design criteria - structures, components ...columbia generating station amendment 58 final safety...

COLUMBIA GENERATING STATION Amendment 53 FINAL SAFETY ANALYSIS REPORT November 1998 Chapter 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS TABLE OF CONTENTS Section Page

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3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA............... 3.1-1 3.1.1 SUMMARY DESCRIPTION.......................................................... 3.1-1 3.1.2 CRITERION CONFORMANCE ..................................................... 3.1-1 3.1.2.1 Group I - Overall Requirements .................................................... 3.1-1 3.1.2.1.1 Criterion 1 - Quality Standards and Records................................... 3.1-1 3.1.2.1.2 Criterion 2 - Design Bases for Protection Against Natural Phenomena... 3.1-3 3.1.2.1.3 Criterion 3 - Fire Protection ...................................................... 3.1-4 3.1.2.1.4 Criterion 4 - Environmental and Missile Design Bases ...................... 3.1-5 3.1.2.1.5 Criterion 5 - Sharing of Structures, Systems, and Components ............ 3.1-6 3.1.2.2 Group II - Protection by Multiple Fission Product Barriers ................... 3.1-7 3.1.2.2.1 Criterion 10 - Reactor Design .................................................... 3.1-7 3.1.2.2.2 Criterion 11 - Reactor Inherent Protection ..................................... 3.1-8 3.1.2.2.3 Criterion 12 - Suppression of Reactor Power Oscillations................... 3.1-9 3.1.2.2.4 Criterion 13 - Instrumentation and Control .................................... 3.1-10 3.1.2.2.5 Criterion 14 - Reactor Coolant Pressure Boundary ........................... 3.1-12 3.1.2.2.6 Criterion 15 - Reactor Coolant System Design ................................ 3.1-14 3.1.2.2.7 Criterion 16 - Containment Design .............................................. 3.1-15 3.1.2.2.8 Criterion 17 - Electrical Power Systems........................................ 3.1-16 3.1.2.2.9 Criterion 18 - Inspection and Testing of Electric Power Systems.......... 3.1-18 3.1.2.2.10 Criterion 19 - Control Room .................................................... 3.1-19 3.1.2.3 Group III - Protection and Reactivity Control System .......................... 3.1-21 3.1.2.3.1 Criterion 20 - Protection System Functions .................................... 3.1-21 3.1.2.3.2 Criterion 21 - Protection System Reliability and Testability ................ 3.1-22 3.1.2.3.3 Criterion 22 - Protection System Independence ............................... 3.1-23 3.1.2.3.4 Criterion 23 - Protection System Failure Modes .............................. 3.1-24 3.1.2.3.5 Criterion 24 - Separation of Protection and Control Systems ............... 3.1-25 3.1.2.3.6 Criterion 25 - Protection System Requirements for Reactivity

Control Malfunctions ............................................................... 3.1-26 3.1.2.3.7 Criterion 26 - Reactivity Control System Redundancy and Capability .... 3.1-27 3.1.2.3.8 Criterion 27 - Combined Reactivity Control Systems Capability........... 3.1-29 3.1.2.3.9 Criterion 28 - Reactivity Limits .................................................. 3.1-30 3.1.2.3.10 Criterion 29 - Protection Against Anticipated Operational

Occurrences ........................................................................ 3.1-32 3.1.2.4 Group IV - Fluid Systems............................................................ 3.1-33 3.1.2.4.1 Criterion 30 - Quality of Reactor Coolant Pressure Boundary.............. 3.1-33

COLUMBIA GENERATING STATION Amendment 58 FINAL SAFETY ANALYSIS REPORT December 2005 Chapter 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS TABLE OF CONTENTS (Continued) Section Page

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3.1.2.4.2 Criterion 31 - Fracture Prevention of Reactor Coolant Pressure Boundary.............................................................................. 3.1-34

3.1.2.4.3 Criterion 32 - Inspection of Reactor Coolant Pressure Boundary .......... 3.1-35 3.1.2.4.4 Criterion 33 - Reactor Coolant Makeup ........................................ 3.1-36 3.1.2.4.5 Criterion 34 - Residual Heat Removal .......................................... 3.1-37 3.1.2.4.6 Criterion 35 - Emergency Core Cooling........................................ 3.1-39 3.1.2.4.7 Criterion 36 - Inspection of Emergency Core Cooling System ............. 3.1-41 3.1.2.4.8 Criterion 37 - Testing of Emergency Core Cooling System................. 3.1-42 3.1.2.4.9 Criterion 38 - Containment Heat Removal ..................................... 3.1-43 3.1.2.4.10 Criterion 39 - Inspection of Containment Heat Removal System ......... 3.1-44 3.1.2.4.11 Criterion 40 - Testing of Containment Heat Removal System ............ 3.1-45 3.1.2.4.12 Criterion 41 - Containment Atmosphere Cleanup ........................... 3.1-46 3.1.2.4.13 Criterion 42 - Inspection of Containment Atmosphere Cleanup

Systems ............................................................................. 3.1-47 3.1.2.4.14 Criterion 43 - Testing of Containment Atmosphere Cleanup Systems ... 3.1-47 3.1.2.4.15 Criterion 44 - Cooling Water.................................................... 3.1-48 3.1.2.4.16 Criterion 45 - Inspection of Cooling Water System ......................... 3.1-49 3.1.2.4.17 Criterion 46 - Testing of Cooling Water System ............................ 3.1-50 3.1.2.5 Group V - Containment (Criteria 50-57) .......................................... 3.1-50 3.1.2.5.1 Criterion 50 - Containment Design Basis....................................... 3.1-50 3.1.2.5.2 Criterion 51 - Fracture Prevention of Containment Pressure Boundary... 3.1-52 3.1.2.5.3 Criterion 52 - Capability for Containment Leakage Rate Testing .......... 3.1-53 3.1.2.5.4 Criterion 53 - Provisions for Containment Testing and Inspection ........ 3.1-53 3.1.2.5.5 Criterion 54 - Piping Systems Penetrating Containment ..................... 3.1-54 3.1.2.5.6 Criterion 55 - Reactor Coolant Pressure Boundary Penetrating

Containment .......................................................................... 3.1-54 3.1.2.5.7 Criterion 56 - Primary Containment Isolation ................................. 3.1-56 3.1.2.5.8 Criterion 57 - Closed System Isolation Valves ................................ 3.1-57 3.1.2.6 Group VI - Fuel and Reactivity Control........................................... 3.1-57 3.1.2.6.1 Criterion 60 - Control of Releases of Radioactive Materials to the

Environment......................................................................... 3.1-57 3.1.2.6.2 Criterion 61 - Fuel Storage and Handling and Radioactivity Control ..... 3.1-59 3.1.2.6.2.1 New Fuel Storage ................................................................ 3.1-59 3.1.2.6.2.2 Spent Fuel Handling and Storage.............................................. 3.1-59 3.1.2.6.2.3 Radioactive Waste Systems..................................................... 3.1-60


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3.1.2.6.3 Criterion 62 - Prevention of Criticality in Fuel Storage and Handling .... 3.1-61 3.1.2.6.4 Criterion 63 - Monitoring Fuel and Waste Storage ........................... 3.1-62 3.1.2.6.5 Criterion 64 - Monitoring Radioactivity Releases............................. 3.1-63 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS,

AND SYSTEMS ........................................................................... 3.2-1 3.2.1 SEISMIC CLASSIFICATION ........................................................ 3.2-1 3.2.2 SYSTEM QUALITY GROUP CLASSIFICATIONS ............................. 3.2-2 3.2.3 SAFETY CLASSIFICATIONS ....................................................... 3.2-2 3.2.3.1 Safety Class 1 .......................................................................... 3.2-3 3.2.3.1.1 Definition of Safety Class 1....................................................... 3.2-3 3.2.3.1.2 Design Requirements for Safety Class 1........................................ 3.2-3 3.2.3.2 Safety Class 2 .......................................................................... 3.2-3 3.2.3.2.1 Definition of Safety Class 2....................................................... 3.2-3 3.2.3.2.2 Design Requirements for Safety Class 2........................................ 3.2-4 3.2.3.3 Safety Class 3 .......................................................................... 3.2-4 3.2.3.3.1 Definition of Safety Class 3....................................................... 3.2-4 3.2.3.3.2 Design Requirement for Safety Class 3 ......................................... 3.2-4 3.2.3.4 General Class G, Structures, Systems, and Components....................... 3.2-4 3.2.3.4.1 Definition of General Class Structures, Systems, and Components ....... 3.2-4 3.2.3.4.2 Design Requirements for General Class G Structures, Systems, and

Components .......................................................................... 3.2-5 3.2.4 QUALITY ASSURANCE CLASSIFICATION.................................... 3.2-5 3.2.5 CORRELATION OF SAFETY CLASSES WITH OTHER DESIGN

REQUIREMENTS....................................................................... 3.2-6 3.2.6 IDENTIFICATION OF SAFETY-RELATED SYSTEMS AND

COMPONENTS ON FLOW DIAGRAMS AND IN THE MASTER EQUIPMENT LIST ..................................................................... 3.2-7

3.3 WIND AND TORNADO LOADINGS................................................. 3.3-1 3.3.1 WIND LOADINGS ..................................................................... 3.3-1 3.3.1.1 Design Wind Velocity ................................................................ 3.3-1 3.3.1.2 Determination of Applied Forces................................................... 3.3-1 3.3.2 TORNADO LOADINGS............................................................... 3.3-3 3.3.2.1 Applicable Design Parameters ...................................................... 3.3-3

