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| | issue date = 12/18/2012 | | | issue date = 12/18/2012 |
| | title = PG&E Handouts from the December 18, 2012, Meeting with the NRC Related to Emergency Core Cooling System Evaluations (TAC Nos. MF0313 and MF0315) | | | title = PG&E Handouts from the December 18, 2012, Meeting with the NRC Related to Emergency Core Cooling System Evaluations (TAC Nos. MF0313 and MF0315) |
| | author name = Andrachek J D, Fink D J, Gresham J, Schrader K, Sharp M, Summy J | | | author name = Andrachek J, Fink D, Gresham J, Schrader K, Sharp M, Summy J |
| | author affiliation = Pacific Gas & Electric Co, Westinghouse Electric Co | | | author affiliation = Pacific Gas & Electric Co, Westinghouse Electric Co |
| | addressee name = | | | addressee name = |
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| | docket = 05000275, 05000323 | | | docket = 05000275, 05000323 |
| | license number = DPR-080, DPR-082 | | | license number = DPR-080, DPR-082 |
| | contact person = Sebrosky J M | | | contact person = Sebrosky J |
| | case reference number = TAC MF0313, TAC MF0315 | | | case reference number = TAC MF0313, TAC MF0315 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 19 | | | page count = 19 |
| | project = TAC:MF0313, TAC:MF0315 | | | project = TAC:MF0313, TAC:MF0315 |
| | | stage = Meeting |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:DiabloCanyonPowerPlantDiablo Canyon Power Plant Use of Leak-before-break for Fuel Structural AnalysesJeff SummyKen Schrader Mark SharpPacific Gas & Electric Co.Jim GreshamDave Fink Jim AndrachekWestinghouseDecember 18, 20121 ObjectivesDescribe the Licensing Basis Verification ProjectDescribe the Issue in the Corrective Action ProgramDescribe the Emergency Core Cooling System (ECCS) lfdif10CFR5046(b)(1)(b)(2)analyses performed to satisfy 10CFR50.46(b)(1), (b)(2), (b)(3), (b)(4), and (b)(5) DescribethefuelassemblyseismicandLOCAstructuralDescribe the fuel assembly seismic and LOCA structural analysis and the interface with 10CFR50.46 (b)(4)Actions going forwardQuestions and Feedback2 LicensingBasisVerificationProgramPG&E is performing a Licensing Basis Verification Project (LBVP) for DiabloCanyonLicensing Basis Verification ProgramDiablo CanyonThe LBPV is a comprehensive program to verify the Diablo Canyon licensing basis and to identify and correct deficiencies and inaccuraciesinaccuraciesThe goal of the LBVP is to develop a clear and accurate licensing basis for Diablo Canyon3 DescriptionofNonConformingConditionPG&E identified a potential deficiency in the way that the use of leak-before-break(LBB)methodologywasincorporatedintoDescription of Non-Conforming Conditionleakbeforebreak (LBB) methodology was incorporated into licensing basis Specifically, PG&E did not perform a 10 CFR 50.59 review for a changewhereLBBmethodologywasimplementedtoexcludethechange where LBB methodology was implemented to exclude the dynamic effects of a break in the main loop piping in the fuel assembly structural analyses performed to address Appendix A of SRPSection42"FuelSystemDesign"SRP Section 4.2, Fuel System DesignThe results of the fuel assembly structural analyses are used in part to demonstrate compliance with the 10 CFR 50.46(b)(4) fuel lbltitcoolable geometry requirements On September 25, 2012, PG&E documented the deficiency as a non-conforming condition in the Diablo Canyon corrective action 4program DescriptionofNonConformingConditionAn operability determination was performed and the fuel and ECCS wasdeterminedtobeoperablebasedonthecurrentanalysisDescription of Non-Conforming Conditionwas determined to be operable based on the current analysis (WCAP-16946) conclusions being valid and previous NRC approval in licensing actions at two other plantsPG&EhasidentifiedasignificantamountofinformationonthePG&E has identified a significant amount of information on the existing Diablo Canyon licensing basis and how other plants have adopted use of LBB methodology in the fuel assembly structural analysesanalysesA summary of the information is provided in this presentation for discussion5 LOCA analyses performed tosatisfy10CFR5046to satisfy 10CFR50.46The NRC approved Diablo Canyon large break LOCA Emergency Core Cooling System (ECCS) analysis for each unit is based on NRC approved Westinghouse best-estimate LOCA (BELOCA) evaluation models:-Unit 1: WCAP-12945-P-A, Addendum 1-A-Unit 2: WCAP-16009-P-A (ASTRUM)AdblddilltilbkLOCAithilA double-ended guillotine large break LOCA in the main loop piping is considered in the ECCS analysis.6 LOCA analyses performed tosatisfy10CFR5046to satisfy 10CFR50.46In the BELOCA ECCS evaluation models, no credit is taken for LBB to eliminate primary coolant main loop piping breaks when demonstrating that the acceptance criteria of 10CFR50.46 are met:*(b)(1) -Peak Cladding Temperature*(b)(2) -Maximum Cladding Oxidation*(b)(3) -Maximum Hydrogen Generation*(b)(4) -Coolable Geometry ()()y*(b)(5) -Long Term Cooling7 LOCA analyses performed tosatisfy10CFR5046(b)(4)to satisfy 10CFR50.46(b)(4)Coolablegeometry is considered in the BELOCA ECCS gyanalyses by modeling the effects of individual rod or hot assembly fuel rod burst and blockage, and is satisfied by demonstratingcompliancewith10CFR5046b(1)demonstrating compliance with 10CFR50.46 b(1) and b(2)The BELOCA ECCS evaluation models, include additional evaluations to confirm coolablegeometry, beyond rod burst/blockage, in the ECCS analysis when fuel assembly /g,yygrid deformation is determined to occurWCAP-12945-P-A, Volume 5 Rev 1 describes methodMethoddependsonlocationofassemblieswithgrid8Method depends on location of assemblies with grid deformation, independent of break size LOCA analyses