Establishes the requirements for preservice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants, including light-water small modular reactors (SMRs). It identifies the components subject to test or examination, responsibilities, methods, intervals, parameters to be measured and evaluated, criteria for evaluating the results, corrective action, personnel qualification, and record keeping. These requirements apply to : (a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident; (b) pressure relief devices that protect systems or portions of systems that perform one or more of these three functions; and (c) dynamic restraints (snubbers) used in systems that perform one or more of these three functions. Table of Contents

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4	CONTENTS
15	FOREWORD
16	COMMITTEE ON OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS
20	CORRESPONDENCE WITH THE OM COMMITTEE
22	PREFACE
24	ASME OM CASES AND APPLICABILITY INDEX FOR ASME OM CASES
25	CROSS-REFERENCING IN ASME OM
26	ASME OM-2022 SUMMARY OF CHANGES
30	DIVISION 1 OM CODE: SECTION IST Subsection ISTA General Requirements ISTA-1000 INTRODUCTION ISTA-1100 Scope ISTA-1200 Jurisdiction ISTA-1300 Application ISTA-1400 Referenced Standards and Specifications ISTA-1500 Owner’s Responsibilities
31	ISTA-1600 Accessibility ISTA-2000 DEFINITIONS
32	ISTA-3000 GENERAL REQUIREMENTS ISTA-3100 Test and Examination Program
33	ISTA-3200 Administrative Requirements
34	ISTA-3300 Corrective Actions ISTA-4000 INSTRUMENTATION AND TEST EQUIPMENT ISTA-4100 Range and Accuracy ISTA-4200 Calibration ISTA-5000 SPECIFIC TEST REQUIREMENTS ISTA-6000 MONITORING, ANALYSIS, AND EVALUATION ISTA-7000 TO BE PROVIDED AT A LATER DATE ISTA-8000 TO BE PROVIDED AT A LATER DATE ISTA-9000 RECORDS AND REPORTS ISTA-9100 Scope ISTA-9200 Requirements ISTA-9300 Retention
36	Subsection ISTB Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants — Pre-2000 Plants1 Pre-2000 plant: a nuclear power plant that was issued its construction permit by the applicable regulatory authority prior to January 1, 2000. ISTB-1000 INTRODUCTION ISTB-1100 Applicability ISTB-1200 Exclusions ISTB-1300 Pump Categories ISTB-1400 Owner’s Responsibility ISTB-2000 SUPPLEMENTAL DEFINITIONS ISTB-3000 GENERAL TESTING REQUIREMENTS ISTB-3100 Preservice Testing
37	ISTB-3200 Inservice Testing ISTB-3300 Reference Values
38	ISTB-3400 Frequency of Inservice Tests
39	ISTB-3500 Data Collection
40	ISTB-4000 TO BE PROVIDED AT A LATER DATE ISTB-5000 SPECIFIC TESTING REQUIREMENTS ISTB-5100 Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)
42	ISTB-5200 Vertical Line Shaft Centrifugal Pumps
44	ISTB-5300 Positive Displacement Pumps
45	Figures Figure ISTB-5223-1 Vibration Limits
46	Tables Table ISTB-5321-1 Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria
47	ISTB-6000 MONITORING, ANALYSIS, AND EVALUATION ISTB-6100 Trending ISTB-6200 Corrective Action Table ISTB-5321-2 Reciprocating Positive Displacement Pump Test Acceptance Criteria
48	ISTB-6300 Systematic Error ISTB-6400 Analysis of Related Conditions ISTB-7000 TO BE PROVIDED AT A LATER DATE ISTB-8000 TO BE PROVIDED AT A LATER DATE ISTB-9000 RECORDS AND REPORTS ISTB-9100 Pump Records ISTB-9200 Test Plans ISTB-9300 Record of Tests ISTB-9400 Record of Corrective Action
49	Subsection ISTC Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants ISTC-1000 INTRODUCTION ISTC-1100 Applicability ISTC-1200 Exclusions ISTC-1300 Valve Categories ISTC-1400 Owner’s Responsibility ISTC-2000 SUPPLEMENTAL DEFINITIONS
50	ISTC-3000 GENERAL TESTING REQUIREMENTS ISTC-3100 Preservice Testing ISTC-3200 Inservice Testing ISTC-3300 Reference Values
51	ISTC-3400 To Be Provided at a Later Date ISTC-3500 Valve Testing Requirements Table ISTC-3500-1 Inservice Test Requirements
53	ISTC-3600 Leak Testing Requirements ISTC-3700 Position Verification Testing
54	ISTC-4000 INSTRUMENTATION AND TEST EQUIPMENT ISTC-5000 SPECIFIC TESTING REQUIREMENTS ISTC-5100 Power-Operated Valves
55	ISTC-5200 Other Valves
58	ISTC-6000 MONITORING, ANALYSIS, AND EVALUATION ISTC-7000 TO BE PROVIDED AT A LATER DATE ISTC-8000 TO BE PROVIDED AT A LATER DATE ISTC-9000 RECORDS AND REPORTS ISTC-9100 Records ISTC-9200 Test Plans
59	Subsection ISTD Preservice and Inservice Requirements for Dynamic Restraints (Snubbers) in Water-Cooled Reactor Nuclear Power Plants ISTD-1000 INTRODUCTION ISTD-1100 Applicability ISTD-1400 Owner’s Responsibility ISTD-1500 Snubber Maintenance or Repair ISTD-1600 Snubber Modification and Replacement ISTD-1700 Deletions of Unacceptable Snubbers
60	ISTD-1800 Evaluation of Affected Systems, Structures, and Components ISTD-2000 DEFINITIONS
61	ISTD-3000 GENERAL REQUIREMENTS ISTD-3100 General Examination Requirements ISTD-3200 General Testing Requirements ISTD-3300 General Service-Life Monitoring Requirements ISTD-4000 SPECIFIC EXAMINATION REQUIREMENTS ISTD-4100 Preservice Examination
62	ISTD-4200 Inservice Examination
63	ISTD-5000 SPECIFIC TESTING REQUIREMENTS ISTD-5100 Preservice Operational Readiness Testing
64	Table ISTD-4252-1 Visual Examination Table
65	ISTD-5200 Inservice Operational Readiness Testing
66	ISTD-5300 The 10% Testing Sample
67	ISTD-5400 The 37 Testing Sample Plan
68	ISTD-5500 Retests of Previously Unacceptable Snubbers ISTD-6000 SERVICE LIFE MONITORING REQUIREMENTS ISTD-6100 Initial Service Life Figure ISTD-5431-1 The 37 Testing Sample Plan
