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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:Technical Specification
MONTHYEARW3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections ML21148A1042021-05-28028 May 2021 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program W3F1-2021-0038, Technical Specification Index and Bases Update to the NRC for the Period June 11, 2019 Through March 3, 20212021-05-18018 May 2021 Technical Specification Index and Bases Update to the NRC for the Period June 11, 2019 Through March 3, 2021 W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B2021-02-0808 February 2021 Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B W3F1-2019-0062, License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2019-09-20020 September 2019 License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2019-0047, Application for Technical Specification Change to Control Room Air Conditioning System2019-08-27027 August 2019 Application for Technical Specification Change to Control Room Air Conditioning System W3F1-2018-0013, Supplement to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-02-28028 February 2018 Supplement to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. W3F1-2017-0079, Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 20172017-12-0606 December 2017 Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 2017 W3F1-2017-0080, Submittal of Technical Requirements Manual Update2017-12-0606 December 2017 Submittal of Technical Requirements Manual Update ML17341A6512017-12-0606 December 2017 Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 2017 ML15170A1262015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 5 of 5 ML15170A1252015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 4 of 5 W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part2015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5 ML15170A1232015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 2 of 5 ML15170A1222015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 1 of 5 W3F1-2014-0067, Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 20142014-11-0505 November 2014 Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 2014 W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years W3F1-2013-0040, Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 20132013-07-0909 July 2013 Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013 W3F1-2011-0080, Technical Specification Bases Update to the NRC for the Period January 25, 2011 Through October 31, 20112011-11-0909 November 2011 Technical Specification Bases Update to the NRC for the Period January 25, 2011 Through October 31, 2011 W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. ML11224A0102011-07-20020 July 2011 License Amendment Request, Technical Specification Change Regarding Steam Generator Tube Integrity W3F1-2011-0010, Submittal of an Update to All Changes Made to Technical Specification Bases for the Period May 25, 2010 Through January 24, 20112011-01-24024 January 2011 Submittal of an Update to All Changes Made to Technical Specification Bases for the Period May 25, 2010 Through January 24, 2011 W3F1-2011-0005, Withdrawal of Technical Specification Change Regarding Steam Generator Program2011-01-19019 January 2011 Withdrawal of Technical Specification Change Regarding Steam Generator Program W3F1-2010-0051, Technical Specification Bases Update to the NRC for Period July 2, 2009 Through May 24, 20102010-05-25025 May 2010 Technical Specification Bases Update to the NRC for Period July 2, 2009 Through May 24, 2010 W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations2010-02-22022 February 2010 . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations W3F1-2009-0031, Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 20092009-07-0909 July 2009 Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 2009 ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 W3F1-2008-0073, Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 20082008-11-11011 November 2008 Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 2008 W3F1-2008-0045, License Amendment Request Relocation of TS 3.7.8 and Addition of LCO 3.0.8 the Inoperability of Snubbers2008-09-18018 September 2008 License Amendment Request Relocation of TS 3.7.8 and Addition of LCO 3.0.8 the Inoperability of Snubbers W3F1-2008-0052, Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration2008-09-17017 September 2008 Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration W3F1-2008-0016, Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 20082008-02-20020 February 2008 Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 2008 W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0036, License Amendment Request NPF-38-270 to Modify Diesel Generator Fuel Oil Testing Surveillance Requirements2007-07-0303 July 2007 License Amendment Request NPF-38-270 to Modify Diesel Generator Fuel Oil Testing Surveillance Requirements W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/20072007-06-13013 June 2007 Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 ML0624201532006-08-29029 August 2006 Amendment Technical Specification Pages, Moderator Temperature Coefficient W3F1-2006-0037, Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 20062006-07-18018 July 2006 Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006 W3F1-2006-0005, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation2006-02-15015 February 2006 License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation W3F1-2005-0075, License Amendment Request NPF-38-266, Remove Limitation to Perform Various Surveillance Only During Shutdown2005-10-27027 October 2005 License Amendment Request NPF-38-266, Remove Limitation to Perform Various Surveillance Only During Shutdown ML0513003032005-05-0909 May 2005 Technical Specifications, Issuance of Amendment No. 200 Modification of TS 5.3.1, Fuel Assemblies; TS 5.6.1, Criticality; TS 6.9.1.11.1, Core Operating Limits Reports & Deletion of TS Index W3F1-2005-0019, Supplement to Amendment Request NPF-38-249, Extended Power Uprate2005-03-17017 March 2005 Supplement to Amendment Request NPF-38-249, Extended Power Uprate W3F1-2004-0090, Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/042004-10-0707 October 2004 Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/04 2023-07-26
[Table view] Category:Bases Change
