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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
MONTHYEARML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20244042024-01-18018 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000498/2024404; 05000499/2024404 IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 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 ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses ML23271A1942023-10-0303 October 2023 Notification of Commercial Grade Dedication Inspection (05000498/2024013 and 05000499/2024013) and Request for Information ML23270B2592023-09-27027 September 2023 Update Foreign Ownership, Control, or Influence ML23263B1132023-09-20020 September 2023 Operator Licensing Examination Schedule Revision 1 IR 05000498/20243012023-09-0707 September 2023 Notification of NRC Initial Operator Licensing Examination 05000498/2024301; 05000499/2024301 IR 05000498/20233012023-09-0101 September 2023 NRC Examination Report 05000498/2023301 and 05000499/2023301 ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23236A6042023-08-24024 August 2023 Annual Dose Report for 2022 IR 05000498/20230052023-08-22022 August 2023 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023005 and 05000499/2023005) - Mid Cycle Letter ML23229A5262023-08-17017 August 2023 Inservice Inspection Summary Report - 1 RE24, ML23229A5892023-08-17017 August 2023 Voluntary Response to Regulatory Issue Summary (RIS) 2023-02, Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23228A2102023-08-15015 August 2023 Closure of Investigation (OI 4-22-19) ML23222A0322023-08-10010 August 2023 Report of Changes Made to Quality Assurance Program for Radioactive Material Packages ML23221A3002023-08-0909 August 2023 RE22 Inspection Summary Report for Steam Generator Tubinq, Rev. 1 (Epld L-2023-LRO-0029) ML23222A2792023-08-0909 August 2023 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20230022023-07-28028 July 2023 Integrated Inspection Report 05000498/2023002 and 05000499/2023002 ML23198A0532023-07-24024 July 2023 Request for Withholding Information from Public Disclosure ML23188A1612023-07-14014 July 2023 the Associated ISFSI - Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing (EPID L-2023-LLM-0004) - Letter ML23193A9932023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23192A0482023-07-11011 July 2023 NRC Initial Operator Licensing Examination Approval 05000498/2023301; 05000499/2023301 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) ML23180A2822023-06-29029 June 2023 Operator Licensing Examination Schedule ML23177A2522023-06-26026 June 2023 Units 1, 2 & Independent Spent Fuel Storage Installation - Biennial Submittal of Technical Specification Bases Changes, Commitment Changes, 10 CFR 50.59 Evaluation Summary, and 10 CFR 72.48 Evaluation Summary ML23166B0802023-06-14014 June 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23163A1762023-06-12012 June 2023 Application for Order Approving Indirect Transfer of Control of Licenses 2024-01-29
[Table view] Category:Safety Evaluation
MONTHYEARML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23279A0482023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Enclosure 4 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Nonproprietary Safety Evaluation) ML23015A0012023-02-0606 February 2023 Issuance of Amendment Nos. 225 and 210 to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML22300A2492022-12-0606 December 2022 Approval for Alternate Disposal Procedures for Very Low-Level Radioactive Material (EPID: L?2021?LLL?0022) ML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code ML21319A3552021-12-0909 December 2021 Issuance of Amendment Nos. 224 and 209 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21320A0022021-12-0808 December 2021 Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 22021-05-11011 May 2021 Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 ML21033A2392021-04-0808 April 2021 Issuance of Amendment Nos. 222 and 207 to Revise Technical Specifications to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML20253A0462020-09-29029 September 2020 Issuance of Amendment Nos. 220 and 205 to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping ML20199M1622020-07-21021 July 2020 Proposed Alternatives PRR-01, PRR-02, PRR-03, and PRR-04 to the Requirements of the ASME OM Code (Epids L-2020-LLR-0007 to L-2020-LLR-0010) ML20141L6122020-05-28028 May 2020 Issuance of Amendment No. 219 to Revise Technical Specifications to Reduce Safety Injection Accumulators Minimum Pressures (Exigent Circumstances) ML19322A7192019-12-0909 December 2019 Issuance of Amendment Nos. 218 and 204 to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML19217A0602019-10-24024 October 2019 Issuance of Amendment Nos. 217 and 203 Revision to Technical Specification Tables to Change Terminology for the P-13 Permissive Interlock Description ML19213A1472019-08-20020 August 2019 Issuance of Amendment Nos. 216 and 202 