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.

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PDF Pages	PDF Title
5	TABLE OF CONTENTS
8	List of Sections
9	INTERPRETATIONS CODE CASES
10	Foreword
12	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
13	Submittal of Technical Inquiries to the Boiler and Pressure Vessel Standards Committees 1 INTRODUCTION 2 INQUIRY FORMAT
14	3 CODE REVISIONS OR ADDITIONS 4 CODE CASES 5 CODE INTERPRETATIONS
15	6 SUBMITTALS
16	Personnel
38	Preface to Section XI INTRODUCTION GENERAL INSERVICE TESTING OF PUMP AND VALVES OWNER RESPONSIBILITIES
39	DUTIES OF THE AUTHORIZED NUCLEAR INSERVICE INSPECTOR
40	Organization of Section XI 1 DIVISIONS 2 ORGANIZATION OF DIVISION 1
41	3 ORGANIZATION OF DIVISION 2 4 REFERENCES
43	Cross-Referencing and Stylistic Changes in the Boiler and Pressure Vessel Code Subparagraph Breakdowns/Nested Lists Hierarchy Footnotes Submittal of Technical Inquiries to the Boiler and Pressure Vessel Standards Committees Cross-References
45	ARTICLE 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’S RESPONSIBILITY
46	RIM-1.5 STANDARD UNITS RIM-1.6 INSPECTION RIM-1.6.1 Duties of the Inspector 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
47	Tables Table RIM-1.9-1 Referenced Standards and Specifications
48	ARTICLE 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)
49	RIM-2.4 PLANT AND SSC RELIABILITY TARGET ALLOCATION 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
50	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 RIM-2.7.1 RIM Program Documentation RIM-2.7.2 Inspection Interval
51	RIM-2.7.3 Preservice Inspection RIM-2.7.4 Design Requirements for RIM RIM-2.7.5 Leak Detection System Requirements for RIM
52	RIM-2.7.6 Examination and Inspection Requirements for RIM
53	RIM-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
54	RIM-2.9.2 Surface Examination RIM-2.9.3 Volumetric Examination
55	RIM-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
56	ARTICLE RIM-3 ACCEPTANCE STANDARDS RIM-3.1 EVALUATION OF EXAMINATION RESULTS AND ACCEPTANCE STANDARDS
57	ARTICLE RIM-4 REPAIR/REPLACEMENT ACTIVITIES RIM-4.1 SCOPE RIM-4.2 LEAK TEST REQUIREMENTS AFTER A REPAIR/REPLACEMENT ACTIVITY 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
58	RIM-4.2.5 Exemptions RIM-4.3 RESPONSIBILITIES RIM-4.4 CORRECTIVE ACTION RIM-4.5 RECORDS
59	ARTICLE RIM-5 SYSTEM LEAK MONITORING AND PERIODIC TESTS RIM-5.1 SCOPE RIM-5.2 LEAKAGE MONITORING RIM-5.2.1 General RIM-5.2.2 Periodic Leak Test RIM-5.3 CORRECTIVE ACTION RIM-5.4 RECORDS
60	ARTICLE RIM-6 RECORDS AND REPORTS RIM-6.1 SCOPE RIM-6.2 REQUIREMENTS 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 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
61	RIM-6.3.5 Repair/Replacement Activity Records
62	ARTICLE RIM-7 GLOSSARY RIM-7.1 TERMS AND DEFINITIONS
64	MANDATORY APPENDIX I RIM DECISION FLOWCHARTS FOR USE WITH THE RIM PROGRAM ARTICLE I-1 FLOWCHARTS I-1.1 GENERAL