69	ISTD-6200 Service Life Reevaluation ISTD-6300 Cause Determination ISTD-6400 Additional Monitoring Requirements for Snubbers That Are Tested Without Applying a Load to the Snubber Piston Rod ISTD-6500 Testing for Service Life Monitoring Purposes ISTD-6600 Review of Operational Readiness Test Data ISTD-6700 Examination During Assembly ISTD-7000 TO BE PROVIDED AT A LATER DATE ISTD-8000 TO BE PROVIDED AT A LATER DATE ISTD-9000 RECORDS AND REPORTS ISTD-9100 Snubber Records ISTD-9200 Test Plans
70	ISTD-9300 Record of Tests ISTD-9400 Record of Corrective Action ISTD-9500 Service Life Records
71	Subsection ISTE Risk-Informed Inservice Testing of Components in Water-Cooled Reactor Nuclear Power Plants ISTE-1000 INTRODUCTION ISTE-1100 Applicability ISTE-1200 Alternative ISTE-1300 General ISTE-2000 SUPPLEMENTAL DEFINITIONS
72	ISTE-3000 GENERAL REQUIREMENTS ISTE-3100 Implementation ISTE-3200 Probabilistic Risk Assessment ISTE-3300 Integrated Decision Making
73	ISTE-3400 Evaluation of Aggregate Risk ISTE-3500 Feedback and Corrective Actions ISTE-4000 SPECIFIC COMPONENT CATEGORIZATION REQUIREMENTS ISTE-4100 Component Risk Categorization
74	ISTE-4200 Component Safety Categorization
75	ISTE-4300 Testing Strategy Formulation ISTE-4400 Evaluation of Aggregate Risk
76	ISTE-4500 Inservice Testing Program ISTE-5000 SPECIFIC TESTING REQUIREMENTS ISTE-5100 Pumps
77	ISTE-5200 Check Valves ISTE-5300 Motor-Operated Valve Assemblies ISTE-5400 Pneumatically Operated Valves ISTE-5500 To Be Provided at a Later Date Table ISTE-5121-1 LSSC Pump Testing
78	ISTE-6000 MONITORING, ANALYSIS, AND EVALUATION ISTE-6100 Performance Monitoring ISTE-6200 Feedback and Corrective Actions ISTE-7000 TO BE PROVIDED AT A LATER DATE ISTE-8000 TO BE PROVIDED AT A LATER DATE ISTE-9000 RECORDS AND REPORTS ISTE-9100 Plant Expert Panel Records ISTE-9200 Component Records
79	Subsection ISTF Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants — Post-2000 Plants ISTF-1000 INTRODUCTION ISTF-1100 Applicability ISTF-1200 Exclusions ISTF-1300 Owner’s Responsibility ISTF-2000 SUPPLEMENTAL DEFINITIONS ISTF-3000 GENERAL TESTING REQUIREMENTS ISTF-3100 Preservice Testing
80	ISTF-3200 Inservice Testing ISTF-3300 Reference Values Table ISTF-3000-1 Inservice Test Parameters
81	ISTF-3400 Frequency of Inservice Tests ISTF-3500 Data Collection Table ISTF-3510-1 Required Instrument Accuracy
82	ISTF-4000 TO BE PROVIDED AT A LATER DATE ISTF-5000 SPECIFIC TESTING REQUIREMENTS ISTF-5100 Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)
83	ISTF-5200 Vertical Line Shaft Centrifugal Pumps
84	ISTF-5300 Positive Displacement Pumps Table ISTF-5120-1 Centrifugal Pump Test Acceptance Criteria
85	ISTF-6000 MONITORING, ANALYSIS, AND EVALUATION ISTF-6100 Trending ISTF-6200 Corrective Action Table ISTF-5220-1 Vertical Line Shaft and Centrifugal Pump Test Acceptance Criteria
86	ISTF-6300 Systematic Error ISTF-6400 Analysis of Related Conditions Table ISTF-5320-1 Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria Table ISTF-5320-2 Reciprocating Positive Displacement Pump Test Acceptance Criteria
87	ISTF-7000 TO BE PROVIDED AT A LATER DATE ISTF-8000 TO BE PROVIDED AT A LATER DATE ISTF-9000 RECORDS AND REPORTS ISTF-9100 Pump Records ISTF-9200 Test Plans ISTF-9300 Record of Tests ISTF-9400 Record of Corrective Action
88	Division 1, Mandatory Appendices Division 1, Mandatory Appendix I Inservice Testing of Pressure Relief Devices in Water-Cooled Reactor Nuclear Power Plants I-1000 GENERAL REQUIREMENTS
90	I-2000 INTRODUCTION I-3000 PRESSURE RELIEF DEVICE TESTING
94	I-4000 TEST METHODS
97	I-5000 RECORDS AND RECORD KEEPING Table I-4220-1 Seat Tightness Testing Methods for Pressure Relief Devices
98	Division 1, Mandatory Appendix II Check Valve Condition-Monitoring Program II-1000 PURPOSE II-2000 GROUPINGS II-3000 ANALYSIS II-4000 CONDITION-MONITORING ACTIVITIES
99	II-5000 CORRECTIVE MAINTENANCE Table II-4000-1 Maximum Intervals for Use When Applying Internal Extensions
100	II-6000 DOCUMENTATION
101	Division 1, Mandatory Appendix III Preservice and Inservice Testing of Active Electric Motor-Operated Valve Assemblies in Water-Cooled Reactor Nuclear Power Plants III-1000 INTRODUCTION III-2000 SUPPLEMENTAL DEFINITIONS III-3000 GENERAL TESTING REQUIREMENTS
103	III-4000 TO BE PROVIDED AT A LATER DATE III-5000 TEST METHODS
104	III-6000 ANALYSIS AND EVALUATION OF DATA
105	III-7000 TO BE PROVIDED AT A LATER DATE III-8000 TO BE PROVIDED AT A LATER DATE III-9000 RECORDS AND REPORTS
106	Division 1, Mandatory Appendix IV Preservice and Inservice Testing of Active Pneumatically Operated Valve Assemblies in Nuclear Reactor Power Plants IV-1000 INTRODUCTION IV-2000 SUPPLEMENTAL DEFINITIONS
107	IV-3000 GENERAL TESTING REQUIREMENTS
109	IV-4000 RESERVED IV-5000 PERFORMANCE ASSESSMENT TEST METHODS
110	IV-6000 PERFORMANCE ASSESSMENT TEST ANALYSIS AND EVALUATION
111	IV-7000 STROKE TEST AND FAIL SAFE DATA ANALYSIS AND EVALUATION IV-8000 RESERVED IV-9000 RECORDS AND REPORTS
112	Division 1, Nonmandatory Appendices Division 1, Nonmandatory Appendix A Preparation of Test Plans A-1000 PURPOSE A-2000 TEST PLAN CONTENTS
113	A-3000 SUBSTITUTE TESTS AND EXAMINATIONS
114	Division 1, Supplement to Nonmandatory Appendix A AS-1000 SUPPLEMENT 1: INFORMATION FOR ISTB PUMP TEST TABLES AS-2000 SUPPLEMENT 2: INFORMATION FOR ISTC VALVE TEST TABLES AS-3000 SUPPLEMENT 3: INFORMATION FOR ISTD DYNAMIC RESTRAINT (SNUBBER) TABLES
