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Administration
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Results
Other: ML120540570, ML120540610, ML120540667, ML120540727, ML120540816, ML120610068, ML120610074, ML120610102, ML12145A438, ML12145A466, ML12335A174, ML12335A177
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MONTHYEARML1200901012012-01-10010 January 2012 Notice of Forthcoming Public Meeting Via Conference Call with South Texas Project Nuclear Operating Company Project stage: Meeting ML1204400602012-01-26026 January 2012 Summary of January 12, 2012 Chemical Effects Meeting Project stage: Request ML1203003642012-02-0202 February 2012 3/8/12 Forthcoming Meeting by Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, U Project stage: Meeting ML1203400432012-02-0303 February 2012 Notice of Forthcoming Meeting Via Conference Call with STP Nuclear Operating Company Project stage: Meeting ML1204400612012-02-0808 February 2012 Email Licensee Slides for 2/9/12 Public Meeting Via Conference Call Project stage: Meeting ML1205407272012-02-0909 February 2012 Actions Taken to Resolved Pirt Items Project stage: Other ML1204400652012-02-0909 February 2012 Licensee Slides for 2/9/12 Meeting Regarding GSI-191 Project stage: Meeting ML1205406672012-02-22022 February 2012 Casa Grande Summary Project stage: Other ML1205405092012-02-22022 February 2012 Email Meeting Materials for March 1, 2012 Conference Call Project stage: Meeting ML1205406102012-02-22022 February 2012 Email Casa Grande Summary Project stage: Other ML1205406942012-02-22022 February 2012 Email Additional Meeting Materials for the 3/01/12 Meeting to Discuss GSI- 191 Project stage: Meeting ML1205407582012-02-22022 February 2012 STP Summary of January Meeting Project stage: Meeting ML1205405572012-02-22022 February 2012 Licensee Slides for 03/1/12 Meeting with STP Nuclear Operating Company Meeting to Discuss GSI-191 Project stage: Meeting ML1205405702012-02-22022 February 2012 Uncertainty Modeling of LOCA Frequencies and Break Size Distributions for the STP GSI-191 Resolution Project stage: Other ML1205406042012-02-22022 February 2012 Meeting Materials for 3/1/12 Conference Call Project stage: Meeting ML1205408162012-02-23023 February 2012 Experimental Setup for Chle Test Equipment Project stage: Other ML1205407842012-02-23023 February 2012 Email Documents Transmitted for March 1, 2012 Meeting Project stage: Meeting ML1206100682012-02-28028 February 2012 Southtexas Project, Units 1 and 2 - Test Plan for STP High Temperature Vertical Loops Testing Project stage: Other ML1206100632012-02-29029 February 2012 Intro for March 8, 2012 Public Meeting to Discuss GSI-191 Project stage: Meeting ML1206101022012-02-29029 February 2012 Proposed STP Strainer Fiber Bypass Test Protocol Project stage: Other ML1206100742012-02-29029 February 2012 Corrosion Head Loss Experiments Test Program Project stage: Other ML1206205412012-03-0606 March 2012 2/9/12 Summary of Meeting by Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Un Project stage: Meeting ML1207400312012-03-15015 March 2012 3/29/12 Notice of Meeting Viaconference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for Units 1 and 2 Project stage: Meeting ML1208300862012-03-29029 March 2012 Summary of Meeting by Conference Call with STP Nuclear Operating Co. to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Units 1 & 2 Project stage: Meeting ML1208301032012-03-30030 March 2012 3/1/12 Summary of Meeting by Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Un Project stage: Meeting ML1210800062012-05-0404 May 2012 Staff Comments and Questions Related to Review of STP Nuclear Operating Company'S Report Entitled, Risk-Informed Resolution of GSI-191 at South Texas Project, Discussed at Public Meeting on 3/1/12 (TAC ME7735-36) Project stage: Meeting ML12145A4382012-05-18018 May 2012 Licensee Handout on Calibration and Benchmarking of Single and Two-Phase Jet Cfd Models Project stage: Other ML12145A3122012-05-18018 May 2012 E-mail Documents for Public Meeting on LOCA Frequency and Jet Formation Project stage: Meeting ML12145A4662012-05-18018 May 2012 Loca-Hybrid-Final Project stage: Other ML12146A0202012-05-31031 May 2012 Notice of 6/11/12 Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Unit Project stage: Meeting ML1213805222012-05-31031 