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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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 31,2012 LICENSEE: STP Nuclear Operating Company FACILITY: South Texas Project, Units 1 and 2
SUBJECT:
SUMMARY
OF MARCH 29, 2012, PRE-LICENSING PUBLIC MEETING WITH STP NUCLEAR OPERATING COMPANY HELD VIA CONFERENCE CALL TO DISCUSS THE PROPOSED RISK-INFORMED APPROACH TO THE RESOLUTION OF GSI-191, "ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE" (TAC NOS. ME7735 AND ME7736)
On March 29, 2012, a public meeting was held via conference call between the U.S. Nuclear Regulatory Commission (NRC), and representatives of STP Nuclear Operating Company (STPNOC, the licensee), at NRC Headquarters, Rockville, Maryland. The meeting notice and agenda, dated March 15, 2012, is located in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML120740031. The purpose of the meeting was to discuss the proposed risk-informed approach to the resolution of Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on PWR [Pressurized-Water Reactor]
Sump Performance." South Texas Project (STP) is the lead plant and STPNOC plans to submit a license amendment request before the end of the year. The licensee previously provided an overview of its proposed approach during the public meetings held on June 2, July 7, July 26, August 22, October 3, November 1, November 2, and December 1, 2011, and February 9, March 1, and March 8, 20121. The purpose of this conference call was to discuss GSI-191 bypass testing and head-loss protocols and plans for the STP pilot program (follow-up discussion from the meeting on March 1, 2012) and resolution of the outstanding chemical effects phenomena identification and ranking table (PIRT) issues.
A list of meeting attendees is provided in the Enclosure to this meeting summary.
Meeting Summary The discussion was based on the following previously provided meeting materials/handouts and no additional meeting materials were provided for the purposes of this meeting.
- 1. STP Corrosion Head Loss Experiments (CHLE) Test Plan (Working Draft), Revision 1.2, dated February 29,2012 (ADAMS Accession No. ML120610074)
- 2. Resolution of Outstanding Chemical Effects PIRT Issues by Kerry Howe, February 9, 2012 (ADAMS Accession No. ML120540727)
Summaries of the meetings held on June 2, July 7, July 26, August 22, October 3, November 1, November 2, and December 1, 2011, and February 9, March 1, and March 8, 2012, are available in ADAMS Accession Nos. ML111640160, ML111950094, ML112130165, ML112411419, ML112840114, ML113120129, ML113180196, ML113430087, ML120620541. ML120830103, and ML120830086, respectively.
- 2 Results of Discussions STPNOC asked if the NRC staff had additional comments on the fiber bypass and vertical loop test procedures discussed during the call on March 8,2012. The NRC staff stated that they did not have additional comments.
The NRC staff and licensee discussed item 2, "Resolution of Outstanding Chemical Effects PIRT Issues." STPNOC provided an updated copy of the document dated March 28, 2012, just before the meeting. The NRC staff clarified that the discussion during the meeting would be based on the version dated February 9, 2012, since the NRC staff was not able to review the contents of the version dated March 28, 2012. The NRC staff also reiterated its expectation that materials intended to be discussed during the meetings need to be provided in sufficient time for the staff to review and discuss internally before the meeting. For sake of efficiency, the NRC and STPNOC had agreed previously that the meeting materials will be provided at the time the meeting request is made and last-minute updates may require rescheduling of the meeting.
Highlights from discussions related to the Chemical Effects PIRT Issues document follow:
- The NRC staff had no additional comments on PIRT items 1.3, 2.3, 4.1, 4.4, 6.3, and 7.1 during the previous meeting. These items were not discussed during the meeting on March 29, 2012.
- Based on its review of the document provided, the NRC staff indicated that it had no additional comments for PIRT items 1.4, 1.5,3.2,3.3,3.4,3.8,3.9,3.10,3.11, 4.5, 5.1, and 7.2.