MONTHYEARW3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement W3F1-2021-0038, Technical Specification Index and Bases Update to the NRC for the Period June 11, 2019 Through March 3, 20212021-05-18018 May 2021 Technical Specification Index and Bases Update to the NRC for the Period June 11, 2019 Through March 3, 2021 W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual W3F1-2019-0047, Application for Technical Specification Change to Control Room Air Conditioning System2019-08-27027 August 2019 Application for Technical Specification Change to Control Room Air Conditioning System W3F1-2018-0013, Supplement to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-02-28028 February 2018 Supplement to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. W3F1-2017-0079, Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 20172017-12-0606 December 2017 Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 2017 W3F1-2017-0080, Submittal of Technical Requirements Manual Update2017-12-0606 December 2017 Submittal of Technical Requirements Manual Update ML17341A6512017-12-0606 December 2017 Technical Specification Index and Bases Update to the NRC for the Period June 2, 2016 Through November 30, 2017 ML15170A1262015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 5 of 5 ML15170A1252015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 4 of 5 W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part2015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5 ML15170A1232015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 2 of 5 ML15170A1222015-06-17017 June 2015 Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 1 of 5 W3F1-2014-0067, Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 20142014-11-0505 November 2014 Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 2014 W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years W3F1-2013-0040, Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 20132013-07-0909 July 2013 Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013 W3F1-2011-0080, Technical Specification Bases Update to the NRC for the Period January 25, 2011 Through October 31, 20112011-11-0909 November 2011 Technical Specification Bases Update to the NRC for the Period January 25, 2011 Through October 31, 2011 W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. W3F1-2011-0010, Submittal of an Update to All Changes Made to Technical Specification Bases for the Period May 25, 2010 Through January 24, 20112011-01-24024 January 2011 Submittal of an Update to All Changes Made to Technical Specification Bases for the Period May 25, 2010 Through January 24, 2011 W3F1-2011-0005, Withdrawal of Technical Specification Change Regarding Steam Generator Program2011-01-19019 January 2011 Withdrawal of Technical Specification Change Regarding Steam Generator Program W3F1-2010-0051, Technical Specification Bases Update to the NRC for Period July 2, 2009 Through May 24, 20102010-05-25025 May 2010 Technical Specification Bases Update to the NRC for Period July 2, 2009 Through May 24, 2010 W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations2010-02-22022 February 2010 . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations W3F1-2009-0031, Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 20092009-07-0909 July 2009 Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 2009 W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 W3F1-2008-0073, Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 20082008-11-11011 November 2008 Technical Specification Bases Update to the NRC for the Period February 16, 2008 Through November 10, 2008 W3F1-2008-0052, Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration2008-09-17017 September 2008 Transmittal of Waterford Steam Electric Station, Unit 3, License Amendment Request to Modify Technical Specification Section 5.6, Fuel Storage and Add New Technical Specification 3/4 9.12, Spent Fuel Pool Boron Concentration W3F1-2008-0016, Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 20082008-02-20020 February 2008 Technical Specification Bases Update to the NRC for the Period June 2, 2007 Through February 15, 2008 W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/20072007-06-13013 June 2007 Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 W3F1-2006-0037, Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 20062006-07-18018 July 2006 Technical Specification Bases Update to the NRC for the Period of November 1, 2005 Through July 1, 2006 W3F1-2004-0090, Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/042004-10-0707 October 2004 Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/04 W3F1-2004-0016, Technical Specificaiton Bases Update to the NRC for Period July 24, 2003 Through February 25, 20042004-02-26026 February 2004 Technical Specificaiton Bases Update to the NRC for Period July 24, 2003 Through February 25, 2004 W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 20032003-07-24024 July 2003 TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003 W3F1-2003-0002, Technical Specification Bases Update to the NRC for the Period October 1, 2002 Through January 7, 20032003-01-15015 January 2003 Technical Specification Bases Update to the NRC for the Period October 1, 2002 Through January 7, 2003 W3F1-2002-0090, Technical Specification Bases Update to the NRC for the Period January 16, 2002 Through September 30, 20022002-10-14014 October 2002 Technical Specification Bases Update to the NRC for the Period January 16, 2002 Through September 30, 2002 W3F1-2002-0012, Revision to Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.22002-01-31031 January 2002 Revision to Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.2 W3F1-2002-0005, Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 20022002-01-16016 January 2002 Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 2002 ML18053A6971991-05-0808 May 1991 License Amendment Request Technical Specification Change Request NPF-38-114 2023-07-26
[Table view] |
Text
W3F1-2011-0080 November 9, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Technical Specification Bases Update to the NRC for the Period January 25, 2011 through October 31, 2011 Waterford Steam Electric Station, Unit 3
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Pursuant to Waterford Steam Electric Station Unit 3 Technical Specification (TS) 6.16, Entergy Operations, Inc. (EOI) hereby submits an update of all changes made to Waterford 3 Technical Specification Bases since the last submittal per letter W3F1-2011-0010 (ADAMS Accession #ML110270215), dated January 24, 2011. This TS Bases update satisfies the submittal frequency requirement listed in 10CFR50.71(e)(4).
