ASME OM 2020

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ASME OM-2020: Operation and Maintenance of Nuclear Power Plants

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ASME	2020	457

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Description

Establishes the requirements for preservice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor power plants. 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.

PDF Catalog

PDF Pages	PDF Title
4	CONTENTS
15	FOREWORD
16	COMMITTEE ROSTER
19	CORRESPONDENCE WITH THE OM COMMITTEE
21	PREFACE
23	ASME OM-2020 SUMMARY OF CHANGES
26	APPLICABILITY INDEX FOR ASME OM CASES
28	CROSS-REFERENCING AND STYLISTIC CHANGES IN ASME OM
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 ISTA-3300 Corrective Actions ISTA-4000 INSTRUMENTATION AND TEST EQUIPMENT ISTA-4100 Range and Accuracy ISTA-4200 Calibration Tables Table ISTA-3170-1 Test Frequency and Time Between Tests
34	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
35	Subsection ISTB Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants — Pre-2000 Plants 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
36	ISTB-3200 Inservice Testing ISTB-3300 Reference Values Table ISTB-3000-1 Inservice Test Parameters
37	ISTB-3400 Frequency of Inservice Tests Table ISTB-3400-1 Inservice Test Frequency
38	ISTB-3500 Data Collection ISTB-4000 TO BE PROVIDED AT A LATER DATE ISTB-5000 SPECIFIC TESTING REQUIREMENTS Table ISTB-3510-1 Required Instrument Accuracy
39	ISTB-5100 Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)
40	ISTB-5200 Vertical Line Shaft Centrifugal Pumps Table ISTB-5121-1 Centrifugal Pump Test Acceptance Criteria
42	ISTB-5300 Positive Displacement Pumps Table ISTB-5221-1 Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria
43	Figures Figure ISTB-5223-1 Vibration Limits
44	Table ISTB-5321-1 Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria Table ISTB-5321-2 Reciprocating Positive Displacement Pump Test Acceptance Criteria
45	ISTB-6000 MONITORING, ANALYSIS, AND EVALUATION ISTB-6100 Trending ISTB-6200 Corrective Action 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
46	ISTB-9300 Record of Tests ISTB-9400 Record of Corrective Action
47	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
48	ISTC-3000 GENERAL TESTING REQUIREMENTS ISTC-3100 Preservice Testing ISTC-3200 Inservice Testing ISTC-3300 Reference Values ISTC-3400 To Be Provided at a Later Date
49	ISTC-3500 Valve Testing Requirements Table ISTC-3500-1 Inservice Test Requirements
50	ISTC-3600 Leak Testing Requirements
51	ISTC-3700 Position Verification Testing ISTC-4000 INSTRUMENTATION AND TEST EQUIPMENT
52	ISTC-5000 SPECIFIC TESTING REQUIREMENTS ISTC-5100 Power-Operated Valves (POVs)
53	ISTC-5200 Other Valves
56	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
57	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
58	ISTD-1800 Evaluation of Affected Systems, Structures, and Components ISTD-2000 DEFINITIONS
59	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
60	ISTD-4200 Inservice Examination
61	ISTD-5000 SPECIFIC TESTING REQUIREMENTS ISTD-5100 Preservice Operational Readiness Testing ISTD-5200 Inservice Operational Readiness Testing
62	Table ISTD-4252-1 Visual Examination Table
63	ISTD-5300 The 10% Testing Sample
64	ISTD-5400 The 37 Testing Sample Plan
65	ISTD-5500 Retests of Previously Unacceptable Snubbers Figure ISTD-5431-1 The 37 Testing Sample Plan
66	ISTD-6000 SERVICE LIFE MONITORING REQUIREMENTS ISTD-6100 Initial Service Life 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-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 ISTD-9300 Record of Tests
67	ISTD-9400 Record of Corrective Action ISTD-9500 Service Life Records
68	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