Standby Diesel Generator Surveillance Requirements ML19142A3072019-08-13013 August 2019 Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles ML19067A2222019-06-0606 June 2019 Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18303A2062018-11-0707 November 2018 Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval ML18187A1492018-07-24024 July 2018 Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18159A2122018-07-19019 July 2018 Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265) ML18128A3422018-06-0707 June 2018 Issuance of Amendment Nos. 213 and 199 to Revise TSs for Administrative Changes and to Relocate Fxy Exclusion Zones to the Colrs(Cac Nos. MG0253 and MG0254, EPID-L-2017-LLA-0300) ML17038A2232017-07-11011 July 2017 Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML17019A0022017-07-11011 July 2017 Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16319A0102016-12-21021 December 2016 Issuance of Amendment No. 211, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16174A0912016-06-30030 June 2016 Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval ML16116A0072016-04-29029 April 2016 Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years ML15342A0032015-12-28028 December 2015 Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179) ML15343A1282015-12-11011 December 2015 Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) ML15209A6412015-09-22022 September 2015 Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169 ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval ML15201A1952015-08-20020 August 2015 Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6 ML15075A1462015-04-29029 April 2015 Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits ML14339A1702015-02-13013 February 2015 Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability ML14281A0652015-01-29029 January 2015 Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13221A0042013-09-0909 September 2013 Issuance of Amendment Nos. 201 and 189, Revise TS 5.0, Design Features, to Reflect Removal of Visitor'S Center Building and References to Emergency Operations Facility ML13142A1602013-06-0606 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13008A5282013-04-25025 April 2013 Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation ML13087A5172013-04-12012 April 2013 Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage ML13004A3392013-03-12012 March 2013 Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval ML13007A1362013-01-31031 January 2013 Review of Operations Quality Assurance Plan, Revision 20 ML12243A3432012-09-10010 September 2012 RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds ML12235A3472012-08-28028 August 2012 Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054) ML12201A2562012-08-16016 August 2012 Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012 ML12152A2452012-08-14014 August 2012 Issuance of Amendment Nos. 199 and 187, Revise Applicability of Risk-Managed Technical Specifications (TS) to TS 3.7.7, Control Room Makeup and Cleanup Filtration System ML1124402222011-11-17017 November 2011 Issuance of Amendment Nos. 198 and 186, Revise Technical Specifications 5.3.1 and 6.9.1.6 to Allow Fuel Assemblies with Optimized Zirlo Cladding ML1126500712011-10-14014 October 2011 Relief Request RR-ENG-3-05, from Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds for Third 10-Year Inservice Inspection ML1118605352011-07-29029 July 2011 Relief Request RR-ENG-2-55 from ASME Code Requirements for Weld Examinations, Second 10-Year Inservice Inspection Interval 2023-02-06
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December 19, 2007 Mr. James J. Sheppard President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 330 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - APPROVAL OF EXTENSION REQUEST FOR CORRECTIVE ACTIONS RE: GENERIC LETTER 2004-02 "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS," (TAC NOS. MC4719 AND MC4720)
Dear Mr. Sheppard:
By letter dated December 10, 2007, as supplemented by letter dated December 13, 2007, the STP Nuclear Operating Company (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) staff a request for extension of the South Texas Project (STP), Units 1 and 2, sump clogging corrective actions completion date of December 31, 2007, as required in Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," to June 30, 2007.
The NRC staff has evaluated the licensees request. Based on its evaluation, the NRC staff concludes that the licensee has a reasonable plan for completion of corrective actions at STP, Units 1 and 2, that should result in acceptable strainer function with adequate margin for uncertainties. The NRC staff further concludes that the licensee has mitigation measures in place at STP, Units 1 and 2, to adequately reduce the risk for the requested extension period.
Therefore, the NRC staff finds that extension of the completion of corrective actions and modifications until June 30, 2008, is acceptable.
