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| | issue date = 04/24/2006 | | | issue date = 04/24/2006 |
| | title = License Amendment, Issuance of Amendments Revision to TS 3.7.5 for Auxiliary Feedwater System | | | title = License Amendment, Issuance of Amendments Revision to TS 3.7.5 for Auxiliary Feedwater System |
| | author name = Thadani M C | | | author name = Thadani M |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
| | addressee name = Blevins M R | | | addressee name = Blevins M |
| | addressee affiliation = TXU Power | | | addressee affiliation = TXU Power |
| | docket = 05000445, 05000446 | | | docket = 05000445, 05000446 |
| | license number = NPF-087, NPF-089 | | | license number = NPF-087, NPF-089 |
| | contact person = Thadani M C | | | contact person = Thadani M |
| | case reference number = TAC M5794, TAC M5795 | | | case reference number = TAC M5794, TAC M5795 |
| | package number = ML060860267 | | | package number = ML060860267 |
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| =Text= | | =Text= |
| {{#Wiki_filter:April 24, 2006Mr. M. R. Blevins Senior Vice President | | {{#Wiki_filter:April 24, 2006 Mr. M. R. Blevins Senior Vice President |
| & Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
| | & Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795) | | COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 - |
| | ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795) |
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| ==Dear Mr. Blevins:== | | ==Dear Mr. Blevins:== |
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| The Commission has issued the enclosed Amendment No. 126 to Facility Operating LicenseNo. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for C PSES,Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005.The amendments revise TS 3.7.5, "Auxiliary Feedwater (AFW) System." Specifically, theproposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and3.7.5.4 that states, "AFW train(s) may be considered OPERABLE during alignment andoperation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation." A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included inthe Commission's next biweekly Federal Register notice.Sincerely,/RA/Mohan C. Thadani, Senior Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-445 and 50-446 | | The Commission has issued the enclosed Amendment No. 126 to Facility Operating License No. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005. |
| | The amendments revise TS 3.7.5, Auxiliary Feedwater (AFW) System. Specifically, the proposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation. |
| | A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 126 to NPF-872. Amendment No. 126 to NPF-89 | | : 1. Amendment No. 126 to NPF-87 |
| : 3. Safety Evaluationcc w/encls: See next page April 24, 2006Mr. M. R. Blevins Senior Vice President | | : 2. Amendment No. 126 to NPF-89 |
| & Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
| | : 3. Safety Evaluation cc w/encls: See next page |
| | |
| | April 24, 2006 Mr. M. R. Blevins Senior Vice President |
| | & Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795) | | COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 - |
| | ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795) |
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| ==Dear Mr. Blevins:== | | ==Dear Mr. Blevins:== |
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| The Commission has issued the enclosed Amendment No. 126 to Facility Operating LicenseNo. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for C PSES,Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005.The amendments revise TS 3.7.5, "Auxiliary Feedwater (AFW) System." Specifically, theproposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and3.7.5.4 that states, "AFW train(s) may be considered OPERABLE during alignment andoperation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation." A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included inthe Commission's next biweekly Federal Register notice.Sincerely,/RA/Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-445 and 50-446 | | The Commission has issued the enclosed Amendment No. 126 to Facility Operating License No. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005. |
| | The amendments revise TS 3.7.5, Auxiliary Feedwater (AFW) System. Specifically, the proposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation. |
| | A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 126 to NPF-872. Amendment No. 126 to NPF-89 | | : 1. Amendment No. 126 to NPF-87 |
| : 3. Safety Evaluationcc w/encls: See next pageDISTRIBUTION | | : 2. Amendment No. 126 to NPF-89 |
| :PUBLICRidsOgcRpRidsRgn4MailCenter LPLIV ReadingRidsAcrsAcnwMailCenterRidsNrrDorlDprRidsNrrDorlLplgRidsNrrDirsItsbGHill(4)
| | : 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| RidsNrrPMMThadaniRHernandez RidsNrrLADJohnsonRidsNrrDssSbpbADAMS (Pkg):ML060860267(Amd): (TS): ML061160064*no significant changes to SE inputOFFICENRR/LPL4/PMNRR/LPL4/LASBPB/BCOGCNRR/LPL4/BCNAMEMThadaniDJohnsonSJones*SHamrick (NLO)DTerao DATE4/14/064/13/0612/13/20054/20/064/24/06OFFICIAL RECORD COPY TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1DOCKET NO. 50-445AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 126License No. NPF-871.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by TXU Generation Company LP datedJanuary 24, 2005, complies with the standards and requirements of the AtomicEnergy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, as amended, theprovisions of the Act, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense and security or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment; and paragraph 2.C.(2) of FacilityOperating License No. NPF-87 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the TechnicalSpecifications and the Environmental Protection Plan.3.The license amendment is effective as of its date of issuance and shall be implementedwithin 90 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | PUBLIC RidsOgcRp RidsRgn4MailCenter LPLIV Reading RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDorlLplg RidsNrrDirsItsb GHill(4) |