May 2012 3/29/12 Summary of Conference Call Meeting with STP Nuclear Operating Company, Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Units Project stage: Meeting ML12187A0812012-07-11011 July 2012 Summary of 6/11/12 Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Uni Project stage: Meeting ML12234A6042012-08-21021 August 2012 Email - Documents for NRC Public Meeting on Corrosion Head Loss Experiments (Chle) Part 1 and 2 Project stage: Meeting ML12227A5902012-08-23023 August 2012 9/6/2012 Notice of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Uni Project stage: Meeting ML12243A4742012-08-30030 August 2012 Email - Risk-Informed Approach to GSI-191, STP Cfd Data Analysis Report - Bypass Test Protocol Project stage: Acceptance Review ML12261A3012012-09-21021 September 2012 Notice of Forthcoming Public Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach Project stage: Meeting ML12270A0552012-10-0404 October 2012 9/6/2012 Summary of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Un Project stage: Meeting ML12300A2972012-11-0808 November 2012 Summary of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Units 1 and Project stage: Meeting ML12321A1222012-11-20020 November 2012 12/3/12 Notice of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Unit Project stage: Meeting ML12335A1902012-11-26026 November 2012 Licensee Documents for December 12, 2012 Public Meeting Project stage: Meeting ML12335A1842012-11-26026 November 2012 Licensee Documents for December 12, 2012 Public Meeting Project stage: Meeting ML12335A1772012-11-26026 November 2012
- Licensee Documents ALION-CAL-STP for 12-10-12 Public Telecon GSI-191
Project stage: Other ML12335A1742012-11-26026 November 2012 Email Licensee Documents for 12-10-12 Public Telecon GSI-191 Project stage: Other ML12331A2922012-11-27027 November 2012 Notice of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Units 1 and Project stage: Meeting ML12340A1352012-11-27027 November 2012 Meeting Notice by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution South Texas Project, Units 1 and 2 Project stage: Meeting ML12341A1702012-12-20020 December 2012 12/3/12 Summary of Meeting by Conference Call with STP Nuclear Operating Company; Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Uni Project stage: Meeting ML13004A4012013-01-31031 January 2013 Summary of Meeting by Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas, Units 1 & Project stage: Meeting 2012-02-08
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Category:Meeting Summary
MONTHYEARML22252A0432022-09-12012 September 2022 Summary of August 31, 2022, Webinar with STP Nuclear Operating Company to Discuss a Proposed LAR to Revise the Dose Consequence Analysis for Main Steam Line Break and Locked Rotor Analysis Events for STP, Units 1 & 2 ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21236A3082021-09-10010 September 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Moderator Temperature Coefficient Surveillance Requirements 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 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML20279A8152020-10-20020 October 2020 Summary of September 14, 2020, Presubmittal Teleconference with STP Nuclear Operating Company Regarding the Proposed LAR to Revise the Moderator Temperature Coefficient Surveillance Requirement for South Texas Project, Units 1 and 2 (EPID L ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML20163A5522020-06-12012 June 2020 Summary of April 21, 2020, Teleconference with STP Nuclear Operating Company to Discuss the License Amendment Request to Revise the Emergency Plan for South Texas Project, Units 1 and 2 ML20140A2612020-05-27027 May 2020 May 5, 2020, Summary of Teleconference with STP Nuclear Operating Company to Discuss a Proposed Exigent License Amendment Request to Revise the Pressure of the Safety Injection Accumulators for South Texas Project, Unit 1 ML20107J5482020-04-15015 April 2020 Teleconference Regarding NRC Observations on the March 30, 2020, License Amendment Request to Revise the Emergency Plan STP Nuclear Operation Company South Texas Project, Units 1 and 2, Dockets 50-498 and 50-499 ML20049A0572020-02-26026 February 2020 Summary of February 6, 2020, Meeting with STP Nuclear Operating Company to Discuss a Proposed License Amendment