69	ISTE-3000 GENERAL REQUIREMENTS ISTE-3100 Implementation ISTE-3200 Probabilistic Risk Assessment ISTE-3300 Integrated Decision Making
70	ISTE-3400 Evaluation of Aggregate Risk ISTE-3500 Feedback and Corrective Actions ISTE-4000 SPECIFIC COMPONENT CATEGORIZATION REQUIREMENTS ISTE-4100 Component Risk Categorization
71	ISTE-4200 Component Safety Categorization
72	ISTE-4300 Testing Strategy Formulation ISTE-4400 Evaluation of Aggregate Risk
73	ISTE-4500 Inservice Testing Program ISTE-5000 SPECIFIC TESTING REQUIREMENTS ISTE-5100 Pumps
74	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
75	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
76	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
77	ISTF-3200 Inservice Testing ISTF-3300 Reference Values Table ISTF-3000-1 Inservice Test Parameters
78	ISTF-3400 Frequency of Inservice Tests ISTF-3500 Data Collection Table ISTF-3510-1 Required Instrument Accuracy
79	ISTF-4000 TO BE PROVIDED AT A LATER DATE ISTF-5000 SPECIFIC TESTING REQUIREMENTS ISTF-5100 Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)
80	ISTF-5200 Vertical Line Shaft Centrifugal Pumps ISTF-5300 Positive Displacement Pumps Table ISTF-5120-1 Centrifugal Pump Test Acceptance Criteria
81	ISTF-6000 MONITORING, ANALYSIS, AND EVALUATION ISTF-6100 Trending ISTF-6200 Corrective Action ISTF-6300 Systematic Error
82	ISTF-6400 Analysis of Related Conditions 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 Table ISTF-5320-1 Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria Table ISTF-5320-2 Reciprocating Positive Displacement Pump Test Acceptance Criteria
83	ISTF-9200 Test Plans ISTF-9300 Record of Tests ISTF-9400 Record of Corrective Action
84	Mandatory Appendices Division 1, Mandatory Appendix I Inservice Testing of Pressure Relief Devices in Water-Cooled Reactor Nuclear Power Plants I-1000 GENERAL REQUIREMENTS
86	I-2000 INTRODUCTION I-3000 PRESSURE RELIEF DEVICE TESTING
90	I-4000 TEST METHODS
93	I-5000 RECORDS AND RECORD KEEPING Table I-4220-1 Seat Tightness Testing Methods for Pressure Relief Devices
94	Division 1, Mandatory Appendix II Check Valve Condition Monitoring Program II-1000 PURPOSE II-2000 GROUPINGS II-3000 ANALYSIS II-4000 CONDITION-MONITORING ACTIVITIES
95	II-5000 CORRECTIVE MAINTENANCE II-6000 DOCUMENTATION Table II-4000-1 Maximum Intervals for Use When Applying Internal Extensions
96	Division 1, Mandatory Appendix III Preservice and Inservice Testing of Active ElectricMotor-Operated Valve Assemblies in Water-Cooled Reactor Nuclear Power Plants III-1000 INTRODUCTION III-2000 SUPPLEMENTAL DEFINITIONS III-3000 GENERAL TESTING REQUIREMENTS
98	III-4000 TO BE PROVIDED AT A LATER DATE III-5000 TEST METHODS III-6000 ANALYSIS AND EVALUATION OF DATA
100	III-7000 TO BE PROVIDED AT A LATER DATE III-8000 TO BE PROVIDED AT A LATER DATE III-9000 RECORDS AND REPORTS
101	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
102	IV-3000 GENERAL TESTING REQUIREMENTS
104	IV-4000 RESERVED IV-5000 PERFORMANCE ASSESSMENT TEST METHODS
105	IV-6000 PERFORMANCE ASSESSMENT TEST ANALYSIS AND EVALUATION
106	IV-7000 STROKE TEST AND FAIL SAFE DATA ANALYSIS AND EVALUATION IV-8000 RESERVED IV-9000 RECORDS AND REPORTS
107	Division 1, Mandatory Appendix V Pump Periodic Verification Test Program
108	Nonmandatory Appendices Division 1, Nonmandatory Appendix A Preparation of Test Plans A-1000 PURPOSE A-2000 TEST PLAN CONTENTS
109	A-3000 SUBSTITUTE TESTS AND EXAMINATIONS A-3100 General A-3200 Justification of Substitute Tests and Examinations
110	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
111	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
112	Division 1, Nonmandatory Appendix C Dynamic Restraint Design and Operating Information C-1000 PURPOSE C-2000 DESIGN AND OPERATING ITEMS
113	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
