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| | number = ML070240464 | | | number = ML070240464 |
| | issue date = 01/24/2007 | | | issue date = 01/24/2007 |
| | title = Comanche Peak Steam Electric Station, Unit 1 - E-Mail to Fred Madden and Timothy Hope, Txu Power, from Mohan Thadani, Nrc/Nrr - Request for Additional Information - Relief Request No. B-6 (TAC No. MD3315) | | | title = E-Mail to Fred Madden and Timothy Hope, Txu Power, from Mohan Thadani, Nrc/Nrr - Request for Additional Information - Relief Request No. B-6 |
| | author name = Thadani M C | | | author name = Thadani M |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Hope T, Madden F | | | addressee name = Hope T, Madden F |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Mohan ThadaniTo:fred.madden@txu.com ; Timothy.Hope@txu.comDate: 1/24/2007 1:39:52 PM | | {{#Wiki_filter:From: Mohan Thadani To: fred.madden@txu.com ; Timothy.Hope@txu.com Date: 1/24/2007 1:39:52 PM |
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| ==Subject:== | | ==Subject:== |
| REQUEST FOR ADDITIONAL INFORMATION: RR B-6 (TAC MD3315) Fred/Tim: | | REQUEST FOR ADDITIONAL INFORMATION: RR B-6 (TAC MD3315) |
| The NRC staff has reviewed your request for Relief No. B-6, and has identified the followingRAI. Your response to the RAI below is needed in order to facilitate the NRC response to your request. If TXU Generation Company LP would like a formal request for this RAI, such a request will be promptly provided.Thank you for your cooperation. | | Fred/Tim: |
| Mohan OFFICE OF NUCLEAR REACTORREGULATION REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. B-6 COMANCHE PEAK STEAM ELECTRIC STATION TXU GENERATION COMPANY LP DOCKET NO. 50-4451.On page 18 of your transmittal, you indicate that weld shrinkage caused byapplication of the overlays will be measured and evaluated for any system impacts, as required by Code Case N-504-2, paragraph (g)(3). It is the staff's expectation that the requirements of Code Case N-504-2 (g)(2) and (g)(3) be completed prior to startup. Please discuss your time line for completing these requirements with respect to plant startup.2.On page 18 of your submittal, you state in part that your basis for increasing the overlaysurface area to 300 in2 is because the staff approved a 300 in2 at Susquehanna Steam Electric Station. Since each granting of relief is plant specific, please provide additional detail why your configuration(s) are similar in design and material to the SSES relief request as the basis why your modification to Code Case N-638-1 provides an acceptable level of quality and safety.3.On page 19 of your submittal, you state that Reg. Guide 1.147 Rev. 14 condition on useof N-638-1 is not applicable and will not be applied. Identify the UT acceptance criteria that will be used for the complete full structural weld overlay and heat-affected zone beneath the weld overlay. Since the acceptance criteria to be used is not consistent with the respective positionsstated in Regulatory Guide 1.147 for the applicable code cases, provide the technical bases for its use. 4. Provide a commitment to provide within 14 days from completion of UT examination ofthe weld overlays, a report that summarizes the results of the examinations, consistent with the September 14, 2006 letter from Exelon to NRC regarding Byron Station, Unit 1 Relief Request I3R-03.5.On page 20 of your submittal, you propose the use of contact pyrometers versusattached thermocouples. Please provide a more detailed discussion of your basis on the modification to use contact pyrometers and why your modification provides an acceptable level of quality and safety.6.Please discuss your repair strategy if the post overlay preservice inspection resultsidentify indications that exceed the acceptance criteria under Table IWB-3514-2. | | The NRC staff has reviewed your request for Relief No. B-6, and has identified the following RAI. Your response to the RAI below is needed in order to facilitate the NRC response to your request. If TXU Generation Company LP would like a formal request for this RAI, such a request will be promptly provided. |
| CC:Steingass, Timothy Mail Envelope Properties(45B7A7F8.D83 : 23 : 35106) | | Thank you for your cooperation. |