COLUMBIA GENERATING STATION Amendment 54 FINAL SAFETY ANALYSIS REPORT April 2000 Chapter 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS TABLE OF CONTENTS (Continued) Section Page

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3.3.2.2 Determination of Forces on Structures ............................................ 3.3-3 3.3.2.3 Additional Design Features .......................................................... 3.3-5 3.3.2.4 Effect of Failure of Structures or Components Not Designed for

Tornado Loads ......................................................................... 3.3-6 3.3.2.5 Conformance with Regulatory Guide 1.76, Revision 0......................... 3.3-8 3.3.3 REFERENCES........................................................................... 3.3-8 3.4 WATER LEVEL (FLOOD) DESIGN.................................................. 3.4-1 3.4.1 FLOOD PROTECTION................................................................ 3.4-1 3.4.1.1 External Flood Levels ................................................................ 3.4-1 3.4.1.1.1 Design Basis Flood ................................................................. 3.4-1 3.4.1.1.2 Breach of the Grand Coulee Dam................................................ 3.4-1 3.4.1.1.3 Acceptance Criteria................................................................. 3.4-1 3.4.1.2 Groundwater Levels .................................................................. 3.4-1 3.4.1.2.1 Design Basis Groundwater ........................................................ 3.4-1 3.4.1.2.2 Breach of the Grand Coulee Dam................................................ 3.4-2 3.4.1.2.3 Design Basis Flood Probable Maximum Precipitation ....................... 3.4-2 3.4.1.3 Identification of Structures, Systems, and Components ........................ 3.4-2 3.4.1.4 Description of Structures, Systems, and Components .......................... 3.4-2 3.4.1.4.1 Flood Protection Requirements................................................... 3.4-2 3.4.1.4.1.1 External Flood Protection Requirements ..................................... 3.4-2 3.4.1.4.1.2 Internal Flood Protection Requirements...................................... 3.4-2 3.4.1.4.2 Groundwater Protection Requirements.......................................... 3.4-4 3.4.1.5 Flood Protection Measures .......................................................... 3.4-6 3.4.1.5.1 External Flood Protection Measures............................................. 3.4-6 3.4.1.5.2 Internal Flood Protection Measures ............................................. 3.4-6 3.4.1.6 Emergency Flood Protection ........................................................ 3.4-6 3.4.2 ANALYSIS PROCEDURES .......................................................... 3.4-6 3.5 MISSILE PROTECTION................................................................. 3.5-1 3.5.1 MISSILE SELECTION AND DESCRIPTIONS................................... 3.5-1 3.5.1.1 Internally Generated Missiles (Outside Containment)........................... 3.5-1 3.5.1.1.1 Systems Available for Safe Shutdown........................................... 3.5-1 3.5.1.1.2 Missiles Due to Rotating Equipment Failure................................... 3.5-2 3.5.1.1.3 Missiles Due to Pressurized Component Failure .............................. 3.5-2


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3.5.1.1.4 Evaluation of Postulated Missiles ................................................ 3.5-5 3.5.1.1.5 Example of Postulated Missile Evaluation ..................................... 3.5-9 3.5.1.2 Internally Generated Missiles (Inside Containment)............................. 3.5-10 3.5.1.2.1 Systems Available for Safe Shutdown........................................... 3.5-10 3.5.1.2.2 Missiles Due to Rotating Equipment ............................................ 3.5-11 3.5.1.2.3 Missiles Due to Pressurized Component Failure .............................. 3.5-11 3.5.1.2.4 Falling Objects ...................................................................... 3.5-12 3.5.1.2.5 Secondary Missiles Generated by Postulated Credible Primary

Missiles .............................................................................. 3.5-12 3.5.1.3 Turbine Missiles ....................................................................... 3.5-12 3.5.1.3.1 Safety-Related Targets ............................................................. 3.5-13 3.5.1.3.2 Turbine Placement and Orientation.............................................. 3.5-13 3.5.1.3.3 Missile Identification and Characteristics....................................... 3.5-13 3.5.1.3.3.1 High Pressure Turbine .......................................................... 3.5-13 3.5.1.3.3.2 Low Pressure Turbine ........................................................... 3.5-14 3.5.1.3.4 Strike and Damage Probability ................................................... 3.5-15 3.5.1.3.4.1 Missile Generation Probability................................................. 3.5-15 3.5.1.3.4.2 Strike Probability (P2) and Damage Probability (P3)...................... 3.5-17 3.5.1.3.4.3 Combined Overall Probability (P4) ........................................... 3.5-17 3.5.1.3.5 Turbine Overspeed Protection System and Testing ........................... 3.5-17 3.5.1.3.6 Turbine Valve Testing ............................................................. 3.5-18 3.5.1.3.7 Turbine Characteristics ............................................................ 3.5-18 3.5.1.4 Missiles Generated by Natural Phenomena ....................................... 3.5-18 3.5.1.4.1 Tornado-Generated External Missiles ........................................... 3.5-18 3.5.1.4.2 Tornado-Generated Internal Missiles............................................ 3.5-21 3.5.1.4.3 Flood Generated Missiles.......................................................... 3.5-21 3.5.1.4.4 Protection and Design.............................................................. 3.5-21 3.5.1.5 Missiles Generated by Events Near the Site ...................................... 3.5-21 3.5.1.6 Aircraft Hazards....................................................................... 3.5-22 3.5.1.6.1 Airports............................................................................... 3.5-22 3.5.1.6.2 Military Airspace Use.............................................................. 3.5-23 3.5.1.6.3 Federal Airways and Airport Approaches ...................................... 3.5-23 3.5.1.6.4 Summary ............................................................................. 3.5-24 3.5.2 SYSTEMS TO BE PROTECTED .................................................... 3.5-24


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3.5.3 BARRIER DESIGN ..................................................................... 3.5-26 3.5.3.1 Concrete Barriers...................................................................... 3.5-26 3.5.3.2 Steel Barriers........................................................................... 3.5-27 3.5.3.3 Earth Barriers .......................................................................... 3.5-27 3.5.3.4 Applications ............................................................................ 3.5-27 3.5.4 REFERENCES........................................................................... 3.5-28 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH

THE POSTULATED RUPTURE OF PIPING ....................................... 3.6-1 3.6.1 PLANT DESIGN FOR PROTECTION AGAINST POSTULATED

PIPING FAILURES IN FLUID SYSTEMS OUTSIDE PRIMARY CONTAINMENT ....................................................................... 3.6-1

3.6.1.1 Energy Classification of Fluid Piping Systems Outside Containment ........ 3.6-2 3.6.1.1.1 High and Moderate Energy Criteria ............................................. 3.6-2 3.6.1.1.2 Systems Subject to Analysis ...................................................... 3.6-2 3.6.1.2 Criteria for Establishing the Postulated Design Basis Break Locations ...... 3.6-2 3.6.1.3 Criteria for Establishing the Postulated Design Basis Break Orientations... 3.6-3 3.6.1.4 Summary of Dynamic Analysis of Category I Piping and Supports.......... 3.6-3 3.6.1.4.1 Design Basis Breaks for the Dynamic Analysis Outside

Primary Containment .............................................................. 3.6-3 3.6.1.4.2 Diagrams of Mathematical Models Used in the Dynamic Analysis........ 3.6-3 3.6.1.4.2.1 Models Used for Pipe Whip Restraint Design .............................. 3.6-3 3.6.1.4.2.2 Models Used for Structural Analysis ......................................... 3.6-3 3.6.1.4.2.3 Models Used to Represent Jet Stream Dynamics ........................... 3.6-3 3.6.1.4.3 Effect of Postulated Fluid Piping System Ruptures on Structures,

Systems, or Components Necessary for Safe Reactor Operation........... 3.6-3 3.6.1.5 Methods to Protect Structures, Systems, or Components Necessary for

Safe Reactor Operation From the Dynamic Effects of Postulated Fluid Piping System Ruptures ...................................................... 3.6-3

3.6.1.5.1 Pipe Whip Restraints ............................................................... 3.6-3 3.6.1.5.2 Protective Provisions for Structures, Systems, and Components

Important to Safety ................................................................. 3.6-4 3.6.1.5.3 Physical Separation of Systems or Components Important to Safety ...... 3.6-4 3.6.1.5.4 Description, Number, and Location of Pipe Whip Restraints

Outside Primary Containment .................................................... 3.6-4


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3.6.1.6 Procedures to Evaluate the Structural Adequacy of Seismic Category I Structures Under Pipe Break Effects Outside Containment ...... 3.6-5

3.6.1.6.1 General Approach................................................................... 3.6-5 3.6.1.6.2 Local Damage Prediction.......................................................... 3.6-5 3.6.1.6.2.1 Reinforced Concrete Targets ................................................... 3.6-6 3.6.1.6.2.2 Steel Targets ...................................................................... 3.6-7 3.6.1.6.3 Overall Structural Response ...................................................... 3.6-8 3.6.1.6.3.1 General ............................................................................. 3.6-8 3.6.1.6.3.2 Structural Response to Whipping Pipe Missile Impact Load ............. 3.6-8 3.6.1.6.3.3 Jet Impingement .................................................................. 3.6-14 3.6.1.6.4 Allowable Design Stresses and Strains.......................................... 3.6-14 3.6.1.6.4.1 Pipe Whip Loading With or Without Other Loads ......................... 3.6-14 3.6.1.6.4.2 Pipe Break Loads (Excluding Pipe Whip) With or Without