114	Division 1, Nonmandatory Appendix E Flowcharts for 10% and 37 Snubber Testing Plans E-1000 PURPOSE
115	Figure E-1000-1 Flowchart for 10% Snubber Testing Plan (ISTD-5300)
116	Figure E-1000-2 Flowchart for 37 Snubber Testing Plan (ISTD-5400)
117	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
118	F-4000 SHORTENED SERVICE LIFE F-5000 SERVICE LIFE EXTENSION F-6000 SEPARATE SERVICE LIFE POPULATIONS
119	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
120	G-4000 CASE 2: EXAMINE ACCESSIBLE AND INACCESSIBLE SNUBBERS SEPARATELY
121	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
123	Division 1, Nonmandatory Appendix J Check Valve Testing Following Valve Reassembly J-1000 PURPOSE J-2000 POSTDISASSEMBLY TEST RECOMMENDATIONS J-3000 TEST MATRIX
124	Table J-2000-1 Check Valve Test Matrix
125	Division 1, Nonmandatory Appendix K Sample List of Component Deterministic Considerations K-1000 PURPOSE K-2000 SAMPLE DETERMINISTIC CONSIDERATIONS
126	Division 1, Nonmandatory Appendix L Acceptance Guidelines L-1000 PURPOSE L-2000 ACCEPTANCE GUIDELINES
127	Figure L-2100-1 Acceptance Guidelines for CDF (Adapted From RG 1.174)
128	Figure L-2100-2 Acceptance Guidelines for LERF (Adapted From RG 1.174)
129	Division 1, Nonmandatory Appendix M Design Guidance for Nuclear Power Plant Systems and Component Testing M-1000 PURPOSE M-2000 BACKGROUND M-3000 GUIDANCE
134	M-4000 REFERENCES
135	DIVISION 2 OM STANDARDS Part 2 Performance Testing of Closed Cooling Water Systems in Light-Water Reactor Power Plants
136	Part 3 Vibration Testing of Piping Systems 1 SCOPE 2 DEFINITIONS
137	3 GENERAL REQUIREMENTS Figure 1 Typical Components of a Vibration Monitoring System (VMS)
138	3.1 Classification Table 1 System Tolerances
139	3.2 Monitoring Requirements and Acceptance Criteria
141	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
143	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
144	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
145	Figure 10 Correction Factor C1
146	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 Modal Response Technique
147	6.2 Measured Stress Technique 7 INSTRUMENTATION AND VIBRATION MEASUREMENT REQUIREMENTS 7.1 General Requirements
148	8 CORRECTIVE ACTION Table 2 Examples of Specifications of VMS Minimum Requirements; Measured Variable — Displacement
149	Part 3, Nonmandatory Appendix A Instrumentation and Measurement Guidelines A-1 VISUAL METHODS (VMG 3) A-2 ELECTRONIC MEASUREMENT METHODS (VMG 2 AND VMG 1)
152	Part 3, Nonmandatory Appendix B Analysis Methods B-1 FOURIER TRANSFORM METHOD1 The user of this method is referred to the latest revision of ANSI S2.10, Methods for Analysis and Presentation of Shock and Vibration Data. B-2 OTHER METHODS
153	Part 3, Nonmandatory Appendix C Test/Analysis Correlation Methods C-1 TEST/ANALYSIS CORRELATION C-2 EVALUATION OF THE MEASURED RESPONSES
154	Part 3, Nonmandatory Appendix D Velocity Criterion D-1 VELOCITY CRITERION D-2 SCREENING VELOCITY CRITERION D-3 USE OF SCREENING VIBRATION VELOCITY VALUE
155	Part 3, Nonmandatory Appendix E Excitation Mechanisms, Responses, and Corrective Actions E-1 EXCITATION MECHANISMS AND PIPING RESPONSES
157	E-2 ADDITIONAL TESTING AND ANALYSIS
158	Part 3, Nonmandatory Appendix F Flowchart — Outline of Vibration Qualification of Piping Systems
159	Figure F-1 Flowchart — Outline of Vibration Qualification of Piping Systems
160	Part 3, Nonmandatory Appendix G Qualitative Evaluations
161	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
162	Figure H-1 Monitoring and Qualification of Piping Steady-State Vibration
164	H-4 ALLOWABLE DISPLACEMENT LIMIT Table H-1 Recommended Actions for Piping Vibration Problem Resolution
166	Part 3, Nonmandatory Appendix I Acceleration Limits for Small Branch Piping
167	Figure I-1 Determination of LE and WT
