Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML13323A186, ML13323A189, ML13323A190, ML13323A191, ML13323B187, ML13323B191, ML13323B194, ML13323B196, ML13323B198, ML13323B199, ML13323B200, ML13323B201, ML13323B202, ML13323B204, ML13323B207, ML13323B208, ML13323B209, ML14015A045, ML14052A053, ML14072A076, ML14086A386, ML14149A089, ML14149A434, ML14149A435, ML14178A481, ML14321A438, ML14321A677, ML14344A545, ML14344A546, ML14349A790, ML15119A326, ML15175A024, ML15183A007, ML15183A009, ML15246A128, ML15246A129, ML15265A601, ML16230A232, NOC-AE-13003039, Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI), NOC-AE-13003040, Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test., NOC-AE-13003065, Response to STP-GSI-191-EMCB-RAI-1, NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3, NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application, NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1, NOC-AE-14003104, Revised Affidavit for Withholding for Casa Grande Analyses for Risk-Informed GSI-191 Licensing Application, NOC-AE-14003105, Third Set of Responses to April, 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Licensing Application, NOC-AE-14003106, Second Submittal of Casa Grande Source Code for Stp'S Risk-Informed GSI- 191 Licensing Application, NOC-AE-14003111, Submittal of Casa Grande Source Code for Stp'S Risk-Informed GSI-191 Licensing Application, NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application, NOC-AE-15003220, Description of Revised Risk-Informed Methodology and Responses to Round 2 Requests for Additional Information Regarding STP Risk-Informed GSI-191 Licensing Application... further results
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MONTHYEARML13323B1962012-06-12012 June 2012 Attachment 4: CHLE-008, Rev. 3, Debris Bed Preparation and Formation Test Results. Project stage: Other ML13323B1942012-08-11011 August 2012 Attachment 3: CHLE-007, Rev. 3, Debris Bed Requirements and Preparation Procedures. Project stage: Other 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. Project stage: Other ML13323B1912012-08-14014 August 2012 Attachment 2: CHLE-006, Rev. 1, STP Material Calculations. Project stage: Other ML13323B1982012-08-19019 August 2012 Attachment 5: CHLE-010, Rev. 2, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition. Project stage: Other ML13323B2002013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Figure 53 Through End Project stage: Other ML13323B1992013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Cover Through Figure 52 Project stage: Other ML13323B2022013-01-15015 January 2013 Attachment 8: CHLE-015, Rev. 3, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal. Project stage: Other ML13323B2042013-01-22022 January 2013 Attachment 9: CHLE-016, Rev. 2, Calculated Material Release to Estimate Chemical Effects. Project stage: Other ML13323B2012013-01-22022 January 2013 Attachment 7: CHLE-014, Rev. 2, T2 LBLOCA Test Report. Project stage: Other NOC-AE-13002954, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-1912013-01-31031 January 2013 Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 Project stage: Request ML13214A0312013-08-13013 August 2013 Acceptance Review, Exemption Requests and License Amendment Request to Revise UFSAR for Resolution of Generic Safety Issue 191, Assessment of Debris Accumulation on PWR Sump Performance (TAC MF0613-MF0614; MF2400-09) Project stage: Acceptance Review ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. Project stage: Other ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) Project stage: Other NOC-AE-13003039, Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)2013-10-0303 October 2013 Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI) Project stage: Other ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). Project stage: Other ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis Project stage: Other ML13323B1872013-10-31031 October 2013 Project, Units 1 & 2, Submittal of GSI-191 Chemical Effects Test Reports (TAC Nos. MF2400 and MF2401) Project stage: Other ML13323A1912013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Page 212 of 1-122 Project stage: Other ML13323A1902013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Cover - Page 211 of 248 Project stage: Other ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 Project stage: Other ML13323A1852013-11-13013 November 2013 Enclosure 3 - License Amendment Request for STP Piloted Risk-Informed Approach to Closure for GSI-191 Project stage: Request NOC-AE-13003043, Enclosure 5 - Response to NRC Supplemental Information Items2013-11-13013 November 2013 Enclosure 5 - Response to NRC Supplemental Information Items Project stage: Supplement ML13323A1832013-11-13013 November 2013 Project Units 1 and 2 - Supplement 1 to Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 Project stage: Supplement NOC-AE-13003054, Supplement 1 to Revised STP Pilot Submittal for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 to Supersede and Replace the Revised Pilot Submittal2013-11-21021 November 2013 Supplement 1 to Revised STP Pilot Submittal for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 to Supersede and Replace the Revised Pilot Submittal Project stage: Supplement ML13330B2222013-12-0505 December 2013 Notice 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 Project, Units 1 and 2 (TAC MF2400-MF24 Project stage: Meeting NOC-AE-13003070, Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application2013-12-23023 December 2013 Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application Project stage: Request NOC-AE-13003065, Response to STP-GSI-191-EMCB-RAI-12013-12-23023 December 2013 Response to STP-GSI-191-EMCB-RAI-1 Project stage: Other ML13357A2662013-12-24024 December 2013 1/8/14 - Notice of Meeting with STP Nuclear Operating Co. 