Other Loads ....................................................................... 3.6-15 3.6.1.6.5 Loads, Definition of Terms, and Nomenclature............................... 3.6-15 3.6.1.6.6 Load Combinations ................................................................. 3.6-15 3.6.1.6.6.1 Seismic Category I Concrete Structures...................................... 3.6-15 3.6.1.6.6.2 Seismic Category I Steel Structures ........................................... 3.6-15 3.6.1.7 Structural Design Loads.............................................................. 3.6-15 3.6.1.8 Analysis of Load Reversal ........................................................... 3.6-15 3.6.1.9 Modified Structures ................................................................... 3.6-16 3.6.1.10 Verification That Failure of Any Structure Does Not Preclude

Safe Reactor Shutdown ............................................................. 3.6-16 3.6.1.11 Verification That Adequate Redundancy Exists for All Postulated

Fluid Piping System Ruptures ..................................................... 3.6-16 3.6.1.11.1 Approach............................................................................ 3.6-16 3.6.1.11.2 Method of Analysis for Postulated High-Energy Fluid

System Ruptures................................................................... 3.6-17 3.6.1.11.2.1 Effects of Postulated Passive Component Failures........................ 3.6-17 3.6.1.11.2.2 Analytical Procedure ........................................................... 3.6-17 3.6.1.11.3 Method of Analysis for Postulated Moderate-Energy Fluid

System Ruptures................................................................... 3.6-18 3.6.1.11.3.1 Approach ......................................................................... 3.6-18 3.6.1.11.3.2 Method of Analysis............................................................. 3.6-18 3.6.1.11.4 Summary of Analysis ............................................................. 3.6-18


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3.6.1.12 Control Room Habitability ......................................................... 3.6-20 3.6.1.13 Electrical Equipment Environmental Qualifications ........................... 3.6-21 3.6.1.13.1 Identification of Equipment...................................................... 3.6-21 3.6.1.13.2 Environmental Design ............................................................ 3.6-21 3.6.1.13.3 Jet Impingement Barriers ........................................................ 3.6-22 3.6.1.13.4 Control Room Equipment........................................................ 3.6-22 3.6.1.13.5 Onsite Power Distribution System Equipment ............................... 3.6-22 3.6.1.14 Design Diagrams of Nuclear Steam Supply System Piping .................. 3.6-22 3.6.1.15 Flooding Analysis.................................................................... 3.6-22 3.6.1.15.1 Postulated Rupture of the Reactor Feedwater Piping ....................... 3.6-22 3.6.1.15.1.1 Consequences..................................................................... 3.6-22 3.6.1.15.2 Postulated Ruptures of Reactor Water Cleanup System .................... 3.6-23 3.6.1.15.3 Postulated Ruptures of the Auxiliary Steam, Heating Steam,

Auxiliary Condensate, and Heating Steam Condensate Systems.......... 3.6-23 3.6.1.15.4 Additional Considerations ....................................................... 3.6-23 3.6.1.16 Quality Control and Inspection Programs ....................................... 3.6-23 3.6.1.17 Leak Detection System Capabilities .............................................. 3.6-24 3.6.1.18 Emergency Procedures to Mitigate the Consequences of a Postulated

Fluid Piping System Rupture Outside Primary Containment................. 3.6-24 3.6.1.18.1 Reactor Not Isolated .............................................................. 3.6-24 3.6.1.18.2 Reactor Isolated.................................................................... 3.6-24 3.6.1.18.2.1 Reactivity Control .............................................................. 3.6-24 3.6.1.18.2.2 Core Coolant Level Maintenance ............................................ 3.6-24 3.6.1.18.3 Methods of Shutdown Following a Postulated Rupture of a

Fluid Piping System .............................................................. 3.6-25 3.6.1.18.3.1 Postulated Rupture of Main Steam Piping in the Main Steam

Tunnel Vicinity .................................................................. 3.6-25 3.6.1.18.3.2 Postulated Rupture of Reactor Feedwater Piping ......................... 3.6-25 3.6.1.18.3.3 Postulated Rupture of Reactor Core Isolation Cooling System

Piping ............................................................................. 3.6-25 3.6.1.18.3.4 Postulated Rupture of Residual Heat Removal System Piping.......... 3.6-26 3.6.1.18.3.5 Postulated Rupture of the Control Rod Drive System Piping ........... 3.6-26 3.6.1.18.3.6 Postulated Ruptures of the Auxiliary Steam, Heating Steam,

Auxiliary Condensate, and Heating Steam Condensate Piping ......... 3.6-26


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3.6.1.18.3.7 Postulated Rupture of the Reactor Water Cleanup System Piping ............................................................................. 3.6-26

3.6.1.19 Seismic and Quality Classifications of Piping Used in the Dynamic Analysis ............................................................................... 3.6-26

3.6.1.20 Method Used to Predict Blowdown Rates and Subcompartment Pressure Transient After a Postulated Pipe Break.............................. 3.6-27

3.6.1.20.1 Blowdown Analysis for a Postulated Pipe Break Outside the Primary Containment ............................................................. 3.6-27

3.6.1.20.1.1 Method of Analysis for a Postulated Pipe Break in Larger Pipes ...... 3.6-27 3.6.1.20.1.2 Method of Analysis for a Postulated Pipe Break in Smaller Pipes ..... 3.6-27 3.6.1.20.1.3 Blowdown Mass and Energy Release Rates for a Postulated Pipe

Break in the Main Steam Line and the Reactor Feedwater Line in the Main Steam Tunnel ..................................................... 3.6-27

3.6.1.20.2 Subcompartment Analysis for Postulated Pipe Break Outside the Primary Containment Excluding the Main Steam Tunnel, Ventway, and Tunnel Extension............................................................. 3.6-27

3.6.1.20.2.1 Method of Analysis............................................................. 3.6-27 3.6.1.20.2.2 Initial Atmospheric Conditions ............................................... 3.6-28 3.6.1.20.2.3 Vent Flow ........................................................................ 3.6-29 3.6.1.20.2.4 Results of Subcompartment Analyses ....................................... 3.6-29 3.6.1.20.2.5 Verification of Structural Adequacy......................................... 3.6-29 3.6.1.20.3 Subcompartment Analysis for a Postulated Pipe Break in the

Main Steam Tunnel ............................................................... 3.6-29 3.6.1.20.3.1 General Approaches ............................................................ 3.6-29 3.6.1.20.3.2 Description of the Main Steam Tunnel, Ventway, and

Tunnel Extension................................................................ 3.6-29 3.6.1.20.3.3 Analysis for a Postulated Pipe Break in the Main Steam Tunnel....... 3.6-30 3.6.1.20.3.4 Analysis for a Postulated Pipe Break in the Tunnel Extension ......... 3.6-32 3.6.1.20.3.5 Verification of Structural Adequacy......................................... 3.6-33 3.6.1.20.3.6 Turbine Building Consequences of a Postulated Pipe Break in the

Steam Tunnel Extension ....................................................... 3.6-33 3.6.1.21 Description of Methods of Analyses to Ensure That Primary or

Secondary Containment Integrity Is Not Compromised by a Postulated Passive Component Failure........................................... 3.6-34


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3.6.2 DETERMINATION OF BREAK LOCATIONS FOR DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING ............................................................................... 3.6-34

3.6.2.1 Criteria Used to Define Break and Crack Location and Configuration ...... 3.6-34 3.6.2.1.1 Postulated Pipe Break Locations in High-Energy Fluid System

Piping Not in the Containment Penetration Area.............................. 3.6-36 3.6.2.1.1.1 Postulated Pipe Break Locations in ASME Section III Class I

Piping Runs........................................................................ 3.6-36 3.6.2.1.1.2 Postulated Pipe Break Locations in ASME Section III Class 2

and 3 Piping Runs ................................................................ 3.6-37 3.6.2.1.1.3 Break Locations in Other Piping Runs ....................................... 3.6-37 3.6.2.1.2 Postulated Pipe Break Locations in High-Energy Fluid System

Piping Between Primary Containment Isolation Valves...................... 3.6-38 3.6.2.1.2.1 Postulated Pipe Break Locations in ASME Section III Class 1

Piping Between Primary Containment Isolation Valves ................... 3.6-38 3.6.2.1.2.2 Postulated Pipe Break Locations in ASME Section III Class 2

and 3 Piping Between Primary Containment Isolation Valves............ 3.6-38 3.6.2.1.2.3 Primary Containment Penetration Piping .................................... 3.6-39 3.6.2.1.3 Postulated Through Wall Leakage Crack Locations in High-

and Moderate-Energy Fluid Systems............................................ 3.6-39 3.6.2.1.4 Types of Breaks and Cracks Postulated in High-Energy and

Moderate-Energy Fluid System Piping ......................................... 3.6-40 3.6.2.1.4.1 Breaks in High-Energy Fluid System Piping ................................ 3.6-40 3.6.2.1.4.2 Cracks in High-Energy and Moderate-Energy Fluid System Piping .... 3.6-41 3.6.2.1.5 Protection Criteria for the Effects of Pipe Break.............................. 3.6-42 3.6.2.2 Analytic Methods to Define Blowdown Forcing Functions and