168	Part 5 Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactor Power Plants 1 PURPOSE AND SCOPE 1.1 Purpose 1.2 Scope 1.3 Application 1.4 Definitions 2 BACKGROUND
169	Figure 1 Reactor Arrangement Showing Typical Ex-Core Detector Locations
170	3 PROGRAM DESCRIPTION 4 BASELINE PHASE 4.1 Objective 4.2 Data Acquisition Periods 4.3 Data Acquisition and Reduction
171	Table 1 Summary of Program Phases
172	4.4 Data Evaluation 5 SURVEILLANCE PHASE 5.1 Objective 5.2 Frequency of Data Acquisition 5.3 Data Acquisition and Reduction 5.4 Data Evaluation 6 DIAGNOSTIC PHASE 6.1 Objective 6.2 Data Acquisition Periods
173	6.3 Data Acquisition, Reduction, and Evaluation
174	Part 5, Nonmandatory Appendix A Theoretical Basis
175	Figure A-1 Idealized Analysis for Core Barrel Motion
176	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)
177	Figure B-1 Representative Spectra
178	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
179	C-6 SIGNAL BUFFERING C-7 DATA ASSURANCE C-8 DATA RETENTION C-9 STATISTICAL UNCERTAINTIES IN NEUTRON NOISE DATA ANALYSIS Table C-1 Parameters to Be Documented During Data Acquisition
181	Part 5, Nonmandatory Appendix D Data Evaluation D-1 BASELINE
182	D-2 SURVEILLANCE PHASE D-3 DIAGNOSTIC PHASE Figure D-1 Narrowband rms
183	Figure D-2 Example of Wideband rms Amplitude Versus Boron Concentration
185	Part 5, Nonmandatory Appendix E Guidelines for Evaluating Baseline Signal Deviations
186	Figure E-1 Typical Ex-Core Neutron Noise Signatures From Six PWRs
187	Figure E-2 Typical Baseline NPSD Range
188	Figure E-3 Examples of Changes in the Neutron Noise Signature Over a Fuel Cycle
189	Figure E-4 Example of Loss of Axial Restraint
190	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
191	Part 5, Nonmandatory Appendix G Bibliography
192	Part 7 Thermal Expansion Testing of NuclearPower Plant Piping Systems 1 SCOPE 2 DEFINITIONS
193	3 GENERAL REQUIREMENTS 3.1 Specific Requirements
194	3.2 Acceptance Criteria 4 RECONCILIATION METHODS
195	4.1 Reconciliation Method 1 4.2 Reconciliation Method 2 4.3 Reconciliation Method 3 5 CORRECTIVE ACTION
196	Figure 1 System Heatup, Reconciliation, and Corrective Action
197	6 INSTRUMENTATION REQUIREMENTS FOR THERMAL EXPANSION MEASUREMENT 6.1 General Requirements Figure 2 Typical Components of a TEMS Table 1 An Example of Specification of TEMS Minimum Requirements
198	6.2 Precautions
199	Part 7, Nonmandatory Appendix A TEMS Instrumentation and Equipment Guidelines
200	Table A-1 Typical Transducers
201	Table A-2 Typical Signal Conditioners Table A-3 Typical Data Processing, Display, and Recording Equipment
202	Part 7, Nonmandatory Appendix B Thermal Stratification and Thermal Transients B-1 INTRODUCTION B-2 THERMAL STRATIFICATION
203	B-3 THERMAL TRANSIENTS Figure B-1 Simplified Schematic of Surge Line Stratification
205	Part 12 Loose Part Monitoring in Water-CooledReactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Overview 2 DEFINITIONS
207	3 REFERENCES 4 EQUIPMENT 4.1 General 4.2 Field Equipment
208	Figure 1 Typical Broadband Sensor Response to Nearby Impact Figure 2 Typical Broadband Sensor Response to More Distant Impact
209	Figure 3 Range of Loose Part Signal Amplitude and Predominant Frequency Content Figure 4 Field Equipment
210	Figure 5 Direct Stud Mount Figure 6 Clamped Mount
211	Table 1 Recommended PWR Accelerometer Locations
212	Figure 7 Recommended Sensor Array for PWR With U-Tube Steam Generator
213	Figure 8 Recommended Sensor Array for PWR With Once-Through Steam Generator Table 2 Recommended BWR Accelerometer Locations
214	Figure 9 Recommended Sensor Array for BWR
215	4.3 Control Cabinet Equipment
216	4.4 Analysis and Diagnostic Equipment 5 PROGRAM ELEMENTS 5.1 General 5.2 ALARA 5.3 Precautions 5.4 Calibration
217	5.5 Baseline Impact Testing Figure 10 Block Diagram for Charge Converter Calibration Tests
