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Construction Control 982.5.4.5.2Granular Fill2.5-98 General 98 | Construction Control 982.5.4.5.2Granular Fill2.5-98 General 98 | ||
Section 1032 Material 98 Section 1075 Material 1002.5.4.6Groundwater Conditions2.5-101 2.5.4.7Response of Soil and Rock to Dynamic Loading2.5-1032.5.4.8Liquefaction Potential2.5-1032.5.4.9Earthquake Design Basis2.5-113 2.5.4.10Static Analysis2.5-1132.5.4.10.1Settlement2.5-1132.5.4.10.2Bearing Capacity2.5-114 2.5.4.11Safety-Related Criteria for Foundations2.5-1152.5.4.11.1General2.5-1152.5.4.11.2Rock Strength2.5-1152.5.4.11.3Soil Strength2.5-1152.5.4.12Techniques to Improve Subsurface Conditions2.5-1152.5.4.13Construction Notes2.5-1182.5.5Stability of Slopes2.5-1182.5.5.1Slope Characteristics2.5-118 1-xlivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.5.5.1.1Essential Raw Cooling Water Intake Channel Slopes2.5-1182.5.5.1.2Underground Barrier for Protection Ag ainst Potential Soil Liquefaction 2.5-1182.5.5.2Design Criteria and Analysis2.5-1202.5.5.2.1Design Criteria and Analyses for the Essential Raw Coolant Water2.5-1202.5.5.2.2Additional Analyses Due to Unexp ected Soil Conditions Encountered During Excavation of the Intake Channel2.5-1232.5.5.2.3Design Criteria and Analysis for the Underground Barrier for the ERCW Pipeline and 1E Conduit Alignment2.5-1252.5.5.3Logs of Borings2.5-1272.5.5.4Compaction Specifications2.5-127 2.5.6Embankments2.5-1273.0DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.1CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA3.1-13.1.1Introduction3.1-13.1.2WBNP Conformance with GDCs3.1-1 3.1.2.1Overall Requirements3.1-13.1.2.2Protection By Multiple Fission Product Barriers3.1-53.1.2.3Protection and Reactivity Control Systems3.1-123.1.2.4Fluid Systems3.1-173.1.2.5Reactor Containment3.1-303.1.2.6Fuel and Radioactivity Control3.1-353.2CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS3.2-1 | Section 1032 Material 98 Section 1075 Material 1002.5.4.6Groundwater Conditions2.5-101 2.5.4.7Response of Soil and Rock to Dynamic Loading2.5-1032.5.4.8Liquefaction Potential2.5-1032.5.4.9Earthquake Design Basis2.5-113 2.5.4.10Static Analysis2.5-1132.5.4.10.1Settlement2.5-1132.5.4.10.2Bearing Capacity2.5-114 2.5.4.11Safety-Related Criteria for Foundations2.5-1152.5.4.11.1General2.5-1152.5.4.11.2Rock Strength2.5-1152.5.4.11.3Soil Strength2.5-1152.5.4.12Techniques to Improve Subsurface Conditions2.5-1152.5.4.13Construction Notes2.5-1182.5.5Stability of Slopes2.5-1182.5.5.1Slope Characteristics2.5-118 1-xlivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.5.5.1.1Essential Raw Cooling Water Intake Channel Slopes2.5-1182.5.5.1.2Underground Barrier for Protection Ag ainst Potential Soil Liquefaction 2.5-1182.5.5.2Design Criteria and Analysis2.5-1202.5.5.2.1Design Criteria and Analyses for the Essential Raw Coolant Water2.5-1202.5.5.2.2Additional Analyses Due to Unexp ected Soil Conditions Encountered During Excavation of the Intake Channel2.5-1232.5.5.2.3Design Criteria and Analysis for the Underground Barrier for the ERCW Pipeline and 1E Conduit Alignment2.5-1252.5.5.3Logs of Borings2.5-1272.5.5.4Compaction Specifications2.5-127 2.5.6Embankments2.5-1273.0DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.1CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA3.1-13.1.1Introduction3.1-13.1.2WBNP Conformance with GDCs3.1-1 3.1.2.1Overall Requirements3.1-13.1.2.2Protection By Multiple Fission Product Barriers3.1-53.1.2.3Protection and Reactivity Control Systems3.1-123.1.2.4Fluid Systems3.1-173.1.2.5Reactor Containment3.1-303.1.2.6Fuel and Radioactivity Control3.1-353.2CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS3.2-1 3.2.1 Seismic Classifications 3.2-13.2.2System Quality Group Classification3.2-13.2.2.1Class A3.2-23.2.2.2Class B3.2-23.2.2.3Class C3.2-2 3.2.2.4Class D3.2-23.2.2.5Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents 3.2-33.2.2.6Nonnuclear Safety Class (NNS)3.2-33.2.2.7Heating, Ventilation and Air Conditioning (HVAC) Safety Classification3.2-33.2.3Code Cases and Code Editions and Addenda3.2-33.2.3.1TVA Design and Fabrication3.2-33.2.3.2Purchased Materials and Components3.2-43.3Wind and Tornado Loading3.3-13.3.1Wind Loadings3.3-13.3.1.1Design Wind Velocity3.3-1 Table of Contents1-xlvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.3.1.2Determination of Applied Force3.3-13.3.2Tornado Loadings3.3-13.3.2.1Applicable Design Parameters3.3-13.3.2.2Determination of Forces on Structures3.3-23.3.2.3Ability of Category I Structures to Pe rform Despite Failure of Structures Not Designed for Tornado Loads3.3-33.4WATER LEVEL (FLOOD) DESIGN3.4-13.4.1Flood Protection3.4-1 3.4.2Analysis Procedure3.4-13.5MISSILE PROTECTION3.5-13.5.1Missile Selection and Description3.5-23.5.1.1Internally Generated Missiles (Outside Containment)3.5-23.5.1.1.1Shield Building3.5-23.5.1.1.2North and South Steam Valve Rooms3.5-23.5.1.1.3Auxiliary Building3.5-3 3.5.1.1.4Control Building3.5-43.5.1.1.5ERCW Structures3.5-43.5.1.1.6ERCW Pipe Tunnels and RWST Foundations3.5-43.5.1.1.7Diesel Generator Building3.5-43.5.1.2Internally Generated Missiles (Inside Containment)3.5-53.5.1.2.1Missile Selection3.5-53.5.1.2.2Missile Description3.5-73.5.1.2.3Electrical Cables3.5-83.5.1.2.4Upper Compartment3.5-8 3.5.1.2.5Ice Condenser Compartment3.5-83.5.1.2.6Lower Compartment3.5-83.5.1.3Turbine Missiles3.5-9 3.5.1.3.1Introduction3.5-93.5.1.3.2Potential Missile Sources and Missile Characteristics3.5-103.5.1.3.3Primary Safety-Related Equipment Installations and Structures3.5-153.5.1.3.4Turbine Missile Protection Criterion3.5-153.5.1.3.5Turbine Missile Hazard Evaluation3.5-163.5.1.3.6Turbine Missile Selection3.5-223.5.1.4Missiles Generated By Natural Phenomena3.5-233.5.1.5Missiles Generated by Events Near the Site.3.5-233.5.1.6Aircraft Hazards3.5-243.5.2Systems To Be Protected3.5-243.5.3Barrier Design Procedures3.5-25 3.5.3.1Additional Diesel Generator Building (And Other Category I Structures Added After July 1979)3.5-283.5.AESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES3.5-1 1-xlviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.6PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-13.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WI TH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING)3.6-13.6A.1Postulated Piping Failures in Fluid Systems Inside and Outside Containment3.6-83.6A.1.1Design Bases3.6-8 3.6A.1.1.1List of Potential Targets3.6-83.6A.1.1.2Interaction Criteria3.6-83.6A.1.1.3Acceptability Criteria3.6-9 3.6A.1.1.4Protective Measures3.6-103.6A.1.2Description of Piping System Arrangement3.6-103.6A.1.3Safety Evaluation3.6-10 3.6A.2Determination of Break Lo cations and Dynamic Effects Associated with the Postu-lated Rupture of Piping3.6-113.6A.2.1Criteria Used to Define Break and Crack Location and Configuration3.6-113.6A.2.1.1Pipe Failure Type, Size, and Orientation3.6-113.6A.2.1.2Break Location3.6-123.6A.2.1.3Failure Consequences3.6-15 3.6A.2.1.4Flooding3.6-163.6A.2.1.5Leak-Before-Break Application3.6-173.6A.2.2Analytical Methods to Define Forcing Functions and Response Models3.6-173.6A.2.2.1Assumptions3.6-173.6A.2.2.2Blowdown Thrust Loads3.6-173.6A.2.2.3Jet Impingement Loads3.6-19 3.6A.2.3Dynamic Analysis Methods to Verify Integrity and Operability3.6-213.6A.2.3.1General Criteria for Pipe Whip Evaluation3.6-213.6A.2.3.2Main Reactor Coolant Loop Piping System3.6-213.6A.2.3.3Other Piping Systems3.6-213.6A.2.3.4Simplified Pipe Whip Analysis3.6-223.6A.2.3.5Pipe Whip Restraint Design3.6-23 3.6A.2.3.6Energy Absorbing Materials 3.6-243.6A.2.4Guard Pipe Assembly Design Criteria3.6-243.6A.2.5Summary of Dynamic Analysis Results3.6-253.6A.2.5.1Stress Summary and Isometrics - Inside Containment3.6-253.6A.2.5.2Summary of Protection Requirement s and Isometrics-Outside Contain-ment3.6-263.6BPROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-263.6B.1Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture3.6-26 3.6B.2Analytical Methods to Define Fo rcing Function and Response Models3.6-273.6B.3Dynamic Analysis of the Reactor Cool ant Loop Piping Equipment Supports and Pipe Whip Restraints3.6-29 Table of Contents1-xlviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7SEISMIC DESIGN3.7-13.7.1Seismic Input3.7-23.7.1.1Ground Response Spectra3.7-23.7.1.1.1Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.1.2Site Specific Ground Response Spectra (Set B)3.7-23.7.1.2Design Time Histories3.7-2 3.7.1.2.1Time Histories for Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.2.2Time Histories for Site Specific Ground Response Spectra (Set B)3.7-23.7.1.3Critical Damping Values3.7-33.7.1.4Supporting Media for Seismic Category I Structures3.7-33.7.2Seismic System Analysis3.7-3 3.7.2.1Seismic Analysis Methods3.7-43.7.2.1.1Category I Rock-Supported Structures - Original Analyses (Set A)3.7-43.7.2.1.2Category I Rock - Supported Struct ures - Evaluation and New Design or Modification Analyses (Set B and Set B+C)3.7-93.7.2.1.3Category I Soil-Supported Structures - Original Analysis (Set A)3.7-133.7.2.1.4Category I Soil-Supported Structures - Evaluation and New Design/Mod-ification Analysis (Set B and Set B+C)3.7-183.7.2.1.5Category I Pile-Supported Structures - Original Analysis (Set A)3.7-193.7.2.1.6Category I Pile-Supported Structures - Evaluation and New Design/Mod-ification Analyses (Set B and Set B+C)3.7-213.7.2.2Natural Frequencies and Response Loads for NSSS3.7-223.7.2.3Procedures Used for Modeling3.7-22 3.7.2.3.1Other Than NSSS3.7-223.7.2.3.2For NSSS Analysis3.7-223.7.2.4Soil/Structure Interaction3.7-23 3.7.2.4.1Original Analysis (Set A)3.7-233.7.2.4.2Evaluation and New Design or Modification Analyses3.7-233.7.2.5Development of Floor Response Spectra3.7-24 3.7.2.5.1Original Analysis3.7-243.7.2.5.2Evaluation and New Design or Modification Analysis3.7-243.7.2.6Three Components of Earthquake Motion3.7-25 3.7.2.6.1Original Analysis (Set A)3.7-253.7.2.6.2Evaluation and New Design/Modifi cation Analyses (Set B and Set C) 3.7-253.7.2.7Combination of Modal Responses3.7-263.7.2.7.1Other Than NSSS3.7-26 Original Analysis (Set A) 26 Evaluation and New Design or Modification Analyses 263.7.2.7.2NSSS System3.7-27 3.7.2.8Interaction of Non-Cate gory I Structures With Seismic Category I Structures 3.7-29 1-xlviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.2.9Effects of Parameter Variations on Floor Response Spectra3.7-293.7.2.10Use of Constant Vertical Load Factors3.7-293.7.2.10.1Other Than NSSS3.7-29 Original Analysis (Set A) 29 Evaluation and New Design or Modification Analyses 303.7.2.10.2For NSSS3.7-30 3.7.2.11Methods Used to Account for Torsional Effects3.7-303.7.2.12Comparison of Responses - Set A versus Set B3.7-303.7.2.13Methods for Seismic Analysis of Dams3.7-31 3.7.2.14Determination of Category I Structure Overturning Moments3.7-313.7.2.14.1Original Analysis3.7-313.7.2.14.2Evaluation and New Design or Modification Analysis3.7-313.7.2.15Analysis Procedure for Damping3.7-313.7.3Seismic Subsystem Analysis3.7-313.7.3.1Seismic Analysis Methods for Other Than NSSS3.7-31 3.7.3.2Determination of Number of Earthquake Cycles3.7-323.7.3.2.1Category I Systems and Components Other Than NSSS3.7-323.7.3.2.2NSSS System3.7-33 3.7.3.3Procedure Used for Modeling3.7-333.7.3.3.1Other Than NSSS3.7-33 Modeling of Piping Systems for Detailed Rigorous Analysis 33 Modeling of Equipment 33 Modeling of HVAC, Conduit, a nd Cable Tray Subsystems 333.7.3.3.2Modeling of NSSS Subsystems3.7-34 3.7.3.4Basis for Selection of Frequencies3.7-343.7.3.4.1Other Than NSSS3.7-343.7.3.4.2NSSS Basis for Selection of Forcing Frequencies3.7-343.7.3.5Use of Equivalent Static Load Method of Analysis3.7-353.7.3.5.1Other Than NSSS3.7-353.7.3.5.2Use of Equivalent Static Load Method of Analysis for NSSS3.7-363.7.3.6Three Components of Earthquake Motion3.7-363.7.3.6.1Piping Subsystems3.7-363.7.3.6.2HVAC Ducting, Conduit, and Cable Tray Subsystems3.7-363.7.3.6.3Other Than NSSS Equipment and Components3.7-363.7.3.7Combination of Modal Responses3.7-373.7.3.7.1Other Than NSSS3.7-37 3.7.3.7.2Combination of Modal Responses of NSSS3.7-373.7.3.8Analytical Procedures for Piping Other Than NSSS3.7-373.7.3.8.1General3.7-373.7.3.8.2Detailed Seismic Analysis (Rigorous) for Piping Systems3.7-413.7.3.8.3Alternate (Simplified) Analysis for Piping Systems3.7-433.7.3.8.4Seismic Analysis of Piping Systems That Span Two or More Seismic Sup-port Zones Such as Buildings, Porti ons of Buildings, or Primary Compo-nents3.7-44 Table of Contents1-xlixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.3.9Multiple Supported Equipment and Components with Distinct Inputs3.7-443.7.3.9.1Other Than NSSS3.7-443.7.3.9.2Multiple Supported NSSS Equipment a nd Components with Distinct In-puts3.7-443.7.3.10Use of Constant Vertical Load Factors3.7-453.7.3.10.1Use of Constant Load Factors for Equipment Other Than NSSS3.7-453.7.3.10.2Use of Constant Vertical Load Factors for NSSS3.7-453.7.3.11Torsional Effects of Eccentric Masses3.7-453.7.3.11.1Piping Other Than NSSS3.7-45 3.7.3.11.2Torsional Effects of Eccentric Masses of NSSS3.7-463.7.3.12Buried Seismic Category I Piping Systems3.7-463.7.3.13Interaction of Other Piping with Seismic Category I Piping3.7-523.7.3.14Seismic Analyses for Fuel Elements , Control Rod Assemblies, Control Rod Drives, and Reactor Internals3.7-523.7.3.15Analysis Procedure for Damping3.7-54 3.7.3.16Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-543.7.3.16.1Dynamic Analysis Method For Equipment and Components3.7-553.7.3.16.2Simplified Dynamic Analysis Method For Equipment and Components 3.7-553.7.3.16.3Equivalent Static Load Method3.7-56 3.7.3.16.4Testing Method3.7-563.7.3.16.5Equipment and Component Mounting Considerations3.7-563.7.3.17Seismic Analysis and Design of HVAC Duct and Duct Support Systems3.7-573.7.3.17.1Description of HVAC Duct and Duct Support Subsystems3.7-573.7.3.17.2Applicable Codes, Standards, and Specifications3.7-573.7.3.17.3Loads and Load Combinations3.7-583.7.3.17.4Analysis and Design Procedures3.7-593.7.3.17.5Structural Acceptance Criteria3.7-59 3.7.3.17.6Materials and Quality Control3.7-603.7.3.18Seismic Qualification of Main Control Room Suspended Ceiling and Air Deliv-ery Components3.7-61 3.7.4Seismic Instrumentation Program3.7-613.7.4.1Comparison with Regulatory Guide 1.123.7-613.7.4.2Location and Description of Instrumentation3.7-613.7.4.3Control Room Operator Notification3.7-643.7.4.4Controlled Shutdown Logic3.7-643.7.4.5Comparison of Measured and Predicted Responses3.7-653.7.4.5.1Retrieval of Data3.7-653.7.4.5.2Evaluation of Recorded Earthquake3.7-663.8DESIGN OF CATEGORY I STRUCTURES3.8-13.8.1Concrete Shield Building3.8-1 1-lTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.1.1Description of the Shield Building3.8-13.8.1.1.1Equipment Hatch Doors and Sleeves3.8-23.8.1.2Applicable Codes, Standards, and Specifications3.8-33.8.1.3Loads and Loading Combinations3.8-53.8.1.4Design and Analysis Procedures3.8-73.8.1.5Structural Acceptance Criteria3.8-10 3.8.1.6Materials, Quality Control and Special Construction Techniques3.8-113.8.1.6.1Materials3.8-113.8.1.6.2Quality Control3.8-12 3.8.1.6.3Construction Techniques3.8-133.8.2Testing and Inservice Surveillance Requirements3.8-133.8.2Steel Containment System3.8-13.8.2.1Description of the Containment and Penetrations3.8-13.8.2.1.1Description of the Containment3.8-13.8.2.1.2Description of Penetrations3.8-1 3.8.2.2Applicable Codes, Standards and Specifications3.8-33.8.2.2.1Codes3.8-33.8.2.2.2Design Specification Summary3.8-4 3.8.2.2.3NRC Regulatory Guides3.8-63.8.2.3Loads and Loading Combinations3.8-73.8.2.3.1Design Loads3.8-7 3.8.2.3.2Loading Conditions3.8-93.8.2.4 Design and Analysis Procedures3.8-113.8.2.4.1Introduction3.8-11 3.8.2.4.2Static Stress Analysis3.8-123.8.2.4.3Dynamic Seismic Analysis3.8-123.8.2.4.4Non-Axisymmetric Pressure Loading Analysis3.8-133.8.2.4.5Thermal Analysis3.8-143.8.2.4.6Penetrations Analysis3.8-143.8.2.4.7Interaction of Containment and Attached Equipment3.8-163.8.2.4.8Anchorage3.8-173.8.2.5Structural Acceptance Criteria3.8-183.8.2.5.1Margin of Safety3.8-18 3.8.2.6Materials, Quality Control, and Special Construction Techniques3.8-183.8.2.6.1Materials - General3.8-183.8.2.6.2Corrosion Protection3.8-21 3.8.2.6.3Protective Coatings3.8-233.8.2.6.4Tolerances3.8-243.8.2.6.5Vessel Material Inspection and Test3.8-243.8.2.6.6Impact Testing3.8-253.8.2.6.7Post-Weld Heat Treatment3.8-253.8.2.6.8Welding3.8-253.8.2.7Testing and Inservice Inspection