Response Models ...................................................................... 3.6-42 3.6.2.2.1 Analytical Methods to Define Blowdown Forcing Functions ............... 3.6-42 3.6.2.2.2 Analytical Methods to Define Response Models .............................. 3.6-45 3.6.2.2.2.1 General Description of Analytical Methods ................................. 3.6-45 3.6.2.2.2.2 Dynamic Analysis of the Effects of Pipe Rupture .......................... 3.6-45 3.6.2.2.3 Material Properties Under Dynamic Loads .................................... 3.6-49 3.6.2.2.3.1 Dynamic Yield Strength......................................................... 3.6-49 3.6.2.2.3.2 Maximum Strain of Tension Members ....................................... 3.6-49 3.6.2.2.3.3 Maximum Deformation of Flexural Members .............................. 3.6-50


LDCN-98-078 3-xi

3.6.2.2.3.4 Materials and Proportions of Structural Shapes............................. 3.6-50 3.6.2.3 Dynamic Analysis Methods to Verify Integrity and Operability .............. 3.6-50 3.6.2.3.1 Dynamic Analysis Methods for Jet Impingement Effects.................... 3.6-50 3.6.2.3.2 Jet Impingement Effect ............................................................ 3.6-54 3.6.2.3.2.1 Physical Separation .............................................................. 3.6-54 3.6.2.3.2.2 Jet Impingement Evaluation .................................................... 3.6-54 3.6.2.3.2.3 Postulated Pipe Rupture Locations Inside Containment ................... 3.6-54 3.6.2.3.2.4 Signals From Primary Containment........................................... 3.6-55 3.6.2.3.2.5 Signals to the Primary Containment .......................................... 3.6-55 3.6.2.3.2.6 Power Requirement Inside Primary Containment .......................... 3.6-55 3.6.2.3.2.7 Mechanical Engineered Safety Systems ...................................... 3.6-56 3.6.2.3.2.8 Jet Impingement on Major Structures Inside Primary Containment ..... 3.6-56 3.6.2.3.3 Pipe Whip Restraints ............................................................... 3.6-56 3.6.2.3.3.1 Definition of Function ........................................................... 3.6-56 3.6.2.3.3.2 Pipe Whip Restraint Features .................................................. 3.6-57 3.6.2.3.3.3 Pipe Whip Restraint Loading................................................... 3.6-58 3.6.2.3.4 Pipe Whip Effects on Safety-Related Components............................ 3.6-59 3.6.2.3.4.1 Pipe Displacement Effects on Components in Same Piping Run ........ 3.6-59 3.6.2.3.4.2 Pipe Displacement Effects on Structures, Other Systems,

and Components.................................................................. 3.6-60 3.6.2.4 Guard Pipe Assembly Design Criteria for Dual Barrier Containment ....... 3.6-60 3.6.2.5 Implementation of Criteria for Pipe Whip and Jet Impingement

Protection ............................................................................... 3.6-61 3.6.2.5.1 Piping Systems Outside Primary Containment................................. 3.6-61 3.6.2.5.2 Piping Systems Inside Primary Containment................................... 3.6-61 3.6.2.5.3 System Requirements Subsequent to Postulated Pipe Rupture .............. 3.6-62 3.6.2.5.3.1 Control Rod Insertion Capability .............................................. 3.6-62 3.6.2.5.3.2 Core Cooling Requirements .................................................... 3.6-62 3.6.2.5.3.3 Maximum Allowable Break Areas ............................................ 3.6-62 3.6.2.5.3.4 Break Combinations ............................................................. 3.6-62 3.6.2.5.3.5 Required Cooling Systems...................................................... 3.6-62 3.6.2.5.3.6 Containment System Integrity.................................................. 3.6-63 3.6.2.5.4 System by System Description of Pipe Whip Protection..................... 3.6-63 3.6.2.5.4.1 Main Steam System .............................................................. 3.6-63 3.6.2.5.4.2 Reactor Feedwater System (Inside Primary Containment) ................ 3.6-64


LDCN-98-078 3-xii

3.6.2.5.4.3 Reactor Water Cleanup System ................................................ 3.6-65 3.6.2.5.4.4 Standby Liquid Control Piping................................................. 3.6-66 3.6.2.5.4.5 Residual Heat Removal System - Shutdown Cooling Supply

and Return Piping ................................................................ 3.6-66 3.6.2.5.4.6 Reactor Core Isolation Cooling Reactor Pressure Vessel

Head Spray System .............................................................. 3.6-67 3.6.2.5.4.7 Low-Pressure and High-Pressure Core Spray Piping ...................... 3.6-68 3.6.2.5.4.8 Residual Heat Removal Condensing Mode and Reactor Core

Isolation Cooling Turbine Steam Supply System ........................... 3.6-68 3.6.2.5.4.9 Main Steam Valve Drainage Piping........................................... 3.6-69 3.6.2.5.4.10 Main Steam Reactor Pressure Vessel Head Vent System................ 3.6-70 3.6.2.5.4.11 Main Steam and Reactor Feedwater Piping Inside Main

Steam Tunnel .................................................................... 3.6-71 3.6.2.5.4.12 Residual Heat Removal System - Low Pressure Core Injection ........ 3.6-71 3.6.2.5.4.13 Reactor Pressure Vessel Drain System...................................... 3.6-72 3.6.2.5.4.14 Reactor Recirculation Cooling System...................................... 3.6-73 3.6.3 REFERENCES........................................................................... 3.6-74 3.7 SEISMIC DESIGN......................................................................... 3.7-1 3.7.1 SEISMIC INPUT ........................................................................ 3.7-1 3.7.1.1 Design Response Spectra............................................................. 3.7-1 3.7.1.2 Design Time History.................................................................. 3.7-2 3.7.1.3 Critical Damping Values ............................................................. 3.7-4 3.7.1.4 Supporting Media for Seismic Category I Structures ........................... 3.7-4 3.7.2 SEISMIC SYSTEM ANALYSIS ..................................................... 3.7-4 3.7.2.1 Seismic Analysis Methods ........................................................... 3.7-5 3.7.2.1.1 Introduction .......................................................................... 3.7-5 3.7.2.1.2 The Equations of Dynamic Equilibrium ........................................ 3.7-5 3.7.2.1.3 Solution of the Equations of Dynamic Equilibrium by Direct

Integration ........................................................................... 3.7-6 3.7.2.1.4 Solution of the Equations of Dynamic Equilibrium by Mode-

Superposition........................................................................ 3.7-6 3.7.2.1.5 Response Spectrum Method of Analysis........................................ 3.7-7 3.7.2.1.5.1 Combination of Modal Response .............................................. 3.7-8 3.7.2.1.5.1.1 Square Root-of-the-Sum-of-the-Squares Method.......................... 3.7-8


LDCN-99-000 3-xiii

3.7.2.1.5.1.2 Double Sum Method ........................................................... 3.7-8 3.7.2.1.6 Time-History Method of Analysis ............................................... 3.7-9 3.7.2.1.7 Analysis for Differential Support Displacements.............................. 3.7-10 3.7.2.1.8 Dynamic Analysis of Seismic Category I Structures, Systems,

and Components .................................................................... 3.7-11 3.7.2.1.8.1 Dynamic Analysis of Buildings ................................................ 3.7-11 3.7.2.1.8.2 Dynamic Analysis of Piping Systems......................................... 3.7-11 3.7.2.1.8.3 Dynamic Analysis of Equipment .............................................. 3.7-12 3.7.2.1.8.3.1 Differential Seismic Movement of Interconnected Components....... 3.7-13 3.7.2.1.9 Equivalent Static Load Method................................................... 3.7-14 3.7.2.1.10 Dynamic Testing .................................................................. 3.7-14 3.7.2.2 Natural Frequencies and Response Loads......................................... 3.7-15 3.7.2.3 Procedure Used for Modeling....................................................... 3.7-16 3.7.2.3.1 Modeling of Structures............................................................. 3.7-18 3.7.2.3.2 Modeling of Piping Systems ...................................................... 3.7-18 3.7.2.3.3 Modeling of Equipment............................................................ 3.7-19 3.7.2.3.4 Modeling of Reactor Pressure Vessel and Internals .......................... 3.7-19 3.7.2.4 Soil/Structure Interaction ............................................................ 3.7-20 3.7.2.5 Development of Floor Response Spectra.......................................... 3.7-21 3.7.2.6 Three Components of Earthquake Motion ........................................ 3.7-22 3.7.2.7 Combination of Modal Responses .................................................. 3.7-23 3.7.2.8 Interaction of Non-Category I Structures With Seismic

Category I Structures.................................................................. 3.7-23 3.7.2.9 Effects of Parameter Variations on Floor Response Spectra................... 3.7-23 3.7.2.10 Use of Constant Vertical Static Factors.......................................... 3.7-24 3.7.2.11 Method Used to Account for Torsional Effects ................................ 3.7-24 3.7.2.12 Comparison of Responses .......................................................... 3.7-24 3.7.2.13 Methods for Seismic Analysis of Dams.......................................... 3.7-25 3.7.2.14 Determination of Seismic Category I Structure Overturning Moments .... 3.7-25 3.7.2.15 Analysis Procedure for Damping ................................................. 3.7-26 3.7.3 SEISMIC SUBSYSTEM ANALYSIS................................................ 3.7-29 3.7.3.1 Seismic Analysis Methods ........................................................... 3.7-29 3.7.3.2 Determination of Number of Earthquake Cycles ................................ 3.7-29 3.7.3.2.1 Number of Cycles for All Items Except Nuclear Steam Supply