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 Project stage: Meeting NOC-AE-13003057, Response to Request for Additional Information Re Use of RELAP5 in Analyses for Risk-Informed GSI-191 Licensing Application2014-01-0909 January 2014 Response to Request for Additional Information Re Use of RELAP5 in Analyses for Risk-Informed GSI-191 Licensing Application Project stage: Response to RAI ML14009A3072014-01-0909 January 2014 NRR E-mail Capture - Request for Additional Information - TACs MF2400 Through MF2409 Project stage: RAI ML14015A0452014-01-14014 January 2014 NRR E-mail Capture - Rai'S Regarding South Texas Project'S Submittal for Risk-Informed Resolution of GS-191 Project stage: Other ML13358A0622014-01-14014 January 2014 Summary of 12/16/13 Meeting with STP Nuclear Operating Co. 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 Project stage: Meeting ML14052A0532014-02-13013 February 2014 Project Units 1 & 2, Submittal of Casa Grande Code & Analyses for Risk-Informed GSI-191 Licensing Application Project stage: Other NOC-AE-14003081, STP-Specific Casa Grande Inputs CASA01 JT4, CASA09 JT4, CASA22 JT4, CASA26 JT4, & CASA43 JT42014-02-13013 February 2014 STP-Specific Casa Grande Inputs CASA01 JT4, CASA09 JT4, CASA22 JT4, CASA26 JT4, & CASA43 JT4 Project stage: Request ML14149A4352014-02-14014 February 2014 Project, Units 1 and 2 - ALION-REP-STP-8998-02, Rev. 0, STP Casa Grande Analysis and LAR Enclosure 4-3 RAI Response, Enclosure 1 to Attachment 1 Project stage: Other ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 Project stage: Request ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 Project stage: Request ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 Project stage: Request ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 Project stage: Request ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 Project stage: Request ML14072A0762014-02-27027 February 2014 Project, Units 1 and 2, Submittal of GSI-191 Chemical Effects Test Reports (TAC Nos. MF2400 and MF2401) Project stage: Other ML14072A2112014-03-0606 March 2014 NRR E-mail Capture - STP Sensitivity Report and Presentation for Proposed Meeting Project stage: Request NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 32014-03-11011 March 2014 Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3 Project stage: Other ML14086A3862014-03-17017 March 2014 STP Risk-Informed GSI-191 Aadb RAI 3 Response, Attachment 2 Project stage: Other ML14086A3852014-03-17017 March 2014 Project, Units 1 & 2 - Response to NRC Accident Dose Branch Request for Additional Information Regarding STP Risk-Informed GSI-191 Application Project stage: Request NOC-AE-14003111, Submittal of Casa Grande Source Code for Stp'S Risk-Informed GSI-191 Licensing Application2014-03-18018 March 2014 Submittal of Casa Grande Source Code for Stp'S Risk-Informed GSI-191 Licensing Application Project stage: Other NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai.. Project stage: Request ML14091A4522014-04-0808 April 2014 Request for Withholding Information from Public Disclosure - 12/9/13 G. Powell, STPNOC Affidavit Enclosing RELAP5 Digital Media Related to GSI-191 License Amendment and Exemption Requests Project stage: Withholding Request Acceptance ML14087A0752014-04-15015 April 2014 Request for Additional Information, Request for Exemptions and Revised Pilot License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 Project stage: RAI 2013-12-05
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Category:Meeting Briefing Package/Handouts
MONTHYEARML22243A1312022-08-31031 August 2022 STP Nuclear Operating Company August 31, 2022 Presentation - Pre-Submittal Meeting for Updated Main Steam Line Break and Locked Rotor Dose Consequence Analysis to Address Extended Cooldown Timelines ML22214A0972022-08-0202 August 2022 Presentation by South Texas Project ML22153A2942022-06-17017 June 2022 richardsd-hv-th28 ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change ML20125A3362020-05-0404 May 2020 STP Presubmittal Meeting Exigent Accumulator LAR 2020-05-05 Presentation L-2020-LRM-0039 ML19326A0072019-11-22022 November 2019 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan - December 3, 2019 ML16356A0612016-12-21021 December 2016 12/21/2016 South Texas Project Aluminum Bronze Aging Management Request for Additional Information ML16264A3632016-09-20020 September 2016 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan Staff Augmentation Times ML16210A0442016-07-28028 July 2016 STP Nuclear Operating Company Handouts for July 28, 2016 Public Meeting on GSI-191 ML16172A0192016-07-25025 July 2016 STP Aluminum Bronze Selective Leaching Public Meeting - June 21, 2016 ML16202A4872016-07-21021 July 2016 07/21/2016 Talking Points, Supplemental Information for South Texas Project and NRC Public Meeting ML16111A0272016-04-18018 April 2016 STP Nuclear Operating Company Slideshow for Public Meeting on April 21, 2016 for GSI-191 Resolution (CAC No. MF2400-01) ML16062A3042016-03-0202 March 2016 TS 5.3.2 LAR Pre-Submittal Meeting Presentation - March 2, 2016 ML16033A0042016-01-19019 January 2016 Applicant's Slides for STP Meeting on Aluminum Bronze Aging Management ML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call ML15271A3042015-09-28028 September 2015 Public Phone Call Meeting Description of Supplement 2 to STPNOC Risk-Informed Licensing Application to Address GSI-191 and Respond to GL-2004-02 ML15111A0582015-04-15015 April 2015 Licensee