- For item 1.1, "RCS Coolant Chemistry Conditions at Break" and Item 1.2, "pH Variability," the NRC staff and the licensee expressed general agreement that testing should occur at representative pH values and consider pH variability. The staff indicated that it would like to know more details about pH used during the test and pH variation as a function of time, particularly since there is a range of pool pH that can occur following a loss-of-coolant accident (LOCA) and the pH is a key factor in material corrosion rates and species solubility. The licensee stated that alternate source term-related calculations predicted the sump pool pH at STP to decrease by approximately 0.15 pH units over time due to post-LOCA acid formation. The NRC staff expressed the view that the licensee should account for the expected drop in the value of pH during testing.
- For item 2.1, "Radiolytic Environment," and item 2.2, "Radiological Effects Corrosion Rate Changes," the licensee indicated that it would be adding both nitric acid and hydrochloric acid later to the test loop to simulate post-LOCA acid formation. The NRC staff expressed the view that adding both acids would be acceptable since analysis indicates both acids could form in the post-LOCA environment.
- For item 2.5, "Additional Debris Bed Chemical Reactions," the NRC staff indicated that additional discussion would be needed concerning potential radiation effects on plant debris such as non-qualified coatings and microtherm.
The licensee agreed to discuss this matter during future meetings.
- 3
- For item 3.1, "Crud Release," the NRC staff stated that additional discussion would be needed to determine if simulated crud should be included as a particulate source in some of the chemical tests. The licensee agreed to discuss this matter during future meetings.
- For item 3.5, "Containment Spray Transport," the NRC staff questioned whether, after the sprays are secured, the CHLE tank tests would dry the materials above the water line more than in a plant that experienced a LOCA. The NRC staff questioned whether the 30-day test wetting of coupons located above the water level in the CHLE tank would be representative of postulated plant conditions.
- For item 3.6, "Initial Debris Dissolution," the NRC staff stated that the initial debris dissolution is a critical part of the experiments. Previous NRC staff comments related to the use of extra coupons in lieu of testing at the highest projected post LOCA temperatures are contained in the summary of the phone call on March 8, 2012. Since the temperature can influence other reaction processes in addition to leaching rates, the NRC staff is interested to know how (e.g., bench tests) the licensee will confirm that the extra coupon approach will produce representative amounts of dissolved materials.
- For item 3.7, "Submerged Source Terms: Lead Shielding," the licensee indicated that lead blankets in STP containments are either in barrels that would protect the blanket from a break zone of influence or are sealed from post-LOCA fluid by vinyl covers. STPNOC does not plan to include lead in the 30-day CHLE tests.
However, the NRC staff expressed the view that the licensee should include lead in the bench tests.
- For item 3.12, "Submerged Source Terms: Biological Growth in Debris Beds,"
during its review of licensees' responses to NRC Generic Letter 2004-02, the NRC staff noted that at least one plant indicated the presence of biological material in a wet sump in containment. The NRC staff, therefore, expects the licensee to verify that it does not have an eXisting source term of biological material in containment.
- For Item 3.13, "Reactor Core: Fuel Deposition Spalling" the licensee stated that the PWROG developed a generic method to evaluate deposit formation (LOCADM) would be used at STP. In addition, the precipitation of materials with retrograde solubility will be addressed in bench scale testing based on plant-specific parameters. The NRC staff stated that the proposed approach is acceptable.
- For item 4.2, "Heat Exchanger: Solid Species Formation," the licensee stated that the CHLE test would include a heat exchanger loop to simulate the temperature drop that occurs as emergency core cooling system (ECCS) flow passes through a heat exchanger prior to entering the reactor vessel. The NRC staff expressed the view that it would be worthwhile to visually inspect the heat exchanger for evidence of precipitates after each 30-day test.
- 4
- For item 4.3, "Reactor Core: Precipitation," the NRC staff and licensee discussed whether some high-temperature autoclave tests would be needed to address precipitates that may form due to retrograde solubility. The NRC staff stated that licensee should evaluate for materials that could exhibit retrograde solubility.
- For item 6.1! "Break Proximity to Organic Sources," and item 6.2, "Organic Agglomeration," the NRC staff and licensee agreed to have additional discussions concerning the potential role of organic materials. The licensee stated that it is evaluating various options to address the issue.