There are no commitments associated with this submittal. Should you have any questions or comments concerning this submittal, please contact William J. Steelman at (504) 739-6685.
Sincerely, WJS/RJP/ssf Attachments:
- 1. Waterford 3 Technical Specification Bases Change List
- 2. Waterford 3 Technical Specification Bases Revised Pages
William J. SteelmanLicensing Manager Waterford 3
Entergy Nuclear South Entergy Operations, Inc. 17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 wsteelm@entergy.com W3F1-2011-0080 Page 2 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission
Region IV
612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 RidsRgn4MailCenter@nrc.gov NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 Marlone.Davis@nrc.gov Dean.Overland@nrc.gov U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam
Mail Stop O-07D1 Washington, DC 20555-0001 Kaly.Kalyanam@nrc.gov
Attachment 1 to W3F1-2011-0080 Waterford 3 Technical Specification Bases Change List to W3F1-2011-0080
Page 1 of 2 Waterford 3 Technical Specification (TS) Bases Change List T.S. Bases Change No. Implementation Date Affected TS Bases Pages Topic of Change 68 03/16/11 B 3/4 7-2c B 3/4 7-2d
B 3/4 7-2e
B 3/4 7-2f Change No. 68 to TS Bases section 3/4.7.1.2 Emergency Feedwater System was implemented by Engineering Change (EC) 27828. The change addresses the License Amendment 230, which added ACTION (g) to Technical Specification 3/4.7.1.2 to indicate that the provisions of Specifications 3.0.4 and 4.0.4 are not applicable to the turbine-driven Emergency Feedwater (EFW) pump for entry into Mode 3 only as allowed by Surveillance Requirements 4.7.1.2(b) and 4.7.1.2(c). Change No. 68 to TS Bases section 3/4.7.1.2 explains that ACTION (g) is intended to clarify verbatim compliance issue associated with entering Mode 3 and not having performed the operability testing for the
turbine-driven EFW pump. The exception to TS LCO 3.0.4 and 4.0.4 during plant startup allows the turbine- driven EFW pump to be INOPERABLE only when entering Mode 3 under the conditions and for the period (i.e., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 750 psig in both steam generators) as contained in TSSR 4.7.1.2(b) and 4.7.1.2(c), quarterly Inservice Testing (IST) and 18
month Engineered Safety Features
Actuation System Instrumentation -
Functional Unit Emergency Feedwater (EFAS), respectively. to W3F1-2011-0080
Page 2 of 2 T.S. Bases Change No. Implementation Date Affected TS Bases Pages Topic of Change 69 05/24/11 IX XIV B 3/4 9-2
B 3/4 9-3
B 3/4 9-4
B 3/4 9-5 Change No. 69 to TS Bases section 3/4.9.4, "Containment Building Penetrations" and 3/4.9.9, "Containment Purge Valve Isolation System" was implemented by EC 28875. The change addresses License Amendment 231, which was related to Refueling Outage Penetration Protection. The amendment modified Technical Specification (TS) 3/4.9.4, "Containment Building Penetrations" to allow alternative means of penetration closure during Core Alterations or irradiated fuel movement while in refueling operations.
Additionally TS 3/4.9.9, "Containment Purge Valve Isolation System" was eliminated and those actions and surveillance requirements being retained were moved into TS 3/4.9.4 and the associated TS Bases. In addition, the TS Index Pages for the changes to TS 3/4.9.4 and deletion of
TS 3/4.9.9 are included in the page changes.
Attachment 2 to W3F1-2011-0080 Waterford 3 Technical Specification Bases Revised Pages (There are 12 unnumbered pages following this cover page)
TECHNICAL SPECIFICATION BASES CHANGE NO. 68 REPLACEMENT PAGE(S)
(4 pages)
Replace the following pages of the Waterf ord 3 Technical Specification Bases with the attached pages. The revised pages are identified by Change Number 68 and contain the appropriate EC number and a vertical line indicating the areas of change.