J. J. Sheppard The NRC staffs safety evaluation is enclosed. If you have any questions, please contact me at (301) 415-1476 or email mct@nrc.gov.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Safety Evaluation cc w/encl: See next page
ML073520076 (*) SE input memo OFFICE DORL/LPL4/PM DORL/LPL4/LA DSS/SSIB/BC DORL/LPL4/BC NAME MThadani JBurkhardt MScott (*) THiltz DATE 12/19/07 12/19/07 12/14/07 12/19/07 South Texas Project, Units 1 and 2 12/5/2007 cc:
Senior Resident Inspector STP Nuclear Operating Company U.S. Nuclear Regulatory Commission P.O. Box 289, Mail Code: N5014 P.O. Box 289 Wadsworth, TX 77483 Wadsworth, TX 77483 C. T. Bowman, General Manager, Oversight C. M. Canady STP Nuclear Operating Company City of Austin P.O Box 289 Electric Utility Department Wadsworth, TX 77483 721 Barton Springs Road Austin, TX 78704 Ms. Marilyn Kistler Senior Staff Specialist, Licensing J. J. Nesrsta/R. K. Temple STP Nuclear Operating Company E. Alercon/Kevin Pollo P.O. Box 289, Mail Code 5014 CPS Energy Wadsworth, TX 77483 P.O. Box 1771 San Antonio, TX 78296 Environmental and Natural Resources Policy Director INPO P.O. Box 12428 Records Center Austin, TX 78711-3189 700 Galleria Parkway Atlanta, GA 30339-3064 Mr. Jon C. Wood Cox, Smith, & Matthews Regional Administrator, Region IV 112 East Pecan, Suite 1800 U.S. Nuclear Regulatory Commission San Antonio, TX 78205 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Director, Division of Compliance & Inspection Bureau of Radiation Control Steve Winn/Christie Jacobs Texas Department of State Health Services Eddy Daniels/Marty Ryan 1100 West 49th Street NRC Energy, Inc. Austin, TX 78756 211 Carnegie Center Princeton, NJ 08540 Mr. Ted Enos 4200 South Hulen Mr. Nate McDonald Suite 422 County Judge for Matagorda County Ft. Worth, TX 76109
\1700 7th Street, Room 301 Bay City, TX 77414 Mr. Brian Almon Public Utility Commission of Texas A. H. Gutterman, Esq. P.O. Box 13326 Morgan, Lewis & Bockius Austin, TX 78711-3326 1111 Pennsylvania Avenue, NW Washington, DC 20004 E. D. Halpin, Site Vice President STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483 S. M. Head, Manager, Licensing
South Texas Project, Units 1 and 2 12/5/2007 Ms. Susan M. Jablonski Office of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087 Mr. Ken Coates, Plant General Manager STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483 Mr. Anthony P. Jones, Chief Boiler Inspector Texas Department of Licensing and Regulation Boiler Division E.O. Thompson State Office Building P.O. Box 12157 Austin, TX 78711
SAFETY EVALUATION BY OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO GENERIC LETTER 2004-02 FACILITY OPERATING LICENSES NOS. NPF-76 AND NPF-80 SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 In a letter dated December 10, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072520021), STP Nuclear Operating Company (STPNOC, the licensee), requested an extension of the due date of December 31, 2007, stated in Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," for completion of corrective actions at South Texas Project (STP), Units 1 and 2. In a telephone conference on December 12, 2007, the U.S. Nuclear Regulatory Commission (NRC) staff asked the licensee to provide additional information on actions taken to date at STP, Units 1 and 2, to address GL 2004-02. STPNOC supplemented its submittal, in a letter dated December 13, 2007 (ADAMS Accession No. ML07XXXXXXX), to provide the requested additional information.