System Systems and Components ............................................... 3.7-29


LDCN-02-000 3-xiv

3.7.3.2.2 Number of Cycles for Nuclear Steam Supply System Systems and Components .................................................................... 3.7-29

3.7.3.2.2.1 Nuclear Steam Supply System Piping......................................... 3.7-29 3.7.3.2.2.2 Other Nuclear Steam Supply System Equipment and Components...... 3.7-29 3.7.3.3 Procedure Used for Modeling....................................................... 3.7-30 3.7.3.4 Basis for Selection of Frequencies ................................................. 3.7-31 3.7.3.5 Use of Equivalent Static Load Method of Analysis ............................. 3.7-31 3.7.3.6 Three Components of Earthquake Motion ........................................ 3.7-31 3.7.3.7 Procedure for Combining Modal Responses...................................... 3.7-32 3.7.3.8 Analytical Procedures for Piping ................................................... 3.7-32 3.7.3.9 Equipment Components Supported at Multiple Locations with

Distinct Inputs .......................................................................... 3.7-32 3.7.3.10 Use of Constant Vertical Static Factors.......................................... 3.7-32 3.7.3.11 Torsional Effects of Eccentric Masses ........................................... 3.7-32 3.7.3.12 Buried Seismic Category I Piping Systems and Tunnels...................... 3.7-33 3.7.3.12.1 Procedures for Predicting the Stresses of Buried Pipes in the

Free Field........................................................................... 3.7-33 3.7.3.12.1.1 Method of Analysis............................................................. 3.7-33 3.7.3.12.1.2 Axial Stresses in Pipe .......................................................... 3.7-33 3.7.3.12.1.3 Bending Stresses in Pipes...................................................... 3.7-33 3.7.3.12.1.4 Buried Piping Encased in Oversized Culvert Sections ................... 3.7-33 3.7.3.12.2 Procedures for Predicting the Stresses of Buried Pipes at

Connections to Various Buildings .............................................. 3.7-34 3.7.3.13 Interaction of Other Piping With Seismic Category I Piping................. 3.7-34 3.7.3.14 Seismic Analyses for Reactor Internals .......................................... 3.7-34 3.7.3.15 Analysis Procedure for Damping ................................................. 3.7-34 3.7.4 SEISMIC INSTRUMENTATION .................................................... 3.7-34 3.7.4.1 Comparison With Regulatory Guide 1.12......................................... 3.7-34 3.7.4.2 Location and Description of Instrumentation ..................................... 3.7-34 3.7.4.3 Control Room Operator Notification............................................... 3.7-36 3.7.4.4 Comparison of Measured and Predicted Responses ............................. 3.7-36 3.7.5 REFERENCES........................................................................... 3.7-37 3.8 DESIGN OF SEISMIC CATEGORY I STRUCTURES ............................ 3.8-1 3.8.1 CONCRETE CONTAINMENT VESSEL (Not Applicable to CGS)........... 3.8-2


LDCN-99-000 3-xv

3.8.2 STEEL CONTAINMENT VESSEL (ASME Class MC Components)......... 3.8-2 3.8.2.1 Description of the Primary Containment Vessel ................................. 3.8-3 3.8.2.1.1 Description of Penetrations ....................................................... 3.8-10 3.8.2.1.1.1 Pipe Penetrations ................................................................. 3.8-10 3.8.2.1.1.2 Electrical Penetrations ........................................................... 3.8-10 3.8.2.1.1.3 Traversing In-Core Probe Penetrations....................................... 3.8-11 3.8.2.1.1.4 Personnel Access Lock and the (Combined) Equipment Hatch

and Control Rod Drive Removal Hatch ...................................... 3.8-11 3.8.2.1.1.5 Pressure Suppression Chamber Access Hatch............................... 3.8-12 3.8.2.1.1.6 Access for Refueling Operations .............................................. 3.8-12 3.8.2.1.2 Description of Crane Girder (Not Applicable to CGS)....................... 3.8-12 3.8.2.1.3 Description of Vacuum Relief System .......................................... 3.8-12 3.8.2.1.4 Containment Pressure Boundaries ............................................... 3.8-14 3.8.2.1.5 Primary Containment Environmental Conditions ............................. 3.8-14 3.8.2.2 Applicable Codes, Standards, Specifications, and Regulatory Guides ....... 3.8-15 3.8.2.2.1 Codes, Standards, and Specifications ........................................... 3.8-15 3.8.2.2.2 Code Classification ................................................................. 3.8-15 3.8.2.2.3 Code Compliance ................................................................... 3.8-16 3.8.2.2.3.1 Containment Vessel .............................................................. 3.8-16 3.8.2.2.3.2 Code Stamp........................................................................ 3.8-16 3.8.2.2.3.3 Exceptions ......................................................................... 3.8-16 3.8.2.2.3.4 Attachments ....................................................................... 3.8-16 3.8.2.2.4 Regulatory Guides .................................................................. 3.8-16 3.8.2.3 Loads and Loading Combinations .................................................. 3.8-17 3.8.2.3.1 Design Pressures and Temperatures ............................................. 3.8-17 3.8.2.3.2 Operating Pressure and Temperature............................................ 3.8-18 3.8.2.3.3 Dead Loads .......................................................................... 3.8-19 3.8.2.3.4 Live Loads ........................................................................... 3.8-20 3.8.2.3.5 Mechanical Piping Loads.......................................................... 3.8-20 3.8.2.3.5.1 Jet Forces in Drywell ............................................................ 3.8-21 3.8.2.3.5.2 Vent Pipe (Downcomer) Thrusts .............................................. 3.8-21 3.8.2.3.5.3 Pipe Whip.......................................................................... 3.8-22 3.8.2.3.6 Thermal Loads ...................................................................... 3.8-22 3.8.2.3.7 Construction Loads ................................................................. 3.8-22 3.8.2.3.8 Missile Loads........................................................................ 3.8-22


LDCN-99-000 3-xvi

3.8.2.3.9 Loss-of-Coolant Accident Loads ................................................. 3.8-22 3.8.2.3.10 Accident Recovery Loads........................................................ 3.8-23 3.8.2.3.11 Seismic Loads...................................................................... 3.8-23 3.8.2.3.12 Loading Combinations............................................................ 3.8-23 3.8.2.4 Design and Analysis Procedure..................................................... 3.8-29 3.8.2.4.1 Description........................................................................... 3.8-30 3.8.2.4.1.1 Bottom Ellipsoidal Head and Bell-Jar Shaped Shell ........................ 3.8-30 3.8.2.4.1.2 Steel Containment Vessel Embedment Region .............................. 3.8-31 3.8.2.4.1.3 Penetrations ....................................................................... 3.8-31 3.8.2.4.1.4 Personnel Access Lock and the (Combined) Equipment Hatch

and Control Rod Drive Removal Hatch ...................................... 3.8-32 3.8.2.4.2 Computer Programs Utilized in Design and Analysis ........................ 3.8-33 3.8.2.4.3 Seismic Analysis .................................................................... 3.8-34 3.8.2.4.3.1 Computer Program Utilized in the Seismic Dynamic Analysis .......... 3.8-36 3.8.2.4.3.2 Seismic Dynamic Analysis of Water in Suppression Chamber

(Sloshing Effects)................................................................. 3.8-36 3.8.2.4.4 Protective Coatings ................................................................. 3.8-37 3.8.2.5 Structural Acceptance Criteria ...................................................... 3.8-37 3.8.2.5.1 Primary Stresses .................................................................... 3.8.37 3.8.2.5.2 Primary and Secondary Stresses ................................................. 3.8-38 3.8.2.5.3 Peak Stresses ........................................................................ 3.8-38 3.8.2.5.4 Buckling Criteria for the Primary Containment Vessel ...................... 3.8-38 3.8.2.6 Materials, Quality Control, and Special Construction Techniques ........... 3.8-39 3.8.2.6.1 Materials.............................................................................. 3.8-39 3.8.2.6.2 Quality Control...................................................................... 3.8-42 3.8.2.6.3 Special Construction Techniques................................................. 3.8-44 3.8.2.7 Testing and Inservice Inspection Requirements .................................. 3.8-44 3.8.2.7.1 Inspection of Material and Parts for Fabrication .............................. 3.8-44 3.8.2.7.2 Testing of Primary Containment Vessel During Field Erection ............ 3.8-45 3.8.2.7.3 Testing of the Erected Primary Containment Vessel ......................... 3.8-45 3.8.2.7.4 Tests on Electrical and Mechanical Penetrations .............................. 3.8-48 3.8.2.7.5 Tests on Personnel Access Lock ................................................. 3.8-48 3.8.2.7.6 Tests on Penetration Field Welds ................................................ 3.8-50 3.8.2.7.7 Preoperational Leakage Rate Test and Periodic Leakage Rate Tests ...... 3.8-50 3.8.2.7.8 Examination of Coatings on Immersed Surfaces .............................. 3.8-51


LDCN-99-000 3-xvii

3.8.3 CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL CONTAINMENT ....................................................................... 3.8-51

