{"id":431724,"date":"2024-10-20T07:29:54","date_gmt":"2024-10-20T07:29:54","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/asme-bpvc-xi-2-2023\/"},"modified":"2024-10-26T14:14:11","modified_gmt":"2024-10-26T14:14:11","slug":"asme-bpvc-xi-2-2023","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/asme\/asme-bpvc-xi-2-2023\/","title":{"rendered":"ASME BPVC XI 2 2023"},"content":{"rendered":"

Provides requirements to maintain the nuclear power plant while in operation and to return the plant to service following plant outages. The rules require a mandatory program to evidence adequate safety and manage deterioration and aging effects. The rules also stipulate duties of the Authorized Nuclear Inservice Inspector to verify that the mandatory program has been completed, permitting the plant to return to service in a safe and expeditious manner. Application of this Section begins when the requirements of the construction code have been satisfied. DIVISION 2 This Division provides the requirements for the creation of the Reliability and Integrity Management (RIM) Program for advanced nuclear reactor designs. The RIM Program addresses the entire life cycle for all types of nuclear power plants, it requires a combination of monitoring, examination, tests, operation, and maintenance requirements that ensures each Structure, System, and Component (SSC) meets plant risk and reliability goals that are selected for the RIM Program.<\/p>\n

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PDF Pages<\/th>\nPDF Title<\/th>\n<\/tr>\n
5<\/td>\nTABLE OF CONTENTS <\/td>\n<\/tr>\n
10<\/td>\nList of Sections <\/td>\n<\/tr>\n
11<\/td>\nFOREWORD <\/td>\n<\/tr>\n
13<\/td>\nSTATEMENT 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 <\/td>\n<\/tr>\n
14<\/td>\nPersonnel <\/td>\n<\/tr>\n
36<\/td>\nCorrespondence With the Committee <\/td>\n<\/tr>\n
38<\/td>\nPREFACE TO SECTION XI
INTRODUCTION
GENERAL <\/td>\n<\/tr>\n
39<\/td>\nORGANIZATION OF SECTION XI
1\u2002DIVISIONS
2\u2002ORGANIZATION OF DIVISION 1 <\/td>\n<\/tr>\n
40<\/td>\n 3\u2002ORGANIZATION OF DIVISION 2 <\/td>\n<\/tr>\n
41<\/td>\n 4\u2002REFERENCES <\/td>\n<\/tr>\n
43<\/td>\nSUMMARY OF CHANGES <\/td>\n<\/tr>\n
44<\/td>\nCross-Referencing in the ASME BPVC <\/td>\n<\/tr>\n
45<\/td>\nARTICLE RIM-1 SCOPE AND RESPONSIBILITY
RIM-1.1 Scope
RIM-1.2 Jurisdiction
RIM-1.3 Components Subject to the Requirements of This Division
RIM-1.4 Owner\u2019s Responsibility <\/td>\n<\/tr>\n
46<\/td>\nRIM-1.5 Standard Units
RIM-1.6 Inspection
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 <\/td>\n<\/tr>\n
47<\/td>\nRIM-1.9 Referenced Standards and Specifications
Tables
Table RIM-1.9-1 Referenced Standards and Specifications <\/td>\n<\/tr>\n
48<\/td>\nARTICLE RIM-2 RELIABILITY AND INTEGRITY MANAGEMENT (RIM) PROGRAM
RIM-2.1 RIM Program Overview
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) <\/td>\n<\/tr>\n
49<\/td>\nRIM-2.4 Facility and SSC Reliability Target Allocation
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
RIM-2.5.1 Identification of RIM Strategies <\/td>\n<\/tr>\n
50<\/td>\nRIM-2.5.2 Evaluation of RIM Strategy Impacts on SSC Reliability
RIM-2.6 Evaluation of Uncertainties
RIM-2.7 RIM Program Implementation
RIM-2.7.1 RIM Program Documentation
RIM-2.7.2 Inservice Inspection Interval <\/td>\n<\/tr>\n
51<\/td>\nRIM-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 <\/td>\n<\/tr>\n
