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ASME BPVC - XI - 2 -2021 BPVC Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants, 2021
- TABLE OF CONTENTS
- LIST OF SECTIONS [Go to Page]
- INTERPRETATIONS
- CODE CASES
- 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
- SUBMITTAL OF TECHNICAL INQUIRIES TO THE BOILER AND PRESSURE VESSEL STANDARDS COMMITTEES
- PERSONNEL
- PREFACE TO SECTION XI [Go to Page]
- INTRODUCTION
- GENERAL
- INSERVICE TESTING OF PUMP AND VALVES
- OWNER RESPONSIBILITIES
- DUTIES OF THE AUTHORIZED NUCLEAR INSERVICE INSPECTOR
- ORGANIZATION OF SECTION XI [Go to Page]
- 1 DIVISIONS
- 2 ORGANIZATION OF DIVISION 1 [Go to Page]
- 2.1 SUBSECTIONS
- 2.2 ARTICLES
- 2.3 SUBARTICLES
- 2.4 SUBSUBARTICLES
- 2.5 PARAGRAPHS
- 2.6 SUBPARAGRAPHS
- 3 ORGANIZATION OF DIVISION 2
- 4 REFERENCES
- SUMMARY OF CHANGES
- LIST OF CHANGES IN RECORD NUMBER ORDER
- CROSS-REFERENCING AND STYLISTIC CHANGES IN THE BOILER AND PRESSURE VESSEL CODE
- 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 PLANT AND SSC RELIABILITY TARGET ALLOCATION [Go to Page]
- RIM-2.4.1 Plant-Level Risk and Reliability Targets
- RIM-2.4.2 SSC-Level Reliability Target
- 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 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 Examination and Inspection 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 LEAK TEST REQUIREMENTS AFTER A REPAIR/REPLACEMENT ACTIVITY [Go to Page]
- RIM-4.2.1 Test Boundaries
- RIM-4.2.2 Gas Leak Test
- RIM-4.2.3 Liquid Leak Test
- RIM-4.2.4 Volumetric and Surface Examination
- RIM-4.2.5 Exemptions
- RIM-4.3 RESPONSIBILITIES
- RIM-4.4 CORRECTIVE ACTION
- RIM-4.5 RECORDS
- ARTICLE RIM-5 SYSTEM LEAK 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 Leak 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 REQUIREMENTS [Go to Page]
- RIM-6.2.1 Owner’s Responsibilities
- RIM-6.2.2 Owner 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 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
- 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 PLANT 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 RELIABILITY TARGET DERIVATION [Go to Page]
- II-2.1 PLANT-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 PLANT-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 REQUIREMENTS
- ARTICLE IV-2 PROCEDURES, EQUIPMENT, AND PERSONNEL REQUIREMENTS [Go to Page]
- IV-2.1 BASIC QUALIFICATION (FIGURES I-1.1-1 THROUGH I-1.1-6)
- IV-2.2 METHOD/TECHNIQUE PERSONNEL-SPECIFIC QUALIFICATIONS
- ARTICLE IV-3 RELIABILITY-BASED QUALIFICATION OF MONITORING AND NDE (MANDE) METHODS AND TECHNIQUES [Go to Page]
- IV-3.1 GENERAL
- IV-3.2 DETERMINATION OF THE QUALIFICATION REQUIREMENTS
- IV-3.3 QUALIFICATION PROCESS
- ARTICLE IV-4 PERFORMANCE DEMONSTRATIONS FOR MANDE PERSONNEL (FIGURE I-1.1-6) [Go to Page]
- IV-4.1 GENERAL
- IV-4.2 PERFORMANCE DEMONSTRATION FOR PERSONNEL FOR MONITORING METHODS
- IV-4.3 PERFORMANCE DEMONSTRATION FOR NDE PERSONNEL
- 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 TABLES
- V-1.1 GENERAL
- MANDATORY APPENDIX VI RELIABILITY AND INTEGRITY MANAGEMENT EXPERT PANEL (RIMEP) [Go to Page]
- ARTICLE VI-1 OVERVIEW
- VI-1.1 RESPONSIBILITIES AND QUALIFICATIONS OF RIMEP
- MANDATORY APPENDIX VII SUPPLEMENTS FOR TYPES OF NUCLEAR PLANTS [Go to Page]
- ARTICLE VII-1 SUPPLEMENT FOR LIGHT WATER REACTOR–TYPE PLANTS [Go to Page]
- VII-1.1 SCOPE
- VII-1.2 RIM PROGRAM — DAMAGE DEGRADATION ASSESSMENT
- VII-1.3 ACCEPTANCE STANDARDS
- VII-1.4 ACCEPTANCE STANDARDS FOR SPECIFIC EXAMINATION CATEGORIES
- VII-1.5 ANALYTICAL EVALUATION OF PLANAR FLAWS
- VII-1.6 ANALYTICAL EVALUATION OF PLANT OPERATING EVENTS
- ARTICLE VII-2 SUPPLEMENT FOR LIQUID METAL REACTOR–TYPE PLANTS
- ARTICLE VII-3 SUPPLEMENT FOR HIGH-TEMPERATURE GAS REACTOR–TYPE PLANTS [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 Standards for Examination Categories A and B of Pressure-Retaining Welds in Reactor Vessel and Other Vessels
- VII-3.4.2 Standards for Examination Category D for Full Penetration Welds of Nozzles in Vessels
- VII-3.4.3 Standards for Examination Category F for Pressure-Retaining Dissimilar Metal Welds in Vessel Nozzles and Category J for Pressure-Retaining Welds in Piping