115	Division 1, Nonmandatory Appendix B Dynamic Restraint Examination Checklist Items B-1000 PURPOSE B-2000 EXAMPLES FOR PRESERVICE AND INSERVICE B-3000 EXAMPLES FOR PRESERVICE ONLY
116	Division 1, Nonmandatory Appendix C Dynamic Restraint Design and Operating Information C-1000 PURPOSE C-2000 DESIGN AND OPERATING ITEMS
117	Division 1, Nonmandatory Appendix D Comparison of Sampling Plans for Inservice Testing of Dynamic Restraints D-1000 PURPOSE D-2000 DESCRIPTION OF THE SAMPLING PLANS D-3000 COMPARISON OF SAMPLING PLANS
118	Division 1, Nonmandatory Appendix E Flowcharts for 10% and 37 Snubber Testing Plans E-1000 PURPOSE
119	Figure E-1000-1 Flowchart for 10% Snubber Testing Plan (ISTD-5300)
120	Figure E-1000-2 Flowchart for 37 Snubber Testing Plan (ISTD-5400)
121	Division 1, Nonmandatory Appendix F Dynamic Restraints (Snubbers) Service Life Monitoring Methods F-1000 PURPOSE F-2000 PREDICTED SERVICE LIFE F-3000 SERVICE LIFE REEVALUATION
122	F-4000 SHORTENED SERVICE LIFE F-5000 SERVICE LIFE EXTENSION F-6000 SEPARATE SERVICE LIFE POPULATIONS
123	Division 1, Nonmandatory Appendix G Application of Table ISTD-4252-1, Snubber Visual Examination G-1000 PURPOSE G-2000 ASSUMPTIONS G-3000 CASE 1: EXAMINE ACCESSIBLE AND INACCESSIBLE SNUBBERS JOINTLY
124	G-4000 CASE 2: EXAMINE ACCESSIBLE AND INACCESSIBLE SNUBBERS SEPARATELY
125	Division 1, Nonmandatory Appendix H Test Parameters and Methods H-1000 PURPOSE H-2000 TEST VARIABLES H-3000 TEST PARAMETER MEASUREMENT H-4000 GENERAL TESTING CONSIDERATIONS
127	Division 1, Nonmandatory Appendix J Check Valve Testing Following Valve Reassembly J-1000 PURPOSE J-2000 POSTDISASSEMBLY TEST RECOMMENDATIONS J-3000 TEST MATRIX
128	Table J-2000-1 Check Valve Test Matrix
129	Division 1, Nonmandatory Appendix K Sample List of Component Deterministic Considerations K-1000 PURPOSE K-2000 SAMPLE DETERMINISTIC CONSIDERATIONS
130	Division 1, Nonmandatory Appendix L Acceptance Guidelines L-1000 PURPOSE L-2000 ACCEPTANCE GUIDELINES
131	Figure L-2100-1 Acceptance Guidelines for CDF (Adapted From RG 1.174)
132	Figure L-2100-2 Acceptance Guidelines for LERF (Adapted From RG 1.174)
133	Division 1, Nonmandatory Appendix M Design Guidance for Nuclear Power Plant Systems and Component Testing M-1000 PURPOSE M-2000 BACKGROUND M-3000 GUIDANCE
138	M-4000 REFERENCES
139	DIVISION 2 OM STANDARDS Part 2 Performance Testing of Closed Cooling Water Systems in Light-Water Reactor Power Plants
140	Part 3 Vibration Testing of Piping Systems 1 SCOPE 2 DEFINITIONS
141	3 GENERAL REQUIREMENTS Figure 1 Typical Components of a Vibration Monitoring System (VMS)
142	3.1 Classification Table 1 System Tolerances
143	3.2 Monitoring Requirements and Acceptance Criteria
145	4 VISUAL INSPECTION METHOD 4.1 Objective 4.2 Evaluation Techniques 4.3 Precautions 5 SIMPLIFIED METHOD FOR QUALIFYING PIPING SYSTEMS 5.1 Steady-State Vibration
147	Figure 2 Deflection Measurement at the Intersection of Pipe and Elbow Figure 3 Single Span Deflection Measurement Figure 4 Cantilever Span Deflection Measurement Figure 5 Cantilever Span/Elbow Span In-Plane Deflection Measurement Figure 6 Cantilever Span/Elbow Guided Span In-Plane Deflection Measurement Figure 7 Span/Elbow Span Out-of-Plane Deflection Measurement, Span Ratio < 0.5
148	Figure 8 Span/Elbow Span Out-of-Plane Deflection Measurement, Span Ratio > 0.5 Figure 9 Span/Elbow Span Out-of-Plane Configuration Coefficient Versus Ratio of Spans
149	Figure 10 Correction Factor C1
150	5.2 Transient Vibration 5.3 Inaccessible Piping (for Both Steady-State and Transient Vibration Evaluation) 6 RIGOROUS VERIFICATION METHOD FOR STEADY-STATE AND TRANSIENT VIBRATION 6.1 Test and Analysis Correlation Technique
151	6.2 Measured Stress Technique 7 INSTRUMENTATION AND VIBRATION MEASUREMENT REQUIREMENTS 7.1 General Requirements
152	8 CORRECTIVE ACTION Table 2 Examples of Specifications of VMS Minimum Requirements; Measured Variable — Displacement
153	Part 3, Nonmandatory Appendices Part 3, Nonmandatory Appendix A Instrumentation and Measurement Guidelines A-1 PURPOSE A-2 VISUAL METHODS (VMG 3) A-3 ELECTRONIC MEASUREMENT METHODS (VMG 2 AND VMG 1)
157	Part 3, Nonmandatory Appendix B Data Processing Methods B-1 PURPOSE B-2 TIME DOMAIN DATA PROCESSING CONSIDERATIONS
158	Figure B-1 Example of Time Span Selection to Exclude Spurious Data Figure B-2 Example of DC Offset Removal
159	Figure B-3 Example of Band-Pass Filtering Between 5 Hz and 200 Hz Figure B-4 Example of Band-Stop Filtering for a 60 Hz Electrical Noise Peak
160	B-3 FREQUENCY DOMAIN DATA PROCESSING CONSIDERATIONS Figure B-5 Example of Zero‐to-Peak and Peak‐to-Peak Values
162	Figure B-6 Example of 50% Spectral Block Overlapping
163	Part 3, Nonmandatory Appendix C Vibration Analysis Methods C-1 PURPOSE C-2 RESPONSE SPECTRUM ANALYSIS METHOD C-3 TIME HISTORY ANALYSIS METHOD C-4 VIBRATION ACCEPTANCE CRITERIA ANALYSIS
164	C-5 ACOUSTIC VIBRATION ANALYSIS
165	Part 3, Nonmandatory Appendix D Velocity Criterion D-1 VELOCITY CRITERION D-2 SCREENING VELOCITY CRITERION D-3 USE OF SCREENING VIBRATION VELOCITY VALUE
166	Part 3, Nonmandatory Appendix E Excitation Mechanisms, Responses, and Corrective Actions E-1 EXCITATION MECHANISMS AND PIPING RESPONSES
168	E-2 ADDITIONAL TESTING AND ANALYSIS
169	Part 3, Nonmandatory Appendix F Flowchart — Outline of Vibration Qualification of Piping Systems