53<\/td>\nRIM-2.7.7 Examination Methods and Volumes
RIM-2.8 Performance Monitoring and RIM Program Updates
RIM-2.9 Examination Methods
RIM-2.9.1 Visual Examinations <\/td>\n<\/tr>\n
54<\/td>\nRIM-2.9.2 Surface Examination
RIM-2.9.3 Volumetric Examination <\/td>\n<\/tr>\n
55<\/td>\nRIM-2.9.4 Alternative Examinations
RIM-2.10 Additional Considerations for RIM Program Implementation
RIM-2.10.1 Consequence, External Event, and Shutdown Considerations
RIM-2.10.2 Principles of Risk-Informed Decision Making <\/td>\n<\/tr>\n
57<\/td>\nARTICLE RIM-3 ACCEPTANCE STANDARDS
RIM-3.1 Evaluation of Examination Results and Acceptance Standards <\/td>\n<\/tr>\n
58<\/td>\nARTICLE RIM-4 REPAIR\/REPLACEMENT ACTIVITIES
RIM-4.1 Scope
RIM-4.2 Leakage Test Requirements After a Repair\/Replacement Activity
RIM-4.2.1 Test Boundaries
RIM-4.2.2 Gas Leakage Test
RIM-4.2.3 Liquid Leakage Test <\/td>\n<\/tr>\n
59<\/td>\nRIM-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 <\/td>\n<\/tr>\n
60<\/td>\nARTICLE RIM-5 SYSTEM LEAKAGE MONITORING AND PERIODIC TESTS
RIM-5.1 Scope
RIM-5.2 Leakage Monitoring
RIM-5.2.1 General
RIM-5.2.2 Periodic Leakage Test
RIM-5.3 Corrective Action
RIM-5.4 Records <\/td>\n<\/tr>\n
61<\/td>\nARTICLE RIM-6 RECORDS AND REPORTS
RIM-6.1 Scope
RIM-6.2 Documentation Requirements
RIM-6.2.1 Owner\u2019s Responsibilities
RIM-6.2.2 Owner\u2019s Activity Report, Form OAR-1
RIM-6.2.3 Contracted Repair\/Replacement Organization Responsibilities
RIM-6.2.4 Owners\u2019 Repair\/Replacement Certification Record NIS-2 Responsibilities
RIM-6.3 Record Retention
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 <\/td>\n<\/tr>\n
62<\/td>\nRIM-6.3.5 Repair\/Replacement Activity Records <\/td>\n<\/tr>\n
63<\/td>\nARTICLE RIM-7 GLOSSARY
RIM-7.1 Terms and Definitions <\/td>\n<\/tr>\n
65<\/td>\nRIM-7.2 Acronyms <\/td>\n<\/tr>\n
66<\/td>\nMANDATORY APPENDIX I RIM DECISION FLOWCHARTS FOR USE WITH THE RIM PROGRAM
ARTICLE I-1 FLOWCHARTS
I-1.1 General <\/td>\n<\/tr>\n
67<\/td>\nFigures
Figure I-1.1-1 Inputs to the RIMEP for NPP Owner’s RIM Program Development <\/td>\n<\/tr>\n
68<\/td>\nFigure I-1.1-2 RIM Program Development and Integration <\/td>\n<\/tr>\n
69<\/td>\nFigure I-1.1-3 Process for Identifying the SSCs to Be in MANDE Program <\/td>\n<\/tr>\n
70<\/td>\nFigure I-1.1-4 Selection of Strategies for SSCs to Meet Reliability Targets <\/td>\n<\/tr>\n
71<\/td>\nFigure 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 <\/td>\n<\/tr>\n
72<\/td>\nFigure I-1.1-6 Select, Develop, and Validate Performance Demonstration Approach to Meet SSC Reliability Target <\/td>\n<\/tr>\n
73<\/td>\nMANDATORY APPENDIX II DERIVATION OF COMPONENT RELIABILITY TARGETS FROM FACILITY SAFETY REQUIREMENTS
ARTICLE II-1 GENERAL REQUIREMENTS
II-1.1 SCOPE
II-1.2 ADEQUACY OF THE PRA
II-1.3 PROCEDURE OVERVIEW <\/td>\n<\/tr>\n
74<\/td>\nARTICLE II-2 DERIVATION OF RELIABILITY TARGETS
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 <\/td>\n<\/tr>\n
75<\/td>\nMANDATORY APPENDIX III OWNER\u2019S RECORD AND REPORT FOR RIM PROGRAM ACTIVITIES
ARTICLE III-1 GUIDES TO COMPLETING FORMS
III-1.1 Form OAR-1
III-1.2 Form NIS-2 <\/td>\n<\/tr>\n
76<\/td>\nTable III-1.1-1 Guide for Completing Form OAR-1 <\/td>\n<\/tr>\n
77<\/td>\nMANDATORY APPENDIX IV MONITORING AND NDE QUALIFICATION
ARTICLE IV-1 INTRODUCTION
IV-1.1 Scope
IV-1.2 Methods
