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Category:Graphics incl Charts and Tables
MONTHYEARML22033A5442022-02-0202 February 2022 Inservice Inspection Summary Report -1RE23 ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. ML13323B2042013-01-22022 January 2013 Attachment 9: CHLE-016, Rev. 2, Calculated Material Release to Estimate Chemical Effects. ML13323B2012013-01-22022 January 2013 Attachment 7: CHLE-014, Rev. 2, T2 LBLOCA Test Report. ML13323B2022013-01-15015 January 2013 Attachment 8: CHLE-015, Rev. 3, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal. ML13323B2002013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Figure 53 Through End ML13323B1992013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Cover Through Figure 52 ML13323B1982012-08-19019 August 2012 Attachment 5: CHLE-010, Rev. 2, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition. ML13323B1912012-08-14014 August 2012 Attachment 2: CHLE-006, Rev. 1, STP Material Calculations. NOC-AE-13003040, Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test.2012-08-13013 August 2012 Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test. ML13323B1942012-08-11011 August 2012 Attachment 3: CHLE-007, Rev. 3, Debris Bed Requirements and Preparation Procedures. ML13323B1962012-06-12012 June 2012 Attachment 4: CHLE-008, Rev. 3, Debris Bed Preparation and Formation Test Results. 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 ML1112504292011-04-26026 April 2011 Annual Environmental and Annual Radiological Environmental Operating Reports, Part 2 of 2 ML1019004182010-06-28028 June 2010 Quick View Chart ML1005413692010-01-0505 January 2010 TS Pages from Licensee ML0930200982009-10-29029 October 2009 Summary of Meeting with STP Nuclear Operating Company, Licensee for South Texas Project, Units 1 and 2, to Discuss Experience with Implementation of Risk-Managed Technical Specification Pilot Amendment (Initiative 4b) and Other Initiatives ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists NOC-AE-06001960, Inservice Inspection Summary Report2006-01-19019 January 2006 Inservice Inspection Summary Report ML0426502472004-09-13013 September 2004 One Page from 033004 Open Items Table Riv Fire Protection ML0426100732004-09-13013 September 2004 One Page from the Open Items Table CY-02-012, Project Response to AIF Generator Survey2002-02-28028 February 2002 Project Response to AIF Generator Survey 2022-02-02
[Table view] 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
[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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 29, 2009 LICENSEE STP Nuclear Operating Company FACILITY South Texas Project, Units 1 and 2 SUB~IECT:
SUMMARY
OF SEPTEMBER 29,2009 MEETING WITH REPRESENTATIVES OF STP NUCLEAR OPERATING COMPANY, LICENSEE FOR SOUTH TEXAS PROJECT, UNITS 1 AND 2, REGARDING LICENSEE'S RISK-INFORMED PERFORMANCE-BASED PROGRAMS On September 29,2009, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of STP Nuclear Operating Company (STPNOC), the licensee for South Texas Project (STP), Units 1 and 2, at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the status, lessons learned, and get feedback for the following programs.
- Risk Managed Technical Specifications
- Exemption from special treatment requirements
- Risk-informed safety sulture
- Proposed exemption from the work-hour requirements in 10 CFR Part 26 The licensee described the lessons learned from Risk Managed Technical Specifications (RMTS) program, Surveillance Frequency Control Program (SFCP), and Exemption from Special Treatment Requirements. The licensee also discussed the Risk-Informed Safety Culture at STP, Units 1 and 2, and how the alignment of the programs focuses attention to safety, and improves decision-making.
-2 The NRC staff expressed appreciation for the licensee's presentation. and the staff from the NRC Technical Specifications Branch, Probabilistic Risk Asse.ssment Licensing Branch, and Fire Protection Branch shared insights from the NRC's experience in risk-informed activities. A list of attendees is provided in Enclosure 1. The licensee's presentation viewgraphs are provided in Enclosure 2.
The meeting notice and agenda for this meeting are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML092570390. There was one member of the public in attendance. No Public Meeting Feedback forms were submitted related to the meeting.
Ifthere are any questions or comments, please contact me by telephone at 301-415-1476 or by electronic mail at Mohan.Thadani@nrc.gov.
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Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosures:
- 1. List of Attendees
- 2. Licensee presentation cc w/encls: Distribution via Listserv
LIST OF ATrENDEES MEETING WITH STP NUCLEAR OPERATINQ COMPANY Tuesday. September 29. 2009 2:00 p.m. - 5:30 p.m.
NAME AFFIIJATION Mohan Thadani NRC/NRRlDORLlLPL4 Michael Markley NRC/NRRlDORLlLPL4 Gerald Waig NRC/NRRlDIRS/lTSB Robert Elliott NRC/NRRlDIRS/ITSB Steven A. Laur NRC/NRRlDRA A. Wayne Harrison STPNOC Rick Granton STPNOC Jin Chung MNES Donnie Harrison NRC/NRRlDRA/APLA Andrew Howe NRC/NRRlDRA/APLA Michael Boggi NRC/NRRlDIRS/IHPB Daniel M. Frumkin NRC/NRRlDRAlAFPB Enclosure 1
I ) ~
STPNOC Risk Informed, Performance Based Programs Where we've been.
