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MONTHYEARML21049A2652021-02-16016 February 2021 NRR E-mail Capture - South Texas Project - Acceptance of License Amendment Request to Revise the Moderator Temperature Coefficient Surveillance Requirements (L-2021-LLA-0004) Project stage: Acceptance Review ML21058A0002021-02-26026 February 2021 NRR E-mail Capture - South Texas Units 1 and 2 - License Amendment Request to Revise Moderator Temperature Coefficient SRs - Audit Plan and Setup of Online Document Access (L-2021-LLA-0004) Project stage: Other ML21196A4132021-07-15015 July 2021 Teleconference and Webinar with STP Nuclear Operating Company Regarding the License Amendment Request to Revise the Moderator Temperature Coefficient Surveillance Requirement for South Texas Project, Units 1 and 2 Project stage: Meeting ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change Project stage: Meeting ML21222A1192021-08-12012 August 2021 Summary of Meeting with STP Nuclear Operating Company Regarding the License Amendment Request to Revise the Moderator Temperature Coefficient Surveillance Requirements for South Texas Project, Units 1 and 2 Project stage: Meeting ML21237A0562021-09-10010 September 2021 Withdrawal of an Amendment Request Project stage: Withdrawal ML21236A3082021-09-10010 September 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Moderator Temperature Coefficient Surveillance Requirements Project stage: Other 2021-07-15
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Category:Meeting Briefing Package/Handouts
MONTHYEARML22243A1312022-08-31031 August 2022 STP Nuclear Operating Company August 31, 2022 Presentation - Pre-Submittal Meeting for Updated Main Steam Line Break and Locked Rotor Dose Consequence Analysis to Address Extended Cooldown Timelines ML22214A0972022-08-0202 August 2022 Presentation by South Texas Project ML22153A2942022-06-17017 June 2022 richardsd-hv-th28 ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change ML20125A3362020-05-0404 May 2020 STP Presubmittal Meeting Exigent Accumulator LAR 2020-05-05 Presentation L-2020-LRM-0039 ML19326A0072019-11-22022 November 2019 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan - December 3, 2019 ML16356A0612016-12-21021 December 2016 12/21/2016 South Texas Project Aluminum Bronze Aging Management Request for Additional Information ML16264A3632016-09-20020 September 2016 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan Staff Augmentation Times ML16210A0442016-07-28028 July 2016 STP Nuclear Operating Company Handouts for July 28, 2016 Public Meeting on GSI-191 ML16172A0192016-07-25025 July 2016 STP Aluminum Bronze Selective Leaching Public Meeting - June 21, 2016 ML16202A4872016-07-21021 July 2016 07/21/2016 Talking Points, Supplemental Information for South Texas Project and NRC Public Meeting ML16111A0272016-04-18018 April 2016 STP Nuclear Operating Company Slideshow for Public Meeting on April 21, 2016 for GSI-191 Resolution (CAC No. MF2400-01) ML16062A3042016-03-0202 March 2016 TS 5.3.2 LAR Pre-Submittal Meeting Presentation - March 2, 2016 ML16033A0042016-01-19019 January 2016 Applicant's Slides for STP Meeting on Aluminum Bronze Aging Management ML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call ML15271A3042015-09-28028 September 2015 Public Phone Call Meeting Description of Supplement 2 to STPNOC Risk-Informed Licensing Application to Address GSI-191 and Respond to GL-2004-02 ML15111A0582015-04-15015 April 2015 Licensee Handouts (2 of 2) for 4/22/2015 Public Meeting Possible Roverd Section on Fixed Filtration (TAC Nos. MF2400-MF2409) ML15111A0562015-04-15015 April 2015 Licensee Handouts (1 of 2) for 4/22/2015 Public Meeting Revised Roverd Section on Large Early Release Frequency Change for Large Break Loss-of-Coolant Accident(Tac Nos. MF2400-MF2409) ML15056A3862015-02-25025 February 2015 NRC Slides for February 25, 2015 Public Meeting with STPNOC Concerning GSI-191 ML15049A4882015-02-18018 February 2015 Slides for February 25, 2015 Public