Letter Sequence Other |
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TAC:MD1414, (Open) TAC:MD1415, (Open) TAC:MD1416, (Open) TAC:MD1417, (Open) TAC:MD1418, (Open) TAC:MD1419, (Open) TAC:MD1420, (Open) TAC:MD1421, (Open) TAC:MD1422, (Open) TAC:MD1423, (Open) |
Results
Other: ML070810264, NOC-AE-06002076, Examination Results of a Pressurizer Nozzle Safe-End Weld Overlay (RR-ENG-2-43), NOC-AE-06002085, Summary Assessment of Pressurizer Surge Line Weld Overlay; Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) (TAC Nos. MD1414-1423), NOC-AE-07002161, Weld Overlay Examination Results (RR-ENG-2-43), NOC-AE-07002168, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43), NOC-AE-08002297, Unit 1 Weld Overlay Examination Results (RR-ENG-2-43) (TAC MD1414-1423), NOC-AE-08002323, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)
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MONTHYEARNOC-AE-06002000, Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43)2006-05-0101 May 2006 Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43) Project stage: Request NOC-AE-06002055, Response to NRC Request for Additional Information on Proposed Alternative to ASME Section XI Requirements for Application of Weld Overlay (RR-ENG-2-43)2006-08-22022 August 2006 Response to NRC Request for Additional Information on Proposed Alternative to ASME Section XI Requirements for Application of Weld Overlay (RR-ENG-2-43) Project stage: Response to RAI NOC-AE-06002066, Commitment in Support of Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43)2006-09-19019 September 2006 Commitment in Support of Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43) Project stage: Request NOC-AE-06002068, Response to Request for Additional Information: Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43)2006-09-28028 September 2006 Response to Request for Additional Information: Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43) Project stage: Response to RAI NOC-AE-06002076, Examination Results of a Pressurizer Nozzle Safe-End Weld Overlay (RR-ENG-2-43)2006-11-0101 November 2006 Examination Results of a Pressurizer Nozzle Safe-End Weld Overlay (RR-ENG-2-43) Project stage: Other NOC-AE-06002085, Summary Assessment of Pressurizer Surge Line Weld Overlay; Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) (TAC Nos. MD1414-1423)2006-11-29029 November 2006 Summary Assessment of Pressurizer Surge Line Weld Overlay; Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) (TAC Nos. MD1414-1423) Project stage: Other ML0708102642007-04-0202 April 2007 Relief, Request for Relief No. RR-ENG-2-43 for Remainder of Second 10-year Inservice Inspection Interval Application of Weld Overlays in Pressurizer Nozzle Safe End Welds (TAC Nos. MD1414 - MD1423) Project stage: Other NOC-AE-07002161, Weld Overlay Examination Results (RR-ENG-2-43)2007-05-0101 May 2007 Weld Overlay Examination Results (RR-ENG-2-43) Project stage: Other NOC-AE-07002168, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)2007-05-29029 May 2007 Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) Project stage: Other NOC-AE-08002297, Unit 1 Weld Overlay Examination Results (RR-ENG-2-43) (TAC MD1414-1423)2008-04-29029 April 2008 Unit 1 Weld Overlay Examination Results (RR-ENG-2-43) (TAC MD1414-1423) Project stage: Other NOC-AE-08002323, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)2008-06-18018 June 2008 Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) Project stage: Other 2006-09-28
[Table View] |
Summary Assessment of Pressurizer Surge Line Weld Overlay; Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) (TAC Nos. MD1414-1423)ML063450122 |
Person / Time |
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Site: |
South Texas ![STP Nuclear Operating Company icon.png](/w/images/9/9c/STP_Nuclear_Operating_Company_icon.png) |
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Issue date: |
11/29/2006 |
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From: |
Berg M South Texas |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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NOC-AE-06002085, RR-ENG-2-43, STI NO: 32092752, TAC MD1414, TAC MD1415, TAC MD1416, TAC MD1417, TAC MD1418, TAC MD1419, TAC MD1420, TAC MD1421, TAC MD1422, TAC MD1423 |
Download: ML063450122 (3) |
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Category:Letter type:NOC
MONTHYEARNOC-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. 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2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. 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[Table view] |
Text
Nuclear Operating Company South Texas Pro/ed Eledric GenemalngStation P0. Box 289 Wadsworth Tws 77483 -
November 29, 2006 NOC-AE-06002085 File No.: G25 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Unit 1 Docket No. STN 50-498 Summary Assessment of Pressurizer Surge Line Weld Overlay:
Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) (TAC Nos. MD1414-1423)
Reference:
Letter dated September 28, 2006, from David W. Rencurrel, STPNOC, to NRC Document Control Desk, "Response to Request for Additional Information on Proposed Alternative to ASME Section Xl Requirements for Application of a Weld Overlay (RR-ENG-2-43) (TAC Nos. MD1414-1423)," (NOC-AE-06002068)
Pursuant to 10 CFR 50.55a(a)(3)(i), the STP Nuclear Operating Company (STPNOC) requested approval to use an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the structural weld overlays on the South Texas Project Unit 1 and Unit 2 pressurizer spray, relief, safety, and surge nozzle safe-ends. Verbal approval to perform structural weld overlays in Unit 1 was given in subsequent discussions with the NRC. The scope of the overlays to be performed in the October 2006 Unit 1 refueling outage (1 RE1 3) was subsequently limited to only the pressurizer surge line. This supplement to the request fulfills commitments made in Reference 1.