| | RidsNrrPMMThadani RHernandez RidsNrrLADJohnson RidsNrrDssSbpb ADAMS (Pkg):ML060860267 (Amd): (TS): ML061160064 |
| | *no significant changes to SE input OFFICE NRR/LPL4/PM NRR/LPL4/LA SBPB/BC OGC NRR/LPL4/BC NAME MThadani DJohnson SJones* SHamrick (NLO) DTerao DATE 4/14/06 4/13/06 12/13/2005 4/20/06 4/24/06 OFFICIAL RECORD COPY |
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| | TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. NPF-87 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by TXU Generation Company LP dated January 24, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows: |
| | |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Technical SpecificationsDate of Issuance: April 24, 2006 TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2DOCKET NO. 50-446AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 126License No. NPF-891.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by TXU Generation Company LP datedJanuary 24, 2005, complies with the standards and requirements of the AtomicEnergy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, as amended, theprovisions of the Act, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense and security or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment; and paragraph 2.C.(2) of FacilityOperating License No. NPF-89 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the TechnicalSpecifications and the Environmental Protection Plan.3.This license amendment is effective as of its date of issuance and shall be implementedwithin 90 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | Changes to the Technical Specifications Date of Issuance: April 24, 2006 |
| | |
| | TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. NPF-89 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by TXU Generation Company LP dated January 24, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows: |
| | |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Technical SpecificationsDate of Issuance: April 24, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-87AND AMENDMENT NO. 126TO FACILITY OPERATING LICENSE NO. NPF-89DOCKET NOS. 50-445 AND 50-446Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsert3.7-143.7-143.7-153.7-15 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 126 TOFACILITY OPERATING LICENSE NO. NPF-87AND AMENDMENT NO. 126 TOFACILITY OPERATING LICENSE NO. NPF-89TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2DOCKET NOS. 50-445 AND 50-44 | | Changes to the Technical Specifications Date of Issuance: April 24, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Remove Insert 3.7-14 3.7-14 3.7-15 3.7-15 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-89 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated January 24, 2005, (Agencywide Documents Access and Management System Accession No. ML050330389) TXU Generation Company LP (the licensee) requested changes to Facility Operating Licenses DPR-87 and DPR-89 for Comanche Peak Steam Electric Station, Units 1 and 2, respectively. License Amendment Request 04-013 proposed Technical Specification (TS) changes to TS 3.7.5, Auxiliary Feedwater System (AFW). Specifically, the proposed changes would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation. |
| | |
| | ==2.0 REGULATORY EVALUATION== |
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| | Industry Standard Technical Specification Change Traveler (TSTF) 245-A, Revision 1, AFW Train Operable When in Service, was approved by the NRC staff on January 13, 1999. The approved TSTF 245-A proposed to add a note to SRs 3.7.5.1, SR 3.7.5.3, and SR 3.7.5.4 that states AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation. TSTF-245-A, Revision 1, was approved based on the applicable Nuclear Regulatory Commission (NRC) regulations. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | The licensees application is based on TSTF-245-A, Revision 1, which showed that the proposed type of changes meet the relevant NRC regulations and there is reasonable assurance that the health and safety of the public will not be endangered. The NRC staff approved TSTF-245-A, Revision 1, on January 13, 1999. |
| | |
| | Based on its review, the NRC staff has verified that the requested TS changes are consistent with the current Standard Technical Specifications and reflect changes based on TSTF-245-A, Revision 1. Consequently, the changes satisfy the underlying applicable NRC regulations. |
| | Therefore, the staff finds the licensees proposed changes to SR 3.7.5.1, SR 3.7.5.3, SR 3.7.5.4, to be acceptable. |
| | |
| | ==4.0 STATE CONSULTATION== |
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| ==61.0INTRODUCTION==
| | In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| By letter dated January 24, 2005, (Agencywide Documents Access and Management SystemAccession No. ML050330389) TXU Generation Company LP (the licensee) requested changes to Facility Operating Licenses DPR-87 and DPR-89 for Comanche Peak Steam Electric Station, Units 1 and 2, respectively. License Amendment Request 04-013 proposed Technical Specification (TS) changes to TS 3.7.5, "Auxiliary Feedwater System (AFW)." Specifically, theproposed changes would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and3.7.5.4 that states, "AFW train(s) may be considered OPERABLE during alignment andoperation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation."
