Letter Sequence Acceptance Review |
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TAC:MF2651, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) TAC:MF2652, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) |
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MONTHYEARCP-201301065, Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-08-29029 August 2013
Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
Project stage: Request
ULNRC-06035, CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests2013-08-29029 August 2013
CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests
Project stage: Other
ML13246A3042013-08-30030 August 2013
Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
Project stage: Other
ML13246A3072013-09-0909 September 2013
Memorandum to File - Verbal Authorization of Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
Project stage: Other
ML13256A1862013-09-12012 September 2013
Acceptance Review Email, Adoption of TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Using Consolidated Line Item Improvement Process
Project stage: Acceptance Review
ML14027A0572014-01-29029 January 2014
Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
Project stage: Other
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)
Project stage: Approval
ML14176A7482014-07-18018 July 2014
Request to Use a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI (TAC MF2640-51)
Project stage: Other
2013-09-09
[Table View] |
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Category:E-Mail
MONTHYEARML24292A0282024-10-18018 October 2024
NRR E-mail Capture - Acceptance Review Comanche Peak Adoption of TSTF-51, TSTF-471, and TSTF-571
ML24262A1302024-09-18018 September 2024
NRR E-mail Capture - Acceptance Review Comanche Peak Multiple Relief Requests for Unit 2 Third Inservice Inspection Interval Due to Impracticality (EPID L-2024-LLR-0053 Through -0058)
ML24205A2162024-07-23023 July 2024
September 2024 Emergency Preparedness Program Inspection - Request for Information
ML24204A0022024-07-18018 July 2024
NRR E-mail Capture - Request for Additional Information Comanche Peak Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
ML24095A1532024-04-0404 April 2024
NRR E-mail Capture - Acceptance Review Comanche Peak Request to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program (EPID 2024-LLA-0023)
ML24095A2382024-04-0404 April 2024
NRR E-mail Capture - Acceptance Review Comanche Peak Request to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown
ML24052A0122024-02-16016 February 2024
NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications
ML24033A2642024-02-0202 February 2024
NRR E-mail Capture - Comanche Peak - Revised Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24036A0122024-02-0202 February 2024
NRR E-mail Capture - Comanche Peak - Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24025A0172024-01-22022 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
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
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
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
2024-09-18
[Table view] |
Text
Burkhardt, Janet From: Singal, Balwant Sent: Thursday, September 12, 2013 4:43 PM To: 'Hope, Timothy' Cc: 'Jack.Hicks@luminant.com'
Subject:
Acceptance of Application - License Amendment Request 13-002 for Revision to Technical Specifications (TSs) 3.8.1 for Adoption of TSTF-510 (TACs MF2651 and MF2652)
By letter dated August 29, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13255A021), Luminant Generation Company, LLC submitted a license amendment request for Comanche Peak Nuclear Power Plant, Units 1 and 2, for revision to Technical Specifications (TSs) for adoption of Technical Specification Task Force (TSTF)-510. The proposed change revises TSs 3.4.17, Steam Generator (SG) Tube Integrity, TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Tube Inspection Report. 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 TSs) 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 staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3016.
Balwant K. Singal Senior Project Manager (Comanche Peak and STP)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222 1
