Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML110620203, ML11140A163, ML11224A265, ML11230A003, ML11318A121, ML11318A122, ML11318A123, ML11318A124, ML11318A125, ML11318A126, ML11318A127, ML11318A128, ML11318A129, ML11318A130, ML11318A131, ML11318A132, ML11318A133, ML11318A135, ML11318A136, ML11318A138, ML11318A139, ML11318A140, ML11318A141, ML11318A142, ML11318A143, ML11318A144, ML11318A145, ML11318A146, ML11318A147, ML11318A148, ML11318A149, ML11318A150, ML11318A151, ML11318A152, ML11318A153, ML11318A154, ML11318A155, ML11318A156, ML11318A157, ML11318A158, ML11318A159, ML11318A160, ML11318A161, ML11318A162, ML11318A163, ML11318A164, ML11318A165, ML11318A166, ML11318A167, ML11318A168... further results
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MONTHYEARML1106202032011-03-17017 March 2011 License Renewal Application Online Reference Portal Project stage: Other ML1108907642011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application-Electrical Branch Scoping Project stage: RAI ML1108205792011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application -Section 2.4 Structural (TAC Nos. ME4936, ME4937) Project stage: RAI ML1108309782011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application, Fire Protection and Component Integrity (TAC Nos. ME4536 ME4637 Project stage: RAI NOC-AE-11002670, Response to Request for Additional Information for License Renewal Application2011-05-0505 May 2011 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI NOC-AE-11002672, Response to Request for Additional Information for Licence Renewal Application2011-05-12012 May 2011 Response to Request for Additional Information for Licence Renewal Application Project stage: Response to RAI ML11137A0922011-05-24024 May 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application Future Consideration of Operating Experience Project stage: RAI ML11140A1632011-06-0606 June 2011 Plan for the Aging Management Program Regulatory Audit Regarding the South Texas Project, Units 1 and 2 License Renewal Application Review (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002681, Amendment 2 to the License Renewal Application2011-06-16016 June 2011 Amendment 2 to the License Renewal Application Project stage: Other NOC-AE-11002683, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-06-23023 June 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML11154A0132011-07-0606 July 2011 Summary of Telephone Conference Call Held on May 23, 2011, Between the NRC and STPNOC, Concerning Requests for Additional Information Pertaining to the South Texas Project, LRA-Future Consideration of Operating Experience Project stage: RAI ML11166A2392011-07-12012 July 2011 Letter Request for Additional Information for South Texas Project Electric Generating Station, Units 1 and 2 License Renewal Application - Scoping and Screening Balance of Plant (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11201A0552011-07-28028 July 2011 Requests for Additional Information for the Review of the South Texas Project, License Renewal Application - Scoping and Screening Audit (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002702, Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application2011-08-0909 August 2011 Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application Project stage: Response to RAI ML11214A0882011-08-15015 August 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Plant Systems (TAC ME4936 and ME4937) Project stage: RAI ML11214A0052011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Structures/Electrical (TAC ME4936 and ME4937) Project stage: RAI ML11214A0272011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Reactor Systems (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002716, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-18018 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML1123000162011-08-18018 August 2011 License Renewal - Errata in AMP RAI Package Project stage: RAI NOC-AE-11002714, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-23023 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML11230A0032011-09-0606 September 2011 Scoping and Screening Audit Report Regarding the South Texas Project, Units 1 and 2 (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002730, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002731, Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML1124402012011-09-21021 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 2 (TAC Nos. ME4936, ME4937) Project stage: RAI ML11250A0432011-09-22022 September 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 1 (TAC Nos. ME4936 and ME4937) Project stage: RAI 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) Project stage: Other ML11258A1612011-09-22022 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 3 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11272A1652011-10-0404 October 2011 Summary of Telephone Conference Call Held on September 28, 2011, Between the NRC and STP Nuclear Operating Company, Concerning Request for Additional Information Pertaining to the South Texas Project, LRA (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002732, Response to Requests for Additional Information for the License Renewal Application2011-10-10010 October 2011 Response to Requests for Additional Information for the License Renewal Application Project stage: Response to RAI ML11273A0172011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 5 