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| | number = ML062420153 | | | number = ML062420153 |
| | issue date = 08/29/2006 | | | issue date = 08/29/2006 |
| | title = Waterford, Unit 3, Amendment Technical Specification Pages, Moderator Temperature Coefficient | | | title = Amendment Technical Specification Pages, Moderator Temperature Coefficient |
| | author name = Fields M B | | | author name = Fields M |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Venable J E | | | addressee name = Venable J |
| | addressee affiliation = Entergy Operations, Inc | | | addressee affiliation = Entergy Operations, Inc |
| | docket = 05000382 | | | docket = 05000382 |
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| =Text= | | =Text= |
| {{#Wiki_filter:-4-or indirectly any control over (i) the facility, (ii) power or energy produced by the facility, or (iii) the licensees of the facility. | | {{#Wiki_filter: or indirectly any control over (i) the facility, (ii)power or energy produced by the facility, or (iii) the licensees of the facility. Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the NRC's regulations. For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended, are fully applicable to the equity investors and any successors in interest to the equity investors, as long as the license for the facility remains in effect. |
| Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the NRC's regulations. | | (b) Entergy Louisiana, LLC (or its designee) to notify the NRC in writing prior to any change in (i) the terms or conditions of any lease agreements executed as part of the above authorized financial transactions, (ii)any facility operating agreement involving a licensee' that is in effect now or will be in effect in the future, or (iii) the existing property insurance coverages for the facility, that would materially alter the representations and conditions, set forth in the staffs Safety Evaluation enclosed to the NRC letter dated September 18, 1989. In addition, Entergy Louisiana, LLC or its designee is required to notify the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on the operation of the facility. |
| For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended, are fully applicable to the equity investors and any successors in interest to the equity investors, as long as the license for the facility remains in effect.(b) Entergy Louisiana, LLC (or its designee) to notify the NRC in writing prior to any change in (i) the terms or conditions of any lease agreements executed as part of the above authorized financial transactions, (ii) any facility operating agreement involving a licensee'that is in effect now or will be in effect in the future, or (iii) the existing property insurance coverages for the facility, that would materially alter the representations and conditions, set forth in the staffs Safety Evaluation enclosed to the NRC letter dated September 18, 1989. In addition, Entergy Louisiana, LLC or its designee is required to notify the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on the operation of the facility.C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: 1. Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the conditions specified herein.2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 206 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.AMENDMENT NO.206 REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the COLR. The maximum upper design limit shall be: a. Less positive than 0.5 x 104 delta k/k/cF whenever THERMAL POWER is S 7 0%RATED THERMAL POWER, and b. Less positive than 0.0 x 10Q4 delta k/k/OF whenever THERMAL POWER is >70%RATED THERMAL POWER.APPLICABILITY: | | C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| MODES 1 and 2 OX2)ACTION: With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours.SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. | | : 1. Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the conditions specified herein. |
| MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.(3) 4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle: a. Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.(3) | | : 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 206 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| : b. At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup.c. At any THERMAL POWER, within +/- 7 EFPD of reaching two-thirds of expected core burnup.(4)( With Ke,, greater than or equal to 1.0.(2) See Special Test Exception 3.10.2.(33 For fuel cycles that meet the applicability requirements given in WCAP-1601 1-P-A, the verification prior to entering MODE I may be made using the predicted MTC as adjusted for the measured boron concentration. | | AMENDMENT NO. |
| (4) The MTC determination of Paragraph 4.1.1.3.2.c is not required if the results of the tests required in surveillance 4.1.1.3.2.a and 4.1.1.3.2.b are within a tolerance of +/- 0.16 X 10 -4 delta k/k/oF from the corresponding design values. For cycles that meet the applicability requirements given in WCAP-16011-P-A, the MTC determination of surveillance 4.1.1.3.2.c is not required if the result of the test required in surveillance 4.1.1.3.2.b is within a tolerance of+ 0.16 x 10-4 delta k/k/CF from the corresponding design value.WATERFORD | | 206 |
| -UNIT 3 3/4 1-4 AMENDMENT NO. 5-+6,-02 ,-85, 4-59,206}} | | |
| | REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the COLR. The maximum upper design limit shall be: |
| | : a. Less positive than 0.5 x 104 delta k/k/cF whenever THERMAL POWER is S7 0% |
| | RATED THERMAL POWER, and |
| | : b. Less positive than 0.0 x 10Q4 delta k/k/OF whenever THERMAL POWER is >70% |
| | RATED THERMAL POWER. |
| | APPLICABILITY: MODES 1 and 2 OX2) |
| | ACTION: |
| | With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours. |
| | SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. |
| | MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.(3) 4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle: |