Where might we go?
Rick Grantom - Manager, Risk Management Wayne Harrison - Manager, Licensing September 29, 2009 Enclosure 2
Desired Outcomes
- Discuss with NRC the status, feedback, and lessons learned for the following risk informed programs
- Risk Managed Technical Specifications
- Configuration Risk Management (48)
- Exemption from Special Treatment Requirements
- Discuss with NRC potential future STP risk informed, performance based efforts
- Risk Informed, Performance Based Fire Protection
- Redefinition of Large Break LOCA 2
Risk-Informed Safety Culture
- Management and Operations are aligned on use of risk management in station programs to focus on safety and improve decision-making processes
- Programmatic risk management improves focus on safety
- Risk Index is a Tier 1 Performance Indicator (Le.,
tracks and monitors long term configuration risk trends)
- Real-time risk calculations are used for managing work (i.e., tracks and monitors short term risk trends) 3
Overview of STP RIPS Applications
- Graded Quality Assurance and Exemption that piloted 10CFR50.69
- Improved safety focus
- Risk-Managed Technical Specifications
- Significant safety improvement in industry & regulatory Tech Spec approaches by establishing Configuration Risk Management methods for maintaining focus on risk significant activities and test interval methodology
- Operational flexibility
- Fewer challenges to LCO ACTION times 4
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SFCP Outline
- Independent Decisionmaking Panel
- Identification of candidate STI changes
- SFCP evaluations after PRA updates 7
SFCP Background
- Submitted License Amendment Request (LAR) to implement TSTF-425 on 10/23/07
- NEI 04-1 0 Rev.1 process followed - onIy exception is Independent Oecisionmaking Panel (lOP) - STP uses Graded Quality Assurance program lOP instead of Maintenance Rule Expert Panel
- NRC issued STP SER on 10/31/08 8
Completed STI Changes Phased Curr Prop'd KICK* INPUTS STRIDE Parameter Impl. IWG EP Impl.
Freq Freq OFF DUE Status Likely?
SG Water Level Lo-Lo ACOT, TT/FI Q R Yes 01/20 03/04 03/19 07101 Complete Hi-Hi ACOT Loss of Voltage, Degraded Voltage Q 01/28 SA No 03/04 03/19 04/02 Complete TADOTS WR Containment Water Level R R2 No 01119 02/05 02/18 02126 04/02 Complete Calibration AFW Monthly Op. Test and Channel Q M No 01/19 02/25 04/01 04116 05/15 Complete checks motor-driven pumps only PZR Level ACOT Q R Yes 02/09 04/16 04/29 05/14 06114 Working PZR Press ACOT Q R Yes 02/09 06/11 06/24 07/23 08/23 Working Containment Press ACOT Q R Yes 02/09 06/11 06/24 07/23 08/23 Working SSDG Fuel Oil Tank Cleaning 10 yr 20 yr No 04/21 06/30 07108 08/20 09/20 Main Steam Press ACOTs Q R Yes 05/12 07/15 08/05 08/20 09/20 RCS Flow ACOT Q R Yes 05/12 07/31 08/19 09/17 11117*
RWST Level ACOT Q R Yes 06/16 08/15 09/02 09/17 11117*
9
STP SFCP Lessons Learned
- Two IWG meetings are required to review each STRIDE
- First meeting identifies comments that require resolution
- Second meeting resolves comments and finalizes recommendations
- Reactor and ESF instrumentation STI changes Engineering resources needed to evaluate drift impact on Tech Spec allowable value and Setpoint Methodology
- PRA maintains an aggregate "analysis" model to evaluate previous and current STI changes. Will need to be re-created after each PRA model update.
10
STP SFCP Lessons Learned
- Previous STI changes require re-evaluation after PRA model update if PRA quantitative analysis performed
- Will be significant work load, i.e., re-perform previous STI change PRA analyses with updated PRA model part of RI-application update process after model revIsion
- Assessing aggregate effects can/should be accommodated with Risk Index approach 11
Risk Managed Technical Specifications
- RITS Initiative 48 STP Units 1 & 2
RMTS Outline
RMTS at STP
- Approved by NRC on 7/13/07
- k. Configuration Risk Management Program (CR~fP)
AprograIIl to calculate risk-infomlcd cOTnpleLion time in accordance with NEI 06-09,
~'Rlsk-t\1anaged Technical Specifications (RMTS) Guidelines, Rev. (r. The CR~P may be used for calculat.ing a risk-informed completion time only in Mode 1and Mode 2. In accordance with NEI 06-09, the completion time determined using the CRMP shall not be morc than 30 davs.