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| ==2.0REGULATORY EVALUATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| Industry Standard Technical Specification Change Traveler (TSTF) 245-A, Revision 1, "AFWTrain Operable When in Service," was approved by the NRC staff on January 13, 1999. Theapproved TSTF 245-A proposed to add a note to SRs 3.7.5.1, SR 3.7.5.3, and SR 3.7.5.4 thatstates "AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation." TSTF-245-A, Revision 1, was approved based on the applicable Nuclear Regulatory Commission (NRC) regulations.
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| ==3.0TECHNICAL EVALUATION==
| | The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published November 8, 2005 (70 FR 67753). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. |
| The licensee's application is based on TSTF-245-A, Revision 1, which showed that theproposed type of changes meet the relevant NRC regulations and there is reasonableassurance that the health and safety of the public will not be endangered. The NRC staffapproved TSTF-245-A, Revision 1, on January 13, 1999. Based on its review, the NRC staff has verified that the requested TS changes are consistentwith the current Standard Technical Specifications and reflect changes based on TSTF-245-A, Revision 1. Consequently, the changes satisfy the underlying applicable NRC regulations.Therefore, the staff finds the licensee's proposed changes to SR 3.7.5.1, SR 3.7.5.3,SR 3.7.5.4, to be acceptable. | |
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| ==4.0STATE CONSULTATION== | | ==6.0 CONCLUSION== |
| In accordance with the Commission's regulations, the Texas State official was notified of theproposed issuance of the amendment. The State official had no comments.
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| ==5.0ENVIRONMENTAL CONSIDERATION==
| | The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| The amendments change a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff hasdetermined that the amendments involve no significant increase in the amounts, and nosignificant change in the types, of any effluents that may be released offsite, and that there isno significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published November 8, 2005 (70 FR 67753). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. | | Principal Contributor: R. Hernandez Date: April 24, 2006 |
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| ==6.0CONCLUSION==
| | Comanche Peak Steam Electric Station cc: |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendments will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributor: R. Hernandez Date: April 24, 2006 December 2004Comanche Peak Steam Electric Station cc:Senior Resident InspectorU.S. Nuclear Regulatory Commission P. O. Box 2159 Glen Rose, TX 76403-2159Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011Mr. Fred W. Madden, DirectorRegulatory Affairs TXU Generation Company LP P. O. Box 1002 Glen Rose, TX 76043George L. Edgar, Esq.Morgan Lewis 1111 Pennsylvania Avenue, NW Washington, DC 20004County Judge P. O. Box 851 Glen Rose, TX 76043Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189Mr. Richard A. Ratliff, ChiefBureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189Mr. Brian AlmonPublic Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326Ms. Susan M. JablonskiOffice of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P. O. Box 13087 Austin, TX 78711-3087Terry Parks, Chief InspectorTexas Department of Licensing and Regulation Boiler Program P. O. Box 12157 Austin, TX 78711}}
| | Senior Resident Inspector Mr. Brian Almon U.S. Nuclear Regulatory Commission Public Utility Commission P. O. Box 2159 William B. Travis Building Glen Rose, TX 76403-2159 P. O. Box 13326 1701 North Congress Avenue Regional Administrator, Region IV Austin, TX 78701-3326 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Ms. Susan M. Jablonski Arlington, TX 76011 Office of Permitting, Remediation and Registration Mr. Fred W. Madden, Director Texas Commission on Environmental Regulatory Affairs Quality TXU Generation Company LP MC-122 P. O. Box 1002 P. O. Box 13087 Glen Rose, TX 76043 Austin, TX 78711-3087 George L. Edgar, Esq. Terry Parks, Chief Inspector Morgan Lewis Texas Department of Licensing 1111 Pennsylvania Avenue, NW and Regulation Washington, DC 20004 Boiler Program P. O. Box 12157 County Judge Austin, TX 78711 P. O. Box 851 Glen Rose, TX 76043 Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189 Mr. Richard A. Ratliff, Chief Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 December 2004}} |
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Category:Letter
MONTHYEARIR 05000445/20244042024-10-23023 October 2024
Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public)
IR 05000445/20243012024-10-15015 October 2024
NRC Initial Operator Licensing Examination Approval 05000445/2024301 and 05000446/2024301
IR 07200074/20244012024-10-10010 October 2024
Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public
05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-10-0303 October 2024
Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions
05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-09-30030 September 2024
Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024
License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
ML24031A6322024-09-11011 September 2024
Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter
ML24243A0152024-09-0303 September 2024
– Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information
ML24194A1332024-08-28028 August 2024
Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown
ML24228A2252024-08-22022 August 2024
Relief to Use Later Code Edition for Inservice Inspection Program
ML24179A0772024-08-20020 August 2024
Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24232A2262024-08-19019 August 2024
Information Request, Security IR 2024404
ML24232A2412024-08-19019 August 2024
Information Request, ISFSI Security IR 2024401
IR 05000445/20240052024-08-15015 August 2024
Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005)
CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024
(CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule
CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024
(CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality
ML24177A2692024-08-0707 August 2024
Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024
(Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality
IR 05000445/20240022024-07-31031 July 2024
Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001
IR 05000445/20244032024-07-16016 July 2024
Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report)
ML24187A0372024-07-15015 July 2024
Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses
ML24192A1862024-07-10010 July 2024
Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information
ML24185A1382024-07-0202 July 2024
Inservice Inspection Request for Information
CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024
(Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5
IR 05000445/20244012024-06-26026 June 2024
MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final
CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024
(Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0
IR 05000445/20240122024-06-17017 June 2024
Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012
ML24120A3632024-06-10010 June 2024
Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants
CP-202400120, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024
(Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions
CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024
(Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval
CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024
(CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator
CP-202400100, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024
(Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications
CP-202400097, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024
Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning
ML24120A2942024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation
ML24120A3032024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe
ML24120A2972024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma
ML24120A3072024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town
ML24120A3062024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town
ML24107B1012024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana
ML24120A3012024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes
ML24120A3042024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas
ML24120A2932024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas
ML24120A2902024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians
ML24120A2912024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma
ML24120A2962024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma
ML24120A3002024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town
ML24120A2922024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation
ML24120A2952024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma
CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024
(Cpnpp), Registration of Dry Spent Fuel Storage Canisters
ML24120A2982024-04-29029 April 2024
Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe
2024-09-30
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24179A0772024-08-20020 August 2024
Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24177A2692024-08-0707 August 2024
Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
ML24136A1342024-07-30030 July 2024
Renewed License
ML24136A1332024-07-30030 July 2024
Renewed License
ML24120A3632024-06-10010 June 2024
Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants
ML24023A2962024-02-0909 February 2024
Issuance of Amendment Nos. 186 and 186 Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81
ML23319A3872023-12-20020 December 2023
Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology
ML23348A2392023-12-19019 December 2023
Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual
ML23313A0732023-12-0606 December 2023
Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications
ML23237B4412023-09-29029 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Federal Register Notice, Direct and Indirect License Transfer Issuance Order
ML23237B4302023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public)