170	Figure F-1 Flowchart — Outline of Vibration Qualification of Piping Systems
171	Part 3, Nonmandatory Appendix G Qualitative Evaluations
172	Part 3, Nonmandatory Appendix H Guidance for Monitoring Piping Steady-State Vibration Per Vibration Monitoring Group 2 H-1 PURPOSE H-2 ASSUMPTIONS H-3 IMPLEMENTATION
174	Figure H-1 Monitoring and Qualification of Piping Steady-State Vibration
175	Table H-1 Recommended Actions for Piping Vibration Problem Resolution
176	H-4 ALLOWABLE DISPLACEMENT LIMIT
177	Part 3, Nonmandatory Appendix I Acceleration Limits for Small Branch Piping
178	Figure I-1 Determination of LE and WT
179	Part 5 Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactor Power Plants 1 PURPOSE AND SCOPE 2 BACKGROUND
180	Figure 1 Reactor Arrangement Showing Typical Ex-Core Detector Locations
181	3 PROGRAM DESCRIPTION 4 BASELINE PHASE
182	Table 1 Summary of Program Phases
183	5 SURVEILLANCE PHASE 6 DIAGNOSTIC PHASE
185	Part 5, Nonmandatory Appendices Part 5, Nonmandatory Appendix A Theoretical Basis
186	Figure A-1 Idealized Analysis for Core Barrel Motion
187	Part 5, Nonmandatory Appendix B Data Reduction Techniques B-1 NORMALIZED POWER SPECTRAL DENSITY (NPSD) B-2 NORMALIZED ROOT MEAN SQUARE OF THE SIGNAL B-3 NORMALIZED CROSS-POWER SPECTRAL DENSITY (NCPSD), COHERENCE (COH), AND PHASE (ϕ)
188	Figure B-1 Representative Spectra
189	Part 5, Nonmandatory Appendix C Data Acquisition and Reduction C-1 INSTRUMENTATION C-2 SIGNAL CONDITIONING C-3 DATA ACQUISITION PARAMETERS C-4 PLANT CONDITIONS FOR DATA ACQUISITION C-5 DATA REDUCTION PARAMETERS
190	C-6 SIGNAL BUFFERING C-7 DATA ASSURANCE C-8 DATA RETENTION Table C-1 Parameters to Be Documented During Data Acquisition
191	C-9 STATISTICAL UNCERTAINTIES IN NEUTRON NOISE DATA ANALYSIS
192	Part 5, Nonmandatory Appendix D Data Evaluation D-1 BASELINE
193	D-2 SURVEILLANCE PHASE D-3 DIAGNOSTIC PHASE Figure D-1 Narrowband rms
194	Figure D-2 Example of Wideband rms Amplitude Versus Boron Concentration
196	Part 5, Nonmandatory Appendix E Guidelines for Evaluating Baseline Signal Deviations
197	Figure E-1 Typical Ex-Core Neutron Noise Signatures From Six PWRs
198	Figure E-2 Typical Baseline NPSD Range
199	Figure E-3 Examples of Changes in the Neutron Noise Signature Over a Fuel Cycle
200	Figure E-4 Example of Loss of Axial Restraint
201	Part 5, Nonmandatory Appendix F Correlation of rms Amplitude of the Ex-Core Signal (Percent Noise) and Amplitude of Core Barrel Motion Table F-1 Ratio of the Amplitude of the Neutron Noise to Core Barrel Motion
202	Part 5, Nonmandatory Appendix G Bibliography
203	Part 7 Thermal Expansion Testing of Nuclear Power Plant Piping Systems 1 SCOPE 2 DEFINITIONS
204	3 GENERAL REQUIREMENTS
205	4 RECONCILIATION METHODS
206	5 CORRECTIVE ACTION
207	Figure 1 System Heatup, Reconciliation, and Corrective Action
208	6 INSTRUMENTATION REQUIREMENTS FOR THERMAL EXPANSION MEASUREMENT Figure 2 Typical Components of a TEMS Table 1 An Example of Specification of TEMS Minimum Requirements
210	Part 7, Nonmandatory Appendices Part 7, Nonmandatory Appendix A TEMS Instrumentation and Equipment Guidelines
211	Table A-1 Typical Transducers
212	Table A-2 Typical Signal Conditioners Table A-3 Typical Data Processing, Display, and Recording Equipment
213	Part 7, Nonmandatory Appendix B Thermal Stratification and Thermal Transients B-1 INTRODUCTION B-2 THERMAL STRATIFICATION
214	B-3 THERMAL TRANSIENTS Figure B-1 Simplified Schematic of Surge Line Stratification
216	Part 12 Loose Part Monitoring in Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 2 DEFINITIONS
218	3 REFERENCES 4 EQUIPMENT
219	Figure 1 Typical Broadband Sensor Response to Nearby Impact Figure 2 Typical Broadband Sensor Response to More Distant Impact
220	Figure 3 Range of Loose Part Signal Amplitude and Predominant Frequency Content Figure 4 Field Equipment
221	Figure 5 Direct Stud Mount Figure 6 Clamped Mount
222	Table 1 Recommended PWR Accelerometer Locations
223	Figure 7 Recommended Sensor Array for PWR With U-Tube Steam Generator
224	Figure 8 Recommended Sensor Array for PWR With Once-Through Steam Generator Table 2 Recommended BWR Accelerometer Locations
225	Figure 9 Recommended Sensor Array for BWR
227	5 PROGRAM ELEMENTS
228	Figure 10 Block Diagram for Charge Converter Calibration Tests
230	Figure 11 Cable Properties (Typical for Twisted-Shielded Pair Cable)
231	6 DOCUMENTATION
233	Part 12, Nonmandatory Appendix A References
234	Part 16 Performance Testing and Monitoring of Standby Diesel Generator Systems in Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Purpose 1.3 Risk-Informed Analysis 1.4 Subsystems Included Within the Diesel Generator Boundary
235	Figure 1 Boundary and Support Systems of Emergency Diesel Generator Systems
236	1.5 Definitions
237	2 NONOPERATING CHECKS 3 TESTING
239	Table 1 Periodic Tests
241	4 INSERVICE MONITORING OF COMPONENT OPERATING AND STANDBY CONDITIONS
242	4.1 Engine 4.2 Lubrication Subsystem 4.3 Jacket Water and Intercooler Subsystem 4.4 Starting Subsystem 4.5 Combustion Air Intake Subsystem
243	4.6 Exhaust Subsystem 4.7 Fuel Oil Subsystem 4.8 Crankcase Ventilation Subsystem 4.9 Governor and Control Subsystem 4.10 Generator Subsystem 4.11 Ventilation and Cooling Subsystem 4.12 Exciter and Voltage Regulator Subsystem 4.13 Control and Protection Subsystem 4.14 Diesel Generator Output Breaker 5 OTHER CONDITION-MONITORING METHODS/GUIDELINES 5.1 Diesel Engine Analysis
