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| | number = ML081510175 | | | number = ML081510175 |
| | issue date = 06/27/2008 | | | issue date = 06/27/2008 |
| | title = Comanche Peak Units 1 and 2 - License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt | | | title = License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
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| {{#Wiki_filter:-3-(3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented | | {{#Wiki_filter: (3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by 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 I 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 Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 13 and 3612 megawatts thermal starting with Cycle 14 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. 146 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | Unit 1 Amendment No. 146 |
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| and amended;(4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission | | (3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| =s regulations set forth in 10 CFR Chapter I 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 LevelLuminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 13 and 3612 megawatts thermal starting with Cycle 14 in accordance with the conditions specified herein. (2) Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A as revised through Amendment No. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Unit 1 Amendment No. | | 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 I 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: |
| 146 146 (3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented
| | (1) Maximum Power Level Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 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. 146 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Antitrust Conditions DELETED Unit 2 Amendment No. 146 |
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| and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission
| | Definitions 1.1 1.1 Definitions (continued) |
| =s regulations set forth in 10 CFR Chapter I 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 LevelLuminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 in accordance with the conditions specified herein. (2) Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A as revised through Amendment No. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Antitrust Conditions DELETEDUnit 2 Amendment No.
| | QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. |
| 146 146 Definitions 1.1 1.1 Definitions (continued) COMANCHE PEAK - UNITS 1 AND 2 1.1-6 Amendment No. 89QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower
| | RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3458 MWt through Cycle 13 for Unit 1 and through Cycle 11 for Unit 2. Starting with Cycles 14 and 12 of Units 1 and 2, respectively, RTP shall be 3612 MWt. |
| | | REACTOR TRIP The RTS RESPONSE TIME shall be that time interval from SYSTEM (RTS) RESPONSE when the monitored parameter exceeds its RTS trip setpoint TIME at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. |
| excore detector calibrated output to the average of the lower | | SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: |
| | | : a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and |
| excore detector calibrated outputs, whichever is greater. RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP)reactor coolant of 3458 MWt through Cycle 13 for Unit 1 and through Cycle 11 for Unit 2. Starting with Cycles 14 and 12 of | | : b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures. |
| | | (continued) |
| Units 1 and 2, respectively, RTP shall be 3612 MWt. REACTOR TRIP The RTS RESPONSE TIME shall be that time interval from SYSTEM (RTS) RESPONSE when the monitored parameter exceeds its RTS trip setpoint TIMEat the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of | | COMANCHE PEAK - UNITS 1 AND 2 1.1-6 Amendment No. 89, 146}} |
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| any series of sequential, overlapping, or total steps so that | |
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| the entire response time is measured. In lieu of | |
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| measurement, response time may be verified for selected | |
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| components provided that the components and methodology | |
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| for verification have been previously reviewed and approved | |
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| by the NRC. SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its | |
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| present condition assuming: a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity | |
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| worth, which is assumed to be fully withdrawn. With any | |
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| RCCA not capable of being fully inserted, the reactivity | |
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| worth of the RCCA must be accounted for in the | |
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| determination of SDM; and b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures. (continued) | |
| , 146}} | |
Letter Sequence Other |
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MONTHYEARML0727001092007-10-0909 October 2007 Acceptance Review of License Amendment Request 07-004, Revision to the OL and TS 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power (TAC MD6615/MD6616) Project stage: Acceptance Review CP-200700016, Supplemental Information to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage.2007-10-24024 October 2007 Supplemental Information to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage. Project stage: Supplement ML0728200122007-11-0606 November 2007 Request for Withholding Information from Public Disclosure Proprietary Request for Stretch Power Uprate Information (Tac Nos. MD6615 and MD6616) Project stage: Withholding Request Acceptance ML0728200252007-11-0606 November 2007 Request for Withholding Information from Public Disclosure WCAP-16827-P (Tac Nos. MD6615 and MD6616) Project stage: Withholding Request Acceptance CP-200700075, Clarification of Proprietary Nature of Information Regarding Gothic Code Input Data2007-11-0707 November 2007 Clarification of Proprietary Nature of Information Regarding Gothic Code Input Data Project stage: