)701-3758.
Manager, Regulatory Compliance Attachment www. duke-energy. com
UPDATE INSTRUCTIONS FOR CATAWBA SELECTED LICENSEE COMMITMENTS (SLC)
MANUAL Please update your copy of the Catawba SLC Manual as follows:
Remove Insert List of Effective Sections, Revision 49 List of Effective Sections, Revision 50 16.7-9, Revision 6 16.7-9, Revision 7
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 13 03/05/12 16.1 1 08/27/08 16.2 2 08/21/09 16.3 1 08/21/09 16.5-1 2 02/20/12 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 0 10/09/02 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 1 08/21/09 16.7-1 1 08/21/09 16.7-2 4 02/03/11 16.7-3 2 02/03/11 16.7-4 2 08/21/09 16.7-5 2 08/21/09 Catawba Units 1 and 2 Page 1 Revision 50
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 2 08/21/09 16.7-7 1 08/21/09 16.7-8 2 08/21/09 16.7-9 7 04/11/12 16.7-10 4 10/24/11 16.7-11 08/21/09 16.7-12 21 08/21/09 16.7-13 2 08/21/09 16.7-14 1 08/21/09 3
16.7-15 1 08/21/09 16.7-16 0 06/08/09 16.8-1 3 08/21/09 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 7 08/21/09 16.9-7 4 08/21/09 16.9-8 5 08/21/09 Catawba Units 1 and 2 Page 2 Revision 50
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.9-9 3 08/21/09 16.9-10 5 08/21/09 16.9-11 3 08/21/09 16.9-12 2 08/21/09 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 0 10/09/02 16.11-2 3 06/23/10 16.11-3 0 10/09/02 Catawba Units 1 and 2 Page 3 Revision 50
LIST OF EFFECTIVE SECTIONS 0 SECTION 16.11-4 REVISION NUMBER 1
REVISION DATE 08/21/09 16.11-5 0 10/09/02 16.11-6 1 06/08/09 16.11-7 6 10/24/11 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 0 10/09/02 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 1 08/21/09 16.11-21 0 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 16.13-4 0 10/09/02 Catawba Units 1 and 2 Page 4 Revision 50
SSS 16.7-9 16.7 INSTRUMENTATION 16.7-9 Standby Shutdown System (SSS)
COMMITMENT The SSS shall be FUNCTIONAL.
APPLICABILITY: MODES 1, 2, and 3.
REMEDIAL ACTIONS
I------------------------------------------------------------
SLC 16.2.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. SSS non-functional. A.1 Restore SSS to 7 days FUNCTIONAL status.
B. Total accumulative B.1 Declare the standby Immediately LEAKAGE from makeup pump non-unidentified LEAKAGE, functional and enter identified LEAKAGE, Condition A.
and reactor coolant pump seal LEAKAGE >
20 gpm.
C. More than one cell in a C.1 Enter Condition A. Immediately 24-Volt battery bank is <
1.36 volts on float charge with no other cells jumpered.
D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
D.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Catawba Units 1 and 2 16.7-9-1 Revision 7
SSS 16.7-9 TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-9-1 Verify that the electrolyte level of each SSS diesel 7 days starting 24-Volt battery is > the low mark and < the high mark.
TR 16.7-9-2 Verify that the overall SSS diesel starting 24-Volt battery 7 days voltage is > 24 volts on float charge.
TR 16.7-9-3 Verify that the requirements of SLC 16.9-21 are met and 7 days the boron concentration in the storage pool is > the minimum specified in the COLR.
TR 16.7-9-4 Verify the fuel level in the SSS diesel generator fuel 31 days storage tank is > 67 inches.
TR 16.7-9-5 Verify the SSS diesel generator starts from ambient 31 days conditions and operates for > 30 minutes at > 700 kW.
TR 16.7-9-6 Verify that the electrolyte level of each SSS 250/125-Volt 31 days battery is above the plates.
TR 16.7-9-7 Verify the total SSS 250/125-Volt battery terminal voltage 31 days is > 258/129 volts on float charge.
TR 16.7-9-8 Perform CHANNEL CHECK of each SSS 31 days instrumentation device.
TR 16.7-9-9 Verify the fuel oil properties of new and stored fuel oil for In accordance with the SSS diesel generator are tested in accordance with, the Diesel Fuel Oil and maintained within the limits of, the Diesel Fuel Oil Testing Program Testing Program.
TR 16.7-9-10 Verify that the SSS diesel starting 24-Volt battery 92 days individual cell voltage is > 1.36 volts on float charge.
(continued)
Catawba Units 1 and 2 16.7-9-2 Revision 7
SSS 16.7-9 TESTING REQUIREMENTS (continued)
TEST FREQUENCY TR 16.7-9-11 Verify that the Standby Makeup Pump's developed head 92 days at the test flow point is > the required developed head, in accordance with the Inservice Testing Program.
TR 16.7-9-12 Verify that the specific gravity of the SSS 250/125-Volt 92 days battery is appropriate for continued service of the battery.