Meeting ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. NRC Public Meeting Slides - ILRT License Amendment ML15034A1142015-02-0404 February 2015 STP Risk- Informed Approach to GSI - 191 Roverd 2015 Meeting Blue 1 29 15 ML14192A9842014-08-0404 August 2014 Summary of Pre-Licensing Meeting with STP Nuclear Operating Company to Discuss Future License Amendment Request to Revise TS 6.9.1.6.b.9 to the Leading Edge Flow Meter Technology for Feedwater Flow Measurement ML14120A0112014-04-29029 April 2014 4/29/2014 - South Texas Project Regulatory Approach for Risk-Informed Pilot Submittal Presentation Relating to 10 CFR 50.46c ML13352A1422013-12-16016 December 2013 GSI-191 Licensing Submittal Comparison of Changes Between Rev 1 and Rev 2 ML13352A1242013-12-16016 December 2013 NRC Staff Slides South Texas Project Risk-Informed Generic Safety Issue - 191, December 16, 2013 ML13316B9052013-11-13013 November 2013 Albrz Testing Update for NRR Final ML13150A2162013-05-23023 May 2013 Licensee Slides for 5/23/13 Public Meeting Regarding GSI-191 ML13140A2562013-05-20020 May 2013 Licensee Slides for 5/23/13 Meeting - STP Pilot Submittal for Risk Informed Approach to Resolving GSI-191 ML13023A3342013-02-25025 February 2013 1/15/2013 Summary of Public Meetings Conducted to Discuss Draft Supplemental Environmental Impact Statement Related to Review of South Texas Project, Units 1 & 2, License Renewal Application ML13051A8552013-02-20020 February 2013 Licensee Slides for 3/5/13 Pre-Application Meeting for Proposed Licensing Action to Revise the Fire Protection Program at STP ML13029A4972013-01-15015 January 2013 Slides - Preliminary Site-Specific Results of the Environmental Review for South Texas Project License Renewal ML12297A3312012-11-27027 November 2012 Summary of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 ML12264A3202012-10-11011 October 2012 Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program ML12145A4382012-05-18018 May 2012 Licensee Handout on Calibration and Benchmarking of Single and Two-Phase Jet Cfd Models ML1209004042012-03-30030 March 2012 3-27-2012 - STP Public Meeting Handout from Nuclear Innovation North America, LLC on Fukushima Lessons Learned for South Texas Project Units 3 and 4 ML1205407582012-02-22022 February 2012 STP Summary of January Meeting ML1205405572012-02-22022 February 2012 Licensee Slides for 03/1/12 Meeting with STP Nuclear Operating Company Meeting to Discuss GSI-191 ML1205405702012-02-22022 February 2012 Uncertainty Modeling of LOCA Frequencies and Break Size Distributions for the STP GSI-191 Resolution ML1204400652012-02-0909 February 2012 Licensee Slides for 2/9/12 Meeting Regarding GSI-191 ML1133505632011-12-0101 December 2011 Licensee Presentation from 12/1/11 Meeting Via Conference Call to Discuss Risk-Informed GSI-191,Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance ML1130506322011-10-26026 October 2011 Licensee Handouts from November 1, 2011 Meeting with STP Nuclear Operating Company on GSI-191 ML1127702032011-10-0303 October 2011 Licensee Slides from 10/3/11 Meeting LOCA Frequencies, Final Results ML1127701762011-10-0303 October 2011 Licensee Handouts from 10/3/11 Meeting STP LOCA Frequency ML1123508732011-08-22022 August 2011 Models and Methods Used for Casa Grande ML1123508832011-08-22022 August 2011 LOCA Initiating Event Frequencies and Uncertainties Status Report ML1120707072011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slide Models and Methods Used for Casa Grande ML1120707292011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slides Computational Fluid Dynamics Validation Plan ML1118903802011-07-0707 July 2011 Licensee Slides, LOCA Initiating Event Frequencies and Uncertainties(Draft) ML1118904082011-07-0606 July 2011 Licensee Handout Loca Frequencie Approach and Example Application 2022-08-31
[Table view] Category:Slides and Viewgraphs
