Letter Sequence RAI |
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MONTHYEARCP-201500402, Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency2015-04-20020 April 2015 Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency Project stage: Request CP-201500999, Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection..2015-10-15015 October 2015 Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection.. Project stage: Request 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 Project stage: RAI ML16057A3102016-02-12012 February 2016 Westinghouse LTR-PAFM-16-8 Attachment B - Responses to the NRC RAIs Re Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years Project stage: Other ML16057A3092016-02-15015 February 2016 Response to Request for Additional Information Re Relief Request 1B3-3 Project stage: Response to RAI CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-02-29029 February 2016 Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. Project stage: Other ML16053A4462016-03-10010 March 2016 Request for Withholding Information from Public Disclosure, 2/10/16 Affidavit Executed by J. Gresham, Westinghouse Electric Company LLC LTR-PAFM-16-8 and LTR-PAFM-16-2-P, Revision 0, Relief Request 1B3-3 Project stage: Withholding Request Acceptance 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 Project stage: Other 2016-02-12
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Category:E-Mail
MONTHYEARML24205A2162024-07-23023 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 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 ML23214A0172023-01-17017 January 2023 (External Sender) NRC License Extension? No! ML23214A0122023-01-13013 January 2023 (External Sender) Correction to Comment Submitted 01-13-23 - C11 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, ML22362A0992022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Apply Westinghouse Fsloca Evaluation Model 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 ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 2024-07-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0022024-07-18018 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 ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information 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 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 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 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 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 ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23188A0452023-07-0707 July 2023 Request for Additional Information Requests - Comanche Peak - Set 3 ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23181A0212023-06-29029 June 2023 Request for Additional Information Requests - Comanche Peak - 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 2024-07-18
[Table view] |
Text
NRR-PMDAPEm Resource From: Singal, Balwant Sent: Thursday, January 14, 2016 1:26 PM To: Hope, Timothy Cc: Jack.Hicks@luminant.com; Alley, David; Collins, Jay
Subject:
Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 (CAC No. MF6125)
Attachments: MF6125-RAI.docx By letter dated April 20, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15119A216), as supplemented by letter dated October 15, 2015 (ADAMS Accession No.
ML15300A013), Luminant Generation Company, LLC (the licensee), proposed an alternative to Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(6)(ii)(F) for Comanche Peak Nuclear Power Plant, Unit 1. This regulation, in part, defines the inspection frequency requirement for the reactor vessel inlet butt welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR
[Pressurized Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1 with U. S. Nuclear Regulatory Commission (NRC) conditions. The licensee is requesting an extension of the required inspection frequency from once every 7 calendar years to once every 9 calendar years.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the information described in the attachment to this e-mail is needed in order to complete its review of the relief request.
The Draft request for additional information (RAI) was transmitted on January 12, 2016. Rob Slough of your organization informed us on January 14, 2016 that a clarification call is not needed. You are requested to respond to this request within 30 days of this e-mail. However, considering the fact that relief is needed in support of the upcoming Unit 1 refueling outage, please expedite your response.
Please treat this e-mail as formal transmittal of RAIs.
Thanks.
Balwant K. Singal Senior Project Manager (Comanche Peak and Columbia)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222 1
Hearing Identifier: NRR_PMDA Email Number: 2596 Mail Envelope Properties (b196d572e3a549578e173b8f944e86e0)
Subject:
Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 (CAC No. MF6125)
Sent Date: 1/14/2016 1:26:00 PM Received Date: 1/14/2016 1:26:00 PM From: Singal, Balwant Created By: Balwant.Singal@nrc.gov Recipients:
"Jack.Hicks@luminant.com" <Jack.Hicks@luminant.com>
Tracking Status: None "Alley, David" <David.Alley@nrc.gov>
Tracking Status: None "Collins, Jay" <Jay.Collins@nrc.gov>
Tracking Status: None "Hope, Timothy" <Timothy.Hope@luminant.com>
Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 2064 1/14/2016 1:26:00 PM MF6125-RAI.docx 26457 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF FROM 10 CFR 50.55a(g)(6)(ii)(F) REQUIREMENTS FOR COLD LEG WELD INSPECTION FREQUENCY LUMINANT GENERATION COMPANY, LLC, COMANCHE PEAK NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-445 By letter dated April 20, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15119A216), as supplemented by letter dated October 15, 2015 (ADAMS Accession No. ML15300A013), Luminant Generation Company, LLC (the licensee),
proposed an alternative to Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(6)(ii)(F) for Comanche Peak Nuclear Power Plant, Unit 1. This regulation, in part, defines the inspection frequency requirement for the reactor vessel inlet butt welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR [Pressurized Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1 with U. S. Nuclear Regulatory Commission (NRC) conditions. The licensee is requesting an extension of the required inspection frequency from once every 7 calendar years to once every 9 calendar years.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request.
Discussion on Flow Tolerance (Page 3 of 7 of the Letter Dated October 15, 2015)
A discussion of flaw tolerance is provided as part of the technical basis to support the relief request. The licensee states, in part, Based on the circumferential crack growth results, even for the most conservative case (high temperature with a 25% weld repair), a flaw with a depth of 15% of the wall thickness would not grow to the maximum allowable ASME flaw size in less than 10 years of continued operation.