TR 16.7-9-13 Subject the SSS diesel generator to an inspection in 18 months accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
TR 16.7-9-14 Verify that the SSS diesel starting 24-Volt batteries, cell 18 months plates, and battery racks show no visual indication of physical damage or abnormal deterioration.
TR 16.7-9-15 Verify that the SSS diesel starting 24-Volt battery-to- 18 months battery and terminal connections are clean, tight, and free of corrosion.
TR 16.7-9-16 Verify that the SSS 250/125-Volt batteries, cell plates, 18 months and battery racks show no visual indications of physical damage or abnormal deterioration.
TR 16.7-9-17 Verify that the SSS 250/125-Volt battery-to-battery and 18 months terminal connections are clean, tight, free of corrosion, and coated with anti-corrosion material.
TR 16.7-9-18 Verify that the steam turbine driven auxiliary feedwater 18 months pump and controls from the Standby Shutdown Facility function as designed from the SSS.
TR 16.7-9-19 Perform CHANNEL CALIBRATION of each SSS 18 months instrumentation device.
(continued)
Catawba Units 1 and 2 16.7-9-3 Revision 7
SSS 16.7-9 TESTING REQUIREMENTS (continued) 0 TEST FREQUENCY TR 16.7-9-20 Verify proper installation of pressurizer insulation. 18 months TR 16.7-9-21 Verify pressurizer heaters powered from the SSS have a 18 months capacity of > 65 kW.
BASES The SSS is designed to mitigate the consequences of certain postulated fire, security, and station blackout incidents by providing capability to maintain MODE 3 conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50, Appendix R, NUREG-0800, Section 9.5-1, and Appendix A to Branch Technical Position APSCB 9.5-1.
The TESTING REQUIREMENTS ensure that the SSS systems and components are capable of performing their intended functions. The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> uninterrupted operation. It is assumed that, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either offsite power can be restored or additional fuel can be added to the storage tank.
Although the standby makeup pump is not nuclear safety related and was not designed according to ASME Code requirements, it is tested quarterly to ensure its FUNCTIONALITY. The TESTING REQUIREMENT concerning the standby makeup pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Total accumulative LEAKAGE is calculated in the NC System Leakage 0 Calculation procedure as identified + unidentified + seal leakoff (References 2 and 3). The REMEDIAL ACTION limit of 20 gpm total accumulative LEAKAGE provides additional margin to allow for instrument inaccuracy, and for the predicted increase in seal leakoff rate due to heatup of the reactor coolant pump seal injection water supply temperature following the SSS event (due to spent fuel pool heatup).
Following the increase in seal injection temperature, the standby makeup pump flow of 26 gpm is sufficient to provide in excess of this total accumulative LEAKAGE, thereby assuring that reactor coolant system inventory is maintained at MODE 3 conditions. The supporting evaluation is provided in CNC-1223.04-00-0072 (Ref. 4).
A visual inspection of the diesel starting 24-volt batteries, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Since Catawba Units 1 and 2 16.7-9-4 Revision 7
SSS 16.7-9
- BASES (continued) the battery cell jars are not transparent, a direct visual inspection of the cell plates cannot be performed. Instead, the cell plates are inspected for physical damage and abnormal deterioration by: 1) visually inspecting the jar sides of each cell for excessive bowing and/or deformation, and 2) visually inspecting the electrolyte of each cell for abnormal appearance.
Verifying individual cell voltage while on float charge for the SSS diesel starting 24-Volt batteries ensures that each cell is capable of supporting its intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or battery cell) in a fully charged state. The battery cell voltage limit of 1.36 volts is consistent with the nominal design voltage of the battery and is based on the manufacturer's recommended minimum float charge voltage for a fully charged cell with adequate capacity. The battery is designed and sized with a capacity margin sufficient to allow up to one cell per battery bank to be fully degraded with a voltage < 1.36 volts assuming that no cells are jumpered out. The battery sizing calculations account for one degraded cell per battery bank by assuming the degraded cells undergo a worst case polarity reversal during SSS diesel starting.
Verification of proper installation of pressurizer insulation ensures that pressurizer heat losses during an SSS event do not exceed the capacity of the pressurizer heaters powered from the SSS.
Testing of the pressurizer heater capacity ensures the full capacity of the heaters is available to maintain a steam bubble in the pressurizer during an SSS event.
REFERENCES 1. Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.
- 2. PT/1(2)/A/4150/001 D, NC System Leakage Calculation.
- 3. PT/1(2)/A/4150/001 I, Manual NC Leakage Calculation.
- 4. CNC-1223.04-00-0072, Reactor Coolant Pumps No. 1 Seal Leakoff Annunciator Alarm Setpoint for Unit 1 and Unit 2.
- 5. CNS-1560.SS-00-0001, Design Basis Specification for the Standby Shutdown Facility.
- 6. Catawba Technical Specification Amendments 206/200, July 10, 2003.
- 7. Catawba UFSAR, Section 18.2.4.
Catawba Units 1 and 2 16.7-9-5 Revision 7
I . I I SSS 16.7-9 REFERENCES (continued)
- 8. Catawba License Renewal Commitments, CNS-1274.00 0016, Section 4.5.
Catawba Units 1 and 2 16.7-9-6 Revision 7