MONTHYEARML22243A1312022-08-31031 August 2022 STP Nuclear Operating Company August 31, 2022 Presentation - Pre-Submittal Meeting for Updated Main Steam Line Break and Locked Rotor Dose Consequence Analysis to Address Extended Cooldown Timelines ML22214A0972022-08-0202 August 2022 Presentation by South Texas Project ML22153A2942022-06-17017 June 2022 richardsd-hv-th28 ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change ML20248H5322020-09-0404 September 2020 STP Nuclear Operating Company September 14, 2020, Presentation - Pre-Submittal Meeting for Proposed South Texas Project Moderator Temperature Coefficient Surveillance Requirement Technical Specification Change ML20125A3362020-05-0404 May 2020 STP Presubmittal Meeting Exigent Accumulator LAR 2020-05-05 Presentation L-2020-LRM-0039 ML20034E8192020-02-0606 February 2020 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan ML19095A6562019-04-0404 April 2019 NRR E-mail Capture - (External_Sender) Handout for 4/10/19 Meeting to Discuss a Proposed Request for South Texas Project, Units 1 and 2, Regarding Repair of Piping Using Carbon Fiber Repair Methods ML17004A0292017-01-0404 January 2017 Slides for January 4, 2017, Public Meeting on South Texas Project's Resposne to Aluminum Bronze Aging Management Request for Additional Information ML16356A0612016-12-21021 December 2016 12/21/2016 South Texas Project Aluminum Bronze Aging Management Request for Additional Information ML16350A3272016-11-17017 November 2016 Transcript of Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Meeting - November 17, 2016 ML16264A3632016-09-20020 September 2016 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan Staff Augmentation Times ML16172A0192016-07-25025 July 2016 STP Aluminum Bronze Selective Leaching Public Meeting - June 21, 2016 ML16188A3682016-07-0606 July 2016 Audit Presentation - Westinghouse Methodology for South Texas Unit 1 LAR: Operation with 56 Control Rods ML16062A3042016-03-0202 March 2016 TS 5.3.2 LAR Pre-Submittal Meeting Presentation - March 2, 2016 ML16033A0042016-01-19019 January 2016 Applicant's Slides for STP Meeting on Aluminum Bronze Aging Management ML15334A3972015-11-30030 November 2015 TS 5 3 2 Emergency LAR Pre-Submittal Meeting Presentation ML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. NRC Public Meeting Slides - ILRT License Amendment ML15034A1142015-02-0404 February 2015 STP Risk- Informed Approach to GSI - 191 Roverd 2015 Meeting Blue 1 29 15 ML14192A9842014-08-0404 August 2014 Summary of Pre-Licensing Meeting with STP Nuclear Operating Company to Discuss Future License Amendment Request to Revise TS 6.9.1.6.b.9 to the Leading Edge Flow Meter Technology for Feedwater Flow Measurement ML14149A0892014-05-21021 May 2014 NRR E-mail Capture - STP-GSI-191 Presentation ML14120A0112014-04-29029 April 2014 4/29/2014 - South Texas Project Regulatory Approach for Risk-Informed Pilot Submittal Presentation Relating to 10 CFR 50.46c ML13352A1242013-12-16016 December 2013 NRC Staff Slides South Texas Project Risk-Informed Generic Safety Issue - 191, December 16, 2013 ML13352A1422013-12-16016 December 2013 GSI-191 Licensing Submittal Comparison of Changes Between Rev 1 and Rev 2 ML13316B9052013-11-13013 November 2013 Albrz Testing Update for NRR Final ML13150A2162013-05-23023 May 2013 Licensee Slides for 5/23/13 Public Meeting Regarding GSI-191 ML13140A2562013-05-20020 May 2013 Licensee Slides for 5/23/13 Meeting - STP Pilot Submittal for Risk Informed Approach to Resolving GSI-191 ML13023A3342013-02-25025 February 2013 1/15/2013 Summary of Public Meetings Conducted to Discuss Draft Supplemental Environmental Impact Statement Related to Review of South Texas Project, Units 1 & 2, License Renewal Application ML13051A8552013-02-20020 February 2013 Licensee Slides for 3/5/13 Pre-Application Meeting for Proposed Licensing Action to Revise the Fire Protection Program at STP ML13029A4972013-01-15015 January 2013 Slides - Preliminary Site-Specific Results of the Environmental Review for South Texas Project License Renewal ML12297A3312012-11-27027 November 2012 Summary of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 