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MONTHYEARNOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 202015-12-0303 December 2015 Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20 Project stage: Request NOC-AE-15003318, Response to Request for Additional Information and Supplement to Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 202015-12-0909 December 2015 Response to Request for Additional Information and Supplement to Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20 Project stage: Supplement NOC-AE-16003351, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies2016-04-0707 April 2016 License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: Request ML16127A4522016-05-12012 May 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: Acceptance Review NOC-AE-16000338, Supplement to License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies2016-05-25025 May 2016 Supplement to License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: Supplement ML16158A0622016-06-0606 June 2016 Acceptance of Requested Licensing Action Following Supplement, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: Acceptance Review ML16188A3682016-07-0606 July 2016 Audit Presentation - Westinghouse Methodology for South Texas Unit 1 LAR: Operation with 56 Control Rods Project stage: Request ML16214A2912016-08-26026 August 2016 Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: Other ML16246A0952016-09-15015 September 2016 Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies Project stage: RAI 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 Project stage: Approval 2016-05-12
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Category:Audit Report
MONTHYEARML21236A3082021-09-10010 September 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Moderator Temperature Coefficient Surveillance Requirements ML20142A2792020-05-27027 May 2020 Regulatory Audit Summary Regarding Exigent License Amendment Request to Revise the Safety Injection Accumulators Pressures ML17107A3192017-05-16016 May 2017 Aluminum Bronze Selective Leaching Aging Management Program Audit Report Regarding the South Texas Project, Units 1 and 2, License Renewal Application (CAC Nos. ME4936 and ME4937) ML16218A2562016-08-30030 August 2016 Aluminum Bronze Selective Leaching Aging Management Program and PWR Reactor Internals Program Inspection Plan Audit Report Regarding the South Texas Project, Units 1 and 2 ML16214A2912016-08-26026 August 2016 Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16141B0812016-05-31031 May 2016 Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information ML16127A4002016-05-11011 May 2016 Audit Summary, Thermal-Hydraulic Review on February 23-25, 2016 at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue 191 (CAC MF2400-MF2409) ML16103A3442016-04-26026 April 2016 Summary of February 24-26, 2016 Audit, Debris Transport Review at Alion Science and Technology Corporation, Albuquerque, Nm; Pilot Submittal and Exemption Request, Risk-Informed Approach to Resolve GSI 191 ML16095A0102016-04-13013 April 2016 Summary of November 17-19, 2015 Thermal-Hydraulic Review at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC MF2400-MF2409) ML16096A0652016-04-13013 April 2016 Summary of February 4 and 16, 2016, Regulatory Audit at Westinghouse in Rockville, MD, Boric Acid Precipitation, Exemption and License Amendment Request, Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16029A2722016-03-15015 March 2016 12/7-8/2015 Audit Summary, Audit Conducted to Support License Amendment Request to Revise TS 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) ML15175A0242015-07-29029 July 2015 Audit Summary for May 12-14, 2015 Audit of Roverd Methodology Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (TAC Nos. MF2400 Through MF2409) ML15183A0072015-07-15015 July 2015 Audit Summary, 3/31 to 4/2/15 Audit of Systems, Structures and Equipment at STP Facility; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 ML15131A1452015-06-0404 June 2015 Audit Report for the 2015 Supplemental Audit STP License Renewal ML15111A4652015-05-0606 May 2015 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15183A0092015-04-0202 April 2015 Photos, Audit Summary, 3/31 to 4/2/15 Audit of Systems, Structures and Equipment at STP Facility; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 ML14321A6772015-01-15015 January 2015 Audit Report for 9/16-17/2014 Audit at University of New Mexico Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (TAC MF2400 Through and MF2409) ML13339A7362014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML12165A2392012-06-15015 June 2012 Report Regarding the Follow-up Audit of the Selective Leaching of Aluminum Bronze Aging Management Program for the South Texas Project, Units 1 and 2, License Renewal Application (TAC ME4936 and ME4937) ML11224A2652011-09-22022 September 2011 Aging Management Programs Audit Report Regarding the South Texas Project, Units 1 and 2, Station License Renewal Application (TAC Nos. ME4936 and ME4937) ML1122106582011-09-0707 September 2011 Audit of the Licensee Regulatory Commitment Management Program, Audit Performed July 19-20, 2011 ML11230A0032011-09-0606 