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11273A0082011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 4 (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002737, Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937)2011-10-18018 October 2011 Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Supplement ML11277A0472011-10-18018 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Program, Set 6 Project stage: RAI ML11305A0762011-10-25025 October 2011 Response to Requests for Additional Information for License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002756, Contact Information Change, License Renewal Application (TAC ME4936 and ME4937)2011-10-26026 October 2011 Contact Information Change, License Renewal Application (TAC ME4936 and ME4937) Project stage: Other ML11318A1792011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1802011-11-0303 November 2011 Drawing No. LR-STP-WS-6R329F05048#1, Rev. 1, Piping and Instrumentation Diagram Solid Waste Processing System Project stage: Other ML11318A1762011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F05024#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1652011-11-0303 November 2011 Drawing No. LR-STP-PS9Z329Z00047#1, Rev. 1, Piping and Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1642011-11-0303 November 2011 Drawing No. LR-STP-PS-5Z329Z00045#2, Rev. 1, Piping & Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1782011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#1, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1682011-11-0303 November 2011 Drawing No. LR-STP-RC-5R149F05004#2, Rev. 1, Piping and Instrumentation Diagram Acs Pressurizer Relief Tank. Project stage: Other ML11318A1722011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05022#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System. Project stage: Other ML11318A1702011-11-0303 November 2011 Drawing No. LR-STP-RM-5R279F05033#2, Rev. 1, Piping & Instrumentation Reactor Makeup Water System. Project stage: Other ML11318A1602011-11-0303 November 2011 Drawing No. LR-STP-IA-8Q119F05050#2, Rev. 1, Piping & Instrumentation Diagram Mechanical Aux. Building Instrument Air. Project stage: Other NOC-AE-11002749, Drawing No. LR-STP-SB-7S209F200032, Rev. 0, Piping and Instrumentation Diagram Steam Generator Blowdown System2011-11-0303 November 2011 Drawing No. LR-STP-SB-7S209F20003#2, Rev. 0, Piping and Instrumentation Diagram Steam Generator Blowdown System Project stage: Other ML11318A1742011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05027#2, Rev. 1, Piping & Instrumentation Diagram Auxiliary Steam and Condensate Return System (Lwps) Project stage: Other ML11318A1462011-11-0303 November 2011 Drawing LR-STP-ED-5Q069F05030 #2, Rev. 17, Piping & Instrumentation Diagram Radioactive Vent & Drain System Sump Pumps. Project stage: Other ML11318A1552011-11-0303 November 2011 Drawing No. LR-STP-FP-7Q272F00046, Rev. 1, Piping and Instrumentation Diagram Fire Protection Loop. Project stage: Other ML11318A1482011-11-0303 November 2011 Drawing No. LR-STP-ED-5Q069F90011#2, Revision 1, Piping & Instrumentation Diagram Radioactive Vent and Drain System Fuel Handling Building Gravity Drains. Project stage: Other 2011-06-16
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Category:Audit Report
MONTHYEARML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML21236A3082021-09-10010 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 2024-02-07
[Table view] Category:Letter
MONTHYEARML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20243012024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 NOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24184C0832024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24183A1742024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump ML24179A3412024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24171A0112024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A3172024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 ML24092A1902024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) ML24017A2972024-02-15015 February 2024 Project Manager Assignment ML24039A1602024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24039A1112024-02-0808 February 2024 Operator Licensing Examination Schedule Revision 2 ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24029A2752024-01-29029 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 2024-09-11
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 2016 Mr. James Connolly Site Vice President STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
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 (TAC NOS. ME4936 AND ME4937)
Dear Mr. Connolly:
By letter, dated October 25, 2010, STP Nuclear Operating Company (or the applicant) submitted an application for renewal of operating licenses NPF-76 and NPF-80 for the South Texas Project (STP), Units 1 and 2. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) conducted an audit of aluminum bronze selective leaching aging management program in two parts: (1) during the week of March 21, 2016, onsite at STP in Bay City, Texas, and (2) on June 22, 2016, in the Westinghouse offices in Rockville, Maryland.
In addition, the staff conducted an in-office audit of PWR Reactor Internals Program Inspection Plan for Reactor Vessel Internals. The audit report is enclosed.
If you have any questions, please contact me by telephone at (301) 415-3306 or by e-mail at Lois.James@nrc.gov.