Requirements3.8-25 Table of Contents 1-liWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.2.7.1Bottom Liner Plates Test3.8-253.8.2.7.2Vertical Wall and Dome Tests3.8-253.8.2.7.3Soap Bubble Tests3.8-253.8.2.7.4Overpressure Tests3.8-263.8.2.7.5Leakage Rate Test3.8-263.8.2.7.6Operational Testing3.8-263.8.2.7.7Leak Testing Airlocks3.8-263.8.2.7.8Penetration Tests3.8-273.8.2.7.9Inservice Inspection Requirements3.8-273.8.3Concrete Interior Structure3.8-13.8.3.1Description of the Interior Structure3.8-13.8.3.2General3.8-1 3.8.3.3Containment Floor Structural Fill Slab3.8-13.8.3.4Reactor Cavity Wall3.8-23.8.3.5Compartment Above Reactor3.8-2 3.8.3.6Refueling Canal Walls and Floor (Divider Barrier)3.8-33.8.3.7Crane Wall3.8-33.8.3.8Steam Generator Compartments (Divider Barrier)3.8-5 3.8.3.9Pressurizer Compartment (Divider Barrier)3.8-53.8.3.10Divider Deck at Elevation 756.63 (Divider Barrier)3.8-53.8.3.11Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier)3.8-53.8.3.12Penetrations Through the Divider Barrier Canal Gate3.8-63.8.3.13Applicable Codes, Standards and Specifications3.8-73.8.3.14Loads and Loading Combinations3.8-13 3.8.3.15Design and Analysis Procedures3.8-163.8.3.16General3.8-163.8.3.17Structural Fill Slab on Containment Floor3.8-163.8.3.18Reactor Cavity Wall3.8-163.8.3.19Compartment Above Reactor3.8-183.8.3.20Seals Between Upper and Lower Compartments3.8-183.8.3.21Refueling Canal Walls and Floor (Divider Barrier)3.8-193.8.3.22Crane Wall3.8-203.8.3.23Steam Generator Compartments (Divider Barrier)3.8-23 3.8.3.24Pressurizer Compartment (Divider Barrier)3.8-253.8.3.25Operating Deck at Elevation 756.63 (Divider Barrier)3.8-263.8.3.26Ice Condenser Support Floor El evation 744.5 (Divider Barrier)3.8-273.8.3.27Ice Condenser3.8-283.8.3.28Penetrations Through the Divider Barrier3.8-293.8.3.29Structural Acceptance Criteria3.8-313.8.3.30General3.8-313.8.3.31Structural Fill Slab on Containment Floor3.8-313.8.3.32Reactor Cavity Wall and Compartment Above Reactor3.8-313.8.3.33Refueling Canal Walls and Floor3.8-32 1-liiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.3.34Crane Wall3.8-323.8.3.35Steam Generator and Pressurizer Compartment3.8-323.8.3.36Operating Deck at Elevation 756.633.8-323.8.3.37Ice Condenser Support Floor Elevation 744.53.8-323.8.3.38Penetrations Through the Divider Barrier3.8-323.8.3.39Personnel Access Doors in Crane Wall3.8-333.8.3.40Seals Between Upper and Lower Compartments3.8-333.8.3.41Ice Condenser3.8-333.8.3.42Materials, Quality Control and Special Construction Techniques3.8-343.8.3.43Materials3.8-343.8.3.44Quality Control3.8-353.8.3.45Construction Technique3.8-36 3.8.3.46Ice Condenser3.8-363.8.3.47Testing and Inservice Surveillance Requirements3.8-383.8.3.48Environmental Effects3.8-38 3.8.3.49Interface Control 3.8-393.8.4Other Category I Structures3.8-13.8.4.1Description of the Structures3.8-1 3.8.4.2Auxiliary-Control Building3.8-13.8.4.3Diesel Generator Building3.8-103.8.4.4Category I Water Tanks and Pipe Tunnels3.8-12 3.8.4.5Class 1E Electrical System Manholes and Duct Runs3.8-133.8.4.6North Steam Valve Room3.8-133.8.4.7Intake Pumping Station and Retaining Walls3.8-14 3.8.4.8Miscellaneous Essential Raw Cooling Water (ERCW) Structures3.8-153.8.4.9Additional Diesel Generator Building3.8-163.8.4.10Applicable Codes, Standards, and Specifications3.8-173.8.4.11List of Documents3.8-173.8.4.12Basis for Use of the 1963 Edition of ACI 3183.8-193.8.4.13Loads and Loading Combinations3.8-21 3.8.4.14Description of Loads3.8-213.8.4.15Load Combinations and Allowable Stresses3.8-223.8.4.16Design and Analysis Procedures3.8-23 3.8.4.17Auxiliary-Control Building3.8-233.8.4.18Diesel Generator Building3.8-303.8.4.19Category I Water Tanks and Pipe Tunnels3.8-31 3.8.4.20Class 1E Electrical System Manholes3.8-313.8.4.21North Steam Valve Room3.8-313.8.4.22Intake Pumping Station and Reta ining Walls Pumping Station3.8-323.8.4.23Miscellaneous ERCW Structures3.8-323.8.4.24Additional Diesel Generator Building3.8-333.8.4.25Structural Acceptance Criteria3.8-353.8.4.26Concrete3.8-35 Table of Contents1-liiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.4.27Structural and Miscellaneous Steel3.8-353.8.4.28Miscellaneous Components of the Auxiliary Building3.8-363.8.4.29Intake Pumping Station Traveling Water Screens3.8-373.8.4.30Diesel Generator Building Doors and Bulkheads3.8-373.8.4.31Additional Diesel Generator Building Missile Barriers3.8-373.8.4.32Materials, Quality Control, and Special Construction Techniques General3.8-373.8.4.33Materials3.8-373.8.4.34Quality Control3.8-383.8.4.35Special Construction Techniques3.8-383.8.4.36Testing and Inservice Surveillance Requirements3.8-383.8.4.37Concrete and Struct ural Steel Portions of Structures3.8-383.8.4.38Miscellaneous Components of Auxiliary-Control Building3.8-393.8.4.39Deleted by Amendment 793.8-403.8.4.40Miscellaneous Components of the Intake Pumping Station3.8-403.8.5Foundations and Concrete Supports3.8-13.8.5.1Description of Foundations and Supports3.8-13.8.5.1.1Primary Containment3.8-13.8.5.1.2Foundations of Other Category I Structures3.8-13.8.5.2Applicable Codes, Standards, and Specifications3.8-33.8.5.3Loads and Loading Combinations3.8-33.8.5.4Design and Analysis Procedure3.8-4 3.8.5.4.1Primary Containment Foundation3.8-43.8.5.4.2Auxiliary-Control Building3.8-43.8.5.4.3Intake Pumping Station3.8-4 3.8.5.4.4Soil-Supported Structures3.8-43.8.5.4.5Pile Supported Structures3.8-53.8.5.5Structural Acceptance Criteria3.8-53.8.5.5.1Primary Containment Foundation3.8-53.8.5.5.2Foundations of Other Category I Structures Auxiliary-Control Building3.8-53.8.5.6Materials, Quality Control, and Special Construction Techniques3.8-63.8.5.6.1Materials3.8-63.8.5.6.2Quality Control3.8-73.8.5.6.3Special Construction Techniques3.8-73.8.6Category I(L) Cranes3.8-13.8.6.1Polar Cranes3.8-13.8.6.1.1Description3.8-13.8.6.1.2Applicable Codes, Standards, and Specifications3.8-13.8.6.1.3Loads, Loading Combinations, and Allowable Stresses3.8-23.8.6.1.4Design and Analysis Procedure3.8-23.8.6.1.5Structural Acceptance Criteria3.8-23.8.6.1.6Materials, Quality Controls, and Special Construction Techniques3.8-33.8.6.1.7Testing and Inservice Surveillance Requirements3.8-3 1-livTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.6.1.8Safety Features3.8-33.8.6.2Auxiliary Building Crane3.8-43.8.6.2.1Description3.8-43.8.6.2.2Applicable Codes, Standards, and Specifications3.8-53.8.6.2.3Loads, Loading Combinations, and Allowable Stresses3.8-53.8.6.2.4Design and Analysis Procedure3.8-5 3.8.6.2.5Structural Acceptance Criteria3.8-63.8.6.2.6Materials, Quality Controls, and Special Construction Techniques3.8-63.8.6.2.7Testing and Inservice Surveillance Requirements3.8-73.8.6.2.8Safety Features3.8-73.8ASHELL TEMPERATURE TRANSIENTS3.8-13.8BBUCKLING STRESS CRITERIA3.8-13.8B.1INTRODUCTION3.8-13.8B.2SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS3.8-13.8B.2.1Circular Cylindrical Shells Under Axial Compression3.8-13.8B.2.2Circular Cylindrical Shells in Circumferential Compression3.8-23.8B.2.3Circular Cylindrical Shells Under Torsion3.8-23.8B.2.4where a is the effective length and b is the circumference of the cylinder. The coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending3.8-33.8B.2.5Circular Cylindrical Shell Under Combined Loads3.8-33.8B.3SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS3.8-53.8B.4SPHERICAL SHELLS3.8-73.8B.2.1The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation:3.8-73.8B.2.2Spherical Shell Under Combined Loads3.8-73.8B.3FACTOR OF SAFETY3.8-83.8CDOCUMENTATION OF CB&I COMPUTER PROGRAMS3.8-13.8C.1INTRODUCTION3.8-1 3.8C.2PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE3.8-13.8C.3PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES3.8-13.8C.4PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS3.8-33.8C.5PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS3.8-33.8C.6PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E13743.8-43.8C.7PROGRAM E1374-SHELL DYNAMIC ANALYSIS3.8-53.8C.7.1Introduction3.8-53.8C.8PROGRAM E1622-LOAD GENERATI ON PREPROCESSOR FOR PROGRAM E1374 3.8-6 Table of Contents1-lvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8C.9PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION3.8-73.8C.10PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS3.8-73.8C.11PROGRAM 119-CHECK of FLANGE DESIGN3.8-73.8C.12PROGRAM 772-NOZZLE REINFORCEMENT CHECK3.8-73.8C.13PROGRAM 1027-WRC 107 STRESS INTEN SITIES AT L OADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WI TH ROUND OR SQUARE ATTACHMENT3.8-83.8C.14PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES3.8-83.8DCOMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS3.8-13.8ECODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 19793.8-13.8E.1Application Codes and Standards3.8-13.8E.2Load Definitions3.8-1 3.8E.3Load Combinations - Concrete3.8-33.8E.4Load Combinations - Structural Steel3.8-53.9MECHANICAL SYSTEMS AND COMPONENTS3.9-13.9.1General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-13.9.1.1Design Transients3.9-1 3.9.1.2Computer Programs Used in Analysis and Design3.9-13.9.1.2.1Other Than NSSS Systems, Components, Equipment, and Supports3.9-13.9.1.2.2Programs Used for Category I Components of NSSS3.9-3 3.9.1.3Experimental Stress Analysis3.9-33.9.1.4Consideration for the Evaluation of the Faulted Condition3.9-33.9.1.4.1Subsystems and Components Analyzed by Westinghouse3.9-33.9.1.4.2Subsystems and Components Analyzed by TVA3.9-33.9.2Dynamic Testing and Analysis3.9-43.9.2.1Preoperational Vibration and Dynamic Effects Testing on Piping3.9-43.9.2.2Seismic Qualification Testing of Safety-Related Mechanical Equipment3.9-63.9.2.3Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions3.9-8 3.9.2.4Preoperational Flow-Induced Vibration Testing of Reactor Internals3.9-103.9.2.5Dynamic System Analysis of the R eactor Internals Under Faulted Conditions 3.9-123.9.2.5.1Evaluation of Reactor Internals fo r Limited Displacement RPV Inlet and Outlet Nozzle Break3.9-173.9.2.6Correlations of Reactor Internals Vibration Tests Wi th the Analytical Results 3.9-193.9.3ASME Code Class 1, 2 and 3 Component s, Component Supports and Core Support Structures 3.9-20 1-lviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.9.3.1Loading Combinations, Design Transients, and Stress Limits3.9-203.9.3.1.1Subsystems and Components Supplied by Westinghouse3.9-20 Plant Conditions and Design Loading Combinations For ASME Code Cla ss 2 and 3 Components Supplied by Westinghouse 21 Design Loading Combinations by Westinghouse 21 Design Stress Limits By Westinghouse 22 3.9.3.1.2Subsystems and Components Analyzed or Specified by TVA3.9-223.9.3.2Pumps and Valve Operability Assurance3.9-273.9.3.2.1Active* ASME Class 1, 2, & 3 Pumps and Valves3.9-27 3.9.3.2.2Operability Assurance3.9-28 Westinghouse Scope of Supply 28 TVA Scope of Supply 33 3.9.3.2.3Criteria For Assuring Functional Adequacy of Active Seismic Category I Fluid System Components (Pumps and Valves) and Associated Essential Auxiliary Equipment3.9-343.9.3.3Design and Installation Details for Mounting of Pressure Relief Devices3.9-393.9.3.4Component Supports3.9-423.9.3.4.1Subsystem and Component Supports Analyzed or Specified by Westing-house3.9-423.9.3.4.2Subsystem and Component Supports Analyzed or Specified by TVA3.9-433.9.4Control Rod System3.9-463.9.4.1Descriptive Information of CRDS3.9-463.9.4.2Applicable CRDS Design Specifications3.9-463.9.4.3Design Loadings, Stress Limits, and Allowable Deformations3.9-463.9.4.4CRDS Performance Assurance Program3.9-473.9.5Reactor Pressure Vessel Internals3.9-473.9.5.1Design Arrangements3.9-473.9.5.2Design Loading Conditions3.9-473.9.5.3Design Loading Categories3.9-47 3.9.5.4Design Basis3.9-473.9.6Inservice Testing of Pumps and Valves3.9-473.10SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIP-MENT3.10-13.10.1Seismic Qualification Criteria3.10-13.10.2Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-63.10.3Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables3.10-63.10.3.1Electrical Equipment and Instrumentation Assemblies3.10-73.10.3.2Cable Trays and Supports3.10-73.10.3.2.1Cable Trays3.10-73.10.3.2.2Supports3.10-7 Table of Contents 1-lviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.10.3.3Conduit and Supports3.10-83.10.3.3.1Conduit3.10-83.10.3.3.2Supports3.10-83.10.3.4Conduit Banks3.10-93.10.4Operating License Review3.10-93.10.4.1TVA Supplied Instrumentation and Electrical Equipment3.10-93.11ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT3.11-13.11.1 Equipment Identification and Environmental Conditions3.11-13.11.1.1Identification of Safety Systems and Justification3.11-13.11.1.2Identification of Equipment in Harsh Environments3.11-13.11.2Environmental Conditions3.11-23.11.2.1Harsh Environment3.11-23.11.2.2Mild Environment3.11-3 3.11.3Electrical Equipment Within the Scope of 10 CFR 50.493.11-43.11.4Qualification Tests and Analyses3.11-43.11.5Qualification Test Results3.11-4 3.11.6Loss of Heating, Ventilating, and Air-Conditioning (HVAC)3.11-43.11.7Estimated Chemical and Radiation Environment3.11-43.11.7.1Chemical Spray3.11-4 3.11.7.2Radiation3.11-53.11.7.2.1Inside Containment3.11-53.11.7.2.2Radiation - Auxiliary Building Spaces3.11-64.0REACTOR4.1 | ||
Classifications 3.2-13.2.2System Quality Group Classification3.2-13.2.2.1Class A3.2-23.2.2.2Class B3.2-23.2.2.3Class C3.2-2 3.2.2.4Class D3.2-23.2.2.5Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents 3.2-33.2.2.6Nonnuclear Safety Class (NNS)3.2-33.2.2.7Heating, Ventilation and Air Conditioning (HVAC) Safety Classification3.2-33.2.3Code Cases and Code Editions and Addenda3.2-33.2.3.1TVA Design and Fabrication3.2-33.2.3.2Purchased Materials and Components3.2-43.3Wind and Tornado Loading3.3-13.3.1Wind Loadings3.3-13.3.1.1Design Wind Velocity3.3-1 Table of Contents1-xlvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.3.1.2Determination of Applied Force3.3-13.3.2Tornado Loadings3.3-13.3.2.1Applicable Design Parameters3.3-13.3.2.2Determination of Forces on Structures3.3-23.3.2.3Ability of Category I Structures to Pe rform Despite Failure of Structures Not Designed for Tornado Loads3.3-33.4WATER LEVEL (FLOOD) DESIGN3.4-13.4.1Flood Protection3.4-1 3.4.2Analysis Procedure3.4-13.5MISSILE PROTECTION3.5-13.5.1Missile Selection and Description3.5-23.5.1.1Internally Generated Missiles (Outside Containment)3.5-23.5.1.1.1Shield Building3.5-23.5.1.1.2North and South Steam Valve Rooms3.5-23.5.1.1.3Auxiliary Building3.5-3 3.5.1.1.4Control Building3.5-43.5.1.1.5ERCW Structures3.5-43.5.1.1.6ERCW Pipe Tunnels and RWST Foundations3.5-43.5.1.1.7Diesel Generator Building3.5-43.5.1.2Internally Generated Missiles (Inside Containment)3.5-53.5.1.2.1Missile Selection3.5-53.5.1.2.2Missile Description3.5-73.5.1.2.3Electrical Cables3.5-83.5.1.2.4Upper Compartment3.5-8 3.5.1.2.5Ice Condenser Compartment3.5-83.5.1.2.6Lower Compartment3.5-83.5.1.3Turbine Missiles3.5-9 3.5.1.3.1Introduction3.5-93.5.1.3.2Potential Missile Sources and Missile Characteristics3.5-103.5.1.3.3Primary Safety-Related Equipment Installations and Structures3.5-153.5.1.3.4Turbine Missile Protection Criterion3.5-153.5.1.3.5Turbine Missile Hazard Evaluation3.5-163.5.1.3.6Turbine Missile Selection3.5-223.5.1.4Missiles Generated By Natural Phenomena3.5-233.5.1.5Missiles Generated by Events Near the Site.3.5-233.5.1.6Aircraft Hazards3.5-243.5.2Systems To Be Protected3.5-243.5.3Barrier Design Procedures3.5-25 3.5.3.1Additional Diesel Generator Building (And Other Category I Structures Added After July 1979)3.5-283.5.AESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES3.5-1 1-xlviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.6PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-13.