Chapter
2.4 Evolution of Nuclear Power Generation
2.5 Nuclear Power in the United States
2.6 Plans for New Reactors Worldwide
2.8 Nuclear Plant Construction
2.9 Nuclear Plant Licensing
2.10 Current Commercial Nuclear Plants
Pressurized Water Reactors
2.11 Evolutionary Commercial Nuclear Plants
Underwater Nuclear Power Generating Plants
2.13 Nuclear Accidents: Three Mile Island, Chernobil, and Fukushima Events
Fukushima Accident – 2011
3 Special Regulations and Requirements
3.3 NRC Regulatory Guides
4 Unique Requirements: Class 1E Power System
4.1 Class 1E Electrical Systems: General Description
4.2 Specific Requirements for Class 1E ac Power Systems
4.3 Specific Requirements for Class 1E DC Power Systems
4.4 Specific Requirements for Class 1E Instrumentation and Control Systems
4.5 Specific Requirements for Class 1E Containment Electrical Penetrations
4.6 Specific Requirements for Emergency On-Site ac Power Sources
5 Nuclear Plants Containment Electrical Penetration Assemblies
5.1 Containment Electrical Penetration Assemblies: General (Information on this chapter is based on the requirements of IEEE 317)
5.2 Service Classification
Medium Voltage Power Penetrations
Low Voltage Power Penetrations
Control Voltage Penetrations
Instrumentation Penetrations
Optical Fibers Penetrations
5.3 Electrical Design Requirements (extracted from IEEE 317)
Rated Short Time Overload Current/Duration
Rated Short Circuit Current
Rated Short Circuit Thermal Capacity
Rated Continuous Current During the Most Severe DBE Environmental Conditions
Rated Short Time Overload Current and Duration during the Most Severe DBE Environmental Conditions
Rated Short Circuit Current during the Most Severe DBE Environmental Conditions
Rated Short Circuit Thermal Capacity (I2 t) during the Most Severe DBE Environmental Conditions
5.4 Mechanical Design Requirements (Extracted from IEEE 317)
Design Pressure and Temperature
Minimum Design Temperature
Gas Leak Rate Testing and Monitoring Provisions
5.5 Fire Resistance Requirements (Extracted from IEEE 317)
5.8 Design Tests (Extracted from IEEE 317)
Dielectric Strength Tests
Insulation Resistance Test
Partial Discharge (Corona) Test
Rated Continuous Current Test
Rated Short Time Overload Current Test
Rated Short Circuit Thermal Capacity (I2t) Test
Installation Welding Test
Electro-Magnetic Compatibility Test
Determining Qualified Life
5.10 Monitoring and Testability
6 On-Site Emergency Alternating Current Source
6.1 General Requirements of the Emergency Alternating Current Source
6.2 General Requirements of Diesel Generators Used as Emergency Alternating Current Source (Information in this chapter is based on the requirements of IEEE 387)
EDG General Requirements: Load-Carrying Capability
EDG General Requirements: Speed Control
EDG General Requirements: Protection Considerations
6.3 Specific Design Requirements for Emergency Diesel Generators
EDG-Specific Design Requirements: Starting and Loading
EDG-Specific Design Requirements: Surveillance Systems
6.4 Factory Qualification
Factory Qualification: Testing and Analyses
Factory Qualification: Engine Tests
Factory Qualification: Generator Tests
Factory Qualification: Initial Type Tests of the EDG Set
Factory Qualification: Start and Load Acceptance Tests
Factory Qualification: Aging Test
Factory Qualification: Seismic Requirements
6.5 Site Acceptance Testing
6.6 Site Preoperational Testing
6.7 Site Operational Testing
Site Periodic Testing Applicable Terms
Test Parameters to be Recorded
6.8 Site Periodic Testing and Surveillance: Preventive Maintenance Program
Recommended Program for EDG Monitoring and Trending Parameters
Diesel Generator Unit Reliability Program Elements
7 On-Site Emergency Direct Current Source
7.1 Energy Storage Systems for Nuclear Generating Stations
7.2 General Requirements of Direct Current Systems
Operating Mode of Direct Current Storage Systems
Capability, Availability, Independence, and Testing of Battery Systems
Installation of Battery Systems
Classification of Loads in Terms of Service Duration Requirements
7.5 Classification of Loads in Terms of Power versus Voltage Characteristics