Sincerely,
/RA/
Lois M. James, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc: Listserv
ML16218A256 OFFICE LA:RPB1:DLR PM:RPB1:DLR BC:RARB:DLR BC:RASB:DLR NAME IBetts LJames DMorey BWittick DATE 8/11/16 8/24/16 8/24/16 8/24/16 OFFICE BC:RPB1:DLR PM:RPB1:DLR NAME YDiaz-Sanabria LJames DATE 8/30/16 8/30/16 Letter to J. Connolly from L. James dated August 30, 2016
SUBJECT:
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 (TAC NOS. ME4936 AND ME4937)
E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrPMSouthTexasProject Resource RidsOgcMailCenter LJames, DLR YDiaz-Sanabria, DLR TTran, DLR JDanna, DLR DMcIntyre, OPA LRegner, DORL NTaylor, RIV DProulx, RIV SJanicki, RIV SMoney, RIV ASanchez, RIV NHernandez, RIV WMaier, RIV VDricks, RIV GPick, RIV SGraves, RIV ajaldridge@STPEGS.COM, STP rjgonzales@STPEGS.COM, STP lsterling@STPEGS.COM, STP mpmurray@STPEGS.COM, STP jwconnolly@stpegs.com, STP
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION, DIVISION OF LICENSE RENEWAL Docket Nos: 50-498 and 50-499 License Nos: NPF-76 Licensee: STP Nuclear Operating Company Facility: South Texas Project, Units 1 and 2 Location: P.O. Box 289 Wadsworth, TX 77483 Dates: March 21-24, 2016 June 22, 2016 Reviewers: Margaret Audrain, Materials Engineer, Corrosion and Metallurgy Branch, Division of Engineering (DE), Office of Regulatory Research (RES)
(Formerly Mechanical & Civil Engineering Branch, DE, Office of Reactor Regulations (NRR))
William Holston, Senior Mechanical Engineer, Aging Management Reactor System Branch (RARB), Division of License Renewal (DLR), NRR Matthew Homiack, Materials Engineer, RES/DE/Component Integrity Branch Christopher Hovanec, Materials Engineer, Vessels & Internals Integrity Branch, DE, NRR (formerly of NRR/DLR/RARB)
Lois James, Senior Project Manager, Project Branch 1 (RBP1)
James Medoff, Senior Mechanical Engineer, Aging Management of Structural, Electrical & System Branch (RASB), DLR, NRR Approved By: Dennis Morey, Chief Aging Management Reactor System Branch Division of License Renewal Brian Wittick, Chief Aging Management of Structural, Electrical & System Branch Division of License Renewal Yoira Diaz-Sanabria, Chief Projects Branch 1 Division of License Renewal
INTRODUCTION The U.S. Nuclear Regulatory Commission (NRC or the staff) conducted an onsite audit at the South Texas Project (STP), Units 1 and 2, in Bay City, Texas, from March 21 to 24, 2016, an in-office audit from March 21 to 24, 2016, and an onsite audit in the Westinghouse Office in Rockville, Maryland, on June 22, 2016. The purpose of the audit was to examine STP Nuclear Operating Company (STPNOC) aging management programs (AMPs) and related documentation associated with the AMPs for Aluminum Bronze Selective Leaching and for Pressurized Water Reactor (PWR) Reactor Vessel Internals (RVI). Results of this audit will be ultimately documented in the staffs safety evaluation report (SER).
Regarding the Aluminum Bronze Selective Leaching AMP, the purpose of the audit was to gain an understanding of the applicants AMP for welds that are susceptible to aluminum bronze selective leaching such that the staff has confidence that Open Item 3.0.3.3.3-1 in the 2013 Safety Evaluation Report with Open Items (Agency Document and Access Management System (ADAMS) Accession No. ML13044A115) has a closure path. This audit focused on material information, material process information, microstructure information, and structural integrity evaluations regarding the welds that may be susceptible to selective leaching needed in order for the staff to complete its review.
Regarding the PWR RVI AMP, the purpose of the audit was to determine if the supporting plant documents for this AMP provide an acceptable basis for demonstrating that the design stresses for the RVI components at STP, Units 1 and 2, are within the bounding design stress assumptions for these components in ERPI MRP Technical Report (TR) No. 1022863, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A), dated January 2012, and EPRI MRP TR No. 1013234, "Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191)," dated November 2006.
In performing the audit, the staff examined the applicants license renewal application (LRA),
supplements to the LRA, program-bases documents, and related references, and interviewed various applicant representatives.