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WI TH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING)3.6-13.6A.1Postulated Piping Failures in Fluid Systems Inside and Outside Containment3.6-83.6A.1.1Design Bases3.6-8 3.6A.1.1.1List of Potential Targets3.6-83.6A.1.1.2Interaction Criteria3.6-83.6A.1.1.3Acceptability Criteria3.6-9 3.6A.1.1.4Protective Measures3.6-103.6A.1.2Description of Piping System Arrangement3.6-103.6A.1.3Safety Evaluation3.6-10 3.6A.2Determination of Break Lo cations and Dynamic Effects Associated with the Postu-lated Rupture of Piping3.6-113.6A.2.1Criteria Used to Define Break and Crack Location and Configuration3.6-113.6A.2.1.1Pipe Failure Type, Size, and Orientation3.6-113.6A.2.1.2Break Location3.6-123.6A.2.1.3Failure Consequences3.6-15 3.6A.2.1.4Flooding3.6-163.6A.2.1.5Leak-Before-Break Application3.6-173.6A.2.2Analytical Methods to Define Forcing Functions and Response Models3.6-173.6A.2.2.1Assumptions3.6-173.6A.2.2.2Blowdown Thrust Loads3.6-173.6A.2.2.3Jet Impingement Loads3.6-19 3.6A.2.3Dynamic Analysis Methods to Verify Integrity and Operability3.6-213.6A.2.3.1General Criteria for Pipe Whip Evaluation3.6-213.6A.2.3.2Main Reactor Coolant Loop Piping System3.6-213.6A.2.3.3Other Piping Systems3.6-213.6A.2.3.4Simplified Pipe Whip Analysis3.6-223.6A.2.3.5Pipe Whip Restraint Design3.6-23 3.6A.2.3.6Energy Absorbing Materials 3.6-243.6A.2.4Guard Pipe Assembly Design Criteria3.6-243.6A.2.5Summary of Dynamic Analysis Results3.6-253.6A.2.5.1Stress Summary and Isometrics - Inside Containment3.6-253.6A.2.5.2Summary of Protection Requirement s and Isometrics-Outside Contain-ment3.6-263.6BPROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-263.6B.1Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture3.6-26 3.6B.2Analytical Methods to Define Fo rcing Function and Response Models3.6-273.6B.3Dynamic Analysis of the Reactor Cool ant Loop Piping Equipment Supports and Pipe Whip Restraints3.6-29 Table of Contents1-xlviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7SEISMIC DESIGN3.7-13.7.1Seismic Input3.7-23.7.1.1Ground Response Spectra3.7-23.7.1.1.1Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.1.2Site Specific Ground Response Spectra (Set B)3.7-23.7.1.2Design Time Histories3.7-2 3.7.1.2.1Time Histories for Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.2.2Time Histories for Site Specific Ground Response Spectra (Set B)3.7-23.7.1.3Critical Damping Values3.7-33.7.1.4Supporting Media for Seismic Category I Structures3.7-33.7.2Seismic System Analysis3.7-3 3.7.2.1Seismic Analysis Methods3.7-43.7.2.1.1Category I Rock-Supported Structures - Original Analyses (Set A)3.7-43.7.2.1.2Category I Rock - Supported Struct ures - Evaluation and New Design or Modification Analyses (Set B and Set B+C)3.7-93.7.2.1.3Category I Soil-Supported Structures - Original Analysis (Set A)3.7-133.7.2.1.4Category I Soil-Supported Structures - Evaluation and New Design/Mod-ification Analysis (Set B and Set B+C)3.7-183.7.2.1.5Category I Pile-Supported Structures - Original Analysis (Set A)3.7-193.7.2.1.6Category I Pile-Supported Structures - Evaluation and New Design/Mod-ification Analyses (Set B and Set B+C)3.7-213.7.2.2Natural Frequencies and Response Loads for NSSS3.7-223.7.2.3Procedures Used for Modeling3.7-22 3.7.2.3.1Other Than NSSS3.7-223.7.2.3.2For NSSS Analysis3.7-223.7.2.4Soil/Structure Interaction3.7-23 3.7.2.4.1Original Analysis (Set A)3.7-233.7.2.4.2Evaluation and New Design or Modification Analyses3.7-233.7.2.5Development of Floor Response Spectra3.7-24 3.7.2.5.1Original Analysis3.7-243.7.2.5.2Evaluation and New Design or Modification Analysis3.7-243.7.2.6Three Components of Earthquake Motion3.7-25 3.7.2.6.1Original Analysis (Set A)3.7-253.7.2.6.2Evaluation and New Design/Modifi cation Analyses (Set B and Set C) 3.7-253.7.2.7Combination of Modal Responses3.7-263.7.2.7.1Other Than NSSS3.7-26 Original Analysis (Set A) 26 Evaluation and New Design or Modification Analyses 263.7.2.7.2NSSS System3.7-27 3.7.2.8Interaction of Non-Cate gory I Structures With Seismic Category I Structures 3.7-29 1-xlviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.2.9Effects of Parameter Variations on Floor Response Spectra3.7-293.7.2.10Use of Constant Vertical Load Factors3.7-293.7.2.10.1Other Than NSSS3.7-29 Original Analysis (Set A) 29 Evaluation and New Design or Modification Analyses 303.7.2.10.2For NSSS3.7-30 3.7.2.11Methods Used to Account for Torsional Effects3.7-303.7.2.12Comparison of Responses - Set A versus Set B3.7-303.7.2.13Methods for Seismic Analysis of Dams3.7-31 3.7.2.14Determination of Category I Structure Overturning Moments3.7-313.7.2.14.1Original Analysis3.7-313.7.2.14.2Evaluation and New Design or Modification Analysis3.7-313.7.2.15Analysis Procedure for Damping3.7-313.7.3Seismic Subsystem Analysis3.7-313.7.3.1Seismic Analysis Methods for Other Than NSSS3.7-31 3.7.3.2Determination of Number of Earthquake Cycles3.7-323.7.3.2.1Category I Systems and Components Other Than NSSS3.7-323.7.3.2.2NSSS System3.7-33 3.7.3.3Procedure Used for Modeling3.7-333.7.3.3.1Other Than NSSS3.7-33 Modeling of Piping Systems for Detailed Rigorous Analysis 33 Modeling of Equipment 33 Modeling of HVAC, Conduit, a nd Cable Tray Subsystems 333.7.3.3.2Modeling of NSSS Subsystems3.7-34 3.7.3.4Basis for Selection of Frequencies3.7-343.7.3.4.1Other Than NSSS3.7-343.7.3.4.2NSSS Basis for Selection of Forcing Frequencies3.7-343.7.3.5Use of Equivalent Static Load Method of Analysis3.7-353.7.3.5.1Other Than NSSS3.7-353.7.3.5.2Use of Equivalent Static Load Method of Analysis for NSSS3.7-363.7.3.6Three Components of Earthquake Motion3.7-363.7.3.6.1Piping Subsystems3.7-363.7.3.6.2HVAC Ducting, Conduit, and Cable Tray Subsystems3.7-363.7.3.6.3Other Than NSSS Equipment and Components3.7-363.7.3.7Combination of Modal Responses3.7-373.7.3.7.1Other Than NSSS3.7-37 3.7.3.7.2Combination of Modal Responses of NSSS3.7-373.7.3.8Analytical Procedures for Piping Other Than NSSS3.7-373.7.3.8.1General3.7-373.7.3.8.2Detailed Seismic Analysis (Rigorous) for Piping Systems3.7-413.7.3.8.3Alternate (Simplified) Analysis for Piping Systems3.7-433.7.3.8.4Seismic Analysis of Piping Systems That Span Two or More Seismic Sup-port Zones Such as Buildings, Porti ons of Buildings, or Primary Compo-nents3.7-44 Table of Contents1-xlixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.3.9Multiple Supported Equipment and Components with Distinct Inputs3.7-443.7.3.9.1Other Than NSSS3.7-443.7.3.9.2Multiple Supported NSSS Equipment a nd Components with Distinct In-puts3.7-443.7.3.10Use of Constant Vertical Load Factors3.7-453.7.3.10.1Use of Constant Load Factors for Equipment Other Than NSSS3.7-453.7.3.10.2Use of Constant Vertical Load Factors for NSSS3.7-453.7.3.11Torsional Effects of Eccentric Masses3.7-453.7.3.11.1Piping Other Than NSSS3.7-45 3.7.3.11.2Torsional Effects of Eccentric Masses of NSSS3.7-463.7.3.12Buried Seismic Category I Piping Systems3.7-463.7.3.13Interaction of Other Piping with Seismic Category I Piping3.7-523.7.3.14Seismic Analyses for Fuel Elements , Control Rod Assemblies, Control Rod Drives, and Reactor Internals3.7-523.7.3.15Analysis Procedure for Damping3.7-54 3.7.3.16Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-543.7.3.16.1Dynamic Analysis Method For Equipment and Components3.7-553.7.3.16.2Simplified Dynamic Analysis Method For Equipment and Components 3.7-553.7.3.16.3Equivalent Static Load Method3.7-56 3.7.3.16.4Testing Method3.7-563.7.3.16.5Equipment and Component Mounting Considerations3.7-563.7.3.17Seismic Analysis and Design of HVAC Duct and Duct Support Systems3.7-573.7.3.17.1Description of HVAC Duct and Duct Support Subsystems3.7-573.7.3.17.2Applicable Codes, Standards, and Specifications3.7-573.7.3.17.3Loads and Load Combinations3.7-583.7.3.17.4Analysis and Design Procedures3.7-593.7.3.17.5Structural Acceptance Criteria3.7-59 3.7.3.17.6Materials and Quality Control3.7-603.7.3.18Seismic Qualification of Main Control Room Suspended Ceiling and Air Deliv-ery Components3.7-61 3.7.4Seismic Instrumentation Program3.7-613.7.4.1Comparison with Regulatory Guide 1.123.7-613.7.4.2Location and Description of Instrumentation3.7-613.7.4.3Control Room Operator Notification3.7-643.7.4.4Controlled Shutdown Logic3.7-643.7.4.5Comparison of Measured and Predicted Responses3.7-653.7.4.5.1Retrieval of Data3.7-653.7.4.5.2Evaluation of Recorded Earthquake3.7-663.8DESIGN OF CATEGORY I STRUCTURES3.8-13.8.1Concrete Shield Building3.8-1 1-lTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.1.1Description of the Shield Building3.8-13.8.1.1.1Equipment Hatch Doors and Sleeves3.8-23.8.1.2Applicable Codes, Standards, and Specifications3.8-33.8.1.3Loads and Loading Combinations3.8-53.8.1.4Design and Analysis Procedures3.8-73.8.1.5Structural Acceptance Criteria3.8-10 3.8.1.6Materials, Quality Control and Special Construction Techniques3.8-113.8.1.6.1Materials3.8-113.8.1.6.2Quality Control3.8-12 3.8.1.6.3Construction Techniques3.8-133.8.2Testing and Inservice Surveillance Requirements3.8-133.8.2Steel Containment System3.8-13.8.2.1Description of the Containment and Penetrations3.8-13.8.2.1.1Description of the Containment3.8-13.8.2.1.2Description of Penetrations3.8-1 3.8.2.2Applicable Codes, Standards and Specifications3.8-33.8.2.2.1Codes3.8-33.8.2.2.2Design Specification Summary3.8-4 3.8.2.2.3NRC Regulatory Guides3.8-63.8.2.3Loads and Loading Combinations3.8-73.8.2.3.1Design Loads3.8-7 3.8.2.3.2Loading Conditions3.8-93.8.2.4 Design and Analysis Procedures3.8-113.8.2.4.1Introduction3.8-11 3.8.2.4.2Static Stress Analysis3.8-123.8.2.4.3Dynamic Seismic Analysis3.8-123.8.2.4.4Non-Axisymmetric Pressure Loading Analysis3.8-133.8.2.4.5Thermal Analysis3.8-143.8.2.4.6Penetrations Analysis3.8-143.8.2.4.7Interaction of Containment and Attached Equipment3.8-163.8.2.4.8Anchorage3.8-173.8.2.5Structural Acceptance Criteria3.8-183.8.2.5.1Margin of Safety3.8-18 3.8.2.6Materials, Quality Control, and Special Construction Techniques3.8-183.8.2.6.1Materials - General3.8-183.8.2.6.2Corrosion Protection3.8-21 3.8.2.6.3Protective Coatings3.8-233.8.2.6.4Tolerances3.8-243.8.2.6.5Vessel Material Inspection and Test3.8-243.8.2.6.6Impact Testing3.8-253.8.2.6.7Post-Weld Heat Treatment3.8-253.8.2.6.8Welding3.8-253.8.2.7Testing and Inservice Inspection Requirements3.8-25 Table of Contents 1-liWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.2.7.1Bottom Liner Plates Test3.8-253.8.2.7.2Vertical Wall and Dome Tests3.8-253.8.2.7.3Soap Bubble Tests3.8-253.8.2.7.4Overpressure Tests3.8-263.8.2.7.5Leakage Rate Test3.8-263.8.2.7.6Operational Testing3.8-263.8.2.7.7Leak Testing Airlocks3.8-263.8.2.7.8Penetration Tests3.8-273.8.2.7.9Inservice Inspection Requirements3.8-273.8.3Concrete Interior Structure3.8-13.8.3.1Description of the Interior Structure3.8-13.8.3.2General3.8-1 3.8.3.3Containment Floor Structural Fill Slab3.8-13.8.3.4Reactor Cavity Wall3.8-23.8.3.5Compartment Above Reactor3.8-2 3.8.3.6Refueling Canal Walls and Floor (Divider Barrier)3.8-33.8.3.7Crane Wall3.8-33.8.3.8Steam Generator Compartments (Divider Barrier)3.8-5 3.8.3.9Pressurizer Compartment (Divider Barrier)3.8-53.8.3.10Divider Deck at Elevation 756.63 (Divider Barrier)3.8-53.8.3.11Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier)3.8-53.8.3.12Penetrations Through the Divider Barrier Canal Gate3.8-63.8.3.13Applicable Codes, Standards and Specifications3.8-73.8.3.14Loads and Loading Combinations3.8-13 3.8.3.15Design and Analysis Procedures3.8-163.8.3.16General3.8-163.8.3.17Structural Fill Slab on Containment Floor3.8-163.8.3.18Reactor Cavity Wall3.8-163.8.3.19Compartment Above Reactor3.8-183.8.3.20Seals Between Upper and Lower Compartments3.8-183.8.3.21Refueling Canal Walls and Floor (Divider Barrier)3.8-193.8.3.22Crane Wall3.8-203.8.3.23Steam Generator Compartments (Divider Barrier)3.8-23 3.8.3.24Pressurizer Compartment (Divider Barrier)3.8-253.8.3.25Operating Deck at Elevation 756.63 (Divider Barrier)3.8-263.8.3.26Ice Condenser Support Floor El evation 744.5 (Divider Barrier)3.8-273.8.3.27Ice Condenser3.8-283.8.3.28Penetrations Through the Divider Barrier3.8-293.8.3.29Structural Acceptance Criteria3.8-313.8.3.30General3.8-313.8.3.31Structural Fill Slab on Containment Floor3.8-313.8.3.32Reactor Cavity Wall and Compartment Above Reactor3.8-313.8.3.33Refueling Canal Walls and Floor3.8-32 1-liiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.3.34Crane Wall3.8-323.8.3.35Steam Generator and Pressurizer Compartment3.8-323.8.3.36Operating Deck at Elevation 756.633.8-323.8.3.37Ice Condenser Support Floor Elevation 744.53.8-323.8.3.38Penetrations Through the Divider Barrier3.8-323.8.3.39Personnel Access Doors in Crane Wall3.8-333.8.3.40Seals Between Upper and Lower Compartments3.8-333.8.3.41Ice Condenser3.8-333.8.3.42Materials, Quality Control and Special Construction Techniques3.8-343.8.3.43Materials3.8-343.8.3.44Quality Control3.8-353.8.3.45Construction Technique3.8-36 3.8.3.46Ice Condenser3.8-363.8.3.47Testing and Inservice Surveillance Requirements3.8-383.8.3.48Environmental Effects3.8-38 3.8.3.49Interface Control 3.8-393.8.4Other Category I Structures3.8-13.8.4.1Description of the Structures3.8-1 3.8.4.2Auxiliary-Control Building3.8-13.8.4.3Diesel Generator Building3.8-103.8.4.4Category I Water Tanks and Pipe Tunnels3.8-12 3.8.4.5Class 1E Electrical System Manholes and Duct Runs3.8-133.8.4.6North Steam Valve Room3.8-133.8.4.7Intake Pumping Station and Retaining Walls3.8-14 3.8.4.8Miscellaneous Essential Raw Cooling Water (ERCW) Structures3.8-153.8.4.9Additional Diesel Generator Building3.8-163.8.4.10Applicable Codes, Standards, and Specifications3.8-173.8.4.11List of Documents3.8-173.8.4.12Basis for Use of the 1963 Edition of ACI 3183.8-193.8.4.13Loads and Loading Combinations3.8-21 3.8.4.14Description of Loads3.8-213.8.4.15Load Combinations and Allowable Stresses3.8-223.8.4.16Design and Analysis Procedures3.8-23 3.8.4.17Auxiliary-Control Building3.8-233.8.4.18Diesel Generator Building3.8-303.8.4.19Category I Water Tanks and Pipe Tunnels3.8-31 3.8.4.20Class 1E Electrical System Manholes3.8-313.8.4.21North Steam Valve Room3.8-313.8.4.22Intake Pumping Station and Reta ining Walls Pumping Station3.8-323.8.4.23Miscellaneous ERCW Structures3.8-323.8.4.24Additional Diesel Generator Building3.8-333.8.4.25Structural Acceptance Criteria3.8-353.8.4.26Concrete3.8-35 Table of Contents1-liiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.4.27Structural and Miscellaneous Steel3.8-353.8.4.28Miscellaneous Components of the Auxiliary Building3.8-363.8.4.29Intake Pumping Station Traveling Water Screens3.8-373.8.4.30Diesel Generator Building Doors and Bulkheads3.8-373.8.4.31Additional Diesel Generator Building Missile Barriers3.8-373.8.4.32Materials, Quality Control, and Special Construction Techniques General3.8-373.8.4.33Materials3.8-373.8.4.34Quality Control3.8-383.8.4.35Special Construction Techniques3.8-383.8.4.36Testing and Inservice Surveillance Requirements3.8-383.8.4.37Concrete and Struct ural Steel Portions of Structures3.8-383.8.4.38Miscellaneous Components of Auxiliary-Control Building3.8-393.8.4.39Deleted by Amendment 793.8-403.8.4.40Miscellaneous Components of the Intake Pumping Station3.8-403.8.5Foundations and Concrete Supports3.8-13.8.5.1Description of Foundations and Supports3.8-13.8.5.1.1Primary Containment3.8-13.8.5.1.2Foundations of Other Category I Structures3.8-13.8.5.2Applicable Codes, Standards, and Specifications3.8-33.8.5.3Loads and Loading Combinations3.8-33.8.5.4Design and Analysis Procedure3.8-4 3.8.5.4.1Primary Containment Foundation3.8-43.8.5.4.2Auxiliary-Control Building3.8-43.8.5.4.3Intake Pumping Station3.8-4 3.8.5.4.4Soil-Supported Structures3.8-43.8.5.4.5Pile Supported Structures3.8-53.8.5.5Structural Acceptance Criteria3.8-53.8.5.5.1Primary Containment Foundation3.8-53.8.5.5.2Foundations of Other Category I Structures Auxiliary-Control Building3.8-53.8.5.6Materials, Quality Control, and Special Construction Techniques3.8-63.8.5.6.1Materials3.8-63.8.5.6.2Quality Control3.8-73.8.5.6.3Special Construction Techniques3.8-73.8.6Category I(L) Cranes3.8-13.8.6.1Polar Cranes3.8-13.8.6.1.1Description3.8-13.8.6.1.2Applicable Codes, Standards, and Specifications3.8-13.8.6.1.3Loads, Loading Combinations, and Allowable Stresses3.8-23.8.6.1.4Design and Analysis Procedure3.8-23.8.6.1.5Structural Acceptance Criteria3.8-23.8.6.1.6Materials, Quality Controls, and Special Construction Techniques3.8-33.8.6.1.7Testing and Inservice Surveillance Requirements3.8-3 1-livTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.6.1.8Safety Features3.8-33.8.6.2Auxiliary Building Crane3.8-43.8.6.2.1Description3.8-43.8.6.2.2Applicable Codes, Standards, and Specifications3.8-53.8.6.2.3Loads, Loading Combinations, and Allowable Stresses3.8-53.8.6.2.4Design and Analysis Procedure3.8-5 3.8.6.2.5Structural Acceptance Criteria3.8-63.8.6.2.6Materials, Quality Controls, and Special Construction Techniques3.8-63.8.6.2.7Testing and Inservice Surveillance Requirements3.8-73.8.6.2.8Safety Features3.8-73.8ASHELL TEMPERATURE TRANSIENTS3.8-13.8BBUCKLING STRESS CRITERIA3.8-13.8B.1INTRODUCTION3.8-13.8B.2SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS3.8-13.8B.2.1Circular Cylindrical Shells Under Axial Compression3.8-13.8B.2.2Circular Cylindrical