Request to Revise the Emergency Plan for South Texas Project, Units 1 and 2 (EPID L- 2020-LRM-0004) ML19350C5902019-12-17017 December 2019 12/3/19, Summary of Teleconference with STP Nuclear Operating Company to Discuss a Proposed License Amendment Request to Revise the Emergency Plan for South Texas Project, Units 1 and 2, ML19102A0162019-04-16016 April 2019 4/10/2019 Summary of Public Teleconference Regarding Potential Submission of a Relief Request to Allow Use of Carbon Fiber Reinforced Polymer for Selected Piping Repairs at South Texas, Units 1 and 2 ML17005A1002017-01-18018 January 2017 January 4, 2017, Summary of Meeting to Discussion Stp'S Response to Request for Additional Information the Revised Aluminum Bronze Selective Leaching Aging Management Program for All Potentially Susceptible Welds Throughout the Facility ML16279A3312016-10-27027 October 2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) ML16272A4362016-10-14014 October 2016 Summary of Public Preapplication Meeting with STP Nuclear Operating Company to Discuss Possible License Amendment Request to Modify Emergency Response Organization for South Texas Project, Units 1 and 2 ML16246A0222016-10-0505 October 2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items Related to Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400 - MF2409) ML16238A5272016-09-0101 September 2016 Summary of 7/28/16, Public Meeting with STP Nuclear Operating Company to Discuss the License Amendment and Exemption Requests to Use a Risk-Informed Approach to the Resolution of GSI-191 (CAC Nos. MF2400 - MF2409) ML16218A3672016-08-30030 August 2016 07/21/2016 Summary of Public Teleconference Meeting with STP Nuclear Operating Company Discussing Revisions to License Renewal Application Aluminum Bronze Selective Leaching Aging Management Program and Background Document ML16236A0322016-08-23023 August 2016 08/18/2016 Summary of Conference Call With STP Nuclear Operating Company Concerning the Aluminum Bronze Selective Leaching Aging Management Program in the South Texas Project, License Renewal Application ML16236A3042016-08-23023 August 2016 08/11/2016 Summary of Conference Call Between NRC and STP Nuclear Operating Company Concerning the 2016 Annual Update to the South Texas Project License Renewal Application ML16180A0142016-07-25025 July 2016 Summary of Meeting Discussion Between South Texas Project, Units 1 and 2, and NRC Staff Regarding the Revised Aluminum Bronze Selective Leaching Aging Management Program for All Potentially Susceptible Welds Throughout the Facility ML16190A0082016-07-13013 July 2016 Summary of 6/22/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) ML16188A0072016-07-0707 July 2016 Summary of Telecon Held on July 5, 2016 With STP Nuclear Operating Company, Concerning Additional Information Pertaining to the STP, License Renewal Application (TAC. Nos. ME4936, ME4937) ML16188A0112016-07-0707 July 2016 Summary of Telecon Held on July 5, 2016 With STP Nuclear Operating Company, Concerning Additional Information Pertaining to the STP, License Renewal Application (TAC Nos. ME4936, ME4937) ML16188A0092016-07-0707 July 2016 Summary of Telecon Held on July 5, 2016 with STP Nuclear Operating Company, Concerning Additional Information Pertaining to the STP, License Renewal Application (Tac. Nos. ME4936, ME4937) - Enclosure 1 ML16175A1082016-06-24024 June 2016 Summary of 4/21/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 ML16166A0272016-06-14014 June 2016 Summary of Telephone Conference Call Held on 06/08/2016, Between the USNRC and STP Nuclear Operating Company Response to Request for Additional Information B2.1.18-6 Pertaining to the South Texas Project License Renewal Application ML16092A0852016-04-13013 April 2016 3/17/2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2401-MF2409) ML16092A0442016-04-11011 April 2016 Summary of 3/3/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) ML16088A2432016-04-0101 April 2016 2/18/2016, Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) ML16081A2052016-03-24024 March 2016 Summary of Meeting with STP Nuclear Operating Company to Discuss Potential License Amendment Request for South Texas Project, Unit 1 Regarding Permanent Operation with 56 Control Rods ML16074A0412016-03-14014 March 2016 Summary of a Call Held on March 10, 