ML12264A3202012-10-11011 October 2012 Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program ML1209004042012-03-30030 March 2012 3-27-2012 - STP Public Meeting Handout from Nuclear Innovation North America, LLC on Fukushima Lessons Learned for South Texas Project Units 3 and 4 ML1204400652012-02-0909 February 2012 Licensee Slides for 2/9/12 Meeting Regarding GSI-191 ML1133505632011-12-0101 December 2011 Licensee Presentation from 12/1/11 Meeting Via Conference Call to Discuss Risk-Informed GSI-191,Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance ML1130506322011-10-26026 October 2011 Licensee Handouts from November 1, 2011 Meeting with STP Nuclear Operating Company on GSI-191 ML1127701762011-10-0303 October 2011 Licensee Handouts from 10/3/11 Meeting STP LOCA Frequency ML1127702032011-10-0303 October 2011 Licensee Slides from 10/3/11 Meeting LOCA Frequencies, Final Results ML1123508832011-08-22022 August 2011 LOCA Initiating Event Frequencies and Uncertainties Status Report ML1123508732011-08-22022 August 2011 Models and Methods Used for Casa Grande ML1120707292011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slides Computational Fluid Dynamics Validation Plan ML1120707072011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slide Models and Methods Used for Casa Grande ML1118903802011-07-0707 July 2011 Licensee Slides, LOCA Initiating Event Frequencies and Uncertainties(Draft) ML1118904202011-07-0606 July 2011 Licensee Slide from 7/7/11 Meeting with STP Nuclear ML11157A0102011-06-0202 June 2011 STP Nuclear Operating Company, Licensee Handouts, 6/2/2011 Meeting Risk-Informed GSI-191 Closure Plan for GSI-191 Resolution ML1114501952011-05-24024 May 2011 Summary of Meeting with South Texas Project Electric Generating Station 2010 Performance ML1105503952011-02-22022 February 2011 Licensee Slides from 2/22/11 Public Meeting with STP Nuclear Operating Company ML1103206432011-01-27027 January 2011 1/27/11 Presentation on Risk-Informed GSI-191 Project Overview ML1021803392010-08-0505 August 2010 Ltr to E. Halpin Re Participation in Commission Meeting on the Resolution of Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Performance on 09/29/10 2022-08-31
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NRC meeting for proposed South Texas Project Moderator Temperature Coefficient Tech Spec change July 26, 2021
Introductions / Opening Remarks
Meeting Objective Discuss Moderator Temperature Coefficient (MTC) verification approach details and provide additional information in support of the proposed change to the STP MTC Technical Specification 3
Verification of the BOL and EOL Tech Spec Surveillances
- Historically, a measurement has been used to satisfy both the beginning of life (BOL) and end of life (EOL) moderator temperature coefficient (MTC) TS Surveillances
- Therefore, the TS BOL and EOL Surveillances state measure
- The precedent for verifying the EOL MTC TS Surveillance was implemented via WCAP-13749
- The reason for the LAR is to allow both the BOL and EOL TS Surveillances to be performed via a verification, as well as a measurement, if required
- The BOL and EOL TS Surveillance verification procedure is not a method of evaluation in accordance with 10CFR50.59 because it is not used to establish the design basis or in the safety analyses 4
Verification of the BOL and EOL Tech Spec Surveillances
- Current NRC approved codes have demonstrated the capability to accurately predict MTC values and can be used in place of BOL and EOL TS Surveillance measurements
- NRC approved code predictions are integral and necessary to confirm the TS MTC at both BOL and EOL 5
Current MTC Measurements Utilize NRC Approved Code Predictions
- The MTC is inferred by measuring the isothermal temperature coefficient (ITC) and subtracting the NRC approved code predicted doppler temperature coefficient
- The MTC is not measured at the most limiting conditions for accident scenarios
- Confirmation of the analysis of record results therefore rely on code predictions of core reactivity feedback