Shells in Circumferential Compression3.8-23.8B.2.3Circular Cylindrical Shells Under Torsion3.8-23.8B.2.4where a is the effective length and b is the circumference of the cylinder. The coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending3.8-33.8B.2.5Circular Cylindrical Shell Under Combined Loads3.8-33.8B.3SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS3.8-53.8B.4SPHERICAL SHELLS3.8-73.8B.2.1The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation:3.8-73.8B.2.2Spherical Shell Under Combined Loads3.8-73.8B.3FACTOR OF SAFETY3.8-83.8CDOCUMENTATION OF CB&I COMPUTER PROGRAMS3.8-13.8C.1INTRODUCTION3.8-1 3.8C.2PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE3.8-13.8C.3PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES3.8-13.8C.4PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS3.8-33.8C.5PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS3.8-33.8C.6PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E13743.8-43.8C.7PROGRAM E1374-SHELL DYNAMIC ANALYSIS3.8-53.8C.7.1Introduction3.8-53.8C.8PROGRAM E1622-LOAD GENERATI ON PREPROCESSOR FOR PROGRAM E1374 3.8-6 Table of Contents1-lvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8C.9PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION3.8-73.8C.10PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS3.8-73.8C.11PROGRAM 119-CHECK of FLANGE DESIGN3.8-73.8C.12PROGRAM 772-NOZZLE REINFORCEMENT CHECK3.8-73.8C.13PROGRAM 1027-WRC 107 STRESS INTEN SITIES AT L OADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WI TH ROUND OR SQUARE ATTACHMENT3.8-83.8C.14PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES3.8-83.8DCOMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS3.8-13.8ECODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 19793.8-13.8E.1Application Codes and Standards3.8-13.8E.2Load Definitions3.8-1 3.8E.3Load Combinations - Concrete3.8-33.8E.4Load Combinations - Structural Steel3.8-53.9MECHANICAL SYSTEMS AND COMPONENTS3.9-13.9.1General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-13.9.1.1Design Transients3.9-1 3.9.1.2Computer Programs Used in Analysis and Design3.9-13.9.1.2.1Other Than NSSS Systems, Components, Equipment, and Supports3.9-13.9.1.2.2Programs Used for Category I Components of NSSS3.9-3 3.9.1.3Experimental Stress Analysis3.9-33.9.1.4Consideration for the Evaluation of the Faulted Condition3.9-33.9.1.4.1Subsystems and Components Analyzed by Westinghouse3.9-33.9.1.4.2Subsystems and Components Analyzed by TVA3.9-33.9.2Dynamic Testing and Analysis3.9-43.9.2.1Preoperational Vibration and Dynamic Effects Testing on Piping3.9-43.9.2.2Seismic Qualification Testing of Safety-Related Mechanical Equipment3.9-63.9.2.3Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions3.9-8 3.9.2.4Preoperational Flow-Induced Vibration Testing of Reactor Internals3.9-103.9.2.5Dynamic System Analysis of the R eactor Internals Under Faulted Conditions 3.9-123.9.2.5.1Evaluation of Reactor Internals fo r Limited Displacement RPV Inlet and Outlet Nozzle Break3.9-173.9.2.6Correlations of Reactor Internals Vibration Tests Wi th the Analytical Results 3.9-193.9.3ASME Code Class 1, 2 and 3 Component s, Component Supports and Core Support Structures 3.9-20 1-lviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.9.3.1Loading Combinations, Design Transients, and Stress Limits3.9-203.9.3.1.1Subsystems and Components Supplied by Westinghouse3.9-20 Plant Conditions and Design Loading Combinations For ASME Code Cla ss 2 and 3 Components Supplied by Westinghouse 21 Design Loading Combinations by Westinghouse 21 Design Stress Limits By Westinghouse 22 3.9.3.1.2Subsystems and Components Analyzed or Specified by TVA3.9-223.9.3.2Pumps and Valve Operability Assurance3.9-273.9.3.2.1Active* ASME Class 1, 2, & 3 Pumps and Valves3.9-27 3.9.3.2.2Operability Assurance3.9-28 Westinghouse Scope of Supply 28 TVA Scope of Supply 33 3.9.3.2.3Criteria For Assuring Functional Adequacy of Active Seismic Category I Fluid System Components (Pumps and Valves) and Associated Essential Auxiliary Equipment3.9-343.9.3.3Design and Installation Details for Mounting of Pressure Relief Devices3.9-393.9.3.4Component Supports3.9-423.9.3.4.1Subsystem and Component Supports Analyzed or Specified by Westing-house3.9-423.9.3.4.2Subsystem and Component Supports Analyzed or Specified by TVA3.9-433.9.4Control Rod System3.9-463.9.4.1Descriptive Information of CRDS3.9-463.9.4.2Applicable CRDS Design Specifications3.9-463.9.4.3Design Loadings, Stress Limits, and Allowable Deformations3.9-463.9.4.4CRDS Performance Assurance Program3.9-473.9.5Reactor Pressure Vessel Internals3.9-473.9.5.1Design Arrangements3.9-473.9.5.2Design Loading Conditions3.9-473.9.5.3Design Loading Categories3.9-47 3.9.5.4Design Basis3.9-473.9.6Inservice Testing of Pumps and Valves3.9-473.10SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIP-MENT3.10-13.10.1Seismic Qualification Criteria3.10-13.10.2Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-63.10.3Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables3.10-63.10.3.1Electrical Equipment and Instrumentation Assemblies3.10-73.10.3.2Cable Trays and Supports3.10-73.10.3.2.1Cable Trays3.10-73.10.3.2.2Supports3.10-7 Table of Contents 1-lviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.10.3.3Conduit and Supports3.10-83.10.3.3.1Conduit3.10-83.10.3.3.2Supports3.10-83.10.3.4Conduit Banks3.10-93.10.4Operating License Review3.10-93.10.4.1TVA Supplied Instrumentation and Electrical Equipment3.10-93.11ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT3.11-13.11.1 Equipment Identification and Environmental Conditions3.11-13.11.1.1Identification of Safety Systems and Justification3.11-13.11.1.2Identification of Equipment in Harsh Environments3.11-13.11.2Environmental Conditions3.11-23.11.2.1Harsh Environment3.11-23.11.2.2Mild Environment3.11-3 3.11.3Electrical Equipment Within the Scope of 10 CFR 50.493.11-43.11.4Qualification Tests and Analyses3.11-43.11.5Qualification Test Results3.11-4 3.11.6Loss of Heating, Ventilating, and Air-Conditioning (HVAC)3.11-43.11.7Estimated Chemical and Radiation Environment3.11-43.11.7.1Chemical Spray3.11-4 3.11.7.2Radiation3.11-53.11.7.2.1Inside Containment3.11-53.11.7.2.2Radiation - Auxiliary Building Spaces3.11-64.0REACTOR4.1 | |||
==SUMMARY== | ==SUMMARY== | ||
Revision as of 14:20, 11 July 2019
| ML093570483 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/14/2009 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
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Table of Contents1-xxxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page003_TVA_WB_FSAR_Section_1.pdf004_TVA_WB_FSAR_Section_2_A.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 013_TVA_WB_FSAR_Section_4.pdf 014_TVA_WB_FSAR_Section_5.pdf 017_TVA_WB_FSAR_Section_7.pdf 018_TVA_WB_FSAR_Section_8
024_TVA_WB_FSAR_Section_13.pdf026_TVA_WB_FSAR_Section_15.pdf 027_TVA_WB_FSAR_Section_16.pdf 028_TVA_WB_FSAR_Section_17.0.pdf
1.0INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1INTRODUCTION
1.1-11.2GENERAL PLANT DESCRIPTION1.2-11.2.1Site Characteristics1.2-11.2.1.1Location1.2-1 1.2.1.2Demography1.2-11.2.1.3Meteorology1.2-11.2.1.4Hydrology1.2-1 1.2.1.5Geology1.2-11.2.1.6Seismology1.2-21.2.2Facility Description1.2-2 1.2.2.1Design Criteria1.2-21.2.2.2Nuclear Steam Supply System (NSSS)1.2-21.2.2.3Control and Instrumentation1.2-4 1.2.2.4Fuel Handling System1.2-51.2.2.5Waste Processing System1.2-51.2.2.6Steam and Power Conversion System1.2-51.2.2.7Plant Electrical System1.2-61.2.2.8Cooling Water1.2-71.2.2.9Component Cooling System1.2-7 1.2.2.10Chemical and Volume Control System1.2-71.2.2.11Sampling and Water Quality System1.2-81.2.2.12Ventilation1.2-9 1.2.2.13Fire Protection System1.2-91.2.2.14Compressed Air Systems1.2-91.2.2.15Engineered Safety Features1.2-9 1.2.2.16Shared Facilities and Equipment1.2-101.2.3General Arrangement of Major Structures and Equipment1.2-131.3COMPARISON TABLES1.3-11.3.1Comparisons With Similar Facility Designs1.3-11.3.2Comparison Of Final And Preliminary Designs1.3-11.4IDENTIFICATION OF AGENTS AND CONTRACTORS1.4-11.5REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION1.5-11.5.117 x 17 Fuel Assembly1.5-11.5.1.1Rod Cluster Control Spider Tests1.5-11.5.1.2Grid Tests1.5-11.5.1.3Fuel Assembly Structural Tests1.5-1 1.5.1.4Guide Tube Tests1.5-21.5.1.5Prototype Assembly Tests1.5-2 1-xxxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page1.5.2Heat Transfer Tests (17 x 17)1.5-21.5.2.117 x 17 LOCA Heat Transfer Tests1.5-21.5.2.2Departure from Nucleate Boiling (DNB)1.5-21.6MATERIAL INCORPORATED BY REFERENCE1.6-11.7ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS1.7-1 1.8TECHNICAL QUALIFICATION OF APPLICANT1.8-11.9NUCLEAR PERFORMANCE PLAN1.9-11.9.1Corrective Action Plans1.9-11.9.1.1Cable Issues1.9-1 1.9.1.2Cable Tray and Cable Tray Supports1.9-21.9.1.3Design Baseline and Verification Program (DBVP)1.9-21.9.1.4Electrical Conduit and Conduit Support1.9-2 1.9.1.5Electrical Issues1.9-21.9.1.6Equipment Seismic Qualification1.9-31.9.1.7Fire Protection1.9-3 1.9.1.8Hanger and Analysis Update Program (HAAUP)1.9-31.9.1.9Heat Code Traceability1.9-31.9.1.10Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports1.9-31.9.1.11Instrument Lines1.9-41.9.1.12Prestart Test Program1.9-41.9.1.13QA Records1.9-4 1.9.1.14Q-LIST1.9-41.9.1.15Replacement Items Program (RIP-CAP)1.9-41.9.1.16Seismic Analysis1.9-5 1.9.1.17Vendor Information1.9-51.9.1.18Welding1.9-51.9.2Special Programs (SPs)1.9-5 1.9.2.1Concrete Quality Program1.9-61.9.2.2Containment Cooling1.9-61.9.2.3Detailed Control room Design Review1.9-6 1.9.2.4Environmental Qualification Program1.9-61.9.2.5Master Fuse List1.9-61.9.2.6Mechanical Equipment Qualification1.9-61.9.2.7Microbiologically Induced Corrosion (MIC)1.9-71.9.2.8Moderate Energy Line Break Flooding (MELB)1.9-71.9.2.9Radiation Monitoring System1.9-71.9.2.10Soil Liquefaction1.9-71.9.2.11Use-As-Is CAQs1.9-7 1.
9.3REFERENCES
1.9-72.0SITE CHARACTERISTICS Table of Contents1-xxxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.1GEOGRAPHY AND DEMOGRAPHY2.1-12.1.1Site Location and Description2.1-12.1.1.1Specification of Location2.1-12.1.1.2Site Area Map2.1-12.1.1.3Boundaries for Establishing Effluent Limits2.1-22.1.2Exclusion Area Authority And Control2.1-22.1.2.1Authority2.1-22.1.2.2Control of Activities Unrelated to Plant Operation2.1-22.1.2.3Arrangements for Traffic Control2.1-22.1.2.4Abandonment or Relocation of Roads2.1-22.1.3Population Distribution2.1-22.1.3.1Population Within 10 Miles2.1-3 2.1.3.2Population Between 10 and 50 Miles2.1-32.1.3.3Transient Population2.1-42.1.3.4Low Population Zone2.1-4 2.1.3.5Population Center2.1-42.1.3.6Population Density2.1-42.2NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES2.2-12.2.1Location and Route2.2-1 2.2.2Descriptions2.2-12.2.2.1Description of Facilities2.2-1 2.2.2.2Description of Products and Materials2.2-12.2.2.3Pipelines2.2-12.2.2.4Waterways2.2-1 2.2.2.5Airports2.2-22.2.2.6Projections of Industrial Growth2.2-22.2.3Evaluation of Potential Accidents2.2-22.2.
3.1REFERENCES
2.2-32.3METEOROLOGY2.3-12.3.1Regional Climate2.3-1 2.3.1.1Data Sources2.3-12.3.1.2General Climate2.3-12.3.1.3Severe Weather2.3-2 2.3.2Local Meteorology2.3-52.3.2.1Data Sources2.3-52.3.2.2Normal and Extreme Values of Meteorological Parameters2.3-62.3.2.3Potential Influence of the Plant and Its Facilities on Local Meteorology2.3-82.3.2.4Local Meteorological Conditions for Design and Operating Bases2.3-92.3.3Onsite Meteorological Measurements Program2.3-92.3.3.1Preoperational Program2.3-92.3.3.2Operational Meteorological Program2.3-12 1-xlTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.3.3.3Onsite Data Summaries of Parameters for Dispersion Meteorology2.3-122.3.4Short-Term (Accident) Diffusion Estimates2.3-132.3.4.1Objective2.3-132.3.4.2Calculation Results2.3-152.3.5Long-Term (Routine) Diffusion Estimates2.3-162.4HYDROLOGIC ENGINEERING2.4-12.4.1Hydrological Description2.4-12.4.1.1Sites and Facilities2.4-12.4.1.2Hydrosphere2.4-2 2.4.2Floods2.4-62.4.2.1Flood History2.4-62.4.2.2Flood Design Considerations2.4-7 2.4.2.3Effects of Local Intense Precipitation2.4-92.4.3Probable Maximum Flood (PMF) on Streams and Rivers2.4-122.4.3.1Probable Maximum Precipitation (PMP)2.4-13 2.4.3.2Precipitation Losses2.4-142.4.3.3Runoff and Stream Course Model2.4-142.4.3.4Probable Maximum Flood Flow2.4-18 2.4.3.5Water Level Determinations2.4-252.4.3.6Coincident Wind Wave Activity2.4-262.4.4Potential Dam Failures, Seismically Induced2.4-28 2.4.4.1Dam Failure Permutations2.4-282.4.4.2Unsteady Flow Analysis of Potential Dam Failures2.4-392.4.4.3Water Level at Plantsite2.4-40 2.4.5Probable Maximum Surge and Seiche Flooding2.4-402.4.6Probable Maximum Tsunami Flooding2.4-402.4.7Ice Effects2.4-40 2.4.8Cooling Water Canals and Reservoirs2.4-412.4.9Channel Diversions2.4-422.4.10Flooding Protection Requirements2.4-42 2.4.11Low Water Considerations2.4-422.4.11.1 Low Flow in Rivers and Streams2.4-422.4.11.2Low Water Resulting From Surges, Seiches, or Tsunami2.4-432.4.11.3Historical Low Water2.4-432.4.11.4Future Control2.4-432.4.11.5Plant Requirements2.4-44 2.4.12Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-452.4.12.1Radioactive Liquid Wastes2.4-452.4.12.2Accidental Slug Releases to Surface Water 2.4-452.4.12.2.1Calculations2.4-46 2.4.12.3Effects on Ground Water2.4-472.4.13Groundwater2.4-48 Table of Contents1-xliWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.4.13.1Description and On-Site Use2.4-482.4.13.2 Sources2.4-482.4.13.3Accident Effects2.4-502.4.13.4Monitoring and Safeguard Requirements2.4-502.4.13.5Design Basis for Subsurface Hydrostatic Loading2.4-512.4.14 Flooding Protection Requirements2.4-512.4.14.1Introduction2.4-512.4.14.1.1Design Basis Flood2.4-512.4.14.1.2Combinations of Events2.4-52 2.4.14.1.3Post Flood Period2.4-522.4.14.1.4Localized Floods2.4-522.4.14.2Plant Operation During Floods Above Grade2.4-52 2.4.14.2.1Flooding of Structures2.4-522.4.14.2.2Fuel Cooling2.4-532.4.14.2.3Cooling of Plant Loads2.4-54 2.4.14.3Warning Scheme2.4-552.4.14.4Preparation for Flood Mode2.4-552.4.14.4.1Reactor Initially Operating at Power2.4-552.4.14.4.2Reactor Initially Refueling2.4-552.4.14.4.3Plant Preparation Time2.4-562.4.14.5Equipment2.4-56 2.4.14.5.1Equipment Qualification2.4-562.4.14.5.2Temporary Modification and Setup2.4-562.4.14.5.3Electric Power2.4-56 2.4.14.5.4Instrument, Control, Communication and Ventilation Systems2.4-572.4.14.6Supplies2.4-572.4.14.7Plant Recovery2.4-57 2.4.14.8Warning Plan2.4-582.4.14.8.1Rainfall Floods2.4-582.4.14.8.2Seismically-Induced Dam Failure Floods2.4-582.4.14.9Basis For Flood Protection Plan In Rainfall Floods2.4-592.4.14.9.1Overview2.4-592.4.14.9.2TVA Forecast System2.4-592.4.14.9.3Basic Analysis2.4-612.4.14.9.4Hydrologic Basis for Warning System2.4-612.4.14.9.5Hydrologic Basis for Target States2.4-62 2.4.14.9.6Communications Reliability2.4-632.4.14.10Basis for Flood Protection Plan in Seismic-Caused Dam Failures2.4-642.4.14.11Special Condition Allowance2.4-652.5GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING
SUMMARY
OF FOUNDATION CONDITIONS2.5-12.5.1Basic Geology and Seismic Information2.5-22.5.1.1Regional Geology2.5-3 1-xliiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.5.1.1.1Regional Physiography2.5-32.5.1.1.2Regional Tectonics and Geology2.5-72.5.1.1.3Regional Geologic Setting2.5-92.5.1.1.4Regional Geologic History2.5-102.5.1.1.5Regional Lithologic, Stratigraphic, and Structural Geology2.5-202.5.1.1.6Regional Tectonics2.5-22 2.5.1.1.7Groundwater2.5-262.5.1.2Site Geology2.5-262.5.1.2.1Site Physiography2.5-26 2.5.1.2.2Site Lithologic, Stratigraphic, and Structural Geologic Conditions2.5-272.5.1.2.3Site Structural Geology2.5-292.5.1.2.4Surface Geology2.5-30 2.5.1.2.5Site Geologic History2.5-312.5.1.2.6Plot Plan2.5-312.5.1.2.7Bedrock Foundation Characteristics2.5-31 2.5.1.2.8Excavation and Backfill2.5-312.5.1.2.9Evaluation of Geologic Conditions2.5-322.5.1.2.10Groundwater2.5-33 2.5.1.2.11Geophysical Surveys2.5-332.5.1.2.12Soil and Rock Properties2.5-342.5.2Vibratory Ground Motion2.5-34 2.5.2.1Seismicity2.5-342.5.2.2Geologic Structures and Tectonic Activity2.5-412.5.2.3Correlation of Earthquake Activity With Geologic Structures to Tectonic Prov-inces 2.5-422.5.2.4Maximum Earthquake Potential2.5-422.5.2.5Seismic Wave Transmission Characteristics of the Site2.5-442.5.2.6Safe Shutdown Earthquake2.5-452.5.2.7Operating Basis Earthquake2.5-452.5.3Surface Faulting2.5-45 2.5.3.1Geologic Conditions of the Site2.5-452.5.3.2Evidence of Fault Offset2.5-452.5.3.3Earthquakes Associated With Capable Faults2.5-54 2.5.3.4Investigations of Capable Faults2.5-542.5.3.5Correlation of Epicenters With Capable Faults2.5-562.5.3.6Description of Capable Faults2.5-56 2.5.3.7Zone Requiring Detailed Faulting Investigation2.5-562.5.3.8Results of Faulting Investigations2.5-562.5.4Stability of Subsurface Materials2.5-562.5.4.1Geologic Features2.5-562.5.4.2Properties of Subsurface Materials2.5-57 2.5.4.2.1In Situ Soils2.5-57 General Description 57 Investigations 57 Table of Contents 1-xliiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page Test Results and Selecti on of Design Properties 612.5.4.2.2Rock2.5-74 Engineering Description of Bedrock 74 Test Program 75 Description of Te sting Techniques 75Test Results for Menard Pressuremeter 77
