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MONTHYEARNOC-AE-05001862, 90-Day Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2005-03-0808 March 2005 90-Day Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0515302852005-06-0202 June 2005 6/2/05, South Texas Project, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI NOC-AE-05001907, 45-Day Response to a Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors2005-07-13013 July 2005 45-Day Response to a Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: Response to RAI NOC-AE-05001922, Supplement 1 to the Response to Generic Letter 2004-022005-08-31031 August 2005 Supplement 1 to the Response to Generic Letter 2004-02 Project stage: Supplement NOC-AE-06001968, Supplement 2 to the Response to Generic Letter 2004-022006-01-30030 January 2006 Supplement 2 to the Response to Generic Letter 2004-02 Project stage: Supplement ML0603902462006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactor. Project stage: RAI NOC-AE-07002237, Request for Extension for Final Response to Generic Letter 2004-02 and Implementation of Revised Design Basis for ECCS Sump2007-12-10010 December 2007 Request for Extension for Final Response to Generic Letter 2004-02 and Implementation of Revised Design Basis for ECCS Sump Project stage: Request ML0735200762007-12-19019 December 2007 Approval of Extension Request for Corrective Actions GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC4719 & MC4720) Project stage: Other ML0801403182008-01-28028 January 2008 Staff Audit Report on Results of Corrective Actions to Address GSI-191 GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs Project stage: Other ML0801400072008-01-28028 January 2008 Report on Results of Staff Audit of Corrective Actions to Address GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs Project stage: Other NOC-AE-07002240, Supplement 3 to the Response to Generic Letter 2004-022008-02-29029 February 2008 Supplement 3 to the Response to Generic Letter 2004-02 Project stage: Supplement NOC-AE-08002316, Request for Extension for Final Response to Generic Letter 2004-02 and Implementation of Revised Design Basis for ECCS Sump2008-06-19019 June 2008 Request for Extension for Final Response to Generic Letter 2004-02 and Implementation of Revised Design Basis for ECCS Sump Project stage: Request ML0818201642008-06-30030 June 2008 South Texas Project, Units 1 and 2 - E-mail from Albon Harrison (Stpegs) to Mohan Thadani (NRC PM) Request to Extend June 30, 2008 Implementation Due Date of a Revised ECCS Sump Strainer Project stage: Request ML0818300032008-07-0202 July 2008 Approval of Extension Request for Corrective Actions Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other ML0825301962008-09-0808 September 2008 Point Beach - Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request NOC-AE-08002372, Supplement 4 to the Response to Generic Letter 2004-02, (TAC Nos. MC4719 & MC4720)2008-12-11011 December 2008 Supplement 4 to the Response to Generic Letter 2004-02, (TAC Nos. MC4719 & MC4720) Project stage: Supplement ML0934106072009-12-23023 December 2009 Request for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1023004452010-08-27027 August 2010 Notice of Conference Call with STP Nuclear Operating Corp., to Discuss Request for Additional Information for Generic Letter 2004-02 Project stage: RAI ML1028103452010-10-13013 October 2010 9/13/2010 Summary of Conference Call with STP Nuclear Operating Company to Discuss Request for Additional Information Responses for South Texas Project, Units 1 and 2 on Generic Letter 2004-02 Project stage: RAI 2008-01-28
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Category:Letter type:NOC
MONTHYEARNOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 NOC-AE-240040, Annual Dose Report for 20232024-04-29029 April 2024 Annual Dose Report for 2023 NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing 2024-07-31
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Text
Nuclear Operating Company South TewsPr/csdEklctrcGnratingStation PO. o289 HMdsavrth, fiwas77483 JAVA January 30, 2006 NOC-AE-06001968 10CFR50.54(f)
U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Supplement 2 to the Response to Generic Letter 2004-02 (TAC Nos. MC4719 and MC4720)
Reference:
Letter, T. J. Jordan to Document Control Desk, "Supplement 1 to the Response to Generic Letter 2004-02", dated August 31, 2005 (NOC-AE-05001922, ML052500311)
In the referenced letter regarding STPNOC's response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors", STPNOC committed to provide an update of pending analyses and testing by January 31, 2006. Attachment 1 to this letter provides the current status.
The commitments in this letter are listed in Attachment 2.