Handouts (2 of 2) for 4/22/2015 Public Meeting Possible Roverd Section on Fixed Filtration (TAC Nos. MF2400-MF2409) ML15111A0562015-04-15015 April 2015 Licensee Handouts (1 of 2) for 4/22/2015 Public Meeting Revised Roverd Section on Large Early Release Frequency Change for Large Break Loss-of-Coolant Accident(Tac Nos. MF2400-MF2409) ML15056A3862015-02-25025 February 2015 NRC Slides for February 25, 2015 Public Meeting with STPNOC Concerning GSI-191 ML15049A4882015-02-18018 February 2015 Slides for February 25, 2015 Public Meeting ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. NRC Public Meeting Slides - ILRT License Amendment ML15034A1142015-02-0404 February 2015 STP Risk- Informed Approach to GSI - 191 Roverd 2015 Meeting Blue 1 29 15 ML14192A9842014-08-0404 August 2014 Summary of Pre-Licensing Meeting with STP Nuclear Operating Company to Discuss Future License Amendment Request to Revise TS 6.9.1.6.b.9 to the Leading Edge Flow Meter Technology for Feedwater Flow Measurement ML14120A0112014-04-29029 April 2014 4/29/2014 - South Texas Project Regulatory Approach for Risk-Informed Pilot Submittal Presentation Relating to 10 CFR 50.46c ML13352A1422013-12-16016 December 2013 GSI-191 Licensing Submittal Comparison of Changes Between Rev 1 and Rev 2 ML13352A1242013-12-16016 December 2013 NRC Staff Slides South Texas Project Risk-Informed Generic Safety Issue - 191, December 16, 2013 ML13316B9052013-11-13013 November 2013 Albrz Testing Update for NRR Final ML13150A2162013-05-23023 May 2013 Licensee Slides for 5/23/13 Public Meeting Regarding GSI-191 ML13140A2562013-05-20020 May 2013 Licensee Slides for 5/23/13 Meeting - STP Pilot Submittal for Risk Informed Approach to Resolving GSI-191 ML13023A3342013-02-25025 February 2013 1/15/2013 Summary of Public Meetings Conducted to Discuss Draft Supplemental Environmental Impact Statement Related to Review of South Texas Project, Units 1 & 2, License Renewal Application ML13051A8552013-02-20020 February 2013 Licensee Slides for 3/5/13 Pre-Application Meeting for Proposed Licensing Action to Revise the Fire Protection Program at STP ML13029A4972013-01-15015 January 2013 Slides - Preliminary Site-Specific Results of the Environmental Review for South Texas Project License Renewal ML12297A3312012-11-27027 November 2012 Summary of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 ML12264A3202012-10-11011 October 2012 Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program ML12145A4382012-05-18018 May 2012 Licensee Handout on Calibration and Benchmarking of Single and Two-Phase Jet Cfd Models ML1209004042012-03-30030 March 2012 3-27-2012 - STP Public Meeting Handout from Nuclear Innovation North America, LLC on Fukushima Lessons Learned for South Texas Project Units 3 and 4 ML1205407582012-02-22022 February 2012 STP Summary of January Meeting ML1205405572012-02-22022 February 2012 Licensee Slides for 03/1/12 Meeting with STP Nuclear Operating Company Meeting to Discuss GSI-191 ML1205405702012-02-22022 February 2012 Uncertainty Modeling of LOCA Frequencies and Break Size Distributions for the STP GSI-191 Resolution ML1204400652012-02-0909 February 2012 Licensee Slides for 2/9/12 Meeting Regarding GSI-191 ML1133505632011-12-0101 December 2011 Licensee Presentation from 12/1/11 Meeting Via Conference Call to Discuss Risk-Informed GSI-191,Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance ML1130506322011-10-26026 October 2011 Licensee Handouts from November 1, 2011 Meeting with STP Nuclear Operating Company on GSI-191 ML1127702032011-10-0303 October 2011 Licensee Slides from 10/3/11 Meeting LOCA Frequencies, Final Results ML1127701762011-10-0303 October 2011 Licensee Handouts from 10/3/11 Meeting STP LOCA Frequency ML1123508732011-08-22022 August 2011 Models and Methods Used for Casa Grande ML1123508832011-08-22022 August 2011 LOCA Initiating Event Frequencies and Uncertainties Status Report ML1120707072011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slide Models and Methods Used for Casa Grande ML1120707292011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slides Computational Fluid Dynamics Validation Plan ML1118903802011-07-0707 July 2011 Licensee Slides, LOCA Initiating Event Frequencies and Uncertainties(Draft) ML1118904082011-07-0606 July 2011 Licensee Handout Loca Frequencie Approach and Example Application 2022-08-31
[Table view] Category:Slides and Viewgraphs
MONTHYEARML22243A1312022-08-31031 August 2022 STP Nuclear Operating Company August 31, 2022 Presentation - Pre-Submittal Meeting for Updated Main Steam Line Break and Locked Rotor Dose Consequence Analysis to Address Extended Cooldown Timelines ML22214A0972022-08-0202 August 2022 Presentation by South Texas Project ML22153A2942022-06-17017 June 2022 richardsd-hv-th28 ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change ML20248H5322020-09-0404 September 2020 STP Nuclear Operating Company September 14, 2020, Presentation - Pre-Submittal Meeting for Proposed South Texas Project Moderator Temperature Coefficient Surveillance Requirement Technical Specification Change ML20125A3362020-05-0404 May 2020 STP Presubmittal Meeting Exigent Accumulator LAR 2020-05-05 Presentation L-2020-LRM-0039 ML20034E8192020-02-0606 February 2020 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan ML19095A6562019-04-0404 April 2019 NRR E-mail Capture - (External_Sender) Handout for 4/10/19 Meeting to Discuss a Proposed Request for South Texas Project, Units 1 and 2, Regarding Repair of Piping Using Carbon Fiber Repair Methods ML17004A0292017-01-0404 January 2017 Slides for January 4, 2017, Public Meeting on South Texas Project's Resposne to Aluminum Bronze Aging Management