RELIABILITY AND INTEGRITY MANAGEMENT (RIM

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ASME NUCLEAR CODES & STANDARDSRELIABILITY AND INTEGRITY MANAGEMENT (RIM)- REWRITE OF SECTION XI, DIVISION II,USING RISK INFORMED METHODOLOGY FRANK J. SCHAAF,JR, P.E.ASME CHAIRMAN, SWGRIMCONSULTANT, STERLING REFRIGERATION CORPBNCS WorkshopPrague, Czech RepublicJuly 7-8, 20141

AGENDA Background History Rewrite Criteria RIM (Reliability and Integrity Management) SBC (System Based Code) Rewrite Status Conclusion2

BACKGROUND & HISTORYPHILOSOPHY OF SECTION XIThe philosophy of Section XI is tomandate a sufficient number of examinationsand tests (selected deterministically)to provideassurance that the original safety that wasdesigned and built into the plant ismaintained throughout it’s service life.L.J. Chockie (1975)Chair, Section XI3

BACKGROUND & HISTORY4

BACKGROUND & HISTORYSection XI Program – Two Loop PWR(SECTION XI CODE WRITTEN AFTER PLANT WAS BUILT) Class 1 Exams Tests –225 Class 2 Exams & Tests – 450 Class 3 Exams & Tests – 24010 yearTotal - 9155

BACKGROUND & HISTORY May 2012 – Meeting with mPower Issues1.S/G tube sampling2.Interval length3.Use the Non-LWR PRA Standard4.Curren adequate safety5.Feedback to Design Phase to ensure reliability meetoperation & examination6

BACKGROUND & HISTORYSection XI Program – Two Loop PWR Class 1 Categories BA Pressure Retaining Welds in Reactor VesselBB Pressure Retaining Welds in Vessels Other ThanReactor VesselsBD Full Penetration Welded Nozzles in VesselsBF Pressure Retaining Dissimilar Metal Welds in VesselNozzlesBG1 Pressure Retaining Bolting, Greater Than 2 in. (50mm) in DiameterBG2 Pressure Retaining Bolting, 2 in. (50 mm) andLess in Diameter7BJ* Pressure Retaining Welds in Piping

BACKGROUND & HISTORYSection XI Program – Two Loop PWR Class 1 Categories (cont)BK Welded Attachments for Vessels, Piping, Pumps, andValvesBL2 Pump Casings BM2 Valve BodiesBN1 Interior of Reactor VesselBN2 Welded Core Support Structures and InteriorAttachments to Reactor VesselsBN3 Removable Core Support StructuresBO Pressure Retaining Welds in Control Rod Drive andInstrument Nozzle HousingsBP All Pressure Retaining Components8BQ Steam Generator Tubing

BACKGROUND & HISTORYSection XI Program – LWR SMR Class 1 Exam & Tests - 100Major reduction in BJ WeldsReduction in BF WeldsReduction in Vessel NozzlesNo CRDM Nozzles Question – Are the current deterministicrequirements good enough for LWRSMR?9

BACKGROUND & HISTORY May 2012 – Meeting with mPower Issues1.S/G tube sampling2.Interval length3.Use the Non-LWR PRA Standard4.Current Division 1 (deterministic) may not provideadequate safety5.Feedback to Design Phase to ensure reliability tomeet operation & examination10

BACKGROUND & HISTORY Rewrite Criteria INTERNATIONALIZATION QUESTIONS Limit use to only plants designed to Section IIIrules Materials - Section II NDE Performance Based qualifications (forprocedure and personnel) Quality assurance programs Design to inspect - assume a variety ofconstruction codes Remove Regulatory Requirements11

RIM (RELIABILITY AND INTEGRITYMANAGEMENT)SYSTEM BASED CODE2004 – The idea was introduced by JSMEThe key concepts are Designing to clearly defined targetreliabilities for SSCs Life‐cycle margin optimization, and Expansion of technical options as well ascombinations of technical options beyondthe current codes and standards.12

RIM (RELIABILITY AND INTEGRITYMANAGEMENT)SYSTEM BASED CODE13

RIM (RELIABILITY AND INTEGRITYMANAGEMENT)SYSTEM BASED CODE(2) life‐cycle margin optimization, and14

RIM (RELIABILITY AND INTEGRITYMANAGEMENT)SYSTEM BASED CODE(3) expansion of technical options as wellas combinations of technical optionsbeyond the current codes and standards.Focus of RIM Program, Section XI,Division 215

RIM (RELIABILITY AND INTEGRITY MANAGEMENT)SYSTEM BASED CODENeed for new PRA Standard2006 – The Working Group Non-LWR PRAStandard created, including;Design ElementLevel 1, 2, and 3 ElementsMulti-unitsISI & NDE Methods2013 – Non-LWR PRA Standard,Approved for Trial-Use16