3.8.3.1 Description of Internal Structures .................................................. 3.8-51 3.8.3.1.1 Reactor Pedestal..................................................................... 3.8-52 3.8.3.1.2 Sacrificial Shield Wall ............................................................. 3.8-53 3.8.3.1.3 Drywell Floor Structural System and Support Elements..................... 3.8-53 3.8.3.1.4 Radial Beam Framing Systems ................................................... 3.8-55 3.8.3.1.5 Stabilizer Truss...................................................................... 3.8-56 3.8.3.1.6 Refueling Bellows Seals ........................................................... 3.8-57 3.8.3.1.7 Reactor Steam Supply System Hangers and Supports ........................ 3.8-57 3.8.3.1.8 Reinforced-Concrete Lining Inside the Bottom Head of the Primary

Containment Vessel ................................................................ 3.8-57 3.8.3.2 Applicable Codes, Standards, Specifications, and Regulatory Guides ....... 3.8-57 3.8.3.2.1 Reactor Pedestal..................................................................... 3.8-58 3.8.3.2.2 Sacrificial Shield Wall ............................................................. 3.8-58 3.8.3.2.3 Drywell Floor Structural System and Support Elements..................... 3.8-58 3.8.3.2.3.1 Reinforced-Concrete Slab....................................................... 3.8-58 3.8.3.2.3.2 Reinforced-Concrete Columns ................................................. 3.8-59 3.8.3.2.3.3 Reinforced-Concrete Reactor Pedestal........................................ 3.8-59 3.8.3.2.3.4 Circular Closure Girder ......................................................... 3.8-59 3.8.3.2.3.5 Drywell Floor Peripheral Seal ................................................. 3.8-59 3.8.3.2.3.6 Peripheral Seal Jet Deflectors .................................................. 3.8-59 3.8.3.2.3.7 Shear Lugs......................................................................... 3.8-59 3.8.3.2.3.8 Downcomers ...................................................................... 3.8-59 3.8.3.2.3.9 Downcomer Jet Deflectors...................................................... 3.8-59 3.8.3.2.4 Radial Beam Framing Systems ................................................... 3.8-60 3.8.3.2.5 Stabilizer Truss...................................................................... 3.8-60 3.8.3.2.6 Refueling Bellows Seals ........................................................... 3.8-60 3.8.3.2.7 Reactor Steam Supply System Hangers and Supports ........................ 3.8-60 3.8.3.2.8 Reinforced-Concrete Lining Inside Bottom Head of Primary

Containment Vessel ................................................................ 3.8-60 3.8.3.3 Loads and Load Combinations ...................................................... 3.8-60 3.8.3.3.1 Load Conditions..................................................................... 3.8-61 3.8.3.3.2 Load Categories ..................................................................... 3.8-61 3.8.3.3.3 Load Definitions .................................................................... 3.8-63


LDCN-99-000 3-xviii

3.8.3.3.4 Internal Structures in the Suppression Chamber............................... 3.8-66 3.8.3.3.5 Internal Structures in the Drywell................................................ 3.8-68 3.8.3.4 Design and Analysis Procedures.................................................... 3.8-69 3.8.3.4.1 Reactor Pedestal..................................................................... 3.8-69 3.8.3.4.2 Sacrificial Shield Wall ............................................................. 3.8-70 3.8.3.4.3 Drywell Floor Structural System and Support Elements, Including

the Peripheral Seal Assembly, Peripheral Seal Jet Deflectors, and Peripheral Shear Lugs ............................................................. 3.8-70

3.8.3.4.3.1 Drywell Floor Slab and Columns.............................................. 3.8-70 3.8.3.4.3.2 Structural Steel Members ....................................................... 3.8-71 3.8.3.4.3.3 Drywell Floor Peripheral Seal Assembly .................................... 3.8-71 3.8.3.4.3.4 Drywell Floor Peripheral Shear Lugs ........................................ 3.8-72 3.8.3.4.4 Radial Beam Framing Systems ................................................... 3.8-73 3.8.3.4.5 Stabilizer Truss...................................................................... 3.8-73 3.8.3.4.6 Refueling Bellows Seals ........................................................... 3.8-73 3.8.3.4.7 Reactor Steam Supply System Hangers and Supports ........................ 3.8-74 3.8.3.4.8 Reinforced-Concrete Lining Inside Bottom Head of Primary

Containment Vessel ................................................................ 3.8-74 3.8.3.4.9 Downcomer Vent Pipes............................................................ 3.8-74 3.8.3.5 Structural Acceptance Criteria ...................................................... 3.8-75 3.8.3.5.1 Reinforced Concrete................................................................ 3.8-75 3.8.3.5.2 Structural Steel ...................................................................... 3.8-75 3.8.3.6 Materials, Quality Control and Special Construction Techniques ............ 3.8-76 3.8.3.7 Testing and Inservice Surveillance Programs .................................... 3.8-76 3.8.4 OTHER SEISMIC CATEGORY I STRUCTURES ............................... 3.8-77 3.8.4.1 Description of Structures............................................................. 3.8-77 3.8.4.1.1 Reactor Building .................................................................... 3.8-78 3.8.4.1.1.1 Basic Structure.................................................................... 3.8-80 3.8.4.1.1.2 Personnel and Equipment Access.............................................. 3.8-81 3.8.4.1.1.3 Biological Shield Wall ........................................................... 3.8-82 3.8.4.1.1.4 Main Steam Tunnel, Ventway, and Tunnel Extension..................... 3.8-83 3.8.4.1.1.5 Operating Floor, Steel Superstructure, and Overhead Bridge Crane.... 3.8-84 3.8.4.1.1.6 Refueling Pools ................................................................... 3.8-85 3.8.4.1.2 Radwaste and Control Building .................................................. 3.8-86 3.8.4.1.3 Turbine Generator Building....................................................... 3.8-88


LDCN-98-078 3-xix

3.8.4.1.4 Diesel Generator Building......................................................... 3.8-88 3.8.4.1.5 Spray Ponds and Standby Service Water Pump Houses ..................... 3.8-89 3.8.4.1.6 Makeup Water Pump House ...................................................... 3.8-91 3.8.4.1.7 Condensate Storage Tanks Retaining Area ..................................... 3.8-93 3.8.4.1.8 Fresh Air Intake Structures 1 and 2 ............................................. 3.8-94 3.8.4.2 Applicable Codes, Standards, Specifications, and Regulatory Guides ....... 3.8-95 3.8.4.3 Loads and Load Combinations ...................................................... 3.8-96 3.8.4.3.1 Load Conditions..................................................................... 3.8-96 3.8.4.3.2 Load Categories ..................................................................... 3.8-96 3.8.4.3.3 Load Definitions .................................................................... 3.8-98 3.8.4.4 Design and Analysis Procedures.................................................... 3.8-103 3.8.4.4.1 Reactor Building .................................................................... 3.8-104 3.8.4.4.1.1 Biological Shield Wall ........................................................... 3.8-105 3.8.4.5 Structural Acceptance Criteria ...................................................... 3.8-108 3.8.4.5.1 Reinforced Concrete................................................................ 3.8-108 3.8.4.5.2 Structural Steel ...................................................................... 3.8-108 3.8.4.6 Materials, Quality Control, and Special Construction Techniques ........... 3.8-109 3.8.4.7 Testing and Inservice Surveillance Requirements ............................... 3.8-109 3.8.5 FOUNDATIONS ........................................................................ 3.8-109 3.8.5.1 Descriptions of Foundations......................................................... 3.8-109 3.8.5.1.1 Reactor Building .................................................................... 3.8-110 3.8.5.1.2 Radwaste and Control Building .................................................. 3.8-110 3.8.5.1.3 Diesel Generator Building......................................................... 3.8-110 3.8.5.1.4 Standby Service Water Pump House and Spray Pond........................ 3.8-111 3.8.5.1.5 Condensate Storage Tank Retaining Area ...................................... 3.8-111 3.8.5.1.6 Turbine Generator Building....................................................... 3.8-112 3.8.5.1.7 Non-Seismic Category I Safety-Related Foundations......................... 3.8-112 3.8.5.2 Applicable Codes, Standards, and Specifications................................ 3.8-112 3.8.5.3 Loads and Loading Combinations .................................................. 3.8-113 3.8.5.4 Design and Analysis Procedures.................................................... 3.8-113 3.8.5.4.1 General ............................................................................... 3.8-113 3.8.5.4.2 Reactor Building Foundation Mat................................................ 3.8-113 3.8.5.4.3 Radwaste and Control Building .................................................. 3.8-113 3.8.5.4.4 Diesel Generator Building......................................................... 3.8-114


LDCN-04-000 3-xx

3.8.5.4.5 Standby Service Water Pump Houses, Spray Ponds, and Condensate Storage Tank Retaining Area ..................................................... 3.8-114

