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ASME BPVC.XI.2-2023 Section XI, Rules for Inservice Inspection of Nuclear Reactor Facility Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities, 2023
- TABLE OF CONTENTS
- List of Sections
- FOREWORD
- STATEMENT OF POLICY ON THE USE OF THE ASME SINGLE CERTIFICATION MARK AND CODE AUTHORIZATION IN ADVERTISING
- STATEMENT OF POLICY ON THE USE OF ASME MARKING TO IDENTIFY MANUFACTURED ITEMS
- Personnel
- Correspondence With the Committee
- PREFACE TO SECTION XI [Go to Page]
- INTRODUCTION
- GENERAL
- ORGANIZATION OF SECTION XI [Go to Page]
- 1 DIVISIONS
- 2 ORGANIZATION OF DIVISION 1
- 3 ORGANIZATION OF DIVISION 2
- 4 REFERENCES
- SUMMARY OF CHANGES
- Cross-Referencing in the ASME BPVC
- ARTICLE RIM-1 SCOPE AND RESPONSIBILITY [Go to Page]
- RIM-1.1 Scope
- RIM-1.2 Jurisdiction
- RIM-1.3 Components Subject to the Requirements of This Division
- RIM-1.4 Owner’s Responsibility
- RIM-1.5 Standard Units
- RIM-1.6 Inspection [Go to Page]
- RIM-1.6.1 Duties of the Inspector and Authorized Nuclear Inservice Inspector Supervisor
- RIM-1.6.2 Qualification of Authorized Inspection Agencies, Inspectors, and Supervisors
- RIM-1.6.3 Access for Inspector
- RIM-1.7 Regulatory Review
- RIM-1.8 Tolerances
- RIM-1.9 Referenced Standards and Specifications
- ARTICLE RIM-2 RELIABILITY AND INTEGRITY MANAGEMENT (RIM) PROGRAM [Go to Page]
- RIM-2.1 RIM Program Overview [Go to Page]
- RIM-2.1.1 Basis, Objective, and Process
- RIM-2.1.2 Responsibilities
- RIM-2.2 RIM Program Scope and Definition
- RIM-2.3 Degradation Mechanism Assessment (DMA)
- RIM-2.4 Facility and SSC Reliability Target Allocation [Go to Page]
- RIM-2.4.1 Facility-Level Risk and Reliability Targets
- RIM-2.4.2 SSC-Level Reliability Targets
- RIM-2.4.3 Scope, Level of Detail, and Technical Adequacy of the PRA
- RIM-2.5 Identification and Evaluation of RIM Strategies [Go to Page]
- RIM-2.5.1 Identification of RIM Strategies
- RIM-2.5.2 Evaluation of RIM Strategy Impacts on SSC Reliability
- RIM-2.6 Evaluation of Uncertainties
- RIM-2.7 RIM Program Implementation [Go to Page]
- RIM-2.7.1 RIM Program Documentation
- RIM-2.7.2 Inservice Inspection Interval
- RIM-2.7.3 Preservice Inspection
- RIM-2.7.4 Design Requirements for RIM
- RIM-2.7.5 Leak Detection System Requirements for RIM
- RIM-2.7.6 MANDE Requirements for RIM
- RIM-2.7.7 Examination Methods and Volumes
- RIM-2.8 Performance Monitoring and RIM Program Updates
- RIM-2.9 Examination Methods [Go to Page]
- RIM-2.9.1 Visual Examinations
- RIM-2.9.2 Surface Examination
- RIM-2.9.3 Volumetric Examination
- RIM-2.9.4 Alternative Examinations
- RIM-2.10 Additional Considerations for RIM Program Implementation [Go to Page]
- RIM-2.10.1 Consequence, External Event, and Shutdown Considerations
- RIM-2.10.2 Principles of Risk-Informed Decision Making
- ARTICLE RIM-3 ACCEPTANCE STANDARDS [Go to Page]
- RIM-3.1 Evaluation of Examination Results and Acceptance Standards
- ARTICLE RIM-4 REPAIR/REPLACEMENT ACTIVITIES [Go to Page]
- RIM-4.1 Scope
- RIM-4.2 Leakage Test Requirements After a Repair/Replacement Activity [Go to Page]
- RIM-4.2.1 Test Boundaries
- RIM-4.2.2 Gas Leakage Test
- RIM-4.2.3 Liquid Leakage Test
- RIM-4.2.4 NDE in Lieu of Leakage Testing
- RIM-4.2.5 Exemptions From Leakage Tests
- RIM-4.3 Responsibilities
- RIM-4.4 Corrective Action
- RIM-4.5 Records
- ARTICLE RIM-5 SYSTEM LEAKAGE MONITORING AND PERIODIC TESTS [Go to Page]
- RIM-5.1 Scope
- RIM-5.2 Leakage Monitoring [Go to Page]
- RIM-5.2.1 General
- RIM-5.2.2 Periodic Leakage Test
- RIM-5.3 Corrective Action