performed tosatisfy10CFR5046(b)(4)to satisfy 10CFR50.46(b)(4)BELOCA ECCS grid deformation modelgFuel assembly periphery grid deformation: No peak cladding temperature penalty assessedFuelassemblyinboard(interior)griddeformation:Fuel assembly in-board (interior) grid deformation: Additional evaluations performed as defined in WCAP-12945-P-A, Volume 5 Rev 19 LOCA analyses performed tosatisfy10CFR5046(b)(4)to satisfy 10CFR50.46(b)(4)ThefuelassemblyseismicandLOCAstructuralanalysisThe fuel assembly seismic and LOCA structural analysis determine if fuel grid deformation occurs due to the impact forces exceeding the minimum grid test strength TheDCPPBELOCAanalysesdonotneedtoaddresstheThe DCPP BELOCA analyses do not need to address the effect of grid deformation, since in-board (interior) grid deformation is not calculated to occur in the fuel assemblystructuralanalysesassembly structural analysesConsistent with the WCAP-12945-P-A, Volume 5, Revision 1 methodology10 Fuel assembly seismic and LOCAstructuralanalysisLOCA structural analysisThtDiblCflbliidThe current Diablo Canyon fuel assembly seismic and LOCA structural analysis is documented in WCAP-16946 that supported reactor head ltreplacementThe analysis is performed in accordance with AppendixAtoSRPSection4.2,"FuelSystemDesign"Appendix A to SRP Section 4.2, Fuel System Design "input for the fuel assembly response should include motions of the core plate, core shroud , fuel alignment plate, or other relevant structures (these motions should correspond to the break that produced the peak fuel assembly loadings in the primary coolant system and reactor internals analysis)"11 Fuel assembly seismic and LOCAstructuralanalysisLOCA structural analysisThthdlfthflttlliThe methodology for the fuel structural analyses is based on the NRC approved method contained in WCAP-9401-P-A, "Verification and Testing Analysis of th1717OtiidFlAbl"dtdAtthe 17x17 Optimized Fuel Assembly," dated August 1981SRSS combination of LOCA and seismic loadsReferenced in the Diablo Canyon LAR and associated Amendments 37/36 for the use of Vantage5OptimizedFuelVantage 5 Optimized Fuel12 Fuel assembly seismic and LOCAstructuralanalysisLOCA structural analysisThflttllitidiThe fuel structural analysis contained in WCAP-9401-P-A, "Verification and Testing Analysis of the 17x17 Optimized Fuel Assembly," used a main loop iibkf~1ft2piping break of ~ 1ft2Based on a reactor vessel inlet nozzle break being structurally limited to less than 1ft2The same break size was assumed in a report for Diablo Canyon, "Response to Combinations of CalculatedLoadsForPipeBreakandEarthquake,"Calculated Loads For Pipe Break and Earthquake, submitted to the NRC on February 2, 1978 and referenced in Supplement 8 to the Safety EvaluationReportdatedNovember15,197813Evaluation Report dated November 15, 1978 Fuel assembly seismic andLOCAstructuralanalysisand LOCA structural analysisThNRCdthLBBli(WCAP13039)fThe NRC approved the LBB analysis (WCAP-13039) for the Diablo Canyon main loop piping in a Safety Evaluation dated March 2, 1993SffliThffldhhli'LBBStaff conclusion: The staff concludes that the licensee's LBB analysis is consistent with the criteria in NUREG-1061, Volume 3, and draft SRP 3.6.3.; therefore, the analysis complies withGDC-4.Thus,theprobabilityoflargepipebreakswith GDC4. Thus, the probability of large pipe breaks occurring in the RCS line is sufficiently low that the dynamic effects associated with postulated pipe breaks need not be a design basis14 Fuel assembly seismic andLOCAstructuralanalysisand LOCA structural analysisThitlddithflblThe pipe rupture loads used in the fuel assembly structural analyses (WCAP-16946), are based on the most limiting of an accumulator, pressurizer surge line, dRHRbhlibkand RHR branch line breaksLimitation of breaks to branch line breaks (exclusion of mainloopbreaks)isbasedonapplicationoftheLBBmain loop breaks) is based on application of the LBB methodology in accordance with the 1987 revision to GDC-4 AllowsexclusionofdynamiceffectsfromthedesignbasisAllows exclusion of dynamic effects from the design basis analyses when LBB analyses are approved by the Commission15 Fuel assembly seismic and LOCA structural analysisThe NRC Leak-Before-Break Knowledge Management Document (page 3) provides additional information on (pg)pthe dynamic effects that can be excluded when LBB is approved*OnlylocaldynamiceffectsOnly local dynamic effects*Discharging fluidsThe NRC Leak-Before-Break Knowledge Management ()lDocument (page 3) provides permitted plant activities*Decompression waves within the intact portion of the piping system16 Fuel assembly seismic andLOCAstructuralanalysisand LOCA structural analysisWCAP-16498-NP, "17x17 Next Generation Fuel (17x17 NGF),"datedMarch2008,hasstatedfuelqualificationNGF), dated March 2008, has stated fuel qualification analyses are performed postulating the rupture of branch lines connected to the main coolant loop (page 61):"Currently, all Westinghouse designed US PWR primary coolant main loop piping has been excluded from consideration for dynamic effects associated with postulatedpiperuptureunderReference61orpostulated pipe rupture under Reference 61 or subsequent LBB analyses. As a result, all current fuel qualification analyses are performed on the basis of postulated rupture of branch lines connected to the iltl"primary coolant loop."WCAP-16498-NP was approved in an NRC Safety Evaluation dated March 16, 2011 17, Fuel assembly seismic andLOCAstructuralanalysisand LOCA structural analysisThe Staff recently approved the use of LBB for fuel assemblyseismicandLOCAstructuralanalysesaspartassembly seismic and LOCA structural analyses as part of the Turkey Point Units 3 and 4 