Remove Insert B 3/4 7-2c B 3/4 7-2c B 3/4 7-2d B 3/4 7-2d B 3/4 7-2e B 3/4 7-2e B 3/4 7-2f B 3/4 7-2f
WATERFORD - UNIT 3B 3/4 7-2cCHANGE NO. 7 , 68 PLANT SYSTEMS BASES
3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM (Continued)
Limiting Conditions for Operation (Continued)
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time is reasonable based on the redundant capabilities afforded by the EFW system, the time needed for repairs, and the low probability of a design
basis event occurring during this period. e.By maintaining OPERABLE pumping capacity capable of supplying 100% of the required EFW flow and flow paths capable of delivering 100% of the required EFW flow to the
steam generators the EFW system is capable of supporting a unit cooldown but may not
be capable of performing its design function of residual heat removal for all events. Due to
the seriousness of this condition, the unit must be placed in at least MODE 3 within 6
hours, and in MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed completion time is
reasonable, based on operating experience, to reach the required unit conditions from
full power conditions in an orderly m anner and without challenging unit systems.
This ACTION primarily addresses flow pat h inoperability when the system no longer has the ability to deliver 100% of the required EFW flow to one or both steam generators. For
example, with one flow path inoperable and not able to provide 100% flow to its
respective steam generator this ACTION would be entered. Similarly, if both flow paths
were inoperable and only one of the inoperable flow paths could provide 100% of the
required EFW flow to its respective steam generator this ACTION would be entered.
Also, if both flow paths were inoperable and neither could provide 100% of the required
EFW flow to its respective steam generator but together both flow paths could provide
100% of the required EFW flow to the steam generators (e.g., 50% to one and 50% to
the other (or some combination equaling 100%)) this ACTION would be entered. f.ACTION (f) indicates that all required MODE changes or power reductions are suspended until the EFW system is capable of delivering 100% of the required EFW flow
to the steam generators.
With pumping capacity unable to supply 100% of the required EFW flow and/or two flow paths not capable of delivering 100% of the required EFW flow to the steam generators
in MODEs 1, 2, and 3, the unit is in a seriously degraded condition with no safety-related
means for conducting a cooldown. In such a condition, the unit should not be perturbed
by any action, including a power change that might result in a trip. The seriousness of
this condition requires that action be started immediately to restore the ability to deliver at
least 100% of the required EFW flow to the steam generators combined as soon as
possible. This ACTION is modified to indicate that all MODE changes or power reductions
are suspended until the ability to deliver 100% of the required flow to the
steam generators combined can be restored because they could force the unit into a less
than safe condition.
>(EC-27828, Ch. 68)g.ACTION (g) is intended to clarify verbatim compliance issue associated with entering Mode 3 and not having performed the operability testing for the turbine-driven EFW pump.
The exception to TS LCO 3.0.4 and 4.0.4 during plant startup allows the turbine-
<(EC-27828, Ch. 68)
WATERFORD - UNIT 3B 3/4 7-2d CHANGE NO. 7, 30, 37, 68 PLANT SYSTEMS BASES
3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM (Continued)
Limiting Conditions for Operation (Continued)
>(EC-27828, Ch. 68) driven EFW pump to be INOPERABLE only when entering Mode 3 under the conditions and for the period (i.e., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 750 psig in both steam generators) as contained in TS SR 4.7.1.2(b) and 4.7.1.2(c), quarterly Inservice Testing (IST) and 18 month Engineered Safety Features Actuation System Instrumentation - Functional Unit
Emergency Feedwater (EFAS), respectively. When the plant enters Mode 3 during a
plant startup coming out of an outage, there is insufficient steam pressure to complete
the dynamic final calibration of the governor valve speed control unit of the turbine-
driven EFW pump. In this condition, the turbine-driven EFW pump is available (i.e., there is a reasonable expectation that once sufficient steam pressure is available to the
turbine-driven EFW pump turbine, it will be able to successfully complete the quarterly IST and 18 month EFAS surveillance requirements to fully demonstrate operability).
Although the turbine-driven EFW pump does not have sufficient steam pressure to
complete dynamic final calibration of the governor valve speed control unit, the turbine-
driven EFW pump still maintains performance capability (albeit at a potentially reduced
flow performance based upon governor valve speed control unit settings) to provide the
system safety function of cooling the plant to shutdown cooling entry conditions. This
exception does not allow Mode 3 to be entered during a plant startup while performing
maintenance activities that cause the turbine driven EFW pump to be unavailable. The safety function of the EFW System to ensure the Reactor Coolant System can be cooled to shutdown cooling system entry conditions continues to be met under all plant
conditions and for the worst case postulated accident from the point in time when the
plant enters Mode 3 during the plant startup with the inoperable turbine-driven EFW
pump through the point in time when the turbine-driven EFW pump is restored to
OPERABLE condition. The delay of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both steam generators have reached
sufficient steam pressure on the secondary side is to complete post maintenance
activities (i.e., dynamic final calibration of the governor valve speed control unit) and
then to complete IST and EFAS testing surveillance requirements.