244	5.2 Vibration Analysis
245	5.3 Lube Oil Analysis 5.4 Cooling Water Analysis 5.5 Thermography
246	6 ALARM AND SHUTDOWN DURING TESTS 7 DIESEL GENERATOR OPERATING DATA AND RECORDS 7.1 Data/Records 7.2 Data Evaluation and Trending 7.3 Failure to Function (Root Cause)
247	Part 16, Nonmandatory Appendices Part 16, Nonmandatory Appendix A Post-Major Maintenance Test Data Figure A-1 Post-Major Maintenance Test Data Form
248	Part 16, Nonmandatory Appendix B Functional/Inservice Test Data Figure B-1 Functional/Inservice Test Data Form
249	Part 16, Nonmandatory Appendix C Data Trending Examples
250	Figure C-1 Typical Lube Oil System
251	Figure C-2 Typical Jacket Water System
252	Figure C-3 Intercooler Water System
253	Figure C-4 Typical Air/Exhaust System
254	Figure C-5 Typical Fuel Oil System
255	Part 21 Inservice Performance Testing of Heat Exchangers in Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Exclusions 1.3 Owner’s Responsibility 2 DEFINITIONS
257	3 REFERENCES 3.1 Standard References 3.2 Appendix References
258	4 SELECTION AND PRIORITIZATION OF HEAT EXCHANGERS 4.1 Heat Exchanger Selection 4.2 Heat Exchanger Prioritization 5 BASIC REQUIREMENTS 5.1 Program Requirements 5.2 Preservice Requirements 5.3 Inservice Requirements
259	5.4 Interval Requirements 6 SELECTION OF METHODS 6.1 Functional Test Method
260	Figure 1 Intervals, Limits, and Parameter Trending (Typical)
261	Figure 2 Method Selection Chart
262	6.2 Heat-Transfer Coefficient Test Method (Without Phase Change) 6.3 Heat-Transfer Coefficient Test Method (With Condensation)
263	6.4 Transient Test Method 6.5 Temperature Effectiveness Test Method
264	6.6 Batch Test Method
265	6.7 Temperature-Difference Monitoring Method 6.8 Pressure-Loss Monitoring Method
266	6.9 Visual Inspection Monitoring Method 6.10 Parameter Trending 7 TESTING AND MONITORING CONDITIONS 7.1 Steady State
267	7.2 Flow Regimes
268	7.3 Temperatures 8 ERRORS, SENSITIVITIES, AND UNCERTAINTIES 8.1 Measurement Errors 8.2 Result Sensitivities 8.3 Total Uncertainty
269	8.4 Calculations and Averaging 8.5 Validity Check 8.6 Correlational Uncertainty 9 ACCEPTANCE CRITERIA 9.1 System Operability Limits 9.2 Component Design Limits
270	9.3 Required Action Limits 10 CORRECTIVE ACTION 11 RECORDS AND RECORD KEEPING 11.1 Equipment Records 11.2 Plans and Procedures
271	11.3 Record of Results 11.4 Record of Corrective Action
272	Part 21, Nonmandatory Appendices Part 21, Nonmandatory Appendix A Diagnostics A-1 HEAT DUTY DEFICIENCY
273	A-2 EXCESSIVE PRESSURE LOSS A-3 MECHANICAL DYSFUNCTION
275	Part 21, Nonmandatory Appendix B Precautions B-1 EXCESSIVE FLOW B-2 CROSSING FLOW REGIMES B-3 TEMPERATURE STRATIFICATION B-4 OVERCOOLING
276	B-5 FLASHING B-6 EFFECTIVE SURFACE AREA B-7 WATER HAMMER B-8 MISCELLANEOUS CONSIDERATIONS B-9 FLOW INSTABILITY B-10 PLATE HEAT EXCHANGERS B-11 FOULING CHARACTERISTICS
277	B-12 COMPONENT DESIGN FUNCTION B-13 THERMAL DELAYS B-14 MATERIAL PROPERTIES
278	Part 21, Nonmandatory Appendix C Examples C-1 FUNCTIONAL TEST METHOD C-2 HEAT TRANSFER COEFFICIENT TEST METHOD (WITHOUT PHASE CHANGE)
288	C-3 HEAT TRANSFER COEFFICIENT TEST METHOD (WITH CONDENSATION)
289	Figure C-1 One Tube Row Air-to-Water Cross-Flow Heat Exchanger
290	Figure C-2 Fin, Condensate Layer, and Interfaces
294	C-4 TRANSIENT TEST METHOD
296	Figure C-3 Schematic Representation of a Countercurrent Shell-and-Tube Heat Exchanger Figure C-4 A Small Element of a Countercurrent Shell-and-Tube Heat Exchanger
298	C-5 TEMPERATURE EFFECTIVENESS TEST METHOD
299	C-6 BATCH TEST METHOD
301	C-7 TEMPERATURE DIFFERENCE MONITORING METHOD
302	Figure C-5 Cooling Water Inlet Temperature Versus Temperature Difference
303	C-8 PRESSURE LOSS MONITORING METHOD
304	C-9 VISUAL INSPECTION MONITORING METHOD
305	C-10 PARAMETER TRENDING
306	C-11 UNCERTAINTY ANALYSIS
310	Part 24 Reactor Coolant and Recirculation Pump Condition Monitoring 1 INTRODUCTION 1.1 Scope 1.2 Approach 2 DEFINITIONS
312	3 REFERENCES 4 MACHINE FAULTS 4.1 Introduction 5 VIBRATION, AXIAL POSITION, AND BEARING TEMPERATURE MONITORING EQUIPMENT 5.1 General
313	Table 1 Pumpset Mechanical Faults Table 2 Seal Faults
314	5.2 Monitoring System 5.3 Radial Proximity Sensor Locations Table 3 Electrical Motor Faults
315	5.4 Axial Proximity Sensor Locations 5.5 Phase-Reference Sensor Location 5.6 Bearing Temperature Sensors 5.7 Sensor Locations for Optional Accelerometers 5.8 Other Specifications 6 VIBRATION DATA ANALYSIS SYSTEM REQUIREMENTS 6.1 Introduction 6.2 Data Acquisition for Dynamic Signals
316	6.3 System Accuracy and Calibration 6.4 Data Analysis and Display 6.5 Data Storage
317	6.6 Continuous Display of Dynamic Signals 7 SEAL MONITORING 7.1 Introduction 7.2 Monitoring System 7.3 Monitoring and Analysis Requirements
318	7.4 Seal Alarm Response 7.5 Enhanced Monitoring of a Troubled Seal 8 VIBRATION, AXIAL POSITION, AND BEARING TEMPERATURE MONITORING 8.1 Introduction 8.2 Postmaintenance Monitoring Table 4 Minimum Monitoring and Recording Intervals
319	8.3 Baseline 8.4 Periodic Monitoring
320	8.5 Preoutage Coastdown 8.6 Vibration Alarm Response 8.7 Enhanced Monitoring of a Troubled Pumpset 9 ALARM SETTINGS 9.1 Determining Alarm Points for Overall Vibration Amplitude
