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MONTHYEARCP-201500778, Relief Request B-11, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-11, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request CP-201500777, Relief Request B-10, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-10, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request CP-201500776, Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request CP-201500775, Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request ML15317A1552015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-11 for Reactor Coolant System Pipe to Valve Weld, Second 10-year Inservice Inspection Interval Project stage: RAI ML15317A1522015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-10 for Safety Injection System Elbow to Pipe Weld, Second 10-year Inservice Inspection Interval Project stage: RAI ML15317A1502015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-3 for Reactor Coolant System Pipe to Pipe Flange Weld, Second 10-year Inservice Inspection Interval Project stage: RAI ML15317A1482015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-9 for Reactor Pressure Vessel Outlet Nozzle Safe End to Piping Welds, Second 10-year Inservice Inspection Interval Project stage: RAI CP-201501100, Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) Project stage: Response to RAI CP-201501103, Response to Request for Additional Information for Relief Request B-11 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-11 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) Project stage: Response to RAI CP-201501101, Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) Project stage: Response to RAI CP-201501102, Response to Request for Additional Information for Relief Request B-10 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME, Section...)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-10 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME, Section...) Project stage: Response to RAI CP-201600147, Revision Response to Request for Additional Information Regarding for Relief Request B-3 for Second Ten Year Interval Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code Section XI, 2000 Addenda.2016-03-0202 March 2016 Revision Response to Request for Additional Information Regarding for Relief Request B-3 for Second Ten Year Interval Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code Section XI, 2000 Addenda. Project stage: Response to RAI CP-201600148, Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval2016-03-0202 March 2016 Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval Project stage: Request 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 Project stage: Other 2015-08-03
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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] Category:Request for Additional Information (RAI)
MONTHYEARML24019A0742024-01-19019 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 ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23256A1502023-09-11011 September 2023 Request for Additional Information Requests - Comanche Peak - Set 4 ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23213A2162023-08-0202 August 2023 Vistra Operations Company, LLC Notification of License Renewal Inspection and Request for Information ML23188A0452023-07-0707 July 2023 Request for Additional Information Requests - Comanche Peak - Set 3 ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0212023-06-29029 June 2023 Request for Additional Information Requests - Comanche Peak - Set 2 ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 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 ML23167A0232023-06-14014 June 2023 Request for Additional Information (RAI) for the Review of the Comanche Peak Initial License Renewal Application (Lra), Set 1 ML23145A2322023-05-25025 May 2023 LRA - Request for Confirmation of Information - Set 2 ML23143A1372023-05-23023 May 2023 LRA - Request for Confirmation of Information - Set 1 ML23132A2542023-05-23023 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization & Treatment of Structures,Systems & Components for Nuclear Power Reactors EPID L-2023-LLA-0057 ML23068A0562023-05-0909 May 2023 Request for Additional Information - Comanche Peak License Renewal Application Environmental Review ML23068A0732023-04-13013 April 2023 Requests for Confirmation of Information for the Environmental Review of the Comanche Peak Nuclear Power Plant, Units 1 and 2, Licensed Renewal Application (EPID Number: L-2022-LNE-0004) (Docket Numbers 50-445 and 50-446) 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 ML23010A1442023-01-0909 January 2023 Inservice Inspection Request for Information 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 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 ML22179A3032022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000445/2022401; 05000446/2022401 ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 ML21286A7912021-10-13013 October 2021 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1 ML21253A2242021-09-0909 September 2021 Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021 ML21253A2332021-09-0909 September 2021 Request for Information: Comanche Peak Nuclear Power Plant, Units 1 and 2 (05000445 and 05000446); Occupation Radiation Safety (71124.01, 71124.02, 7511) ML21245A3072021-09-0202 September 2021 Request for Information ML21245A307 ML21166A3382021-06-22022 June 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21165A1022021-06-13013 June 2021 Pi&R; Request for Information ML21103A3982021-04-13013 April 2021 CP Security Inspection Information Request 2021403 ML20225A0932020-08-12012 August 2020 Notification of Inspection 05000445/2020004 and 05000446/2020004 and Request for Information ML20105A1072020-04-13013 April 2020 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Exigent Amendment Request for One Time Change to Unit 2 Steam Generator Inspection Frequency ML20104A0022020-04-11011 April 2020 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - Proposed