Prior to entry into Mode 2, surveillance requirement testing of various combinations of EFW pumps and valves will ensure ALL requi red EFW system flow paths and equipment (including the turbine-driven EFW pump as previously described in second paragraph of
this section of the bases) are demonstrated operable before the core is taken critical and
significant heat is generated.
<(EC-27828, Ch. 68)
Surveillance Requirementsa. Verifying the correct alignment for manual, power operated, and automatic valves in the EFW water and steam supply flow paths provides assurance that the proper flow paths
exist for EFW operation. This Surveillance Requirement (SR) does not apply to valves
that are locked, sealed, or otherwise secured in position, since these valves are verified
to be in the correct position prior to locking, sealing, or securing. This SR also does not
apply to valves that cannot be inadvertently misaligned, such as check valves. This SR
does not require any testing or valve manipulation; rather, it involves verification that
those valves capable of potentially being mispositioned are in the correct position.
WATERFORD - UNIT 3B 3/4 7-2eCHANGE NO. 7, 68 PLANT SYSTEMS BASES
3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM (Continued)
Surveillance Requirements (Continued)
>(DRN 03-1807, Ch. 30)b. The SR to verify pump OPERABILITY pur suant to the Inservice Testing Program ensures that the requirements of ASME Code Section XI are met and provides
reasonable assurance that the pumps are capable of satisfying the design basis
accident flow requirements. Because it is undesirable to introduce cold EFW into the
steam generators while they are operating, test ing is typically performed on recirculation flow. Such in-service tests confirm component OPERABILITY, trend performance, and
detect incipient failures by indicating abnormal performance.
<(DRN 03-1807, Ch. 30)
This SR is modified to indicate the SR should be deferred until suitable test conditions
have been established. This deferral is required because there is an insufficient steam
pressure to perform post maintenance activities which may need to be completed prior to
performing the required turbine-driven pump SR. This deferral allows the unit to
transition from MODE 4 to MODE 3 prior to the performance of the SR and provides a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period once a steam generator pressure of 750 psig is reached to complete the
required post maintenance activities and SR. If this SR is not completed within the 24
hour period or fails, then the appropriate ACTION must be entered. The twenty-five
percent grace period allowed by TS 4.0.2 can not be applied to the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
>(DRN 05-42, Ch. 37)c. The SR for actuation testing ensures that EFW can be delivered to the appropriate steam generator in the event of any accident or transient that generates EFAS and/or
MSIS signals, by demonstrating that each automat ic valve in the flow path actuates to its correct position and that the EFW pumps will start on an actual or simulated actuation
signal. This Surveillance covers the automatic flow control valves, automatic isolation
valves, and steam admission valves but is not required for valves that are locked,
sealed, or otherwise secured in the required position under administrative controls. The
18 month frequency is acceptable, based on the design reliability and operating
experience of the equipment.
<(DRN 05-42, Ch. 37)
This SR is modified to indicate that the SR should be deferred until suitable test
conditions have been established. This deferral is required because there is an
insufficient steam pressure to perform post maintenance activities which may need to be
completed prior to performing the required turbine-driven pump SR. This deferral allows
the unit to transition from MODE 4 to MODE 3 prior to the performance of the SR and
provides a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period once a steam generator pressure of 750 psig is reached to
complete the required post maintenance activities and SR. If this SR is not completed
within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period or fails, then the appropriate ACTION must be entered. The
twenty-five percent grace period allowed by TS 4.0.2 can not be applied to the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
period.
WATERFORD - UNIT 3B 3/4 7-2fCHANGE NO. 7, 38, 68 PLANT SYSTEMS BASES
3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM (Continued)
Surveillance Requirements (Continued)d. The SR for flow testing ensures that the EF W system is aligned properly by verifying the flow paths from the condensate storage pool (CSP) to each steam generator before
entering MODE 2 operation after being in MODE 4, 5, 6, or defueled, for 30 days or
longer, or whenever feedwater line cleaning through the emergency feedwater line has
been performed. Various combinations of pumps and valves may be used such that all
flow paths (and flow legs) are tested at least once during the Surveillance.
OPERABILITY of EFW flow paths must be verified before sufficient core heat is generated that would require the operation of the EFW System during a subsequent
shutdown. The frequency is reasonable, based on engineering judgment, and other
administrative controls to ensure that flow paths remain OPERABLE. To further ensure
EFW system alignment, the OPERABILITY of the flow paths is verified following
extended outages to determine that no misalignment of valves has occurred. This SR
ensures that the flow paths from the CSP to the steam generators are properly aligned.