Additionally, Figure 4 of Attachment 9.1 of letter dated April 20, 2015, shows that a Long SE
[Safe End] 25% Repair AR [Aspect Ratio] =10, High Temp flaw would grow from 10% through-wall to the ASME Code allowable flaw depth of 75% through-wall in approximately 20 years.
NRC staff performed a series of independent calculations and determined these values are not conservative. Additionally, the NRC staff did not identify a sufficient technical basis to address the potential of axial flaw growth. Therefore, the NRC staff requests the following;
- 1. The axial and hoop weld residual stresses (WRS) at operating temperature of the subject welds. If a generic WRS is used, include a basis for the WRS being conservative. (e.g. 50% weld repair, WRS validation used, safe end length, etc.)
- 2. Piping loads for the subject welds to include pressure, deadweight, 100% power normal operating thermal expansion, seismic events, and Loss of Coolant Accident (LOCA).
- 3. Weld dimensions for the subject welds include outside diameter and weld thickness.
NRR-PMDAPEm Resource From: Singal, Balwant Sent: Thursday, January 14, 2016 1:26 PM To: Hope, Timothy Cc: Jack.Hicks@luminant.com; Alley, David; Collins, Jay
Subject:
Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 (CAC No. MF6125)
Attachments: MF6125-RAI.docx By letter dated April 20, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15119A216), as supplemented by letter dated October 15, 2015 (ADAMS Accession No.
ML15300A013), Luminant Generation Company, LLC (the licensee), proposed an alternative to Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(6)(ii)(F) for Comanche Peak Nuclear Power Plant, Unit 1. This regulation, in part, defines the inspection frequency requirement for the reactor vessel inlet butt welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR
[Pressurized Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1 with U. S. Nuclear Regulatory Commission (NRC) conditions. The licensee is requesting an extension of the required inspection frequency from once every 7 calendar years to once every 9 calendar years.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the information described in the attachment to this e-mail is needed in order to complete its review of the relief request.
The Draft request for additional information (RAI) was transmitted on January 12, 2016. Rob Slough of your organization informed us on January 14, 2016 that a clarification call is not needed. You are requested to respond to this request within 30 days of this e-mail. However, considering the fact that relief is needed in support of the upcoming Unit 1 refueling outage, please expedite your response.
Please treat this e-mail as formal transmittal of RAIs.
Thanks.
Balwant K. Singal Senior Project Manager (Comanche Peak and Columbia)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222 1
Hearing Identifier: NRR_PMDA Email Number: 2596 Mail Envelope Properties (b196d572e3a549578e173b8f944e86e0)
Subject:
Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 (CAC No. MF6125)
Sent Date: 1/14/2016 1:26:00 PM Received Date: 1/14/2016 1:26:00 PM From: Singal, Balwant Created By: Balwant.Singal@nrc.gov Recipients:
"Jack.Hicks@luminant.com" <Jack.Hicks@luminant.com>
Tracking Status: None "Alley, David" <David.Alley@nrc.gov>
Tracking Status: None "Collins, Jay" <Jay.Collins@nrc.gov>
Tracking Status: None "Hope, Timothy" <Timothy.Hope@luminant.com>
Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 2064 1/14/2016 1:26:00 PM MF6125-RAI.docx 26457 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF FROM 10 CFR 50.55a(g)(6)(ii)(F) REQUIREMENTS FOR COLD LEG WELD INSPECTION FREQUENCY LUMINANT GENERATION COMPANY, LLC, COMANCHE PEAK NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-445 By letter dated April 20, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15119A216), as supplemented by letter dated October 15, 2015 (ADAMS Accession No. ML15300A013), Luminant Generation Company, LLC (the licensee),
proposed an alternative to Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(6)(ii)(F) for Comanche Peak Nuclear Power Plant, Unit 1. This regulation, in part, defines the inspection frequency requirement for the reactor vessel inlet butt welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR [Pressurized Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1 with U. S. Nuclear Regulatory Commission (NRC) conditions. The licensee is requesting an extension of the required inspection frequency from once every 7 calendar years to once every 9 calendar years.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request.
Discussion on Flow Tolerance (Page 3 of 7 of the Letter Dated October 15, 2015)
A discussion of flaw tolerance is provided as part of the technical basis to support the relief request. The licensee states, in part, Based on the circumferential crack growth results, even for the most conservative case (high temperature with a 25% weld repair), a flaw with a depth of 15% of the wall thickness would not grow to the maximum allowable ASME flaw size in less than 10 years of continued operation.
Additionally, Figure 4 of Attachment 9.1 of letter dated April 20, 2015, shows that a Long SE
[Safe End] 25% Repair AR [Aspect Ratio] =10, High Temp flaw would grow from 10% through-wall to the ASME Code allowable flaw depth of 75% through-wall in approximately 20 years.
NRC staff performed a series of independent calculations and determined these values are not conservative. Additionally, the NRC staff did not identify a sufficient technical basis to address the potential of axial flaw growth. Therefore, the NRC staff requests the following;
- 1. The axial and hoop weld residual stresses (WRS) at operating temperature of the subject welds. If a generic WRS is used, include a basis for the WRS being conservative. (e.g. 50% weld repair, WRS validation used, safe end length, etc.)
- 2. Piping loads for the subject welds to include pressure, deadweight, 100% power normal operating thermal expansion, seismic events, and Loss of Coolant Accident (LOCA).
- 3. Weld dimensions for the subject welds include outside diameter and weld thickness.