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| | number = ML072070387 | | | number = ML072070387 |
| | issue date = 07/25/2007 | | | issue date = 07/25/2007 |
| | title = (E-MAIL) RAI Information Revision of TS 3.8.1, AC Sources-Operating Extension of Completion Times for Diesel Generators (TAC Nos. MD4066, MD4067) | | | title = (E-MAIL) RAI Information Revision of TS 3.8.1, AC Sources-Operating Extension of Completion Times for Diesel Generators |
| | author name = Singal B | | | author name = Singal B |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
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| Describe the testing and maintenance program for the AACPS and its associated components. | | Describe the testing and maintenance program for the AACPS and its associated components. |
| : 2. The staff believes that certain compensatory measures in the form of regulatory commitments are needed during the extended DG CT to assure continued safe operation of the plant. In the past, other licensees have provided the following regulatory commitments in their DG CT extension requests. Provide a discussion as to how you would address each commitment listed below as it relates to CPSES: | | : 2. The staff believes that certain compensatory measures in the form of regulatory commitments are needed during the extended DG CT to assure continued safe operation of the plant. In the past, other licensees have provided the following regulatory commitments in their DG CT extension requests. Provide a discussion as to how you would address each commitment listed below as it relates to CPSES: |
| !
| |
| The extended CT will be typically used to perform infrequent (i.e., no more frequently than once every 24 months) diesel manufacturers recommended inspections and preventive maintenance activities. | | The extended CT will be typically used to perform infrequent (i.e., no more frequently than once every 24 months) diesel manufacturers recommended inspections and preventive maintenance activities. |
| !No maintenance or testing that affects the reliability of the train associated with the OPERABLE DG will be scheduled during the extended CT. If any testing and maintenance activities must be performed while the extended CT is in effect, an evaluation will be performed in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.65(a)(4). | | !No maintenance or testing that affects the reliability of the train associated with the OPERABLE DG will be scheduled during the extended CT. If any testing and maintenance activities must be performed while the extended CT is in effect, an evaluation will be performed in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.65(a)(4). |
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| !The scheduling of DG preplanned maintenance will be avoided during seasons when the probability of severe weather or grid stress conditions are high or forecasted to be high. | | !The scheduling of DG preplanned maintenance will be avoided during seasons when the probability of severe weather or grid stress conditions are high or forecasted to be high. |
| !
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| The system load dispatcher will be contacted once per day to ensure no significant grid perturbations are expected during the extended CT. Also, the system load dispatcher should inform the plant operator if conditions change during the extended CT (e.g., unacceptable voltages could result due to a trip of the nuclear unit). | | The system load dispatcher will be contacted once per day to ensure no significant grid perturbations are expected during the extended CT. Also, the system load dispatcher should inform the plant operator if conditions change during the extended CT (e.g., unacceptable voltages could result due to a trip of the nuclear unit). |
| !Component testing or maintenance of safety systems and important non-safety equipment including offsite power systems (auxiliary and startup transformers) that increase the likelihood of a plant transient or loss-of-offsite power will be avoided. In addition, no discretionary switchyard maintenance will be allowed. | | !Component testing or maintenance of safety systems and important non-safety equipment including offsite power systems (auxiliary and startup transformers) that increase the likelihood of a plant transient or loss-of-offsite power will be avoided. In addition, no discretionary switchyard maintenance will be allowed. |
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MONTHYEARCPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators2007-01-18018 January 2007 License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators Project stage: Request ML0717700432007-06-21021 June 2007 6/21/07 E-Mail from M. Thadani, Nrr/Dorl/Lpliv, to F. Madden and T. Hope, Txu Power - Request for Additional Information on License Amendment Request on Extension of Completion Times (MD4066, MD4067) Project stage: RAI ML0720703872007-07-25025 July 2007 (E-MAIL) RAI Information Revision of TS 3.8.1, AC Sources-Operating Extension of Completion Times for Diesel Generators Project stage: RAI CP-200800183, Withdrawal of License Amendment Request (LAR) 06-009, Revision to Technical Specification 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators2008-01-30030 January 2008 Withdrawal of License Amendment Request (LAR) 06-009, Revision to Technical Specification 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators Project stage: Withdrawal ML0812904622008-05-21021 May 2008 Withdrawal of License Amendment Request 06-009 to Revise Technical Specification 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators Project stage: Withdrawal 2007-07-25
[Table View] |
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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
[Table view] |
Text
From: Balwant Singal To: timothy.hope@txu.com Date: 07/25/2007 5:20:34 PM
Subject:
Revision to TS 3.8.1 - Extension of Completion Times for Diesel G, MD4066 and MD4067 Tim:
Our electrical engineering branch has completed the review of the subject amendment request and has requested for additional information to complete the review. The attached file provides the details of Request for Additional Information (RAIs) needed for completing our review.