PLANT-SPECIFIC PROGRAM Selective Leaching of Aluminum Bronze Aging Management Program During this audit of the Selective Leaching of Aluminum Bronze Program, the staff interviewed the applicants on-site and contractor staff, and reviewed on-site documentation provided by the applicant. The table below lists the documents that were reviewed by the staff and found relevant to the audit. These documents were provided by the applicant.
Relevant Documents Reviewed Document Title Revision/Date 31511389 Review of Buried Pipe Stresses and Leak Rate Margins in 04/17/1995 ECW System (APTECH Report AES 93061964-1Q-1) 920742 Station Problem Report 1994 5-Y-57 0-Y-10001 Yard-Civil Essential Cooling Water Pipe Installation Details Revision 7
Relevant Documents Reviewed Document Title Revision/Date 5-Y-57 0-Y-10002 Yard-Civil Essential Cooling Water Pipe Installation Plan Revision 3 Section and Details AES-C-1630-1 Bounding Stress Analysis of Buried ECW Piping Revision 0, 05/26/1992 AES-C-1630-2 Calculation of Critical Bending Stress for Flawed Pipe Welds Revision 0, in the ECW System 07/06/1992 AES-C-5862-1 Significance of Circumferential Cracking in 30 [diameter] 07/25/2005 Al-Br [aluminum bronze] Pipe in ECW [essential cooling water]
AES-C-1964-7 Leak Rate Analysis for a Circumferential Crack in 10-Inch and 04/13/1995 30-Inch Underground ECW Piping CREE 12-29261-108 Condition Report Engineering Evaluation 05/25/2016 Letter from R. Cipolla to Review of Buried Pipe Stresses and Leak Rate Margins in 04/17/1995 S. Timmaraju ECW (APTECH Report AES 93061964-1Q-1)
Letter from J. Thompson South Texas Project Electric Generating Station Materials 04/06/1984 to B. McCullough Applications Department Report #540 Titled Welding of Aluminum Bronze Essential Cooling Water Piping System Letter from R. Keilbach Welding of Aluminum Bronze ECW Piping System 08/19/1992 to D. Denver MT-3521A Evaluation of Cracked Elbow-Nozzle Weld from South Texas 12/17/1991 Project Unit 1 Essential Cooling Water System MT-3521B Evaluation of Cracked Aluminum Bronze Pipe-to-Pipe Weld 01/08/1992 from South Texas Project Unit 2 Essential Cooling Water System MT3800 Evaluation of Cracked Aluminum Bronze Repair Weld from 05/06/1992 South Texas Project Unit 1 Essential Cooling Water System MT-5623 Evaluation of Cracked Pipe Weld Joint EW1302/FW0032 03/03/1995 from South Texas Project Unit 1 MT-4181 Evaluation of Dealloying in Boat Sample from 30-inch Weld 01/28/1993 Number EW1102-FW0032 MT-5487 Evaluation of Aluminum Bronze Pipe to Elbow Weld in ECW 04/24/1995 Line MT-5050 Metallurgical Evaluation of Two Failed Aluminum-Bronze Pipe 06/06/1994 Sections from ECW System at South Texas Project Unit 2 Office Memorandum Evaluation of a Leak in an Aluminum Bronze Pipe-to-Tee 11/13/1992 from S. L. Wilson to S. Weld from South Texas Project, Unit 1, EW 1202-AQ Timmaraju QW-483 ASME Welding Procedure Qualification Record (PQR) 06/26/1992 Houston Lighting and Power Company Procedure Qualification Record No. 093 PQR No. 093 Welding Procedure Qualification Sheet 02/24/1992 RC 9890 Stress Summary for Large Bore ECW Piping (2-1/2 and 05/20/1991 above)
STP-AMP-PSALBZ South Texas Project License Renewal Program Evaluation Revision 9 Report - Selective Leaching of Aluminum Bronze - B2.1.37 STP - PSALBZ WPS-120 Welding Procedure Specification No. 120 09/28/1982
Relevant Documents Reviewed Document Title Revision/Date WPS-158 Welding Procedure Specification No. 158 05/15/1985 WPS-2016 Welding Procedure Specification No. 2016 06/31/1981 The staff reviewed reports, calculations, procedures, condition reports, and other basis documents associated with dealloying of aluminum-bronze welds. These reports summarized the evaluations performed on welds that were found leaking while in-service. The staff made the following observations based on the content of the reports.