3/4.7.1.3 CONDENSATE STORAGE POOL The OPERABILITY of the condensate storage pool (CSP) with the minimum water volume of 173,500 gallons (170,000 gallons for EFW system usage and 3,500 gallons for CCW
makeup system usage), plus makeup from one Wet Cooling Tower (WCT) basin, ensures that
sufficient water is available to cool the Reactor Coolant System to shutdown cooling entry
conditions following any design basis accident. This makeup water includes the capability to
maintain HOT STANDBY for at least an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to initiating shutdown cooling.
The combined capacity (CSP and one WCT) provides sufficient cooling for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until shutdown cooling is initiated in the event the ultimate heat sink sustains tornado damage
concurrent with the tornado event.
If natural circulation is required, the combined capacity (CSP and one WCT) is sufficient to maintain the plant at HOT STANDBY for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to shutdown cooling
entry conditions assuming the availability of only onsite or only offsite power, and the worst
single failure (loss of a diesel generator or atmospheric dump valve). This requires
approximately 303,000 gallons of EFW and complies with BTP RSB 5-1.
>(DRN 04-1243, Ch. 38)
The CSP contained water volume limit (92% indicated in MODES 1, 2, and 3) includes an allowance for water not usable because of vortexing and instrumentation uncertainties. This
provides an assurance that a minimum of 170,000 gallons is available for the EFW system and
that 3,500 gallons is available for the CCW makeup system. The CSP contained water volume
limit (11% indicated in MODE 4) also includes an allowance for water not usable because of
vortexing and instrumentation uncertainties. This provides an assurance that minimum of 3,500
gallons is available in the CSP for the CCW makeup system.
The maximum limit on CSP temperature ensures that the assumptions used in design basis accidents with EFW flow remain valid. The minimum limit on CSP temperature ensures
that the assumptions used in the MSLB return to power event remain valid.
<(DRN 04-1243, Ch. 38)
TECHNICAL SPECIFICATION BASES CHANGE NO. 69 REPLACEMENT PAGE(S)
(6 pages)
Replace the following pages of the Waterf ord 3 Technical Specification Bases with the attached pages. The revised pages are identified by Change Number 69 and contain the appropriate EC number and a vertical line indicating the areas of change.
Remove Insert IX IX XIV XIV B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 B 3/4 9-3 B 3/4 9-4 B 3/4 9-4 B 3/4 9-5 B 3/4 9-5
>(DRN 05-747, Ch. 40)WATERFORD - UNIT 3IX
<(DRN 05-747, Ch. 40)
AMENDMENT NO. 176 CHANGE NO. 40 , 65, 69>(DRN 05-747, Ch. 40)
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS (Continued)3/4.8.3ONSITE POWER DISTRIBUTION SYSTEMS OPERATING........................................................................3/4 8-13 SHUTDOWN........................................................................3/4 8-153/4.8.4ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOROVERCURRENT PROTECTIVE DEVICES....................3/4 8-16 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES...................................3/4 8-52 3/4.9 REFUELING OPERATIONS3/4.9.1BORON CONCENTRATION....................................................3/4 9-13/4.9.2INSTRUMENTATION..............................................................3/4 9-2 3/4.9.3DECAY TIME.......................................................................... 3/4 9-3 3/4.9.4CONTAINMENT BUILDING PENETRATIONS........................3/4 9-4 3/4.9.5COMMUNICATIONS................................................................3/4 9-5 3/4.9.6REFUELING MACHINE...........................................................3/4 9-6 3/4.9.7CRANE TRAVEL - FUEL HANDLING BUILDING....................3/4 9-7 3/4.9.8SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL...........................................................3/4 9-8 LOW WATER LEVEL............................................................3/4 9-9
>(EC-28875, Am. 69)3/4.9.9DELETED................................................................................3/4 9-10
<(EC-28875, Am. 69)3/4.9.10WATER LEVEL - REACTOR VESSEL FUEL ASSEMBLIES............................................................3/4 9-11 CEAs.....................................................................................3/4 9-123/4.9.11WATER LEVEL - SPENT FUEL POOL...................................... 3/4 9-13
>(EC-18742, Ch. 65)3/4.9.12SPENT FUEL POOL (SFP) BORON CONCENTRATION............ 3/4 9-13a3/4.9.13SPENT FUEL STORAGE.............................................................3/4 9-13b
<(EC-18742, Ch. 65)3/4.10 SPECIAL TEST EXCEPTIONS3/4.10.1SHUTDOWN MARGIN................................................................. 3/4 10-1
<(DRN 05-747, Ch. 40)
>(DRN 05-747, Ch. 40)WATERFORD - UNIT 3XIV
<(DRN 05-747, Ch. 40)
AMENDMENT NO 68
, 176 , 188 CHANGE NO. 40 , 69>(DRN 05-747, Ch. 40)
INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued)
>(EC-28875, Am. 69)3/4.9.9DELETED 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL POOL............................................................
