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| | number = ML110050241 | | | number = ML110050241 |
| | issue date = 01/05/2011 | | | issue date = 01/05/2011 |
| | title = Acceptance Review Email, License Amendment Request, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria (TAC ME5110 and ME5111) | | | title = Acceptance Review Email, License Amendment Request, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria |
| | author name = Singal B K | | | author name = Singal B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Hope T | | | addressee name = Hope T |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Singal, Balwant Sent: Wednesday, January 05, 2011 10:48 AM To: 'Timothy.Hope@luminant.com' Cc: 'Hicks, Jack'; Burkhardt, Janet | | {{#Wiki_filter:From: Singal, Balwant Sent: Wednesday, January 05, 2011 10:48 AM To: 'Timothy.Hope@luminant.com' Cc: 'Hicks, Jack'; Burkhardt, Janet |
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| ==Subject:== | | ==Subject:== |
| Acceptance of Application - Amendment Request for Approval of the Steam Generator Tube Temporary Alternate Criteria - TAC ME5110 and ME5111 By letter dated December 1, 2010, Luminant Generation Company LLC submitted an amendment request for approval of the Steam Generator Tube Temporary Repair Criteria for Comanche Peak Nuclear Power Plant, Units 1 and 2. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | | Acceptance of Application - Amendment Request for Approval of the Steam Generator Tube Temporary Alternate Criteria - TAC ME5110 and ME5111 By letter dated December 1, 2010, Luminant Generation Company LLC submitted an amendment request for approval of the Steam Generator Tube Temporary Repair Criteria for Comanche Peak Nuclear Power Plant, Units 1 and 2. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
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| Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. | | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. |
| This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence. | | The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence. |
| | | If you have any questions, please contact me. |
| If you have any questions, please contact me. | |
| | |
| Balwant K. Singal Senior Project Manager (Columbia, Comanche Peak, and Wolf Creek) | | Balwant K. Singal Senior Project Manager (Columbia, Comanche Peak, and Wolf Creek) |
| Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222}} | | Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222}} |
Letter Sequence Acceptance Review |
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MONTHYEARML1100502412011-01-0505 January 2011 Acceptance Review Email, License Amendment Request, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria Project stage: Acceptance Review ML1034705962011-01-10010 January 2011 Request for Withholding Information from Public Disclosure, 12/5/2010 Affidavit Executed by J. Gresham, Westinghouse, WCAP-17330-P Project stage: Withholding Request Acceptance 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 Project stage: Approval 2011-01-05
[Table View] |
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Category:Acceptance Review Letter
MONTHYEARML23136B2962023-05-31031 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding General Design Criteria 5 and Regulatory Guide 1.81 ML19268A0392019-09-16016 September 2019 Acceptance Review for Comanche Peak QA Change Regarding Biennial Review of Procedures and Station Operations Review Committee Meetings (L-2019-LLQ-0002) ML18333A1302018-11-26026 November 2018 Acceptance of License Amendment Request to Change Emergency Plan for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML13253A0052013-09-11011 September 2013 Acceptance Review Following Supplement, Amendment Request to 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 ML13220A0032013-08-0707 August 2013 Acceptance Review Email, Request to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Using Consolidated Line Item Improvement Process (TAC Nos. MF2433-MF2434) ML13032A2412013-01-31031 January 2013 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, for Extension of Two 14-Day Completion Times for Offsite Circuits ML13018A0672013-01-18018 January 2013 Acceptance Review Email, Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, the Third 10-Year Inservice Inspection Interval ML12347A3162012-12-12012 December 2012 Acceptance Review E-mail, License Amendment Request 12-005 for Revision to Technical Specifications 3.3.1 and 3.3.2 ML12334A4562012-11-29029 November 2012 Independent Spent Fuel Storage Installation - Acceptance Review