65	Figures Figure I-1.1-1 Conceptual Framework for RIM Program
66	Figure I-1.1-2 MANDE Selection Overview
67	Figure I-1.1-3 MANDE Selection Process
68	Figure I-1.1-4 MANDEEP Performance-Based Process
69	Figure I-1.1-5 MANDE Selection When Section XI, Division 1 Is Used
70	Figure I-1.1-6 Qualification Process for MANDE
71	Figure I-1.1-7 Process for Evaluating Which SSCs to Include in RIM Program and Redesign Process
72	MANDATORY APPENDIX II DERIVATION OF COMPONENT RELIABILITY TARGETS FROM PLANT SAFETY REQUIREMENTS ARTICLE II-1 GENERAL REQUIREMENTS II-1.1 SCOPE II-1.2 ADEQUACY OF THE PRA II-1.3 PROCEDURE OVERVIEW
73	ARTICLE II-2 RELIABILITY TARGET DERIVATION 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
74	MANDATORY APPENDIX III OWNER’S 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
75	Table III-1.1-1 Guide for Completing Form OAR-1
76	MANDATORY APPENDIX IV MONITORING AND NDE QUALIFICATION ARTICLE IV-1 INTRODUCTION IV-1.1 SCOPE IV-1.2 METHODS IV-1.3 OWNER’S REQUIREMENTS
78	ARTICLE IV-2 PROCEDURES, EQUIPMENT, AND PERSONNEL REQUIREMENTS IV-2.1 BASIC QUALIFICATION (FIGURES I-1.1-1 THROUGH I-1.1-7) IV-2.2 METHOD/TECHNIQUE PERSONNEL-SPECIFIC QUALIFICATIONS
79	ARTICLE IV-3 RELIABILITY-BASED QUALIFICATION OF MONITORING AND NDE (MANDE) METHODS AND TECHNIQUES IV-3.1 GENERAL IV-3.2 DETERMINATION OF THE QUALIFICATION REQUIREMENTS IV-3.3 QUALIFICATION PROCESS
81	ARTICLE IV-4 PERFORMANCE DEMONSTRATIONS FOR MANDE PERSONNEL (FIGURE I-1.1-6) IV-4.1 GENERAL IV-4.2 PERFORMANCE DEMONSTRATION FOR PERSONNEL FOR MONITORING METHODS IV-4.3 PERFORMANCE DEMONSTRATION FOR NDE PERSONNEL
82	ARTICLE IV-5 RECORDS IV-5.1 GENERAL IV-5.2 RECORDS FOR METHODS AND TECHNIQUE QUALIFICATION IV-5.3 RECORDS FOR PERSONNEL PERFORMANCE DEMONSTRATIONS
83	MANDATORY APPENDIX V CATALOG OF NDE REQUIREMENTS AND AREAS OF INTEREST ARTICLE V-1 TABLES V-1.1 GENERAL Table V-1.1-1 Examination Category A, Pressure-Retaining Welds in Reactor Vessels
84	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
85	Table V-1.1-4 Examination Category F, Pressure-Retaining Dissimilar Welds in Vessel Nozzles
86	Table V-1.1-5 Examination Category G-1, Pressure-Retaining Bolting Greater Than 2 in. (50 mm) in Diameter
87	Table V-1.1-6 Examination Category G-2, Pressure-Retaining Bolting 2 in. (50 mm) or Less in Diameter
88	Table V-1.1-7 Examination Category J, Pressure-Retaining Welds in Piping
89	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
90	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
91	Table V-1.1-13 Examination Category F-A, Supports
92	MANDATORY APPENDIX VI RELIABILITY AND INTEGRITY MANAGEMENT EXPERT PANEL (RIMEP) ARTICLE VI-1 OVERVIEW VI-1.1 RESPONSIBILITIES AND QUALIFICATIONS OF RIMEP
93	MANDATORY APPENDIX VII SUPPLEMENTS FOR TYPES OF NUCLEAR PLANTS ARTICLE VII-1 SUPPLEMENT FOR LIGHT WATER REACTOR–TYPE PLANTS VII-1.1 SCOPE VII-1.2 RIM PROGRAM — DAMAGE DEGRADATION ASSESSMENT VII-1.3 ACCEPTANCE STANDARDS