321	9.2 Determining 1x and 2x Vector Acceptance Regions 9.3 Determining Alarm Points for Thrust Position 9.4 Determining Alarm Points for Bearing Temperature 9.5 Alarm Settings 10 ANALYSIS AND DIAGNOSTICS 10.1 Introduction 10.2 Data Types 10.3 Analysis Methods Table 5 Typical Thrust Position Alarm Setpoints for a Pump With Normal Upthrust
322	10.4 Data Analysis 11 ADDITIONAL TECHNOLOGIES 11.1 Thermography 11.2 Lube Oil Analysis 11.3 Motor Current Signature Analysis 11.4 Motor Electrical Monitoring and Testing
323	11.5 Loose Parts Monitoring 12 OTHER 12.1 Calibrations 12.2 Quality
324	Part 24, Nonmandatory Appendices Part 24, Nonmandatory Appendix A References
325	Part 24, Nonmandatory Appendix B Thermography
326	Part 24, Nonmandatory Appendix C Lube Oil Analysis
327	Part 24, Nonmandatory Appendix D Motor Current Signature Analysis
328	Part 24, Nonmandatory Appendix E Loose Parts Monitoring
329	Part 25 Performance Testing of Emergency Core Cooling Systems in Light-Water Reactor Power Plants
330	Part 26 Determination of Reactor Coolant Temperature From Diverse Measurements 1 INTRODUCTION 1.1 Scope 1.2 Applicability 1.3 Basic Methodology 2 DEFINITIONS
331	3 REFERENCES 4 REQUIREMENTS 4.1 Plant Conditions 4.2 Test Equipment 4.3 Uncertainty Methodologies
332	5 DEVELOP TEST PROCEDURES AND PERFORM TESTING 5.1 Establish Primary-to-Secondary Side ΔTps 5.2 Test Procedure Development
333	5.3 Perform Test 6 DOCUMENTATION
334	Part 26, Nonmandatory Appendix A Measurement Equipment Uncertainties
335	Part 28 Standard for Performance Testing of Systems in Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Exclusions 1.3 Owner’s Responsibilities 2 DEFINITIONS
336	3 REFERENCES 4 GENERAL TESTING REQUIREMENTS 4.1 Establish System Test Boundaries 4.2 Identify System Performance Requirements
337	4.3 Identify Testable Characteristics 4.4 Establish Acceptance Criteria
338	4.5 Develop Test Procedures and Perform Testing, Inspections, and Engineering Analysis
341	5 SPECIFIC TESTING REQUIREMENTS 5.1 Emergency Core Cooling Systems 5.2 Auxiliary or Emergency Feedwater Systems 5.3 Closed Cooling Water Systems 5.4 Emergency Service Water Systems 5.5 Instrument Air Systems 6 EVALUATE TEST DATA 6.1 Compare Data to Acceptance Criteria 6.2 Trend Test Data 6.3 Evaluate Test Interval
342	7 DOCUMENTATION 7.1 System Test Plan 7.2 Test Results and Corrective Actions
343	Part 28, Mandatory Appendix I Specific Testing Requirements of Emergency Core Cooling Systems in BWR Power Plants I-1 INTRODUCTION I-2 DEFINITIONS I-3 REFERENCE I-4 BWR ECCS TESTING REQUIREMENTS I-4.1 Establish System Testing Boundaries I-4.2 Identify System Performance Requirements I-4.3 Identify Testable Characteristics That Represent Performance Requirements Part 28, Mandatory Appendices
344	I-4.3.1 Component Characteristics. I-4.3.2 Instrumentation and Control (I&C) Characteristics. I-4.3.3 ECCS Logic Characteristics. I-4.3.4 System Characteristics. I-4.3.4.1 High-Pressure Injection Mode Characteristics. I-4.3.4.2 Depressurization Mode Characteristics. I-4.3.4.3 Low-Pressure Injection Mode Characteristics. I-4.3.4.4 Long-Term Decay Heat Removal Mode Characteristics. I-4.4 Establish Characteristic Acceptance Criteria I-4.5 Develop Test Procedures and Perform Testing, Inspections, and Engineering Analysis I-4.5.1 Preservice Testing.
345	I-4.5.1.1 Preservice Test Prerequisites. I-4.5.1.2 Preservice Performance Test. I-4.5.1.3 Preservice Test Interval. I-4.5.2 Inservice Testing. I-4.5.2.1 High-Pressure Injection Mode. I-4.5.2.2 Depressurization Mode I-4.5.2.3 Low-Pressure Injection Mode. I-4.5.2.4 Long-Term Decay Heat Removal Mode. I-4.5.2.5 Inservice Test Interval.
347	Part 28, Mandatory Appendix II Specific Testing Requirements of Emergency Core Cooling Systems in PWR Power Plants II-1 INTRODUCTION II-2 DEFINITIONS II-3 REFERENCES II-4 PWR ECCS TESTING REQUIREMENTS
351	Part 28, Mandatory Appendix III Specific Testing Requirements of Auxiliary or Emergency Feedwater Systems in Water-Cooled Reactor Nuclear Power Plants III-1 INTRODUCTION III-2 DEFINITION III-3 REFERENCES III-4 AUXILIARY FEEDWATER SYSTEM TESTING REQUIREMENTS
353	Part 28, Mandatory Appendix IV Specific Testing Requirements of Closed Cooling Water Systems in Water-Cooled Reactor Nuclear Power Plants IV-1 INTRODUCTION IV-2 DEFINITIONS IV-3 CLOSED COOLING WATER SYSTEM TESTING REQUIREMENTS
354	Figure IV-1 CCWS Typical Flow Diagram
357	Part 28, Mandatory Appendix V Specific Testing Requirements of Emergency Service Water Systems in Water-Cooled Reactor Nuclear Power Plants (Open Cooling Water Systems) V-1 INTRODUCTION V-2 DEFINITIONS V-3 EMERGENCY SERVICE WATER SYSTEM TEST REQUIREMENTS V-4 ESTABLISH SYSTEM TEST BOUNDARIES
360	Part 28, Mandatory Appendix VI Specific Testing Requirements of Instrument Air Systems in Water-Cooled Reactor Nuclear Power Plants VI-1 INTRODUCTION VI-2 DEFINITIONS VI-3 INSTRUMENT AIR SYSTEM TESTING REQUIREMENTS
361	Figure VI-1 Typical Instrument Air System
365	Part 28, Nonmandatory Appendices Part 28, Nonmandatory Appendix A Industry Guidance
366	Table A-1 Operating Experience Information
369	Part 28, Nonmandatory Appendix B Guidance for Testing Certain System Characteristics B-1 PURPOSE B-2 VERIFYING ECCS ACCUMULATOR DISCHARGE FLOW PATH RESISTANCE IN PWRS B-3 TYPICAL PROCESS SUBSYSTEM B-4 IDENTIFYING AND VERIFYING PUMP TDH VERSUS FLOW ACCEPTANCE CRITERIA B-5 VERIFYING DISCHARGE FLOW PATH RESISTANCE
370	Figure B-1 Typical Branch Line System Figure B-2 Verifying Pump TDH Versus Flow: Correction of Measured Data for Instrument Accuracy