September 2011 Scoping and Screening Audit Report Regarding the South Texas Project, Units 1 and 2 (TAC Nos. ME4936 and ME4937) ML11173A3042011-07-18018 July 2011 Audit Report Regarding South Texas Project License Renewal Application - Cultural Resource ML11145A0642011-06-21021 June 2011 Plan for the Environmental Related Regulatory Audit Regarding the South Texas Project, Units 1 and 2, License Renewal Application Review (TAC Nos. ME4938 and ME4939) ML0834501622008-12-24024 December 2008 Audit Report of Licensee Regulatory Commitment Management Program for Audit Performed August 19, 2008 ML0721101192007-08-16016 August 2007 Us NRC Audit Report for South Texas Project Combined License Application Review ML0426702502004-09-22022 September 2004 Audit of the Licensees Management of Regulatory Commitments NOC-AE-04001712, Appendix a Cameco Corporation 2003 Consolidated Audited Financial Statements2004-02-27027 February 2004 Appendix a Cameco Corporation 2003 Consolidated Audited Financial Statements 2021-09-10
[Table view] 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:Request for Additional Information (RAI)
MONTHYEARML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information ML23334A0062023-11-29029 November 2023 NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements ML23319A4442023-11-15015 November 2023 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements ML23278A1532023-10-0505 October 2023 NRR E-mail Capture - South Texas Project Request for Additional Information - Request for Indirect Transfer of Licenses and Conforming Amendments (L-2023-LLM-0004) ML23264A0972023-09-21021 September 2023 NRR E-mail Capture - South Texas Project - Request for Additional Information - License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047) ML23255A2862023-09-12012 September 2023 NRR E-mail Capture - South Texas Project Draft Request for Additional Information License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047) ML23145A1872023-05-24024 May 2023 July 2023 Emergency Preparedness Program Inspection - Request for Information ML22255A1542022-09-13013 September 2022 Operating Company Information Request for the Cyber Security Baseline Inspection 05000498/2022401 and 05000499/2022401 ML22206A0142022-07-20020 July 2022 NRR E-mail Capture - South Texas Project - Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22194A0502022-07-0707 July 2022 NRR E-mail Capture - South Texas Project - Updated Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22194A0492022-06-0808 June 2022 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22123A3272022-05-0303 May 2022 STP EP Exercise Inspection July 2022 RFI ML22084A0762022-04-0404 April 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000498/2022012 and 05000499/2022012) and Request for Information ML21286A5732021-10-18018 October 2021 Notification of NRC Design Bases Assurance Inspection (Programs) (05000498/2022011 and 05000499/2022011) and Request for Information ML21166A2392021-06-16016 June 2021 Notification of Inspection (NRC Inspection Report 05000498/2021003 and 05000499/2021003) and Request for Information ML21160A1522021-06-0909 June 2021 Request for Information NRC Inspection 2021-003 Public Radiation Safety ML21133A2372021-05-0505 May 2021 Request for Additional Information: STP EP Exercise Inspection - July 2021 ML21039A8902021-02-0808 February 2021 NRR E-mail Capture - South Texas Project - Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing ML21029A3312021-01-29029 January 2021 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing ML20280A5452020-08-17017 August 2020 STP 2020 PIR Request for Information ML20111A0052020-04-17017 April 2020 NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME OM Code 2012 Edition - Relief Request PRR-01 ML20070N0222020-03-10010 March 2020 NRC Selection for Onsite Review ML20057G4612020-02-26026 February 2020 05000498/499 Request for Information - Occupational Radiation Safety Inspection ML20045E2172020-02-13013 February 2020 Licensed Operator Positive Fitness-For-Duty Test ML20036F5862020-02-0404 February 2020 Request for Additional Information - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L-2019-LLR-0096)Redacted ML19165A1032019-06-14014 June 2019 NRR E-mail Capture - Draft RAI for STP TS 3.8.1.1 Sbdg SR Change ML19081A1512019-03-21021 March 2019 NRR E-mail Capture - Draft Round 2 RAI - Sbdg Voltage and Frequency LAR (L-2018-LLA-0078) ML18283B9522018-10-10010 October 2018 NRR E-mail Capture - Final RAI - South Texas Standby DG TS Change (L-2018-LLA-0078) ML18263A1432018-09-12012 September 2018 NRR E-mail Capture - Final RAI for South Texas Project RR-ENG-E-16 (L-2018-LLR-0097) ML18197A4172018-07-17017 July 2018 Notification of NRC Triennial Heat Sink Performance Inspection (05000498/2018003 and 05000499/2018003) and Request for Information ML18003B4222018-01-0303 January 2018 NRR E-mail Capture - Final Request for Additional Information Amendment Request to Modify the Emergency Response Organization for South Texas Project ML17229B4672017-08-16016 August 2017 Notification of NRC Inspection 05000499/2017008 and Request for Information ML17132A0712017-05-15015 May 2017 Information Request