ASME NUCLEAR CODES & STANDARDS
RELIABILITY AND INTEGRITY MANAGEMENT (RIMRIM))
- REWRITE OF SECTION XI, DIVISION II,- REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - USING RISK INFORMED METHODOLOGY -
FRANK J. SCHAAF,JR, P.E.FRANK J. SCHAAF,JR, P.E.ASME CHAIRMAN, SWGRIMASME CHAIRMAN, SWGRIM
CONSULTANT, STERLING REFRIGERATION CORP CONSULTANT, STERLING REFRIGERATION CORP
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NESCCNESCC
Washington DCWashington DC
November 3, 2014November 3, 2014
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Disclaimer
This presentation is the intellectual property of Frank Schaaf, the comments made are his alone and are not an ASME official position.
AGENDA
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Background Review RIM (Reliability and Integrity Management)
SBC (System Based Code)
Update Progress (last year) Conclusion
BACKGROUND
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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
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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 years 3-5 years 5-10 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
RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
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).
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
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
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
SYSTEM BASED CODE MODEL
Need for new PRA Standard2006 – Non-LWR PRA Standard created, includes;
Design ElementLevel 1, 2, and 3 ElementsMulti-units on same siteISI & NDE Methods
2013 – Non-LWR PRA Standard, Approved for Trial-Use
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
ASME, SECTION XI, DIVISION 2SCOPE
All reactor types (water, gas, metal, salt)All reactor sizesTarget reliabilities for passive SSCsEvaluate consequences of SSC failure Flexible Inspection IntervalsExamination Strategies developmentRepair/Replacement & Maintenance
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
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
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
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
RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
1.E-08
1.E-07
1.E-06
1.E-05
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04
DOSE (REM) AT EXCLUSION AREA BOUNDARY (EAB)
EV
EN
T S
EQ
UE
NC
E M
EA
N F
RE
QU
EN
CY
(P
ER
PL
AN
T Y
EA
R) A00 REGION
DBE REGION
BDBE REGION
Unacceptable
Acceptable
Event AS
Event AF
Event AD
Event BS
Event BF
Event BD
LBE Legend A - Example of SSC in Category NSRST Event AS - LBE (AOO) with successful Operation of A Event AF - LBE (DBE) with failure of A Event AD - LBEs AS and AF with assumed degradation of A B - Example SSC in Category SR Event BS - LBE (DBE) with successful Operation of B Event BF - LBE (BDBE) with failure of B Event BD - LBEs BS and BF with assumed degradation of B C - Example of SSC in Category NSR Event CS - LBE (DBE) with successful operation of C Event CF - LBE (BDBE) with successful operation of C Event CD - LBEs CS and CF with assumed degradation of C
Event CF
Event CSEvent CD
Increasing Risk
Iso-risk Contours
TLRC
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
UPDATE IN LAST YEAR
Development of NDE Strategies Appendix
Development of NDE Qualification Appendix(Procedures and Personnel)
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
UPDATE IN LAST YEARDevelopment of NDE Strategies Appendix
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RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
UPDATE IN LAST YEARDevelopment of NDE Qualification Appendix
Totally Performance BasedProcedures and PersonnelPerformance demonstration use use Section V, Article
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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
RIM (RELIABILITY AND INTEGRITY MANAGEMENT)
SSC CLASSIFICATIONNo Classification requiredAll passive SSC in RIM ProgramRIM Program developed by OwnerASME would not reference another
organization's documentFor construction would use NRC documents
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