218	Figure 11 Cable Properties (Typical for Twisted-Shielded Pair Cable)
219	5.6 Initial LPM Setpoints 5.7 Heat-Up and Cool-Down Monitoring 5.8 Periodic Monitoring and Testing
220	5.9 Alarm Response and Diagnostics 6 DOCUMENTATION
222	Part 12, Nonmandatory Appendix A References
223	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
224	Figure 1 Boundary and Support Systems of Emergency Diesel Generator Systems
225	1.5 Definitions
226	2 NONOPERATING CHECKS 2.1 Post-Maintenance Checks 2.2 Pre-Start Checks 3 TESTING 3.1 Post-Maintenance/Baseline Testing
227	3.2 Periodic Tests
228	Table 1 Periodic Tests
230	3.3 Other Testing Guidelines 4 INSERVICE MONITORING OF COMPONENT OPERATING AND STANDBY CONDITIONS
231	4.1 Engine 4.2 Lubrication Subsystem 4.3 Jacket Water and Intercooler Subsystem 4.4 Starting Subsystem 4.5 Combustion Air Intake Subsystem
232	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
233	5.2 Vibration Analysis
234	5.3 Lube Oil Analysis 5.4 Cooling Water Analysis 5.5 Thermography
235	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)
236	Part 16, Nonmandatory Appendix A Post-Major Maintenance Test Data Figure A-1 Post-Major Maintenance Test Data Form
237	Part 16, Nonmandatory Appendix B Functional/Inservice Test Data Figure B-1 Functional/Inservice Test Data Form
238	Part 16, Nonmandatory Appendix C Data Trending Examples
239	Figure C-1 Typical Lube Oil System
240	Figure C-2 Typical Jacket Water System
241	Figure C-3 Intercooler Water System
242	Figure C-4 Typical Air/Exhaust System
243	Figure C-5 Typical Fuel Oil System
244	Part 21 Inservice Performance Testing of Heat Exchangersin Water-Cooled Reactor Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Exclusions 1.3 Owner’s Responsibility 2 DEFINITIONS
246	3 REFERENCES 3.1 Standard References 3.2 Appendix References
247	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
248	5.4 Interval Requirements 6 SELECTION OF METHODS 6.1 Functional Test Method
249	Figure 1 Intervals, Limits, and Parameter Trending (Typical)
250	Figure 2 Method Selection Chart
251	6.2 Heat-Transfer Coefficient Test Method (Without Phase Change) 6.3 Heat-Transfer Coefficient Test Method (With Condensation)
252	6.4 Transient Test Method 6.5 Temperature Effectiveness Test Method
253	6.6 Batch Test Method
254	6.7 Temperature-Difference Monitoring Method 6.8 Pressure-Loss Monitoring Method
255	6.9 Visual Inspection Monitoring Method 6.10 Parameter Trending 7 TESTING AND MONITORING CONDITIONS 7.1 Steady State
256	7.2 Flow Regimes
257	7.3 Temperatures 8 ERRORS, SENSITIVITIES, AND UNCERTAINTIES 8.1 Measurement Errors 8.2 Result Sensitivities 8.3 Total Uncertainty
258	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
259	9.3 Required Action Limits 10 CORRECTIVE ACTION 11 RECORDS AND RECORD KEEPING 11.1 Equipment Records 11.2 Plans and Procedures
260	11.3 Record of Results 11.4 Record of Corrective Action
261	Part 21, Nonmandatory Appendix A Diagnostics A-1 HEAT DUTY DEFICIENCY
262	A-2 EXCESSIVE PRESSURE LOSS A-3 MECHANICAL DYSFUNCTION
264	Part 21, Nonmandatory Appendix B Precautions B-1 EXCESSIVE FLOW B-2 CROSSING FLOW REGIMES B-3 TEMPERATURE STRATIFICATION B-4 OVERCOOLING
265	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
266	B-12 COMPONENT DESIGN FUNCTION B-13 THERMAL DELAYS B-14 MATERIAL PROPERTIES
267	Part 21, Nonmandatory Appendix C Examples C-1 FUNCTIONAL TEST METHOD C-2 HEAT TRANSFER COEFFICIENT TEST METHOD (WITHOUT PHASE CHANGE)
277	C-3 HEAT TRANSFER COEFFICIENT TEST METHOD (WITH CONDENSATION)
278	Figure C-1 One Tube Row Air-to-Water Cross-Flow Heat Exchanger
283	C-4 TRANSIENT TEST METHOD
285	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
287	C-5 TEMPERATURE EFFECTIVENESS TEST METHOD
288	C-6 BATCH TEST METHOD
290	C-7 TEMPERATURE DIFFERENCE MONITORING METHOD
291	Figure C-5 Cooling Water Inlet Temperature Versus Temperature Difference