Comparison of Results from Menard Pressu remeter and Birdwell 3D Sonic Logger 78 Settlement Analysis 78 Behavior of Watts Bar Lock 83
Excavation Experience in the Rutl edge Shale at Watts Bar Lock 85 Evaluation of Settlement 862.5.4.3Exploration2.5-89 2.5.4.4Geophysical Surveys2.5-902.5.4.4.1Rock Characteristics2.5-902.5.4.4.2Soil Characteristics2.5-90
Equipment 90 Velocity Measurement Procedures 90 Data Analysis and Results 91
Data Analysis and Results - Eval uation Seismic Criteria and New 932.5.4.5Excavations and Backfill2.5-932.5.4.5.1Earthfill2.5-93
Investigation 93 Test Results 94 Field Work 97
Construction Control 982.5.4.5.2Granular Fill2.5-98 General 98
Section 1032 Material 98 Section 1075 Material 1002.5.4.6Groundwater Conditions2.5-101 2.5.4.7Response of Soil and Rock to Dynamic Loading2.5-1032.5.4.8Liquefaction Potential2.5-1032.5.4.9Earthquake Design Basis2.5-113 2.5.4.10Static Analysis2.5-1132.5.4.10.1Settlement2.5-1132.5.4.10.2Bearing Capacity2.5-114 2.5.4.11Safety-Related Criteria for Foundations2.5-1152.5.4.11.1General2.5-1152.5.4.11.2Rock Strength2.5-1152.5.4.11.3Soil Strength2.5-1152.5.4.12Techniques to Improve Subsurface Conditions2.5-1152.5.4.13Construction Notes2.5-1182.5.5Stability of Slopes2.5-1182.5.5.1Slope Characteristics2.5-118 1-xlivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.5.5.1.1Essential Raw Cooling Water Intake Channel Slopes2.5-1182.5.5.1.2Underground Barrier for Protection Ag ainst Potential Soil Liquefaction 2.5-1182.5.5.2Design Criteria and Analysis2.5-1202.5.5.2.1Design Criteria and Analyses for the Essential Raw Coolant Water2.5-1202.5.5.2.2Additional Analyses Due to Unexp ected Soil Conditions Encountered During Excavation of the Intake Channel2.5-1232.5.5.2.3Design Criteria and Analysis for the Underground Barrier for the ERCW Pipeline and 1E Conduit Alignment2.5-1252.5.5.3Logs of Borings2.5-1272.5.5.4Compaction Specifications2.5-127 2.5.6Embankments2.5-1273.0DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.1CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA3.1-13.1.1Introduction3.1-13.1.2WBNP Conformance with GDCs3.1-1 3.1.2.1Overall Requirements3.1-13.1.2.2Protection By Multiple Fission Product Barriers3.1-53.1.2.3Protection and Reactivity Control Systems3.1-123.1.2.4Fluid Systems3.1-173.1.2.5Reactor Containment3.1-303.1.2.6Fuel and Radioactivity Control3.1-353.2CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS3.2-1 3.2.1 Seismic Classifications 3.2-13.2.2System Quality Group Classification3.2-13.2.2.1Class A3.2-23.2.2.2Class B3.2-23.2.2.3Class C3.2-2 3.2.2.4Class D3.2-23.2.2.5Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents 3.2-33.2.2.6Nonnuclear Safety Class (NNS)3.2-33.2.2.7Heating, Ventilation and Air Conditioning (HVAC) Safety Classification3.2-33.2.3Code Cases and Code Editions and Addenda3.2-33.2.3.1TVA Design and Fabrication3.2-33.2.3.2Purchased Materials and Components3.2-43.3Wind and Tornado Loading3.3-13.3.1Wind Loadings3.3-13.3.1.1Design Wind Velocity3.3-1 Table of Contents1-xlvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.3.1.2Determination of Applied Force3.3-13.3.2Tornado Loadings3.3-13.3.2.1Applicable Design Parameters3.3-13.3.2.2Determination of Forces on Structures3.3-23.3.2.3Ability of Category I Structures to Pe rform Despite Failure of Structures Not Designed for Tornado Loads3.3-33.4WATER LEVEL (FLOOD) DESIGN3.4-13.4.1Flood Protection3.4-1 3.4.2Analysis Procedure3.4-13.5MISSILE PROTECTION3.5-13.5.1Missile Selection and Description3.5-23.5.1.1Internally Generated Missiles (Outside Containment)3.5-23.5.1.1.1Shield Building3.5-23.5.1.1.2North and South Steam Valve Rooms3.5-23.5.1.1.3Auxiliary Building3.5-3 3.5.1.1.4Control Building3.5-43.5.1.1.5ERCW Structures3.5-43.5.1.1.6ERCW Pipe Tunnels and RWST Foundations3.5-43.5.1.1.7Diesel Generator Building3.5-43.5.1.2Internally Generated Missiles (Inside Containment)3.5-53.5.1.2.1Missile Selection3.5-53.5.1.2.2Missile Description3.5-73.5.1.2.3Electrical Cables3.5-83.5.1.2.4Upper Compartment3.5-8 3.5.1.2.5Ice Condenser Compartment3.5-83.5.1.2.6Lower Compartment3.5-83.5.1.3Turbine Missiles3.5-9 3.5.1.3.1Introduction3.5-93.5.1.3.2Potential Missile Sources and Missile Characteristics3.5-103.5.1.3.3Primary Safety-Related Equipment Installations and Structures3.5-153.5.1.3.4Turbine Missile Protection Criterion3.5-153.5.1.3.5Turbine Missile Hazard Evaluation3.5-163.5.1.3.6Turbine Missile Selection3.5-223.5.1.4Missiles Generated By Natural Phenomena3.5-233.5.1.5Missiles Generated by Events Near the Site.3.5-233.5.1.6Aircraft Hazards3.5-243.5.2Systems To Be Protected3.5-243.5.3Barrier Design Procedures3.5-25 3.5.3.1Additional Diesel Generator Building (And Other Category I Structures Added After July 1979)3.5-283.5.AESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES3.5-1 1-xlviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.6PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-13.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WI TH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING)3.6-13.6A.1Postulated Piping Failures in Fluid Systems Inside and Outside Containment3.6-83.6A.1.1Design Bases3.6-8 3.6A.1.1.1List of Potential Targets3.6-83.6A.1.1.2Interaction Criteria3.6-83.6A.1.1.3Acceptability Criteria3.6-9 3.6A.1.1.4Protective Measures3.6-103.6A.1.2Description of Piping System Arrangement3.6-103.6A.1.3Safety Evaluation3.6-10 3.6A.2Determination of Break Lo cations and Dynamic Effects Associated with the Postu-lated Rupture of Piping3.6-113.6A.2.1Criteria Used to Define Break and Crack Location and Configuration3.6-113.6A.2.1.1Pipe Failure Type, Size, and Orientation3.6-113.6A.2.1.2Break Location3.6-123.6A.2.1.3Failure Consequences3.6-15 3.6A.2.1.4Flooding3.6-163.6A.2.1.5Leak-Before-Break Application3.6-173.6A.2.2Analytical Methods to Define Forcing Functions and Response Models3.6-173.6A.2.2.1Assumptions3.6-173.6A.2.2.2Blowdown Thrust Loads3.6-173.6A.2.2.3Jet Impingement Loads3.6-19 3.6A.2.3Dynamic Analysis Methods to Verify Integrity and Operability3.6-213.6A.2.3.1General Criteria for Pipe Whip Evaluation3.6-213.6A.2.3.2Main Reactor Coolant Loop Piping System3.6-213.6A.2.3.3Other Piping Systems3.6-213.6A.2.3.4Simplified Pipe Whip Analysis3.6-223.6A.2.3.5Pipe Whip Restraint Design3.6-23 3.6A.2.3.6Energy Absorbing Materials 3.6-243.6A.2.4Guard Pipe Assembly Design Criteria3.6-243.6A.2.5Summary of Dynamic Analysis Results3.6-253.6A.2.5.1Stress Summary and Isometrics - Inside Containment3.6-253.6A.2.5.2Summary of Protection Requirement s and Isometrics-Outside Contain-ment3.6-263.6BPROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING3.6-263.6B.1Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture3.6-26 3.6B.2Analytical Methods to Define Fo rcing Function and Response Models3.6-273.6B.3Dynamic Analysis of the Reactor Cool ant Loop Piping Equipment Supports and Pipe Whip Restraints3.6-29 Table of Contents1-xlviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7SEISMIC DESIGN3.7-13.7.1Seismic Input3.7-23.7.1.1Ground Response Spectra3.7-23.7.1.1.1Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.1.2Site Specific Ground Response Spectra (Set B)3.7-23.7.1.2Design Time Histories3.7-2 3.7.1.2.1Time Histories for Original Site Ground Response Spectra (Set A and Set C)3.7-23.7.1.2.2Time Histories for Site Specific Ground Response Spectra (Set B)3.7-23.7.1.3Critical Damping Values3.7-33.7.1.4Supporting Media for Seismic Category I Structures3.7-33.7.2Seismic System Analysis3.7-3 3.7.2.1Seismic Analysis Methods3.7-43.7.2.1.1Category I Rock-Supported Structures - Original Analyses (Set A)3.7-43.7.2.1.2Category I Rock - Supported Struct ures - Evaluation and New Design or Modification Analyses (Set B and Set B+C)3.7-93.7.2.1.3Category I Soil-Supported Structures - Original Analysis (Set A)3.7-133.7.2.1.4Category I Soil-Supported Structures - Evaluation and New Design/Mod-ification Analysis (Set B and Set B+C)3.7-183.7.2.1.5Category I Pile-Supported Structures - Original Analysis (Set A)3.7-193.7.2.1.6Category I Pile-Supported Structures - Evaluation and New Design/Mod-ification Analyses (Set B and Set B+C)3.7-213.7.2.2Natural Frequencies and Response Loads for NSSS3.7-223.7.2.3Procedures Used for Modeling3.7-22 3.7.2.3.1Other Than NSSS3.7-223.7.2.3.2For NSSS Analysis3.7-223.7.2.4Soil/Structure Interaction3.7-23 3.7.2.4.1Original Analysis (Set A)3.7-233.7.2.4.2Evaluation and New Design or Modification Analyses3.7-233.7.2.5Development of Floor Response Spectra3.7-24 3.7.2.5.1Original Analysis3.7-243.7.2.5.2Evaluation and New Design or Modification Analysis3.7-243.7.2.6Three Components of Earthquake Motion3.7-25 3.7.2.6.1Original Analysis (Set A)3.7-253.7.2.6.2Evaluation and New Design/Modifi cation Analyses (Set B and Set C) 3.7-253.7.2.7Combination of Modal Responses3.7-263.7.2.7.1Other Than NSSS3.7-26 Original Analysis (Set A) 26 Evaluation and New Design or Modification Analyses 263.7.2.7.2NSSS System3.7-27 3.7.2.8Interaction of Non-Cate gory I Structures With Seismic Category I Structures 3.7-29 1-xlviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.2.9Effects of Parameter Variations on Floor Response Spectra3.7-293.7.2.10Use of Constant Vertical Load Factors3.7-293.7.2.10.1Other Than NSSS3.7-29 Original Analysis (Set A) 29 Evaluation and New Design or Modification Analyses 303.7.2.10.2For NSSS3.7-30 3.7.2.11Methods Used to Account for Torsional Effects3.7-303.7.2.12Comparison of Responses - Set A versus Set B3.7-303.7.2.13Methods for Seismic Analysis of Dams3.7-31 3.7.2.14Determination of Category I Structure Overturning Moments3.7-313.7.2.14.1Original Analysis3.7-313.7.2.14.2Evaluation and New Design or Modification Analysis3.7-313.7.2.15Analysis Procedure for Damping3.7-313.7.3Seismic Subsystem Analysis3.7-313.7.3.1Seismic Analysis Methods for Other Than NSSS3.7-31 3.7.3.2Determination of Number of Earthquake Cycles3.7-323.7.3.2.1Category I Systems and Components Other Than NSSS3.7-323.7.3.2.2NSSS System3.7-33 3.7.3.3Procedure Used for Modeling3.7-333.7.3.3.1Other Than NSSS3.7-33 Modeling of Piping Systems for Detailed Rigorous Analysis 33 Modeling of Equipment 33 Modeling of HVAC, Conduit, a nd Cable Tray Subsystems 333.7.3.3.2Modeling of NSSS Subsystems3.7-34 3.7.3.4Basis for Selection of Frequencies3.7-343.7.3.4.1Other Than NSSS3.7-343.7.3.4.2NSSS Basis for Selection of Forcing Frequencies3.7-343.7.3.5Use of Equivalent Static Load Method of Analysis3.7-353.7.3.5.1Other Than NSSS3.7-353.7.3.5.2Use of Equivalent Static Load Method of Analysis for NSSS3.7-363.7.3.6Three Components of Earthquake Motion3.7-363.7.3.6.1Piping Subsystems3.7-363.7.3.6.2HVAC Ducting, Conduit, and Cable Tray Subsystems3.7-363.7.3.6.3Other Than NSSS Equipment and Components3.7-363.7.3.7Combination of Modal Responses3.7-373.7.3.7.1Other Than NSSS3.7-37 3.7.3.7.2Combination of Modal Responses of NSSS3.7-373.7.3.8Analytical Procedures for Piping Other Than NSSS3.7-373.7.3.8.1General3.7-373.7.3.8.2Detailed Seismic Analysis (Rigorous) for Piping Systems3.7-413.7.3.8.3Alternate (Simplified) Analysis for Piping Systems3.7-433.7.3.8.4Seismic Analysis of Piping Systems That Span Two or More Seismic Sup-port Zones Such as Buildings, Porti ons of Buildings, or Primary Compo-nents3.7-44 Table of Contents1-xlixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.3.9Multiple Supported Equipment and Components with Distinct Inputs3.7-443.7.3.9.1Other Than NSSS3.7-443.7.3.9.2Multiple Supported NSSS Equipment a nd Components with Distinct In-puts3.7-443.7.3.10Use of Constant Vertical Load Factors3.7-453.7.3.10.1Use of Constant Load Factors for Equipment Other Than NSSS3.7-453.7.3.10.2Use of Constant Vertical Load Factors for NSSS3.7-453.7.3.11Torsional Effects of Eccentric Masses3.7-453.7.3.11.1Piping Other Than NSSS3.7-45 3.7.3.11.2Torsional Effects of Eccentric Masses of NSSS3.7-463.7.3.12Buried Seismic Category I Piping Systems3.7-463.7.3.13Interaction of Other Piping with Seismic Category I Piping3.7-523.7.3.14Seismic Analyses for Fuel Elements , Control Rod Assemblies, Control Rod Drives, and Reactor Internals3.7-523.7.3.15Analysis Procedure for Damping3.7-54 3.7.3.16Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-543.7.3.16.1Dynamic Analysis Method For Equipment and Components3.7-553.7.3.16.2Simplified Dynamic Analysis Method For Equipment and Components 3.7-553.7.3.16.3Equivalent Static Load Method3.7-56 3.7.3.16.4Testing Method3.7-563.7.3.16.5Equipment and Component Mounting Considerations3.7-563.7.3.17Seismic Analysis and Design of HVAC Duct and Duct Support Systems3.7-573.7.3.17.1Description of HVAC Duct and Duct Support Subsystems3.7-573.7.3.17.2Applicable Codes, Standards, and Specifications3.7-573.7.3.17.3Loads and Load Combinations3.7-583.7.3.17.4Analysis and Design Procedures3.7-593.7.3.17.5Structural Acceptance Criteria3.7-59 3.7.3.17.6Materials and Quality Control3.7-603.7.3.18Seismic Qualification of Main Control Room Suspended Ceiling and Air Deliv-ery Components3.7-61 3.7.4Seismic Instrumentation Program3.7-613.7.4.1Comparison with Regulatory Guide 1.123.7-613.7.4.2Location and Description of Instrumentation3.7-613.7.4.3Control Room Operator Notification3.7-643.7.4.4Controlled Shutdown Logic3.7-643.7.4.5Comparison of Measured and Predicted Responses3.7-653.7.4.5.1Retrieval of Data3.7-653.7.4.5.2Evaluation of Recorded Earthquake3.7-663.8DESIGN OF CATEGORY I STRUCTURES3.8-13.8.1Concrete Shield Building3.8-1 1-lTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.1.1Description of the Shield Building3.8-13.8.1.1.1Equipment Hatch Doors and Sleeves3.8-23.8.1.2Applicable Codes, Standards, and Specifications3.8-33.8.1.3Loads and Loading Combinations3.8-53.8.1.4Design and Analysis Procedures3.8-73.8.1.5Structural Acceptance Criteria3.8-10 3.8.1.6Materials, Quality Control and Special Construction Techniques3.8-113.8.1.6.1Materials3.8-113.8.1.6.2Quality Control3.8-12 3.8.1.6.3Construction Techniques3.8-133.8.2Testing and Inservice Surveillance Requirements3.8-133.8.2Steel Containment System3.8-13.8.2.1Description of the Containment and Penetrations3.8-13.8.2.1.1Description of the Containment3.8-13.8.2.1.2Description of Penetrations3.8-1 3.8.2.2Applicable Codes, Standards and Specifications3.8-33.8.2.2.1Codes3.8-33.8.2.2.2Design Specification Summary3.8-4 3.8.2.2.3NRC Regulatory Guides3.8-63.8.2.3Loads and Loading Combinations3.8-73.8.2.3.1Design Loads3.8-7 3.8.2.3.2Loading Conditions3.8-93.8.2.4 Design and Analysis Procedures3.8-113.8.2.4.1Introduction3.8-11 3.8.2.4.2Static Stress Analysis3.8-123.8.2.4.3Dynamic Seismic Analysis3.8-123.8.2.4.4Non-Axisymmetric Pressure Loading Analysis3.8-133.8.2.4.5Thermal Analysis3.8-143.8.2.4.6Penetrations Analysis3.8-143.8.2.4.7Interaction of Containment and Attached Equipment3.8-163.8.2.4.8Anchorage3.8-173.8.2.5Structural Acceptance Criteria3.8-183.8.2.5.1Margin of Safety3.8-18 3.8.2.6Materials, Quality Control, and Special Construction Techniques3.8-183.8.2.6.1Materials - General3.8-183.8.2.6.2Corrosion Protection3.8-21 3.8.2.6.3Protective Coatings3.8-233.8.2.6.4Tolerances3.8-243.8.2.6.5Vessel Material Inspection and Test3.8-243.8.2.6.6Impact Testing3.8-253.8.2.6.7Post-Weld Heat Treatment3.8-253.8.2.6.8Welding3.8-253.8.2.7Testing and Inservice Inspection Requirements3.8-25 Table of Contents 1-liWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.2.7.1Bottom Liner Plates Test3.8-253.8.2.7.2Vertical Wall and Dome Tests3.8-253.8.2.7.3Soap Bubble Tests3.8-253.8.2.7.4Overpressure Tests3.8-263.8.2.7.5Leakage Rate Test3.8-263.8.2.7.6Operational Testing3.8-263.8.2.7.7Leak Testing Airlocks3.8-263.8.2.7.8Penetration Tests3.8-273.8.2.7.9Inservice Inspection Requirements3.8-273.8.3Concrete Interior