STPNOC completed a stress analysis of the surge line pre-emptive weld overlay prior to restart of Unit 1. Summaries of the results are provided in the attachment. The stress analysis results support the conclusion that structural weld overlays are a suitable pre-emptive measure for anticipated flaw development. Unit 2 is expected to have similar results when weld overlays are installed in the upcoming refueling outage (2RE1 1) in March 2007.
There are no commitments in this submittal.
If there are any questions, please contact either Mr. Philip L. Walker at (361) 972-8392 or me at (361) 972-7030.
M. J. Berg Manager, Testing/Programs PLW
Attachment:
Summary Assessment of Pressurizer Surge Line Weld Overlay: Shrinkage and Fatigue Crack Growth STI NO: 32092752 mO'
NOC-AE-06002085 Page 2 of 2 cc:
(paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Richard A. Ratliff Steve Winn Bureau of Radiation Control Christine Jacobs Texas Department of State Health Services Eddy Daniels 1100 West 49th Street NRG South Texas LP Austin, TX 78756-3189 C. Kirksey City of Austin Senior Resident Inspector J. J. Nesrsta U. S. Nuclear Regulatory Commission R. K. Temple P. O. Box 289, Mail Code: MN116 E. Alarcon Wadsworth, TX 77483 City Public Service C. M. Canady Jon C. Wood City of Austin Cox Smith Matthews Electric Utility Department 721 Barton Springs Road Austin, TX 78704
9 1 Attachment NOC-AE-06002085 Page 1 of 1 South Texas Project Unit 1 Summary Assessment of Pressurizer Surge Line Weld Overlay:
Shrinkage and Fatigue Crack Growth Shrinkage Assessment:
Calculated Limits on design stress due to shrinkage were determined prior to completing the weld overlay.
The calculation was performed using WESTDYN 7.1, a program acceptable for use in piping analysis, with an assumed pipe temperature of 700F. A displacement of 0.25-inch was applied to the pressurizer safe end as cold spring loading. This displacement is assumed as the main loading input to represent shrinkage due to the nozzle weld overlay.
The highest bending stress due to shrinkage as determined by computer calculations is 1620 psi. The code allowable stress for piping at 70°F is 40,000 psi (2Sm). Therefore, piping where shrinkage does not exceed 0.25-inch will qualify under code stress requirements.
Actual Actual measured shrinkage on the surge line nozzle following the overlay was measured at 0.080-inch or less at 90* increments around the circumference of the overlay. Because the piping is designed for significantly greater shrinkage and still satisfies code design requirements, the actual shrinkage experienced results in even greater design margin.
Consequently, there is no need to update the shrinkage calculation to reflect the actual values.
The design pressure and normal operating pressure are 2,485 psig and 2,235 psig, respectively. With the additional stress provided by the structural weld overlay, the total stresses remain significantly below the code allowable stresses.
Fatigue crack growth assessment:
WCAP-16611-P, "South Texas Units 1 and 2 Pressurizer Safety/Relief, Spray, and Surge Nozzles Structural Weld Overlay Qualification," August 2006, addresses the issue of fatigue crack growth. Chapter 8 is specifically applicable to the pressurizer surge line nozzle. Figure 8-10 depicts the expected service life relative to the ratio of initial flaw depth to the original wall thickness. If an assumed flaw in the piping extends through 75% of the pipe thickness, Figure 8-10 indicates that more than 23 years can be expected to pass before the flaw grows through the base metal. Consequently, such a flaw would not grow through-wall before the next inservice inspection. There is additional assurance in that post-weld overlay inspection did not identify any flaws in the inspectable volume of the base metal for the pressurizer surge line weld overlay.