|
---|
Category:Letter type:NOC
MONTHYEARNOC-AE-240040, Inservice Inspection Summary Report - 2RE232024-09-0404 September 2024 Inservice Inspection Summary Report - 2RE23 NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 NOC-AE-240040, Annual Dose Report for 20232024-04-29029 April 2024 Annual Dose Report for 2023 NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update NOC-AE-240040, Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation2024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation 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 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) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 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-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-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update 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 2024-09-04
[Table view] |
Text
Nuclear Operating Company South Ek-crk enemtbnSSbiZon PO 2ox229 vrU, Matb 774831AAa otxAsPr*d May 19, 2005 NOC-AE-05001886 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units I and 2 Docket Nos. STN 50-498, STN 50-499 Additional Information Regarding Welded Attachments on Piping Systems from which Arbitrary Intermediate Breaks were Previously Eliminated (TAC Nos. MC5191 and MC5192)
Reference:
Letter, S. E. Thomas to NRC, "Addition of Welded Attachments to Piping Systems from which Arbitrary Intermediate Breaks were Previously Eliminated,"
dated November 18, 2004 (NOC-AE-04001823)
The referenced letter reported two locations in each unit where welded attachments were added to piping systems from which arbitrary intermediate breaks were previously eliminated. The NRC review of the referenced letter resulted in an informal request for additional information.
The attachment to this letter provides the response to that request.
There are no commitments in this letter.
If there are any questions regarding this submittal, please contact John Conly at (361) 972-7336 or me at (361) 972-7136.
Scott M. Hea Manager, Licensing jtc
Attachment:
Response to Request for Additional Information STI: 31882289
NOC-AE-05001 886 Page 2 of 2 cc:
(paper copy) (electronic copy)
Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 David H. Jaffe Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission C. M. Canady Jack A. Fusco City of Austin Michael A. Reed Electric Utility Department Texas Genco, LP 721 Barton Springs Road Austin, TX 78704 Jon C. Wood Cox Smith Matthews Richard A. Ratliff C. Kirksey Bureau of Radiation Control City of Austin Texas Department of State Health Services 1100 West 49th Street J. J. Nesrsta Austin, TX 78756-3189 R. K. Temple E. Alarcon City Public Service Jeffrey Cruz U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483
NOC-AE-05001886 Attachment Page I of 4 Response to Request for Additional Information
- 1. In your request letter (Reference 1), you indicated that the enveloping assessment was performed using Bechtel standard computer program ME-916. The current evaluation for the addition of welded attachment was performed using ME101. Confirm whether MEIOI computer code uses the same methodology as used in ME916 for the design basis enveloping assessment.
Response
The feedwater piping is analyzed using ME101 to determine the primary and secondary stresses and the support loads. The methodology used (ASME Section III, Code Class 2) for design stress limits and support loading combinations is the same for both the original and the modified feedwater piping.
The ME916 program calculates piping stresses at the integral attachments. The methodology used (ASME Code cases N-122, N-391) is the same for both the original attachments and the new attachments. Reference 2 details the methods of analysis used.
STP Nuclear Operating Company (STPNOC) used MEIOI for piping analysis and ME916 to qualify integral welded attachments. As seen in DCN 9704761 on pages 121-133 of 151, STPNOC also used the evaluation procedure added in Code case N-122-2.
- 2. Subsection NC-3645(a) of ASME Section III, requires that attachments be designed to minimize stress concentrations in applications where the number of stress cycles, due either to pressure or thermal effect, is relatively large for the expected life of the equipment. Confirm whether the stress concentration has been adequately accounted for in your calculation using either ME916 or MEI01 computer code.
Response
The stress concentration has been adequately accounted for in the calculation. STPNOC used the stress indices for the feedwater piping analysis (ME101) for ASME Section III, Code Class 2 piping. The stress indices for the pipe and attachments (ME916) are enveloped stress indices per ASME Code Case N-391 (circular welded attachment for FW-9012-HL5010). The stress indices for the bounding case support (FW-9012-HL5010) are summarized in Table 1.
- 3. In the request letter, you indicated that the evaluation of the additional welded attachments in the rerouted feedwater piping following the steam generator replacement (SGR) indicated that the existing enveloping assessment performed previously in 1987 (Reference 2) remains bounding for the feedwater piping welded attachments and conform with the stress criteria for the elimination of AlBs discussed in UTFSAR Section
NOC-AE-0500 1886 Attachment Page 2 of 4 3.6.2.1.1. Provide summary evaluation results for the primary stress intensity, the primary plus secondary stress and the cumulative factors for the additional welded attachments on the rerouted feedwater piping due to SGR.