| | Mohan OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. B-6 COMANCHE PEAK STEAM ELECTRIC STATION TXU GENERATION COMPANY LP DOCKET NO. 50-445 |
| | : 1. On page 18 of your transmittal, you indicate that weld shrinkage caused by application of the overlays will be measured and evaluated for any system impacts, as required by Code Case N-504-2, paragraph (g)(3). It is the staffs expectation that the requirements of Code Case N-504-2 (g)(2) and (g)(3) be completed prior to startup. Please discuss your time line for completing these requirements with respect to plant startup. |
| | : 2. On page 18 of your submittal, you state in part that your basis for increasing the overlay surface area to 300 in2 is because the staff approved a 300 in2 at Susquehanna Steam Electric Station. Since each granting of relief is plant specific, please provide additional detail why your configuration(s) are similar in design and material to the SSES relief request as the basis why your modification to Code Case N-638-1 provides an acceptable level of quality and safety. |
| | : 3. On page 19 of your submittal, you state that Reg. Guide 1.147 Rev. 14 condition on use of N-638-1 is not applicable and will not be applied. Identify the UT acceptance criteria that will be used for the complete full structural weld overlay and heat-affected zone beneath the weld overlay. Since the acceptance criteria to be used is not consistent with the respective positions stated in Regulatory Guide 1.147 for the applicable code cases, provide the technical bases for its use. |
| | : 4. Provide a commitment to provide within 14 days from completion of UT examination of the weld overlays, a report that summarizes the results of the examinations, consistent with the September 14, 2006 letter from Exelon to NRC regarding Byron Station, Unit 1 Relief Request I3R-03. |
| | : 5. On page 20 of your submittal, you propose the use of contact pyrometers versus attached thermocouples. Please provide a more detailed discussion of your basis on the modification to use contact pyrometers and why your modification provides an acceptable level of quality and safety. |
| | : 6. Please discuss your repair strategy if the post overlay preservice inspection results identify indications that exceed the acceptance criteria under Table IWB-3514-2. |
| | CC: Steingass, Timothy |
| | |
| | Mail Envelope Properties (45B7A7F8.D83 : 23 : 35106) |
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| ==Subject:== | | ==Subject:== |
| REQUEST FOR ADDITIONAL INFORMATION: RR A-7Creation Date 1/24/2007 1:39:52 PMFrom: Mohan ThadaniCreated By:MCT@nrc.govRecipientsnrc.gov TWGWPO02.HQGWDO01 TXS3 CC (Timothy Steingass)txu.com fred.madden (fred.madden@txu.com ) | | REQUEST FOR ADDITIONAL INFORMATION: RR A-7 Creation Date 1/24/2007 1:39:52 PM From: Mohan Thadani Created By: MCT@nrc.gov Recipients nrc.gov TWGWPO02.HQGWDO01 TXS3 CC (Timothy Steingass) txu.com fred.madden (fred.madden@txu.com ) |
| Timothy.Hope (Timothy.Hope@txu.com)Post OfficeRoute TWGWPO02.HQGWDO01nrc.govtxu.comFilesSizeDate & Time MESSAGE46421/24/2007 1:39:52 PM Options Expiration Date: | | Timothy.Hope (Timothy.Hope@txu.com) |
| None Priority: Standard ReplyRequested: | | Post Office Route TWGWPO02.HQGWDO01 nrc.gov txu.com Files Size Date & Time MESSAGE 4642 1/24/2007 1:39:52 PM Options Expiration Date: None Priority: Standard ReplyRequested: No Return Notification: None Concealed |
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| ==Subject:== | | ==Subject:== |
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MONTHYEARML0702404642007-01-24024 January 2007 E-Mail to Fred Madden and Timothy Hope, Txu Power, from Mohan Thadani, Nrc/Nrr - Request for Additional Information - Relief Request No. B-6 Project stage: RAI CPSES-200700229, Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date..2007-02-0202 February 2007 Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date.. Project stage: Response to RAI ML0722707042007-09-12012 September 2007 Relief Request for Implementation of the EPRI-PDI Supplement 11 Program Requirements, and Weld Overlays, Relief Request B-6 (Tac No. MD3315) Project stage: Other 2007-02-02
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Category:E-Mail
