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MONTHYEARML0603903012006-02-0909 February 2006 GSI Letter RAI Response to GL 2004-02 (TAC Nos. MC4676 and 4677) Project stage: RAI ML0817601002008-06-27027 June 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Approval of Extension Request Project stage: Other ML0835004652008-11-26026 November 2008 Comanche Peak - Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Cover Letter Project stage: Request ML0916604102009-05-11011 May 2009 E-mail Draft Request for Additional Information, Licensee'S Supplemental Responses Dated February 29 and November 26, 2008, to GL 2004-02 Project stage: Draft RAI ML0916604222009-05-11011 May 2009 Request for Additional Information Supplemental Responses to Generic Letter (GL) 2004-02 Dated 02/29/2008 and 11/26/2008 Project stage: RAI ML0918207102009-07-0202 July 2009 Revised Notice of Meeting with Representatives of Luminant Generation Co., LLC, Comanche Peak to Discuss Draft Request for Information for Generic Letter 2004-02 Response Project stage: Draft RAI ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing Project stage: Request ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues Project stage: Request ML0919402762009-07-0909 July 2009 NRC Opening Remarks Discuss the Draft Us Nuclear Regulatory Commission Request for Additional Information for Generic Letter GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressur Project stage: Draft RAI ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 Project stage: Request ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question Project stage: Request ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing Project stage: Request ML0916707382009-07-15015 July 2009 Request for Additional Information Supplemental Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0920203432009-07-22022 July 2009 Revised Conference Call with Luminant Generation Company, LLC, to Discuss Draft Request for Additional Information Re Generic Letter 2004-02, Dated May 11, 2009 Project stage: Draft RAI ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Meeting ML0926107912009-09-10010 September 2009 Comanche Peak Supplement Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request CP-200901396, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors.2009-10-12012 October 2009 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors. Project stage: Supplement ML0930800032009-10-13013 October 2009 Comanche Peak - Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009505642010-04-19019 April 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other ML13045A4102013-02-15015 February 2013 2/28/13 Notice of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting ML13059A2022013-02-28028 February 2013 Email Licensee Slides for 2/28/13 Meeting Via Conference Call Project stage: Meeting ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, Project stage: Meeting ML13067A0292013-03-15015 March 2013 2/28/13 - Summary of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting CP-201300670, Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance Project stage: Other ML13267A1972013-09-30030 September 2013 Request for Additional Information, Closure of Option 2a to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191 Project stage: RAI CP-201301214, Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 1912013-10-31031 October 2013 Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 191 Project stage: Response to RAI 2009-07-31
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Category:Letter
MONTHYEARCP-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 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 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final 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 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-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 ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe 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 ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report IR 05000445/20244022024-04-17017 April 2024 Security Baseline Inspection Report 05000445/2024402 and 05000446/2024402 (Full Report) ML24085A2252024-04-11011 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0037 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable ML24068A0762024-03-18018 March 2024 Final Transmittal Letter for Comanche Peak SE for LRA Review CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation IR 05000445/20230062024-02-28028 February 2024 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 Reports 05000445/2023006 and 05000446/2023006 2024-08-07
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Mike Blevins Executive Vice President& Chief Nuclear Officer Mike.Blevins@Luminlant.com Luminant Power P 0Box 1002 .6322 Norlh FM 56 Glen Rose, TX 76043 Lw,-ýALým2nt ,T 254 897 5209 C 817 559 9085 F 254 897 6652 CP-200801606 Log # TXX-08141 Ref. # GL 2004-02 November 26, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 SUPPLEMENT TO RESPONSE TO NRC GENERIC LETTER (GL) 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS"
REFERENCE:
- 1. Letter Logged TXX-05047 from M. Blevins to the NRC dated March 7, 2005, providing a 90-day response to NRC Generic Letter 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" 2. Letter Logged TXX-05162 from M. Blevins to the NRC dated September 1, 2005, providing a response to requested information part 2 of NRC Generic Letter 2004-02,"POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" 3. Letter Logged TXX-03130 from C. L. Terry to the NRC dated August 8, 2003, providing a response to NRC BULLETIN 2003-01, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER-REACTORS" 4. Letter Logged TXX-08033 from M. Blevins to the NRC dated February 29, 2008, providing an NRC Generic Letter 2004-02 supplemental response 5. Letter Logged TXX-08095 from M. Blevins to the NRC dated August 28, 2008, providing an NRC Generic Letter 2004-02 supplemental response
Dear Sir or Madam:
Luminant Power provided responses to NRC Bulletin 2003-01 and NRC Generic Letter (GL 2004-02) in References 1, 2, and 3. Subsequently, Luminant Power provided an update to the modifications and maintenance actions for resolution of GL 2004-02 per Reference
- 4. Reference 5 stated that all required actions in support of resolution of GL 2004-02 have been completed.