If there are any questions regarding this response, please contact Scott Head at (361) 972-7136 or me at (361) 972-7902.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on J L AyV: 30,0 zoo Vice President, Engineering awh/
Attachments:
- 1. Supplement 2 to the Response to Gaeneric Letter 2004-02
- 2. List of Commitments 06001968 (Supplement 2 Reponse to GNL 2004-02, Sump lssue).doc STI:31978136
NOC-AE-06001 968 Page 2 of 2 cc:
(paper copy) (electronic copy)
Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Mohan C. Thadani Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Richard A. Ratliff Jack A. Fusco Bureau of Radiation Control Michael A. Reed Texas Department of State Health Services Texas Genco, LP 1100 West 49th Street Austin, TX 78756-3189 Jeffrey Cruz C. Kirksey U. S. Nuclear Regulatory Commission City of Austin P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 Jon C. Wood Cox Smith Matthews C. M. Canady J. J. Nesrsta City of Austin R. K. Temple Electric Utility Department E. Alarcon 721 Barton Springs Road City Public Service Austin, TX 78704 NOC-AE-06001968 Page 1 of 1 SUPPLEMENT 2 TO THE RESPONSE TO GENERIC LETTER 2004-02 As previously stated, STP Nuclear Operating Company (STPNOC) will be in full compliance with the regulatory requirements discussed in the applicable regulatory requirements section of GNL 2004-02 by December 31, 2007. This includes the full implementation of all plant modifications and required corrective actions.
STPNOC has a contract in place for Performance Contracting Inc. to provide an advanced design sump strainer for each Unit to replace the current sump screens. The modifications are scheduled to be implemented in Unit 1 during the Fall 2006 refueling outage and in Unit 2 during the Spring 2007 refueling outage. Laboratory testing for the STP specific strainer design is pending. *The testing will demonstrate the adequacy of the Net Pump Suction Head margins for the Emergency Core Cooling System and Containment Spray System Pumps. The strainer testing will also include bypass sampling and an evaluation to determine the quantity and characteristics of debris that bypasses the strainer.
A three-dimensional computational fluid dynamics analysis for debris transport is being finalized. The results are expected to yield transport fractions that are smaller than those determined in the baseline transport analysis. This will result in less debris loading on the strainer.
A latent debris walkdown inside containment was previously scheduled for the Fall 2005 refueling outage in Unit 2. This walkdown has been rescheduled to be performed in Unit 1 during power operation prior to the start of the Fall 2006 refueling outage. The at-power walkdown near the end of the fuel cycle is expected to be more representative of latent debris conditions than during an outage when the Unit is shutdown and many maintenance and inspection activities are taking place.
Resolution of the debris blockage issue concerning fuel assemblies is pending. A generic approach is ongoing by the Westinghouse Owners Group that includes evaluation of flow paths within the reactor vessel and evaluation of proposed testing of fuel assemblies in the laboratory. In addition, the results of the strainer bypass tests mentioned above will be used to reduce the fiber loading on the fuel assemblies.
A coatings test will be conducted by Westinghouse to demonstrate that the zone of influence for coatings may be defined using a radius of 5D (5 times the diameter of the break pipe). This result may be used to reduce the debris loading on the sump and to demonstrate margin for the new sump strainer design. The testing is planned to be completed by the second quarter of 2006.
Chemical effects testing and evaluation is; being conducted by the Westinghouse Owners Group. The results will be applied by STPNOC to the sump strainer design to show that acceptable NPSH margins are maintained.
STPNOC will provide another supplemental response with an update on the sump performance evaluation upon completion of pending analyses and testing.
Attachment 2 NOC-AE-06001 968 Page 1 of 1 List of Commitments The following table identifies those actions to which STP Nuclear Operating Company committed in this document. Any statements in this submittal with the exception of those in the table below are provided for information purposes and are not considered commitments. Please direct questions regarding these commitments to Scott Head at (361) 972-7136.
Commitment Due Date Condition Report
- 1. STPNOC will provide a Supplemental Response to August 31, 04-12498-11 Generic Letter 2004-02 upon completion of pending 2006 analyses and testing.
Text
Nuclear Operating Company South TewsPr/csdEklctrcGnratingStation PO. o289 HMdsavrth, fiwas77483 JAVA January 30, 2006 NOC-AE-06001968 10CFR50.54(f)
U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Supplement 2 to the Response to Generic Letter 2004-02 (TAC Nos. MC4719 and MC4720)
Reference:
Letter, T. J. Jordan to Document Control Desk, "Supplement 1 to the Response to Generic Letter 2004-02", dated August 31, 2005 (NOC-AE-05001922, ML052500311)
In the referenced letter regarding STPNOC's response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors", STPNOC committed to provide an update of pending analyses and testing by January 31, 2006. Attachment 1 to this letter provides the current status.