- RIM-5.4 Records
- ARTICLE RIM-6 RECORDS AND REPORTS [Go to Page]
- RIM-6.1 Scope
- RIM-6.2 Documentation Requirements [Go to Page]
- RIM-6.2.1 Owner’s Responsibilities
- RIM-6.2.2 Owner’s Activity Report, Form OAR-1
- RIM-6.2.3 Contracted Repair/Replacement Organization Responsibilities
- RIM-6.2.4 Owners’ Repair/Replacement Certification Record NIS-2 Responsibilities
- RIM-6.3 Record Retention [Go to Page]
- RIM-6.3.1 Maintenance of Records
- RIM-6.3.2 Reproduction, Digitization, and Microfilming
- RIM-6.3.3 Construction Records
- RIM-6.3.4 RIM Program Records
- RIM-6.3.5 Repair/Replacement Activity Records
- ARTICLE RIM-7 GLOSSARY [Go to Page]
- RIM-7.1 Terms and Definitions
- RIM-7.2 Acronyms
- MANDATORY APPENDIX I RIM DECISION FLOWCHARTS FOR USE WITH THE RIM PROGRAM [Go to Page]
- ARTICLE I-1 FLOWCHARTS [Go to Page]
- I-1.1 General
- MANDATORY APPENDIX II DERIVATION OF COMPONENT RELIABILITY TARGETS FROM FACILITY SAFETY REQUIREMENTS [Go to Page]
- ARTICLE II-1 GENERAL REQUIREMENTS [Go to Page]
- II-1.1 SCOPE
- II-1.2 ADEQUACY OF THE PRA
- II-1.3 PROCEDURE OVERVIEW
- ARTICLE II-2 DERIVATION OF RELIABILITY TARGETS [Go to Page]
- II-2.1 Facility-Level Safety Requirements
- II-2.2 Allocation of Reliability Targets
- II-2.3 Identification of Component Groups
- II-2.4 Trial Assignment of Reliability Targets
- II-2.5 Evaluation of Impacts of Reliability Targets on Facility-Level Risk
- II-2.6 Determination of Reliability Targets
- MANDATORY APPENDIX III OWNER’S RECORD AND REPORT FOR RIM PROGRAM ACTIVITIES [Go to Page]
- ARTICLE III-1 GUIDES TO COMPLETING FORMS [Go to Page]
- III-1.1 Form OAR-1
- III-1.2 Form NIS-2
- MANDATORY APPENDIX IV MONITORING AND NDE QUALIFICATION [Go to Page]
- ARTICLE IV-1 INTRODUCTION [Go to Page]
- IV-1.1 Scope
- IV-1.2 Methods
- IV-1.3 Owner’s Monitoring and NDE Expert Panel (MANDEEP) [Go to Page]
- IV-1.3.1 General Responsibilities
- IV-1.3.2 MANDEEP-Specific Responsibilities
- IV-1.3.3 MANDEEP Qualifications
- ARTICLE IV-2 PERSONNEL QUALIFICATION [Go to Page]
- IV-2.1 Basic Personnel Qualification
- IV-2.2 Method-Specific or Technique-Specific Personnel Qualifications [Go to Page]
- IV-2.2.1 Data Acquisition Personnel
- IV-2.2.2 Data Evaluation Personnel
- ARTICLE IV-3 MANDE METHODS AND TECHNIQUES RELIABILITY-BASED QUALIFICATION [Go to Page]
- IV-3.1 General
- IV-3.2 Determination of the Qualification Requirements
- IV-3.3 Qualification Process [Go to Page]
- IV-3.3.1 General
- IV-3.3.2 SSC MANDE Specifications (Figure I-1.1-5)
- IV-3.3.3 MANDE Technical Justification (Figure I-1.1-6)
- IV-3.3.4 Levels of Rigor (Figure I-1.1-6)
- IV-3.3.5 Qualification of NDE Methods and Techniques (Figure I-1.1-6)
- IV-3.3.6 Monitoring Methods and Techniques (Figure I-1.1-6)
- IV-3.3.7 Qualification Alternatives
- ARTICLE IV-4 MANDE PERFORMANCE DEMONSTRATIONS (FIGURE I-1.1-6) [Go to Page]
- IV-4.1 General
- IV-4.2 Personnel Performance Demonstration for Monitoring Methods
- IV-4.3 NDE Personnel Performance Demonstration
- IV-4.4 Procedure and Equipment Performance Demonstration
- ARTICLE IV-5 RECORDS [Go to Page]
- IV-5.1 General
- IV-5.2 Records for Methods and Technique Qualification
- IV-5.3 Records for Personnel Performance Demonstrations
- MANDATORY APPENDIX V CATALOG OF NDE REQUIREMENTS AND AREAS OF INTEREST [Go to Page]
- ARTICLE V-1 EXAMINATION CATEGORIES [Go to Page]
- V-1.1 Initial Consideration
- MANDATORY APPENDIX VI RELIABILITY AND INTEGRITY MANAGEMENT EXPERT PANEL (RIMEP) [Go to Page]
- ARTICLE VI-1 OVERVIEW [Go to Page]
- VI-1.1 Responsibilities and Qualifications of RIMEP