IV-1.3 Owner\u2019s Monitoring and NDE Expert Panel (MANDEEP)
IV-1.3.1 General Responsibilities
IV-1.3.2 MANDEEP-Specific Responsibilities <\/td>\n<\/tr>\n
78<\/td>\nIV-1.3.3 MANDEEP Qualifications <\/td>\n<\/tr>\n
79<\/td>\nARTICLE IV-2 PERSONNEL QUALIFICATION
IV-2.1 Basic Personnel Qualification
IV-2.2 Method-Specific or Technique-Specific Personnel Qualifications
IV-2.2.1 Data Acquisition Personnel
IV-2.2.2 Data Evaluation Personnel <\/td>\n<\/tr>\n
80<\/td>\nARTICLE IV-3 MANDE METHODS AND TECHNIQUES RELIABILITY-BASED QUALIFICATION
IV-3.1 General
IV-3.2 Determination of the Qualification Requirements
IV-3.3 Qualification Process
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) <\/td>\n<\/tr>\n
81<\/td>\nIV-3.3.6 Monitoring Methods and Techniques (Figure I-1.1-6)
IV-3.3.7 Qualification Alternatives <\/td>\n<\/tr>\n
82<\/td>\nARTICLE IV-4 MANDE PERFORMANCE DEMONSTRATIONS (FIGURE I-1.1-6)
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 <\/td>\n<\/tr>\n
83<\/td>\nARTICLE IV-5 RECORDS
IV-5.1 General
IV-5.2 Records for Methods and Technique Qualification
IV-5.3 Records for Personnel Performance Demonstrations <\/td>\n<\/tr>\n
84<\/td>\nMANDATORY APPENDIX V CATALOG OF NDE REQUIREMENTS AND AREAS OF INTEREST
ARTICLE V-1 EXAMINATION CATEGORIES
V-1.1 Initial Consideration
Table V-1.1-1 Examination Category A, Pressure-Retaining Welds in Reactor Vessels <\/td>\n<\/tr>\n
85<\/td>\nTable 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 <\/td>\n<\/tr>\n
86<\/td>\nTable V-1.1-4 Examination Category F, Pressure-Retaining Dissimilar Welds in Vessel Nozzles <\/td>\n<\/tr>\n
87<\/td>\nTable V-1.1-5 Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter <\/td>\n<\/tr>\n
88<\/td>\nTable V-1.1-6 Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) or Less in Diameter <\/td>\n<\/tr>\n
89<\/td>\nTable V-1.1-7 Examination Category J, Pressure-Retaining Welds in Piping <\/td>\n<\/tr>\n
90<\/td>\nTable 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 <\/td>\n<\/tr>\n
91<\/td>\nTable 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 <\/td>\n<\/tr>\n
92<\/td>\nTable V-1.1-13 Examination Category F-A, Supports <\/td>\n<\/tr>\n
93<\/td>\nMANDATORY APPENDIX VI RELIABILITY AND INTEGRITY MANAGEMENT EXPERT PANEL (RIMEP)
ARTICLE VI-1 OVERVIEW
VI-1.1 Responsibilities and Qualifications of RIMEP <\/td>\n<\/tr>\n
94<\/td>\nMANDATORY APPENDIX VII SUPPLEMENTS FOR TYPES OF NUCLEAR REACTOR FACILITIES
ARTICLE VII-1 SUPPLEMENT FOR LIGHT WATER REACTOR\u2013TYPE FACILITIES
VII-1.1 Scope
VII-1.2 RIM Program \u2014 Damage Degradation Assessment
VII-1.3 Acceptance Standards
VII-1.3.1 Evaluation of Examination Results <\/td>\n<\/tr>\n
95<\/td>\nTable VII-1.2-1 Degradation Mechanism Attributes and Attribute Criteria (LWR) <\/td>\n<\/tr>\n
102<\/td>\nVII-1.3.2 Supplemental Examinations
VII-1.3.3 Acceptance Standards <\/td>\n<\/tr>\n
103<\/td>\nVII-1.3.4 Characterization
VII-1.3.5 Acceptability
VII-1.4 Acceptance Standards for Specific Examination Categories
VII-1.4.1 Acceptance Standards for Examination Categories A and B, Pressure-Retaining Welds in Reactor Vessel and Other Vessels
Table VII-1.3.3-1 Acceptance Standards <\/td>\n<\/tr>\n
104<\/td>\nVII-1.4.2 Acceptance Standards for Examination Category D, Full-Penetration Welds of Nozzles in Vessels <\/td>\n<\/tr>\n
105<\/td>\nVII-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 <\/td>\n<\/tr>\n