the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000498/2017407; 05000499/2017407 ML17103A6272017-04-13013 April 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000498/2017007 and 05000499/2017007) and Request for Information ML16351A1502016-12-16016 December 2016 Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409) ML16302A4532016-12-12012 December 2016 Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409) ML16343A0422016-12-0808 December 2016 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application (CAC NOS. ME4936, ME4937) ML16340A1022016-12-0505 December 2016 Requests for Additional Information for the Review of the South Texas Project License Renewal Application (CAC Nos. ME4936 and ME4937) ML16246A0952016-09-15015 September 2016 Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16214A2912016-08-26026 August 2016 Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16187A0522016-07-0707 July 2016 Request for Additional Information Regarding License Renewal Application ML16141B0812016-05-31031 May 2016 Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information ML16125A2902016-05-26026 May 2016 Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) ML16127A4522016-05-12012 May 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16104A3522016-04-22022 April 2016 Requests for Additional Information Set 35 for the Review of the South Texas Project License Renewal Application (Tac Nos. ME4936, ME4937) ML16082A5072016-04-11011 April 2016 Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) ML16082A4842016-03-22022 March 2016 NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Risk Review for GSI-191 ML16081A0042016-03-18018 March 2016 NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Thermal-hydraulic Review for GSI-191 ML16053A1872016-03-0101 March 2016 Request for Additional Information, Request to Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years (CAC MF6176-MF6177) ML16060A2872016-02-29029 February 2016 NRR E-mail Capture - Request for Additional Information - STP LRA Safety Review 2024-01-24
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 26, 2016 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNIT 1 -
SUMMARY
OF JUNE 28-30, 2016, REGULATORY AUDIT AND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 5.3.2 TO ALLOW LONG-TERM OPERATION WITH 56 FULL-LENGTH CONTROL ROD ASSEMBLIES (CAC NO. MF7577)
Dear Mr. Powell:
By letter dated April 7, 2016, as supplemented by letter dated May 25, 2016, STP Nuclear Operating Company, the licensee for South Texas Project, Unit 1, submitted a license amendment request (LAR) to allow long-term operation of Unit 1 with 56 full-length control rod assemblies instead of the originally designed 57 control rods.
The U.S. Nuclear Regulatory Commission (NRC) staff determined that a regulatory audit, conducted in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits," would be useful to better understand the LAR and more efficiently make a regulatory decision. Accordingly, the NRC staff conducted a regulatory audit on June 28-30, 2016, at the Westinghouse Corporation offices in Rockville, Maryland. The audit included the examination of supporting calculations and bases documents to verify information and identify material to be docketed to support the basis for the NRC staff's regulatory decision on the LAR. to this letter describes the results of the NRC staffs audit. During the audit, the NRC staff identified key technical issues and e-mailed a draft request for additional information (RAI) to your staff on August 10, 2016. Enclosure 2 to this letter includes the final RAI. The RAI was discussed with Mr. Drew Richards of your staff on August 18, 2016, and a mutually agreed upon date for the RAI response was determined to be September 29, 2016.
G. T. Powell ti If you have any questions, please contact me by telephone at 301-415-1906 or by e-mail at lisa.regner@nrc.gov.
~1rt-- -
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Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-498
Enclosures:
- 1. Audit Summary
- 2. Request for Additional Information cc w/encls: Distribution via Listserv
SUMMARY
OF JUNE 28-30, 2016, REGULATORY AUDIT REVIEW OF LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ALLOW LONG-TERM OPERATION WITH 56 FULL-LENGTH CONTROL ROD ASSEMBLIES STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNIT 1 DOCKET NO. 50-498
1.0 BACKGROUND
By letter dated April 7, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16110A297), as supplemented by letter dated May 25, 2016 (ADAMS Accession No. ML16162A196), STP Nuclear Operating Company (STPNOC), the licensee for South Texas Project (STP), Unit 1, submitted a license amendment request (LAR) to revise the licensing bases to allow operation with 56 full-length control rod assemblies.
The Unit 1 reactor has been operating since December 2015 with 56 full-length control rod assemblies following U.S. Nuclear Regulatory Commission (NRC) approval of an emergency license amendment request dated December 3, 2015. 1 The April 6, 2016, submittal requests long-term operation in the 56-control-rod configuration instead of the originally-designed 57-control-rod configuration.