Response
The specific support primary stress intensity, primary plus secondary stress, and the cumulative usage factor for the new added integral welded attachments (IWAs) were not calculated.
However, the new IWAs are qualified by comparison with welded IWAs for supports having a higher range of thermal/OBE loads and stresses. Refer to Table 2 for details.
References
- 1. STP Nuclear Operating Company letter to NRC, "Addition of Welded Attachments to Piping Systems from Which Arbitrary Intermediate Breaks (AIBS) Were Previously Eliminated," November 18, 2004, NOC-AE-04001823.
- 2. STP Houston Lighting & Power Company letter to NRC, "Elimination of Arbitrary Intermediate Breaks," ST-HL-AE-2290, dated July 8, 1987.
NOC-AE-05001 886 Attachment Page 3 of 4 Table 1 Summary of Stress Indices for Support 18"FW-9012-HL5010 Stress Pipe per ASME Attachment to the Pipe per ASME Code Case N-391 (ME916)
Indices Section III (ME101) Pipe Attachment Enveloped B1 0.5 C, 1.0 Ki 1.0 B2 1.0 C2 1.0 K2 1.0 C3 1.0 K3 1.0 BT or Bw _ _ _ ___4.618 BL _____ 1.1 Bc or BN _ _ _ __ _2.528 Cw 6.6396 9.236 9.236 CL 2.1062 2.2 2.2 Cc or CN __4.2809 5.056 5.056 BT __Not required for this support CT __Not required for this support KT, K1 3.6 3.6 T 3.6
______________ ~ _ ~_ _ _ ~ _ __~ _ _ _ _ _ _ l__ (Partial penetration as weld)
NOC-AE-05001886 Attachment Page 4 of 4 Table 2 Stress Summary for Added Attachments Primary Stress Intensity Primary plus Secondary Stress and Usage factors Design Condition Emergency Condition Faulted Condition Normal and Upset Condition Support No. (NB-3652) (NB -3655.2) (NB-3656) (NB-3653) Cumulative EQ. 9 Allowable EQ. 9 Allowable EQ. 9 Allowable EQ. 10 EQ. 12 EQ. 13 Allowable Usage psi Psi psi psi psi psi Sn Max Se Max Max 3Sm Factor (CUF) 1.5Sm psipsi psi FW-9012- 7706 25950 - - 34910 51900 49635 51900 0.7835 HL5010 FW- 1012- 7200 25950 - - 28500 51900 27497 51900 < 0.635(2.4)
HL5001 (loop A)
FW-1012- 8200 25950 - - 29100 51900 66783(5) 884075 60477' 51900 < 0.635 4 HL5006 (loop A)
FW-1018- 7500 25950 - - 14800 51900 Note (1) - 51900 < 0.635 4)
HL5014 (loop D) _ _ _ _ _ _ _I I II_ _
FW-1014- 15300 25950 - 19100 51900 Note (1) 51900 < 0.635('4 HLSOIS (loop B) I I I I FL-2018- Unit 2 is qualified by comparison with Unit I analysis.
HL5014 (loop D)
HL-2014- Unit 2 is qualified by comparison with Unit I analysis.
HL5015 (loop B)
Notes:
(1) The evaluation was to assess the fatigue effects on new and existing integral welded attachments (IWAs) for all four loops of main feedwater lines. The fatigue effects on piping systems are evaluated with EQ. 10 and EQ. 11 of ASME Section III, Paragraph NB3600 based on thermal range and OBE range loads. Based on a review of all the supports with IWAs and comparisons of thermal/OBE loads and stresses between:
- a. the existing analysis (before steam generator replacement, i.e., pre-SGR)
- b. the new analysis (post-SGR)
- c. the loads for feedwater support F'-V-9012-1IL5010 selected previously for fatigue evaluation.
The two supports on Loop A, HL5001 and HL5006, were subsequently selected for detailed fatigue evaluations as bounding cases to qualify new IWAs added to the supports listed in table above. Thus the stresses and cumulative usage factors for the new IWAs are determined to be lower when compared to bounding case supports analyzed (HL5001 and HL5006).
(2) Alternating stresses Sa,, =23828 psi for support HL5001 (3) Alternating stress S.,, =24899 psi for support 1L5006 (4) CUP = 0.635 calculated for alternating stress Sl,, = 30809 psi (5) Equations 12, 13 and thermal stress ratchet check of NB-3653.7 were satisfied.