Email, Indirect License Transfer, Proposed Energy Future Holdings Corporation Internal Transaction ML12251A1222012-09-0707 September 2012 Acceptance Review E-mail - Relief Request C-2 for the Reactor Pressure Vessel Leak-Off Flange, Third 10-Year Inservice Inspection Interval ML12243A3322012-08-30030 August 2012 Acceptance Review Email Relief Request ML1212107672012-04-30030 April 2012 Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 5.5.9 and TS 5.6.9 for a Permanent Alternate Repair Criteria ML1203403892012-02-0303 February 2012 Acceptance Review Email, Relief Request No. A-2, Relief from Inspection Requirements of ASME Code Case N-729-1 Due to Geometric Limitations, 2nd 10-Year Inservice Inspection Interval ML1125003292011-09-0707 September 2011 Acceptance Review Email, Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section XI for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval ML1123509342011-08-23023 August 2011 Acceptance Review Email, License Amendment Request to Relocate Specific Surveillance Frequencies from Technical Specifications to a Licensee Controlled Program ML1101403932011-01-14014 January 2011 Acceptance Review Email for Relief Request (RR) C-7 for Containment Spray Heat Exchanger and RR C-6 for Excess Letdown Heat Exchanger, Second 10-Year Inservice Inspection Interval ML1100502412011-01-0505 January 2011 Acceptance Review Email, License Amendment Request, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria ML1022204672010-08-10010 August 2010 Acceptance Review Email, License Amendment Request for Approval of Cyber Security Plan ML1018900702010-07-0707 July 2010 Acceptance Review Email, License Amendment Request, Revise TS 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air, to Adopt TSTF-501, R1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML1013301982010-05-20020 May 2010 License Amendment Request for Approval of the Cyber Security Plan ML0934302122009-12-0909 December 2009 Acceptance Review Email License Amendment Request 09-003, Revise Technical Specification 3.8.1, AC Sources - Operating, to Extend Completion Time on a One-time Basis ML0922207482009-08-10010 August 2009 Acceptance Review Email, Relief Request, Request to Delay the Code of Record for the Inservice Inspection Program,1998 Edition of ASME Code, Section XI, 2000 Addenda ML0918005282009-06-29029 June 2009 Acceptance Review Email License Amendment Request to Revise Technical Specifications 5.5.9 and 5.6.9 ML0916903952009-06-18018 June 2009 Acceptance Review Email, Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels ML0911700132009-04-27027 April 2009 Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 (TAC Nos. ME1002 & ME1003) ML0910304582009-04-13013 April 2009 Acceptance Review E-mail, Application for Relief Request B-9 and B-8, and License Amendment Request to Add License Condition for Submittal of Inservice Inspection Info Per WCAP-16168 ML0907101132009-03-12012 March 2009 Acceptance Review Email, Administrative Revision to the Operating Licenses to Change Plant Name, and Reissue Technical Specifications to Remove TS and Tables No Longer Applicable to Operation ML0828316132008-10-0808 October 2008 Acceptance Review Email, Relief Request P-2 for Inservice Testing Plan for Pumps and Valves ML0727001092007-10-0909 October 2007 Acceptance Review of License Amendment Request 07-004, Revision to the OL and TS 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power (TAC MD6615/MD6616) 2023-05-31
[Table view] Category:E-Mail
MONTHYEARML24025A0172024-01-22022 January 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML24019A0742024-01-19019 January 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24008A2492023-12-18018 December 2023 Texas Shpo Response for Comanche Peak Deis Review and Comment ML23311A2202023-11-20020 November 2023 NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2023 ML23255A2882023-09-12012 September 2023 NRR E-mail Capture - Comanche Peak - Acceptance of Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23226A0072023-08-11011 August 2023 NRR E-mail Capture - Comanche Peak 1 and 2 Audit Plan - License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0722023-06-29029 June 2023 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23172A0152023-06-20020 June 2023 NRR E-mail Capture - Re Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23167A0222023-06-14014 June 2023 Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1 ML23145A2332023-05-25025 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 2 ML23143A1382023-05-23023 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 1 ML23139A0802023-05-18018 May 