B 3/4 9-4<(EC-28875, Am. 69)3/4.10 SPECIAL TEST EXCEPTIONS3/4.10.1SHUTDOWN MARGIN.........................................................B 3/4 10-13/4.10.2MTC, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.......................................B 3/4 10-13/4.10.3REACTOR COOLANT LOOPS...........................................B 3/4 10-1 3/4.10.4CENTER CEA MISALIGNMENT...........................................B 3/4 10-1 3/4.10.5NATURAL CIRCULATION TESTING....................................B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1LIQUID EFFLUENTS............................................................B 3/4 11-13/4.11.2GASEOUS EFFLUENTS......................................................B 3/4 11-3
<(DRN 05-747, Ch. 40)
AMENDMENT NO. 144, 148
, CHANGE NO. 19, 21
, 62, 69WATERFORD - UNIT 3B 3/4 9-2 REFUELING OPERATIONS BASES
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS (Continued)
>(DRN 03-178, Ch. 21) closure" rather than "containment OPERABILITY."
Containment closure means that all potential escape paths are closed or capable of being closed. Since there is no potential for containment
pressurization, the Appendix J leakage criteria and tests are not required.
During CORE ALTERATIONS or movement of irradiated fuel within the containment, the escape of radioactivity to the environment is minimized when the LCO requirements are met.
>(EC-28875, Ch. 69)
Containment penetrations, the personnel airlock doors, and/or the equipment door may be open under administrative control during CORE ALTERATIONS or movement of irradiated
fuel in the containment provided a minimum of one closure method (manual or automatic valve, blind flange, or equivalent) in each penetration, one door in each airlock, and the equipment
door are capable of being closed in the event of a fuel handling accident. For closure, the
equipment door will be held in place by a minimum of four symmetrically-placed bolts.
Containment penetrations that provide direct access from containment atmosphere to outside atmosphere must be isolated or capable of being isolated on at least one side. Equivalent
isolation methods must be approved and may include use of a material that can provide a
temporary, atmospheric pressure ventilation barrier for the other containment penetrations
during CORE ALTERATIONS or movement of irradiated fuel.
The containment purge and exhaust isolation system must also be OPERABLE during CORE ALTERATIONS or movement of irradiated fuel when open to the outside atmosphere or
must be closed under LCO 3.9.4.c.1. An OPERABLE containment purge and exhaust isolation
system consists of a containment purge valve capable of isolating on an actual or simulated
actuation signal from containment purge isolation from each of the required radiation monitoring instrumentation channels (Note that Technical Specifications 3/4.3.3, Radiation Monitoring is
also applicable). The containment purge lines are automatically closed upon a containment
purge isolation signal (CPIS) if the fuel handling accident releases activity above prescribed
levels. Closure of at least one of the containment purge isolation valves is sufficient to provide
closure of the penetration.
Administrative controls shall ensure that appropriate personnel are aware that when the equipment door, both personnel airlock doors, and/or containment penetrations are open, a
specific individual(s) is designated and available to close the equipment door, an airlock door
and the penetrations as part of a required evacuation of containment, and any obstruction(s)
(e.g., cables and hoses) that could prevent closure of an airlock door and the equipment door
be capable of being quickly removed.
<(DRN 03-178, Ch. 21; EC-28875, Ch. 69) 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition
during CORE ALTERATIONS.
WATERFORD - UNIT 3B 3/4 9-3CHANGE NO. 19, 21, 69 REFUELING OPERATIONS BASES
3/4.9.6 REFUELING MACHINE
>(EC-17724, Ch. 62)
The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) each hoist has sufficient
load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are
protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. The Technical Specification Actions 'a.' and 'b.' statements allow the movement of
a fuel assembly or CEA to safe condition using administrative controls in the event of a refueling
machine failure.
<(EC-17724, Ch. 62) 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA, and associated handling tool over other irradiated fuel assemblies in the Fuel Handling
Building ensures that in the event this load is dropped (1) the activity release will be limited to
that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage
racks will not result in a critical array. This assumption is consistent with the activity release
assumed in the safety analyses.
3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION
>(DRN 03-375, Ch. 19)
The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the
reactor pressure vessel below 140°F as required during the REFUELING MODE, and
(2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of
a boron dilution incident and prevent boron stratification. If SDC loop requirements are not met, there will be no forced circulation to provide mixing to establish uniform boron concentrations.