Request for Additional Information ML16356A0612016-12-21021 December 2016 12/21/2016 South Texas Project Aluminum Bronze Aging Management Request for Additional Information ML16350A3272016-11-17017 November 2016 Transcript of Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Meeting - November 17, 2016 ML16264A3632016-09-20020 September 2016 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan Staff Augmentation Times ML16172A0192016-07-25025 July 2016 STP Aluminum Bronze Selective Leaching Public Meeting - June 21, 2016 ML16188A3682016-07-0606 July 2016 Audit Presentation - Westinghouse Methodology for South Texas Unit 1 LAR: Operation with 56 Control Rods ML16062A3042016-03-0202 March 2016 TS 5.3.2 LAR Pre-Submittal Meeting Presentation - March 2, 2016 ML16033A0042016-01-19019 January 2016 Applicant's Slides for STP Meeting on Aluminum Bronze Aging Management ML15334A3972015-11-30030 November 2015 TS 5 3 2 Emergency LAR Pre-Submittal Meeting Presentation ML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. NRC Public Meeting Slides - ILRT License Amendment ML15034A1142015-02-0404 February 2015 STP Risk- Informed Approach to GSI - 191 Roverd 2015 Meeting Blue 1 29 15 ML14192A9842014-08-0404 August 2014 Summary of Pre-Licensing Meeting with STP Nuclear Operating Company to Discuss Future License Amendment Request to Revise TS 6.9.1.6.b.9 to the Leading Edge Flow Meter Technology for Feedwater Flow Measurement ML14149A0892014-05-21021 May 2014 NRR E-mail Capture - STP-GSI-191 Presentation ML14120A0112014-04-29029 April 2014 4/29/2014 - South Texas Project Regulatory Approach for Risk-Informed Pilot Submittal Presentation Relating to 10 CFR 50.46c ML13352A1242013-12-16016 December 2013 NRC Staff Slides South Texas Project Risk-Informed Generic Safety Issue - 191, December 16, 2013 ML13352A1422013-12-16016 December 2013 GSI-191 Licensing Submittal Comparison of Changes Between Rev 1 and Rev 2 ML13316B9052013-11-13013 November 2013 Albrz Testing Update for NRR Final ML13150A2162013-05-23023 May 2013 Licensee Slides for 5/23/13 Public Meeting Regarding GSI-191 ML13140A2562013-05-20020 May 2013 Licensee Slides for 5/23/13 Meeting - STP Pilot Submittal for Risk Informed Approach to Resolving GSI-191 ML13023A3342013-02-25025 February 2013 1/15/2013 Summary of Public Meetings Conducted to Discuss Draft Supplemental Environmental Impact Statement Related to Review of South Texas Project, Units 1 & 2, License Renewal Application ML13051A8552013-02-20020 February 2013 Licensee Slides for 3/5/13 Pre-Application Meeting for Proposed Licensing Action to Revise the Fire Protection Program at STP ML13029A4972013-01-15015 January 2013 Slides - Preliminary Site-Specific Results of the Environmental Review for South Texas Project License Renewal ML12297A3312012-11-27027 November 2012 Summary of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 ML12264A3202012-10-11011 October 2012 Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program ML1209004042012-03-30030 March 2012 3-27-2012 - STP Public Meeting Handout from Nuclear Innovation North America, LLC on Fukushima Lessons Learned for South Texas Project Units 3 and 4 ML1204400652012-02-0909 February 2012 Licensee Slides for 2/9/12 Meeting Regarding GSI-191 ML1133505632011-12-0101 December 2011 Licensee Presentation from 12/1/11 Meeting Via Conference Call to Discuss Risk-Informed GSI-191,Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance ML1130506322011-10-26026 October 2011 Licensee Handouts from November 1, 2011 Meeting with STP Nuclear Operating Company on GSI-191 ML1127701762011-10-0303 October 2011 Licensee Handouts from 10/3/11 Meeting STP LOCA Frequency ML1127702032011-10-0303 October 2011 Licensee Slides from 10/3/11 Meeting LOCA Frequencies, Final Results ML1123508832011-08-22022 August 2011 LOCA Initiating Event Frequencies and Uncertainties Status Report ML1123508732011-08-22022 August 2011 Models and Methods Used for Casa Grande ML1120707292011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slides Computational Fluid Dynamics Validation Plan ML1120707072011-07-26026 July 2011 Meeting Notice with South Texas Project, Units 1 and 2 - Licensee Slide Models and Methods Used for Casa Grande ML1118903802011-07-0707 July 2011 Licensee Slides, LOCA Initiating Event Frequencies and Uncertainties(Draft) ML1118904202011-07-0606 July 2011 Licensee Slide from 7/7/11 Meeting with STP Nuclear ML11157A0102011-06-0202 June 2011 STP Nuclear Operating Company, Licensee Handouts, 6/2/2011 Meeting Risk-Informed GSI-191 Closure Plan for GSI-191 Resolution ML1114501952011-05-24024 May 2011 Summary of Meeting with South Texas Project Electric Generating Station 2010 Performance ML1105503952011-02-22022 February 2011 Licensee Slides from 2/22/11 Public Meeting with STP Nuclear Operating Company ML1103206432011-01-27027 January 2011 1/27/11 Presentation on Risk-Informed GSI-191 Project Overview ML1021803392010-08-0505 August 2010 Ltr to E. Halpin Re Participation in Commission Meeting on the Resolution of Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Performance on 09/29/10 2022-08-31
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Text
STP Risk-Informed Approach to GSI-191 NRC Meeting February 4, 2015
STP Agenda
- Purpose and Desired Outcome
- Risk over Deterministic (RoverD) Assessment
- Technical Specification Concept
- Operability Considerations
- Expected Content of Application Supplement
Purpose and Desired Outcome
Purpose:
Present to the NRC staff two changes, RoverD and a Technical Specification concept, that are expected to simplify review and resolve issues
- NRC staff understand proposed changes