Please review the RAI questions and let us know if a conference call is needed to discuss these questions.
Thanks.
Ref.: Application dated January 18, 2007 Balwant K. Singal Senior Project Manager (Comanche Peak) and Divisional Planning Representative Division of Operating Reactor Licensing (DORL)
Tel: (301) 415-3016 Fax: (301) 415-1222 e-mail: bks1@nrc.gov Balwant K. Singal Senior Project Manager (Comanche Peak) and Divisional Planning Representative Division of Operating Reactor Licensing (DORL)
Tel: (301) 415-3016 Fax: (301) 415-1222 e-mail: bks1@nrc.gov CC: fred.madden@txu.com; Hiltz, Thomas; Markley, Michael; McConnell, Matthew; Thadani, Mohan
REQUEST FOR ADDITIONAL INFORMATION COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 REVISION TO TECHNICAL SPECIFICATION (TS) 3.8.1, "AC SOURCES - OPERATING,"
EXTENSION OF COMPLETION TIMES FOR DIESEL GENERATORS By letter dated January 18, 2007 (Agencywide Documents Access and Management System Accession No. ML070230493), TXU Generation Company LP (the licensee) requested an amendment to Facility Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, and Appendix A, Technical Specifications (TSs), of the Facility Operating Licenses. The proposed changes would revise TS 3.8.1 for AC Sources -
Operating by extending the allowable Completion Time (CT) associated with the restoration of an inoperable diesel generator (DG) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. Specifically, the extended CT would establish a 14-day allowable out-of-service time when one DG is inoperable provided an alternate alternating current power source (AACPS) is available.
In order for the staff to proceed with its review of the proposed changes, the following additional information is needed:
- 1. Describe the design, capability, capacity, and reliability of the AACPS.
Describe the testing and maintenance program for the AACPS and its associated components.
- 2. The staff believes that certain compensatory measures in the form of regulatory commitments are needed during the extended DG CT to assure continued safe operation of the plant. In the past, other licensees have provided the following regulatory commitments in their DG CT extension requests. Provide a discussion as to how you would address each commitment listed below as it relates to CPSES:
The extended CT will be typically used to perform infrequent (i.e., no more frequently than once every 24 months) diesel manufacturers recommended inspections and preventive maintenance activities.
!No maintenance or testing that affects the reliability of the train associated with the OPERABLE DG will be scheduled during the extended CT. If any testing and maintenance activities must be performed while the extended CT is in effect, an evaluation will be performed in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.65(a)(4).
!AACPS with capacity equal to or greater than the capacity of the inoperable DG will be available as a backup to the inoperable DG. After entering the extended CT, availability of the AACPS will be verified every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and treated as protected equipment.
!The scheduling of DG preplanned maintenance will be avoided during seasons when the probability of severe weather or grid stress conditions are high or forecasted to be high.
The system load dispatcher will be contacted once per day to ensure no significant grid perturbations are expected during the extended CT. Also, the system load dispatcher should inform the plant operator if conditions change during the extended CT (e.g., unacceptable voltages could result due to a trip of the nuclear unit).
!Component testing or maintenance of safety systems and important non-safety equipment including offsite power systems (auxiliary and startup transformers) that increase the likelihood of a plant transient or loss-of-offsite power will be avoided. In addition, no discretionary switchyard maintenance will be allowed.
!TS requirements of verification that the required systems, subsystems, trains, components, and devices that depend on the remaining DG(s) are operable and positive measures will be provided to preclude subsequent testing or maintenance activities on these systems, subsystems, trains, components, and devices.