2016, between USNRC and STPNOC, Concerning the Staff's Upcoming Audit Regarding the Amp for the Loss Of Material Due to Selective of Al-Br Welds in the ECW System for the STP LRA (TAC Nos. ME4936 And ME4937) ML16060A1272016-03-0707 March 2016 February 23, 2016, Summary of Conference Calls Held between NRC and STP Concerning Staff's Review of Submerged Closure Bolting Portion of 2014 Annual Update for STP License Renewal Application (TAC ME4936 And ME4937) ML16028A1522016-02-18018 February 2016 1/14/2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Modifications to the Licensee'S Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 ML16035A4802016-02-12012 February 2016 Jsc Meeting Summary Attachment ML16011A0612016-02-0202 February 2016 Summary of 10/1/15 Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 (CAC MF ML16011A0702016-01-28028 January 2016 Summary of Preapplication Meeting with STP Nuclear Operating Company to Discuss Exigent License Amendment Request to Operate Following Removal of a D6 Control Rod at South Texas Project, Unit 1 ML16033A0072016-01-19019 January 2016 January 19, 2016, Summary of Public Meeting with STP to Discuss the Plant-Specific Aging Management Program, Selective Leaching of Aluminum Bronze, Associated with STP's License Renewal Application ML16013A0662016-01-14014 January 2016 Summary of 11/9 and 12/30/15 Conference Calls with STP Nuclear Operating Company to Discuss the Fall 2015 Steam Generator Tube Inspection Activities (CAC No. A11018) ML15308A0112015-11-30030 November 2015 Record of Conference Call on STP Request for Additional Information Set 34 ML15201A0032015-07-30030 July 2015 7/2/15 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 ML15177A1042015-07-21021 July 2015 4/22/2015 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 (TAC MF2400 t ML15177A2742015-07-21021 July 2015 5/6/2015 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 (TAC Nos. MF24 ML15180A2732015-07-15015 July 2015 6/3/2015 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 (TAC MF2400 to ML15139A3442015-06-11011 June 2015 Summary of Telephone Conference Call Held on May 12, 2015 Between the U.S. Nuclear Regulatory Commission and STP Nuclear Operating Company, Concerning Request for Additional Information, Set 31, Pertaining to the South Texas Project, Licens ML15103A0022015-05-13013 May 2015 Summary of 4/8/15 Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 ML15084A0032015-04-0606 April 2015 2/4/15 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Units 1 and 2 (TAC MF2400-MF24 ML15084A0042015-04-0101 April 2015 2/5/2015 Summary of Presubmittal Meeting with STP Nuclear Operating Company to Discuss Integrated Leak Rate Testing Program License Amendment Request for South Texas, Units 1 and 2 ML15020A1062015-02-19019 February 2015 12/1-3/2014 Summary of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas, Unit 1 and 2 (TAC MF2400- 2022-09-12
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Page 1 of 7 STP Post-meeting Notes for January 26-27, 2012 Public Meeting STP Team
Participants:
(in alphabetical order)
- Rick Grantom, PE Nuclear Eng.
o Manager, Risk Management Projects, South Texas Project Nuclear Operating Company o STP/Industry/NRC Coordinator for STP Risk-informed GSI-191 project o 25 years of experience in risk management at a commercial nuclear power plant
- Kerry Howe, PE, Ph.D., BCEE.
o Associate Professor at the University of New Mexico o Corrosion/Head Loss Experimental (CHLE) lead for STP Risk-informed GSI-191 project o 5 years of experience in GSI-191
- Ernie Kee, Mechanical Eng.
o Supervisor, Risk-Informed Applications, at the South Texas Project Nuclear Operating Company o STP Technical Leader for STP Risk-informed GSI-191 project o 14 years of experience in Probabilistic Risk Assessment (PRA) at a commercial nuclear power plant
- Janet Leavitt, Ph.D. in Environmental Eng.
o Post-doc in the Civil Eng. Department at the University of New Mexico o Corrosion/Head Loss Experimental (CHLE) team member of STP Risk-informed GSI-191 o 5 years of experience in GSI-191
- Bruce Letellier, Ph.D. in Nuclear Eng.
o Nuclear Reactor Safety and Risk Analysis at Los Alamos National Lab o CASA lead for STP Risk-informed GSI-191 project o 10 years of experience in GSI-191
- Zahra Mohaghegh, Ph.D. in Reliability Eng.