The commitments in this letter are listed in Attachment 2.
If there are any questions regarding this response, please contact Scott Head at (361) 972-7136 or me at (361) 972-7902.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on J L AyV: 30,0 zoo Vice President, Engineering awh/
Attachments:
- 1. Supplement 2 to the Response to Gaeneric Letter 2004-02
- 2. List of Commitments 06001968 (Supplement 2 Reponse to GNL 2004-02, Sump lssue).doc STI:31978136
NOC-AE-06001 968 Page 2 of 2 cc:
(paper copy) (electronic copy)
Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Mohan C. Thadani Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Richard A. Ratliff Jack A. Fusco Bureau of Radiation Control Michael A. Reed Texas Department of State Health Services Texas Genco, LP 1100 West 49th Street Austin, TX 78756-3189 Jeffrey Cruz C. Kirksey U. S. Nuclear Regulatory Commission City of Austin P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 Jon C. Wood Cox Smith Matthews C. M. Canady J. J. Nesrsta City of Austin R. K. Temple Electric Utility Department E. Alarcon 721 Barton Springs Road City Public Service Austin, TX 78704 NOC-AE-06001968 Page 1 of 1 SUPPLEMENT 2 TO THE RESPONSE TO GENERIC LETTER 2004-02 As previously stated, STP Nuclear Operating Company (STPNOC) will be in full compliance with the regulatory requirements discussed in the applicable regulatory requirements section of GNL 2004-02 by December 31, 2007. This includes the full implementation of all plant modifications and required corrective actions.
STPNOC has a contract in place for Performance Contracting Inc. to provide an advanced design sump strainer for each Unit to replace the current sump screens. The modifications are scheduled to be implemented in Unit 1 during the Fall 2006 refueling outage and in Unit 2 during the Spring 2007 refueling outage. Laboratory testing for the STP specific strainer design is pending. *The testing will demonstrate the adequacy of the Net Pump Suction Head margins for the Emergency Core Cooling System and Containment Spray System Pumps. The strainer testing will also include bypass sampling and an evaluation to determine the quantity and characteristics of debris that bypasses the strainer.
A three-dimensional computational fluid dynamics analysis for debris transport is being finalized. The results are expected to yield transport fractions that are smaller than those determined in the baseline transport analysis. This will result in less debris loading on the strainer.
A latent debris walkdown inside containment was previously scheduled for the Fall 2005 refueling outage in Unit 2. This walkdown has been rescheduled to be performed in Unit 1 during power operation prior to the start of the Fall 2006 refueling outage. The at-power walkdown near the end of the fuel cycle is expected to be more representative of latent debris conditions than during an outage when the Unit is shutdown and many maintenance and inspection activities are taking place.
Resolution of the debris blockage issue concerning fuel assemblies is pending. A generic approach is ongoing by the Westinghouse Owners Group that includes evaluation of flow paths within the reactor vessel and evaluation of proposed testing of fuel assemblies in the laboratory. In addition, the results of the strainer bypass tests mentioned above will be used to reduce the fiber loading on the fuel assemblies.
A coatings test will be conducted by Westinghouse to demonstrate that the zone of influence for coatings may be defined using a radius of 5D (5 times the diameter of the break pipe). This result may be used to reduce the debris loading on the sump and to demonstrate margin for the new sump strainer design. The testing is planned to be completed by the second quarter of 2006.
Chemical effects testing and evaluation is; being conducted by the Westinghouse Owners Group. The results will be applied by STPNOC to the sump strainer design to show that acceptable NPSH margins are maintained.
STPNOC will provide another supplemental response with an update on the sump performance evaluation upon completion of pending analyses and testing.
Attachment 2 NOC-AE-06001 968 Page 1 of 1 List of Commitments The following table identifies those actions to which STP Nuclear Operating Company committed in this document. Any statements in this submittal with the exception of those in the table below are provided for information purposes and are not considered commitments. Please direct questions regarding these commitments to Scott Head at (361) 972-7136.
Commitment Due Date Condition Report
- 1. STPNOC will provide a Supplemental Response to August 31, 04-12498-11 Generic Letter 2004-02 upon completion of pending 2006 analyses and testing.