3.8.5.4.6 Turbine Generator Building....................................................... 3.8-114 3.8.5.4.7 Makeup Water Pump House ...................................................... 3.8-115 3.8.5.5 Structural Acceptance Criteria ...................................................... 3.8-115 3.8.5.6 Materials, Quality Control, and Special Construction Techniques ........... 3.8-116 3.8.5.7 Testing and Inservice Surveillance Techniques .................................. 3.8-116 3.8.6 PIPING AND ELECTRICAL PENETRATIONS ................................. 3.8-116 3.8.6.1 Description ............................................................................. 3.8-117 3.8.6.1.1 Piping Penetrations - Type 1...................................................... 3.8-117 3.8.6.1.2 Piping Penetrations - Type 2...................................................... 3.8-119 3.8.6.1.3 Piping Penetrations - Type 3...................................................... 3.8-119 3.8.6.1.4 Electrical Penetrations - Type 4 .................................................. 3.8-120 3.8.6.1.4.1 Configuration ..................................................................... 3.8-121 3.8.6.1.4.2 Ampacity........................................................................... 3.8-124 3.8.6.1.4.3 Auxiliary Hardware.............................................................. 3.8-124 3.8.6.1.4.4 Shop Painting of Electrical Penetrations ..................................... 3.8-125 3.8.6.1.5 Instrumentation Piping Penetrations - Type 5, 6, and 7...................... 3.8-125 3.8.6.2 Applicable Codes, Standards, Specifications, and Regulatory Guides ....... 3.8-125 3.8.6.2.1 Codes, Standards, and Specifications ........................................... 3.8-125 3.8.6.2.2 Conformance with Regulatory Guides .......................................... 3.8-128 3.8.6.3 Loads and Loading Combinations .................................................. 3.8-128 3.8.6.3.1 Loads.................................................................................. 3.8-128 3.8.6.3.2 Loading Combinations ............................................................. 3.8-128 3.8.6.4 Design and Analysis Procedures.................................................... 3.8-129 3.8.6.4.1 Piping Penetrations ................................................................. 3.8-129 3.8.6.4.2 Flued Head Fitting Design ........................................................ 3.8-129 3.8.6.4.3 Thermal Stress Analysis for Flued Head Fittings ............................. 3.8-130 3.8.6.4.4 Primary Containment Vessel Design at Penetration Nozzle Interface ..... 3.8-130 3.8.6.4.5 Electrical Penetrations ............................................................. 3.8-132 3.8.6.4.6 Protective Coatings ................................................................. 3.8-133 3.8.6.5 Structural Acceptance Criteria ....................................................... 3.8-133 3.8.6.5.1 Type I Piping Penetrations ........................................................ 3.8-133 3.8.6.5.2 Types 2 and 3 Piping Penetrations............................................... 3.8-133


LDCN-99-000 3-xxi

3.8.6.5.3 Type 4 Electrical Penetrations and Type 5, 6, and 7 Instrumentation Penetrations .......................................................................... 3.8-133

3.8.6.5.4 Allowable Stresses for Piping, Electrical, and Instrumentation Penetrations .......................................................................... 3.8-133

3.8.6.5.4.1 Electromagnetic Conditions .................................................... 3.8-134 3.8.6.6 Materials, Quality Control, and Special Construction Techniques ........... 3.8-135 3.8.6.6.1 Materials.............................................................................. 3.8-135 3.8.6.6.2 Quality Control...................................................................... 3.8-135 3.8.6.6.3 Special Construction Techniques................................................. 3.8-136 3.8.6.7 Testing and Inservice Inspection Requirements .................................. 3.8-136 3.8.6.7.1 Inspection of Material and Parts for Fabrication .............................. 3.8-136 3.8.6.7.2 Shop Hydrostatic Testing.......................................................... 3.8-136 3.8.6.7.3 Shop Tests on Electrical Penetration Assemblies ............................. 3.8-136 3.8.6.7.4 Field Tests on Electrical Penetration Assemblies ............................. 3.8-139 3.8.6.7.5 Testing of Penetrations After Erected ........................................... 3.8-139 3.8.6.7.6 Tests on Penetration Field Welds ................................................ 3.8-139 3.8.6.7.7 Preoperational Leakage Rate Tests and Periodic Leakage Rate Tests ..... 3.8-139 3.8.7 REFERENCES........................................................................... 3.8-140 3.9 MECHANICAL SYSTEMS AND COMPONENTS ................................ 3.9-1 3.9.1 SPECIAL TOPICS FOR MECHANICAL COMPONENTS .................... 3.9-1 3.9.1.1 Design Transients ..................................................................... 3.9-1 3.9.1.1.1 Control Rod Drive Transients .................................................... 3.9-1 3.9.1.1.2 Control Rod Drive Housing and In-Core Housing Transients .............. 3.9-2 3.9.1.1.3 Hydraulic Control Unit Transients............................................... 3.9-3 3.9.1.1.4 Core Support and Reactor Internals Transients................................ 3.9-3 3.9.1.1.5 Nuclear Steam Supply System Scope Main Steam System Transients..... 3.9-3 3.9.1.1.6 Recirculation System Transients ................................................. 3.9-4 3.9.1.1.7 Reactor Assembly Transients ..................................................... 3.9-5 3.9.1.1.8 Main Steam Isolation Valve Transients ......................................... 3.9-5 3.9.1.1.9 Main Steam Safety/Relief Valve Transients.................................... 3.9-7 3.9.1.1.10 Recirculation Flow Control Valve Transients ................................ 3.9-8 3.9.1.1.11 Recirculation Pump Transients.................................................. 3.9-9 3.9.1.1.12 Recirculation Gate Valve Transients ........................................... 3.9-10 3.9.1.1.13 Balance-of-Plant Transients...................................................... 3.9-11


LDCN-99-000 3-xxii

3.9.1.2 Nuclear Steam Supply System Computer Programs Used in Original Analysis ................................................................................. 3.9-11

3.9.1.2.1 Reactor Pressure Vessel and Internals .......................................... 3.9-12 3.9.1.2.1.1 Reactor Pressure Vessel......................................................... 3.9-12 3.9.1.2.1.1.1 CB&I Program 7-11 - “GENOZZ” ......................................... 3.9-12 3.9.1.2.1.1.2 CB&I Program 9-48 - “NAPALM” ......................................... 3.9-13 3.9.1.2.1.1.3 CB&I Program 1027 .......................................................... 3.9-13 3.9.1.2.1.1.4 CB&I Program 846............................................................ 3.9-13 3.9.1.2.1.1.5 CB&I Program 781 - “KALNINS”.......................................... 3.9-13 3.9.1.2.1.1.6 CB&I Program 979 - “ASFAST”............................................ 3.9-14 3.9.1.2.1.1.7 CB&I Program 766 - “TEMAPR” .......................................... 3.9-14 3.9.1.2.1.1.8 CB&I Program 767 - “PRINCESS” ........................................ 3.9-14 3.9.1.2.1.1.9 CB&I Program 928 - “TGRV” .............................................. 3.9-14 3.9.1.2.1.1.10 CB&I Program 962 - “E0962A”........................................... 3.9-14 3.9.1.2.1.1.11 CB&I Program 984 .......................................................... 3.9-15 3.9.1.2.1.1.12 CB&I Program 992 - “GASP” ............................................. 3.9-15 3.9.1.2.1.1.13 CB&I Program 1037 - “DUNHAM’S” ................................... 3.9-15 3.9.1.2.1.1.14 CB&I Program 1335......................................................... 3.9-16 3.9.1.2.1.1.15 CB&I Programs 1606 and 1657 - “HAP” ............................... 3.9-16 3.9.1.2.1.1.16 CB&I Program 1635......................................................... 3.9-16 3.9.1.2.1.1.17 CB&I Program 953 .......................................................... 3.9-16 3.9.1.2.1.1.18 CB&I Program 955 - “MESHPLOT”..................................... 3.9-16 3.9.1.2.1.1.19 CB&I Program 1028......................................................... 3.9-17 3.9.1.2.1.1.20 CB&I Program 1038......................................................... 3.9-17 3.9.1.2.1.2 Reactor Internals ................................................................. 3.9-17 3.9.1.2.2 Nuclear Steam Supply System Piping............................................ 3.9-17 3.9.1.2.2.1 Piping Analysis Program/PISYS ............................................... 3.9-17 3.9.1.2.2.2 Component Analysis/ANSI7..................................................... 3.9-17 3.9.1.2.2.3 Relief Valve Discharge Pipe Forces Computer Program/RVFOR........ 3.9-17 3.9.1.2.2.4 Turbine Stop Valve Closure/TSFOR........................................... 3.9-18 3.9.1.2.2.5 Integral Attachment/LUGST .................................................... 3.9-18 3.9.1.2.2.6 Piping Dynamic Analysis Program/PDA ..................................... 3.9-18 3.9.1.2.3 Recirculation Pump................................................................. 3.9-18 3.9.1.2.4 Emergency Core Cooling System Pumps and Motors......................... 3.9-18 3.9.1.2.4.1 Rotor Assembly Analysis Program/RTRMEC................................ 3.9-18