o Principal Research Scientist at Soteria Consultants o Oversight lead for STP Risk-informed GSI-191 project o 8 years of experience in Probabilistic Risk Assessment (PRA)
- Seyed Reihani, Ph.D. in Mechanical Eng. {teleconference participant}
o Research Scientist at Soteria Consultants o Oversight team member for STP Risk-informed GSI-191 project o 10 years of experience in catalytic combustion
- Tim Sande, M.S. in Petroleum Eng.
o Engineering Supervisor at Alion Science & Technology o Separate Chemical Effects Tests (SCET) lead for STP Risk-informed GSI-191 project o 8 years of experience in GSI-191
Page 2 of 7 Resolutions & Comments
- 1. The interface of CASA Grande and PRA:
Figure (1), on the next page, shows the schematic interrelationship of PRA and CASA Grande in the STP Risk-informed GSI-191 project. The figure does not attempt to cover all PRA scenarios (to avoid complexity with the figure). The main purpose is to present and to clarify the relationship between PRA and CASA Grande.
In the integrated model, developed in this project, PRA is located at the top level of system analysis.
This plant-specific PRA has the typical Power Plant Fault Trees and Event Trees covering hardware failures and operators actions and so, has the typical PRA cut sets.
One important aspect of this project is that CASA Grande provides estimates for the likelihood of three basic events of Fault Trees in PRA:
(1) the sump strainer failure (which leads to emergency core cooling system failure and, ultimately recirculation in the risk scenarios),
(2) fuel assembly differential pressure (which might lead to long-term cooling and ultimately core blockage in the risk scenarios),
(3) fuel pin localized heating (which leads to long-term cooling and ultimately core blockage in the risk scenarios).
In other words, rather than relying solely on historical failure data for these three basic events (something that a typical PRA does), the STP risk-informed project develops the models (in CASA Grande) for the underlying chemical and mechanical phenomena which lead to the three basic events.
The output of CASA Grande will give a more accurate estimate of the likelihood of these three basic events and can then be imported to Fault Trees of the plant-specific PRA in order to calculate CDF.
In view of this, the response to the question/comment about the cut sets in this project would be we have the typical cut sets of Power Plant PRA And the response to the comment on CASA Grande being a black box is that CASA Grande is not a black box but is, in fact, instrumental in opening the black boxes of two important events in the scenarios of a Power Plant PRA (i.e. recirculation and core blockage) by model-based estimations of the likelihood of their underlying basic events.
CASA Grande, in the Risk-Informed GSI-191 project, provides models for the underlying physical phenomena (i.e. mechanical and chemical phenomena) of three basic events in the PRA of power plants. This means that the Risk-Informed GSI-191 project not only contributes toward the closure of the GSI-191 issues, but can also make a contribution toward PRA research and applications. It can improve the scientific incorporation of underlying physical failure mechanisms into PRA, an important topic of interest in the PRA field.
Page 3 of 7 Fig1. The schematic representation of PRA & CASA Grande in the STP Risk-Informed GSI-191 project
Page 4 of 7
- 2. Chemical Effects PIRT Issues The NRC Phenomena Identification and Ranking Table (PIRT) was reviewed and general agreement was obtained regarding the items that need to be addressed in the realistic chemical effects testing.
Some items requiring further study are summarized in the following paragraphs:
- 1. Item 2.5 (Root issue 2, Radionuclides trapped in the debris bed may cause the bed to break down):
Paul Klein noted that there is a knowledge base of fiberglass debris beds, but questioned whether there are other materials (such as paint or other non-fibrous insulation materials) that could break down in a debris bed. This needs to be further investigated to verify that there is no effect from these contributors.
- 2. Item 3.1 (Root Issues 1 and 2, The crud may influence the localized radiolytic environment and A significant quantity of crud could be released as another source of particulate debris):
The first root issue is directly related to PIRT Item 2.5. The second root issue is a question of the quantity of crud particulate that would be released by the LOCA shock, and how much of it would transport to the strainer. Steve Smith noted that crud is an immediate source term, with no delay for crud appearance. Rob Tregoning noted that if the amount of particulate is reduced, then crud becomes more of a consideration (it may need to be included for cases with lower particulate concentrations). It was also noted that considerations of transport based on the break location are important. The quantity of crud that could be generated and transported to the strainers should be evaluated to determine whether this is a significant factor that needs to be considered in a realistic analysis.