- VII-3.4.4 Standards for Examination Category G-1 for Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
- VII-3.4.5 Standards for Examination Category K for Welded Attachments for Vessels, Piping, Pumps, and Valves
- VII-3.4.6 Standards for Examination Category G-1 for Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter and Examination Category G-2 for Pressure-Retaining Bolting 2 in. (50 mm) and Less in Diameter
- VII-3.4.7 Standards for Examination Categories L-2 and M-2 of Rotating Equipment Casings and Valve Bodies
- VII-3.4.8 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 Standards for Examination Category P, All Pressure-Retaining Components
- VII-3.4.10 Standards for Examination Category O for Pressure-Retaining Welds in Control Rod Drive and Instrument Nozzle Housings
- VII-3.4.11 Standards for Examination Category F-A for 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 Reactor Vessel Head Penetration Nozzles
- VII-3.6 ANALYTICAL EVALUATION OF PLANT 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 Plant Fatigue Assessments
- ARTICLE VII-4 SUPPLEMENT FOR MOLTEN SALT REACTOR–TYPE PLANTS
- ARTICLE VII-5 SUPPLEMENT FOR GENERATION 2 LWR–TYPE PLANTS
- ARTICLE VII-6 SUPPLEMENT FOR FUSION MACHINE–TYPE PLANTS
- NONMANDATORY APPENDIX A ALTERNATE REQUIREMENTS FOR NDE AND MONITORING [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 [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
- A-3.5 DETERMINISTIC APPROACH — MARGIN ASSESSMENT
- 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
- A-5.2 RELIABILITY EVALUATION
- A-5.3 FAILURE SCENARIO SETTING
- A-5.4 MODELING
- A-5.5 RELIABILITY CALCULATION
- ARTICLE A-6 RECORDS AND REPORT [Go to Page]
- A-6.1 RETENTION OF RECORDS AND REPORTS
- ARTICLE A-7 REFERENCES
- NONMANDATORY APPENDIX B REGULATORY ADMINISTRATIVE PROVISIONS FOR NUCLEAR PLANTS 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 AUTHORITIES HAVING JURISDICTION AT THE PLANT SITE
- B-1.5 SUMMARY OF REPORT SUBMITTAL
- ARTICLE B-2 REQUIREMENTS FOR PASSIVE COMPONENTS IN THE RIM PROGRAM [Go to Page]
- B-2.1 REVIEW BY REGULATORY AND ENFORCEMENT AUTHORITIES HAVING JURISDICTION AT THE PLANT SITE
- FIGURES [Go to Page]
- I-1.1-1 Inputs to the RIMEP for NPP Owner's RIM Program Development
- I-1.1-2 RIM Program Development and Integration
- I-1.1-3 Process for Identifying the SSCs to Be in MANDE Program
- I-1.1-4 Selection of Strategies for SSCs to Meet Reliability Targets
- I-1.1-5 Upper Half Shows Input to MANDEEP for Developing MANDE Specification and Lower Half Shows Process
for Evaluating if Division 1 Requirements Meet MANDE Specifications
- I-1.1-6 Select, Develop, and Validate Performance Demonstration Approach to Meet SSC Reliability Target
- A-1.2-1 Logic Flow Diagram of the Process
- A-5.2.1-1 Reliability Evaluation Procedure
- A-5.3.1-1 Failure Scenario Setting Procedure
- A-5.4.1-1 Modeling Procedure
- TABLES [Go to Page]
- RIM-1.9-1 Referenced Standards and
Specifications
- III-1.1-1 Guide for Completing Form OAR-1
- V-1.1-1 Examination Category A, Pressure-Retaining Welds in Reactor Vessels
- V-1.1-2 Examination Category B, Pressure-Retaining Welds in Vessels Other Than Reactor Vessels
- V-1.1-3 Examination Category D, Full-Penetration Welded Nozzles in Vessels
- V-1.1-4 Examination Category F, Pressure-Retaining Dissimilar Welds in Vessel Nozzles
- V-1.1-5 Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
- V-1.1-6 Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) or Less in Diameter
- V-1.1-7 Examination Category J, Pressure-Retaining Welds in Piping
- V-1.1-8 Examination Category K, Welded Attachments for Vessels, Piping, Rotating Equipment, and Valves
- V-1.1-9 Examination Category L-2, Pump Casings; Examination Category M-2, Valve Bodies
- 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
- V-1.1-11 Examination Category O, Pressure-Retaining Welds in Control Rod Drive and Instrument Nozzle Housings
- V-1.1-12 Examination Category P, All Pressure-Retaining Components
- V-1.1-13 Examination Category F-A, Supports
- VII-1.2-1 Degradation Mechanism Attributes and Attribute Criteria (LWR)
- VII-1.3.3-1 Acceptance Standards
- VII-3.2-1 Degradation Mechanism Attributes and Attribute Criteria
- VII-3.3.3-1 Acceptance Standards
- ENDNOTES [Go to Page]