94	Table VII-1.2-1 Degradation Mechanism Attributes and Attribute Criteria (LWR)
101	VII-1.4 ACCEPTANCE STANDARDS FOR SPECIFIC EXAMINATION CATEGORIES
102	Table VII-1.3.3-1 Acceptance Standards
107	VII-1.5 ANALYTICAL EVALUATION OF PLANAR FLAWS
110	VII-1.6 ANALYTICAL EVALUATION OF PLANT OPERATING EVENTS
111	ARTICLE VII-2 SUPPLEMENT FOR LIQUID METAL REACTOR–TYPE PLANTS
112	ARTICLE VII-3 SUPPLEMENT FOR HIGH-TEMPERATURE GAS REACTOR–TYPE PLANTS VII-3.1 SCOPE VII-3.2 RIM PROGRAM — DAMAGE DEGRADATION ASSESSMENT VII-3.3 ACCEPTANCE STANDARDS
113	Table VII-3.2-1 Degradation Mechanism Attributes and Attribute Criteria
119	VII-3.4 ACCEPTANCE STANDARDS FOR SPECIFIC EXAMINATION CATEGORIES Table VII-3.3.3-1 Acceptance Standards
125	VII-3.5 ANALYTICAL EVALUATION OF PLANAR FLAWS
127	VII-3.6 ANALYTICAL EVALUATION OF PLANT OPERATING EVENTS
129	ARTICLE VII-4 SUPPLEMENT FOR MOLTEN SALT REACTOR–TYPE PLANTS
130	ARTICLE VII-5 SUPPLEMENT FOR GENERATION 2 LWR REACTOR–TYPE PLANTS
131	ARTICLE VII-6 SUPPLEMENT FOR FUSION MACHINE–TYPE PLANTS
132	NONMANDATORY APPENDIX A ALTERNATE REQUIREMENTS FOR NDE AND MONITORING ARTICLE A-1 GENERAL A-1.1 SCOPE A-1.2 METHODS A-1.3 RESPONSIBILITIES
133	Figure A-1.2-1 Logic Flow Diagram of the Process
134	ARTICLE A-2 PROCEDURE 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
135	ARTICLE 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 — RELIABILITY EVALUATION A-3.5 DETERMINISTIC APPROACH — MARGIN ASSESSMENT
136	ARTICLE 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
137	A-4.6 PROBABILISTIC APPROACH A-4.7 DETERMINISTIC APPROACH
138	ARTICLE A-5 PROCEDURE FOR STRUCTURAL RELIABILITY EVALUATION FOR PASSIVE COMPONENTS A-5.1 GENERAL REQUIREMENTS A-5.2 RELIABILITY EVALUATION Figure A-5.2.1-1 Reliability Evaluation Procedure
139	A-5.3 FAILURE SCENARIO SETTING Figure A-5.3.1-1 Failure Scenario Setting Procedure
140	A-5.4 MODELING Figure A-5.4.1-1 Modeling Procedure
141	A-5.5 RELIABILITY CALCULATION
142	ARTICLE A-6 RECORDS AND REPORT A-6.1 RETENTION OF RECORDS AND REPORTS
143	ARTICLE A-7 REFERENCES
144	NONMANDATORY APPENDIX B REGULATORY ADMINISTRATIVE PROVISIONS FOR NUCLEAR PLANTS 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 AUTHORITIES HAVING JURISDICTION AT THE PLANT SITE B-1.5 SUMMARY OF REPORT SUBMITTAL
145	ARTICLE B-2 REQUIREMENTS FOR PASSIVE COMPONENTS IN THE RIM PROGRAM B-2.1 REVIEW BY REGULATORY AND ENFORCEMENT AUTHORITIES HAVING JURISDICTION AT THE PLANT SITE
146	ENDNOTES

Published By	Publication Date	Number of Pages
ASME	2019	147


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Standard Title	ASME BPVC – XI – 2 -2019 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
Published Code	ASME
Publication Date	2019
Pages Count	147

ASME BPVC XI 2 2019

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