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| | number = ML083050636 | | | number = ML083050636 |
| | issue date = 11/10/2008 | | | issue date = 11/10/2008 |
| | title = Request for Additional Information Relief Request P-2 for Inservice Testing Plan for Pumps and Valves (TAC Nos. MD9722 and MD9723) | | | title = Request for Additional Information Relief Request P-2 for Inservice Testing Plan for Pumps and Valves |
| | author name = Singal B | | | author name = Singal B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 10, 2008 Mr. M. R. Blevins Executive Vice President | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 10, 2008 Mr. M. R. Blevins Executive Vice President |
| & Chief Nuclear Officer Luminant Generation Company LLC A TIN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723) | | & Chief Nuclear Officer Luminant Generation Company LLC ATIN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 |
| | |
| | ==SUBJECT:== |
| | COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723) |
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| ==Dear Mr. Blevins:== | | ==Dear Mr. Blevins:== |
| By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1 O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation.
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| The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3016.
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| Sincerely,
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| Balwant K. Singal, Senior projectlMan;ger Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 | | By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation. The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter. |
| | If you have any questions, please contact me at 301-415-3016. |
| | Sincerely, b~\\;Jc\~ K1>\.~~ |
| | Balwant K. Singal, Senior projectlMan;ger Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST P-2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES COMPANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request (RR) P-2 for the second 1 O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps (SBSP). The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that the following additional information is needed in order to complete the evaluation: The RR states a test can be performed that demonstrates the SBSP can meet its intended safety functions. | | As stated cc w/encl: Distribution via Listserv |
| Please provide a copy of the test procedure that will be used, including acceptance criteria to be utilized, to determine acceptable pump performance. The RR states the SBSP test will require pumping the same quantity of fluid along a repeatable system path, while measuring flow and vibration. | | |
| Please describe how the flow rate is measured or determined. | | REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST P-2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES COMPANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request (RR) P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps (SBSP). |
| Also, discuss any system parameters associated with the flow path that will affect the results of the test and how those parameters will be controlled such that repeatability is achieved. The RR states the required SBSP head to pump to the Waste Holdup Tank is greater than the required head to discharge to the Floor Drain Tank, which is the normal lineup. Please discuss the safety-related lineup of the sump pumps and how the discharge head required during testing and normal operation differs from the discharge head required during emergency conditions. | | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that the following additional information is needed in order to complete the evaluation: |
| Enclosure November 10, 2008 Mr. M. R. Blevins Executive Vice President | | : 1. The RR states a test can be performed that demonstrates the SBSP can meet its intended safety functions. Please provide a copy of the test procedure that will be used, including acceptance criteria to be utilized, to determine acceptable pump performance. |
| & Chief Nuclear Officer Luminant Generation Company LLC ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723) | | : 2. The RR states the SBSP test will require pumping the same quantity of fluid along a repeatable system path, while measuring flow and vibration. Please describe how the flow rate is measured or determined. Also, discuss any system parameters associated with the flow path that will affect the results of the test and how those parameters will be controlled such that repeatability is achieved. |
| | : 3. The RR states the required SBSP head to pump to the Waste Holdup Tank is greater than the required head to discharge to the Floor Drain Tank, which is the normal lineup. |
| | Please discuss the safety-related lineup of the sump pumps and how the discharge head required during testing and normal operation differs from the discharge head required during emergency conditions. |
| | Enclosure |
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| | November 10, 2008 Mr. M. R. Blevins Executive Vice President |
| | & Chief Nuclear Officer Luminant Generation Company LLC ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043 |
| | |
| | ==SUBJECT:== |
| | COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723) |
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| ==Dear Mr. Blevins:== | | ==Dear Mr. Blevins:== |
| By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1 O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation. | | |
| The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter. Sincerely, IRAI Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 | | By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation. The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter. |