371	Figure B-3 Verifying Pump TDH Versus Flow: Correction of Analysis Limits for Instrument Accuracy
372	Figure B-4 Verifying Discharge Piping Overall Resistance: Correction of Measured Data for Instrument Accuracy Figure B-5 Verifying Discharge Piping Overall Resistance: Correction of Analysis Limits for Instrument Accuracy
373	B-6 VERIFYING BALANCED BRANCH LINE RESISTANCE B-7 SYSTEM ADJUSTMENTS
374	Figure B-6 Measured Subsystem Operating Point and Range of Operating Points Allowed by Analysis Limits
375	Part 28, Nonmandatory Appendix C Measurement Accuracy of System Characteristics C-1 BACKGROUND C-2 NOMENCLATURE
376	C-3 SENSITIVITY COEFFICIENTS C-4 ACCURACY OF DIRECTLY MEASURED VARIABLES C-5 ACCURACY OF DERIVED VARIABLES
377	C-6 ACCURACY OF FLOW RATE C-7 ACCURACY OF PUMP TDH
378	C-8 ACCURACY OF SYSTEM RESISTANCE C-9 EXAMPLE EVALUATION OF PUMP TDH ACCURACY
379	Table C-1 Recorded Test Data Table C-2 Calculated Pump Head Table C-3 Sensitivity Coefficients for Pump TDH
381	Table C-4 Pump TDH Overall Accuracy Calculation
382	DIVISION 3 OM GUIDES Part 11 Vibration Testing and Assessment of Heat Exchangers 1 INTRODUCTION 1.1 Scope 2 DEFINITIONS 3 REFERENCES 4 BACKGROUND DESCRIPTION
383	5 SELECTION OF EQUIPMENT TO BE TESTED 5.1 Equipment Selection Factors
384	6 SELECTION OF TEST METHOD 6.1 Test Measurement Methods
385	6.2 Bases for Selection 6.3 Precautions 7 TEST REQUIREMENTS 7.1 Direct Measurement of Tube Vibration
387	Figure 1 Tube Bundle Configuration With Tube Groupings Most Susceptible to Fluidelastic Instability Denoted by Cross-Hatching
390	7.2 Microphone Scan for Tube Impacting
391	7.3 External Monitoring for Impacting
392	8 TEST CONDITIONS 8.1 Shell-Side Flow Rate 8.2 Rough Process Conditions 9 DOCUMENTATION
393	10 PRECAUTIONS
394	Part 11, Nonmandatory Appendices Part 11, Nonmandatory Appendix A Causes of Vibration A-1 DISCUSSION
395	A-2 REFERENCES
396	Figure A-1 Root Mean Square (rms) Acceleration Versus Flow Rate From Three Typical Tubes
397	Figure A-2 Tube Response PSDs for Various Shell-Side Flow Rates (Ordinate Not to Scale)
398	Part 11, Nonmandatory Appendix B Methods for Comparative Evaluation of Fluidelastic and Turbulence-Induced Vibration B-1 INTRODUCTION B-2 NOMENCLATURE B-3 FLUIDELASTIC INSTABILITY
399	B-4 SIMPLIFIED METHOD FOR ESTIMATING TURBULENCE-INDUCED VIBRATION IN A SIMILAR DESIGN
400	B-5 REFERENCES Table B-1 Upper Bound Estimate of the Random Turbulence Excitation Coefficient for Tube Bundle
401	Part 11, Nonmandatory Appendix C Test Guidelines for Dynamic Characterization of Tubes C-1 TUBE MECHANICAL VIBRATION CHARACTERISTICS C-2 MODAL FREQUENCIES AND DAMPING DETERMINATION C-3 MODE SHAPE CHARACTERIZATION
402	Part 11, Nonmandatory Appendix D External Vibration Surveys D-1 INTRODUCTION D-2 MEASUREMENT LOCATIONS D-3 ACCEPTANCE GUIDELINES AND RECOMMENDED FOLLOW-UP
403	Part 11, Nonmandatory Appendix E Detection Methods and Data Interpretation E-1 INTRODUCTION E-2 AURAL OBSERVATIONS E-3 ACCELEROMETER SIGNAL CHARACTERISTICS DURING METAL-TO-METAL IMPACTING E-4 DETECTION OF VIBRATION CAUSED BY FLUIDELASTIC EXCITATION WITH TUBE-MOUNTED SENSORS
404	Figure E-1 Acoustic rms Spectrum for Nonimpacting Tube (No. 6-1) and Impacting Tube (No. 6-2)
405	Figure E-2 Correlation of Signals From Microphone and In-Tube Accelerometer
407	Figure E-3 Root Mean Square (rms) Tube Response Versus Flow Velocity Figure E-4 Response Versus Flow Velocity (Laboratory Test of 5 × 5 Tube Array)
408	E-5 TUBE SUPPORT PLATE INTERACTION
409	Figure E-5 Response Versus Flow Rate for Four Tubes in Industrial Size Shell-and-Tube Heat Exchanger (Open Symbol: Increasing Flow; Solid Symbol: Decreasing Flow)
410	Figure E-6 Displacement Time Histories From Accelerometer Pair in Heat Exchanger Tube Vibration Test Figure E-7 Acceleration Time Histories From Accelerometer Pair in Heat Exchanger Tube Vibration Test
411	Figure E-8 Tube Vibration Patterns From X-Y Probe and Test of Industrial Size Shell-and-Tube Heat Exchanger
412	Figure E-9 Frequency Response Curves for Tubes in Industrial Size Shell-and-Tube Heat Exchanger
413	Figure E-10 Schematic of Test Setup
414	Figure E-11 Root Mean Square (rms) Tube Displacements As Function of Flow Velocity (Diametral Gap of 1.02 mm)
415	Figure E-12 Frequency Spectra of Tube Displacement at Location “A” (Diametral Gap of 1.27 mm)
416	Figure E-13 Tube Displacement Time Histories at Location “A” (Diametral Gap of 0.51 mm)
417	E-6 REFERENCES
418	Part 11, Nonmandatory Appendix F Vibration Acceptance Guidelines F-1 INTRODUCTION F-2 GUIDELINES FOR INITIAL ASSESSMENT F-3 FOLLOW-UP ACTIONS F-4 METHODS FOR DETAILED WEAR ASSESSMENTS
419	F-5 GUIDELINES FOR THE EVALUATION OF EXTERNAL VIBRATION LEVELS F-6 REFERENCES
420	Part 11, Nonmandatory Appendix G Installation of Strain Gages
421	Part 14 Condition Monitoring of Rotating Equipment in Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Approach 2 DEFINITIONS 3 REFERENCES
422	4 SCOPE OF COVERAGE 5 CONDITION-MONITORING TECHNOLOGIES 5.1 Common Technologies and Faults 5.2 Condition-Monitoring Technologies
423	Table 1 Common Predictive Technology Applications
424	Table 2 Typical Pump Mechanical Faults Table 3 Mechanical Seal Faults Table 4 Electrical Motor Faults
427	Part 14, Nonmandatory Appendices Part 14, Nonmandatory Appendix A Vibration Monitoring A-1 SCOPE A-2 PURPOSE A-3 DEFINITIONS