Extended Power Uprate Licensing Amendment Request in a letter dated June 15, 2012 (ML11293A356)Section 2.8.1 of the NRC Safety Evaluation reflected use of WCA-9401-P-A methodology and use of largest branch line breaksThe licensee evaluated seismic and LOCA loading using the approved methodology described in WCAP-9401-P-A-The largest branch line breaks, either the accumulator line (ACC) break, surge line break, or RHR line break, were considered when generating LOCA hydraulic forcingfunctionsusedasinputtotheanalysis18forcing functions used as input to the analysis ResolutionofIssueResolution of IssuePG&E is prepared to take the actions necessary to resolve the non-conforming condition and improve the gplicensing basisPG&E is determining what conservative approach is idddhfidiidrequired to address the non-conforming condition and close the operability determinationPG&EplanstoworkcollaborativelywiththeStafftoPG&E plans to work collaboratively with the Staff to understand and resolve the issue19 | | {{#Wiki_filter:Diablo Canyon Power Plant Use of Leak-before-break for Fuel Structural Analyses Jeff Summy Ken Schrader Mark Sharp Pacific Gas & Electric Co. |
| }} | | Jim Gresham Dave Fink Jim Andrachek Westinghouse December 18, 2012 1 |
| | |
| | Objectives Describe the Licensing Basis Verification Project Describe the Issue in the Corrective Action Program Describe the Emergency Core Cooling System (ECCS) analyses l performed f d to satisfy i f 10CFR50 10CFR50.46(b)(1), |
| | 46(b)(1) (b)(2) |
| | (b)(2), |
| | (b)(3), (b)(4), and (b)(5) |
| | Describe the fuel assembly seismic and LOCA structural analysis and the interface with 10CFR50.46 (b)(4) |
| | Actions going forward Questions and Feedback 2 |
| | |
| | Licensing Basis Verification Program PG&E is performing a Licensing Basis Verification Project (LBVP) for Diablo Canyon The LBPV is a comprehensive program to verify the Diablo Canyon licensing basis and to identify and correct deficiencies and inaccuracies The goal of the LBVP is to develop a clear and accurate licensing basis for Diablo Canyon 3 |
| | |
| | Description of Non-Conforming Non Conforming Condition PG&E identified a potential deficiency in the way that the use of leak-before-break leak before break (LBB) methodology was incorporated into licensing basis Specifically, PG&E did not perform a 10 CFR 50.59 review for a change where LBB methodology was implemented to exclude the dynamic effects of a break in the main loop piping in the fuel assembly structural analyses performed to address Appendix A of SRP Section 4.2, 4 2 Fuel Fuel System Design Design The results of the fuel assembly structural analyses are used in part to demonstrate compliance with the 10 CFR 50.46(b)(4) fuel coolable l bl geometryt requirements i t On September 25, 2012, PG&E documented the deficiency as a non-conforming condition in the Diablo Canyon corrective action program 4 |
| | |
| | Description of Non-Conforming Non Conforming Condition An operability determination was performed and the fuel and ECCS was determined to be operable based on the current analysis (WCAP-16946) conclusions being valid and previous NRC approval in licensing actions at two other plants PG&E has identified a significant amount of information on the existing Diablo Canyon licensing basis and how other plants have adopted use of LBB methodology in the fuel assembly structural analyses A summary of the information is provided in this presentation for discussion 5 |
| | |
| | LOCA analyses performed to satisfy 10CFR50.46 10CFR50 46 The NRC approved Diablo Canyon large break LOCA Emergency Core Cooling System (ECCS) analysis for each unit is based on NRC approved Westinghouse best-estimate LOCA (BELOCA) evaluation models: |
| | - Unit 1: WCAP-12945-P-A, Addendum 1-A |
| | - Unit 2: WCAP-16009-P-A (ASTRUM) |
| | A double-ended d bl d d guillotine ill ti llarge b breakk LOCA iin th the main i lloop piping is considered in the ECCS analysis. |
| | 6 |
| | |
| | LOCA analyses performed to satisfy 10CFR50.46 10CFR50 46 In the BELOCA ECCS evaluation models, no credit is taken for LBB to eliminate primary coolant main loop piping breaks when demonstrating that the acceptance criteria of 10CFR50.46 are met: |
| | * (b)(1) - Peak Cladding Temperature |
| | * (b)(2) - Maximum Cladding Oxidation |
| | * (b)(3) - Maximum Hydrogen Generation |
| | * ((b)(4) |
| | )( ) - Coolable Geometryy |
| | * (b)(5) - Long Term Cooling 7 |
| | |
| | LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4) |
| | Coolable ggeometryy is considered in the BELOCA ECCS analyses by modeling the effects of individual rod or hot assembly fuel rod burst and blockage, and is satisfied by demonstrating compliance with 10CFR50 10CFR50.4646 b(1) and b(2) |
| | The BELOCA ECCS evaluation models, include additional evaluations to confirm coolable geometry, beyond rod |
| | / g , in the ECCS analysis burst/blockage, y when fuel assemblyy grid deformation is determined to occur WCAP-12945-P-A, Volume 5 Rev 1 describes method Method depends on location of assemblies with grid deformation, independent of break size 8 |
| | |
| | LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4) |
| | BELOCA ECCS ggrid deformation model Fuel assembly periphery grid deformation: No peak cladding temperature penalty assessed Fuel assembly in in-board board (interior) grid deformation: |
| | Additional evaluations performed as defined in WCAP-12945-P-A, Volume 5 Rev 1 9 |
| | |
| | LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4) |