- 3. Item 3.8 (Root Issues 2 and 3, Dissolved copper can enhance the corrosion rate of other metals by forming local galvanic cells and Copper can inhibit corrosion of other metals by depositing and creating a passivation layer):
Root Issue 2 is the only thing to be concerned with in the CHLE experiments. The third root issue (passivation of aluminum by copper) is not considered to be a realistic phenomenon.
Zinc was not included in the PIRT, but needs to be considered in a similar way as with lead and copper. Paul Klein noted that lead and copper would be plant specific issues. They could likely be addressed in bench top experiments. It was noted that the STP Units 3 & 4 team had several discussions with NRC on Zinc issues.
- 4. Item 3.9 (Root Issue 1, Aged concrete may release a larger quantity of calcium):
Paul Klein stated that aging of concrete does not need to be considered. There was general agreement that this issue does not need further consideration.
- 5. Item 3.12 (Root Issue 1, Biological growth in the post-LOCA environment may contribute to clogging issues):
The NRC (and some industry representatives) did not necessarily agree that biological growth is negligible in the post-LOCA containment pool. This issue needs additional evaluation to determine whether it is significant.
Page 5 of 7
- 6. Items 5.1/6.2 (Root Issue 1, Agglomeration of chemical precipitates, insulation particulate, and/or latent particulate may form larger particles that would be more easily captured in a debris bed and Organic agglomeration may form larger particles which would be more easily captured in a debris bed):
NRC agreed that this is probably not an issue, but may be important if chemical precipitates are amorphous. More thought needs to be put into this issue to determine whether it is significant or not.
- 7. Item 6.1 (Root Issues 1 and 2, Certain breaks may result in a significant quantity of oil being released into the containment pool and Other organic materials may be present due to failure of coatings and the organic binders in insulation debris):
Previous integrated chemical effects head loss testing where oil was added did not show any effect from the oil. Rob Tregoning felt that the results of the tests with oil were not clear because there was no differential test to compare against. The oil was poured in after the bed was formed, and particulates were still in solution. Additional plant-specific analysis may be required to address this issue. Matt Edwards indicated that AECL may have test data that could be used for this.
There was additional discussion on the chemical effects due to leaching from coatings. Matt Yoder stated that qualified coatings in general don't leach, but unqualified coatings could leach various materials. However, qualified coating debris (generated inside the ZOI) may be an important factor for leaching due to the significantly higher surface area for failed coatings. There was general agreement that intact qualified coatings or failed epoxy paint chips do not need to be considered for leaching.
Additional analysis is required to address organic materials. The issue of RCP motor oil does not appear to be a significant concern, but for that, more thought will need to be given prior to testing. Also coating leach rates need to be addressed based on previous tests and/or new bench top tests.
- 8. Item 7.2 (Root Issue 1, Precipitation within the heat exchanger may affect the heat exchanger performance):
There was general agreement that the clogging of the heat exchanger is not likely to be a significant issue. However, Rob Tregoning indicated that a post-test inspection of the heat exchanger (to see if there is any significant precipitation) would be a good idea.
- 3. The Status of LOCA Frequency LOCA frequencies should be derived based on a top down rather than the bottom up process used in the initial quantification. The document Partitioning of the NUREG-1829 LOCA frequencies for the STP GSI-191 resolution by Alexander Galenko and Elmira Popova provides a description of the top down methodology we propose to use in CASA Grande. We are currently arranging a public meeting/teleconference to discuss the methodology with the NRC staff during the week of 27 February.
Page 6 of 7 The current STP PRA (Revision 6) uses LOCA frequencies defined in NUREG/CR 5750; however, the model under review for release in 2012 uses NUREG 1829 frequencies as a basis. We intend to use the updated (NUREG 1829) frequencies as the branch LOCA frequencies in the final quantification.
