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

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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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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SYSTEM BASED CODE CONCEPT

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SYSTEM BASED CODE CONCEPT

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SYSTEM BASED CODE MODEL

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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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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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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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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


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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UPDATE IN LAST YEAR

Development of NDE Strategies Appendix

Development of NDE Qualification Appendix(Procedures and Personnel)

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UPDATE IN LAST YEARDevelopment of NDE Strategies Appendix

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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


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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CONCLUSIONHoping NuScale will become pilot plant

RIM publish in 2017 edition of Section XI

Questions

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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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