The NRC staff conducted a regulatory audit of the STPNOC LAR and supporting documentation on June 28-30, 2016, to gain a better understanding of the licensee's request. The audit was conducted at Westinghouse Corporation offices in Rockville, Maryland, to review the STPNOC reload design change process calculations, safety analyses calculations, and shutdown margin calculations which form the bases of the statements contained in the LAR.
The following NRC staff members participated in the audit:
- George Thomas - Technical Reviewer, Senior Reactor Systems Engineer
- Ian Tseng - Technical Reviewer, Mechanical Engineer 1 The NRC staff's safety evaluation dated December 11, 2015, is in ADAMS at Accession No. ML15343A128.
Enclosure 1
STPNOC was represented by the following personnel:
- Brian Guthrie - Westinghouse Corporation
- Danielle Schmitt- Westinghouse Corporation The audit facilitated an expedited review of the LAR and helped the NRC staff develop a clear understanding of the information provided by the licensee. The audit was conducted in accordance with the guidance in the NRR Office Instruction LIC-111 and consistent with the draft audit plan dated June 6, 2016 (ADAMS Accession No. ML16159A023).
During the audit, the NRC staff identified technical issues and generated a draft request for information (RAI), which was e-mailed to STPNOC staff on August 10, 2016 (ADAMS Accession No. ML16228A002). The finalized version of the RAI is included as Enclosure 2 to the letter transmitting this audit summary.
2.0 TECHNICAL ISSUES REVIEWED The basis of this audit was the LAR provided by STPNOC requesting operation of STP Unit 1 with 56 full-length control rod assemblies, and Appendix A, "General Design Criteria for Nuclear Power Plants," to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR).
During the audit, the STPNOC staff provided a history of the rod control cluster assembly (RCCA) malfunction during refueling outage 1RE17 in November 2012 and 1RE19 in November 2015. Westinghouse staff provided an overview of the "Westinghouse Methodology Impacts from the Removal of the RCCA from Core Location D-6," which is available in ADAMS at Accession No. ML16188A368. The STPNOC team provided a summary of the differences between the emergency LAR and the permanent LAR, including the removal of the thimble plug in accordance with the As Low As Reasonably Achievable (ALARA) program, the permanent instrumentation and control changes, and the additional analyses discussed below.
Additionally, the STPNOC staff discussed changes to the submittal which would be addressed in the response to the NRC's RAI. The changes include removal of the dropped bank during full power operations event in LAR Table 4, and the addition of missing legacy items to LAR Table 7.
The focus of the NRC staff's audit was to ensure that the licensee identified the inputs to the safety analysis that were impacted by the control rod removal, ensure that these impacts were adequately addressed, and to ensure that the methods used to analyze the control rod removal had the capability to model the core in this configuration.
As discussed in the Westinghouse presentation, the safety analysis codes use a point kinetics neutronics model without consideration of control rod pattern. Various parameters from the safety analyses of record are used as input into the core neutronics codes (i.e., ANC and PARAGON/NEXUS) which have the capability to model an asymmetric control rod pattern. The
output from the neutronics codes provide the key safety parameters identified in WCAP-9272, which are compared to the key safety parameters used as input to the safety analyses. If the results from the neutronics codes are found to not bound those used in the safety analyses, an evaluation or complete re-analysis is completed for that safety analysis.
The NRC staff identified additional information needed to complete its review regarding how the licensee determined the shutdown margin (SOM). Specifically, the licensee was requested to provide a discussion of how the SOM was calculated for Cycle 20 and the multi-cycle assessment. This concern was captured in question 1 of Enclosure 2.
The NRC staff also identified additional information needed in LAR Table 7. Specifically, the licensee was requested to provide additional details on the impacts to specific accident analyses for key safety parameters. This concern was captured in question 2 of Enclosure 2.
The NRC staff noted during the discussion that the licensee evaluates the total rod worth on a cycle-specific basis each operating cycle. The NRC and STPNOC staff discussed how the licensee evaluated the impact to total rod worth in relation to the permanent removal of control rod D-6, and the impact to the design basis analyses in the UFSAR. This concern was captured in question 3 of Enclosure 2.
The NRC staff requested additional information on why key safety parameters in LAR Table 5 were included in the STP LAR since they are not incorporated into the WCAP-9272-P-A methodology. These appear to be important, and the licensee stated they are calculated regardless of the WCAP-9272-P-A methodology. This concern is captured in question 4 of .
