Letter Sequence Response to RAI |
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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 ML11318A1472011-11-0303 November 2011 Drawing No. LR-STP-ED-5Q069F90011#1, Revision 1, Piping & Instrumentation Diagram Radioactive Vent and Drain System Fuel Handling Building Gravity Drains. 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: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
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Nuclear Operating Company South Texas Project Electric Generating Station P.O Box 289 Wadsworth.
Texas 77483 -May 14, 2012 NOC-AE-12002855 10 CFR 54 STI: 33547424 File: G25 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Response to Requests for Additional Information (RAI) 3.2.2.1-1a for the South Texas Project License Renewal Application (TAC Nos. ME4936 and ME4937)
References:
- 1. STPNOC letter dated October 25, 2010, from G. T. Powell to NRC Document Control Desk, "License Renewal Application" (NOC-AE-10002607)(ML1 03010257)2. NRC letter dated May 14, 2012, "Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application-Aging Management, Set 18 (TAC Nos. ME4936 and ME4937)" (ML1 2124A094)By Reference 1, STP Nuclear Operating Company (STPNOC) submitted a License Renewal Application (LRA) for South Texas Project (STP) Units 1 and 2. By Reference 2, STPNOC received RAI 3.2.2.1-1a.
The response is provided in Enclosure 1 to this letter.One new regulatory commitment is added to Table A4-1 of the LRA and is provided in Enclosure 2 to this letter. There are no other regulatory commitments in this letter.Should you have any questions regarding this letter, please contact either Arden Aldridge, STP License Renewal Project Lead, at (361) 972-8243 or Ken Taplett, STP License Renewal Project regulatory point-of-contact, at (361) 972-8416.I declare under penalty of perjury that the foregoing is true and correct.Executed on Date W. Renr rel Chief Nuclear Officer KJT
Enclosures:
- 1. STPNOC Response to RAI 3.2.2.1-1a
- 2. New Regulatory Commitment A~7 NOC-AE-12002855 Page 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, Texas 76011-4511 Balwant K. Singal Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 8B1)11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 John W. Daily License Renewal Project Manager (Safety)U.S. Nuclear Regulatory Commission One White Flint North (MS 011-Fl)Washington, DC 20555-0001 Tam Tran License Renewal Project Manager (Environmental)
U. S. Nuclear Regulatory Commission One White Flint North (MS O11F01)Washington, DC 20555-0001 A. H. Gutterman, Esquire Kathryn M. Sutton, Esquire Morgan, Lewis & Bockius, LLP John Ragan Chris O'Hara Jim von Suskil NRG South Texas LP Kevin Polio Richard Pena City Public Service Peter Nemeth Crain Caton & James, P.C.C. Mele City of Austin Richard A. Ratliff Alice Rogers Texas Department of State Health Services Balwant K. Singal John W. Daily Tam Tran U. S. Nuclear Regulatory Commission NOC-AE-12002855 Enclosure 1 Enclosure I STPNOC Response to RAI 3.2.2.1-1a Enclosure 1 NOC-AE-1 2002855 Page 1 of 5 SOUTH TEXAS PROJECT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION AGING MANAGEMENT, SET 18 (TAC NOS. ME4936 AND ME4937)Instances of Recurrent Reactor Coolant Leakage (019)NRC RAI 3.2.2.1-1a
Background:
By letter dated September 22, 2011, the staff issued RAI 3.2.2.1-1 requesting that the applicant state why the stainless steel closure bolting exposed to borated water leakage in LRA Table 3.2.2-4, Safety Injection System, was not managed for cracking.
In its response dated November 21, 2011, the applicant stated that the bolting was in an ambient temperature less than 140°F; therefore, stress corrosion cracking is not an applicable aging effect.NRC Inspection Report No. 05000449/2011005 dated February 13, 2012 describes safety injection (SI) system hot leg check valve 1N122XSI001OA, on which a seal cap enclosure had been installed in 1997 due to reactor coolant leakage from the body to bonnet gasket. The enclosure surrounds the valve bolting, preventing direct inspection.
The NRC inspection report also cites multiple occasions of leakage from the seal cap enclosure from 1997 to 2011, indicating that the leak from the bolted connection inside the enclosure was ongoing.Another instance of borated water leakage is described in the "operating experience" program element of LRA Section B2.1.4, "Boric Acid Corrosion," which states that recurring coolant leakage in reactor coolant pump 2C resulted in the replacement of seal housing bolts in 2004 and 2009. The LRA also states that disassembly of this pump was scheduled for Refueling Outage 2RE15 in October 2011 to perform flatness checks of the seal.Issue: 1. Given the multiple instances of reactor coolant leakage from the seal cap enclosure of SI system hot leg check valve 1N122XSIOO1OA, the stainless steel bolting within the enclosure may be submerged in a reactor coolant environment with a temperature greater than 140 0 F. The staff noted that the environment within the enclosure may not be sufficiently controlled for oxygen and other contaminants to preclude stress corrosion cracking.