2023 NRR E-mail Capture - Comanche Peak Draft Supplemental Information Request - License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23138A1522023-05-18018 May 2023 Lr Docs - (External_Sender) Comanche Peak Nuclear Power Plants ML23135A9132023-05-15015 May 2023 NRR E-mail Capture - Comanche Peak - Draft Supplemental Information Request - License Amendment Request to 10 CFR 50.69 ML23131A2932023-05-11011 May 2023 Lr Docs - License Renewal for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23110A7122023-04-20020 April 2023 NRR E-mail Capture - Comanche Peak - Verbal Authorization of Proposed Alternative RV-1 (L-2023-LLR-0019) ML23103A4682023-04-11011 April 2023 NRR E-mail Capture - Comanche Peak Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23086B9852023-03-27027 March 2023 NRR E-mail Capture - Comanche Peak Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23061A1612023-03-0202 March 2023 E-mail from David Griggs Regarding Submission to NRC Electronic Information Exchange on 03/01/2023 for Citizens for Fair Utility Regulation in Comanche Peak Proceeding ML23032A3842023-02-0101 February 2023 LRA On-Site Audit Needs List ML23214A0192023-01-30030 January 2023 (External_Sender) Request to Broaden Extended Deadline to the General Public (with Attachments) - C3 ML23214A0202023-01-29029 January 2023 (External_Sender) Requesting a Deadline Extension on NRC-2002-0183, Comanche Peak License Renewal - C2 ML23214A0182023-01-26026 January 2023 (External Sender) NRC-2022-0183-0003 (with Attachment) - C6 ML23214A0162023-01-24024 January 2023 (External Sender) EPA Scoping Comment Letter for the Comanche Peak Nuclear Power Plant License Renewal (with Attachment) - C8 ML23214A0142023-01-23023 January 2023 (External Sender) Docket NRC-2022-0183 Comanche Peak Nuclear Power Plant Renewal (with Attachment) - C1 ML23214A0172023-01-17017 January 2023 (External Sender) NRC License Extension? No! ML23214A0132023-01-17017 January 2023 (External Sender) Docket Id NRC-2022-0183, Request for Extension of License for Comanche Peak, Comment for Environmental Scoping - C9 ML23214A0122023-01-13013 January 2023 (External Sender) Correction to Comment Submitted 01-13-23 - C11 ML22362A0992022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Apply Westinghouse Fsloca Evaluation Model ML22362A0972022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications, ML22325A2742022-11-21021 November 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22318A3102022-11-10010 November 2022 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22237A2842022-08-25025 August 2022 CPNPP 2022 EP Program Inspection RFI Hjs 08252022 ML22230B1092022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22229A0792022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22220A1942022-08-0808 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22133A0472022-05-13013 May 2022 July 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 ML22031A2122022-01-31031 January 2022 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative to Extend the Snubber Inservice Program Third Interval ML21300A1342021-10-27027 October 2021 NRR E-mail Capture - Comanche Peak Units 1 and 2 - License Amendment Request to Adopt TSTF-505 - Audit Plan Update and Audit Questions (L-2021-LLA-0085) ML21286A7912021-10-13013 October 2021 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1 ML21272A2002021-09-29029 September 2021 NRR E-mail Capture - Comanche Peak Unit 2 - Upcoming Steam Generator Tube Inservice Inspection (L-2021-NFO-0013) ML21270A1632021-09-27027 September 2021 NRR E-mail Capture - Comanche Peak - Acceptance of Quality Assurance Program Change Request Regarding Internal Audit Frequency ML21253A2242021-09-0909 September 2021 Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021 ML21252A0062021-08-26026 August 2021 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-01-22
[Table view] |
Text
From: Singal, Balwant Sent: Wednesday, January 05, 2011 10:48 AM To: 'Timothy.Hope@luminant.com' Cc: 'Hicks, Jack'; Burkhardt, Janet
Subject:
Acceptance of Application - Amendment Request for Approval of the Steam Generator Tube Temporary Alternate Criteria - TAC ME5110 and ME5111 By letter dated December 1, 2010, Luminant Generation Company LLC submitted an amendment request for approval of the Steam Generator Tube Temporary Repair Criteria for Comanche Peak Nuclear Power Plant, Units 1 and 2. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
If you have any questions, please contact me.
Balwant K. Singal Senior Project Manager (Columbia, Comanche Peak, and Wolf Creek)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222