STPNOC stated that it has taken actions toward accomplishing the corrective actions described in GL 2004-02, including replacing the sump screens with substantially larger sump strainers at both units. However, the licensee stated that some testing activities needed to fully address GL 2004-02 will not occur until early 2008, and that additional time will be needed for the licensee to evaluate the test results. STPNOC stated its belief that the testing results will fully support all corrective actions taken in response to issues identified in GL 2004-02. The licensee further stated that, since hardware, procedures, and administrative changes are already implemented, STPNOC has reasonable assurance that plant systems and operators would respond consistent with the intent of the GL 2004-02 corrective actions, including compliance with the regulatory requirements listed in GL 2004-02.
The licensee stated that additional strainer head-loss testing for chemical effects is scheduled to be completed in February 2008, that the test report is expected to be available in May 2008, and that additional actions will then be needed by STPNOC to complete formal verification of design inputs, assumptions, and conclusions of STPNOC calculations and evaluations. In addition, STPNOC stated that revision of downstream effects analyses could possibly be needed. The licensee requested an extension to June 30, 2008, to allow full completion of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, activities to support changing the plant design and licensing bases to be in compliance with actions taken in response to issues identified in GL 2004-02. The licensee stated that it will submit a letter by June 30, 2008, verifying completion of all corrective actions and confirming compliance with the regulatory requirements in GL 2004-02.
As of the date of issuance of this safety evaluation, document not yet placed into ADAMS.
The criteria for granting an extension to the due date of December 31, 2007, for completion of GL 2004-02 corrective actions are stated in SECY-06-0078. Specifically, an extension may be granted if:
- the licensee has a plant-specific technical/experimental plan with milestones and schedules to address outstanding technical issues with enough margin to account for uncertainties, and
- the licensee identifies mitigative measures to be put in place prior to December 31, 2007, and adequately describes how these mitigative measures will minimize the risk of degraded emergency core cooling system (ECCS) and containment spray system (CSS) functions during the extension period.
With regard to the first extension criterion, STPNOC has a plant-specific technical/experimental plan, with milestones and schedules, to complete the GL 2004-02 corrective actions by June 2008, as noted above.
With regard to the second extension criterion, the licensee stated that the following modifications, mitigative measures, compensatory measures, and/or favorable conditions are in effect at STP, Units 1 and 2, minimizing the risk of degraded ECCS and CSS functions during the extension period:
- 1. The three train-specific original design ECCS strainers for both STP units have been replaced with new design strainers. The new design increases the surface area of each strainer from 150.4 square feet to 1818.5 square feet. The diameter of the screen perforations has been reduced from 0.25 inches to 0.095 inches, thus significantly reducing the potential for downstream debris effects.
- 2. The surveillance procedure for inspection of the new design strainers has been implemented. The procedure requires a visual inspection of the entire exterior and the interior of the strainers, which includes a visual inspection of the sump and the vortex suppressor.
- 3. The procedure for design-change packages has been enhanced with additional controls related to managing potential debris sources such as insulation, post-loss-of-coolant accident (LOCA) recirculation flow paths, qualified coatings, addition of aluminum or zinc, and effect of post-LOCA debris on downstream components.
- 4. STPNOC has implemented actions described in its responses dated August 11, 2003, November 11, 2004, and July 13, 2005, to Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors. The measures implemented include refilling the refueling water storage tank after verification of proper swap over to cold-leg recirculation, provision of guidance in emergency operating procedures for restoration of recirculation or for alternate cooling methods if flow blockage occurs, and operator training on indications of and response to strainer clogging.
The NRC believes that STPNOC has a reasonable plan for STP, Units 1 and 2, that should result in acceptable strainer function with adequate margin for uncertainties. Further, the NRC concludes that STPNOC has put mitigation measures in place at STP to adequately reduce risk for the requested extension period.
Based on the licensee satisfactorily addressing the applicable NRC criteria as discussed above, it is acceptable to extend the completion date for certain corrective actions for the issues discussed in GL 2004-02 (specifically, the tests and analyses described above) until June 30, 2008, for STP, Units 1 and 2. While the NRC accepts this date as reasonable allowance for contingencies regarding completion of remaining activities to address GL 2004-02, the NRC expects STPNOC to place a high priority on completing remaining actions and updating the plants licensing bases as soon as possible.
Principal Contributor: M. Scott Date: December 19, 2007