- Identification of any issues with the changes and a path to resolution 3
STP Risk over Deterministic (RoverD):
Test-Based Debris Risk Assessment 4
RoverD motivation 1 Reduce reliance on analysis I Correlations may have epistemic uncertainty that is difficult to quantify I Complexities in the engineering analysis may make results less transparent 2 Reduce scope of review I Deterministic test data used to screen out many scenarios I Risk-based review scope limited to fewer scenarios I Use of test data consistent with (for example) fuel testing approach by establishing a limit for loading 3 Add confidence to conclusions regarding risk significance I Relegates ALL failures above the deterministic threshold to failure I Deterministic test produces a conservatively high threshold 5
Summary of RoverD elements 1 Obtain deterministic fiber loading test data I ECCS strainer loading and fiber penetration I Fuel assembly loading 2 Perform supporting analyses I LOCA scenario analysis for break size I Strainer performance criteria for NPSH, flashing, gas voiding, mechanical strength I Fiber generation, transport, erosion, latent fiber quantity I In-vessel analyses F In-vessel fiber limit analysis (blockage analyses for HLB and CLB)
F Boric acid precipitation analysis F Fuel limits (LOCADM for PWRs) 3 Regulatory Guide 1.174 risk assessment I RG 1.174: CDF , CDF , LERF , LERF I RG 1.174: Defense-in-depth, safety margin 6
RoverD flow charts 7
RoverD flow charts 8
RoverD method overview 1 Use deterministic strainer test data I Coatings failure, chemical effects head loss, fiber loading head loss consistent with deterministic approaches I Note amount of fine debris from break, latent fiber, and erosion 2 Use deterministic core fiber loading data I Coatings failure, chemical effects head loss, fiber loading head loss consistent with deterministic approaches I Determine the amount of fiber (based on the amount available from above) bypassed to the core I Ensure the amount bypassed and collected on the core is less than the acceptable tested amount 3 Using CASA Grande generation and transport methodology, find the smallest break size (by sampling) at each weld that produces more fine fiber in the sump than in the strainer test and relegate all larger breaks to failure 4 Derive a total failure frequency from NUREG 1829 to assign to CDF and ensure the total CDF is in Region III of RG 1.174 I Ensure LERF (using the PRA with the CDF) is in Region III of RG 1.174 I Ensure defense in depth and safety margin requirements of RG 1.174 are met 9
ECCS strainer test data analysis 1 Obtain deterministic strainer test data at some fiber loading (coatings failure, chemical precipitate loading, bed configuration, etc.)
I The amount of fiber fines should be representative of how much could arrive on the strainer in the actual plant including latent fiber and 30-day erosion I Examine scenarios at each weld location in the plant for break sizes and orientations from smallest break size to the largest possible I For each weld location, record the smallest break size (Dismallest ),
i = 1, . . . , N, for the scenario that would result in fiber fines more than the amount used in the acceptable strainer performance test (note that some welds may not have a scenario exceeding the tested fiber fines) 2 Preserve NUREG 1829 total frequency by deriving weights, wi , and cumulative scenario frequencies, fi , for each Dismallest 10
STP ECCS strainer test parameters 1 LDFG fine (191.78 lbm) and small (380.35 lbm) fibers I 24.96 lbm latent fine fiber I 166.82 lbm insulation fine fiber I 380.35 lbm smalls (with fines removed) 2 Particulates, Microtherm R and Marinite R board particulates, latent dust and dirt I 33 lbm Microtherm R powder I 182.7 lbm powdered Marinite R board I 141.1 lbm dust and dirt 3 Chemical precipitates representing 30 days of containment spray operation (1,934 lbm chemical precipitates)
I 1,575 lbm AlOOH, (1,432 lbm NaAlSI3 O8 , 143 lbm AlOOH)
I 359 lbm CaPO4 4 Coatings, zinc, epoxy, polyamid primer, alkyds, baked enamel I 1,368 lbm zinc powder I 582 lbm acrylic powder 11 I 106 lbm acrylic chips (1/64 - 1/4)
Plant CDF analysis (strainer) 1 Use wi and fi to derive a plant strainer CDF as follows:
XN CDF = fi wi (1) i=1 2 IF the CDF from (1) is in Region III of RG 1.174, AND other criteria for strainer performance that are related to pressure drop (for example, NPSHA, gas evolution, flashing, etc.)
meet the acceptance criteria required by design, THEN the risk associated with LERF should be checked for acceptability, ELSE the risk is unacceptable and further analysis may be indicated 12
Plant LERF analysis (strainer) 1 The STP RCFCs are capable of maintaining containment cooling without dependency on ECCS 2 Independence of containment failure from the concerns raised in GSI-191 allow an accurate estimate of LERF based on CDF from (1):
CDF LERF = LERFMOR (2)
CDFMOR where values of CDFMOR and LERFMOR are the average values obtained from the PRA model of record 3 IF LERF is in Region III of RG 1.174, THEN the (strainer) risk related to LERF is acceptable 13
CDF analysis (in-vessel) 1 The risk due to core loading effects needs to be assessed against strainer penetration test data I Cooling effectiveness for fiber blockage I Boron precipitation for blockage from the lower plenum 2 IF thermal-hydraulic analysis shows adequate cooling for hot-leg breaks, AND The plant boric acid precipitation design analysis is compatible with the debris analysis, AND The total amount of the fiber used in the strainer test that penetrates the strainer and arrives in-vessel (for STP) on the bottom of the fuel in cold leg breaks is less than 15 gm/FA (WCAP-16793).