| | : a. Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.(3) |
| | : b. At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup. |
| | : c. At any THERMAL POWER, within +/- 7 EFPD of reaching two-thirds of expected core burnup.(4) |
| | ( With Ke,, greater than or equal to 1.0. |
| | (2) See Special Test Exception 3.10.2. |
| | (33 For fuel cycles that meet the applicability requirements given in WCAP-1601 1-P-A, the verification prior to entering MODE I may be made using the predicted MTC as adjusted for the measured boron concentration. |
| | (4) The MTC determination of Paragraph 4.1.1.3.2.c is not required if the results of the tests required in surveillance 4.1.1.3.2.a and 4.1.1.3.2.b are within a tolerance of +/- 0.16 X 10 -4delta k/k/oF from the corresponding design values. For cycles that meet the applicability requirements given in WCAP-16011-P-A, the MTC determination of surveillance 4.1.1.3.2.c is not required if the result of the test required in surveillance 4.1.1.3.2.b is within a tolerance of |
| | + 0.16 x 10-4 delta k/k/CF from the corresponding design value. |
| | WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. 5-+6,-02 ,-85, 4-59,206}} |
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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:Amendment
MONTHYEARW3F1-2022-0054, 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 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 W3F1-2021-0003, 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 ML11224A0102011-07-20020 July 2011 License Amendment Request, Technical Specification Change Regarding Steam Generator Tube Integrity 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 W3F1-2008-0045, 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 W3F1-2007-0036, 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 ML0624201532006-08-29029 August 2006 Amendment Technical Specification Pages, Moderator Temperature Coefficient 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 W3F1-2004-0068, Supplement to Amendment Request NPF-38-249 Extended Power Uprate2004-08-10010 August 2004 Supplement to Amendment Request NPF-38-249 Extended Power Uprate W3F1-2004-0059, Reactor Coolant System Leakage Detection2004-07-0808 July 2004 Reactor Coolant System Leakage Detection W3F1-2004-0014, License Amendment Request, Deletion of Pressurizer Heatup and Cooldown Limits2004-03-15015 March 2004 License Amendment Request, Deletion of Pressurizer Heatup and Cooldown Limits ML0330000142003-10-21021 October 2003 Tech Spec Pages for Amendment 190, Revising the TSs by Changing the Current Main Steam Isolation Valve TS 3/4.7.1.5 to More Closely Reflect TS 3.7.2 Contained in NUREG-1432, Revision 2 W3F1-2002-0073, Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process2002-08-19019 August 2002 Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process ML0207202782002-03-0505 March 2002 Technical Specification Pages for Amendment 181 ML0201002982002-01-0808 January 2002 TS Pages for Amendment No. 177 Re Revision of Reactor Coolant System Cooldown Requirement 2022-11-01
[Table view] |
Text
or indirectly any control over (i) the facility, (ii)power or energy produced by the facility, or (iii) the licensees of the facility. Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the NRC's regulations. For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended, are fully applicable to the equity investors and any successors in interest to the equity investors, as long as the license for the facility remains in effect.
(b) Entergy Louisiana, LLC (or its designee) to notify the NRC in writing prior to any change in (i) the terms or conditions of any lease agreements executed as part of the above authorized financial transactions, (ii)any facility operating agreement involving a licensee' that is in effect now or will be in effect in the future, or (iii) the existing property insurance coverages for the facility, that would materially alter the representations and conditions, set forth in the staffs Safety Evaluation enclosed to the NRC letter dated September 18, 1989. In addition, Entergy Louisiana, LLC or its designee is required to notify the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
- 1. Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the conditions specified herein.
- 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 206 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
AMENDMENT NO.
206
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the COLR. The maximum upper design limit shall be:
- a. Less positive than 0.5 x 104 delta k/k/cF whenever THERMAL POWER is S7 0%
RATED THERMAL POWER, and
- b. Less positive than 0.0 x 10Q4 delta k/k/OF whenever THERMAL POWER is >70%
RATED THERMAL POWER.
APPLICABILITY: MODES 1 and 2 OX2)
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements.
MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.(3) 4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
- a. Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.(3)
- b. At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup.
- c. At any THERMAL POWER, within +/- 7 EFPD of reaching two-thirds of expected core burnup.(4)
( With Ke,, greater than or equal to 1.0.
(2) See Special Test Exception 3.10.2.
(33 For fuel cycles that meet the applicability requirements given in WCAP-1601 1-P-A, the verification prior to entering MODE I may be made using the predicted MTC as adjusted for the measured boron concentration.
(4) The MTC determination of Paragraph 4.1.1.3.2.c is not required if the results of the tests required in surveillance 4.1.1.3.2.a and 4.1.1.3.2.b are within a tolerance of +/- 0.16 X 10 -4delta k/k/oF from the corresponding design values. For cycles that meet the applicability requirements given in WCAP-16011-P-A, the MTC determination of surveillance 4.1.1.3.2.c is not required if the result of the test required in surveillance 4.1.1.3.2.b is within a tolerance of
+ 0.16 x 10-4 delta k/k/CF from the corresponding design value.
WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. 5-+6,-02 ,-85, 4-59,206