106<\/td>\nVII-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 <\/td>\n<\/tr>\n
107<\/td>\nVII-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 <\/td>\n<\/tr>\n
108<\/td>\nVII-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 <\/td>\n<\/tr>\n
109<\/td>\nVII-1.4.11 Acceptance Standards for Examination Category F-A, Component Supports
VII-1.5 Analytical Evaluation of Planar Flaws <\/td>\n<\/tr>\n
110<\/td>\nVII-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 <\/td>\n<\/tr>\n
111<\/td>\nVII-1.5.4 Evaluation Procedure and Acceptance Criteria for Head Penetration Nozzles of PWR Reactor Vessels <\/td>\n<\/tr>\n
112<\/td>\nVII-1.6 Analytical Evaluation of Facility Operating Events
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 <\/td>\n<\/tr>\n
113<\/td>\nARTICLE VII-2 SUPPLEMENT FOR LIQUID METAL REACTOR\u2013TYPE FACILITIES <\/td>\n<\/tr>\n
114<\/td>\nARTICLE VII-3 SUPPLEMENT FOR HIGH-TEMPERATURE GAS REACTOR\u2013TYPE FACILITIES
VII-3.1 Scope
VII-3.2 RIM Program \u2014 Damage Degradation Assessment
VII-3.3 Acceptance Standards
VII-3.3.1 Evaluation of Examination Results <\/td>\n<\/tr>\n
115<\/td>\nTable VII-3.2-1 Degradation Mechanism Attributes and Attribute Criteria for High Temperature Gas Reactors <\/td>\n<\/tr>\n
121<\/td>\nVII-3.3.2 Supplemental Examinations
VII-3.3.3 Acceptance Standards
VII-3.3.4 Characterization
VII-3.3.5 Acceptability
Table VII-3.3.3-1 Acceptance Standards <\/td>\n<\/tr>\n
122<\/td>\nVII-3.4 Acceptance Standards for Specific Examination Categories
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 <\/td>\n<\/tr>\n
123<\/td>\nVII-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 <\/td>\n<\/tr>\n
124<\/td>\nVII-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 <\/td>\n<\/tr>\n
125<\/td>\nVII-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 <\/td>\n<\/tr>\n
126<\/td>\nVII-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 <\/td>\n<\/tr>\n
127<\/td>\nVII-3.4.11 Acceptance Standards for Examination Category F-A, Component Supports
VII-3.5 Analytical Evaluation of Planar Flaws <\/td>\n<\/tr>\n
128<\/td>\nVII-3.5.1 Acceptance Criteria for Ferritic Steel Components 4 in. (100 mm) and Greater in Thickness <\/td>\n<\/tr>\n
129<\/td>\nVII-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 <\/td>\n<\/tr>\n
130<\/td>\nVII-3.5.4 Evaluation Procedure and Acceptance Criteria for Head Penetration Nozzles of Reactor Vessels
VII-3.6 Analytical Evaluation of Facility Operating Events
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 <\/td>\n<\/tr>\n
132<\/td>\nARTICLE VII-4 SUPPLEMENT FOR MOLTEN SALT REACTOR\u2013TYPE FACILITIES <\/td>\n<\/tr>\n
133<\/td>\nARTICLE VII-5 SUPPLEMENT FOR GENERATION 2 LWR\u2013TYPE FACILITIES <\/td>\n<\/tr>\n
134<\/td>\nARTICLE VII-6 SUPPLEMENT FOR FUSION MACHINE\u2013TYPE FACILITIES <\/td>\n<\/tr>\n
135<\/td>\nNONMANDATORY APPENDIX A ALTERNATE REQUIREMENTS FOR MONITORING AND NDE
ARTICLE A-1 GENERAL
A-1.1 Scope
A-1.2 Methods
A-1.3 Responsibilities <\/td>\n<\/tr>\n
136<\/td>\nFigure A-1.2-1 Logic Flow Diagram of the Process for Determining Acceptability of Alternative Requirements <\/td>\n<\/tr>\n
137<\/td>\nARTICLE A-2 PROCEDURE FOR DETERMINING ACCEPTABILITY OF ALTERNATIVE MONITORING OR NDE
A-2.1 Overview
A-2.2 SSC Reliability Target
A-2.3 Degradation Mechanisms and Failure Modes
A-2.4 Approaches \u2014 Probabilistic and Deterministic <\/td>\n<\/tr>\n