Note that amounts of fines greater than that added in the strainer test are relegated to failure already, THEN CDF from in-vessel effects is insignificant and the plant risk due to the concerns raised in GSI-191 is acceptable ELSE further analysis may be required to determine risk acceptability 14
Preliminary RoverD analysis results 1 No scenarios relegated to failure (due to strainer loading) exceed the core fiber limit I Boron precipitation without lower plenum mixing analysis is in progress I All other in-vessel analyses have been completed satisfactorily 2 There are 45 welds (scenarios) in the risk-informed category 3 The maximum frequency (smallest break size) is a DEGB of the 16 inch surge line (Slide 17) 4 All other strainer performance metrics are met in the strainer deterministic analysis 15
RoverD Regulatory approach Submit RoverD description in near-term to permit early NRC staff review and support ACRS Subcommittee meeting
- Describe purpose of RoverD as the primary basis for the STP application
- Provide assumptions and their bases, including basis for acceptability of 2008 test
- Describe expected impact on STP application 16
Preliminary weld list - Fines mass, Weld ID, Dismallest Fiber Mass (lbm) Location Diameter 207.16 16-RC-1412-NSS-8 12.814 191.83 29-RC-1101-NSS-RSG-1A-IN-SE 13.924 191.99 29-RC-1101-NSS-5.1 13.941 196.04 29-RC-1301-RSG-1C-IN-SE 14.368 192.09 29-RC-1401-NSS-RSG-1D-IN-SE 14.404 198.66 29-RC-1201-NSS-5.1 14.428 192.41 29-RC-1401-NSS-4.1 14.428 197.18 29-RC-1301-NSS-5.1 14.434 201.08 29-RC-1201-RSG-1B-IN-SE 14.542 201.07 29-RC-1101-NSS-4 15.052 195.29 29-RC-1201-NSS-4 15.087 197.42 29-RC-1401-NSS-3 15.294 205.18 29-RC-1301-NSS-4 15.496 192.19 31-RC-1102-NSS-2 16.408 200.29 31-RC-1202-NSS-2 16.777 197.21 31-RC-1202-NSS-RSG-1B-ON-SE 16.928 197.81 31-RC-1202-NSS-1.1 16.981 17
Preliminary weld list - Fines mass, Weld ID, Dismallest Fiber Mass (lbm) Location Diameter 200.54 31-RC-1102-NSS-1.1 17.071 202.54 31-RC-1102-NSS-RSG-1A-ON-SE 17.200 195.30 31-RC-1202-NSS-3 17.240 194.34 31-RC-1302-NSS-2 17.345 194.85 31-RC-1102-NSS-3 17.374 193.02 31-RC-1302-NSS-1.1 17.636 195.21 31-RC-1202-NSS-4 17.843 196.75 31-RC-1302-NSS-3 17.919 198.32 31-RC-1302-NSS-RSG-1C-ON-SE 18.108 197.07 31-RC-1402-NSS-1.1 18.137 197.35 31-RC-1102-NSS-4 18.179 197.95 31-RC-1402-NSS-RSG-1D-ON-SE 18.198 193.08 31-RC-1402-NSS-2 18.311 191.90 31-RC-1302-NSS-4 18.343 191.86 31-RC-1202-NSS-8 19.235 192.96 31-RC-1402-NSS-3 19.247 192.04 27.5-RC-1103-NSS-1 19.461 18
Preliminary weld list - Fines mass, Weld ID, Dismallest Fiber Mass (lbm) Location Diameter 191.92 27.5-RC-1203-NSS-1 19.566 193.04 31-RC-1102-NSS-8 19.617 192.37 31-RC-1402-NSS-4 20.236 192.03 31-RC-1302-NSS-8 20.350 192.45 27.5-RC-1303-NSS-1 21.053 192.11 31-RC-1202-NSS-9 21.116 192.34 31-RC-1102-NSS-9 21.278 191.96 27.5-RC-1403-NSS-1 22.047 192.16 31-RC-1402-NSS-8 22.174 193.18 31-RC-1302-NSS-9 23.169 192.46 31-RC-1402-NSS-9 25.335 19
RoverD RAI impact - APLAB RAI Description RoverD elimi-nates?
APLA-XI-1 Project Quality Assurance No APLA-XI-2 Treatment of Unanalyzed Plant Conditions Yes APLA-XI-3 Human Reliability Analysis Yes APLA-XI-4 Key Assumptions/Key Sources of Uncer- No tainty DEGB APLA-XI-5 Validity of Assumption on Pump Configura- Yes tions APLA-XI-6 Clarification on Response to APLA-IV-5 Yes APLA-XI-7 Fidelity between RELAP simulations and Yes CASA Grande APLA-XI-8 State-of-Knowledge Correlation Yes APLA-XI-9 Mean Values No APLA-XI-10 Selection of Johnson Parameters No 20
RoverD RAI impact - SSIB RAI Description RoverD eliminates?