14
Example RMTS LeO Action 3.7.14 At least three independent Essential Chilled Water System loops shall be OPERABLE.
APPLICABILITY; MODES 1,2,3, and 4, ACTION~
- a. With only two Essential Chilled Water System loops OPERABLE, within 7 days restore at least three loops to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the foJlowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With two or more Essential Chilled Water System loopsinoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore at least two loops to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN with;n the foUowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
15
STP RMTS Experience
- Used for planned 1E 120VAC instrument inverter maintenance, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS front stop.
NRC performed inspection activity and QA performed RMTS audit.
- "Almost" used for instrument inverter failure and emergent ECW pump maintenance.
- Used to replace Train A and Train C class 1E batteries in Units 1 & 2 - 5 day work window planned. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> TS front stop. No risk threshold Issues 16
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Lessons Learned
- Early involvement from Operations and Work Control
- Draft requirements document with multiple review cycles BEFORE beginning software development
- Present RMTS concepts in multiple Licensed Operator Requal cycles
- "multiple clocks" (e.g., front stop, RMAT, RICT ICDP or ILERP, back stop)
- scenario development
- software demos 18
STP RMTS Pre-Implementation Lessons
- Important to train on new concepts like "PRA Functional", RMAT, and RICT.
Operations, Work Control, Management, Engineering.
- Formed RMTS working group and met weekly to develop program, procedures, and policies.
19
STP RMTS Implementation Lessons
- Dose mitigation functions of Control Room HVAC need to be addressed as separate action statements for CRMP purposes.
- Thorough pre-job review involving all stakeholders is important to error-free application
- STP prepared a procedure specifically for battery replacement 20
STP RMTS Conclusion RMTS has improved the quality of the station's working environment by providing an approved process for addressing Tech Spec equipment issues while also reducing administrative and regulatory burden for both STP and NRC
-Questions ?
21
Exemption from Special Treatment Requirements Lessons Learned
- Change management and cultural change issue
- Categorization supports risk informing station processes (corrective action, PREP, Self-Assessments, Audits, etc.) and associated performance indicators (Risk Index, Equipment Reliability clock resets) .
. supports and reinforces safety culture Issues
- heightens awareness and improves communication of concerns and issues related to risk significant SSCs
- Approximately 2 Working Group meetings and 1 Expert Panel meeting to categorize system functions and components for each system on average (-200 man hrs/system)
- Can be used in Fatigue Rule to establish scope of equipment for which the rule will apply 25
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RMTS Phase 2 ??
- Based on the good results for the current RMTS program, STP can foresee another phase of systems being incorporated into the CRMP scope for RMTS
- Systems like FW Iso Vlvs, ESFAS
- Based on the good results of the RITS 58, STP can foresee another phase of surveillances being incorporated into the SFCP
- Additional I&C systems 27
RISK-INFORMED FIRE PROTECTION
- A significant amount of regulatory uncertainty remains with the transition process and industry resources are limited.
- Many facilities (including STP) can effectively resolve non-compliances with their Fire Protection Program Licensing Basis in a more efficient manner using alternative methods.
- STP's approach on previous RIPB applications has been to meet RG 1.200 for PRA technical adequacy
- Need to be able to reference use of RG.1200 for Fire PRA technical adequacy 28
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FIRE LARs
- STP identified 3 fire areas where the Fire Safe Shutdown Analysis does not fully meet Appendix R, III.G.2 requirements
- One amendment approved
- Two remaining amendments under staff review and a request for additional information has been received.
31
Nuclear Safety Culture
- STP participating in Industry Pilot Initiative to develop a process for assessing a facility's nuclear safety culture on a real-time basis.
- STP is doing this because this is the right-thing to-do.
- An Industry desired-outcome is to demonstrate that this process is an effective method to assess nuclear safety culture and that the NRC will revise the ROP to not include a need to identify Substantive Cross-cutting Issues.
32
Nuclear Safety Culture
- Concept is that the Facility has numerous data points to access nuclear safety culture compared to the limited number of data points provided by NRC identified cross cutting aspects.
- Nuclear Safety Culture will be assessed against the INPO Principles for a Strong Nuclear Safety Culture.
- Pilots will start in November and conclude in the April May 2010 time frame. The NRC has been requested to observe.
33
Hurricane Exemption
- Exemption request for not meeting certain work hour requirements during tropical storm or hurricane conditions submitted to the staff on September 21, 2009.
- The STP exemption is a lead-plant request for affected facilities in the industry.
- STP participated in NRC meetings to resolve this issue.
- Ultimate resolution is expected to be Part 26 rulemaking so that the exemption will not be required.
34
Meetina Notice: ML092570390 , Meetma S urnmary: ML093020098 OFFICE DORULPL4/PM DORULPL4/LA DORULPL4/BC DORULPL4/PM NAME MThadani JBurkhardt MMarkley MThadani DATE 10/29/09 10/29/09 10/29/09 10/29/09