| | The fuel assembly seismic and LOCA structural analysis determine if fuel grid deformation occurs due to the impact forces exceeding the minimum grid test strength The DCPP BELOCA analyses do not need to address the effect of grid deformation, since in-board (interior) grid deformation is not calculated to occur in the fuel assembly structural analyses Consistent with the WCAP-12945-P-A, Volume 5, Revision 1 methodology 10 |
| | |
| | Fuel assembly seismic and LOCA structural analysis Th The currentt DiDiablo bl C Canyon ffuell assembly bl seismic i i and d LOCA structural analysis is documented in WCAP-16946 that supported reactor head replacement l t The analysis is performed in accordance with Appendix A to SRP Section 4.2, Fuel Fuel System Design Design input for the fuel assembly response should include motions of the core plate, core shroud , fuel alignment plate, or other relevant structures (these motions should correspond to the break that produced the peak fuel assembly loadings in the primary coolant system and reactor internals analysis) 11 |
| | |
| | Fuel assembly seismic and LOCA structural analysis Th The methodology th d l ffor th the ffuell structural t t l analyses l iis based on the NRC approved method contained in WCAP-9401-P-A, Verification and Testing Analysis of th 17 the 17x17 17 OOptimized ti i d FFuell A Assembly, bl d dated t dAAugustt 1981 SRSS combination of LOCA and seismic loads Referenced in the Diablo Canyon LAR and associated Amendments 37/36 for the use of Vantage 5 Optimized Fuel 12 |
| | |
| | Fuel assembly seismic and LOCA structural analysis Th The ffuell structural t t l analysis l i contained t i d iin WCAP-9401-P-A, Verification and Testing Analysis of the 17x17 Optimized Fuel Assembly, used a main loop piping i i b breakk off ~ 1ft2 Based on a reactor vessel inlet nozzle break being structurally limited to less than 1ft2 The same break size was assumed in a report for Diablo Canyon, Response to Combinations of Calculated Loads For Pipe Break and Earthquake, Earthquake, submitted to the NRC on February 2, 1978 and referenced in Supplement 8 to the Safety Evaluation Report dated November 15, 1978 13 |
| | |
| | Fuel assembly seismic and LOCA structural analysis Th The NRC approved d th the LBB analysisl i (WCAP (WCAP-13039) 13039) for f |
| | the Diablo Canyon main loop piping in a Safety Evaluation dated March 2, 1993 SStaff ff conclusion: |
| | l i Th staff The ff concludes l d that h theh lilicensee's |
| | ' LBB analysis is consistent with the criteria in NUREG-1061, Volume 3, and draft SRP 3.6.3.; therefore, the analysis complies with GDC GDC-4. |
| | : 4. Thus, the probability of large pipe breaks occurring in the RCS line is sufficiently low that the dynamic effects associated with postulated pipe breaks need not be a design basis 14 |
| | |
| | Fuel assembly seismic and LOCA structural analysis Th The pipe i rupture t lloads d usedd iin th the ffuell assembly bl structural analyses (WCAP-16946), are based on the most limiting of an accumulator, pressurizer surge line, andd RHR branch b h liline b breaks k |
| | Limitation of breaks to branch line breaks (exclusion of main loop breaks) is based on application of the LBB methodology in accordance with the 1987 revision to GDC-4 Allows exclusion of dynamic effects from the design basis analyses when LBB analyses are approved by the Commission 15 |
| | |
| | Fuel assembly seismic and LOCA structural analysis The NRC Leak-Before-Break Knowledge Management Document (p (page g 3)) pprovides additional information on the dynamic effects that can be excluded when LBB is approved |
| | * Only local dynamic effects |
| | * Discharging fluids The NRC Leak-Before-Break Knowledge Management Document (page |
| | ( 3)) provides permitted plant l activities |
| | * Decompression waves within the intact portion of the piping system 16 |
| | |
| | Fuel assembly seismic and LOCA structural analysis WCAP-16498-NP, 17x17 Next Generation Fuel (17x17 NGF), dated March 2008, has stated fuel qualification NGF), |
| | analyses are performed postulating the rupture of branch lines connected to the main coolant loop (page 61): |
| | Currently, all Westinghouse designed US PWR primary coolant main loop piping has been excluded from consideration for dynamic effects associated with postulated pipe rupture under Reference 61 or subsequent LBB analyses. As a result, all current fuel qualification analyses are performed on the basis of postulated rupture of branch lines connected to the primary i coolant l t lloop. |
| | WCAP-16498-NP was approved in an NRC Safety Evaluation dated March 16,, 2011 17 |
| | |
| | Fuel assembly seismic and LOCA structural analysis The Staff recently approved the use of LBB for fuel assembly seismic and LOCA structural analyses as part of the Turkey Point Units 3 and 4 Extended Power Uprate Licensing Amendment Request in a letter dated June 15, 2012 (ML11293A356) |
| | Section 2.8.1 of the NRC Safety Evaluation reflected use of WCA-9401-P-A methodology and use of largest branch line breaks The licensee evaluated seismic and LOCA loading using the approved methodology described in WCAP-9401-P-A The largest branch line breaks, either the accumulator line (ACC) break, surge line break, or RHR line break, were considered when generating LOCA hydraulic forcing functions used as input to the analysis 18 |
| | |
| | Resolution of Issue PG&E is prepared to take the actions necessary to resolve the non-conformingg condition and improve p the licensing basis PG&E is determining what conservative approach is required i d to address dd the h non-conforming f i condition di i and d close the operability determination PG&E plans to work collaboratively with the Staff to understand and resolve the issue 19}} |
Letter Sequence Meeting |
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MONTHYEARML12338A0762012-12-0404 December 2012
