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MONTHYEARNL-14-1193, Response to Request for Additional Information Regarding Proposed Alternative to Lnservice Inspection Requirements of ASME Code Case N-770-12014-08-0101 August 2014 Response to Request for Additional Information Regarding Proposed Alternative to Lnservice Inspection Requirements of ASME Code Case N-770-1 Project stage: Response to RAI ML15133A1302015-04-24024 April 2015 Project, Unit 1 - Request for Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis (Relief Request RR-ENG-3-17) Project stage: Request NOC-AE-15003250, LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)2015-04-24024 April 2015 LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary) Project stage: Request ML15170A0662015-06-18018 June 2015 NRR E-mail Capture - Draft SouthTexas-1 RAI N-770-1 RPV Cold Leg Nozzles (MF6174) Project stage: Draft RAI ML15195A4232015-06-25025 June 2015 Request for Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis Supplement (Relief Request RR-ENG-3-17) Project stage: Supplement ML15223B1532015-07-16016 July 2015 NRR E-mail Capture - NRC Question: SouthTexas- RPV Cl Relief Project stage: Other NOC-AE-15003276, Response to Request for Additional Information Regarding Relief Request RR-ENG-3-17 Regarding Deferral of Inservice Inspection of Reactor Pressure Vessel Cold Leg Nozzle Dissimilar Metal Butt Welds2015-07-22022 July 2015 Response to Request for Additional Information Regarding Relief Request RR-ENG-3-17 Regarding Deferral of Inservice Inspection of Reactor Pressure Vessel Cold Leg Nozzle Dissimilar Metal Butt Welds Project stage: Response to RAI ML15205A0512015-08-10010 August 2015 Request for Withholding Information from Public Disclosure, 4/22/15 Affidavit Executed by J. Gresham, Westinghouse LTR-PAFM-15-27-P Provided in Support of Relief Request RR-ENG-3-17, Relief from Code Case N-770-1 Project stage: Withholding Request Acceptance ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval Project stage: Other 2015-06-25
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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 Pro/eot Electric GeneratingStation P.O. Box 289 Wadsworth. Texas 77483 ,v v -
June 25, 2015 NOC-AE-l15003268 10 CFR 50.55a File No. G25 U. S. Nuclear Regulatory Commission Attention: Document Control Deskk Washington, DC 20555-0001 South Texas Project Unit 1 Docket No. STN 50-498 Request for Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-end Welds with Flaw Analysis Supplement (Relief Reauest RR-ENG-3-17' 1 ........... i .......... ... . .. r
References:
- 1. Letter from Michael Berg, STPNOC, to NRC Document Control Desk, "Request for Relief from Code Case N-770-1, Subsection 2400 and Table I Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-end Welds with Flaw Analysis", April 24, 2015. (NOC-AE-1 5003250) (ML15133A130)
- 2. Email from Lisa Regner, NRC to Lance Sterling, STPNOC, "DRAFT SouthTexas-1 RAI N-770-1 RPV Cold Leg Nozzles (MF6174)," dated June 18, 2015. (ML15170A066)
In accordance with the provisions of 10 CFR 50.55a(a)(3)(ii), STP Nuclear Operating Company (STPNOC) requested relief for South Texas Project (STP) Unit 1 for performing the reactor vessel Cold Leg nozzle to safe-end weld inspections in Reference 1. Subsequently, in Reference 2, the NRC provided feedback to STPNOC related to the need of enhancing the original submittal with additional clarification information. The intent of the letter is to provide a Supplement to the original Relief Request (Reference 1) to address the additional clarifications.
This letter contains one enclosure that is considered non-proprietary. There are no commitments in this letter.
Ao4~1 ST1" 34150859
NOC-AE-1 5003268 Page 2 of 3 If there are any questions regarding this Relief Request, please contact Rafael Gonzales at 361-972-4779, or me at 361-972-7030.
Manager Design Engineering!
Testing and Programs rjg
Enclosure:
Supplement Response Related to the Request for Relief from Code Case N-770-I, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-end Welds with Flaw Analysis
NOC-AE-1 5003268 Page 3 of 3 cc:
(paper copy)
(electronic copy)
Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission Steve Frantz 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission Lisa M. Regner Lisa M. Regner Senior Project Manager U.S. Nuclear Regulatory Commission NRG South Texas LP One White Flint North (MS 8 G9A) John Ragan 11555 Rockville Pike Chris O'Hara Rockville, MD 20852 Jim von Suskil NRC Resident Inspector CPS Energy U. S. Nuclear Regulatory Commission Kevin Polio P. 0. Box 289, Mail Code: MN1 16 Cris Eugster Wadsworth, TX 77483 L. D. Blaylock Crain Caton & James, P.C.
Peter Nemeth City of Austin Cheryl Mele John Wester Texas Dept. of State Health Services Richard A. Ratliff Robert Free
NOC-AE-1 5003268 Enclosure Supplement Response Related to the Request for Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-end Welds with Flaw Analysis
NOC-AE-1 5003268 Enciosure Page 1 of 2 Backgqround By letter dated April 24, 2015 (ADAMS Number ML15133A130), STP Nuciear Operating Company (the licensee) requested relief from requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code) for the volumetric examination of the reactor pressure vessel (RPV) cold leg nozzle dissimilar metal (DM) butt welds at the South Texas Project (South Texas), Unit 1.
To complete its review, the NRC staff requests the following additional information.
- 1. When did the licensee complete the ASME Code Case N-770-1 baseline examination of these welds, as required by 10 CFR 50.55a(g)(6)(ii)(F)(1) with conditions?
- 2. (a) Clarify that the proposed alternative is to defer the ASME Code Case N-770-1 required volumetric examination, as required by 10 CFR 50.55a(g)(6)(ii)(F) with conditions, from the fall 2015 refueling outage (1IRE19) up to and including the spring 2017 refueling outage (1 RE20). (b) Clarify that the discussions regarding non-welded stress improvement provided in the relief request and the information provided in Table 2, page 6 of Enclosure 1 of relief request, are for information only and not part of the licensee's proposed alternative.
NRC Issue
- 1. When did the licensee complete the ASME Code Case N-770-1 baseline examination of these welds, as required by 10 CFR 50.55a(g)(6)(ii)(F)(1) with conditions?
STPNOC Response The ASME Code Case N-770-1 baseline examination of these welds, as required by 10 CFR 50.55a(g)(6)(ii)(F)(1), were performed in Unit 1 during the Fall of 2009.
NOC-AE-1 5003268 Enclosure Page 2 of 2 NRC Issue
- 2. (a) Clarify that the proposed alternative is to defer the ASME Code Case N-770-1 required volumetric examination, as required by 10 CFR 50.55a(g)(6)(ii)(F) with conditions, from the fall 2015 refueling outage (I RE 19) up to and including the spring 2017 refueling outage (I1RE20). (b) Clarify that the discussions regarding non-welded stress improvement provided in the relief request and the information provided in Table 2, page 6 of Enclosure I of relief request, are for information only and not part of the licensee's proposed alternative.
STPNOC Response (a) The proposed alternative is to defer the ASME Code Case N-770-I required volumetric examination, as required by 10 CFR 50.55a(g)(6)(ii)(F) with conditions, from the fall 2015 refueling outage (1IRE19) up to and including the spring 2017 refueling outage (1RE20). Essentially, this Relief Request (Reference 1) submittal is a nominal 18 month extension request, i.e. one operating cycle.
(b) This information provided in Table 2, page 6 of Enclosure 1 of the Relief Request (Reference I of the Supplement), is provided for information only and is not a part of STPNOC's proposed alternative.