Structure3.8-13.8.3.1Description of the Interior Structure3.8-13.8.3.2General3.8-1 3.8.3.3Containment Floor Structural Fill Slab3.8-13.8.3.4Reactor Cavity Wall3.8-23.8.3.5Compartment Above Reactor3.8-2 3.8.3.6Refueling Canal Walls and Floor (Divider Barrier)3.8-33.8.3.7Crane Wall3.8-33.8.3.8Steam Generator Compartments (Divider Barrier)3.8-5 3.8.3.9Pressurizer Compartment (Divider Barrier)3.8-53.8.3.10Divider Deck at Elevation 756.63 (Divider Barrier)3.8-53.8.3.11Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier)3.8-53.8.3.12Penetrations Through the Divider Barrier Canal Gate3.8-63.8.3.13Applicable Codes, Standards and Specifications3.8-73.8.3.14Loads and Loading Combinations3.8-13 3.8.3.15Design and Analysis Procedures3.8-163.8.3.16General3.8-163.8.3.17Structural Fill Slab on Containment Floor3.8-163.8.3.18Reactor Cavity Wall3.8-163.8.3.19Compartment Above Reactor3.8-183.8.3.20Seals Between Upper and Lower Compartments3.8-183.8.3.21Refueling Canal Walls and Floor (Divider Barrier)3.8-193.8.3.22Crane Wall3.8-203.8.3.23Steam Generator Compartments (Divider Barrier)3.8-23 3.8.3.24Pressurizer Compartment (Divider Barrier)3.8-253.8.3.25Operating Deck at Elevation 756.63 (Divider Barrier)3.8-263.8.3.26Ice Condenser Support Floor El evation 744.5 (Divider Barrier)3.8-273.8.3.27Ice Condenser3.8-283.8.3.28Penetrations Through the Divider Barrier3.8-293.8.3.29Structural Acceptance Criteria3.8-313.8.3.30General3.8-313.8.3.31Structural Fill Slab on Containment Floor3.8-313.8.3.32Reactor Cavity Wall and Compartment Above Reactor3.8-313.8.3.33Refueling Canal Walls and Floor3.8-32 1-liiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.3.34Crane Wall3.8-323.8.3.35Steam Generator and Pressurizer Compartment3.8-323.8.3.36Operating Deck at Elevation 756.633.8-323.8.3.37Ice Condenser Support Floor Elevation 744.53.8-323.8.3.38Penetrations Through the Divider Barrier3.8-323.8.3.39Personnel Access Doors in Crane Wall3.8-333.8.3.40Seals Between Upper and Lower Compartments3.8-333.8.3.41Ice Condenser3.8-333.8.3.42Materials, Quality Control and Special Construction Techniques3.8-343.8.3.43Materials3.8-343.8.3.44Quality Control3.8-353.8.3.45Construction Technique3.8-36 3.8.3.46Ice Condenser3.8-363.8.3.47Testing and Inservice Surveillance Requirements3.8-383.8.3.48Environmental Effects3.8-38 3.8.3.49Interface Control 3.8-393.8.4Other Category I Structures3.8-13.8.4.1Description of the Structures3.8-1 3.8.4.2Auxiliary-Control Building3.8-13.8.4.3Diesel Generator Building3.8-103.8.4.4Category I Water Tanks and Pipe Tunnels3.8-12 3.8.4.5Class 1E Electrical System Manholes and Duct Runs3.8-133.8.4.6North Steam Valve Room3.8-133.8.4.7Intake Pumping Station and Retaining Walls3.8-14 3.8.4.8Miscellaneous Essential Raw Cooling Water (ERCW) Structures3.8-153.8.4.9Additional Diesel Generator Building3.8-163.8.4.10Applicable Codes, Standards, and Specifications3.8-173.8.4.11List of Documents3.8-173.8.4.12Basis for Use of the 1963 Edition of ACI 3183.8-193.8.4.13Loads and Loading Combinations3.8-21 3.8.4.14Description of Loads3.8-213.8.4.15Load Combinations and Allowable Stresses3.8-223.8.4.16Design and Analysis Procedures3.8-23 3.8.4.17Auxiliary-Control Building3.8-233.8.4.18Diesel Generator Building3.8-303.8.4.19Category I Water Tanks and Pipe Tunnels3.8-31 3.8.4.20Class 1E Electrical System Manholes3.8-313.8.4.21North Steam Valve Room3.8-313.8.4.22Intake Pumping Station and Reta ining Walls Pumping Station3.8-323.8.4.23Miscellaneous ERCW Structures3.8-323.8.4.24Additional Diesel Generator Building3.8-333.8.4.25Structural Acceptance Criteria3.8-353.8.4.26Concrete3.8-35 Table of Contents1-liiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.4.27Structural and Miscellaneous Steel3.8-353.8.4.28Miscellaneous Components of the Auxiliary Building3.8-363.8.4.29Intake Pumping Station Traveling Water Screens3.8-373.8.4.30Diesel Generator Building Doors and Bulkheads3.8-373.8.4.31Additional Diesel Generator Building Missile Barriers3.8-373.8.4.32Materials, Quality Control, and Special Construction Techniques General3.8-373.8.4.33Materials3.8-373.8.4.34Quality Control3.8-383.8.4.35Special Construction Techniques3.8-383.8.4.36Testing and Inservice Surveillance Requirements3.8-383.8.4.37Concrete and Struct ural Steel Portions of Structures3.8-383.8.4.38Miscellaneous Components of Auxiliary-Control Building3.8-393.8.4.39Deleted by Amendment 793.8-403.8.4.40Miscellaneous Components of the Intake Pumping Station3.8-403.8.5Foundations and Concrete Supports3.8-13.8.5.1Description of Foundations and Supports3.8-13.8.5.1.1Primary Containment3.8-13.8.5.1.2Foundations of Other Category I Structures3.8-13.8.5.2Applicable Codes, Standards, and Specifications3.8-33.8.5.3Loads and Loading Combinations3.8-33.8.5.4Design and Analysis Procedure3.8-4 3.8.5.4.1Primary Containment Foundation3.8-43.8.5.4.2Auxiliary-Control Building3.8-43.8.5.4.3Intake Pumping Station3.8-4 3.8.5.4.4Soil-Supported Structures3.8-43.8.5.4.5Pile Supported Structures3.8-53.8.5.5Structural Acceptance Criteria3.8-53.8.5.5.1Primary Containment Foundation3.8-53.8.5.5.2Foundations of Other Category I Structures Auxiliary-Control Building3.8-53.8.5.6Materials, Quality Control, and Special Construction Techniques3.8-63.8.5.6.1Materials3.8-63.8.5.6.2Quality Control3.8-73.8.5.6.3Special Construction Techniques3.8-73.8.6Category I(L) Cranes3.8-13.8.6.1Polar Cranes3.8-13.8.6.1.1Description3.8-13.8.6.1.2Applicable Codes, Standards, and Specifications3.8-13.8.6.1.3Loads, Loading Combinations, and Allowable Stresses3.8-23.8.6.1.4Design and Analysis Procedure3.8-23.8.6.1.5Structural Acceptance Criteria3.8-23.8.6.1.6Materials, Quality Controls, and Special Construction Techniques3.8-33.8.6.1.7Testing and Inservice Surveillance Requirements3.8-3 1-livTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.6.1.8Safety Features3.8-33.8.6.2Auxiliary Building Crane3.8-43.8.6.2.1Description3.8-43.8.6.2.2Applicable Codes, Standards, and Specifications3.8-53.8.6.2.3Loads, Loading Combinations, and Allowable Stresses3.8-53.8.6.2.4Design and Analysis Procedure3.8-5 3.8.6.2.5Structural Acceptance Criteria3.8-63.8.6.2.6Materials, Quality Controls, and Special Construction Techniques3.8-63.8.6.2.7Testing and Inservice Surveillance Requirements3.8-73.8.6.2.8Safety Features3.8-73.8ASHELL TEMPERATURE TRANSIENTS3.8-13.8BBUCKLING STRESS CRITERIA3.8-13.8B.1INTRODUCTION3.8-13.8B.2SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS3.8-13.8B.2.1Circular Cylindrical Shells Under Axial Compression3.8-13.8B.2.2Circular Cylindrical Shells in Circumferential Compression3.8-23.8B.2.3Circular Cylindrical Shells Under Torsion3.8-23.8B.2.4where a is the effective length and b is the circumference of the cylinder. The coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending3.8-33.8B.2.5Circular Cylindrical Shell Under Combined Loads3.8-33.8B.3SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS3.8-53.8B.4SPHERICAL SHELLS3.8-73.8B.2.1The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation:3.8-73.8B.2.2Spherical Shell Under Combined Loads3.8-73.8B.3FACTOR OF SAFETY3.8-83.8CDOCUMENTATION OF CB&I COMPUTER PROGRAMS3.8-13.8C.1INTRODUCTION3.8-1 3.8C.2PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE3.8-13.8C.3PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES3.8-13.8C.4PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS3.8-33.8C.5PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS3.8-33.8C.6PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E13743.8-43.8C.7PROGRAM E1374-SHELL DYNAMIC ANALYSIS3.8-53.8C.7.1Introduction3.8-53.8C.8PROGRAM E1622-LOAD GENERATI ON PREPROCESSOR FOR PROGRAM E1374 3.8-6 Table of Contents1-lvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8C.9PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION3.8-73.8C.10PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS3.8-73.8C.11PROGRAM 119-CHECK of FLANGE DESIGN3.8-73.8C.12PROGRAM 772-NOZZLE REINFORCEMENT CHECK3.8-73.8C.13PROGRAM 1027-WRC 107 STRESS INTEN SITIES AT L OADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WI TH ROUND OR SQUARE ATTACHMENT3.8-83.8C.14PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES3.8-83.8DCOMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS3.8-13.8ECODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 19793.8-13.8E.1Application Codes and Standards3.8-13.8E.2Load Definitions3.8-1 3.8E.3Load Combinations - Concrete3.8-33.8E.4Load Combinations - Structural Steel3.8-53.9MECHANICAL SYSTEMS AND COMPONENTS3.9-13.9.1General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-13.9.1.1Design Transients3.9-1 3.9.1.2Computer Programs Used in Analysis and Design3.9-13.9.1.2.1Other Than NSSS Systems, Components, Equipment, and Supports3.9-13.9.1.2.2Programs Used for Category I Components of NSSS3.9-3 3.9.1.3Experimental Stress Analysis3.9-33.9.1.4Consideration for the Evaluation of the Faulted Condition3.9-33.9.1.4.1Subsystems and Components Analyzed by Westinghouse3.9-33.9.1.4.2Subsystems and Components Analyzed by TVA3.9-33.9.2Dynamic Testing and Analysis3.9-43.9.2.1Preoperational Vibration and Dynamic Effects Testing on Piping3.9-43.9.2.2Seismic Qualification Testing of Safety-Related Mechanical Equipment3.9-63.9.2.3Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions3.9-8 3.9.2.4Preoperational Flow-Induced Vibration Testing of Reactor Internals3.9-103.9.2.5Dynamic System Analysis of the R eactor Internals Under Faulted Conditions 3.9-123.9.2.5.1Evaluation of Reactor Internals fo r Limited Displacement RPV Inlet and Outlet Nozzle Break3.9-173.9.2.6Correlations of Reactor Internals Vibration Tests Wi th the Analytical Results 3.9-193.9.3ASME Code Class 1, 2 and 3 Component s, Component Supports and Core Support Structures 3.9-20 1-lviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.9.3.1Loading Combinations, Design Transients, and Stress Limits3.9-203.9.3.1.1Subsystems and Components Supplied by Westinghouse3.9-20 Plant Conditions and Design Loading Combinations For ASME Code Cla ss 2 and 3 Components Supplied by Westinghouse 21 Design Loading Combinations by Westinghouse 21 Design Stress Limits By Westinghouse 22 3.9.3.1.2Subsystems and Components Analyzed or Specified by TVA3.9-223.9.3.2Pumps and Valve Operability Assurance3.9-273.9.3.2.1Active* ASME Class 1, 2, & 3 Pumps and Valves3.9-27 3.9.3.2.2Operability Assurance3.9-28 Westinghouse Scope of Supply 28 TVA Scope of Supply 33 3.9.3.2.3Criteria For Assuring Functional Adequacy of Active Seismic Category I Fluid System Components (Pumps and Valves) and Associated Essential Auxiliary Equipment3.9-343.9.3.3Design and Installation Details for Mounting of Pressure Relief Devices3.9-393.9.3.4Component Supports3.9-423.9.3.4.1Subsystem and Component Supports Analyzed or Specified by Westing-house3.9-423.9.3.4.2Subsystem and Component Supports Analyzed or Specified by TVA3.9-433.9.4Control Rod System3.9-463.9.4.1Descriptive Information of CRDS3.9-463.9.4.2Applicable CRDS Design Specifications3.9-463.9.4.3Design Loadings, Stress Limits, and Allowable Deformations3.9-463.9.4.4CRDS Performance Assurance Program3.9-473.9.5Reactor Pressure Vessel Internals3.9-473.9.5.1Design Arrangements3.9-473.9.5.2Design Loading Conditions3.9-473.9.5.3Design Loading Categories3.9-47 3.9.5.4Design Basis3.9-473.9.6Inservice Testing of Pumps and Valves3.9-473.10SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIP-MENT3.10-13.10.1Seismic Qualification Criteria3.10-13.10.2Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-63.10.3Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables3.10-63.10.3.1Electrical Equipment and Instrumentation Assemblies3.10-73.10.3.2Cable Trays and Supports3.10-73.10.3.2.1Cable Trays3.10-73.10.3.2.2Supports3.10-7 Table of Contents 1-lviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.10.3.3Conduit and Supports3.10-83.10.3.3.1Conduit3.10-83.10.3.3.2Supports3.10-83.10.3.4Conduit Banks3.10-93.10.4Operating License Review3.10-93.10.4.1TVA Supplied Instrumentation and Electrical Equipment3.10-93.11ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT3.11-13.11.1 Equipment Identification and Environmental Conditions3.11-13.11.1.1Identification of Safety Systems and Justification3.11-13.11.1.2Identification of Equipment in Harsh Environments3.11-13.11.2Environmental Conditions3.11-23.11.2.1Harsh Environment3.11-23.11.2.2Mild Environment3.11-3 3.11.3Electrical Equipment Within the Scope of 10 CFR 50.493.11-43.11.4Qualification Tests and Analyses3.11-43.11.5Qualification Test Results3.11-4 3.11.6Loss of Heating, Ventilating, and Air-Conditioning (HVAC)3.11-43.11.7Estimated Chemical and Radiation Environment3.11-43.11.7.1Chemical Spray3.11-4 3.11.7.2Radiation3.11-53.11.7.2.1Inside Containment3.11-53.11.7.2.2Radiation - Auxiliary Building Spaces3.11-64.0REACTOR4.1
SUMMARY
DESCRIPTION4.1-14.2MECHANICAL DESIGN4.2-14.2.1Fuel4.2-24.2.1.1Design Bases4.2-2 4.2.1.1.1Fuel Rods4.2-24.2.1.1.2Fuel Assembly Structure4.2-34.2.1.2Design Description4.2-5 4.2.1.2.1Fuel Rods4.2-64.2.1.2.2Fuel Assembly Structure4.2-64.2.1.3Design Evaluation4.2-104.2.1.3.1Fuel Rods4.2-104.2.1.3.2Fuel Assembly Structure4.2-17 4.2.1.3.3Operational Experience4.2-184.2.1.3.4Test Rod and Test Assembly Experience4.2-184.2.1.3.5Evaluation of the Reactor Core for a Limiting LOCA Load - Accumulator Line Break4.2-184.2.1.4Tests and Inspections4.2-19 1-lviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.2.1.4.1Quality Assurance Program4.2-194.2.1.4.2Quality Control4.2-194.2.1.4.3Tests and Inspections by Others4.2-224.2.1.4.4Onsite Inspection4.2-224.2.2Reactor Vessel Internals4.2-224.2.2.1Design Bases4.2-22 4.2.2.2Description and Drawings4.2-234.2.2.3Design Loading Conditions4.2-274.2.2.4Design Loading Categories4.2-27 4.2.2.5Design Criteria Basis4.2-284.2.3Reactivity Control System4.2-294.2.3.1Design Bases4.2-29 4.2.3.1.1Design Stresses4.2-294.2.3.1.2Material Compatibility4.2-294.2.3.1.3Reactivity Control Components4.2-294.2.3.1.4Control Rod Drive Mechanisms4.2-314.2.3.2Design Description4.2-324.2.3.2.1Reactivity Control Components4.2-334.2.3.2.2Control Rod Drive Mechanism (CRDM)4.2-374.2.3.3 Design Evaluation4.2-424.2.3.3.1Reactivity Control Components4.2-424.2.3.3.2Control Rod Drive Mechanism4.2-484.2.3.4Tests, Verification, and Inspections4.2-514.2.3.4.1Reactivity Control Components4.2-514.2.3.4.2Control Rod Drive Mechanisms4.2-524.2.3.5Instrumentation Applications4.2-534.2.4Tritium Producing Burnable Absorber Rod - Tritium Production Core4.2-544.3NUCLEAR DESIGN4.3-14.3.1DESIGN BASES4.3-14.3.1.1Fuel Burnup4.3-2 4.3.1.2Negative Reactivity Feedback s (Reactivity Coefficient)4.3-24.3.1.3Control of Power Distribution4.3-34.3.1.4Maximum Controlled Reactivity Insertion Rate4.3-34.3.1.5Shutdown Margins With Vessel Head in Place4.3-44.3.1.6Shutdown Margin for Refueling4.3-44.3.1.7Stability4.3-5 4.3.1.8Anticipated Transients Without Trip4.3-54.3.2Description4.3-54.3.2.1Nuclear Design Description4.3-54.3.2.2Power Distributions4.3-74.3.2.2.1Definitions4.3-7 4.3.2.2.2Radial Power Distributions4.3-94.3.2.2.3Assembly Power Distributions4.3-9 Table of Contents1-lixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.3.2.2.4Axial Power Distribution4.3-94.3.2.2.5Limiting Power Distributions4.3-104.3.2.2.6Experimental Verification of Power Distribution Analysis4.3-144.3.2.2.7Testing4.3-154.3.2.2.8Monitoring Instrumentation4.3-164.3.2.3Reactivity Coefficients4.3-16 4.3.2.3.1Fuel Temperature (Doppler) Coefficient4.3-164.3.2.3.2Moderator Coefficients4.3-174.3.2.3.3Power Coefficient4.3-18 4.3.2.3.4Comparison of Calculated and Experimental Reactivity Coefficients4.3-184.3.2.3.5Reactivity Coefficients Used in Transient Analysis4.3-194.3.2.4Control Requirements4.3-194.3.2.4.1Doppler4.3-204.3.2.4.2Variable Average Moderator Temperature4.3-204.3.2.4.3Redistribution4.3-204.3.2.4.4Void Content4.3-204.3.2.4.5Rod Insertion Allowance4.3-20 4.3.2.4.6Burnup4.3-204.3.2.4.7Xenon and Samarium Concentrations4.3-214.3.2.4.8pH Effects4.3-21 4.3.2.4.9Experimental Confirmation4.3-214.3.2.5Control4.3-214.3.2.5.1Chemical Shim4.3-21 4.3.2.5.2Rod Cluster Control Assemblies4.3-214.3.2.5.3Burnable Absorbers4.3-224.3.2.5.4Peak Xenon Startup4.3-22 4.3.2.5.5Load Follow Control and Xenon Control4.3-224.3.2.5.6Burnup4.3-234.3.2.6Control Rod Patterns and Reactivity Worth4.3-234.3.2.7Criticality of Fuel Assemblies4.3-244.3.2.8Stability4.3-284.3.2.8.1Introduction4.3-28 4.3.2.8.2Stability Index4.3-284.3.2.8.3Prediction of the Core Stability4.3-294.3.2.8.4Stability Measurements4.3-29 4.3.2.8.5Comparison of