Notice of Forthcoming Preapplication Meeting on 12/18/12 with Pacific Gas and Electric Company to Discuss Leak Before Break Assumptions Used in 10 CFR 50.46 Evaluation for Diablo Canyon, Units 1 and 2
Project stage: Meeting
ML12355A1612012-12-18018 December 2012
PG&E Handouts from the December 18, 2012, Meeting with the NRC Related to Emergency Core Cooling System Evaluations (TAC Nos. MF0313 and MF0315)
Project stage: Meeting
ML12355A1502013-01-22022 January 2013
Summary of Preapplication Meeting with Pacific Gas and Electric Company to Discuss Leak Before Break Assumptions Used in 10 CFR 50.46 Evaluation for Diablo Canyon, Units 1 and 2
Project stage: Meeting
2012-12-04
[Table View] |
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|---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24036A3382024-02-0505 February 2024
Environmental Scoping Meeting for the Diablo Canyon License Renewal Application - February 8 Meeting Slides
ML24030A4672024-01-30030 January 2024
Environmental Scoping Meeting for the Diablo Canyon License Renewal Application - February 1 Meeting Slides
ML23249A1592023-09-13013 September 2023
License Renewal Application Pre-Application Meeting: September 13, 2023
ML23255A0012023-09-13013 September 2023
PG&E Slides for 9/13 Public Meeting Related to Diablo Canyon License Renewal
ML23174A0562023-06-26026 June 2023
Slides for TSTF-505 Pre-Submittal Public Teleconference 6-26-2023
ML23143A0882023-05-24024 May 2023
May 24, 2023, Public Meeting Slides Related to Diablo Canyon License Renewal
ML23118A0902023-05-0303 May 2023
May 3, 2023, Diablo Public Meeting Slides
ML23143A0952023-05-0303 May 2023
May 3, 2023, Diablo Public Meeting Slides for PG&E Presentation
ML23079A0452023-03-16016 March 2023
RIC 2023 Slides - Maureen Zawalick TH19
ML22339A1022022-12-0505 December 2022
Pg_E Presentation for NRC Public Meeting
ML22200A0712022-07-21021 July 2022
Post-Shutdown Decommissioning Activities Report Public Meeting Slides - July 21, 2022
ML22200A0722022-07-21021 July 2022
PG&E Slides for Post-Shutdown Decommissioning Activities Report Public Meeting, Site-Specific Decommissioning Cost Estimate, and Irradiated Fuel Management Plan - July 21, 2022
ML21223A0842021-08-11011 August 2021
Slides for Post Shutdown EP pre-submittal Public Teleconference 8-30-2021
ML21060B1872020-01-26026 January 2020
Enclosure 3 - 1-26-21 Diablo Canyon Renewal pre-app Meeting Slides
ML19165A0092019-06-14014 June 2019
Pre-Submittal Meeting - Presentation Slides
ML18333A1092018-11-28028 November 2018
Presentation Slides for Diablo Public Meeting to Discuss Proposed Exemption Request for Decommissioning Funds
ML17296A2222017-08-29029 August 2017
Presentation on Reactor Decommissioning for the August 29, 2017 at Congressman Salud Carbajal'S Public Meeting at San Luis Obispo Near Diablo Canyon
ML15232A0102015-08-0404 August 2015
Diablo Canyon Power Plant - Risk-Informed Technical Specification Completion Times (TSTF-505) License Amendment Request: August 4, 2015
ML15216A4112015-08-0404 August 2015
TSTF-505: August 4, 2015 Public Meeting
ML15216A4082015-08-0404 August 2015
Diablo Canyon Power Plant - Risk-Informed Technical Specification Completion Times (TSTF-505) License Amendment Request: August 4, 2015
ML15209A9442015-07-28028 July 2015
June 24, 2015, Summary of Annual Assessment Meeting with Pacific Gas and Electric and Public Open House Regarding Diablo Canyon Power Plant 2014 Performance
ML15202A0982015-07-21021 July 2015
Slides for the August 5, 2015 Diablo Canyon Power Plant License Renewal Application Public Scoping Meeting
ML15117A0692015-04-28028 April 2015
Pacific Gas and Electric Co. April 28, 2015, Public Meeting Slides for Diablo Canyon Seismic Hazard Reevaluation
ML15117A2262015-04-28028 April 2015
Nuclear Regulatory Commission April 28, 2015, Public Meeting Slides for Diablo Canyon Seismic Hazard Reevaluation
ML15035A0062015-02-0404 February 2015
Meeting Presentation, Diablo Canyon Power Plant Process Protection System Replacement Lessons Learned Using ISG 6 NRC Meeting on Digital I&C.
ML15029A0942015-02-0303 February 2015
Alternate Source Term Pre- Submittal Meeting on February 3, 2015 (TAC Nos. MF5596 and MF5597). AST LAR NRC Meeting Presentation
ML15014A2232015-01-14014 January 2015
Slides Regulatory Conference - January 14, 2015
ML14188A9702014-07-0808 July 2014
14-07-08 ISG-06 Experience Presentation July 8 2014 Digital IC Meeting
ML14155A3742014-06-0404 June 2014
May 22, 2014, Summary of Annual Assessment Meeting with Pacific Gas and Electric Regarding Diablo Canyon Power Plant 2013 Performance
ML14077A2872014-03-18018 March 2014
Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317
ML13150A1712013-11-19019 November 2013
1978 - Rhrp Cavitation
ML13274A5142013-10-0202 October 2013
License Slides, 10/2/13 Pre-Application Meeting with Pacific Gas and Electric Company to Discuss Upcoming Structural Weld Overlay Relief Request to Use an Alternative to Disposition Detected Laminar Indications at Diablo Canyon, Unit 2 (TAC
ML13269A0052013-09-26026 September 2013
Licensee Slides for 9/26/13 Meeting to Discuss Amendment Request to Adopt Technical Specifications Task Force TSTF-505, Provide Risk-Informed Extended Completion Times, RITSTF Initiative 4B
ML13268A0022013-09-25025 September 2013
Slide Presentation for 9/25/13 Preapplication Meeting - Use of Leak-before-break for Fuel Structural Analyses and Coolable Geometry
ML13268A0052013-09-24024 September 2013
Slide Presentation for 9/24/13 Pre-application Meeting, Diesel Generator License Amendment Request
ML13159A0092013-06-0404 June 2013
Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting
ML13066A7402013-03-0707 March 2013
