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| | number = ML16053A187 | | | number = ML16053A187 |
| | issue date = 03/01/2016 | | | issue date = 03/01/2016 |
| | title = South Texas Project, Units 1 and 2 - Request for Additional Information, Request to Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years (CAC MF61 | | | title = Request for Additional Information, Request to Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years (CAC MF6176-MF6177) |
| | author name = Regner L M | | | author name = Regner L |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Koehl D L | | | addressee name = Koehl D |
| | addressee affiliation = South Texas Project Nuclear Operating Co | | | addressee affiliation = South Texas Project Nuclear Operating Co |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
| | license number = NPF-076, NPF-080 | | | license number = NPF-076, NPF-080 |
| | contact person = Regner L M, NRR/DORL/LPLIV-1 | | | contact person = Regner L, NRR/DORL/LPLIV-1 |
| | case reference number = CAC MF6176, CAC MF6177 | | | case reference number = CAC MF6176, CAC MF6177 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Dennis L. Koehl President and CEO/CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483 March 1, 2016 SUBJECT: SOUTH TEXAS PROJECT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY (CAC NOS. MF6176 AND MF6177) Dear Mr. Koehl: By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML 15198A147, ML 15293A509, and ML 15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project, Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information, as described in the enclosure to this letter, is required to complete the review. A draft version of the request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 18, 2016 (ADAMS Accession No. ML 16050A026). The questions were discussed with your staff during a conference call the same day. The RAI was revised and a draft copy of the enclosed request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 24, 2016 (ADAMS Accession No. ML 16057A032). The questions were discussed with your staff during a conference call on February 25, 2016. Your response is requested by March 21, 2016, to allow the NRC staff enough time to make a regulatory decision on your license amendment request by your requested date of April 30, 2016. If you are unable to provide a satisfactory RAI response by March 21, 2016, the staff is unlikely to meet your requested completion date. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 1, 2016 Mr. Dennis L. Koehl President and CEO/CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483 |
| -2 -D. Koehl If you have any questions, please contact me at 301-415-1906 or vis e-mail at Lisa. Reg ner@nrc.gov. Docket Nos. 50-498 and 50-499 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML 15198A147, ML 15293A509, and ML 15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project (STP), Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required to complete the review. SCVB RAI: The STP Updated Final Safety Analysis Report (UFSAR) Section 6.2.1.3, "Mass and Energy Release Analyses for Postulated Loss of Coolant Accidents," states the use of the Westinghouse WCAP-10325-P-A methodology for loss-of-coolant accident (LOCA) mass and energy release analysis. Westinghouse Electric Company LLC (Westinghouse) has issued Nuclear Safety Advisory Letters (NSALs)-06-6, -11-5, and -14-2, and lnfoGram (IG)-14-1 to report errors in this methodology. Also, a new methodology (GOTHIC) is used for the LOCA containment analysis for which the mass and energy input needs to be corrected based on the above NSALs and the lnfoGram. The licensee indicated that the three Westinghouse NSALs were corrected and incorporated into the new LOCA containment analysis and the analysis results have been incorporated into the UFSAR. 1. Please describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis. Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses. Provide a brief description of the changes from the previous analysis results. Enclosure
| | |
| -2 -2. The information provided in the IG-14-1 is generic. Please describe STP specific analysis/evaluations performed to determine the applicability of the errors reported in the lnfoGram to STP and its impact on the current analysis of record.
| | ==SUBJECT:== |
| -2 -D. Koehl If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa. Reg ner@n re. gov. Docket Nos. 50-498 and 50-499 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 Reading RidsACRS_MailCTR Resource RidsNrrDorllpl4-1 Resource RidsNrrDssScvb Resource RidsNrrPMSouthTexas Resource RidsNrrLAJBurkhardt Resource RidsRgn4MailCenter Resource ADAMS Accession No. ML 16053A187 Sincerely, IRA/ Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SCVB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1/PM NAME LRegner (MWatford for) JBurkhardt* RDennig* RPascarelli LRegner DATE 2/25/16 2/25/16 2/25/16 03/01 /16 03/01/16 OFFICIAL RECORD COPY
| | SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY (CAC NOS. MF6176 AND MF6177) |
| }} | | |
| | ==Dear Mr. Koehl:== |
| | |
| | By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project, Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information, as described in the enclosure to this letter, is required to complete the review. |
| | A draft version of the request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 18, 2016 (ADAMS Accession No. ML16050A026). The questions were discussed with your staff during a conference call the same day. The RAI was revised and a draft copy of the enclosed request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 24, 2016 (ADAMS Accession No. ML16057A032). The questions were discussed with your staff during a conference call on February 25, 2016. Your response is requested by March 21, 2016, to allow the NRC staff enough time to make a regulatory decision on your license amendment request by your requested date of April 30, 2016. If you are unable to provide a satisfactory RAI response by March 21, 2016, the staff is unlikely to meet your requested completion date. |
| | |
| | D. Koehl If you have any questions, please contact me at 301-415-1906 or vis e-mail at Lisa. Reg ner@nrc.gov. |
| | Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project (STP), Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required to complete the review. |
| | SCVB RAI: |
| | The STP Updated Final Safety Analysis Report (UFSAR) Section 6.2.1.3, "Mass and Energy Release Analyses for Postulated Loss of Coolant Accidents," states the use of the Westinghouse WCAP-10325-P-A methodology for loss-of-coolant accident (LOCA) mass and energy release analysis. Westinghouse Electric Company LLC (Westinghouse) has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2, and lnfoGram (IG)-14-1 to report errors in this methodology. Also, a new methodology (GOTHIC) is used for the LOCA containment analysis for which the mass and energy input needs to be corrected based on the above NSALs and the lnfoGram. |
| | The licensee indicated that the three Westinghouse NSALs were corrected and incorporated into the new LOCA containment analysis and the analysis results have been incorporated into the UFSAR. |
| | : 1. Please describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis. Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses. Provide a brief description of the changes from the previous analysis results. |
| | Enclosure |
| | : 2. The information provided in the IG-14-1 is generic. Please describe STP plant-specific analysis/evaluations performed to determine the applicability of the errors reported in the lnfoGram to STP and its impact on the current analysis of record. |
| | |
| | ML16053A187 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SCVB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1/PM NAME LRegner (MWatford for) JBurkhardt* RDennig* RPascarelli LRegner DATE 2/25/16 2/25/16 2/25/16 03/01 /16 03/01/16}} |
Letter Sequence RAI |
|---|
|
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MONTHYEARML16050A0262016-02-18018 February 2016
NRR E-mail Capture - South Texas Project Units 1 & 2, Request for Additional Information for Integrated Leak Rate Testing Extension Review
Project stage: RAI
ML16057A0322016-02-24024 February 2016
NRR E-mail Capture - South Texas Project, Units 1 & 2, Draft Request for Additional Information Regarding Integrated Leak Rate Testing Extension
Project stage: Draft RAI
ML16053A1872016-03-0101 March 2016
Request for Additional Information, Request to Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years (CAC MF6176-MF6177)
Project stage: RAI
ML16116A0072016-04-29029 April 2016
Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years
Project stage: Approval
2016-02-24
[Table View] |
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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 05000498/20243012024-08-27027 August 2024
NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301
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
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
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
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
ML24116A2282024-04-25025 April 2024
Annual Environmental Operating Report
ML24116A3032024-04-25025 April 2024
Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment
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
NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024
Nuclear Liability Certificates of Insurance
ML24080A2902024-03-19019 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
2024-09-30
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24207A1782024-07-25025 July 2024
Licensed Operator Positive Fitness-For-Duty Test
ML24052A0112024-02-16016 February 2024
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications (L-2023-LLE-0046)
ML24024A1162024-01-24024 January 2024
STP Unit 2 Request for Information
ML23334A0062023-11-29029 November 2023
NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements
ML23319A4442023-11-15015 November 2023
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements
ML23278A1532023-10-0505 October 2023
NRR E-mail Capture - South Texas Project Request for Additional Information - Request for Indirect Transfer of Licenses and Conforming Amendments (L-2023-LLM-0004)
ML23264A0972023-09-21021 September 2023
NRR E-mail Capture - South Texas Project - Request for Additional Information - License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047)
ML23255A2862023-09-12012 September 2023
NRR E-mail Capture - South Texas Project Draft Request for Additional Information License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047)
ML23145A1872023-05-24024 May 2023
July 2023 Emergency Preparedness Program Inspection - Request for Information
ML22255A1542022-09-13013 September 2022
Operating Company Information Request for the Cyber Security Baseline Inspection 05000498/2022401 and 05000499/2022401
ML22206A0142022-07-20020 July 2022
NRR E-mail Capture - South Texas Project - Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22194A0502022-07-0707 July 2022
NRR E-mail Capture - South Texas Project - Updated Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22194A0492022-06-0808 June 2022
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22123A3272022-05-0303 May 2022
STP EP Exercise Inspection July 2022 RFI
ML22084A0762022-04-0404 April 2022
Notification of NRC Design Bases Assurance Inspection (Team) (05000498/2022012 and 05000499/2022012) and Request for Information
ML21286A5732021-10-18018 October 2021
Notification of NRC Design Bases Assurance Inspection (Programs) (05000498/2022011 and 05000499/2022011) and Request for Information
ML21166A2392021-06-16016 June 2021
Notification of Inspection (NRC Inspection Report 05000498/2021003 and 05000499/2021003) and Request for Information
ML21160A1522021-06-0909 June 2021
Request for Information NRC Inspection 2021-003 Public Radiation Safety
ML21133A2372021-05-0505 May 2021
Request for Additional Information: STP EP Exercise Inspection - July 2021
ML21039A8902021-02-0808 February 2021
NRR E-mail Capture - South Texas Project - Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing
ML21029A3312021-01-29029 January 2021
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing
ML20280A5452020-08-17017 August 2020
STP 2020 PIR Request for Information
ML20111A0052020-04-17017 April 2020
NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME OM Code 2012 Edition - Relief Request PRR-01
ML20070N0222020-03-10010 March 2020
NRC Selection for Onsite Review
ML20057G4612020-02-26026 February 2020
05000498/499 Request for Information - Occupational Radiation Safety Inspection
ML20045E2172020-02-13013 February 2020
Licensed Operator Positive Fitness-For-Duty Test
ML20036F5862020-02-0404 February 2020
Request for Additional Information - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L-2019-LLR-0096)Redacted
ML19165A1032019-06-14014 June 2019
NRR E-mail Capture - Draft RAI for STP TS 3.8.1.1 Sbdg SR Change
ML19081A1512019-03-21021 March 2019
NRR E-mail Capture - Draft Round 2 RAI - Sbdg Voltage and Frequency LAR (L-2018-LLA-0078)
ML18283B9522018-10-10010 October 2018
NRR E-mail Capture - Final RAI - South Texas Standby DG TS Change (L-2018-LLA-0078)
ML18263A1432018-09-12012 September 2018
NRR E-mail Capture - Final RAI for South Texas Project RR-ENG-E-16 (L-2018-LLR-0097)
ML18197A4172018-07-17017 July 2018
Notification of NRC Triennial Heat Sink Performance Inspection (05000498/2018003 and 05000499/2018003) and Request for Information
ML18003B4222018-01-0303 January 2018
NRR E-mail Capture - Final Request for Additional Information Amendment Request to Modify the Emergency Response Organization for South Texas Project
ML17229B4672017-08-16016 August 2017
Notification of NRC Inspection 05000499/2017008 and Request for Information
ML17132A0712017-05-15015 May 2017
Information Request the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000498/2017407; 05000499/2017407
ML17103A6272017-04-13013 April 2017
Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000498/2017007 and 05000499/2017007) and Request for Information
ML16351A1502016-12-16016 December 2016
Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409)
ML16302A4532016-12-12012 December 2016
Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409)
ML16343A0422016-12-0808 December 2016
Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application (CAC NOS. ME4936, ME4937)
ML16340A1022016-12-0505 December 2016
Requests for Additional Information for the Review of the South Texas Project License Renewal Application (CAC Nos. ME4936 and ME4937)
ML16246A0952016-09-15015 September 2016
Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16214A2912016-08-26026 August 2016
Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16187A0522016-07-0707 July 2016
Request for Additional Information Regarding License Renewal Application
ML16141B0812016-05-31031 May 2016
Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information
ML16125A2902016-05-26026 May 2016
Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
ML16127A4522016-05-12012 May 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16104A3522016-04-22022 April 2016
Requests for Additional Information Set 35 for the Review of the South Texas Project License Renewal Application (Tac Nos. ME4936, ME4937)
ML16082A5072016-04-11011 April 2016
Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
ML16082A4842016-03-22022 March 2016
NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Risk Review for GSI-191
ML16081A0042016-03-18018 March 2016
NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Thermal-hydraulic Review for GSI-191
2024-07-25
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 1, 2016 Mr. Dennis L. Koehl President and CEO/CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY (CAC NOS. MF6176 AND MF6177)
Dear Mr. Koehl:
By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project, Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information, as described in the enclosure to this letter, is required to complete the review.
A draft version of the request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 18, 2016 (ADAMS Accession No. ML16050A026). The questions were discussed with your staff during a conference call the same day. The RAI was revised and a draft copy of the enclosed request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 24, 2016 (ADAMS Accession No. ML16057A032). The questions were discussed with your staff during a conference call on February 25, 2016. Your response is requested by March 21, 2016, to allow the NRC staff enough time to make a regulatory decision on your license amendment request by your requested date of April 30, 2016. If you are unable to provide a satisfactory RAI response by March 21, 2016, the staff is unlikely to meet your requested completion date.
D. Koehl If you have any questions, please contact me at 301-415-1906 or vis e-mail at Lisa. Reg ner@nrc.gov.
Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project (STP), Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required to complete the review.
SCVB RAI:
The STP Updated Final Safety Analysis Report (UFSAR) Section 6.2.1.3, "Mass and Energy Release Analyses for Postulated Loss of Coolant Accidents," states the use of the Westinghouse WCAP-10325-P-A methodology for loss-of-coolant accident (LOCA) mass and energy release analysis. Westinghouse Electric Company LLC (Westinghouse) has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2, and lnfoGram (IG)-14-1 to report errors in this methodology. Also, a new methodology (GOTHIC) is used for the LOCA containment analysis for which the mass and energy input needs to be corrected based on the above NSALs and the lnfoGram.
The licensee indicated that the three Westinghouse NSALs were corrected and incorporated into the new LOCA containment analysis and the analysis results have been incorporated into the UFSAR.
- 1. Please describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis. Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses. Provide a brief description of the changes from the previous analysis results.
Enclosure
- 2. The information provided in the IG-14-1 is generic. Please describe STP plant-specific analysis/evaluations performed to determine the applicability of the errors reported in the lnfoGram to STP and its impact on the current analysis of record.
ML16053A187 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SCVB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1/PM NAME LRegner (MWatford for) JBurkhardt* RDennig* RPascarelli LRegner DATE 2/25/16 2/25/16 2/25/16 03/01 /16 03/01/16