Calculations with Measurements4.3-314.3.2.8.6Stability Control and Protection4.3-314.3.2.9Vessel Irradiation4.3-324.3.3Analytical Methods4.3-334.3.3.1Fuel Temperature (Doppler) Calculations4.3-334.3.3.2Macroscopic Group Constants4.3-344.3.3.3Spatial Few-Group Diffusion Calculations4.3-35 1-lxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.4THERMAL AND HYDRAULIC DESIGN4.4-14.4.1Design Bases4.4-14.4.1.1Departure from Nucleate Boiling Design Basis4.4-14.4.1.2Fuel Temperature Design Basis4.4-24.4.1.3Core Flow Design Basis4.4-3 4.4.1.4Hydrodynamic Stability Design Bases4.4-34.4.1.5Other Considerations4.4-34.4.2Description4.4-4 4.4.2.1Summary Comparison4.4-44.4.2.2Fuel and Cladding Temperatures4.4-44.4.2.2.1UO2 Thermal Conductivity4.4-4 4.4.2.2.2Radial Power Distribution in UO2 Fuel Rods4.4-54.4.2.2.3Gap Conductance4.4-64.4.2.2.4Surface Heat Transfer Coefficients4.4-64.4.2.2.5Fuel Clad Temperatures4.4-64.4.2.2.6Treatment of Peaking Factors4.4-64.4.2.3Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology 4.4-74.4.2.3.1Departure from Nucleate Boiling Technology4.4-74.4.2.3.2Definition of Departure from Nucleate Boiling Ratio4.4-84.4.2.3.3Mixing Technology4.4-104.4.2.3.4Hot Channel Factors4.4-114.4.2.3.5Effects of Rod Bow on DNBR4.4-13 4.4.2.4Flux Tilt Considerations4.4-134.4.2.5Void Fraction Distribution4.4-144.4.2.6Deleted4.4-14 4.4.2.7Core Pressure Drops and Hydraulic Loads4.4-144.4.2.7.1Core Pressure Drops4.4-144.4.2.7.2Hydraulic Loads4.4-15 4.4.2.8Correlation and Physical Data4.4-154.4.2.8.1Surface Heat Transfer Coefficients4.4-154.4.2.8.2Total Core and Vessel Pressure Drop4.4-164.4.2.8.3Void Fraction Correlation4.4-174.4.2.9Thermal Effects of Operational Transients4.4-174.4.2.10Uncertainties in Estimates4.4-18 4.4.2.10.1Uncertainties in Fuel and Clad Temperatures4.4-184.4.2.10.2Uncertainties in Pressure Drops4.4-184.4.2.10.3Uncertainties Due to Inlet Flow Maldistribution4.4-194.4.2.10.4 Uncertainties in DNB Correlation4.4-194.4.2.10.5 Uncertainties in DNBR Calculations4.4-194.4.2.10.6Uncertainties in Flow Rates4.4-194.4.2.10.7Uncertainties in Hydraulic Loads4.4-194.4.2.10.8Uncertainties in Mixing Coefficient4.4-204.4.2.11Plant Configuration Data4.4-20 Table of Contents1-lxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.4.3EVALUATION4.4-204.4.3.1Core Hydraulics4.4-204.4.3.1.1Flow Paths Considered in Core Pressure Drop and Thermal Design4.4-204.4.3.1.2Inlet Flow Distributions4.4-214.4.3.1.3Empirical Friction Factor Correlations4.4-224.4.3.2Influence of Power Distribution4.4-224.4.3.2.1Nuclear Enth alpy Rise Hot Channel Factor, FNH4.4-224.4.3.2.2Axial Heat Flux Distributions4.4-23 4.4.3.3Core Thermal Response4.4-244.4.3.4Analytical Techniques4.4-244.4.3.4.1Core Analysis4.4-24 4.4.3.4.2Fuel Temperatures4.4-264.4.3.4.3Hydrodynamic Instability4.4-264.4.3.5Hydrodynamic and Flow Power Coupled Instability4.4-264.4.3.6Temperature Transient Effects Analysis4.4-284.4.3.7Potentially Damaging Temperature Effects During Transients4.4-294.4.3.8Energy Release During Fuel Element Burnout4.4-29 4.4.3.9Deleted4.4-304.4.3.10 Fuel Rod Behavior-Effects from Coolant Flow Blockage4.4-304.4.4Testing and Verification4.4-31 4.4.4.1Tests Prior to Initial Criticality4.4-314.4.4.2Initial Power and Plant Operation4.4-314.4.4.3Component and Fuel Inspections4.4-31 4.4.5Instrumentation Application4.4-314.4.5.1Incore Instrumentation4.4-314.4.5.2Overtemperature and Overpower T Instrumentation4.4-324.4.5.3Instrumentation to Limit Maximum Power Output4.4-325.0REACTOR COOLANT SYSTEM5.1
SUMMARY
DESCRIPTION5.1-15.1.1Schematic Flow Diagram5.1-65.1.2Piping and Instrumentation Diagrams5.1-6 5.1.3Elevation Drawing5.1-65.2INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY5.2-15.2.1Design of Reactor Coolant Pressure Boundary Components5.2-25.2.1.1Performance Objectives5.2-25.2.1.2Design Parameters5.2-3 5.2.1.3Compliance with 10 CFR Part 50, Section 50.55a5.2-45.2.1.4Applicable Code Cases5.2-45.2.1.5Design Transients5.2-5 5.2.1.6Identification of Active Pumps and Valves5.2-14 1-lxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.1.7Design of Active Pumps and Valves5.2-145.2.1.8Inadvertent Operation of Valves5.2-145.2.1.9Stress and Pressure Limits5.2-155.2.1.10Stress Analysis for Structural Adequacy5.2-155.2.1.10.1Loading Conditions5.2-155.2.1.10.2Analysis of the Reactor Coolant Loop and Supports5.2-15 5.2.1.10.3Reactor Coolant Loop Models and Methods5.2-175.2.1.10.4Primary Component Supports Models and Methods5.2-225.2.1.10.5Analysis of Primary Components5.2-24 5.2.1.10.6Reactor Vessel Support L0CA Loads5.2-26 Introduction 26Interface Information 27
Loading Conditions 27 Reactor Vessel and Internals Modeling 28Analytical Methods 30
Results of the Analysis 305.2.1.10.7Stress Criteria fo r Class 1 Components and Component Supports5.2-325.2.1.10.8Computer Program Descriptions5.2-335.2.1.10.9LOCA Evaluation of the Control Rod Drive Mechanisms5.2-345.2.1.11Analysis Methods For Faulted Conditions5.2-345.2.1.12Protection Against Environmental Factors5.2-345.2.1.13Compliance With Code Requirements5.2-345.2.1.14Stress Analysis For Faulted Conditions Loadings5.2-345.2.1.15Stress Levels in Category I Systems5.2-34 5.2.1.16Analytical Methods for Stresses in Pumps and Valves5.2-345.2.1.17Analytical Methods for Evaluation of Pump Speed and Bearing Integrity5.2-34 5.2.1.18Operation of Active Valves Under Transient Loadings5.2-355.2.2Overpressurization Protection5.2-355.2.2.1Location of Pressure Relief Devices5.2-355.2.2.2Mounting of Pressure Relief Devices5.2-355.2.2.3Report on Overpressure Protection5.2-355.2.2.4RCS Pressure Control During Low Temperature Operation5.2-375.2.2.4.1System Operation5.2-375.2.2.4.2Pressure Transient Analyses5.2-37 Evaluation of Low Temperature Overpressure Transients 37 Operating Basis Earthquake Evaluation 385.2.2.4.3Administrative Procedures5.2-385.2.3General Material Considerations5.2-405.2.3.1Material Specifications5.2-405.2.3.2Compatibility With Reactor Coolant5.2-41 5.2.3.3Compatibility With External Insulation and Environmental Atmosphere5.2-425.2.3.4Chemistry of Reactor Coolant5.2-425.2.4Fracture Toughness5.2-43 Table of Contents 1-lxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.4.1Compliance With Code Requirements5.2-435.2.4.2Acceptable Fracture Energy Levels5.2-435.2.4.3Operating Limitations During Startup and Shutdown5.2-435.2.5Austenitic Stainless Steel5.2-465.2.5.1Cleaning and Contamination Protection Procedures5.2-465.2.5.2Solution Heat Treatment Requirements5.2-47 5.2.5.3Material Inspection Program5.2-485.2.5.4Unstablilized Austenitic Stainless Steels5.2-485.2.5.5Prevention of Intergranular Attack of Unstabilized Austenit ic Stainless Steels 5.2-485.2.5.6Retesting Unstabilized Au stenitic Stainless Steel Exposed to Sensitization Temperatures5.2-51 5.2.5.7Control of Delta Ferrite in Austenitic Stainless Steel Welding5.2-515.2.6Pump Flywheels5.2-535.2.6.1Design Basis5.2-53 5.2.6.2Fabrication and Inspection5.2-535.2.6.3Acceptance Criteria and Compliance with Regulatory Guide 1.145.2-545.2.7RCPB Leakage Detection Systems5.2-55 5.2.7.1Collection of Identified Leakage5.2-555.2.7.2Unidentified Leakage to Containment5.2-565.2.7.3Methods of Detection5.2-56 5.2.7.3.1Containment Air Particulate Monitors and Containment Radioactive5.2-565.2.7.3.2Reactor Building Floor and Equipm ent Drain (RBF&ED) Sump and the 5.2-575.2.7.3.3Humidity Monitors5.2-585.2.7.3.4Temperature Monitors5.2-58 5.2.7.4Intersystem Leakage Detection5.2-585.2.7.4.1ECCS Intersystem Leakage5.2-585.2.7.4.2Condenser Vacuum Pump Air Exhaust Monitors5.2-605.2.7.4.3Component Cooling System Liquid Effluent Monitors5.2-615.2.7.4.4Steam Generator Blowdown Liquid Effluent Monitor5.2-625.2.7.5Unidentified Leakage System Sensitivity and Response Time5.2-625.2.7.5.1Containment Air Particulate Monitors and Containment Radioactive Gas Monitors5.2-625.2.7.5.2Reactor Building Floor and Equipm ent Drain (RBF&ED) Pocket Sump 5.2-635.2.7.5.3Humidity Monitors5.2-635.2.7.5.4Temperature Monitors5.2-645.2.7.6Seismic Capability5.2-645.2.7.7Indicators and Alarms5.2-64 5.2.7.7.1Radiation Monitors5.2-645.2.7.7.2RBF&ED Pocket Sump Level Monitors5.2-645.2.7.7.3Humidity Monitors5.2-64 1-lxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.7.7.4Temperature Monitors5.2-645.2.7.8Testing5.2-655.2.8Inservice Inspection of ASME Code Class 1 Components5.2-655.2.8.1Components Subject to Examination and/or Test5.2-655.2.8.2Accessibility5.2-655.2.8.3Examination Techniques and Procedures5.2-675.2.8.4Inspection Intervals5.2-675.2.8.5Examination Categories and Requirements5.2-675.2.8.6Evaluation of Examination Results5.2-675.2.8.7System Pressure Tests5.2-675.3THERMAL HYDRAULIC SYSTEM DESIGN5.3-15.3.1Analytical Methods and Data5.3-1 5.3.2Operating Restrictions On Pumps5.3-15.3.3Power-Flow Operating Map (BWR)5.3-15.3.4Temperature-Power Operating Map5.3-1 5.3.5Load Following Characteristics5.3-15.3.6Transient Effects5.3-15.3.7Thermal and Hydraulic Characteristics Summary Table5.3-15.4REACTOR VESSEL AND APPURTENANCES5.4-15.4.1Design Bases5.4-15.4.1.1Codes and Specifications5.4-1 5.4.1.2Design Transients5.4-15.4.1.3Protection Against Non-Ductile Failure5.4-25.4.1.4Inspection5.4-2 5.4.2Description5.4-25.4.2.1Fabrication Processes5.4-35.4.2.2Protection of Closure Studs5.4-4 5.4.3Evaluation5.4-45.4.3.1Steady State Stresses5.4-45.4.3.2Fatigue Analysis Based on Transient Stresses5.4-45.4.3.3Thermal Stresses Due to Gamma Heating5.4-45.4.3.4Thermal Stresses Due to Loss of Coolant Accident5.4-45.4.3.5Heatup and Cooldown5.4-4 5.4.3.6Irradiation Surveillance Programs5.4-45.4.3.6.1Measurement of Integrated Fast Ne utron (E>l.0MeV) Flux at the Irradia-tion Samples5.4-6 Determination of Sensor Reaction Rates 7Corrections to Reaction Rate Data 8
Least Squares Adjustment Procedure 95.4.3.6.2Calculation of Integrated Fast Neutron (E > 1.0 MeV) Flux at the Irradia-tion Samples5.4-10 Reference Forward Calculation 11 Table of Contents1-lxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle PageCycle Specific Adjoint Calculations 115.4.3.7Capability for Annealing the Reactor Vessel5.4-125.4.4Tests and Inspections5.4-125.4.4.1Ultrasonic Examinations5.4-135.4.4.2Penetrant Examinations5.4-135.4.4.3Magnetic Particle Examination5.4-13 5.4.4.4Inservice Inspection5.4-145.5COMPONENT AND SUBSYSTEM DESIGN5.5-15.5.1Reactor Coolant Pumps5.5-1 5.5.1.1Design Bases5.5-15.5.1.2Design Description5.5-15.5.1.3Design Evaluation5.5-3 5.5.1.3.1Pump Performance5.5-35.5.1.3.2Coastdown Capability5.5-45.5.1.3.3Flywheel Integrity5.5-4 5.5.1.3.4Bearing Integrity5.5-45.5.1.3.5Locked Rotor5.5-45.5.1.3.6Critical Speed5.5-5 5.5.1.3.7Missile Generation5.5-55.5.1.3.8Pump Cavitation5.5-55.5.1.3.9Pump Overspeed Considerations5.5-5 5.5.1.3.10Anti-Reverse Rotation Device5.5-65.5.1.3.11Shaft Seal Leakage5.5-65.5.1.3.12Seal Discharge Piping5.5-6 5.5.1.3.13Spool Piece5.5-75.5.1.3.14Motor Air Coolers5.5-75.5.1.3.15Discharge Nozzle Weir5.5-7 5.5.1.4Tests and Inspections5.5-75.5.2Steam Generators5.5-75.5.2.1Design Basis5.5-7 5.5.2.2Design Description5.5-85.5.2.3Design Evaluation5.5-95.5.2.3.1Forced Convection5.5-9 5.5.2.3.2Natural Circulation Flow5.5-95.5.2.3.3Tube and Tubesheet Stress Analyses5.5-105.5.2.3.4Corrosion5.5-10 5.5.2.3.5Compatibility of Steam Generator Tubing with Primary and5.5-105.5.2.3.6Flow Induced Vibration5.5-125.5.2.4Tests and Inspections5.5-145.5.3Reactor Coolant Piping5.5-155.5.3.1Design Bases5.5-15 5.5.3.2Design Description5.5-165.5.3.3Design Evaluation5.5-18 1-lxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.3.3.1Material Corrosion/Erosion Evaluation5.5-185.5.3.3.2Sensitized Stainless Steel5.5-195.5.3.3.3Contaminant Control5.5-195.5.3.4Tests and Inspections5.5-195.5.4Steam Outlet Flow Restrictor (Steam Generator)5.5-195.5.4.1Design Basis5.5-19 5.5.4.2Description5.5-205.5.4.3Evaluation5.5-205.5.4.4Tests and Inspections5.5-20 5.5.5Main Steam Line Isolation System5.5-205.5.6Reactor Vessel Head Vent System5.5-215.5.6.1Design Basis5.5-21 5.5.6.2System Description5.5-215.5.6.2.1Component Description5.5-225.5.6.2.2 System Operation5.5-22 5.5.6.3Design Evaluation5.5-225.5.6.3.1System Availability and Reliability5.5-225.5.6.3.2Leakage Provisions5.5-23 5.5.6.3.3Pipe Rupture Provisions5.5-235.5.6.3.4 Radiological Considerations5.5-235.5.7Residual Heat Removal System5.5-23 5.5.7.1Design Bases5.5-245.5.7.2System Description5.5-245.5.7.2.1Component Description5.5-25 5.5.7.2.2System Operation5.5-275.5.7.3Design Evaluation5.5-285.5.7.3.1System Availability and Reliability5.5-285.5.7.3.2Leakage Provisions and Activity Release5.5-295.5.7.3.3Overpressurization Protection5.5-295.5.7.3.4Prevention of Exposure of the Residual Heat Removal System to Normal Reactor Coolant System Operating Pressure5.5-305.5.7.3.5Shared Function5.5-305.5.7.3.6Radiological Consideration5.5-31 5.5.7.4Tests and Inspections5.5-315.5.8Reactor Coolant Cleanup System5.5-315.5.9Main Steam Line and Feedwater Piping5.5-31 5.5.10Pressurizer5.5-325.5.10.1Design Bases5.5-325.5.10.1.1Pressurizer Surge Line5.5-325.5.10.1.2Pressurizer Volume5.5-325.5.10.2Design Description5.5-33 5.5.10.2.1Pressurizer Surge Line5.5-335.5.10.2.2Pressurizer Vessel5.5-335.5.10.3Design Evaluation5.5-34 Table of Contents1-lxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.10.3.1System Pressure5.5-345.5.10.3.2Pressurizer Performance5.5-345.5.10.3.3Pressure Setpoints5.5-355.5.10.3.4Pressurizer Spray5.5-355.5.10.3.5Pressurizer Design Analysis5.5-355.5.10.4Tests and Inspections5.5-36 5.5.11Pressurizer Relief Tank5.5-375.5.11.1Design Bases5.5-375.5.11.2Design Description5.5-37 5.5.11.2.1Pressurizer Relief Tank Pressure5.5-385.5.11.2.2Pressurizer Relief Tank Level5.5-385.5.11.2.3Pressurizer Relief Tank Water Temperature5.5-385.5.11.3Design Evaluation5.5-385.5.12Valves5.5-385.5.12.1Design Bases5.5-38 5.5.12.2Design Description5.5-395.5.12.3Design Evaluation5.5-395.5.12.4Tests and Inspections5.5-40 5.5.13Safety and Relief Valves5.5-405.5.13.1Design Bases5.5-405.5.13.2Design Description5.5-40 5.5.13.3Design Evaluation5.5-415.5.13.4Tests and Inspections5.5-415.5.14Component Supports5.5-41 5.5.14.1Design Bases5.5-415.5.14.2Description5.5-425.5.14.3Evaluation5.5-43 5.5.14.4Tests and Inspections5.5-445.6INSTRUMENTATION APPLICATION5.6-16.0ENGINEERED SAFETY FEATURES6.1ENGINEERED SAFETY FEATURE MATERIALS6.1-16.1.1Metallic Materials6.1-1 6.1.1.1Materials Selection and Fabrication6.1-16.1.1.2Composition, Compatibility, and Stabi lity of Containment and Core Spray Coolants 6.1-26.1.2Organic Materials6.1-36.1.2.1Electrical Insulation6.1-3 6.1.2.2Surface Coatings6.1-36.1.2.3Ice Condenser Equipment6.1-46.1.2.4Identification Tags6.1-4 6.1.2.5Valves and Instruments within Containment6.1-4 1-lxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.1.2.6Heating and Ventilating Door Seals6.1-46.1.3Post-Accident Chemistry6.1-46.1.3.1Boric Acid, H3BO36.1-56.1.3.2Lithium Hydroxide6.1-56.1.3.3Sodium Tetraborate6.1-56.1.3.4Final Post-Accident Chemistry6.1-56.1.4Degree of Compliance with Regulatory Gu ide 1.54 for Paints and Coatings Inside Containment6.1-56.2CONTAINMENT SYSTEMS6.2-16.2.1Containment Functional Design6.2-1 6.2.1.1Design Bases6.2-16.2.1.1.1Primary Containment Design Bases6.2-1 6.2.1.2Primary Containment System Design6.2-36.2.1.3Design Evaluation6.2-36.2.1.3.1Primary Containment Evaluation6.2-3 6.2.1.3.2General Description of Containment Pressure Analysis6.2-46.2.1.3.3Long-Term Containment Pressure Analysis6.2-46.2.1.3.4Short-Term Blowdown Analysis6.2-86.2.1.3.5Effect of Steam Bypass6.2-176.2.1.3.6Mass and Energy Release Data6.2-206.2.1.3.7Accident Chronology6.2-24 6.2.1.3.8Energy Balance Tables6.2-246.2.1.3.9Containment Pressure Differentials6.2-256.2.1.3.10Steam Line Break Inside Containment6.2-27 6.2.1.3.11Maximum Reverse Pressure Differentials6.2-336.2.2CONTAINMENT HEAT REMOVAL SYSTEMS6.2-16.2.2.1Design Bases6.2-1 6.2.2.2System Design6.2-36.2.2.3Design Evaluation6.2-56.2.2.4Testing and Inspections6.2-7 6.2.2.5Instrumentation Requirements6.2-86.2.2.6Materials6.2-86.2.3Secondary Containment Functional Design6.2-16.2.3.1Design Bases6.2-1 6.2.3.1.1Secondary Containment Enclosures6.2-16.2.3.1.2Emergency Gas Treatment System (EGTS)6.2-16.2.3.1.3Auxiliary Building Gas Treatment System (ABGTS)6.2-26.2.3.2System Design6.2-2 6.2.3.2.1Secondary Containment Enclosures6.2-26.2.3.2.2Emergency Gas Treatment System (EGTS)6.2-76.2.3.2.3Auxiliary Building Gas Treatment System (ABGTS)6.2-106.2.3.3Design Evaluation6.2-12 Table of Contents 1-lxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.2.3.3.1Secondary