- MANDATORY APPENDIX VII SUPPLEMENTS FOR TYPES OF NUCLEAR REACTOR FACILITIES [Go to Page]
- ARTICLE VII-1 SUPPLEMENT FOR LIGHT WATER REACTOR–TYPE FACILITIES [Go to Page]
- VII-1.1 Scope
- VII-1.2 RIM Program — Damage Degradation Assessment
- VII-1.3 Acceptance Standards [Go to Page]
- VII-1.3.1 Evaluation of Examination Results
- VII-1.3.2 Supplemental Examinations
- VII-1.3.3 Acceptance Standards
- VII-1.3.4 Characterization
- VII-1.3.5 Acceptability
- VII-1.4 Acceptance Standards for Specific Examination Categories [Go to Page]
- VII-1.4.1 Acceptance Standards for Examination Categories A and B, Pressure-Retaining Welds in Reactor Vessel and Other Vessels
- VII-1.4.2 Acceptance Standards for Examination Category D, Full-Penetration Welds of Nozzles in Vessels
- VII-1.4.3 Acceptance Standards for Examination Category F, Pressure-Retaining Dissimilar Metal Welds in Vessel Nozzles and Category J, Pressure-Retaining Welds in Piping
- VII-1.4.4 Acceptance Standards for Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
- VII-1.4.5 Acceptance Standards for Examination Category K, Welded Attachments for Vessels, Piping, Pumps, and Valves
- VII-1.4.6 Standards for Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter, and Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) and Less in Diameter
- VII-1.4.7 Acceptance Standards for Examination Categories L-2 and M-2, Equipment Casings and Valve Bodies
- VII-1.4.8 Acceptance Standards for Examination Category N-1, Interior of Reactor Vessel; Examination Category N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels; and Examination Category N-3, Removable Core Support Structures
- VII-1.4.9 Acceptance Standards for Examination Category P, All Pressure-Retaining Components
- VII-1.4.10 Acceptable Standards for Examination Category O, Pressure-Retaining Welds in Control Rod Drive and Instrument Nozzle Housings
- VII-1.4.11 Acceptance Standards for Examination Category F-A, Component Supports
- VII-1.5 Analytical Evaluation of Planar Flaws [Go to Page]
- VII-1.5.1 Acceptance Criteria for Ferritic Steel Components 4 in. (100 mm) and Greater in Thickness
- VII-1.5.2 Acceptance Criteria for Ferritic Components Less Than 4 in. (100 mm) in Thickness
- VII-1.5.3 Analytical Evaluation Procedures and Acceptance Criteria for Flaws in Austenitic and Ferritic Piping
- VII-1.5.4 Evaluation Procedure and Acceptance Criteria for Head Penetration Nozzles of PWR Reactor Vessels
- VII-1.6 Analytical Evaluation of Facility Operating Events [Go to Page]
- VII-1.6.1 Scope
- VII-1.6.2 Unanticipated Operating Events
- VII-1.6.3 Fracture Toughness Criteria for Protection Against Failure
- VII-1.6.4 Operating Facility Fatigue Assessments
- ARTICLE VII-2 SUPPLEMENT FOR LIQUID METAL REACTOR–TYPE FACILITIES
- ARTICLE VII-3 SUPPLEMENT FOR HIGH-TEMPERATURE GAS REACTOR–TYPE FACILITIES [Go to Page]
- VII-3.1 Scope
- VII-3.2 RIM Program — Damage Degradation Assessment
- VII-3.3 Acceptance Standards [Go to Page]
- VII-3.3.1 Evaluation of Examination Results
- VII-3.3.2 Supplemental Examinations
- VII-3.3.3 Acceptance Standards
- VII-3.3.4 Characterization
- VII-3.3.5 Acceptability
- VII-3.4 Acceptance Standards for Specific Examination Categories [Go to Page]
- VII-3.4.1 Acceptance Standards for Examination Categories A and B, Pressure-Retaining Welds in Reactor Vessel and Other Vessels
- VII-3.4.2 Acceptance Standards for Examination Category D, Full Penetration Welds of Nozzles in Vessels