Suspending positive reactivity additions that could result in failure to meet the minimum boron
concentration limit is required to assure continued safe operation. Introduction of coolant
inventory must be from sources that have a boron concentration greater than that which would
be required in the RCS for minimum refueling boron concentration. This may result in an overall
reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical
operations.
<(DRN 03-375, Ch. 19)
The requirement to have two shutdown cooli ng trains OPERABLE when there is less than 23 feet of water above the top of the fuel seated in the reactor pressure vessel ensures that a
single failure of the operating shutdown cooling train will not result in a complete loss of decay
heat removal capability. When there is no irradiated fuel in the reactor pressure vessel, this is
not a consideration and only one shutdown cooling train is required to be OPERABLE. With the
reactor vessel head removed and 23 feet of water above the top of the fuel seated in the reactor
pressure vessel, a large heat sink is available for core cooling, thus in the event of a failure of the
operating shutdown cooling train, adequate time is provided to initiate emergency procedures to
cool the core.
WATERFORD - UNIT 3B 3/4 9-4CHANGE NO. 19, 21, 22, 39, 65, 69 REFUELING OPERATIONS BASES
>(DRN 03-233, Ch. 22; EC-28875, Am. 69
)<(DRN 03-233, Ch. 22; EC-28875, Am. 69
) 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL POOL
>(DRN 05-131, Ch. 39)
The restrictions on minimum water level ensure that sufficient water depth is available such that the iodine released as a result of a rupture of an irradiated fuel assembly is reduced
by a factor of at least 200. Gap fractions are assumed in accordance with Regulatory Guide
1.183 guidance. The minimum water depth is consistent with assumptions of the safety
analysis.<(DRN 05-131, Ch. 39)
>(EC-18742, Ch. 65) 3/4.9.12 and 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION and SPENT FUEL STORAGE TS 5.6, "FUEL STORAGE," reflects the results of the criticality analysis, crediting soluble boron and allowing more flexibility in storing the more reactive Next Generation Fuel (NGF)
assemblies in the spent fuel storage racks. The Waterford 3 SFP criticality analysis used a
design acceptance criteria of effective (neutron) multiplication factor (keff) no greater than 0.995, if flooded with unborated water, and keff no greater than 0.945, if flooded with borated water.
This provides an additional 0.005 keff analytical margin to the regulatory requirement. This approach provides sufficient margin to offset minor non-conservatisms to provide reasonable
assurance that the regulatory requirements are met. Each storage configuration has a
geometric arrangement which must be maintained so that the SFP criticality analysis remains
valid.The spent fuel pool (SFP) criticality analysis credits 524 parts per million (ppm) of soluble boron to maintain keff less than 0.95 in the SFP during normal conditions, and 870 ppm under the worst-case accident conditions. The analysis determined that a misloading event in
the spent fuel checkerboard loading pattern would have the largest reactivity increase, requiring
870 ppm of soluble boron to meet the regulation. The boron dilution analysis identified a
number of assorted sources for slow addition of unborated water to the SFP that could possibly
continue undetected for an extended period of time. The maximum flow from any of these
sources was determined to be 2 gpm, and dilution of the SFP from 1900 ppm to 870 ppm
soluble boron would take approximately 72 days.
Slow dilution by undetected sources is adequately addressed by sampling the SFP on the 7-day frequency of SR 4.9.12. Higher flow-
rate dilution scenarios would be identified through various alarms and building walkdowns, and
<(EC-18742, Ch. 65)
WATERFORD - UNIT 3B 3/4 9-5CHANGE NO. 65, 69>(EC-18742, Ch. 65)
REFUELING OPERATIONS BASES
3/4.9.12 and 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION and SPENT FUEL STORAGE (Continued) could be addressed by sampling the SFP on the 7-day frequency of SR 4.9.12. Higher flow-rate dilution scenarios would be identified through various alarms and building walkdowns, and could
be addressed within a sufficient time to preclude dilution of the SFP to 870 ppm soluble room.
Adequate safety is maintained in the case of a high flow-rate dilution of the SFP in accordance
with 10 CFR 50.68(b)(4) because keff must remain below 1.0 (subcritical), even if the SFP were flooded with unborated water.
Three qualified storage configurations are allowed for Region 2 Fuel Storage locations, based on burnup versus enrichment restrictions: 1) uniform loading of assemblies, 2)
checkerboard loading of high and low reactivity assemblies, and 3) checkerboard loading of
fresh assemblies and empty cells. The storage configurations may be interspersed with each
other throughout the SFP, provided that the geometric interface requirements are met.
Checkerboard loading is not required for Region I Fuel Storage locations.
<(EC-18742, Ch. 65)