The NRC staff identified a concern with the use of the neutronics codes for the core configuration proposed by STPNOC (i.e., one control rod removed at location D-6). Specifically, the NRC staff requested verification that the neutronics codes had the capability to adequately model the N-2 configuration for a rod eject accident. The NRC staff also discussed its concern with a local return to power in a specific region of the core with the one rod removed and another stuck rod. This concern was captured in question 5 of Enclosure 2.
The NRC staff identified a concern with the main steam line hot zero power methodology. The postulated accident most susceptible to being impacted by the removal of the control rod is the main steam line break hot zero power accident. The NRC staff asked for clarification of the method used to analyze this accident and asked the licensee to demonstrate how WCAP-9272 was implemented to evaluate this accident on a cycle specific basis. The staff was specifically concerned about where in the process the removal of the control rod was captured and how that was evaluated. This concern was captured in question 6 of Enclosure 2.
3.0 DOCUMENTS REVIEWED
- Reload Safety Analysis Checklist (RSAC) Transmittals (Cycle 20)
- RSAC Violations (Cycle 20)
- Reload Safety Evaluation (RSES) for each safety analysis group
- SOM Analysis (Cycle 20 and Multi-Cycle Assessment)
- Design Initialization (DI) Meeting Minutes: NF-TF-15-36
- RSAC Preparation and Evaluation Guidance for Transient Analysis:
NONLOCA-SAS-17.0
- RSAC-HFP and HZP SLB Calculations for South Texas Unit 1 (TGX) Cycle 20:
CN-TG20-013
- Redesign - RSAC - HZP SBL, Trip Reactivity versus Power and Most Positive MDC for South Texas Unit 1 (TGX) Cycle 20: CN-TG20-053
- Thermal Hydraulic Design RSAC Confirmation for South Texas Unit 1 Cycle 20:
CN-TG20-025
- METCOM - Section 6.22 Steam Line Break Analysis, Revision 71, March 2014-Design Initialization (DI) Meeting Minutes: NF-TF-15-36
4.0 CONCLUSION
The NRC staff found that the audit helped the staff to better understand certain aspects of the licensee's submittal, and to clarify several NRC staff concerns and questions. There was open communication throughout the audit and it was conducted in accordance with the draft audit plan with no known deviations.
In Enclosure 2 to the letter transmitting this audit summary, there is the final RAI to the licensee resulting from the audit. The NRC staff may have additional questions once the detailed review of the LAR and supplements is complete.
Attachment:
Audit Report Questions
REQUEST FOR ADDITIONAL INFORMATION STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNIT 1 DOCKET NO. 50-498
- 1. In the license amendment request (LAR) dated April 7, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 1611 OA297), as supplemented by letter dated May 25, 2016 (ADAMS Accession No. ML16162A196), STP Nuclear Operating Company (STPNOC, the licensee) stated, in part, that the required reactor coolant system shutdown margin (SOM) boron concentrations for Operating MODES 3, 4, and 5 will be higher with control rod D-6 removed. Additionally, Table 8 of the LAR provides a summary of the SOM calculated at the end of cycle for the four representative cycles performed for the limiting hot zero power (HZP) main steam line break accident. It is unclear to the U.S. Nuclear Regulatory Commission (NRC) staff how the SOM was determined. The calculated SOM is evaluated for each core reload design to satisfy the General Design Criterion (GDC) 28, "Reactivity limits," of Appendix A to Title 1O of the Code of Federal Regulations (10 CFR) Part 50. The NRC staff requests that the licensee provide a discussion on how the SOM was calculated for Cycle 20 and the multi-cycle assessment.
- 2. Table 7 of the LAR discusses the impact of control rod D-6 on the key safety parameters related to Updated Final Safety Analysis Report (UFSAR) Chapter 15 safety analyses. The discussion only references to the bounding UFSAR Chapter 15 analyses with no further discussion of how the removal of the control impacts the inputs/assumptions of the analyses. The NRC staff requests that the licensee provide the following:
- a. For each Chapter 15 analysis:
- 1. Please discuss how consideration of control rod D-6 was previously incorporated into each accident analysis (e.g., control rod D-6 was part of the shutdown bank that was inserted into the core following reactor trip initiated by a turbine trip).
- 2. Please discuss how the removal of the control rod impacts the key safety parameters (e.g., since the shutdown banks are assumed to insert during this event, the overall trip reactivity is decreased with the removal of control rod D-6).