- All MTC predictions used in the safety analysis confirmation are completed with an NRC approved neutronics code package capable of predicting the MTC 6
MTC Measurement
- The MTC measurement does not detect or determine any core anomaly, since it is a global core parameter
- The predictive performance of the NRC approved core neutronics codes are validated each cycle through more frequently performed TS Surveillances for core reactivity and power distribution
- Measured to predicted critical boron concentrations, radial power distribution, axial power distribution, and the measured vessel average temperature ensure the actual MTC remains in compliance with the TS BOL and EOL limits 7
MTC Measurement
- Measurement of BOL MTC extends the amount of time the core remains close to least negative MTC limit. The core is rarely required to be critical at high boron concentration resulting in less negative MTCs.
- The measurement extends the amount of time the core remains below the point of adding nuclear heat
- Extending the amount of time below the point of adding nuclear heat and at a least negative MTC limits the core feedback mechanisms available to mitigate a transient
- The measurement of the EOL MTC (typically at 300 ppm) requires focused manual operator action to control Tavg at power and results in changes to the axial power distribution 8
Least Negative MTC (Beginning of Life)
- The MTC is primarily impacted by boron concentration with a secondary impact of neutron leakage dictated by the core power distribution
- The boron concentration is confirmed to determine the core reactivity during startup activities and throughout the core life to confirm the Core Reactivity TS Surveillance
- The core power distribution is measured multiple times during startup activities and throughout the core life to confirm the TS core peaking factor limits are met 9
Most Negative MTC (End of Life)
- The boron concentration for the EOL MTC TS Surveillance confirmation is fixed to a specific boron concentration, thereby making power distribution and burnup of the core the primary MTC impacts
- The core reactivity is a measurement of core burnup characteristics and is compared to the predicted core reactivity periodically in accordance with Core Reactivity TS surveillance
- The core power distribution is monitored throughout the core life to confirm various TS:
- Heat Flux Hot Channel Factor
- Nuclear Enthalpy Rise Hot Channel Factor
- Quadrant Power Tilt Ratio 10
MTC Verification Procedure Uncertainties
- The minimum applied uncertainty for the BOL TS MTC verification is 1.5 pcm/F
- Any NRC approved neutronics package that is used to verify the BOL or EOL TS MTC must have an uncertainty less than or equal to 1.5 pcm/F based on previous fleet plant measurements at BOL or use the larger calculated MTC uncertainty for that specific code package
- The minimum applied uncertainty for the EOL TS MTC verification is 2.0 pcm/F
- Any additional uncertainty applied is based on plant measurements of the core power distribution and core reactivity that are performed near the time in core life when the EOL TS MTC is verified, and would only be used to increase the 2.0 pcm/F uncertainty 11
Summary and Conclusions
- The current TS BOL and EOL Surveillances state measure because that is how it was previously performed
- The precedent for verifying the EOL MTC TS Surveillance was implemented via WCAP-13749
- The reason for the LAR is to allow both the BOL and EOL TS Surveillances to be performed via verification, as well as measurement, if required
- The BOL and EOL TS Surveillance verification procedure is not a method of evaluation in accordance with 10CFR50.59 because it is not used to establish the design basis or in the safety analyses
- 10CFR50.36(c)(3), Surveillance requirements, continues to be satisfied because the BOL and EOL MTC TS Surveillances will continue to ensure that the LCO limits are met via verification 12
Questions?
13