ML23237B4282023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments
ML23136B2962023-05-31031 May 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding General Design Criteria 5 and Regulatory Guide 1.81
ML22329A0332022-11-29029 November 2022
Notification of NRC Initial Operator Licensing Examination 05000445/2023301 and 05000446/2023301
ML22208A1582022-07-29029 July 2022
Correction to Issuance of Amendment Nos. 156 and 156 Relocation of Surveillance Frequencies from the Technical Specifications to a Licensee-Controlled Document
ML21321A3492022-02-24024 February 2022
Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections
ML21132A0892021-06-0909 June 2021
Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues
ML21061A2172021-05-19019 May 2021
Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan
ML21103A0392021-04-23023 April 2021
Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147)
ML21015A2122021-02-12012 February 2021
Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating
ML20346A0192021-02-0101 February 2021
Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating
ML20168A9242020-11-16016 November 2020
Issuance of Amendment Nos. 176 and 176 Regarding Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
ML20223A3492020-08-31031 August 2020
Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water
ML20167A3182020-07-0606 July 2020
Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0
ML20108E8782020-04-17017 April 2020
Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances)
ML19267A0182019-11-0404 November 2019
Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan
ML18304A4872018-11-30030 November 2018
Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation
ML18267A3842018-10-25025 October 2018
Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances)
ML17129A0242017-06-29029 June 2017
Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934)
ML16266A0052016-10-0303 October 2016
ISFSI - Issuance of Amendment Nos. 167 and 167 Related to Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments
ML16168A0022016-06-24024 June 2016
Correction of Implementation Date, Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6
ML16137A0562016-06-14014 June 2016
Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6
ML16096A2662016-05-0606 May 2016
Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments
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
ML14183A3422014-09-0808 September 2014
Issuance of Amendment Nos. 163 and 163 to Revise License Condition Related to Approval of Revised Cyber Security Plan Implementation Schedule
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)
ML13232A1432013-09-18018 September 2013
Issuance of Amendment Nos. 160 and 160, Revise Technical Specification 3.8.1, AC Sources - Operating, for Extension of Two 14-Day Completion Times for Offsite Circuits
ML13156A2482013-07-11011 July 2013
Issuance of Amendment Nos. 159 and 159, Revise Technical Specification (TS) 5.7, High Rad Area, and TS Table 3.3.3-1, Post Accident Monitoring Instrumentation
ML12263A0362012-10-18018 October 2012
Issuance of Amendment Nos. 158 and 158, Revise Technical Specification (TS) 5.5.9 and TS 5.6.9 for a Permanent Alternate Repair Criteria
ML12156A0682012-06-29029 June 2012
Issuance of Amendment Nos. 157 and 157, Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications
ML12067A2442012-06-29029 June 2012
Issuance of Amendment Nos. 156 and 156, Adoption of TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specifications Task Force (RITSTF) Initiative 5b
ML1117807452011-07-26026 July 2011
Issuance of Amendment Nos. 155 and 155, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule
ML1107703222011-04-0606 April 2011
Issuance of Amendment Nos. 154 and 154, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria
ML1000705672010-04-26026 April 2010
Issuance of Amendment Nos. 151 and 151, Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Add Surveillance Requirement 3.3.1.16 to Function 3 of Table 3.3.1-1
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
ML0917506632009-08-0707 August 2009
Issuance of Amendment Nos. 148 and 148, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0818400012008-09-12012 September 2008
Issuance of Amendment Nos. 147 and 147, Revise Technical Specification 3.6.7, Spray Additive System to Comply with GL-2004-02
2024-08-07
[Table view]
Category:Safety Evaluation
MONTHYEARML24179A0772024-08-20020 August 2024
Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24177A2692024-08-0707 August 2024
Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
ML24120A3632024-06-10010 June 2024
Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants
ML24023A2962024-02-0909 February 2024
Issuance of Amendment Nos. 186 and 186 Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81
ML23319A3872023-12-20020 December 2023
Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology
ML23313A0732023-12-0606 December 2023
Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications
ML23237B4282023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments
ML23237B4302023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public)
ML23198A3212023-07-27027 July 2023
Authorization and Safety Evaluation for Proposed Alternative RV-1
