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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
[Table view] |
Text
Leakage from BMI Nozzles What do the findings from South Texas mean?
Larry Mathews, Chairman Alloy 600 ITG Southern Nuclear Alloy 600 Issue Task Group Materials Reliability Program
South Texas Project Unit 1 Inspections
- Bare Metal Visual - 57 BMIs inspected via
- UT from ID of nozzle to Nozzle 1 & 46
- Deposit Characterization examination of the
- presence of boron, lithium, surface of J-groove weld and cesium - Nozzle 1 & 46
- No evidence of wastage
- ET from tube ID and of J-
- based on the lack of groove weld surface discoloration of the boric - 8 other nozzles acid deposits
- the small amount of boric
- ET of J-groove weld acid accumulation. surface 2 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
South Texas Project Unit 1 Inspection Results
- 3 axial indications
- One leak path (through wall)
- No crack-like indications on J-groove weld
- Visual grinding marks in side of tube
- Two axial indications
- One leak path (through wall)
- No crack-like indications on J-groove weld 3 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
STP-1 Planned Additional Testing & Repairs
- Visually examine inside bore #1 and #46
- Perform after nozzle capped and separated
- Possibly detect irregularities
- Look for known through wall flaw in #1
- ECT profilometry of #1 and #46
- Metallurgical analyses of removed nozzle ends
- Boat samples from #1 and #46 flaw zones
- Nozzle #1 and #46 will be repaired with half nozzle repair
- Volumetrically interrogate vessel base metal for wastage
- Root Cause expected in October 2003
- Probable Cause in July 2003 4 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
BMI Inspections in Industry
- Approximately 12 plants perform visual inspections of BMIs every refueling outage.
- 15 additional plants have performed visual inspection of BMIs either in the Fall or Spring refueling outages
- MRP recommending that all plants with BMIs perform visual inspections for future refueling outages
- EDF has performed 16 volumetric and surface inspections
(> 500 nozzles) at 12 units since 1992.
- No cracking has been discovered.
- Some inspections have been performed at other units in Europe and Japan.
- One ID indication recently reported in Japan 5 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
Industry Actions
- MRP working with the Owners Groups to develop the strategy to address possible degradation of BMIs.
- Ensure safe operation of plants with BMIs
- Determine the appropriate inspection type and frequency for BMIs
- Possible elements: LOCA analysis, FMEA, Risk Assessment, Stress Analysis, etc.
6 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
Current Recommendation from MRP
- During the current or next refueling outage, a bare metal visual examination of any Alloy 600 nozzles penetrating the bottom head of the reactor vessel be performed.
- Plants whose design significantly impedes access to perform the recommended examinations should initiate expedited actions, up to and including physical modifications, to allow implementation of the recommendation at the earliest possible scheduled outage opportunity.
- Non-visual NDE may ultimately be a prudent and necessary component in a comprehensive inspection plan to fully evaluate the condition of the BMI population of an RPV, particularly following visual detection of a leak.
- Will re-evaluate these recommendations following issuance of root cause by STPNOC.
7 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
Near- Term Owners Group Activities
- WOG IRG has authorized Reasonable Assurance of Continued Operation for Westinghouse and CE Fleet
- Will be completed shortly
- complete 8 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
IMI Nozzle SBLOCA Analyses for B&W-Designed Plants M. A. Schoppman 6/12/03
B&W Plant IMI SBLOCA Analyses
- Framatome ANP performed two SBLOCA analyses for each plant type with a break area of
- Inside diameter of the IMI tube with incore ejected (0.0021 ft2), and
- The RV IMI nozzle vessel bore inside diameter with incore ejected and nozzle not obstructing the break flow area (0.0060 ft2).
10 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
B&W Plant IMI SBLOCA Conclusions
- Any break of a single IMI nozzle at a B&W-designed plant would produce results that remain within the 10 CFR 50.46 acceptance criteria.
- Operator initiated steam generator cooldown improves ECCS delivery. SG depressurization also creates primary side condensate that augments the HPI flow. These contributions increase the minimum core mixture level (decrease PCT) for the largest IMI nozzle break.
11 Copyright © 2003 Electric Power Research Institute, Inc. All rights reserved.
