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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
MONTHYEARML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001-01, 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 05000498/20240052024-08-22022 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 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 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual 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 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 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 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 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 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 NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 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 ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 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) 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) 2024-09-30
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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.