The LRA does not contain an AMR item to address the submerged environment and the potential for stress corrosion cracking.
It is unclear to the staff how bolting within this and other seal cap enclosures will be age managed, since direct inspection is not possible.2. Regarding the recurring borated water leakage from reactor coolant pump 2C, the staff does not have sufficient information to determine if the Boric Acid Corrosion program is effective at preventing recurring leakages.
Enclosure 1 NOC-AE-12002855 Page 2 of 5 Request: 1. For all instances where pressure-retaining bolting is surrounded by seal cap enclosures:
- a. Describe the bolting alloy and the leaking water environment (i.e., reactor coolant, secondary water).b. Add aging management review (AMR) items for the aging management of the bolting for loss of material, loss of preload, and cracking due to stress corrosion cracking, as appropriate, in the submerged environment.
Provide technical justification for any cases where cracking due to stress corrosion cracking is not included as an applicable aging effect.c. If the aging management approach in item (b) does not include direct inspection of the bolting, provide technical justification for how the aging effects will be effectively managed during the period of extended operation.
- 2. Describe the results and any identified corrective actions from the reactor coolant pump 2C seal flatness checks to demonstrate the effectiveness of the Boric Acid Corrosion program.STPNOC Response: la. The bolting alloy for SI system hot leg check valve 1N122XSI001OA and the other instances where pressure-retaining bolting is surrounded by seal cap enclosures is A-286 (SA-453 Gr. 660). The leaking water environment is reactor coolant. The material is an iron-based and precipitation hardened high strength material.
This material has a high chrome and nickel content and is specifically designed to be resistant to boric acid corrosion.
The systems where seal cap enclosures currently exist are the Safety Injection System and the Chemical and Volume Control System. Seal cap enclosures are currently installed on Safety Injection System Check Valve SI0010A in Unit 2 and on Chemical Volume Control System Check Valves CV0001, CV0002, CV0004, and CV0005 in both Unit 1 and Unit 2.The LRA Aging Management Review (AMR) tables that show the material and environments for the affected systems and components are provided below.
Enclosure 1 NOC-AE-1 2002855 Page 3 of 5 Table 3.2.2-4 Engineered Safety Features -Summary of Aging Management Evaluation
-Safety Injection System Component Intended Material Environment Aging Effect Aging NUREG- Table I Notes Type Function Requiring Management 1801 Item Management Program Vol. 2 Item Closure LBS, PB, Carbon Borated Water Loss of material Boric Acid V.E-2 3.2.1.45 A Bolting SIA Steel Leakage (Ext) Corrosion (B2.1.4)Closure LBS, PB, Carbon Plant Indoor Loss of material Bolting Integrity V.E-4 3.2.1.23 B Bolting SIA Steel Air (Ext) (B2.1.7)Closure LBS, PB, Carbon Plant Indoor Loss of preload Bolting Integrity V.E-5 3.2.1.24 B Bolting SIA Steel Air (Ext) (B2.1.7)Valve PB Stainless Reactor Cracking ASME Section Xl IV.C2-5 3.1.1.68 A Steel Coolant (Int) Inservice Inspection, Subsections IWB, IWC, and IWD for Class 1 components (B2.1.1) and Water Chemistry (B2.1.2)Valve PB Stainless Reactor Loss of material Water Chemistry IV.C2-15 3.1.1.83 E, 1 Steel Coolant (Int) (B2.1.2) and One-Time Inspection (B2.1.16)
Enclosure 1 NOC-AE-12002855 Page 4 of 5 Table 3.3.2-19 Auxiliary Systems -Summary of Aging Management Evaluation
-Chemical and Volume Control System Component Intended Material Environment Aging Effect Aging NUREG- Table I Notes Type Function Requiring Management 1801 Vol. Item Management Program 2 Item Closure LBS, SIA Carbon Borated Water Loss of material Boric Acid VII.I-2 3.3.1.89 A Bolting Steel Leakage (Ext) Corrosion (B2.1.4)Closure LBS, SIA Carbon Plant Indoor Air Loss of material Bolting Integrity VII.l-4 3.3.1.43 B Bolting Steel (Ext) (B2.1.7)Closure LBS, SIA Carbon Plant Indoor Air Loss of preload Bolting Integrity VII.I-5 3.3.1.45 B Bolting Steel (Ext) (B2.1.7)Valve PB Stainless Reactor Cracking ASME Section XI IV.C2-5 3.1.1.68 A Steel Coolant (Int) Inservice Inspection, Subsections IWB, IWC, and IWD for Class 1 components (B2.1.1) and Water Chemistry (B2.1.2)Valve PB Stainless Reactor Loss of material Water Chemistry IV.C2-15 3.1.1.83 E, 2 Steel Coolant (Int) (B2.1.2) and One-Time Inspection (B2.1.16)Valve LBS, PB, Stainless Treated Loss of material Water Chemistry VII.El-17 3.3.1.91 E, 2 SIA Steel Borated Water (B2.1.2) and One-(Int) Time Inspection S(B2.1.16)
Valve LBS, PB, Stainless Treated Cracking Water Chemistry VII.E1-20 3.3.1.90 E, 2 SIA Steel Borated Water (B2.1.2) and One-(Int) Time Inspection 1 (B2.1.16)1 b. South Texas Project will permanently remove the seal cap enclosures from the affected components at the next available opportunity.