- 4. Chemical Effects Experimental Issues The following items were discussed or need follow-up:
- 1. What is basis for test duration? Would we have an acceptance criterion for the duration of tests (for example, stable head loss or other criteria?)
- 2. Will the recirculation time be simulated? Recirculation time is a secondary effect. We will be primarily concerned with the velocity through test sections.
- 3. We plan to simulate the nominal temperature histories for three different representative scenarios (nominally, Small, Medium, Large LOCA).
- 4. Will the filter surface area to tank volume be a scaling parameter? Will the strainer area be matched to the volume in the plant?
- 5. In the event differential pressure begins to increase on the debris beds, we will continue to record the pressure. However, the bed will remain in the test section until the end of the test.
- 6. We need to ensure that no fines in the tank get transported to the debris beds. In post test analysis, we need to check any debris left in the tank for preferential deposition.
- 7. The water to be used in the CHLE experiments will have the as-operated plant chemistry.
- 8. We will use a reservoir in the CHLE experiments to make sure the residence times between the heat exchanger and the debris bed are similar to that in the plant.
- 9. Retrograde solubility will be addressed in separate tests (to account for boron precipitation and core deposition).
- 10. The most critical parameter for the heat exchangers is the temperature change. A secondary consideration is the residence time.
- 11. The coupons will be carefully placed to ensure they are wet during the spray-down phase.
- 12. We do not plan to use WCAP precipitate to evaluate debris bed performance.
- 13. We need to ensure PH effects are incorporated in the experiment design.
- 14. Zinc will be considered. Inventories of materials either excluded or under consideration will be listed for consideration in testing.
- 15. We will prepare the fiber in accordance with the new NEI debris preparation protocol.
- 16. We will evaluate the use of coupon weight loss in CASA Grande correlations. We will investigate different protocols (such as ASTM) for removal of the oxide layer.
- 17. The purpose for the long-term and short-term tests will be provided.
- 5. Boron Precipitation Boron precipitation, separate from Chemical Effects, will now need to be directly addressed in GSI-191 analyses. It does not appear that boron precipitation will be a concern for a hot leg break with hot leg injection. For a cold leg break with hot leg injection, or a hot leg break with cold leg injection, it does not appear that boron precipitation will be a concern as long as the flow through the core exceeds the boil-off rate by at least 10%. For a cold leg break with cold leg injection it does not
Page 7 of 7 appear that boron precipitation will be a concern as long as there is less than 15 g of fiber per fuel assembly present in the core.
- 6. Bypass The two critical parameters to evaluate the impact of by-pass fiber on the core are the quantity of fibers that by-pass the ECCS sump screen and the characteristics, i.e. the size distribution, of the bypass fibers. Both parameters are highly dependent on the assumptions of the quantity and characteristics of the fiber reaching the strainer. The fiber characteristics used in all fuel testing performed to date by the PWROG have been based on fiber size distribution presented at the 9/23/2008 ACRS. The average fiber by-pass size distribution presented at the ACRS meeting was:
< 500 m 500 - 1000 m > 1000 m 76.5% 17.9% 5.6%
There is evidence from other recently performed by-pass tests that the by-pass fiber characteristics tend to the longer fibers. Longer fibers will more readily bridge gaps than shorter fibers. These recent tests were performed with debris preparation methods in conformance with the NRC March 2008 guidance. Recently the NEI has issued a debris preparation method that is undergoing review by the NRC. Discussions with NEI indicate that the NRC will shortly issue a note endorsing the use of the NEI debris preparation method. Any new fuel testing should be done with fibers characteristics based on by-pass testing performed with the NEI fiber debris preparation methodology.
- 7. Schedule of the Project The current milestones of the project are:
- 9 February: Public Meeting to discuss CHLE experimental design.
- Month of February: Procure basic materials for experimental apparatus and begin construction of CHLE loop as described at the 01/26-01/27 Public Meeting (NEI Chemical Effects).
- Week of 27 February: Revised LOCA frequency methodology.
- 5 March: Public meeting on bypass and head loss experimental design.
- Month of March: Procurement and construction.
- Month of April: Shakedown of facility.
- Month of May: Conduct baseline 30-day CHLE experiment.
- Month of July: Conduct first CHLE 30-day experiment for LOCA simulation.