!Turbine-driven auxiliary feedwater pump will be controlled as protected equipment, and will not be taken out of service for planned maintenance while an DG is out of service for extended maintenance.
!Any component testing or maintenance that increases the likelihood of a plant transient would be avoided; plant operation should be stable during the DG CT.
- 3. In the past, the staff expects TS requirements to demonstrate that the AACPS is available and functional prior to removing a DG from service for an extended period. The TS requirements should also address the AACPS availability during the extended DG maintenance period including actions to be taken if the AACPS becomes unavailable during the extended DG outage. Discuss how the above staff expectations would be satisfied.
- 4. It is the staffs understanding that the purpose of the requested amendment is to allow an increased DG outage time during power operation for performing DG inspection, maintenance, and overhaul, which would include disassembly of the DG. DG operability verification after a major maintenance or overhaul may require a full-load rejection test. If a full-load rejection test is performed at power, please address the following:
a.What would be the typical and worst-case voltage transients on the 6.9 kilo-volt safety buses as a result of a full-load rejection?
b.If a full-load rejection test is used to test the DG governor after maintenance, provide assurance that an unsafe transient condition on the safety bus (i.e.,
load swing or voltage transient) due to improperly performed maintenance or repair of a governor would not occur.
c.Using maintenance and testing experience on the DG, identify possible transient conditions caused by improperly performed maintenance on the DG governor and voltage regulator. Discuss the electrical system response to these transients.
d.Provide the tests to be performed after overhaul to declare the DG operable and provide justification of performing those tests at power.
- 5. Due to the importance of the offsite power system:
a.Discuss the considerations given to not performing extended DG maintenance when the offsite grid condition or configuration is degraded or when adverse or extreme weather conditions (i.e., high winds, lightning, etc.)
are expected.
b.Discuss how you consider the amount of time needed to complete the extended DG maintenance and the ability to accurately forecast weather conditions that are expected to occur during the maintenance.
Mail Envelope Properties (46A7BEA2.EEC : 12 : 8784)
Subject:
Revision to TS 3.8.1 - Extension of Completion Times for Diesel G, MD4066 and MD4067 Creation Date 07/25/2007 5:20:34 PM From: Balwant Singal Created By: BKS1@nrc.gov Recipients nrc.gov OWGWPO04.HQGWDO01 TGH CC (Thomas Hiltz) nrc.gov TWGWPO01.HQGWDO01 MTM CC (Michael Markley)
MXM4 CC (Matthew McConnell) nrc.gov TWGWPO02.HQGWDO01 MCT CC (Mohan Thadani) txu.com fred.madden CC (fred.madden@txu.com) timothy.hope (timothy.hope@txu.com)
Post Office Route OWGWPO04.HQGWDO01 nrc.gov TWGWPO01.HQGWDO01 nrc.gov TWGWPO02.HQGWDO01 nrc.gov txu.com Files Size Date & Time MESSAGE 1871 07/25/2007 5:20:34 PM md4066-rai.wpd 12929 07/25/2007 3:22:35 PM Options Expiration Date: None Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No Security: Standard
From: Balwant Singal To: timothy.hope@txu.com Date: 07/25/2007 5:20:34 PM
Subject:
Revision to TS 3.8.1 - Extension of Completion Times for Diesel G, MD4066 and MD4067 Tim:
Our electrical engineering branch has completed the review of the subject amendment request and has requested for additional information to complete the review. The attached file provides the details of Request for Additional Information (RAIs) needed for completing our review.
Please review the RAI questions and let us know if a conference call is needed to discuss these questions.
Thanks.
Ref.: Application dated January 18, 2007 Balwant K. Singal Senior Project Manager (Comanche Peak) and Divisional Planning Representative Division of Operating Reactor Licensing (DORL)
Tel: (301) 415-3016 Fax: (301) 415-1222 e-mail: bks1@nrc.gov Balwant K. Singal Senior Project Manager (Comanche Peak) and Divisional Planning Representative Division of Operating Reactor Licensing (DORL)
Tel: (301) 415-3016 Fax: (301) 415-1222 e-mail: bks1@nrc.gov CC: fred.madden@txu.com; Hiltz, Thomas; Markley, Michael; McConnell, Matthew; Thadani, Mohan