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Category:Letter
MONTHYEARCP-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 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 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 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final 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 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 ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana 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 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 ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24107B0292024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters SHPO ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp ML24080A1802024-04-26026 April 2024 Ltr to Ken J. Peters, Sr VP and Chief Nuclear Officer, CPNPP re-NOA Final Plant Specific Supplement 60 2024-09-03
[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
November 30, 2005 Mr. M. R. Blevins Senior Vice President &
Chief Nuclear Officer TXU Power Attn: Regulatory Affairs Department P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 - RESPONSE TO GENERIC LETTER 2004-01, REQUIREMENTS FOR STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MC4811)
Dear Mr. Blevins:
On August 30, 2004, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-01, "Requirements For Steam Generator Tube Inspections." The purpose of GL 2004-01 was to obtain information that would enable the NRC staff to determine whether the licensees steam generator tube inspection programs comply with the existing tube inspection requirements as specified in the plant Technical Specifications in conjunction with Appendix B to Part 50 of Title 10 of the Code of Federal Regulations.
By letter dated October 14, 2004 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML042940371), TXU Generation Company LP, the licensee for Comanche Peak Steam Electric Station (CPSES), responded to GL 2004-01 for CPSES, Units 1 and 2. The NRC staff previously addressed the evaluation of the licensees response for CPSES, Unit 2, by letter dated June 9, 2005 (ADAMS Accession No. ML051520353). This response addresses the NRC staffs evaluation of the licencees response to GL 2004-01 for CPSES, Unit 1. The response for CPSES, Unit 1, was supplemented by the licensees letter dated August 4, 2005 ( ADAMS Accession No. ML052220335).
The NRC staff has completed its review of the licenses response for CPSES, Unit 1, as outlined in the enclosed safety evaluation. Based on that review, the NRC staff finds that the licensees response to GL 2004-01 for CPSES, Unit 1, are acceptable since, (1) the licensee has specified near- and long-term corrective actions to mitigate the inability to inspect behind the nickel band region and has entered that difficulty in its corrective action program, and (2) inspections to be performed during the refueling outage 1RF11 at sleeve joints in the tube-sheet should provide reasonable assurance of the tube integrity in this area of the tube bundle until the planned replacement of the steam generators in the spring of 2007.
M. R. Blevins If you have any questions regarding this matter, please contact me at (301) 415-1476.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
Safety Evaluation cc: See next page
M. R. Blevins If you have any questions regarding this matter, please contact me at (301) 415-1476.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
Safety Evaluation cc: See next page DISTRIBUTION PUBLIC LPLIV Reading RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDorlLplg (DTerao)
RidsNrrPMMThadani RidsNrrLADJohnson RidsNrrDorl K. Karwoski P. Klein J. Terrell M. Yoder RidsRgn4MailCenter(AHowell)
Accession No. ML053190293 NRR-106 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME MThadani DJohnson DTerao DATE 11/29/05 11/28/05 11/30/05 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO GENERIC LETTER 2004-01, REQUIREMENTS FOR STEAM GENERATOR TUBE INSPECTIONS" FACILITY OPERATING LICENSE NO. NPF-87 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 DOCKET NO. 50-445 On August 30, 2004, the NRC issued Generic Letter (GL) 2004-01, Requirements For Steam Generator Tube Inspections. The purpose of GL 2004-01 was to obtain information that would enable the NRC staff to determine whether licensees steam generator tube inspection programs comply with the existing tube inspection requirements (the plant Technical Specifications) in conjunction with Appendix B to Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50, Appendix B).
By letter dated October 14, 2004 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML042940371), TXU Generation Company LP, the licensee for Comanche Peak Steam Electric Station (CPSES), responded to GL 2004-01 for CPSES, Units 1 and 2. That response was supplemented by letter dated August 4, 2005 (ADAMS Accession No. ML052220335). The NRC staff previously addressed the licensees response for CPSES, Unit 2, by letter dated June 9, 2005 (ADAMS Accession No. ML051520353). This safety evaluation addresses the NRC staffs evaluation of the licencees response to GL 2004-01 for CPSES, Unit 1.
In the August 4, 2005, letter, the licensee indicated that its ability to inspect behind the nickel band region of the steam generator tube sleeves may be limited, and there may be a reduced probability of detection of flaws located behind the nickel band. A nickel band is present in the tube-to-sleeve joints located within the tubesheet for both the tungsten inert gas (TIG) sleeves and the Alloy 800 sleeves. TIG sleeves were installed at CPSES, Unit 1, during the 2002 refueling outage (1RF9), and Alloy 800 sleeves were installed during the next refueling outage (1RF10) in 2004. The location where the Alloy 800 tubesheet joints were established was inspected with a +PointTM probe prior to installation of the sleeves and confirmed to be free from degradation.
As a result of the potential limitations in the licensees ability to inspect behind the nickel band region, the licensee indicated that both near- and long-term corrective actions have been entered into the sites corrective action program. The longer term corrective actions include removing the TIG and Alloy 800 sleeves from service when the steam generators are replaced in the spring of 2007 (1RF12), and the authorization to use such sleeving methods is removed for the replacement steam generators. The near-term corrective actions include performing the following during the currently ongoing refueling outage (1RF11): (1) a full length +PointTM coil inspection of a minium of 20 per cent of all inservice TIG sleeves, (2) supplemental analysts training to sensitize the analysts to the potential for axial primary water stress corrosion cracking within the parent tube adjacent to the nickel band and microlok band regions in TIG and Alloy 800 sleeves, and (3) a full length +PointTM coil inspection of all Alloy 800 sleeves.
In addition to these corrective actions, the licensee provided a safety assessment to demonstrate that tube integrity would be maintained, given the inspections performed at the sleeve joints in the tubesheet region. Although the NRC staff could not conclude that it would be able to relicense the sleeves with the technical arguments provided by the licensee in its safety analyses, the staff finds that the inspections to be performed in 1RF11 at the sleeve joints in the tubesheet should provide reasonable assurance of tube integrity in this area of the tube bundle until the planned replacement of the steam generators in 1RF12. The staffs conclusion is based on a limited length of time the sleeves will be in service, the lack of degradation observed in the parent tube at the location where the Alloy 800 sleeve joints were established in 1RF10, the limited amount of primary fluid that can come into contact with this region, the limited potential for a structurally significant circumferential flaw to exist within the short axial distance of the nickel band due to the history of full depth roll expanded tubing and the application of shot peening prior to operation, the possibility that the +PointTM coil may detect severe cracks in this region (the qualification data was based solely on notches), the proximity of the nearby tubes which will limit the potential for a tube to pull out of the tubesheet, and some general insights that joint lengths less than the originally qualified lengths may ensure tube integrity.
In conclusion, the NRC staff finds the licensees response to GL 2004-01 acceptable, since (1) the licensee has entered its limitations in ability to inspect behind the nickel band region in its corrective action program and will address the limitations by taking the near- and long-term corrective actions discussed above, and (2) the inspections to be performed in currently ongoing refueling outage (1RF11) at the sleeve joints in the tubesheet should provide reasonable assurance of tube integrity in this area of the tube bundle until the planned replacement of the steam generators in the spring of 2007.
Principal Contributor: K. Karwoski Date: November 30, 2005
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