LDCN-99-000 3-xxiii

3.9.1.2.4.2 Structural Analysis Program/SAP4G.......................................... 3.9-19 3.9.1.2.4.3 Effects of Flange Joint Connections/FTFLG01.............................. 3.9-19 3.9.1.2.4.4 Structural Analysis of Discharge Head/ANSYS. ............................ 3.9-19 3.9.1.2.4.5 Beam Element Data Processing/POSUM .................................... 3.9-19 3.9.1.2.5 Residual Heat Removal Heat Exchangers ...................................... 3.9-19 3.9.1.2.5.1 Structural Analysis Program/SAP4G.......................................... 3.9-19 3.9.1.2.5.2 Local Stiffness Calculations/BSTIF01......................................... 3.9-19 3.9.1.2.5.3 Calculation of Shell Attachment Parameters and Coefficients/BILRD. . 3.9-20 3.9.1.2.5.4 Beam Element Data Processing/POSUM .................................... 3.9-20 3.9.1.2.6 Dynamic Loads Analysis........................................................... 3.9-20 3.9.1.2.6.1 Dynamic Analysis Program/DYSEA........................................... 3.9-20 3.9.1.2.6.2 Acceleration Response Spectrum Program/SPECA......................... 3.9-20 3.9.1.2.6.3 Fuel Support Loads Program/SEISM ......................................... 3.9-20 3.9.1.2.7 Balance-of-Plant Computer Programs .......................................... 3.9-20 3.9.1.2.7.1 S/RVDAM4 ........................................................................ 3.9-20 3.9.1.3 Experimental Stress Analysis........................................................ 3.9-21 3.9.1.3.1 Experimental Stress Analysis of Piping Components......................... 3.9-22 3.9.1.3.2 Orificed Fuel Support, Vertical, and Horizontal Load Tests................ 3.9-22 3.9.1.4 Considerations for the Evaluation of Faulted Conditions....................... 3.9-22 3.9.1.4.1 Control Rod Drive System Components ........................................ 3.9-22 3.9.1.4.1.1 Control Rod Drives .............................................................. 3.9-22 3.9.1.4.1.2 Hydraulic Control Unit.......................................................... 3.9-23 3.9.1.4.1.3 Control Rod Drive Housing .................................................... 3.9-23 3.9.1.4.2 Standard Reactor Internal Components ......................................... 3.9-23 3.9.1.4.2.1 Control Rod Guide Tube........................................................ 3.9-23 3.9.1.4.2.2 Jet Pump ........................................................................... 3.9-23 3.9.1.4.2.3 Low-Pressure Coolant Injection Coupling ................................... 3.9-23 3.9.1.4.2.4 Orificed Fuel Support............................................................ 3.9-23 3.9.1.4.3 Reactor Pressure Vessel Assembly .............................................. 3.9-24 3.9.1.4.4 Core Structure ....................................................................... 3.9-24 3.9.1.4.5 Main Steam Isolation, Recirculation Gate, and Safety/Relief Valves ..... 3.9-24 3.9.1.4.6 Recirculation System Flow Control Valve ..................................... 3.9-24 3.9.1.4.7 Main Steam and Recirculation Piping ........................................... 3.9-24 3.9.1.4.8 Nuclear Steam Supply System Pumps, Heat Exchangers, and Turbine ... 3.9-24 3.9.1.4.9 Control Rod Drive Housing Supports ........................................... 3.9-25


LDCN-99-000 3-xxiv

3.9.1.4.10 Fuel Storage Racks................................................................ 3.9-25 3.9.1.4.11 Fuel Assembly Including Channels............................................. 3.9-25 3.9.1.4.12 Refueling Equipment ............................................................. 3.9-25 3.9.1.4.13 Balance-of-Plant Equipment ..................................................... 3.9-25 3.9.2 DYNAMIC TESTING AND ANALYSIS .......................................... 3.9-26 3.9.2.1 Preoperational Vibration and Dynamic Effects Testing on Piping............ 3.9-26 3.9.2.1.1 Preoperational Vibration Testing ................................................ 3.9-26 3.9.2.1.2 Small Attached Piping.............................................................. 3.9-26 3.9.2.1.3 Startup Vibration.................................................................... 3.9-26 3.9.2.1.4 Operating Transient Loads ........................................................ 3.9-27 3.9.2.1.5 Test Evaluation and Acceptance Criteria ....................................... 3.9-27 3.9.2.1.5.1 Level 1 Criterion ................................................................. 3.9-28 3.9.2.1.5.2 Level 2 Criterion ................................................................. 3.9-28 3.9.2.1.6 Corrective Actions .................................................................. 3.9-28 3.9.2.1.7 Measurement Locations............................................................ 3.9-29 3.9.2.2 Seismic and Hydrodynamic Loads Qualification of Safety-Related

Mechanical Equipment................................................................ 3.9-29 3.9.2.2.1 Test and Analysis Criteria and Methods ........................................ 3.9-30 3.9.2.2.1.1 Random Vibration Input. ....................................................... 3.9-32 3.9.2.2.1.2 Application of Input Motion.................................................... 3.9-32 3.9.2.2.1.3 Fixture Design .................................................................... 3.9-32 3.9.2.2.1.4 Prototype Testing................................................................. 3.9-32 3.9.2.2.2 Seismic and Hydrodynamic Load Qualification of Specific

Nuclear Steam Supply System Mechanical Components .................... 3.9-32 3.9.2.2.2.1 Jet Pumps .......................................................................... 3.9-32 3.9.2.2.2.2 Control Rod Drive and Control Rod Drive Housing....................... 3.9-32 3.9.2.2.2.3 Core Support (Orificed Fuel Support and Control Rod Guide Tube) ... 3.9-32 3.9.2.2.2.4 Hydraulic Control Unit.......................................................... 3.9-32 3.9.2.2.2.5 Fuel Assembly Including Channels ........................................... 3.9-33 3.9.2.2.2.6 Recirculation Pump and Motor Assembly ................................... 3.9-33 3.9.2.2.2.7 Emergency Core Cooling System Pumps and Motors Assembly ........ 3.9-33 3.9.2.2.2.8 Reactor Core Isolation Cooling Pump Assembly ........................... 3.9-33 3.9.2.2.2.9 Reactor Core Isolation Cooling Turbine Assembly ........................ 3.9-33 3.9.2.2.2.10 Standby Liquid Control Pump and Motor Assembly ..................... 3.9-33 3.9.2.2.2.11 Residual Heat Removal Heat Exchangers .................................. 3.9-33


LDCN-00-099 3-xxv

3.9.2.2.2.12 Standby Liquid Control Tank................................................. 3.9-34 3.9.2.2.2.13 Main Steam Isolation Valves.................................................. 3.9-34 3.9.2.2.2.14 Main Steam Safety/Relief Valves ............................................ 3.9-34 3.9.2.2.2.15 Fuel Pool Cooling and Cleanup System .................................... 3.9-34 3.9.2.2.3 Balance-of-Plant Safety-Related Mechanical Equipment..................... 3.9-34 3.9.2.2.4 Suppression Pool Hydrodynamic Loads Qualification of

Safety-Related Equipment.......................................................... 3.9-35 3.9.2.3 Dynamic Response of Reactor Internals Under Operational Flow

Transients and Steady-State Conditions........................................... 3.9-35 3.9.2.4 Confirmatory Flow-Induced Vibration Testing of Reactor Internals.......... 3.9-36 3.9.2.5 Dynamic System Analysis of the Reactor Internals Under Faulted

Conditions............................................................................... 3.9-37 3.9.2.6 Correlations of Reactor Internals Vibration Tests With the Analytical

Results ................................................................................... 3.9-37 3.9.3 ASME CODE CLASS 1, 2, AND 3 COMPONENTS, COMPONENT

SUPPORTS, AND CORE SUPPORT STRUCTURES........................... 3.9-38 3.9.3.1 Loading Combinations, Design Transients, and Stress Limits ................ 3.9-38 3.9.3.1.1 Plant Conditions..................................................................... 3.9-38 3.9.3.1.1.1 Normal Condition (Level A) ................................................... 3.9-38 3.9.3.1.1.2 Upset Condition (Level B)...................................................... 3.9-38 3.9.3.1.1.3 Emergency Condition (Level C)............................................... 3.9-39 3.9.3.1.1.4 Faulted Condition (Level D) ................................................... 3.9-39 3.9.3.1.1.5 Correlation of Plant Conditions with Event Probability ................... 3.9-39 3.9.3.1.1.6 Safety Class Functional Criteria ............................................... 3.9-40 3.9.3.1.1.7 Compliance with Regulatory Guide 1.48..................................... 3.9-40 3.9.3.1.2 Reactor Pressure Vessel Assembly .............................................. 3.9-42 3.9.3.1.3 Main Steam Piping ................................................................. 3.9-43 3.9.3.1.4 Recirculation Loop Piping......................................................... 3.9-43 3.9.3.1.5 Recirculation System Valves...................................................... 3.9-43 3.9.3.1.6 Recirculation Pump................................................................. 3.9-43 3.9.3.1.7 Standby Liquid Control Tank..................................................... 3.9-44 3.9.3.1.8 Residual Heat Removal Heat Exchangers ...................................... 3.9-44 3.9.3.1.9 Reactor Core Isolation Cooling Turbine ........................................ 3.9-44 3.9.3.1.10 Reactor Core Isolation Cooling Pump ......................................... 3.9-44 3.9.3.1.11 Emergency Core Cooling System Pumps ..................................... 3.9-45


3-xxvi

3.9.3.1.12 Standby Liquid Control Pump .................................................. 3.9-45 3.9.3.1.13 Safety/Relief Valves and Main Steam Isolation Valves..................... 3.9-45 3.9.3.1.14 Safety/Relief Valve Discharge Piping ......................................... 3.9-45 3.9.3.1.14.1 Main Steam Safety/Relief Valve Piping .................................... 3.9-45 3.9.3.1.14.2 Residual Heat Removal Suction Shutdown Thermal Relief

Valve Piping ..................................................................... 3.9-45 3.9.3.1.15 Reactor Water Cleanup System Pump and Heat Exchangers .............. 3.9-45 3.9.3.1.16 Fuel Pool Cooling and Cleanup System Heat Exchangers

and Pumps .......................................................................... 3.9-46 3.9.3.1.17 Control Rod Drive Piping ....................................................... 3.9-46 3.9.3.1.18 Balance-of-Plant Piping ..............................

design criteria - structures, components ...columbia generating station amendment 58 final safety...

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