138<\/td>\nARTICLE A-3 STAGE I EVALUATION
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 \u2014 Reliability Evaluation
A-3.4.1 Evaluation Procedure
A-3.4.2 Criteria
A-3.5 Deterministic Approach \u2014 Margin Assessment
A-3.5.1 Evaluation Procedure
A-3.5.2 Criteria <\/td>\n<\/tr>\n
139<\/td>\nARTICLE A-4 STAGE II EVALUATION
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 <\/td>\n<\/tr>\n
140<\/td>\nA-4.6 Probabilistic Approach
A-4.7 Deterministic Approach <\/td>\n<\/tr>\n
141<\/td>\nARTICLE A-5 PROCEDURE FOR STRUCTURAL RELIABILITY EVALUATION FOR PASSIVE COMPONENTS
A-5.1 General Requirements
A-5.1.1 Scope
A-5.1.2 Referenced Standards and Specifications
A-5.1.3 Application
A-5.2 Reliability Evaluation
A-5.2.1 General
A-5.2.2 Setting of Failure Scenario
Figure A-5.2.1-1 Reliability Evaluation Procedure <\/td>\n<\/tr>\n
142<\/td>\nA-5.2.3 Modeling
A-5.2.4 Failure Probability Calculation
A-5.3 Setting of Failure Scenario
A-5.3.1 General
A-5.3.2 Setting of Limit State
A-5.3.3 Selection of Failure Modes
Figure A-5.3.1-1 Procedure for Setting Failure Scenarios <\/td>\n<\/tr>\n
143<\/td>\nA-5.3.4 Setting of Failure Scenarios and Evaluation Portions
A-5.3.5 Setting of Reference Period
A-5.4 Modeling
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
Figure A-5.4.1-1 Modeling Procedure <\/td>\n<\/tr>\n
144<\/td>\nA-5.5 Reliability Calculation <\/td>\n<\/tr>\n
145<\/td>\nARTICLE A-6 RECORDS AND REPORTS
A-6.1 Retention of Records And Reports <\/td>\n<\/tr>\n
146<\/td>\nARTICLE A-7 REFERENCES <\/td>\n<\/tr>\n
147<\/td>\nNONMANDATORY APPENDIX B REGULATORY ADMINISTRATIVE PROVISIONS FOR NUCLEAR REACTOR FACILITIES USING RIM PROGRAM
ARTICLE B-1 GENERAL REQUIREMENTS
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 <\/td>\n<\/tr>\n
148<\/td>\nARTICLE B-2 REQUIREMENTS FOR PASSIVE COMPONENTS IN THE RIM PROGRAM <\/td>\n<\/tr>\n
149<\/td>\nENDNOTES <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":"

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<\/b><\/p>\n\n\n\n\n
Published By<\/td>\nPublication Date<\/td>\nNumber of Pages<\/td>\n<\/tr>\n
ASME<\/b><\/a><\/td>\n2023<\/td>\n151<\/td>\n<\/tr>\n<\/tbody>\n<\/table>\n","protected":false},"featured_media":431727,"template":"","meta":{"rank_math_lock_modified_date":false,"ep_exclude_from_search":false},"product_cat":[2643],"product_tag":[],"class_list":{"0":"post-431724","1":"product","2":"type-product","3":"status-publish","4":"has-post-thumbnail","6":"product_cat-asme","8":"first","9":"instock","10":"featured","11":"sold-individually","12":"shipping-taxable","13":"purchasable","14":"product-type-simple"},"_links":{"self":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product\/431724","targetHints":{"allow":["GET"]}}],"collection":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product"}],"about":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/types\/product"}],"wp:featuredmedia":[{"embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media\/431727"}],"wp:attachment":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media?parent=431724"}],"wp:term":[{"taxonomy":"product_cat","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_cat?post=431724"},{"taxonomy":"product_tag","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_tag?post=431724"}],"curies":[{"name":"wp","href":"https:\/\/api.w.org\/{rel}","templated":true}]}}