Request ML0731101282007-11-14014 November 2007 LAR 07-004, Revision to OL and TS 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt (Tac Nos. MD6615 & MD6616) Project stage: Other ML0731300292007-11-20020 November 2007 Request for Withholding Information from Public Disclosure Power Stretch Uprate (C. Savage, Westinghouse 10/23/07 Affidavit) Project stage: Withholding Request Acceptance CP-200700085, Supporting Information Regarding the Proprietary Nature of Gothic Code Input Data2007-12-0303 December 2007 Supporting Information Regarding the Proprietary Nature of Gothic Code Input Data Project stage: Request ML0734402082007-12-11011 December 2007 Request for Additional Information, License Amendment Request 07-004, Changes to Technical Specifications to Revise Thermal Power from 3458 Mwt to 3612 Mwt (TACs MD6615 & MD6616) Project stage: RAI CP-200800057, Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-01-10010 January 2008 Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement CP-200800123, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to LAR Associated with Methodology Used to Establish Core Operating Limits and LAR 07-004 Revision to Operating License.2008-01-29029 January 2008 Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to LAR Associated with Methodology Used to Establish Core Operating Limits and LAR 07-004 Revision to Operating License. Project stage: Supplement CP-200800124, Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-01-31031 January 2008 Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement ML0800401822008-02-0101 February 2008 Correction Letter Regarding Safety Evaluation for Audit of Licensee'S Management of Regulatory Commitments Project stage: Approval ML0803108692008-02-0808 February 2008 Request for Additional Information, Iolb, Emcb, Eeeb Tech Branches, License Amendment Request 07-004, Changes to Technical Specifications to Revise Rated Thermal Power from 3458 Mwt to 3612 MWT.(MD6615/MD6616) Project stage: RAI CP-200800263, Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-02-21021 February 2008 Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement CP-200800213, Response to Request for Additional Information2008-02-26026 February 2008 Response to Request for Additional Information Project stage: Response to RAI CP-200800125, Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-02-28028 February 2008 Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement CP-200800357, Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-03-0606 March 2008 Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement ML0806602512008-03-12012 March 2008 Request for Withholding Information from Public Disclosure (Re 2/20/08 Affidavit Executed by J. Gresham, Westinghouse) (Tac Nos. MD6615 and MD6616) Project stage: Withholding Request Acceptance ML0807905452008-03-31031 March 2008 Request for Additional Information, License Amendment Request 07-004, Changes to Technical Specifications to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt (De/Eeeb Follow-up RAI) Project stage: RAI CP-200800560, Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-04-17017 April 2008 Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement ML0811300992008-04-24024 April 2008 Letter Enclosing Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate Project stage: Draft Other ML0811301112008-04-24024 April 2008 Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate Project stage: Draft Other CP-200800645, Supplement to License Amendment Request Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2008-05-14014 May 2008 Supplement to License Amendment Request Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt Project stage: Supplement ML0815102412008-06-16016 June 2008 Letter to Licensee Enclosing Copy of Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate Project stage: Other ML0815102472008-06-16016 June 2008 Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate Project stage: Other ML0816905832008-06-18018 June 2008 Public Transmittal Letter for Draft Safety Evaluation for Stretch Power Uprate, License Amendment Request 07-004, Revision to the Operating License & TS 1.0, Use and Application, to Revise Thermal Power from 3458 to 3612 Mwt Project stage: Draft Approval ML0815101732008-06-27027 June 2008 Issuance of Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt Project stage: Approval ML0815101752008-06-27027 June 2008 License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt Project stage: Other 2008-02-21
[Table View] |
License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 MwtML081510175 |
Person / Time |
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Site: |
Comanche Peak |
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Issue date: |
06/27/2008 |
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From: |
NRC/NRR/ADRO/DORL/LPLIV |
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To: |
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Singal, Balwant, 415-3016, NRR/DORL/LPL4 |
Shared Package |
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ML081510157 |
List: |
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References |
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TAC MD6615, TAC MD6616 |
Download: ML081510175 (3) |
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Category:Technical Specifications
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ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML15309A0732015-12-30030 December 2015 Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos ML15008A1332015-02-24024 February 2015 Issuance of Amendment Nos. 164 and 164, Revise Technical Specification 3.8.1 for a 14-Day Completion Time for Offsite Circuits ML14160A0352014-07-0101 July 2014 Redacted, Issuance of Amendment No. 162, Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals ML14042A2232014-02-27027 February 2014 Issuance of Amendment Nos. 161 and 161, Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Consolidated Line Item Improvement Process (TAC MF2651-MF2652) ML14052A2612014-02-19019 February 2014 Supplement to License Amendment Request 13-002 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using.. CP-201300738, License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..2013-07-10010 July 2013 License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item.. CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.2013-03-28028 March 2013 License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals. CP-201200012, (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent ....2012-03-28028 March 2012 (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent .... CP-201101663, License Amendment Request (LAR)11-003 for Adopting of TSTF-491, Rev. 2, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Tech Specs Using Consolidated Line Item Improvement Process.2011-12-13013 December 2011 License Amendment Request (LAR)11-003 for Adopting of TSTF-491, Rev. 2, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Tech Specs Using Consolidated Line Item Improvement Process. CP-201101038, License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled2011-08-0101 August 2011 License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled ML1011703672010-02-15015 February 2010 Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2 CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 22010-02-15015 February 2010 Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2 CP-201000144, Revision to License Amendment Request 09-001, Administrative Revision to Operating Licenses and Technical Specifications2010-02-0101 February 2010 Revision to License Amendment Request 09-001, Administrative Revision to Operating Licenses and Technical Specifications CP-200901569, License Amendment Request (LAR) 09-010, for Approval of the Cyber Security Plan2009-11-19019 November 2009 License Amendment Request (LAR) 09-010, for Approval of the Cyber Security Plan ML0927400762009-10-0909 October 2009 Issuance of Amendment Nos. 149 and 149, Modify Technical Specifications to Establish Alternate Repair Criteria (ARC) and Include Reporting Requirements Specific to ARC for Steam Generator Program CP-200901308, Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria2009-09-14014 September 2009 Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria CP-200901042, Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria2009-08-20020 August 2009 Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria CP-200900383, License Amendment Request (LAR) 09-006, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-04-0101 April 2009 License Amendment Request (LAR) 09-006, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. CP-200900283, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request2009-02-17017 February 2009 Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request ML0818400022008-09-12012 September 2008 License and Technical Specifications Pages, Amendment Nos. 147 and 147, Revise Technical Specification 3.6.7, Spray Additive System to Comply with GL-2004-02 ML0815101752008-06-27027 June 2008 License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt ML0805800052008-04-0303 April 2008 Tech Spec Pages for Amendment Nos. 145 and 145 Revise TSs 3.1.4, 3.4.10, and 3.7.1 to Reflect Cycle-Specific Safety Analysis Assumptions Re Adoption of Westinghouse Methodologies ML0805100832008-04-0202 April 2008 License and Technical Specifications, Amendment 144 and 144, Changes to TS to Allow Use of Westinghouse-developed/NRC-approved Analytical Methods Used to Establish COLs CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses2008-03-13013 March 2008 Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses CPSES-200701076, Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2007-08-28028 August 2007 Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System..2007-08-16016 August 2007 License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System.. ML0708201932007-04-27027 April 2007 Technical Specifications, Issuance of Amendment Nos. 138 and 138 Revision to Technical Specification 3.8.1, AC Sources - Operating (TAC MD0932 & MD0933) ML0704304542007-03-29029 March 2007 Technical Specifications, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity ML0707700102007-03-26026 March 2007 Technical Specifications, Issuance of Amendment Nos. 135 and 135 Revise Listing of LOCA and Non-LOCA Methodologies ML0707300432007-03-26026 March 2007 Technical Specification, Modify TS Requirements Related to Control Room Envelope Habitability in TS 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs), and TS Section 5.5, Administrative Controls.... ML0704403712007-02-26026 February 2007 Technical Specifications, Issuance of Amendment Nos. 133 & 133 Revision to TS 3.3.1.2 and 3.3.1.3, Reactor Trip System Instrumentation (TAC Nos. MC9492 & MC9493) ML0703104902007-02-20020 February 2007 Technical Specifications, Issuance of Amendment Nos. 130 & 130 New Methods & Assumptions for Radiological Consequences Calculations (TAC Nos. MC8163 & MC8164) ML0703500472007-02-20020 February 2007 Technical Specifications, Issuance of Amendment Nos. 131 & 131 Technical Specification Changes Related to Unit 1 Steam Generator Replacement Project (TAC Nos. MD0187 & MD0188) CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators2007-01-18018 January 2007 License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators ML0628401022006-10-0505 October 2006 Technical Specification, Revisions to TS 3.3.2, ESFAS Instrumentation; and TS 3.5.2, ECCS - Operating ML0625801172006-09-12012 September 2006 Technical Specifications, Issuance of Amendments Steam Generator Tube Surveillance Program, MC9498 and MC9499 2024-02-09
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(3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by 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 I 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 Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 13 and 3612 megawatts thermal starting with Cycle 14 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. 146 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Unit 1 Amendment No. 146
(3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by 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 I 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 Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 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. 146 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions DELETED Unit 2 Amendment No. 146
Definitions 1.1 1.1 Definitions (continued)
QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3458 MWt through Cycle 13 for Unit 1 and through Cycle 11 for Unit 2. Starting with Cycles 14 and 12 of Units 1 and 2, respectively, RTP shall be 3612 MWt.
REACTOR TRIP The RTS RESPONSE TIME shall be that time interval from SYSTEM (RTS) RESPONSE when the monitored parameter exceeds its RTS trip setpoint TIME at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:
- a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and
- b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 1.1-6 Amendment No. 89, 146