In addition, Luminant Power plans on additional enhancements to various procedures and programs related to control of potential debris.Enclosed, please find Luminant Power's update to the modifications and maintenance actions for resolution of GL 2004-02.A- 1 //0 A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak .Diablo Canyon
- Palo Verde .San Onofre South Texas Project
- Wolf Creek U. S. Nuclear Regulatory Commission TXX-08141 Page 2 November 26, 2008 For Comanche Peak Nuclear Power Plant (CPNPP), Luminant Power has implemented an overall holistic approach to resolve NRC Generic Safety Issue (GSI) 191. The holistic approach includes: Implementation of multiple design modifications to substantially increase the size and effectiveness of the containment emergency sump strainers.
The new strainers are qualified by prototypical testing for the design.basis debris loading.Procedures have been implemented to provide clear direction to the operations and technical support staff for monitoring post loss-of-coolant accident (LOCA) long term recirculation operation.
These procedures include directions for monitoring system performance and contingency actions in the event that indications warrant the need.The analyses that support the design modifications include numerous conservatisms to ensure that the overall analyses and modification design include substantial margins to account for uncertainties.
CPNPP recognizes that uncertainties exist in various aspects of this issue and has taken adequate measures to accommodate these uncertainties.
Luminant Power has performed numerous additional activities to establish the qualification of the new, strainer system. These activities are:* Containment Condition Assessments
- Replacement of Radiation Protection Locked High Radiation Doors to the Steam Generator Compartments
- Redesign of the Drain Path to the Inactive Sump* Removal of Radiation Protection Barriers and a Tool Room Enclosure* Implementation of Compensatory Actions in response to NRC Bulletin 2003-01 have been implemented as permanent changes in procedures
- Containment Coatings Assessments 0 Evaluation of the Plant Labeling Program 0 Upstream Effects Evaluation
- Debris Generation Evaluation
- Debris Transport Evaluation
- Downstream Effects Evaluations
-The following evaluations were performed:
- Blockage (except for reactor vessel)* Equipment Wear* Valve Wear* Reactor Vessel Blockage* Fuel Blockage* Evaluation of Long Term Cooling*
- The NRC staff has reviewed Westinghouse Topical Report WCAP-16793, Revision 0, but has not issued a final Safety Evaluation on this report. The CPNPP analysis and licensing basis are in accordance with WCAP-16793.
When the NRC final Safety Evaluation on WCAP-16793 is issued, it will be reviewed for impact and the evaluation of long term cooling will be revised as appropriate.
CPNPP performed evaluations of existing engineering design specifications, engineering design standards, engineering programs, modification and maintenance processes and procedures, and station operation processes and procedures.
Potential changes were identified and the required changes were implemented.
These changes will ensure the inputs and assumptions that support the current analysis U. S. Nuclear Regulatory Commission TXX-08141 Page 3 November 26, 2008 effort are incorporated into the applicable documents to maintain the necessary attributes fdr future compliance with these requirements.
Changes included:* Revision to design control procedures to explicitly address emergency sump performance impacts Revision to Design Basis Documents and Engineering Specifications to ensure necessary control of existing and future materials that could affect sump performance
- Revision to the Coatings Program* Revision to the Station Labeling Program to ensure control of label materials and locations in containment The supplemental response will be revised and submitted within 90 days after issuance of the final Safety Evaluation on WCAP-16793.
This letter contains the following new licensing commitments regarding Comanche Peak Units 1 and 2.Commitment No Description 3641550 The CPNPP analysis and licensing basis are in accordance with WCAP-16793.
When the NRC final Safety Evaluation on WCAP-16793 is issued, it will be reviewed for impact and the evaluation of long term cooling will be revised as appropriate.
The supplemental response will be revised and submitted within 90 days after issuance of the final Safety Evaluation.
Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.I state under penalty of perjury that the foregoing is true and correct.Executed on November 26, 2008.Sincerely, Luminant Generation Company LLC Mike Blevins By Mitchell L. Lucas Vice President, Nuclear Engineering and Support
Enclosure:
ER-ESP-001, Revision 1, Generic Letter 2004-02 Supplemental Response (Luminant Power's Update to the Modifications and Maintenance Actions for Resolution of GL 2004-02)c -E. E. Collins, Region IV clo B. K. Singal, NRR Resident Inspectors, Comanche Peak clo