MONTHYEARML24262A1302024-09-18018 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 ML23138A1522023-05-18018 May 2023 Lr Docs - (External_Sender) Comanche Peak Nuclear Power Plants 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 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 2024-09-18
[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 ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23256A1502023-09-11011 September 2023 Request for Additional Information Requests - Comanche Peak - 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 ML23167A0232023-06-14014 June 2023 Request for Additional Information (RAI) for the Review of the Comanche Peak Initial License Renewal Application (Lra), Set 1 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 ML23145A2322023-05-25025 May 2023 LRA - Request for Confirmation of Information - Set 2 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 ML23143A1372023-05-23023 May 2023 LRA - Request for Confirmation of Information - Set 1 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
From: Mohan Thadani To: fred.madden@txu.com ; Timothy.Hope@txu.com Date: 1/24/2007 1:39:52 PM
Subject:
REQUEST FOR ADDITIONAL INFORMATION: RR B-6 (TAC MD3315)
Fred/Tim:
The NRC staff has reviewed your request for Relief No. B-6, and has identified the following RAI. Your response to the RAI below is needed in order to facilitate the NRC response to your request. If TXU Generation Company LP would like a formal request for this RAI, such a request will be promptly provided.
Thank you for your cooperation.
Mohan OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. B-6 COMANCHE PEAK STEAM ELECTRIC STATION TXU GENERATION COMPANY LP DOCKET NO. 50-445
- 1. On page 18 of your transmittal, you indicate that weld shrinkage caused by application of the overlays will be measured and evaluated for any system impacts, as required by Code Case N-504-2, paragraph (g)(3). It is the staffs expectation that the requirements of Code Case N-504-2 (g)(2) and (g)(3) be completed prior to startup. Please discuss your time line for completing these requirements with respect to plant startup.
- 2. On page 18 of your submittal, you state in part that your basis for increasing the overlay surface area to 300 in2 is because the staff approved a 300 in2 at Susquehanna Steam Electric Station. Since each granting of relief is plant specific, please provide additional detail why your configuration(s) are similar in design and material to the SSES relief request as the basis why your modification to Code Case N-638-1 provides an acceptable level of quality and safety.
- 3. On page 19 of your submittal, you state that Reg. Guide 1.147 Rev. 14 condition on use of N-638-1 is not applicable and will not be applied. Identify the UT acceptance criteria that will be used for the complete full structural weld overlay and heat-affected zone beneath the weld overlay. Since the acceptance criteria to be used is not consistent with the respective positions stated in Regulatory Guide 1.147 for the applicable code cases, provide the technical bases for its use.
- 4. Provide a commitment to provide within 14 days from completion of UT examination of the weld overlays, a report that summarizes the results of the examinations, consistent with the September 14, 2006 letter from Exelon to NRC regarding Byron Station, Unit 1 Relief Request I3R-03.
- 5. On page 20 of your submittal, you propose the use of contact pyrometers versus attached thermocouples. Please provide a more detailed discussion of your basis on the modification to use contact pyrometers and why your modification provides an acceptable level of quality and safety.
- 6. Please discuss your repair strategy if the post overlay preservice inspection results identify indications that exceed the acceptance criteria under Table IWB-3514-2.
CC: Steingass, Timothy
Mail Envelope Properties (45B7A7F8.D83 : 23 : 35106)
Subject:
REQUEST FOR ADDITIONAL INFORMATION: RR A-7 Creation Date 1/24/2007 1:39:52 PM From: Mohan Thadani Created By: MCT@nrc.gov Recipients nrc.gov TWGWPO02.HQGWDO01 TXS3 CC (Timothy Steingass) txu.com fred.madden (fred.madden@txu.com )
Timothy.Hope (Timothy.Hope@txu.com)
Post Office Route TWGWPO02.HQGWDO01 nrc.gov txu.com Files Size Date & Time MESSAGE 4642 1/24/2007 1:39:52 PM Options Expiration Date: None Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No Security: Standard