After the seal cap enclosures are removed, the component bolting will be replaced or inspected for intergranular stress corrosion cracking.
New LRA Table A4-1 Commitment 43 is provided in Enclosure
- 2. Therefore, the aging effects and environment for the affected components will be consistent with the AMR table description in the LRA. No changes to the AMR tables are required.Enclosure 2 provides the line-in of new Commitment 43.lc. The submerged environment associated with the affected components will no longer exist after the seal cap enclosures are permanently removed. The aging effects of the closure bolting of these components will be effectively managed during the period of extended operation by the Boric Acid Corrosion and Bolting Integrity Aging Management Programs.
Enclosure 1 NOC-AE-12002855 Page 5 of 5 2. Seal housing leakage for reactor coolant pump 2C was initially identified by the Boric Acid Walkdown Program in 2004. The joint was disassembled and the gasket was replaced which stopped the leakage. The seal housing leakage for reactor coolant pump 2C was again identified through the Boric Acid Walkdown Program during the Fall 2008 refueling outage (2RE13). A monitoring plan for the reactor coolant pump 2C seal housing leakage was established and permanent repairs were scheduled for the Fall 2011 refueling outage (2RE15). Following a Unit 2 trip in November 2010, the Boric Acid Walkdown Program inspected the seal housing leakage for reactor coolant pump 2C and identified increased leakage. Following plant pressurization to normal operating temperature and pressure, the leak exceeded predetermined leakage criteria.
The plant was depressurized to facilitate corrective action implementation.
The corrective actions were replacement of the reactor coolant pump seal housing and gasket.The apparent cause of the reactor coolant pump 2C seal housing leakage is deformation and distortion of the #1 seal housing caused by pressure cycles and successive retightening of the joint. The deformation and distortion interfered with the fit between the seal housing and the thermal barrier, and between the seal housing and the #1 insert support. Progression of deformation and distortion over time eventually contributed to a leak path between the seal housing and the thermal barrier.As outlined above, the Boric Acid Walkdown Program effectively identified, evaluated and tracked this joint leakage from initial identification to subsequent correction.
The Boric Acid Walkdown Program has not identified any leakage at the seal housing joint of the other seven Reactor Coolant Pumps.
Enclosure 2 NOC-AE-12002855 Enclosure 2 New Regulatory Commitment Enclosure 2 NOC-AE-12002855 Page 1 of 1 A4 LICENSE RENEWAL COMMITMENTS Table A4-1 identifies proposed actions committed to by STPNOC for STP Units 1 and 2 in its License Renewal Application.
These and other actions are proposed regulatory commitments.
This list will be revised, as necessary, in subsequent amendments to reflect changes resulting from NRC questions and STPNOC responses.
STPNOC will utilize the STP commitment tracking system to track regulatory commitments.
The Condition Report (CR) number in the Implementation Schedule column of the table is for STPNOC tracking purposes and is not part of the amended LRA.Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 43 The seal cap enclosures from Unit 2 Safety Iniection System Check Valve SI001OA and from B2.1.7 2012 Refueling Unit 1 and Unit 2 Chemical Volume Control System Check Valves CV0001, CV0002, CV0004, Outage (Unit 1)0 2013 and CV0005 will be permanently removed. After removal of the seal cap enclosures, the Refueling Outage component bolting will be replaced or inspected for intergranular stress corrosion cracking. (Unit 2)CR 12-21155