RIM (RELIABILITY AND INTEGRITY MANAGEMENT)17

RIM (RELIABILITY AND INTEGRITYMANAGEMENT) Reliability and Integrity Management (RIM):Those aspects of the plant design process thatare applied to provide an appropriate level ofreliability of SSCs and a continuing assuranceover the life of the plant that such reliability ismaintained. These include design featuresimportant to reliability performance such asdesign margins, selection of materials, testing andmonitoring, provisions for maintenance, repairand replacement, pressure and leak testing, andIn-service Inspection (ISI).18

RIM (RELIABILITY AND INTEGRITYMANAGEMENT)1. Determine Scope ofSSCs for RIMProgram3 . Determine Plantand SSC Reliabilityand CapabilityRequirements2 . Evaluate SSCDamage Mechanisms4 . Evaluate RIMStrategies to AchieveReliability Targets5 . EvaluateUncertainties inReliabilityPerformance6. Determine Scope ofand Parameters ofRIM Program7 . Monitor SSCReliabilityPerformance andUpdate RIM Program

RIM (RELIABILITY AND INTEGRITY MANAGEMENT)Step 1 Determine Scope of SSCs for RIMProgram Step 2 Evaluate SSC Damage Mechanisms Step 3 Determine Plant and SSC LevelReliability and Capability Requirements Step 4 Evaluate RIM Strategies to AchieveReliability Targets Step 5 Evaluate Uncertainties in ReliabilityPerformance Step 6 Determine Scope and Parameters of RIMProgram Step 7 Monitor SSC Reliability Performance andUpdate RIM Program 20

RIM (RELIABILITY AND INTEGRITY MANAGEMENT)1.E 01UnacceptableEVENT SEQUENCE MEAN FREQUENCY (PER PLANT YEAR)1.E 00A00 REGIONEvent AD1.E-01Event AS1.E-02Acceptable1.E-03LBE LegendA - Example of SSC in Category NSRSTEvent AS - LBE (AOO) with successful Operation of AEvent AF - LBE (DBE) with failure of AEvent AD - LBEs AS and AF with assumed degradation of AB - Example SSC in Category SREvent BS - LBE (DBE) with successful Operation of BEvent BF - LBE (BDBE) with failure of BEvent BD - LBEs BS and BF with assumed degradation of BC - Example of SSC in Category NSREvent CS - LBE (DBE) with successful operation of CEvent CF - LBE (BDBE) with successful operation of CEvent CD - LBEs CS and CF with assumed degradation of CEvent AFDBE REGIONEvent CDEvent CSEvent BDEvent BS1.E-041.E-05TLRCIncreasing RiskBDBE REGIONEvent CFEvent BF1.E-061.E-071.E-081.E-04Iso-risk Contours1.E-031.E-021.E-011.E 001.E 011.E 02DOSE (REM) AT EXCLUSION AREA BOUNDARY (EAB)1.E 031.E 0421

RIM (RELIABILITY AND INTEGRITY MANAGEMENT)22

REWRITE STATUSRIM Format RIM-1000 RIM-2000 RIM-3000 RIM-4000 RIM-5000 RIM-6000 RIM-9000SCOPE AND RESPONSIBILITYRIM PROGRAMEVALUATION & STANDARDSREPAIR/REPLACEMENTSSYSTEM PRESSURE TESTSRECORDSGLOSSARY23

REWRITE STATUSRIM FormatAPPENDICISES1.Plant TypeWaterGasMetalSalt2.MandatoryAppendix I – TBDAppendix II – United States Administrative Requirementsfor Nuclear Plants Using the RIM Program24

REWRITE STATUSRIM FormatAppendix III – Owner’s Reports for RIMProgram ActivitiesAppendix IV – Qualification Program for NDEPersonnelAppendix V – Catalog of NDE ExaminationRequirementsand Areas of InterestAppendix VI – Decision Flow Charts25

CONCLUSION NON-LWR PRA STANDARD(2013) PILOT RIM PROJECTCOMPLETED NRC COMMENTS RESOLUTION PUBLISH RIM IN 2015 CODEEDITION26

In-service Inspection (ISI). 18. RIM (RELIABILITY AND INTEGRITY MANAGEMENT) 1. De te rmine Sco pe o f SSC s fo r RIM Prog ram 2 . Eva lua te SSC Da ma g e Mech a nisms 3 . De te rmine Pla nt a nd SSC Re lia bility a nd Ca pa bility Re q uireme nts 4 . Eva lua te RIM St rate g ie s to Achie ve . for Nuclear Plants Using the RIM Program .

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