292	C-8 PRESSURE LOSS MONITORING METHOD
293	C-9 VISUAL INSPECTION MONITORING METHOD
294	C-10 PARAMETER TRENDING
295	C-11 UNCERTAINTY ANALYSIS
299	Part 24 Reactor Coolant and Recirculation Pump Condition Monitoring 1 INTRODUCTION 1.1 Scope 1.2 Approach 2 DEFINITIONS
301	3 REFERENCES 4 MACHINE FAULTS 4.1 Introduction 5 VIBRATION, AXIAL POSITION, AND BEARING TEMPERATURE MONITORING EQUIPMENT 5.1 General
302	Table 1 Pumpset Mechanical Faults Table 2 Seal Faults Table 3 Electrical Motor Faults
303	5.2 Monitoring System 5.3 Radial Proximity Sensor Locations 5.4 Axial Proximity Sensor Locations 5.5 Phase-Reference Sensor Location
304	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
305	6.3 System Accuracy and Calibration 6.4 Data Analysis and Display 6.5 Data Storage 6.6 Continuous Display of Dynamic Signals
306	7 SEAL MONITORING 7.1 Introduction 7.2 Monitoring System 7.3 Monitoring and Analysis Requirements
307	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
308	8.3 Baseline 8.4 Periodic Monitoring 8.5 Preoutage Coastdown
309	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 9.2 Determining 1× and 2× Vector Acceptance Regions 9.3 Determining Alarm Points for Thrust Position
310	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 10.4 Data Analysis Table 5 Typical Thrust Position Alarm Setpoints for a Pump With Normal Upthrust
311	11 ADDITIONAL TECHNOLOGIES 11.1 Thermography 11.2 Lube Oil Analysis 11.3 Motor Current Signature Analysis 11.4 Motor Electrical Monitoring and Testing 11.5 Loose Parts Monitoring 12 OTHER 12.1 Calibrations 12.2 Quality
312	Part 24, Nonmandatory Appendix A References
313	Part 24, Nonmandatory Appendix B Thermography
314	Part 24, Nonmandatory Appendix C Lube Oil Analysis
315	Part 24, Nonmandatory Appendix D Motor Current Signature Analysis
316	Part 24, Nonmandatory Appendix E Loose Parts Monitoring
317	Part 25 Performance Testing of Emergency Core Cooling Systems in Light-Water Reactor Power Plants
318	Part 26 Determination of Reactor Coolant Temperature From Diverse Measurements 1 INTRODUCTION 1.1 Scope 1.2 Applicability 1.3 Basic Methodology 2 DEFINITIONS
319	3 REFERENCES 4 REQUIREMENTS 4.1 Plant Conditions 4.2 Test Equipment 4.3 Uncertainty Methodologies
320	5 DEVELOP TEST PROCEDURES AND PERFORM TESTING 5.1 Establish Primary-to-Secondary Side ΔTps 5.2 Test Procedure Development
321	5.3 Perform Test 6 DOCUMENTATION
322	Part 26, Nonmandatory Appendix A Measurement Equipment Uncertainties
323	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
324	3 REFERENCES 4 GENERAL TESTING REQUIREMENTS 4.1 Establish System Test Boundaries 4.2 Identify System Performance Requirements
325	4.3 Identify Testable Characteristics 4.4 Establish Acceptance Criteria
326	4.5 Develop Test Procedures and Perform Testing, Inspections, and Engineering Analysis
329	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
330	7 DOCUMENTATION 7.1 System Test Plan 7.2 Test Results and Corrective Actions
331	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
335	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
338	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
340	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
341	Figure IV-1 CCWS Typical Flow Diagram
344	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
347	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
348	Figure VI-1 Typical Instrument Air System
352	Part 28, Nonmandatory Appendix A Industry Guidance
353	Table A-1 Operating Experience Information
356	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
357	Figure B-1 Typical Branch Line System Figure B-2 Verifying Pump TDH Versus Flow: Correction of Measured Data for Instrument Accuracy
358	Figure B-3 Verifying Pump TDH Versus Flow: Correction of Analysis Limits for Instrument Accuracy