Licensee Slides from 3/7/13 Pre-Application Meeting with Pacific Gas and Electric Company(Tac MF0687 & MF0688)
ML13044A7352013-02-12012 February 2013
Licensee Slides from 2/12/13 Public Meeting to Discuss License Amendment Requests for Degraded Voltage Protection and Control Room Dose Analysis of Record at Diablo Canyon, Units 1 and 2
ML13024A4052013-01-24024 January 2013
Licensee Slides from 1/24/13 Meeting to Discuss Offsite Power
ML13018A1342013-01-15015 January 2013
Pacific Gas and Electric Handouts from January 15, 2013 Meeting Regarding Pending License Amendment Request Related to Diesel Generator Technical Specifications
ML12355A1612012-12-18018 December 2012
PG&E Handouts from the December 18, 2012, Meeting with the NRC Related to Emergency Core Cooling System Evaluations (TAC Nos. MF0313 and MF0315)
ML12347A3102012-12-12012 December 2012
Summary of Meeting with Public on Diablo Canyon Power Plant
ML12311A0492012-09-18018 September 2012
Part 26 Public Meeting NEI Presentation Slides
ML12226A2552012-08-0707 August 2012
License Slides from 8/7/12 Meeting with Pacific Gas and Electric Regarding Future License Amendment Associated with Diesel Generator Technical Specifications
ML12193A1412012-07-25025 July 2012
6/28/2012 Summary of Meeting with Pacific Gas and Electric to Discuss Digital Replacement of Process Protection System at Diablo Canyon, Units 1 and 2 and Presubmittal of TSTF-493 Option B License Amendment Request (TAC ME7522-ME7523, ME851
ML12157A2722012-06-11011 June 2012
5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a
ML1202500572012-01-18018 January 2012
Meeting Slides Process Protection System Replacement LAR Acceptance Review Meeting Presentation
ML1202500792012-01-18018 January 2012
Project Plan for Diablo Canyon Digital Upgrade of Process Protection System LAR Review
ML1117205702011-06-20020 June 2011
Licensee Slides from 6/20/11 Pre-Licensing Meeting on Seismic License Amendment Request
ML1116405342011-06-0707 June 2011
Slides from Meeting with Pacific Gas and Electric Company Regarding Diablo Canyon Process Protection System Replacement
2024-02-05
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Category:Slides and Viewgraphs
MONTHYEARML24036A3382024-02-0505 February 2024
Environmental Scoping Meeting for the Diablo Canyon License Renewal Application - February 8 Meeting Slides
ML24030A4672024-01-30030 January 2024
Environmental Scoping Meeting for the Diablo Canyon License Renewal Application - February 1 Meeting Slides
ML23255A0012023-09-13013 September 2023
PG&E Slides for 9/13 Public Meeting Related to Diablo Canyon License Renewal
ML23249A1592023-09-13013 September 2023
License Renewal Application Pre-Application Meeting: September 13, 2023
ML23174A0562023-06-26026 June 2023
Slides for TSTF-505 Pre-Submittal Public Teleconference 6-26-2023
ML23143A0882023-05-24024 May 2023
May 24, 2023, Public Meeting Slides Related to Diablo Canyon License Renewal
ML23118A0902023-05-0303 May 2023
May 3, 2023, Diablo Public Meeting Slides
ML23143A0952023-05-0303 May 2023
May 3, 2023, Diablo Public Meeting Slides for PG&E Presentation
ML23079A0452023-03-16016 March 2023
RIC 2023 Slides - Maureen Zawalick TH19
ML22339A1022022-12-0505 December 2022
Pg_E Presentation for NRC Public Meeting
ML22236A5472022-08-24024 August 2022
NRC Slides for Decommissioning Engagement Panel 8-24-2022 Meeting
ML22200A0712022-07-21021 July 2022
Post-Shutdown Decommissioning Activities Report Public Meeting Slides - July 21, 2022
ML22200A0722022-07-21021 July 2022
PG&E Slides for Post-Shutdown Decommissioning Activities Report Public Meeting, Site-Specific Decommissioning Cost Estimate, and Irradiated Fuel Management Plan - July 21, 2022
ML21223A0842021-08-11011 August 2021
Slides for Post Shutdown EP pre-submittal Public Teleconference 8-30-2021
ML20310A2792020-11-0505 November 2020
Slides for Defueled TS Pre-Submittal Public Teleconference November 24, 2020 (L-2020-LRM-0101)
ML21060B1872020-01-26026 January 2020
Enclosure 3 - 1-26-21 Diablo Canyon Renewal pre-app Meeting Slides
ML19233A0722019-08-27027 August 2019
NEIMA Meeting Slides Public
ML18295A0732018-10-24024 October 2018
Final Diablo Canyon Decommissioning Engagement Panel Meeting Oct 24 2018
ML17296A2222017-08-29029 August 2017
Presentation on Reactor Decommissioning for the August 29, 2017 at Congressman Salud Carbajal'S Public Meeting at San Luis Obispo Near Diablo Canyon
ML16335A4392016-11-30030 November 2016
PG&E Reg Conference Presentation - NRC-11152016
ML15232A0102015-08-0404 August 2015
Diablo Canyon Power Plant - Risk-Informed Technical Specification Completion Times (TSTF-505) License Amendment Request: August 4, 2015
ML15216A4112015-08-0404 August 2015
TSTF-505: August 4, 2015 Public Meeting
ML15216A4082015-08-0404 August 2015
Diablo Canyon Power Plant - Risk-Informed Technical Specification Completion Times (TSTF-505) License Amendment Request: August 4, 2015
ML15209A9442015-07-28028 July 2015
June 24, 2015, Summary of Annual Assessment Meeting with Pacific Gas and Electric and Public Open House Regarding Diablo Canyon Power Plant 2014 Performance
ML15202A0982015-07-21021 July 2015
Slides for the August 5, 2015 Diablo Canyon Power Plant License Renewal Application Public Scoping Meeting
ML15117A2262015-04-28028 April 2015
Nuclear Regulatory Commission April 28, 2015, Public Meeting Slides for Diablo Canyon Seismic Hazard Reevaluation
ML15117A0692015-04-28028 April 2015
Pacific Gas and Electric Co. April 28, 2015, Public Meeting Slides for Diablo Canyon Seismic Hazard Reevaluation
ML15035A0062015-02-0404 February 2015
Meeting Presentation, Diablo Canyon Power Plant Process Protection System Replacement Lessons Learned Using ISG 6 NRC Meeting on Digital I&C.