- VII-3.4.3 Acceptance Standards for Examination Category F, Pressure Dissimilar Metal Welds in Vessel Nozzles, and Examination Category J, Pressure-Retaining Welds in Piping
- VII-3.4.4 Acceptance Standards for Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
- VII-3.4.5 Acceptance Standards for Examination Category K, Welded Attachments for Vessels, Piping, Pumps, and Valves
- VII-3.4.6 Acceptance Standards for Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter, and Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) and Less in Diameter
- VII-3.4.7 Acceptance Standards for Examination Categories L-2 and M-2, Rotating Equipment Casings and Valve Bodies
- VII-3.4.8 Acceptance Standards for Examination Category N-1, Interior of Reactor Vessel; Examination Category N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels; and Examination Category N-3, Removable Core Support Structures
- VII-3.4.9 Acceptance Standards for Examination Category P, All Pressure-Retaining Components
- VII-3.4.10 Acceptance Standards for Examination Category O, Pressure-Retaining Welds in Control Rod Drive and Instrument Nozzle Housings
- VII-3.4.11 Acceptance Standards for Examination Category F-A, Component Supports
- VII-3.5 Analytical Evaluation of Planar Flaws [Go to Page]
- VII-3.5.1 Acceptance Criteria for Ferritic Steel Components 4 in. (100 mm) and Greater in Thickness
- VII-3.5.2 Acceptance Criteria for Ferritic Components Less Than 4 in. (100 mm) in Thickness
- VII-3.5.3 Analytical Evaluation Procedures and Acceptance Criteria for Flaws in Austenitic and Ferritic Piping
- VII-3.5.4 Evaluation Procedure and Acceptance Criteria for Head Penetration Nozzles of Reactor Vessels
- VII-3.6 Analytical Evaluation of Facility Operating Events [Go to Page]
- VII-3.6.1 Scope
- VII-3.6.2 Unanticipated Operating Events
- VII-3.6.3 Fracture Toughness Criteria for Protection Against Failure
- VII-3.6.4 Operating Facility Fatigue Assessments
- ARTICLE VII-4 SUPPLEMENT FOR MOLTEN SALT REACTOR–TYPE FACILITIES
- ARTICLE VII-5 SUPPLEMENT FOR GENERATION 2 LWR–TYPE FACILITIES
- ARTICLE VII-6 SUPPLEMENT FOR FUSION MACHINE–TYPE FACILITIES
- NONMANDATORY APPENDIX A ALTERNATE REQUIREMENTS FOR MONITORING AND NDE [Go to Page]
- ARTICLE A-1 GENERAL [Go to Page]
- A-1.1 Scope
- A-1.2 Methods
- A-1.3 Responsibilities
- ARTICLE A-2 PROCEDURE FOR DETERMINING ACCEPTABILITY OF ALTERNATIVE MONITORING OR NDE [Go to Page]
- A-2.1 Overview
- A-2.2 SSC Reliability Target
- A-2.3 Degradation Mechanisms and Failure Modes
- A-2.4 Approaches — Probabilistic and Deterministic
- ARTICLE A-3 STAGE I EVALUATION [Go to Page]
- A-3.1 Introduction
- A-3.2 Input Related to Safety Evaluation
- A-3.3 Input Related to Structural Evaluation
- A-3.4 Probabilistic Approach — Reliability Evaluation [Go to Page]
- A-3.4.1 Evaluation Procedure
- A-3.4.2 Criteria
- A-3.5 Deterministic Approach — Margin Assessment [Go to Page]
- A-3.5.1 Evaluation Procedure
- A-3.5.2 Criteria
- ARTICLE A-4 STAGE II EVALUATION [Go to Page]
- A-4.1 Introduction
- A-4.2 Input Related to Safety Evaluation
- A-4.3 Input Related to Structural Evaluation
- A-4.4 Detectability
- A-4.5 Criteria to Establish Additional Requirements
- A-4.6 Probabilistic Approach
- A-4.7 Deterministic Approach
- ARTICLE A-5 PROCEDURE FOR STRUCTURAL RELIABILITY EVALUATION FOR PASSIVE COMPONENTS [Go to Page]
- A-5.1 General Requirements [Go to Page]
- A-5.1.1 Scope
- A-5.1.2 Referenced Standards and Specifications
- A-5.1.3 Application
- A-5.2 Reliability Evaluation [Go to Page]
- A-5.2.1 General
- A-5.2.2 Setting of Failure Scenario
- A-5.2.3 Modeling
- A-5.2.4 Failure Probability Calculation