- 1. The staff noted that all the reported instances of dealloying occurred in welds with backing rings.
- 2. The staff noted that all the reported instances of dealloying occurred in welds that had preexisting fabrication defects.
- 3. The staff noted that the dealloying was generally observed to occur locally adjacent to the crack sides and locally in front of the crack tip.
- 4. The staff noted that for upset loads:
- The length of a crack necessary to generate a 10 gpm in 30-inch underground piping is 14.9 inches on the supply side and 21.2 on the discharge side.
- The length of a crack necessary to generate a 10 gpm in 10-inch underground piping is 11.8 inches on the supply side and 13.8 on the discharge side.
- 5. The staff reviewed the yard installation details for the ECW system and confirmed that the ECW piping is installed within a concrete saddle for most of its length. There are short portions (i.e., where lines cross over each other) that are not in a saddle.
- 6. The staff reviewed Station Problem Report (SPR) 920742 and noted that through-wall dealloying occurred in the vicinity of a vendor weld repair in a 30 by 14 extruded tee (not cast). The SPR stated that there are a total of 50 extruded tees, with 6 being installed below ground. The SPR and associated documents also state that:
- 17 tees have similar repairs.
- repair lengths ranged from 0 inch to 12.25 inch, i.e., from 0% to 38% of the circumference.
- The operability evaluation for the station problem report, dated April 2, 1993, states that, a thru-wall crack on the order of 25 [percent] of the circumference would be needed to cause failure.
The staff lacks sufficient information to conclude that the aging effects associated with the extruded tees subject to weld repairs during fabrication will be adequately managed because the operability evaluation states that a flaw size up to 25 percent of the circumference will meet structural integrity requirements; however, at least one repaired area encompassed 38 percent of the circumference. The staff will consider issuing a
request for additional information requesting: (a) a list of the extruded tees subject to weld repairs during fabrication including the size of each tee, the associated repair area, and the tees location in the plant (i.e., above ground or below ground); (b) a copy of the engineering documents that are used to determine whether the tees can perform the pressure boundary function; (c) a comparison of the characteristics of the extruded tee repair welds to that of pipe-to-pipe welds in the essential cooling water system (e.g., phase structure, aluminum content); and (d) how the aging effects associated with the aboveground and below ground extruded tees subject to weld repairs during fabrication will be managed during the period of extended operation.
- 7. The staff reviewed the applicants weld root pass cooling rate analysis and noted that it would be possible to perform its own confirmatory analysis of the cooling rate. The staff noted several details that might be useful in performing such an analysis. Specifically, from the welding qualification data, the amperage ranged from 167 to 200 amps, with a mode of 180 amps; the voltage ranged from 11-12 volts, with a mode of 11 volts; and the travel speed ranged from 2.875 to 8.5 inches per minute, with a mode of 4.875 inches per minute.
The staff also noted details about the piping geometry and weld configuration. Specifically, the thickness of the nominal 30-inch pipe is 0.25 inches with an outside diameter of 30 inches, and the thickness of the nominal 10-inch pipe is 0.365 inches with a 10.75-inch outside diameter. A typical backing ring is approximately 2 inches wide and made from the piping base metal. In addition, a typical repair weld with two root passes would have a total of nine weld beads in three layers.
- 8. The staff noted that the dealloying observed in report MT-5050, dated June 6, 1994, was not limited to the volume immediately in front of the crack tip. The component in report MT-5050 is a pipe-to-tee weld with a backing ring that had a preexisting crack. The preexisting crack appeared to propagate some distance before becoming inactive; however, the dealloying continued throughwall past the crack tip resulting in a leak. Report MT-5050 was reevaluated by the applicant and the results are documented in Report CREE 12-29261-108, dated May 25, 2016. The staffs review of CREE 12-29261-108 confirmed that the (a) crack is in the weld metal and a result of a fabrication flaw; (b) general dealloying occurred beyond the crack and absent of crack growth; (c) general dealloying was completely contained in the weld metal. Therefore, there is OE showing that general dealloying can occur, once the root pass is breached, without the assistance of crack growth.