- 3. Please provide the basis for events that are not impacted by removal of control rod D-6.
- 4. If there is an impact on the key safety parameters, please provide an estimate of the magnitude of the change to the key safety parameter.
Enclosure 2
- b. For the control rod ejection accident, Table 7 identifies "various" as the sections of the reload methodology. Please specify these locations and identify the key safety parameters related to this accident (i.e., those impacted and not impacted by the control rod D-6 removal).
- c. The NRC staff identified several discrepancies between the key safety parameters impacted identified in Table 7 and the key safety parameters identified for each accident in the reload methodology. Please discuss why there are differences between the documents as identified below (note that for this request for additional information, Table 7 of the LAR is abbreviated as Table 7):
- 1. Feedwater System Malfunctions (reduction in feedwater temperature and increased feedwater flow): Table 7 identifies trip reactivity as impacted while the reload methodology does not identify trip reactivity as a key safety parameter.
- 2. Loss of External Load and Turbine Trip: Table 7 identifies trip reactivity as impacted while the reload methodology does not identify trip reactivity as a key safety parameter. The reload methodology identifies moderator density coefficient (MDC) as a key safety parameter while Table 7 does not identify MDC as impacted.
- 3. Feedwater System Pipe Break: Table 7 identifies trip reactivity as impacted while the reload methodology does not identify trip reactivity as a key safety parameter. The reload methodology identifies SOM as a key safety parameter while Table 7 does of the LAR does not identify SOM as impacted.
- 4. Partial Loss of Forced Reactor Coolant Flow, Complete Loss of Forced Reactor Coolant Flow, and Rod Cluster Control Assembly (RCCA)
Misoperation: The reload methodology identifies MDC as a key safety parameter while Table 7 does not identify MDC as impacted.
- 5. Startup of Inactive Reactor Coolant Loop at an Incorrect Temperature:
The reload methodology identifies MDC and SOM as a key safety parameter while Table 7 does not identify MDC and SOM as impacted.
- d. In the column in Table 7, several comments state that an analysis is bounded by another. Please discuss the basis for why these analyses are bounded by another and confirm that these bounding assumptions are unchanged with the removal of the control rod.
- 3. The licensee stated, in part, in Table 3 of the LAR that the total rod worth is evaluated on a cycle-specific basis to ensure that the SOM and trip reactivity limits are met. It is unclear to the NRC staff whether the licensee has evaluated the influence and impact of total rod worth on control rod D-6 in relation to the UFSAR Chapter 15 analyses. The calculated total rod
worth is evaluated for each core reload design to satisfy GDC 28, "Reactivity limits." The NRC staff requests that the licensee provide clarification of the removal of control rod D-6 on total rod worth and the parameters in relation to the UFSAR Chapter 15 analyses.
- 4. Table 5 of the LAR contains additional nuclear design key safety parameters that are not part of the reload methodology. Please clarify if these additional parameters in Table 5 have been analyzed in past reloads. Also, please clarity if these additional parameters in Table 5 have been incorporated into the reload guidance such that they will be analyzed in future reloads.
- 5. GDC 10, "Reactor design," of Appendix A to 10 CFR Part 50 states that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
Such margin is commonly demonstrated using computational models to simulate how the system would behave during normal operation and anticipated operational occurrences.
Because the results of these simulations are used to confirm that such margin exists, the simulations themselves and the computer models which are used to perform them must be trustworthy.
The Advanced Nodal Code (ANC) is used to perform analyses for these scenarios and will have a change in inputs due to the removal of the D-6 control rod. Please provide justification for the continued use of ANC with the removal of the D-6 control rod. This should include a demonstration that any change to the simulations considered (i.e., N-1 to N-2 rods out) are within the capabilities of ANC and the scope of the initial approval of ANC.
- 6. For the Hot Zero Power Main Steam Line Break (HZP MSLB), STPNOC uses multiple computer codes to simulate the scenario. Please provide further details on the methodology for performing the HZP MSLB analysis. Specifically, address how the analysis of record, generated by RETRAN, was used in conjunction with ANC and VIPRE to ensure that there was margin to DNB.
G. T. Powell If you have any questions, please contact me by telephone at 301-415-1906 or by e-mail at lisa.regner@nrc.gov.
Sincerely, IRA!
Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-498
Enclosures:
- 1. Audit Summary
- 2. Request for Additional Information cc w/encls: Distribution via Listserv DISTRIBUTION:
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