Alternative to ASME OM Code for Deferral of Snubber Testing (SNB-1) and Visual Examinations (SNB-2) ML20045E3512020-02-13013 February 2020 Information Request February 13, 2020 Notification of Inspection and Request for Information Comanche Peak Unit 2 NRC Inspection Report 05000446/2020002 ML19346B3812019-12-11011 December 2019 NRR E-mail Capture - Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19319A5432019-11-14014 November 2019 NRR E-mail Capture - Draft Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19058A3592019-02-27027 February 2019 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 - Final Request for Additional Information Concerning License Amendment Request to Revise the Emergency Plan IR 05000445/20170072018-02-0808 February 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000445/2017007 and 05000446/2017007) ML17276B8622017-10-0303 October 2017 Notification of NRC Design Bases Assurance Inspection (Programs)(05000445/2017007 and 05000446/2017007) and Initial Request for Information ML17087A2032017-03-28028 March 2017 NRR E-mail Capture - Comanche Peak, Unit 2 - Final Request for Additional Information Regarding Request No. 2B3-1 ML17066A2372017-03-0707 March 2017 Notification of NRC Triennial Fire Protection Baseline Inspection (05000445/2017008 and 05000446/2017008) and Request for Information ML17048A4172017-02-17017 February 2017 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment... ML16034A1962016-02-0808 February 2016 Independent Spent Fuel Storage Installation - Request for Additional Information, Application for Order Approving Transfer of Facility Operating Licenses and Conforming Amendment ML16015A0032016-01-14014 January 2016 NRR E-mail Capture - Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 ML15345A0112015-12-16016 December 2015 Request for Additional Information, License Amendment Request, Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML15317A1582015-11-13013 November 2015 Request for Additional Information Email, Relief Request 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 ML15317A1482015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-9 for Reactor Pressure Vessel Outlet Nozzle Safe End to Piping Welds, Second 10-year Inservice Inspection Interval ML15317A1502015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-3 for Reactor Coolant System Pipe to Pipe Flange Weld, Second 10-year Inservice Inspection Interval 2024-01-19
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1Burkhardt, JanetFrom:Singal, BalwantSent:Friday, November 13, 2015 8:36 AMTo:'Hope, Timothy' (Timothy.Hope@luminant.com)Cc:'Jack.Hicks@luminant.com' (Jack.Hicks@luminant.com); Burkhardt, Janet
Subject:
Request for Additional Information (RAI) - Relief Request B-11 (CAC No. MF6556)Attachments:RAI-MF6556-RR-B11.docxTim, By letter dated August 3, 2015 (Agencywide Documents Access ad Management System (ADAMS) Accession Number ML15224B364), Luminant Generation Company LLC requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Relief Request (RR) B-11 pertains to the examination coverage of the reactor coolant system pipe to valve weld at the Comanche Peak Nuclear Power Plant, Unit 2.
The NRC staff requests for the attached additional information to complete the review of this RR. Draft RAI were transmitted on November 6, 2015. Jack Hicks of your organization informed the NRC staff on November 12, 2015 that a clarification call is not needed.
Please treat this e-mail as formal transmittal of RAIs. You are requested to respond to this RAI request within 30 days from the date of this e-mail.
Thanks.
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST B-11 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNIT 2 DOCKET NUMBER 50-446 By letter dated August 3, 2015 (Agencywide Documents Access ad Management System (ADAMS) Accession Number ML15224B364), Luminant Generation Company LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Relief Request (RR) B-11 pertains to the examination coverage of the reactor coolant system pipe to valve weld at the Comanche Peak Nuclear Power Plant, Unit 2.
To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information. 1. The NRC staff notes that in a single-sided access or a limited access to far-side, the "Best Effort" examination using the refracted longitudinal (L) waves may be performed as an extra effort to interrogate the required examination volume on the far-side particularly the root of weld and the heat affected zone (HAZ) of base materials typically susceptible to high stresses and potential degradation. The L-waves have been shown capable of detecting planar flaws in the far-side volume of cast austenitic stainless steel and austenitic stainless steel weld and base materials in a single-sided examination. Given the reduced inspection coverage of the weld under consideration: a. Please discuss whether the license performed the "Best Effort" examination as an extra effort to interrogate the examination volume on the far-side (particularly the root of weld and HAZ of base materials typically susceptible to high stresses and potential degradation). b. Please provide percentage of coverage obtained from the "Best Effort" examination if this examination was performed. c. Please clarify whether the ASME Code required ultrasonic testing (UT), (as well as the "Best Effort" examinations if performed) covered the regions that are typically susceptible to higher stresses and, therefore, potential degradation (i.e.,
the weld root and HAZ of the base material near the inside diameter surface of the joint). 2. Section 2 of the RR states; The applicable ASME Boiler and Pressure Vessel Code (hereafter referred to as the "Code") edition and addenda is ASME Section XI, "Rule for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition, through 2000 Addenda. In addition, as required by 10 CFR [Title 10 of Code of Federal Regulations] 50.55a, ASME Section XI, 1995 Edition, 1996 Addenda is used for Appendix VIII, Performance Demonstration for Ultrasonic Examination System.