| | Sincerely, IRAI Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource LPLIV Reading RidsNrrPMBSingal Resource YHuang, NRR/DCI RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDciCptb Resource RidsOgcRp Resource ADAMS Accession No: | | PUBLIC RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource LPLIV Reading RidsNrrPMBSingal Resource YHuang, NRR/DCI RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDciCptb Resource RidsOgcRp Resource ADAMS Accession No: ML083050636 *Memo dated 10/27/08 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPTB/BC NRRlLPL4/BC NRRlLPL4/PM NAME BSingal '-h'ib JBurkhardt JMcHale* MMarkley W",-- BSingal ~>> |
| *Memo dated 10/27/08 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPTB/BC NRRlLPL4/BC NRRlLPL4/PM NAME BSingal '-h'ib JBurkhardt JMcHale* MMarkley W",--BSingal DATE \\,II'lA><b 11/4/08 10/27108 (((Co/7),£ , , \ D.,.C1'" OFFICIAL AGENCY RECORD}} | | DATE \\,II'lA><b 11/4/08 10/27108 (((Co/7),£ , , ~ \ D.,.C1'" |
| | OFFICIAL AGENCY RECORD}} |
Letter Sequence RAI |
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MONTHYEARCP-200801132, Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)2008-09-24024 September 2008 Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval) Project stage: Request ML0828316132008-10-0808 October 2008 Acceptance Review Email, Relief Request P-2 for Inservice Testing Plan for Pumps and Valves Project stage: Acceptance Review ML0830506362008-11-10010 November 2008 Request for Additional Information Relief Request P-2 for Inservice Testing Plan for Pumps and Valves Project stage: RAI CP-200801644, Response to Request for Additional Information for Relief Request No. P-2, Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda, Second Interval Start August 3, 2004)2008-12-0909 December 2008 Response to Request for Additional Information for Relief Request No. P-2, Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda, Second Interval Start August 3, 2004) Project stage: Response to RAI CP-200900707, Revision to Relief Request No. P-2 for the Units 1 & 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)2009-05-14014 May 2009 Revision to Relief Request No. P-2 for the Units 1 & 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval) Project stage: Request ML0916205482009-07-23023 July 2009 Relief Request P-2, Inservice Testing Plan for Pumps and Valves for Second Interval Project stage: Other ML12240A0522012-08-16016 August 2012 Relief Request No. P-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda Third Interval Start Date: August 3, 2013) Project stage: Request 2008-09-24
[Table View] |
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Category:Letter
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants CP-202400120, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400100, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400097, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24107B0292024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters SHPO ML24080A1802024-04-26026 April 2024 Ltr to Ken J. Peters, Sr VP and Chief Nuclear Officer, CPNPP re-NOA Final Plant Specific Supplement 60 IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 2024-09-03
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 10, 2008 Mr. M. R. Blevins Executive Vice President
& Chief Nuclear Officer Luminant Generation Company LLC ATIN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723)
Dear Mr. Blevins:
By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation. The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter.
If you have any questions, please contact me at 301-415-3016.
Sincerely, b~\\;Jc\~ K1>\.~~
Balwant K. Singal, Senior projectlMan;ger Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST P-2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES COMPANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request (RR) P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps (SBSP).
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that the following additional information is needed in order to complete the evaluation:
- 1. The RR states a test can be performed that demonstrates the SBSP can meet its intended safety functions. Please provide a copy of the test procedure that will be used, including acceptance criteria to be utilized, to determine acceptable pump performance.
- 2. The RR states the SBSP test will require pumping the same quantity of fluid along a repeatable system path, while measuring flow and vibration. Please describe how the flow rate is measured or determined. Also, discuss any system parameters associated with the flow path that will affect the results of the test and how those parameters will be controlled such that repeatability is achieved.
- 3. The RR states the required SBSP head to pump to the Waste Holdup Tank is greater than the required head to discharge to the Floor Drain Tank, which is the normal lineup.
Please discuss the safety-related lineup of the sump pumps and how the discharge head required during testing and normal operation differs from the discharge head required during emergency conditions.
Enclosure
November 10, 2008 Mr. M. R. Blevins Executive Vice President
& Chief Nuclear Officer Luminant Generation Company LLC ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RELIEF REQUEST NO. P-2 ASSOCIATED WITH INSERVICE TESTING PLAN FOR PUMPS AND VALVES (TAC NOS. MD9722 AND MD9723)
Dear Mr. Blevins:
By letter dated September 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082770065), Luminant Generation Company LLC (the licensee) submitted relief request P-2 for the second 1O-year pump and valve inservice testing plan for Comanche Peak Steam Electric Station, Units 1 and 2. The licensee requested relief from American Society of Mechanical Engineers Operation and Maintenance Code, 1998 Edition through 2000 Addenda, for the testing of the Safeguards Building Sump Pumps.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in the application and determined that additional information is needed in order to complete the evaluation. The request for additional information (RAI) was discussed with Mr. Jack Hicks of Luminant Generation Company LLC on November 10, 2008 and it was agreed that RAI response will be provided within 30 days from the date of this letter.
Sincerely, IRAI Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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