Converting Loads to Constant Current Loads
Battery Duty Cycle Diagram
Function, Capability, Availability, Independence, and Testing of Battery Chargers
8.2 General Criteria for the Protection System
8.3 Specific Criteria for Protection of Alternating Current Systems
Switchgear and Bus Protection
Bus Voltage Monitoring Schemes
Protection of Motors and Feeder Circuits
Emergency Diesel Generator Protection
Load Shedding and Sequential Loading
Protection against Unbalanced Voltages
Negative-Sequence Protection
Negative-sequence Current Relay (Device 46)
Device 47: Phase-Sequence or Phase-Balance Voltage Relay
8.4 Degraded Voltage Protection
Degraded Voltage Relay Voltage Settings
Loss of Voltage Relay Settings
Off-Site System Voltage Considerations
8.6 Protection for Instrumentation and Control Power System
8.7 Protection Aspects for Auxiliary System Automatic Bus Transfer
Bus Transfer Protection Issues
8.8 Protection for Primary Containment Electrical Penetration Assemblies
8.9 Protection of Valve Actuator Motors (Direct Gear Driven)
Special Considerations for Valve Actuator Motor
Typical Motor Operated Valve Circuit Breaker Protection Options
Information Needed for the Selection and Coordination of Overload Relay Protection
Correction for Ambient Temperature
Correction for Voltage Variation
Typical Procedures for Selection of TORs
8.10 Protection for DC Systems
8.11 Testing and Surveillance of Protective Systems
Protection of Motor-Operated Valves
9 Interface of the Nuclear Plant with the Grid
9.1 Preferred Power Supply Safety Function
9.2 Interface between the Nuclear Plant and the Grid
9.3 Transmission Line and Switchyard Protective Relaying
9.4 Connections of the PPS to the Class 1E Systems
9.6 Switchyard and Transmission Line Surveillance and Testing
9.7 Effect of PPS Voltage Degradation on the Class 1E Bus
9.8 Multiunit Considerations
9.9 Considerations for PPS Reliability in a Deregulated Environment
Transmission System Studies
9.11 Study of Recent Events
Actual Case of Transmission Grid Event Affecting a Nuclear Plant
10 Station Blackout: Issues and Regulations
10.2 Regulations Relating to SBO Requirements
Compliance with 10 CFR 50.63
10.3 Specific SBO Requirements
10.4 Alternate Alternating Current Power Sources
10.5 Procedures and Training
10.6 QA and Specifications for Nonsafety-Related Equipment
10.7 Monitoring of the Grid Condition
11 Review of Electric Power Calculations
11.2 Load and Voltage Calculations
11.3 Motor Starting Calculations
Calculation of Motor Starting Time
Short Circuit Calculations
12 Plant Life: Equipment Aging, Life Extension, and Decommissioning
12.1 Nuclear Plant Licensed Life
12.2 Importance of Maintenance: The Maintenance Rule (Courtesy of the NRC)
Definition of Maintenance
Plant, System, Train, and Component Monitoring Levels
Use of Reliability-Based Programs
Safety Significance Categories
Safety-Significance Ranking Methodology
Use of Probabilistic Risk Assessments
Maintenance Risk Assessments
12.3 Monitoring Issues Affecting Electrical Equipment, Transformers, Motors, Cable, Control Equipment
12.4 Cable-Monitoring Methods and Techniques (Courtesy of NRC)
12.5 Further Information on Cable Testing
12.6 Switchyard Maintenance Activities
12.7 Emergency Diesel Generators
12.8 Interpretation of “Standby”
12.9 Normally Operating SSCs of Low Safety Significance
12.10 Establishing SSC-Specific Performance Criteria
12.11 Clarification of MPFFs Related to Design Deficiencies
12.12 Scope of the Hazards to be Considered during Power Operations
12.13 Scope of Initiators to be Considered for Shutdown Conditions
12.14 Fire Scenario Success Path(s)
12.15 Establishing Action Thresholds Based on Quantitative Considerations
12.16 SSCs Considered under 10 CFR 50.65(a)(1)
12.17 Inclusion of Electrical Distribution Equipment
12.18 The License Renewal Rule
12.19 Interpretation of Aging
12.20 Effects of Plant Aging
13 Electrical and Control Systems Inspections
13.1 Purpose of Inspections
13.2 Objectives of Inspections
13.4 Typical Approach to the Review
Electrical Systems for Nuclear Power Plants
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