- A-5.3 Setting of Failure Scenario [Go to Page]
- A-5.3.1 General
- A-5.3.2 Setting of Limit State
- A-5.3.3 Selection of Failure Modes
- A-5.3.4 Setting of Failure Scenarios and Evaluation Portions
- A-5.3.5 Setting of Reference Period
- A-5.4 Modeling [Go to Page]
- A-5.4.1 General
- A-5.4.2 Formulation of Scenario Developing Process
- A-5.4.3 Setting of Limit-State Function
- A-5.4.4 Setting of Random Variables
- A-5.5 Reliability Calculation
- ARTICLE A-6 RECORDS AND REPORTS [Go to Page]
- A-6.1 Retention of Records And Reports
- ARTICLE A-7 REFERENCES
- NONMANDATORY APPENDIX B REGULATORY ADMINISTRATIVE PROVISIONS FOR NUCLEAR REACTOR FACILITIES USING RIM PROGRAM [Go to Page]
- ARTICLE B-1 GENERAL REQUIREMENTS [Go to Page]
- B-1.1 Scope
- B-1.2 Application of Code Edition
- B-1.3 Application of Code Cases
- B-1.4 Review by Regulatory and Enforcement Authority Having Jurisdiction at the Facility Site
- B-1.5 Report Submittal
- ARTICLE B-2 REQUIREMENTS FOR PASSIVE COMPONENTS IN THE RIM PROGRAM
- Figures [Go to Page]
- Figure I-1.1-1 Inputs to the RIMEP for NPP Owner's RIM Program Development
- Figure I-1.1-2 RIM Program Development and Integration
- Figure I-1.1-3 Process for Identifying the SSCs to Be in MANDE Program
- Figure I-1.1-4 Selection of Strategies for SSCs to Meet Reliability Targets
- Figure I-1.1-5 Upper Half Shows Input to MANDEEP for Developing MANDE Specification and Lower Half Shows Process for Evaluating if Section XI, Division 1 Requirements Meet MANDE Specifications
- Figure I-1.1-6 Select, Develop, and Validate Performance Demonstration Approach to Meet SSC Reliability Target
- Figure A-1.2-1 Logic Flow Diagram of the Process for Determining Acceptability of Alternative Requirements
- Figure A-5.2.1-1 Reliability Evaluation Procedure
- Figure A-5.3.1-1 Procedure for Setting Failure Scenarios
- Figure A-5.4.1-1 Modeling Procedure
- Tables [Go to Page]
- Table RIM-1.9-1 Referenced Standards and Specifications
- Table III-1.1-1 Guide for Completing Form OAR-1
- Table V-1.1-1 Examination Category A, Pressure-Retaining Welds in Reactor Vessels
- Table V-1.1-2 Examination Category B, Pressure-Retaining Welds in Vessels Other Than Reactor Vessels
- Table V-1.1-3 Examination Category D, Full-Penetration Welded Nozzles in Vessels
- Table V-1.1-4 Examination Category F, Pressure-Retaining Dissimilar Welds in Vessel Nozzles
- Table V-1.1-5 Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
- Table V-1.1-6 Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) or Less in Diameter
- Table V-1.1-7 Examination Category J, Pressure-Retaining Welds in Piping
- Table V-1.1-8 Examination Category K, Welded Attachments for Vessels, Piping, Rotating Equipment, and Valves
- Table V-1.1-9 Examination Category L-2, Pump Casings; Examination Category M-2, Valve Bodies
- Table V-1.1-10 Examination Category N-1, Interior of Reactor Vessels; Examination Category N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels; Examination Category N-3, Removable Core Support Structures
- Table V-1.1-11 Examination Category O, Pressure-Retaining Welds in Control Rod Drive and Instrument Nozzle Housings
- Table V-1.1-12 Examination Category P, All Pressure-Retaining Components
- Table V-1.1-13 Examination Category F-A, Supports
- Table VII-1.2-1 Degradation Mechanism Attributes and Attribute Criteria (LWR)
- Table VII-1.3.3-1 Acceptance Standards
- Table VII-3.2-1 Degradation Mechanism Attributes and Attribute Criteria for High Temperature Gas Reactors
- Table VII-3.3.3-1 Acceptance Standards
- ENDNOTES [Go to Page]