F SSIB-RAI-2 Size distributions within the postu- No lated ZOIs F SSIB-RAI-4 Verify methodology results in over- No all realistic or conservative transport fractions considering LDFG conges-tion F SSIB-RAI-6a Justify the debris capture metrics No used in the evaluation are realistic F SSIB-RAI-7b Justify the washdown values from a No 30 minute test are applicable to the STP condition F SSIB-RAI-14 Confidence in the head loss correla- Yes tion used to perform the sensitivity study F SSIB-RAI 15- Use of head loss correlations will meet Yes 18,21,22 the established staff position 21
RoverD RAI impact - SSIB RAI Description RoverD eliminates?
F SSIB-RAI-27 CSHL Yes F SSIB-RAI-28 Individual and aggregate uncertainties Yes F SSIB-RAI-31 Void collection within the strainer Yes F SSIB-RAI-33 Sump water level evaluation Yes F SSIB-RAI-34 Basis for using random flow rates No F SSIB-RAI-41c Credit for strainer backwash No SSIB-RAI-43 Head loss bump up factor Yes SSIB-RAI-44 Bed compression Yes SSIB-RAI-45a Assumptions and modeling techniques re- No garding debris arrival timing and filtration SSIB-RAI-45b Dependency on arrival timing No SSIB-RAI-45c Bypass test result uncertainties No SSIB-RAI-45d Time step sensitivity No SSIB-RAI-45e mtest value No SSIB-RAI-45f Comparisons of filtration efficiencies and No shedding rates 22
RoverD RAI impact - SSIB RAI Description RoverD eliminates?
SSIB-RAI-46 Certain break sizes are not predicted or are No much less likely to occur than would be ex-pected SSIB-RAI-47 Appendix B used for CAD No SSIB-RAI-48 Mass of fiber No SSIB-RAI-49 Damage from a reflected jet No SSIB-RAI-50 Small and fine debris treated as if they have Yes the same properties SSIB-RAI-51 Flashing evaluation Yes SSIB-RAI-52 1/16 bed formation Yes SSIB-RAI-53 Variability in head loss calculations Yes SSIB-RAI-54 Safety margin evaluation Yes SSIB-RAI-55 RCS for hot leg switchover timing No 23
RoverD RAI impact - SNPB RAI Description RoverD eliminates?
SNPB-1 2 inch cold leg break BAP No SNPB-2 One assembly unblocked BAP No SNPB-3 Boric acid density treatment in RELAP5 No SNPB-4 Advection in RELAP5 No SNPB-6 Switchover timing variability No (should be 5) 24
RoverD RAI impact - ESGB RAI Description RoverD eliminates?
ESGB-23 RAI questions that may not be relevant (Yes)
ESGB-24a Detailed description of the chemical head Yes loss model ESGB-24b Bin selections allow the staff to discriminate Yes different outcomes ESGB-24c L* method independence from head loss Yes ESGB-24d Chemical model uncertainties Yes ESGB-25a Further model development Yes ESGB-25b Plausible range of head loss for test Yes ESGB-25c Calculation of scaled head loss value Yes ESGB-25d Basis for scaling equation/limitations Yes ESGB-26a Copy of the Reference 17 (CHLE-SNC-005 Yes Bench Test)
ESGB-26B Orange line in Figure 25 Yes ESGB-26c Aluminum release model prediction Yes 25
RoverD RAI impact- ESGB RAI Description RoverD eliminates?
ESGB-27 Scaffolding corrosion behavior Yes ESGB-28 Range of postulated plant temperature Yes profiles relative to CHLE MBLOCA and LBLOCA profiles ESGB-29 Provide the quantity of zinc that is included No in the particulate source ESGB-30 Which release equations will be used Yes ESGB-31 How model accounts for greater chemical Yes loading for less than three trains ESGB-32 Provide a modified response to ESGB RAI Yes
- 14a ESGB-33 CRUD mass No ESGB-34 Differing fiber amounts in tables Yes 26
RoverD RAI impact - ESGB RAI Description RoverD eliminates?
Ct-ESGB-8 Revised analysis for the unqualified epoxy Yes coatings Ct-ESGB-9 Revised analysis for the ZOI of inorganic zinc Yes coatings Ct-ESGB-10 Revised analysis for the unqualified coatings Yes in upper containment 27
RoverD RAI impact - STSB RAI Description RoverD elimi-nates?
STSB-1 Assumptions listed in page 30 of 35 used for No operability determination STSB-2a Description demonstrating the relationship No between probability and operability STSB-2b Explain probability of occurrence of the as- No sumptions listed in page 30 of 35 change to improve or degrade the impact on contain-ment sump performance 28
RoverD RAI impact - SCVB RAI Description RoverD eliminates?
SCVB-10a Description of revised licensing basis analysis No of the containment heat removal (GDC-38)
SCVB-10b Description of revised Iodine removal (GDC- No 41)
SCVB-10c Description of revised licensing basis analysis No for ECCS (GDC-35)
SCVB-12,1 a,b Full or partial exemption from GDC-38 heat No removal SCVB-12,2 a,b Full or partial exemption from GDC-38 fol- No lowing any LOCA SCVB-12, 3 a,b Full or partial exemption from GDC-38 No LOOP SCVB-12, 4 a,b Full or partial exemption from GDC-38 Single No failure SCVB-13 Operation of the CSS for fission product re- No moval 29
RoverD RAI impact - SCVB RAI Description RoverD eliminates?
