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RIM ) - REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - FRANK J. SCHAAF,JR, P.E. ASME CHAIRMAN, SWGRIM CONSULTANT, STERLING REFRIGERATION.

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Presentation on theme: "RIM ) - REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - FRANK J. SCHAAF,JR, P.E. ASME CHAIRMAN, SWGRIM CONSULTANT, STERLING REFRIGERATION."— Presentation transcript:

1 RIM ) - REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - FRANK J. SCHAAF,JR, P.E. ASME CHAIRMAN, SWGRIM CONSULTANT, STERLING REFRIGERATION CORP ASME NUCLEAR CODES & STANDARDS RELIABILITY AND INTEGRITY MANAGEMENT (RIM ) - REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - FRANK J. SCHAAF,JR, P.E. ASME CHAIRMAN, SWGRIM CONSULTANT, STERLING REFRIGERATION CORP 1 NESCC Washington DC November 3, 2014

2 2 Disclaimer This presentation is the intellectual property of Frank Schaaf, the comments made are his alone and are not an ASME official position.

3 AGENDA 3  Background Review  RIM (Reliability and Integrity Management)  SBC ( System Based Code)  Update Progress (last year)  Conclusion

4 BACKGROUND 4 PHILOSOPHY OF SECTION XI The philosophy of Section XI is to mandate a sufficient number of examinations and tests (selected deterministically) to provide assurance that the original safety that was designed and built into the plant is maintained throughout it’s service life. L.J. Chockie (1975) Chair, Section XI

5 5 VISION FOR ASME NUCLEAR CODE Load and Resistance Factor Design (LRFD) Cold piping Hot piping Current classification Plant PRA insights Current risk criteria Risk-Informed Design Direct use of plant PRA Develop risk criteria Piping application Other components ASME III Code Cases Life-Cycle Process/ System-Based Code ASME III Code Changes 2-3 years3-5 years5-10 years Risk-Informed Safety Classification Review and adapt risk-informed safety classification Code Case N-660 for repair/ replacement to ASME III design ASME Code Case Plant PRA Prior ASME Research & Code Risk- Informed Work ASME Section XI Risk-Informed ISI Risk-Informed RRM ASME O&M Risk-Informed IST Other ASME Nuclear C&S

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10 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) Reliability and Integrity Management (RIM) : Those aspects of the plant design process that are applied to provide an appropriate level of reliability of SSCs and a continuing assurance over the life of the plant that such reliability is maintained. These include design features important to reliability performance such as design margins, selection of materials, testing and monitoring, provisions for maintenance, repair and replacement, pressure and leak testing, and In- service Inspection (ISI). 10

11 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) Step 1 Determine Scope of SSCs for RIM Program Step 2 Evaluate SSC Damage Mechanisms Step 3 Determine Plant and SSC Level Reliability and Capability Requirements Step 4 Evaluate RIM Strategies to Achieve Reliability Targets Step 5 Evaluate Uncertainties in Reliability Performance Step 6 Determine Scope and Parameters of RIM Program Step 7 Monitor SSC Reliability Performance and Update RIM Program 11

12 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) SYSTEM BASED CODE CONCEPT 12

13 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) SYSTEM BASED CODE CONCEPT 13

14 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) SYSTEM BASED CODE MODEL 14

15 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) SYSTEM BASED CODE MODEL Need for new PRA Standard 2006 – Non-LWR PRA Standard created, includes ; Design Element Level 1, 2, and 3 Elements Multi-units on same site ISI & NDE Methods 2013 – Non-LWR PRA Standard, Approved for Trial-Use 15

16 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) 16

17 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) ASME, SECTION XI, DIVISION 2 SCOPE All reactor types (water, gas, metal, salt) All reactor sizes Target reliabilities for passive SSCs Evaluate consequences of SSC failure Flexible Inspection Intervals Examination Strategies development Repair/Replacement & Maintenance 17

18 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) ASME, SECTION XI, DIVISION 2  RIM-1000 SCOPE AND RESPONSIBILITY  RIM-2000 RIM PROGRAM  RIM-3000 EVALUATION & STANDARDS  RIM-4000 REPAIR/REPLACEMENTS  RIM-5000 SYSTEM PRESSURE TESTS  RIM-6000 RECORDS  RIM-9000 GLOSSARY 18

19 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) ASME, SECTION XI, DIVISION 2 APPENDICISES 1. Plant Type (Water, Gas, Metal, and Salt) 2. Mandatory Appendix I – NDE Strategies Appendix II – U.S. Administrative Requirements Appendix III – Owner’s Reports (Program Activities ) Appendix IV – Qualification Program for NDE Appendix V – Catalog of NDE Examination Requirements 3. Non-Mandatory TBD 19

20 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) 20

21 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) 21

22 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) 22

23 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) UPDATE IN LAST YEAR Development of NDE Strategies Appendix Development of NDE Qualification Appendix (Procedures and Personnel) 23

24 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) UPDATE IN LAST YEAR Development of NDE Strategies Appendix 24

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26 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) UPDATE IN LAST YEAR Development of NDE Qualification Appendix Totally Performance Based Procedures and Personnel Performance demonstration use use Section V, Article 14 Performance demonstration establishes the ability of a specific examination system (i.e. equipment, procedures and personnel) to achieve a desirable level of performance i.e.. risk reliability. 26

27 RIM (R ELIABILITY AND I NTEGRITY M ANAGEMENT ) SSC CLASSIFICATION No Classification required All passive SSC in RIM Program RIM Program developed by Owner ASME would not reference another organization's document For construction would use NRC documents 27

28 CONCLUSION Hoping NuScale will become pilot plant RIM publish in 2017 edition of Section XI Questions 28


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