ML22192A0072022-08-22022 August 2022
Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2
ML22194A0592022-07-14014 July 2022
Correction to Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML22129A0722022-05-16016 May 2022
Review of Quality Assurance Program Changes
ML22077A8412022-03-24024 March 2022
Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension
ML21321A3492022-02-24024 February 2022
Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections
ML21322A1032021-12-0707 December 2021
Proposed Alternative for the Continued Use of a Risk-Informed Process for the Selection of Class 1 and 2 Piping Welds for Inservice Inspection
ML21132A0892021-06-0909 June 2021
Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues
ML21061A2172021-05-19019 May 2021
Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan
ML21103A0392021-04-23023 April 2021
Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147)
ML21015A2122021-02-12012 February 2021
Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating
ML21022A1622021-02-0808 February 2021
Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0096 (COVID-19))
ML21021A1002021-02-0101 February 2021
Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19))
ML20346A0192021-02-0101 February 2021
Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating
ML21013A1282021-01-28028 January 2021
Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19))
ML21021A0022021-01-28028 January 2021
Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants
ML20282A7092020-11-17017 November 2020
Proposed Alternative to the Requirements of the ASME Omcode to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0060 (COVID-19))
ML20281A4722020-11-0404 November 2020
Use of Later Code Edition to the Requirements of the ASME OM Code
ML20255A1002020-10-0707 October 2020
Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Test Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0061 and EPID L-2020-LLR-0062 (COVID-19))
ML20223A3492020-08-31031 August 2020
Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water
ML20226A0132020-08-17017 August 2020
Use of Later Code Edition to the Requirements of the ASME Code
ML20167A3182020-07-0606 July 2020
Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0
ML20108E8782020-04-17017 April 2020
Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances)
ML20054A2762020-02-27027 February 2020
Approval of Change to the Quality Assurance Program as Described in the Comanche Peak Nuclear Power Plant Final Safety Analysis Report
ML19267A0182019-11-0404 November 2019
Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan
ML18304A4872018-11-30030 November 2018
Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation
ML18267A3842018-10-25025 October 2018
Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances)
ML18221A6322018-08-15015 August 2018
Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0
ML17129A0242017-06-29029 June 2017
Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934)
ML17074A4942017-04-13013 April 2017
Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
ML17095A2512017-04-0707 April 2017
Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles
ML16334A1732016-12-14014 December 2016
Comanche Peak Nuclear Power Plant, Units 1 And 2; Safety Evaluation Regarding Implementation Of Mitigating Strategies And Reliable Spent Fuel Pool Instrumentation Related To Orders EA-12-049 And EA-12-051
ML16179A4052016-07-11011 July 2016
Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval
ML16137A0562016-06-14014 June 2016
Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6
ML16096A2642016-05-0606 May 2016
Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments
ML16096A2662016-05-0606 May 2016
Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments
ML16074A0012016-03-14014 March 2016
Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval
ML16063A0012016-03-11011 March 2016
Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval
ML16011A0732016-01-19019 January 2016
Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval
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
ML15259A0042015-10-30030 October 2015
Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval
ML15257A2422015-09-18018 September 2015
Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval
2024-08-07
[Table view] |
Text
April 24, 2006 Mr. M. R. Blevins Senior Vice President
& Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795)
Dear Mr. Blevins:
The Commission has issued the enclosed Amendment No. 126 to Facility Operating License No. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005.
The amendments revise TS 3.7.5, Auxiliary Feedwater (AFW) System. Specifically, the proposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 126 to NPF-87
- 2. Amendment No. 126 to NPF-89
- 3. Safety Evaluation cc w/encls: See next page
April 24, 2006 Mr. M. R. Blevins Senior Vice President
& Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION 3.7.5 FOR AUXILIARY FEED WATER SYSTEM (TAC NOS. M5794 AND M5795)
Dear Mr. Blevins:
The Commission has issued the enclosed Amendment No. 126 to Facility Operating License No. NPF-87 and Amendment No. 126 to Facility Operating License No. NPF-89 for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 24, 2005.