SCVB-14, 1 a,b Full or partial exemption from GDC-41 with No hydrogen and oxygen and other substances SCVB-14, 2 a,b Full or partial exemption from GDC-41 pos- No tulated accidents SCVB-14, 3 a,b Full or partial exemption from GDC-41 Leak No detection and isolation SCVB-14, 4 a,b Full or partial exemption from GDC-41 No LOOP SCVB-14, 5 a,b Full or partial exemption from GDC-41 Single No failure SCVB-15 Associated SSCs, procedures and activities No supporting operation of ECCS 30
RoverD RAI impact - SCVB RAI Description RoverD eliminates?
SCVB-16, 1 a,b Full or partial exemption from GDC-35 fuel No and clad damage SCVB-16, 2 a,b Full or partial exemption from GDC-35 fol- No lowing any LOCA SCVB-16, 3 a,b Full or partial exemption from GDC-35 leak No detection and isolation SCVB-16, 4 a,b Full or partial exemption from GDC-35 No LOOP SCVB-16, 5 a,b Full or partial exemption from GDC-35 Single No failure SCVB-17 Justify inputs and assumptions are conserva- No tive SCVB-18a M&E Mass subtracted from the pool No SCVB-18b Table of major qualitative differences No SCVB-18c Summary Comparison of Main Parameter No Values SCVB-18d Heat transfer properties of materials No 31
Technical Specification Concept
- 3Q15 supplement to application will include a proposed LAR to change Technical Specifications to specifically address effects of debris
- Adds clarity to where the plant is in TS space for emergent conditions
- Eliminates issue of applying PRA (risk) to determine operability
- Expect a long Completion Time
- Adequate to resolve the condition
- RG 1.174 risk evaluation provides basis for the proposed Completion Time 32
Technical Specification Concept
Reactor Containment Building emergency sump shall be OPERABLE by limiting the containment debris quantities to be less than or equal to the STP debris analysis assumptions.
With less than the required [ECCS or Containment Spray] Systems OPERABLE due to potential effects of debris, perform the following:
- a. immediately initiate action to implement compensatory actions, and
- b. within [90 days] restore the affected system(s) to OPERABLE status, 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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, 33
Technical Specification Bases
- Only systems that rely on strainers
- Applies only for debris-related conditions
- All applicable TS actions must be entered
- If maintenance is required or concurrent non-debris related condition is identified, the applicable TS action must be entered.
- Debris-related TS will continue to apply
- OPERABILITY is based on deterministic evaluation of characteristics of debris and consistency with STP debris analysis
- Intent is that risk calculation is not needed to make the operability determination
- Recognizes that there is margin and conservatism in the debris assumptions used for the deterministic testing and in the debris generation and transport analysis that can be applied to emergent condition
- Compensatory Action may include:
- Remove the debris or source of debris or take action that would prevent transport of the debris to the emergency sump
- Defer maintenance that would affect availability of the affected systems and strainers
- Increase frequency of RCS leak detection monitoring
- Brief operators on LOCA debris management actions
- Conceptual 90-day required action time is conservative and reasonable
- Based on very low contribution of debris to core damage frequency
- Break frequency of 4E-07/yr for smallest break that results in debris-related failure (pressurizer surge line)
- Operability can be restored by mitigation of the debris or by performing a calculation that shows the Licensing Basis is maintained 34
Operability Considerations
- The Licensing Basis with regard to effects of debris is that there is a high probability that ECCS and CSS can perform their design basis functions based on plant-specific prototypical testing using deterministic NRC-approved assumptions, and that the risk from breaks that could generate debris that is not bounded by the testing is very small in accordance with the criteria of RG 1.174.
- The affected ECCS and CSS are OPERABLE with respect to the effects of debris when the quantity and characteristics of the debris assumed in the plant debris analysis bounds the potential quantity and characteristics of transportable debris present in the Reactor Containment Building.
- Shift Manager will have debris-related reference material to assist in making the Immediate Operability Determination and to support requesting a Prompt Operability Determination
- An emergent condition outside the as-analyzed conditions is within the LB if the risk remains in the RG 1.174 criteria and could be considered Operable
- Proposed LCO would require Operator to enter TS action
- Determining that the condition is within the RG 1.174 LB allows exiting TS action or determining that there has not been a TS violation 35
Expected Content of Application Supplement
- Incorporates RoverD as primary basis
- Restructured to separate RoverD scope and supporting analyses from CASA Grande and Volume 2 (PRA)
- Revises requested exemption to 50.46(b) to be request for exemption from 50.46(d)
- Incorporates TS change and clarifies UFSAR markups
Areas for Clarification
- Disposition of RAIs that may be resolved or made non-relevant by use of RoverD (e.g., head loss)
- RoverD submittal should facilitate this
- Role of CASA Grande conditional probabilities and quantification based on correlations
- Include those sections of Vol. 2 & 3 as an Appendix to the Supplement and describe as providing additional confidence in validity of RoverD
- Need for additional testing
- RoverD assessment indicates additional testing is not needed
- Agreement on submittal process and content
- Technical Specification requirements and Operability 37
Conclusions
- RoverD simplifies application and preserves the very small risk per RG 1.174
- Proposed Technical Specification is consistent with the analysis and uncomplicated
- Need to address content of the STP application and RAI responses 38