LRA AMP B2.1.35, PWR Reactor Internals Program During the week of March 21 to 24, 2016, the staff performed a supplemental audit of the LRA for STP, Units 1 and 2. As part of this audit, the staff audited the applicants basis for demonstrating conformance with the design assumptions stated in Section 2.4 of the MRP-227-A report and for resolving the question on cold-worked materials in EPRI Letter No. 2013-025. Bases for resolving the fuel design or fuel management related matters in EPRI Letter 2013-025 are documented in SER Section 3.0.3.3.2.
Audit Activities.
During its audit, the staff interviewed the applicants staff and reviewed onsite documentation provided by the applicant. The table below lists the documents which were reviewed by the staff and were found relevant to the audit of the applicants Applicant/Licensee Action Items (A/LAIs)
No. 1 basis. These documents were provided by the applicant, issued by the NRC, or docketed by the EPRI MRP.
Relevant Documents Reviewed Document Title Revision / Date EPRI TR No. 1022863 Materials Reliability Program: Pressurized Water Reactor January 2012 Internals Inspection and Evaluation Guidelines (MRP-227-A)
(See Footnote 1 for ADAMS ML #s)
NRC Safety Evaluation Final Safety Evaluation of Electric Power Research Institute Revision 1, (EPRI) . . . Materials Reliability Program (MPR) Report December 16, 2011 1016596 (MRP-227-A), Revision 0, Pressurized Water Reactor (PWR) Internals Inspection and Evaluation (ML11308A770)
Guidelines.
Chapter XI.M16A in PWR Vessel Internals June 3, 2013 NUREG-1801, Revision 2, as documented and (ML12270A436) amended in NRC LR-ISG-2011-04 PWROG-15027 South Texas Units 1&2 Summary Report from the Cold Work Assessment report.
EPRI MRP Letter MRP-227-A Applicability Template Guideline Oct. 14, 2013 No. 2013-025 (ML13322A454)
STP RVI Design - Conformance with the Design Assumptions in MRP-277-A.
The staff found that the scope of program element for the AMP provides an acceptable basis for demonstrating that the MRP-227-A report is bounding for the RVI design at STP Units 1 and
- 2. Specifically, in relation to resolving A/LAI No. 1 for MRP-227-A, the staff noted that the applicants scope of program element basis identifies that:
- 1) the STP reactor units have operated for less than thirty years with high leakage fuel loading patterns
- 2) the STP reactor units operate at fixed load and do not normally vary power based on calendar or load demand schedules
- 3) the applicant has not implemented any design changes at STP Units 1 or 2 not recommended by applicable industry vendors or organizations.
The staff verified that the scope of program element provides sufficient demonstration that: (a) the reactor units have operated for more than 30 years of operations using a low leakage fuel management strategy, (b) the reactor operates using base-load operations, and (c) the applicant has not implemented any design modifications outside of those recommended by Westinghouse Electric Company, the EPRI MRP, or other applicable industry organizations.
Therefore, the staff concludes that the applicant has provided sufficient demonstration that the designs of the RVI components at Units 1 and 2 are in conformance with the design criteria and assumptions stated in Section 2.4 of the MRP-227-A report. A/LAI No. 1 is resolved with respect to demonstrating conformance with these design assumptions.
STP RVI Design - Stress Load and Cold-Work Levels Assumed in the RVI Design The staff found that the supporting plant documents for this AMP provide an acceptable basis for demonstrating that the design stresses for the RVI components at STP Units 1 and 2 are within the bounding design stress assumptions for these components in the MRP-227-A and MRP-191 reports. Specifically, the staff verified that the applicants documents provide sufficient demonstration that the RVI components were not sufficiently cold-worked during component or plant fabrication practices, or else that the additional residual stress loads on the loading of the components was appropriately accounted for in the EPRI MRP design assumptions for the components in the MRP-191 report. Specifically, based on the review of the applicable plant records, the staff noted that the design documents provide sufficient demonstration that the applicant had restricted the procured yield strengths of the component materials to acceptable levels, such that any amounts of strain hardening imparted to the components during the fabrication process would be minimized. Based on this, review, the staff concludes that the applicant has provided sufficient demonstration that the levels of cold work and stress loads for the RVI components are within the design assumptions for these parameters in either the MRP-227-A or MRP-191 reports. Bases for resolving fluence related assessment criteria (i.e., average core power density, heat generation, figure of merit, and active fuel-to-upper core plate distances values) will be evaluated in the SER for STP, Units 1 and 2. A/LAI No. 1 is resolved with respect to demonstrating conformance with design assumptions.