359	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
360	B-6 VERIFYING BALANCED BRANCH LINE RESISTANCE B-7 SYSTEM ADJUSTMENTS
361	Figure B-6 Measured Subsystem Operating Point and Range of Operating Points Allowed by Analysis Limits
362	Part 28, Nonmandatory Appendix C Measurement Accuracy of System Characteristics C-1 BACKGROUND C-2 NOMENCLATURE
363	C-3 SENSITIVITY COEFFICIENTS C-4 ACCURACY OF DIRECTLY MEASURED VARIABLES C-5 ACCURACY OF DERIVED VARIABLES
364	C-6 ACCURACY OF FLOW RATE C-7 ACCURACY OF PUMP TDH
365	C-8 ACCURACY OF SYSTEM RESISTANCE C-9 EXAMPLE EVALUATION OF PUMP TDH ACCURACY
366	Table C-1 Recorded Test Data Table C-2 Calculated Pump Head Table C-3 Sensitivity Coefficients for Pump TDH
368	Table C-4 Pump TDH Overall Accuracy Calculation
369	Part 29 Alternative Treatment Requirements for RISC-3 Pumps and Valves
370	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
371	5 SELECTION OF EQUIPMENT TO BE TESTED 5.1 Equipment Selection Factors
372	6 SELECTION OF TEST METHOD 6.1 Test Measurement Methods
373	6.2 Bases for Selection 6.3 Precautions 7 TEST REQUIREMENTS 7.1 Direct Measurement of Tube Vibration
375	Figure 1 Tube Bundle Configuration With Tube Groupings Most Susceptible to Fluidelastic Instability Denoted by Cross-Hatching
378	7.2 Microphone Scan for Tube Impacting
379	7.3 External Monitoring for Impacting
380	8 TEST CONDITIONS 8.1 Shell-Side Flow Rate 8.2 Rough Process Conditions 9 DOCUMENTATION
381	10 PRECAUTIONS
382	Part 11, Nonmandatory Appendix A Causes of Vibration A-1 DISCUSSION
383	A-2 REFERENCES
384	Figure A-1 Root Mean Square (rms) Acceleration Versus Flow Rate From Three Typical Tubes
385	Figure A-2 Tube Response PSDs for Various Shell-Side Flow Rates (Ordinate Not to Scale)
386	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
387	B-4 SIMPLIFIED METHOD FOR ESTIMATING TURBULENCE-INDUCED VIBRATION IN A SIMILAR DESIGN
388	B-5 REFERENCES Table B-1 Upper Bound Estimate of the Random Turbulence Excitation Coefficient for Tube Bundle
389	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
390	Part 11, Nonmandatory Appendix D External Vibration Surveys D-1 INTRODUCTION D-2 MEASUREMENT LOCATIONS D-3 ACCEPTANCE GUIDELINES AND RECOMMENDED FOLLOW-UP
391	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
392	Figure E-1 Acoustic rms Spectrum for Nonimpacting Tube (No. 6-1) and Impacting Tube (No. 6-2)
393	Figure E-2 Correlation of Signals From Microphone and In-Tube Accelerometer
395	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)
396	E-5 TUBE SUPPORT PLATE INTERACTION
397	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)
398	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
399	Figure E-8 Tube Vibration Patterns From X-Y Probe and Test of Industrial Size Shell-and-Tube Heat Exchanger
400	Figure E-9 Frequency Response Curves for Tubes in Industrial Size Shell-and-Tube Heat Exchanger
401	Figure E-10 Schematic of Test Setup
402	Figure E-11 Root Mean Square (rms) Tube Displacements As Function of Flow Velocity (Diametral Gap of 1.02 mm)
403	Figure E-12 Frequency Spectra of Tube Displacement at Location “A” (Diametral Gap of 1.27 mm)
404	Figure E-13 Tube Displacement Time Histories at Location “A” (Diametral Gap of 0.51 mm)
405	E-6 REFERENCES
406	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
407	F-5 GUIDELINES FOR THE EVALUATION OF EXTERNAL VIBRATION LEVELS F-6 REFERENCES
408	Part 11, Nonmandatory Appendix G Installation of Strain Gages
409	Part 14 Vibration Monitoring of Rotating Equipmentin Nuclear Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Purpose 2 DEFINITIONS
410	3 REFERENCES 3.1 Referenced Standards 3.2 Referenced Publications
411	4 VIBRATION MONITORING 4.1 Types of Monitoring 4.2 Quality Considerations Table 1 Comparison of Periodic and Continuous Monitoring and Relative Advantages