429	A-4 VIBRATION MONITORING
430	A-5 TRANSDUCER SELECTION AND INSTALLATION Table A-1 Comparison of Periodic and Continuous Monitoring and Relative Advantages
432	Table A-2 Noncontacting Displacement Probes — Probes Advantages Versus Disadvantages Table A-3 Velocity Transducers — Transducer Advantages Versus Disadvantages
433	Table A-4 Accelerometers — Transducer Advantages and Disadvantages Table A-5 Combination Probe Attached to Bearing Housing — Transducer Advantages and Disadvantages
434	Table A-6 Shaft Rider — Advantages and Disadvantages
435	Table A-7 Transducer Location Guidelines — Turbines
436	Table A-8 Transducer Location Guidelines — Equipment With Antifriction Bearings
437	Table A-9 Transducer Location Guidelines — Horizontal Pumps — Fluid Film Bearings
438	Table A-10 Transducer Location Guidelines — Motor-Driven Vertical Pumps — Fluid Film Bearings
439	Table A-11 Transducer Location Guidelines — Electric Motors
440	A-6 VIBRATION DATA ANALYSIS SYSTEM REQUIREMENTS
442	A-7 VIBRATION LIMITS A-8 MONITORING INTERVALS Figure A-1 An Example of a Vibration Trend Curve
443	A-9 ANALYSIS AND DIAGNOSTICS A-10 REFERENCES
445	Part 14, Nonmandatory Appendix B Lubricating Oil Analysis and Trending B-1 SCOPE B-2 PURPOSE B-3 DEFINITIONS
450	B-4 LUBRICATING OIL SAMPLING AND TESTING PROGRAM B-5 LUBRICATING OIL ANALYSIS
451	B-6 SETTING ALERT AND DANGER LIMITS B-7 REFERENCES
452	Part 14, Nonmandatory Appendix C Thermography C-1 SCOPE C-2 PURPOSE C-3 DEFINITIONS
455	C-4 EQUIPMENT FAULTS
456	C-5 UNITS OF MEASUREMENT C-6 BASELINE MEASUREMENTS C-7 ALARMS C-8 REFERENCES
458	Part 14, Nonmandatory Appendix D Motor Current Signature Analysis D-1 SCOPE D-2 PURPOSE D-3 DEFINITIONS D-4 EQUIPMENT FAULTS D-5 UNITS OF MEASUREMENT D-6 BASELINE MEASUREMENTS
459	D-7 ALARMS D-8 REFERENCES
460	Part 14, Nonmandatory Appendix E Motor Electrical Parameter Monitoring E-1 MOTOR ELECTRICAL MONITORING E-2 MOTOR ELECTRICAL PARAMETERS E-3 REFERENCE
461	Part 14, Nonmandatory Appendix F Process and Equipment Parameter Monitoring and General Observations F-1 COLLECTION OF EQUIPMENT CONDITION DATA F-2 GENERAL OBSERVATIONS
462	Part 17 Performance Testing of Instrument Air Systems in Light-Water Reactor Power Plants
463	Part 19 Preservice and Periodic Performance Testing of Pneumatically and Hydraulically Operated Valve Assemblies in Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Exclusions 2 DEFINITIONS
464	3 TEST GUIDANCE 3.1 Preservice Test Guidance 3.2 Performance Test Guidance 3.3 Equipment Replacement, Modification, Repair, and Maintenance Test Guidance 4 TEST METHODS 4.1 Prerequisites
465	4.2 Instrument Calibration 4.3 Test Conditions 4.4 Limits and Precautions 4.5 Test Procedures 4.6 Test Parameters 4.7 Test Information
466	5 ANALYSIS AND EVALUATION OF DATA 5.1 Acceptance Criteria 5.2 Analysis of Data 5.3 Evaluation of Data 5.4 Documentation of Analysis and Evaluation of Data 6 CORRECTIVE ACTION
467	Part 23 Inservice Monitoring of Reactor Internals Vibration in Pressurized Water Reactor Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Background 2 DEFINITIONS
468	Figure 1 Schematic of a Pressurized Water Reactor (PWR) Showing Typical Sensor Arrangement
469	3 REFERENCES
470	4 INTERNALS VIBRATION EXCITATION SOURCES, RESPONSES, AND MODES 4.1 Sources of Excitation and Responses 4.2 Vibration Modes 5 SIGNAL DATABASE 5.1 Signals to Be Monitored and Reactor Conditions
471	5.2 Data Acquisition Figure 2 Beam and Shell Mode Vibration of a PWR Core Support Barrel
472	5.3 Signal Sampling 5.4 Signal Recording 5.5 Data Reduction Table 1 Sensor Types and Potential Applications in Reactor Noise Analysis
473	Figure 3 Typical Components in a Signal Data Acquisition System Table 2 Relationships Between Sampling Rates and Analysis Results
474	5.6 Data Storage 5.7 Documentation
475	6 DATA REVIEW 6.1 Initial Data Set 6.2 Subsequent Data Sets
477	Part 23, Nonmandatory Appendices Part 23, Nonmandatory Appendix A Discussion of Spectral Functions A-1 NORMALIZED POWER SPECTRAL DENSITY (NPSD) A-2 NORMALIZED ROOT MEAN SQUARE OF THE SIGNAL A-3 NORMALIZED CROSS-POWER SPECTRAL DENSITY (NCPSD), COHERENCE (COH), AND PHASE (N)
478	Figure A-1 Different Spectral Functions
479	A-4 IN-PHASE AND OUT-OF-PHASE SIGNAL SEPARATION (MAYO, 1977)
480	A-5 REFERENCES
481	Part 23, Nonmandatory Appendix B Supporting Information on Component Vibrations B-1 IN-CORE DETECTOR THIMBLES B-2 BAFFLE JETTING
482	B-3 FUEL ASSEMBLY VIBRATIONS B-4 REFERENCE
483	Part 23, Nonmandatory Appendix C Pump-Induced Vibrations C-1 INTRODUCTION C-2 CASE STUDY 1: COOLANT PUMP OPERATION CHARACTERISTICS C-3 CASE STUDY 2: SPACE-TIME BEATING OF COOLANT PUMPS IN A MULTI-LOOP PWR PLANT
484	C-4 REFERENCES Figure C-1 Reactor Coolant System Arrangement — Plan View
485	Figure C-2 Data Set I, 180 deg Phase NCPSD, A-D
486	Figure C-3 Data Set II, 180 deg NCPSD, A-D and B-C
487	Figure C-4 180 deg Phase NCPSD, X-Y
488	Figure C-5 Lissajous Figure of Ex-Core Neutron Noise Data Showing Motion of Reactor Core in a Multi-Loop Plant
489	Part 23, Nonmandatory Appendix D Sampling Rate and Length of Data Record Requirement to Resolve a Spectral Peak

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Standard Title	ASME OM – 2022 – Operation and Maintenance of Nuclear Power Plants
Published Code	ASME
Publication Date	2022
Pages Count	493

ASME OM 2022

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