ML15029A0942015-02-0303 February 2015
Alternate Source Term Pre- Submittal Meeting on February 3, 2015 (TAC Nos. MF5596 and MF5597). AST LAR NRC Meeting Presentation
ML15014A2232015-01-14014 January 2015
Slides Regulatory Conference - January 14, 2015
ML14195A3742014-07-10010 July 2014
Update of Industry Actions Related to Diablo Canyon OE
ML14188A9702014-07-0808 July 2014
14-07-08 ISG-06 Experience Presentation July 8 2014 Digital IC Meeting
ML14155A3742014-06-0404 June 2014
May 22, 2014, Summary of Annual Assessment Meeting with Pacific Gas and Electric Regarding Diablo Canyon Power Plant 2013 Performance
ML14077A2872014-03-18018 March 2014
Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317
ML13150A1712013-11-19019 November 2013
1978 - Rhrp Cavitation
ML13150A1812013-11-19019 November 2013
Trade-Off Between Tank Vortexing Margin and ECCS Function
ML13274A5142013-10-0202 October 2013
License Slides, 10/2/13 Pre-Application Meeting with Pacific Gas and Electric Company to Discuss Upcoming Structural Weld Overlay Relief Request to Use an Alternative to Disposition Detected Laminar Indications at Diablo Canyon, Unit 2 (TAC
ML13269A0052013-09-26026 September 2013
Licensee Slides for 9/26/13 Meeting to Discuss Amendment Request to Adopt Technical Specifications Task Force TSTF-505, Provide Risk-Informed Extended Completion Times, RITSTF Initiative 4B
ML13268A0022013-09-25025 September 2013
Slide Presentation for 9/25/13 Preapplication Meeting - Use of Leak-before-break for Fuel Structural Analyses and Coolable Geometry
ML13268A0052013-09-24024 September 2013
Slide Presentation for 9/24/13 Pre-application Meeting, Diesel Generator License Amendment Request
ML13159A0092013-06-0404 June 2013
Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting
ML13066A7402013-03-0707 March 2013
Licensee Slides from 3/7/13 Pre-Application Meeting with Pacific Gas and Electric Company(Tac MF0687 & MF0688)
ML13044A7352013-02-12012 February 2013
Licensee Slides from 2/12/13 Public Meeting to Discuss License Amendment Requests for Degraded Voltage Protection and Control Room Dose Analysis of Record at Diablo Canyon, Units 1 and 2
ML13024A4052013-01-24024 January 2013
Licensee Slides from 1/24/13 Meeting to Discuss Offsite Power
ML13018A1342013-01-15015 January 2013
Pacific Gas and Electric Handouts from January 15, 2013 Meeting Regarding Pending License Amendment Request Related to Diesel Generator Technical Specifications
ML12355A1612012-12-18018 December 2012
PG&E Handouts from the December 18, 2012, Meeting with the NRC Related to Emergency Core Cooling System Evaluations (TAC Nos. MF0313 and MF0315)
ML12311A0492012-09-18018 September 2012
Part 26 Public Meeting NEI Presentation Slides
ML12226A2552012-08-0707 August 2012
License Slides from 8/7/12 Meeting with Pacific Gas and Electric Regarding Future License Amendment Associated with Diesel Generator Technical Specifications
ML12193A1412012-07-25025 July 2012
6/28/2012 Summary of Meeting with Pacific Gas and Electric to Discuss Digital Replacement of Process Protection System at Diablo Canyon, Units 1 and 2 and Presubmittal of TSTF-493 Option B License Amendment Request (TAC ME7522-ME7523, ME851
ML12157A2722012-06-11011 June 2012
5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a
2024-02-05
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Text
Diablo Canyon Power Plant Use of Leak-before-break for Fuel Structural Analyses Jeff Summy Ken Schrader Mark Sharp Pacific Gas & Electric Co.
Jim Gresham Dave Fink Jim Andrachek Westinghouse December 18, 2012 1
Objectives Describe the Licensing Basis Verification Project Describe the Issue in the Corrective Action Program Describe the Emergency Core Cooling System (ECCS) analyses l performed f d to satisfy i f 10CFR50 10CFR50.46(b)(1),
46(b)(1) (b)(2)
(b)(2),
(b)(3), (b)(4), and (b)(5)
Describe the fuel assembly seismic and LOCA structural analysis and the interface with 10CFR50.46 (b)(4)
Actions going forward Questions and Feedback 2
Licensing Basis Verification Program PG&E is performing a Licensing Basis Verification Project (LBVP) for Diablo Canyon The LBPV is a comprehensive program to verify the Diablo Canyon licensing basis and to identify and correct deficiencies and inaccuracies The goal of the LBVP is to develop a clear and accurate licensing basis for Diablo Canyon 3
Description of Non-Conforming Non Conforming Condition PG&E identified a potential deficiency in the way that the use of leak-before-break leak before break (LBB) methodology was incorporated into licensing basis Specifically, PG&E did not perform a 10 CFR 50.59 review for a change where LBB methodology was implemented to exclude the dynamic effects of a break in the main loop piping in the fuel assembly structural analyses performed to address Appendix A of SRP Section 4.2, 4 2 Fuel Fuel System Design Design The results of the fuel assembly structural analyses are used in part to demonstrate compliance with the 10 CFR 50.46(b)(4) fuel coolable l bl geometryt requirements i t On September 25, 2012, PG&E documented the deficiency as a non-conforming condition in the Diablo Canyon corrective action program 4
Description of Non-Conforming Non Conforming Condition An operability determination was performed and the fuel and ECCS was determined to be operable based on the current analysis (WCAP-16946) conclusions being valid and previous NRC approval in licensing actions at two other plants PG&E has identified a significant amount of information on the existing Diablo Canyon licensing basis and how other plants have adopted use of LBB methodology in the fuel assembly structural analyses A summary of the information is provided in this presentation for discussion 5
LOCA analyses performed to satisfy 10CFR50.46 10CFR50 46 The NRC approved Diablo Canyon large break LOCA Emergency Core Cooling System (ECCS) analysis for each unit is based on NRC approved Westinghouse best-estimate LOCA (BELOCA) evaluation models:
- Unit 1: WCAP-12945-P-A, Addendum 1-A
- Unit 2: WCAP-16009-P-A (ASTRUM)
A double-ended d bl d d guillotine ill ti llarge b breakk LOCA iin th the main i lloop piping is considered in the ECCS analysis.