412	Table 2 Transducer Location Guidelines — Turbines Table 3 Transducer Location Guidelines — Equipment With Antifriction Bearings
413	Table 4 Transducer Location Guidelines — Horizontal Pumps — Fluid Film Bearings Table 5 Transducer Location Guidelines — Motor-Driven Vertical Pumps — Fluid Film Bearings
414	5 ESTABLISHING THE BASELINE 5.1 Baseline Data Table 6 Transducer Location Guidelines — Electric Motors
415	Figure 1 An Example of a Vibration Data Sheet
416	5.2 Methods to Establish Baseline Figure 2 An Example of a Vibration Trend Curve
417	6 ESTABLISHING VIBRATION LIMITS 6.1 Purpose 6.2 Parameters 6.3 Criteria
418	7 DATA ACQUISITION 8 HARDWARE Figure 3 Vibration Level Trend Plot of Condition One (For Defined Vibration Limits From Manufacturer’s Data or Equivalent)
419	9 DIAGNOSTICS 9.1 Purpose 9.2 Troubleshooting Figure 4 Vibration Level Trend Plot of Condition Two (For Defined Vibration Limits From Manufacturer’s Data or Equivalent)
420	Table 7 Vibration Troubleshooting Chart
421	Part 14, Nonmandatory Appendix A Instrumentation Selection and Use A-1 INSTALLATION OF TRANSDUCERS
422	A-2 CALIBRATION A-3 PRETEST CONDITIONS A-4 MEASURING AND RECORDING INFORMATION A-5 SPECIAL CONSIDERATIONS A-6 PERSONNEL
423	Part 14, Nonmandatory Appendix B Transducers and Analysis Equipment B-1 TRANSDUCERS
424	Table B-1 Noncontacting Displacement Probes — Probe Advantages Versus Disadvantages
425	Table B-2 Velocity Transducers — Transducer Advantages Versus Disadvantages Table B-3 Accelerometers — Transducer Advantages Versus Disadvantages
426	Table B-4 Combination Probe Attached to Bearing Housing — Transducer Advantages Versus Disadvantages Table B-5 Shaft Rider — Transducer Advantages Versus Disadvantages
427	B-2 CONTINUOUS VIBRATION MONITORING INSTRUMENTS B-3 PERIODIC ANALYSIS INSTRUMENTATION
428	Part 17 Performance Testing of Instrument Air Systems in Light-Water Reactor Power Plants
429	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
430	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
431	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
432	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
433	Part 23 Inservice Monitoring of Reactor Internals Vibration in Pressurized Water Reactor Power Plants 1 INTRODUCTION 1.1 Scope 1.2 Background 2 DEFINITIONS
434	Figure 1 Schematic of a Pressurized Water Reactor (PWR) Showing Typical Sensor Arrangement
435	3 REFERENCES
436	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
437	5.2 Data Acquisition Figure 2 Beam and Shell Mode Vibration of a PWR Core Support Barrel
438	5.3 Signal Sampling 5.4 Signal Recording 5.5 Data Reduction Table 1 Sensor Types and Potential Applications in Reactor Noise Analysis
439	Figure 3 Typical Components in a Signal Data Acquisition System Table 2 Relationships Between Sampling Rates andAnalysis Results
440	5.6 Data Storage 5.7 Documentation
441	6 DATA REVIEW 6.1 Initial Data Set 6.2 Subsequent Data Sets
443	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)
444	Figure A-1 Different Spectral Functions
445	A-4 IN-PHASE AND OUT-OF-PHASE SIGNAL SEPARATION (MAYO, 1977)
446	A-5 REFERENCES
447	Part 23, Nonmandatory Appendix B Supporting Information on Component Vibrations B-1 IN-CORE DETECTOR THIMBLES B-2 BAFFLE JETTING
448	B-3 FUEL ASSEMBLY VIBRATIONS B-4 REFERENCE
449	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
450	C-4 REFERENCES Figure C-1 Reactor Coolant System Arrangement — Plan View
451	Figure C-2 Data Set I, 180 deg Phase NCPSD, A-D
452	Figure C-3 Data Set II, 180 deg NCPSD, A-D and B-C
453	Figure C-4 180 deg Phase NCPSD, X-Y Figure C-5 Lissajous Figure of Ex-Core Neutron Noise Data Showing Motion of Reactor Core in a Multi-Loop Plant
454	Part 23, Nonmandatory Appendix D Sampling Rate and Length of Data Record Requirement to Resolve a Spectral Peak