- For item 6.4, "Coating Dissolution and Leaching," the NRC staff expressed the view that licensee should evaluate whether non-qualified coating degradation could impact plant-specific chemical effects. The NRC staff and licensee agreed to re-visit this issue during a future meeting.
- Item 7.3, "Reactor Core: Fuel Deposition and Precipitation," item 7.4, "Reactor Core: Diminished Heat Transfer," item 7.5, "Reactor Core: Blocking of Flow Passages," and item 7.6, "Reactor Core: Particulate Settling," are issues related to reactor core such as debris blockage, and heat transfer and are beyond the scope of the CHLE experiments. The licensee agreed to address these items using a combination of pressurized-water reactor owners group (PWROG) developed methods (e.g., LOCADM to evaluate fuel rod deposition) and plant specific testing/analysis.
- The licensee asked if the NRC staff had any major concerns or questions regarding the overall test approach. The licensee indicated that it was in the process of procuring materials for the test and any additional NRC staff input will be valuable. The NRC staff did not identify any major concerns to the overall approach for the chemical tests. The NRC staff suggested that more interaction may be needed after the test setup details became available to the NRC staff.
- The NRC staff acknowledged that the licensee's plans to conduct a series of tests to force precipitation has merit, since they would provide some indication of the conditions that would result in chemical precipitate formation. The licensee stated that the forced precipitation tests would include calcium sources to evaluate the potential formation of calcium phosphate precipitate.
- The NRC staff noted that standard practices (e.g., American Society for Testing and Materials (ASTM) G1, "Standard Practice for Preparing, Cleaning, and Evaluating Corrosion Test Specimens") are available for preparing, cleaning, and evaluating corrosion test specimens. These practices are designed to remove corrosion products without significant removal of base metal to allow accurate determination of mass loss.
- The NRC staff noted that the description provided in Section 2.2, "Bench-Scale Laboratory Tests," of Appendix B to the "STP Corrosion Head Loss Experiments (CHLE) Test Plan" document was incomplete. The staff plans to review this
- 5 section and provide comments once the licensee provides a more complete description.
No Public Meeting Feedback Forms were received for this meeting.
Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov.
Sincerely, b~ ',-,- I~t ~'a9-Balwant K. Sing ai, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATTENDEES MARCH 29, 2012, MEETING WITH STP NUCLEAR OPERATING COMPANY REGARDING RISK-INFORMED APPROACH TO RESOLUTION OF GSI-191 ISSUE SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 NAME TITLE ORGANIZATION Rick Grantum** Manager Risk Project STPNOC Ernie Kee** Risk Management STPNOC Wes Schulz** - STPNOC Jamie Paul** Licensing Engineer STPNOC Rodolfo Vagetto*'" - Texas A&M University Zahra Mohaghegh** - Soteria Consultants Craig Sellers - CDS Tim Sande*'" Principal Engineer Alion Science and Technology David Johnson** - ABS Consulting Kerry Howe*'" - University of New Mexico Janet Leavitt** - University of New Mexico Alex Galenko - University of Texas Gil Zigler* Senior Scientist/Engineer Alion Science and Technology William Closser Assistant Vice President/Divisional Alion Science and Technology Manager Phillip Grissom*"'* - Southern Nuclear Company Michael Snodderly Senior Reliability and Risk Engineer U.S. Nuclear Regulatory Commission (NRC)
Mark Blumberg Senior Reliability and Risk Analyst NRC Donnie Harrison Branch Chief NRC Lynnea Wilkins Project Manager NRC Paul Klein Senior Materials Engineer NRC Stewart Bailey Branch Chief NRC Steve Smith Reactor Systems Engineer NRC Ervin Geiger Senior Engineer NRC
- Participated via phone and represented STPNOC
- Participated via phone Enclosure
ML121380522 *Via E-mail OFF I NRRlLPL4/LA NRR/DRAlAPLAlBC NAME JBurkhardt* DHarrison 5/18/12 N/A NRR/DE/ESGB C NRR/LPL4/BC NRRlLPL4/PM NAME GKulesa SBailey* MMarkley BSingal DATE 5/24/12 5/24/12 5/31/12 5/31/12