6
LOCA analyses performed to satisfy 10CFR50.46 10CFR50 46 In the BELOCA ECCS evaluation models, no credit is taken for LBB to eliminate primary coolant main loop piping breaks when demonstrating that the acceptance criteria of 10CFR50.46 are met:
- (b)(1) - Peak Cladding Temperature
- (b)(2) - Maximum Cladding Oxidation
)( ) - Coolable Geometryy
- (b)(5) - Long Term Cooling 7
LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4)
Coolable ggeometryy is considered in the BELOCA ECCS analyses by modeling the effects of individual rod or hot assembly fuel rod burst and blockage, and is satisfied by demonstrating compliance with 10CFR50 10CFR50.4646 b(1) and b(2)
The BELOCA ECCS evaluation models, include additional evaluations to confirm coolable geometry, beyond rod
/ g , in the ECCS analysis burst/blockage, y when fuel assemblyy grid deformation is determined to occur WCAP-12945-P-A, Volume 5 Rev 1 describes method Method depends on location of assemblies with grid deformation, independent of break size 8
LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4)
BELOCA ECCS ggrid deformation model Fuel assembly periphery grid deformation: No peak cladding temperature penalty assessed Fuel assembly in in-board board (interior) grid deformation:
Additional evaluations performed as defined in WCAP-12945-P-A, Volume 5 Rev 1 9
LOCA analyses performed to satisfy 10CFR50.46(b)(4) 10CFR50 46(b)(4)
The fuel assembly seismic and LOCA structural analysis determine if fuel grid deformation occurs due to the impact forces exceeding the minimum grid test strength The DCPP BELOCA analyses do not need to address the effect of grid deformation, since in-board (interior) grid deformation is not calculated to occur in the fuel assembly structural analyses Consistent with the WCAP-12945-P-A, Volume 5, Revision 1 methodology 10
Fuel assembly seismic and LOCA structural analysis Th The currentt DiDiablo bl C Canyon ffuell assembly bl seismic i i and d LOCA structural analysis is documented in WCAP-16946 that supported reactor head replacement l t The analysis is performed in accordance with Appendix A to SRP Section 4.2, Fuel Fuel System Design Design input for the fuel assembly response should include motions of the core plate, core shroud , fuel alignment plate, or other relevant structures (these motions should correspond to the break that produced the peak fuel assembly loadings in the primary coolant system and reactor internals analysis) 11
Fuel assembly seismic and LOCA structural analysis Th The methodology th d l ffor th the ffuell structural t t l analyses l iis based on the NRC approved method contained in WCAP-9401-P-A, Verification and Testing Analysis of th 17 the 17x17 17 OOptimized ti i d FFuell A Assembly, bl d dated t dAAugustt 1981 SRSS combination of LOCA and seismic loads Referenced in the Diablo Canyon LAR and associated Amendments 37/36 for the use of Vantage 5 Optimized Fuel 12
Fuel assembly seismic and LOCA structural analysis Th The ffuell structural t t l analysis l i contained t i d iin WCAP-9401-P-A, Verification and Testing Analysis of the 17x17 Optimized Fuel Assembly, used a main loop piping i i b breakk off ~ 1ft2 Based on a reactor vessel inlet nozzle break being structurally limited to less than 1ft2 The same break size was assumed in a report for Diablo Canyon, Response to Combinations of Calculated Loads For Pipe Break and Earthquake, Earthquake, submitted to the NRC on February 2, 1978 and referenced in Supplement 8 to the Safety Evaluation Report dated November 15, 1978 13
Fuel assembly seismic and LOCA structural analysis Th The NRC approved d th the LBB analysisl i (WCAP (WCAP-13039) 13039) for f
the Diablo Canyon main loop piping in a Safety Evaluation dated March 2, 1993 SStaff ff conclusion:
l i Th staff The ff concludes l d that h theh lilicensee's
' LBB analysis is consistent with the criteria in NUREG-1061, Volume 3, and draft SRP 3.6.3.; therefore, the analysis complies with GDC GDC-4.
- 4. Thus, the probability of large pipe breaks occurring in the RCS line is sufficiently low that the dynamic effects associated with postulated pipe breaks need not be a design basis 14
Fuel assembly seismic and LOCA structural analysis Th The pipe i rupture t lloads d usedd iin th the ffuell assembly bl structural analyses (WCAP-16946), are based on the most limiting of an accumulator, pressurizer surge line, andd RHR branch b h liline b breaks k
Limitation of breaks to branch line breaks (exclusion of main loop breaks) is based on application of the LBB methodology in accordance with the 1987 revision to GDC-4 Allows exclusion of dynamic effects from the design basis analyses when LBB analyses are approved by the Commission 15
Fuel assembly seismic and LOCA structural analysis The NRC Leak-Before-Break Knowledge Management Document (p (page g 3)) pprovides additional information on the dynamic effects that can be excluded when LBB is approved
- Only local dynamic effects
- Discharging fluids The NRC Leak-Before-Break Knowledge Management Document (page
( 3)) provides permitted plant l activities
- Decompression waves within the intact portion of the piping system 16
Fuel assembly seismic and LOCA structural analysis WCAP-16498-NP, 17x17 Next Generation Fuel (17x17 NGF), dated March 2008, has stated fuel qualification NGF),
analyses are performed postulating the rupture of branch lines connected to the main coolant loop (page 61):
Currently, all Westinghouse designed US PWR primary coolant main loop piping has been excluded from consideration for dynamic effects associated with postulated pipe rupture under Reference 61 or subsequent LBB analyses. As a result, all current fuel qualification analyses are performed on the basis of postulated rupture of branch lines connected to the primary i coolant l t lloop.
WCAP-16498-NP was approved in an NRC Safety Evaluation dated March 16,, 2011 17
Fuel assembly seismic and LOCA structural analysis The Staff recently approved the use of LBB for fuel assembly seismic and LOCA structural analyses as part of the Turkey Point Units 3 and 4 Extended Power Uprate Licensing Amendment Request in a letter dated June 15, 2012 (ML11293A356)
Section 2.8.1 of the NRC Safety Evaluation reflected use of WCA-9401-P-A methodology and use of largest branch line breaks The licensee evaluated seismic and LOCA loading using the approved methodology described in WCAP-9401-P-A The largest branch line breaks, either the accumulator line (ACC) break, surge line break, or RHR line break, were considered when generating LOCA hydraulic forcing functions used as input to the analysis 18
Resolution of Issue PG&E is prepared to take the actions necessary to resolve the non-conformingg condition and improve p the licensing basis PG&E is determining what conservative approach is required i d to address dd the h non-conforming f i condition di i and d close the operability determination PG&E plans to work collaboratively with the Staff to understand and resolve the issue 19