The amendments revise TS 3.7.5, Auxiliary Feedwater (AFW) System. Specifically, the proposed change would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 126 to NPF-87
- 2. Amendment No. 126 to NPF-89
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsOgcRp RidsRgn4MailCenter LPLIV Reading RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDorlLplg RidsNrrDirsItsb GHill(4)
RidsNrrPMMThadani RHernandez RidsNrrLADJohnson RidsNrrDssSbpb ADAMS (Pkg):ML060860267 (Amd): (TS): ML061160064
- no significant changes to SE input OFFICE NRR/LPL4/PM NRR/LPL4/LA SBPB/BC OGC NRR/LPL4/BC NAME MThadani DJohnson SJones* SHamrick (NLO) DTerao DATE 4/14/06 4/13/06 12/13/2005 4/20/06 4/24/06 OFFICIAL RECORD COPY
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. NPF-87
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by TXU Generation Company LP dated January 24, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 2006
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. NPF-89
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by TXU Generation Company LP dated January 24, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.7-14 3.7-14 3.7-15 3.7-15
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 126 TO FACILITY OPERATING LICENSE NO. NPF-89 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By letter dated January 24, 2005, (Agencywide Documents Access and Management System Accession No. ML050330389) TXU Generation Company LP (the licensee) requested changes to Facility Operating Licenses DPR-87 and DPR-89 for Comanche Peak Steam Electric Station, Units 1 and 2, respectively. License Amendment Request 04-013 proposed Technical Specification (TS) changes to TS 3.7.5, Auxiliary Feedwater System (AFW). Specifically, the proposed changes would add a note to Surveillance Requirements (SRs) 3.7.5.1, 3.7.5.3, and 3.7.5.4 that states, AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.
2.0 REGULATORY EVALUATION
Industry Standard Technical Specification Change Traveler (TSTF) 245-A, Revision 1, AFW Train Operable When in Service, was approved by the NRC staff on January 13, 1999. The approved TSTF 245-A proposed to add a note to SRs 3.7.5.1, SR 3.7.5.3, and SR 3.7.5.4 that states AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation. TSTF-245-A, Revision 1, was approved based on the applicable Nuclear Regulatory Commission (NRC) regulations.
3.0 TECHNICAL EVALUATION
The licensees application is based on TSTF-245-A, Revision 1, which showed that the proposed type of changes meet the relevant NRC regulations and there is reasonable assurance that the health and safety of the public will not be endangered. The NRC staff approved TSTF-245-A, Revision 1, on January 13, 1999.
Based on its review, the NRC staff has verified that the requested TS changes are consistent with the current Standard Technical Specifications and reflect changes based on TSTF-245-A, Revision 1. Consequently, the changes satisfy the underlying applicable NRC regulations.
Therefore, the staff finds the licensees proposed changes to SR 3.7.5.1, SR 3.7.5.3, SR 3.7.5.4, to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published November 8, 2005 (70 FR 67753). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. Hernandez Date: April 24, 2006
Comanche Peak Steam Electric Station cc:
Senior Resident Inspector Mr. Brian Almon U.S. Nuclear Regulatory Commission Public Utility Commission P. O. Box 2159 William B. Travis Building Glen Rose, TX 76403-2159 P. O. Box 13326 1701 North Congress Avenue Regional Administrator, Region IV Austin, TX 78701-3326 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Ms. Susan M. Jablonski Arlington, TX 76011 Office of Permitting, Remediation and Registration Mr. Fred W. Madden, Director Texas Commission on Environmental Regulatory Affairs Quality TXU Generation Company LP MC-122 P. O. Box 1002 P. O. Box 13087 Glen Rose, TX 76043 Austin, TX 78711-3087 George L. Edgar, Esq. Terry Parks, Chief Inspector Morgan Lewis Texas Department of Licensing 1111 Pennsylvania Avenue, NW and Regulation Washington, DC 20004 Boiler Program P. O. Box 12157 County Judge Austin, TX 78711 P. O. Box 851 Glen Rose, TX 76043 Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189 Mr. Richard A. Ratliff, Chief Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 December 2004