The NRC staff notes that pursuant to 10 CFR 50.55a(b)(2)(xv), "Section XI condition:
Appendix VIII specimen set and qualification requirements," licensees using Appendix VIII in the 1995 Edition through the 2001 Edition of the ASME Code may elect to comply with all of the provisions in paragraphs (b)(2)(xv)(A) through (M) of 50.55a, except for paragraph (b)(2)(xv)(F) of 50.55a, which may be used at the licensee's option. Licensees using editions and addenda after 2001 Edition through the 2006 Addenda must use the 2001 Edition of Appendix VIII and may elect to comply with all of the provisions in paragraphs (b)(2)(xv)(A) through (M) of 50.55a, except for paragraph (b)(2)(xv)(F) of 50.55a, which may be used at the licensee's option. a. Please clarify if 1998 Edition through 2000 Addenda to the ASME Code,Section XI, Appendix VIII, was used for ultrasonic testing (UT) personnel qualification and procedures demonstration. b. Please provide justification if other editions and addenda were used.. 3. Please provide the following information: a. Material specifications (e.g., austenitic stainless steel pipes SA-376, TP-304 and austenitic stainless steel ER-308 weldment) for the welds and associated components (e.g., pipe, and valves). b. Thickness of each pipe. 4. Please describe the following: a. The inservice inspection (ISI) history (i.e., inspection years, disposition of detected flaws, extent of condition assessment, and corrective actions). b. Whether the licensee identified any indications during construction and preservice inspections (i.e., radiographic testing or surface examination, or both) on the volume not covered by UT. c. Disposition of identified flaws. 5. Given the reduced inspection coverage of the welds under consideration, please discuss the following:
a. Any walkdowns (e.g., under Boric Acid Corrosion Control Program or normal operator rounds) usually performed to monitor and identify leakage in an unlikely event of a through wall leak. b. Reactor coolant system leakage detection capabilities at the plant, or any measures taken, to monitor and identify leakage during operation in an unlikely event of a through wall leak in the weld under consideration. 6. In an unlikely event of a potential though wall flaw and leakage, please discuss significance of the leak and potential for structural failure of the subject weld. 7. Please discuss any industry or plant-specific operating experience regarding potential degradation (e.g., stress corrosion cracking, corrosion, and fatigue) and potential severe loading (e.g., vibration, water hammer, and overloading) for the subject weld and associated components.
The NRC staff notes that due to recent operating experience regarding thermal fatigue cracking in some plants, the Electric Power Research Institute (EPRI) issued an interim guidance, "EPRI-MRP [Material Reliability Program] Interim Guidance for Management of Thermal Fatigue," (ADAMS Accession Number ML15189A100), that supplemented the existing industry thermal fatigue guidelines (e.g., MRP-1461 and MRP-1922) to better manage thermal fatigue cracking. Please discuss whether the licensee will take any compensatory measures to better manage thermal fatigue cracking in the subject weld to ensure structural integrity and leak tightness since essentially 100 coverage was not achieved by the UT. 8. Please discuss whether use of alternative volumetric examination techniques (e.g., the radiographic testing and phased array UT) would increase examination coverage.
8. It appears that the licensee reported in Attachments 1 and 2 to the RR that the UT was performed only in axial direction. Given that the licensee preformed a single-sided examination due to the valve body, please clarify whether scanning was done in both circumferential and axial directions, and the 50 percent coverage reported in Section 4 of the RR is the aggregate coverage of all ASME Code required UT performed in a single-sided examination (i.e., scanning of the weld in the circumferential and axial directions).
1 Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146) (Non-Publically Available) 2 Materials Reliability Program: Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR [Pressurized Water Reactor] Plants (MRP-192) (Non-Publically Available)