Containment Enclosures6.2-126.2.3.3.2Emergency Gas Treatment System (EGTS)6.2-156.2.3.3.3Auxiliary Building Gas Treatment System (ABGTS)6.2-196.2.3.4Test and Inspections6.2-216.2.3.4.1Emergency Gas Treatment System (EGTS)6.2-216.2.3.4.2Auxiliary Building Gas Treatment System (ABGTS)6.2-226.2.3.5Instrumentation Requirements6.2-236.2.3.5.1Emergency Gas Treatment System (EGTS)6.2-236.2.3.5.2Auxiliary Building Gas Treatment System (ABGTS)6.2-236.2.4Containment Isolation Systems6.2-16.2.4.1Design Bases6.2-16.2.4.2System Design6.2-4 6.2.4.2.1Design Requirements6.2-56.2.4.2.2Containment Isolation Operation6.2-56.2.4.2.3Penetration Design6.2-6 6.2.4.3Design Evaluation6.2-126.2.4.3.1Possible Leakage Paths6.2-146.2.4.4Tests and Inspections6.2-166.2.5Combustible Gas Control in Containment6.2-16.2.5.1The containment combustible gas control sy stem is designed to control the concen-tration of hydrogen that may be released into the containment followi ng a beyond-design-basis ac-cident to ensure that containment structural integrity is maintained. Th e combustible gas control system of the containment air return system, the hydrogen analyzer system (HAS) and the hydro-gen mitigation system (HMS) which conform to 10CFR50.44 requirements.Design Bases6.2-16.2.5.2System Design6.2-26.2.5.3Design Evaluation6.2-46.2.5.4Testing and Inspections6.2-5 6.2.5.5Instrumentation Application6.2-56.2.6Containment Leakage Testing6.2-16.2.6.1Containment Integrated Leak Rate Test6.2-1 6.2.6.2Containment Penetration Leakage Rate Test6.2-26.2.6.3Scheduling and Reporting of Periodic Tests6.2-66.2.6.4Special Testing Requirements6.2-66.3EMERGENCY CORE COOLING SYSTEM6.3-16.3.1Design Bases6.3-1 6.3.1.1Range of Coolant Ruptures and Leaks6.3-16.3.1.2Fission Product Decay Heat6.3-26.3.1.3Reactivity Required for Cold Shutdown6.3-2 6.3.1.4Capability To Meet Functional Requirements6.3-26.3.2System Design6.3-26.3.2.1Schematic Piping and Instrumentation Diagrams6.3-2 1-lxxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.3.2.2Equipment and Component Design6.3-26.3.2.3Applicable Codes and Classifications6.3-156.3.2.4Materials Specifications and Compatibility6.3-156.3.2.5Design Pressures and Temperatures6.3-166.3.2.6Coolant Quantity6.3-166.3.2.7Pump Characteristics6.3-16 6.3.2.8Heat Exchanger Characteristics6.3-166.3.2.9ECCS Flow Diagrams6.3-176.3.2.10Relief Valves6.3-17 6.3.2.11System Reliability6.3-176.3.2.11.1Definitions6.3-176.3.2.11.2Active and Passive Failure Criteria6.3-186.3.2.11.3Subsequent Leakage from Components in Safeguards Systems6.3-196.3.2.12Protection Provisions6.3-216.3.2.13Provisions for Performance Testing6.3-22 6.3.2.14Net Positive Suction Head6.3-226.3.2.15Control of Motor-Operated Isolation Valves6.3-226.3.2.16Motor-Operated Valves and Controls6.3-23 6.3.2.17Manual Actions6.3-236.3.2.18Process Instrumentation6.3-236.3.2.19Materials6.3-23 6.3.3Performance Evaluation6.3-236.3.3.1Evaluation Model6.3-236.3.3.2ECCS Performance6.3-24 6.3.3.3Alternate Analysis Methods6.3-246.3.3.4Fuel Rod Perforations6.3-256.3.3.5Effects of ECCS Operation on the Core6.3-25 6.3.3.6Use of Dual Function Components6.3-256.3.3.7Lag Times6.3-276.3.3.8Thermal Shock Considerations6.3-27 6.3.3.9Limits on System Parameters6.3-276.3.3.10Use of RHR Spray6.3-276.3.4Tests and Inspections6.3-28 6.3.4.1Preoperational Tests(Historical Information - Not Updated)6.3-286.3.4.2Component Testing6.3-29 6.3.4.3Periodic System Testing6.3-296.3.5Instrumentation Application6.3-306.3.5.1Temperature Indication6.3-306.3.5.2Pressure Indication6.3-306.3.5.3Flow Indication6.3-30 6.3.5.4Level Indication6.3-316.3.5.5Valve Position Indication6.3-32 Table of Contents1-lxxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.4HABITABILITY SYSTEMS6.4-16.4.1 Design Bases6.4-16.4.2System Design6.4-16.4.2.1Definition of MCRHS Area6.4-16.4.2.2Ventilation System Design6.4-2 6.4.2.3Leak Tightness6.4-26.4.2.4Interaction with Other Zones and Pressure-Containing Equipment6.4-36.4.2.4.1Other Ventilation Zones6.4-36.4.2.4.2Pressure-Containing Equipment6.4-46.4.2.5Shielding Design6.4-46.4.2.6Control Room Emergency Provisions6.4-4 6.4.2.7MCRHS Fire Protection6.4-46.4.3System Operational Procedures6.4-56.4.4Design Evaluations6.4-7 6.4.4.1Radiological Protection6.4-76.4.4.2Toxic Gas Protection6.4-76.4.5Testing and Inspection6.4-9 6.4.6Instrumentation Requirements6.4-96.5FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS6.5-16.5.1Engineered Safety Feature (ESF) Filter Systems6.5-16.5.1.1Design Bases6.5-16.5.1.1.1Emergency Gas Treatment System Air Cleanup Units6.5-16.5.1.1.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-16.5.1.1.3Reactor Building Purge Air System Air Cleanup Units6.5-16.5.1.1.4Main Control Room Emergency Air Cleanup Units6.5-26.5.1.2System Design6.5-2 6.5.1.2.1Emergency Gas Treatment System Air Cleanup Units6.5-26.5.1.2.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-36.5.1.2.3Reactor Building Purge System Air Cleanup Units6.5-46.5.1.2.4Main Control Room Emergency Air Cleanup Units6.5-46.5.1.3Design Evaluation6.5-56.5.1.3.1Emergency Gas Treatment System Air Cleanup Units6.5-5 6.5.1.3.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-56.5.1.3.3Reactor Building Purge System Air Cleanup Units6.5-56.5.1.3.4Main Control Room Emergency Air Cleanup Units6.5-56.5.1.4Tests and Inspections6.5-56.5.1.4.1Emergency Gas Treatment System Air Cleanup Units6.5-56.5.1.4.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-66.5.1.4.3Reactor Building Purge System Air Cleanup Units6.5-66.5.1.4.4Main Control Room Emergency Air Cleanup Units6.5-66.5.1.5Instrumentation Requirements6.5-66.5.1.5.1Emergency Gas Treatment System Air Cleanup Units6.5-66.5.1.5.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-6 1-lxxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.5.1.5.3Reactor Building Purge System Air Cleanup Units6.5-76.5.1.5.4Main Control Room Emergency Air Cleanup Units6.5-76.5.1.6Materials6.5-76.5.1.6.1Emergency Gas Treatment System Air Cleanup Units6.5-76.5.1.6.2Auxiliary Building Gas Treatment System Air Cleanup Units6.5-76.5.1.6.3Reactor Building Purge System Air Cleanup Units6.5-76.5.1.6.4Main Control Room Emergency Air Cleanup Units6.5-76.5.2Containment Spray System for Fission Product Cleanup6.5-86.5.2.1Design Bases6.5-8 6.5.2.2System Design6.5-86.5.2.3Design Evaluation6.5-86.5.2.4Tests and Inspections6.5-8 6.5.2.5Instrumentation Requirements6.5-86.5.2.6Materials6.5-86.5.3Fission Product Control Systems6.5-8 6.5.3.1Primary Containment6.5-86.5.3.2Secondary Containments6.5-106.5.4Ice Condenser as a Fission Product Cleanup System6.5-106.5.4.1Ice Condenser Design Basis (Fission Product Cleanup Function)6.5-116.5.4.2Ice Condenser System Design6.5-116.5.4.2.1Component Description6.5-11 6.5.4.2.2System Operation6.5-116.5.4.3Ice Condenser System Design Evalua tion (Fission Product Cleanup Function) 6.5-11 6.5.4.4Condenser System Tests and Inspections6.5-136.5.4.4.1Ice Condenser System Instrumentation6.5-136.5.4.5Ice Condenser Materials6.5-136.6INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS6.6-16.6.1Components Subject to Examination and/or Test6.6-16.6.2Accessibility6.6-1 6.6.3Examination Techniques and Procedures6.6-16.6.4Inspection Intervals6.6-16.6.5Examination Categories and Requirements6.6-1 6.6.6Evaluation of Examination Results6.6-16.6.7System Pressure Tests6.6-26.6.8Protection against Postulated Piping Failures6.6-26.7ICE CONDENSER SYSTEM6.7-16.7.1Floor Structure and Cooling System6.7-1 6.7.1.1Design Bases6.7-16.7.1.2Design Evaluation6.7-56.7.2Wall Panels6.7-8 6.7.2.1Design Basis6.7-8 Table of Contents1-lxxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.2.2System Design6.7-86.7.2.3Design Evaluation6.7-96.7.3Lattice Frames and Support Columns6.7-96.7.3.1Design Basis6.7-96.7.3.2System Design6.7-126.7.3.3Design Evaluation6.7-13 6.7.4Ice Baskets6.7-146.7.4.1Design Basis6.7-146.7.4.2System Design6.7-15 6.7.4.3Design Evaluation6.7-186.7.5Crane and Rail Assembly6.7-206.7.5.1Design Basis6.7-20 6.7.5.2System Design6.7-206.7.5.3Design Evaluation6.7-216.7.6Refrigeration System6.7-21 6.7.6.1Design Basis6.7-216.7.6.2System Design6.7-226.7.6.3Design Evaluation6.7-25 6.7.7Air Handling Units6.7-296.7.7.1Design Basis6.7-296.7.7.2System Design6.7-30 6.7.7.3Design Evaluation6.7-316.7.8Lower Inlet Doors6.7-316.7.8.1Design Basis6.7-31 6.7.8.2System Design6.7-346.7.8.3Design Evaluation6.7-366.7.9Lower Support Structure6.7-37 6.7.9.1Design Basis6.7-376.7.9.2System Design6.7-396.7.9.3Design Evaluation6.7-40 6.7.10Top Deck and Doors6.7-496.7.10.1Design Basis6.7-496.7.10.2System Design6.7-51 6.7.11Intermediate Deck and Doors6.7-546.7.11.1Design Basis6.7-546.7.11.2System Design6.7-55 6.7.11.3Design Evaluation6.7-566.7.12Air Distribution Ducts6.7-576.7.12.1Design Basis6.7-576.7.12.2System Design6.7-586.7.12.3Design Evaluation6.7-58 6.7.13Equipment Access Door6.7-586.7.13.1Design Basis6.7-586.7.13.2System Design6.7-59 1-lxxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.13.3Design Evaluation6.7-596.7.14Ice Technology, Ice Performance, and Ice Chemistry6.7-596.7.14.1Design Basis6.7-596.7.14.2System Design6.7-596.7.14.3Design Evaluation6.7-606.7.15Ice Condenser Instrumentation6.7-65 6.7.15.1Design Basis6.7-656.7.15.2Design Description6.7-666.7.15.3Design Evaluation6.7-67 6.7.16Ice Condenser Structural Design6.7-686.7.16.1Applicable Codes, Standards, and Specifications6.7-686.7.16.2Loads and Loading Combinations6.7-68 6.7.16.3Design and Analytical Procedures6.7-686.7.16.4Structural Acceptance Criteria6.7-696.7.17Seismic Analysis6.7-70 6.7.17.1Seismic Analysis Methods6.7-706.7.17.2Seismic Load Development6.7-736.7.17.3Vertical Seismic Response6.7-74 6.7.18Materials6.7-746.7.18.1Design Criteria6.7-746.7.18.2Environmental Effects6.7-75 6.7.18.3Compliance with 10 CFR 50, Appendix B6.7-766.7.18.4Materials Specifications6.7-776.7.19Tests and Inspections6.7-786.8AIR RETURN FANS6.8-16.8.1Design Bases6.8-1 6.8.2System Description6.8-1 6.8.3Safety Evaluation6.8-26.8.4Inspection and Testing6.8-36.8.5Instrumentation Requirements6.8-37.0INSTRUMENTATION AND CONTROLS
7.1INTRODUCTION
7.1-17.1.1Identification of Safety-Related Systems7.1-47.1.1.1 Safety-Related Systems7.1-47.1.1.1.1Reactor Trip System7.1-47.1.1.1.2Engineered Safety Features Actuation System7.1-47.1.1.1.3Vital Instrumentation and Control Power Supply System7.1-47.1.1.1.4Auxiliary Control Air System7.1-47.1.1.2 Safety-Related Display Instrumentation7.1-57.1.1.3 Instrumentation and Control System Designers7.1-5 7.1.1.4 Plant Comparison7.1-5 Table of Contents1-lxxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.1.2Identification of Safety Criteria7.1-57.1.2.1Design Bases7.1-87.1.2.1.1Reactor Trip System7.1-87.1.2.1.2Engineered Safety Features Actuation System (ESFAS)7.1-97.1.2.1.3Vital Control Power Supply System7.1-107.1.2.1.4Standby Power7.1-10 7.1.2.1.5Interlocks7.1-107.1.2.1.6Bypasses7.1-107.1.2.1.7Equipment Protection7.1-10 7.1.2.1.8Diversity7.1-117.1.2.1.9Trip Setpoints7.1-117.1.2.2Independence of Redundant Safety-Related Systems7.1-117.1.2.2.1General7.1-127.1.2.2.2Specific Systems7.1-127.1.2.2.3Fire Protection7.1-14 7.1.2.3Physical Identification of Safety-Related Equipment7.1-147.1.2.4Process Signal Isolation Relays7.1-167.2 REACTOR TRIP SYSTEM7.2-17.2.1Description7.2-1 7.2.1.1System Description7.2-17.2.1.1.1Functional Performance Requirements7.2-27.2.1.1.2Reactor Trips7.2-27.2.1.1.3Reactor Trip System Interlocks7.2-107.2.1.1.4Reactor Coolant Temper ature Sensor Arrangement and Calculational Methodology7.2-127.2.1.1.5Pressurizer Water Level Reference Leg Arrangement7.2-157.2.1.1.6Process Protection System7.2-15 7.2.1.1.7Solid State Logic Protection System7.2-157.2.1.1.8Isolation Devices7.2-167.2.1.1.9Energy Supply and Environmental Variations7.2-167.2.1.1.10Setpoints7.2-167.2.1.1.11Seismic Design7.2-167.2.1.2Design Bases Information7.2-16 7.2.1.2.1Generating Station Conditions7.2-167.2.1.2.2Generating Station Variables7.2-177.2.1.2.3Spatially Dependent Variables7.2-17 7.2.1.2.4Limits, Margins and Levels7.2-177.2.1.2.5Abnormal Events7.2-187.2.1.2.6Minimum Performance Requirements7.2-187.2.1.3Final Systems Drawings7.2-197.2.2Analyses7.2-19 7.2.2.1Evaluation of Design Limits7.2-207.2.2.1.1Trip Setpoint Discussion7.2-20 1-lxxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.2.2.1.2Reactor Coolant Flow Measurement7.2-227.2.2.2Evaluation of Compliance to Applicable Codes and Standards7.2-227.2.2.3Specific Control and Protection Interactions7.2-327.2.2.3.1Neutron Flux7.2-327.2.2.3.2Reactor Coolant Temperature7.2-327.2.2.3.3Pressurizer Pressure7.2-33 7.2.2.3.4Pressurizer Water Level7.2-347.2.2.3.5Steam Generator Water Level7.2-347.2.2.4Additional Postulated Accidents7.2-35 7.2.3Tests and Inspections7.2-357.3ENGINEERED SAFETY FEATURES ACTUATION SYSTEM7.3-17.3.1Description7.3-1 7.3.1.1System Description7.3-17.3.1.1.1Function Initiation7.3-27.3.1.1.2Process Protection Circuitry7.3-3 7.3.1.1.3Logic Circuitry7.3-47.3.1.1.4Final Actuation Circuitry7.3-47.3.1.1.5Support Systems7.3-5 7.3.1.2Design Bases Information7.3-67.3.1.2.1Generating Station Conditions7.3-67.3.1.2.2Generating Station Variables7.3-6 7.3.1.2.3Spatially Dependent Variables7.3-67.3.1.2.4Limits, Margin and Levels7.3-67.3.1.2.5Abnormal Events7.3-7 7.3.1.2.6Minimum Performance Requirements7.3-77.3.1.3Final System Drawings7.3-87.3.2Analysis7.3-8 7.3.2.1System Reliability/Availability and Failure Mode and Effect Analyses7.3-87.3.2.2Compliance With Standards and Design Criteria7.3-87.3.2.2.1Single Failure Criterion7.3-9 7.3.2.2.2Equipment Qualification7.3-97.3.2.2.3Channel Independence7.3-97.3.2.2.4Control and Protection System Interaction7.3-97.3.2.2.5Capability for Sensor Checks and Equipment Test and Calibration7.3-97.3.2.2.6Manual Initiation, Reset and Bl ocks of Protective Actions7.3-157.3.2.3 Further Considerations7.3-15 7.3.2.4Summary7.3-167.3.2.4.1Loss-of-Coolant Protection7.3-167.3.2.4.2Steam Line Break Protection7.3-177.4SYSTEMS REQUIRED FOR SAFE SHUTDOWN7.4-17.4.1Description7.4-1 7.4.1.1Monitoring Indicators7.4-1 Table of Contents1-lxxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.4.1.2Controls7.4-27.4.1.2.1General Considerations7.4-27.4.1.2.2Pumps and Fans7.4-37.4.1.2.3Diesel Generators7.4-47.4.1.2.4Valves and Heaters7.4-47.4.1.3Equipment and Systems Available for Cold Shutdown7.4-57.4.2Analysis7.4-57.5INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY7.5-17.5.1Post Accident Monitoring Instrumentation (PAM)7.5-17.5.1.1System Description7.5-17.5.1.2Variable Types7.5-17.5.1.3Variable Categories7.5-2 7.5.1.4Design Bases7.5-37.5.1.4.1Definitions7.5-37.5.1.4.2 Selection Criteria7.5-3 7.5.1.4.3 Design Criteria For Category 1 Variables7.5-47.5.1.4.4 Design Criteria For Category 2 Variables7.5-57.5.1.4.5Design Criteria For Category 3 Variables7.5-57.5.1.5General Requirements7.5-67.5.1.5.1Display Requirements7.5-67.5.1.5.2Identification7.5-6 7.5.1.6Analysis7.5-77.5.1.7Tests and Inspections7.5-77.5.1.7.1Programs7.5-7 7.5.1.7.2Removal of Channels from Service7.5-87.5.1.7.3Administrative Control7.5-87.5.2Plant Computer System7.5-8 7.5.2.1Safety Parameter Display System7.5-87.5.2.1.1System Description7.5-87.5.2.1.2Design Bases7.5-9 7.5.2.2Bypassed and Inoperable Status Indication System (BISI)7.5-117.5.2.3Technical Support Center and Nuclear Data Links7.5-137.5.2.3.1Technical Support Center7.5-13 7.5.2.3.2 Communication Data Links7.5-137.6ALL OTHER SYSTEMS REQUIRED FOR SAFETY7.6-17.6.1120V ac and 125V dc Vital Plant Control Power System7.6-17.6.2Residual Heat Removal Isolation Valves7.6-17.6.2.1Description7.6-1 7.6.2.2Analysis7.6-27.6.3Refueling Interlocks7.6-27.6.4Deleted by Amendment 63.7.6-2 7.6.5Accumulator Motor-Operated Valves7.6-2 1-lxxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.6.6Spurious Actuation Protection for Motor Operated Valves7.6-37.6.7Loose Part Monitoring System (LPMS) System Description7.6-47.6.8Interlocks for RCS Pressure Control During Low Temperature Operation7.6-87.6.8.1Analysis of Interlock7.6-97.6.9Switchover From Injection to Recirculation Mode Following a LOCA7.6-107.7CONTROL SYSTEMS7.7-17.7.1Description7.7-17.7.1.1Control Rod Drive Reactor Control System7.7-17.7.1.1.1Reactor Control Input Signals7.7-1 7.7.1.1.2Rod Speed Control Program7.7-37.7.1.2Rod Control System7.7-37.7.1.2.1Rod Control System Function7.7-3 7.7.1.2.2Rod Control System Failures7.7-57.7.1.3Plant Control Signals for Monitoring and Indicating7.7-97.7.1.3.1Monitoring Functions Provided by the Nuclear Instrumentation System 7.7-97.7.1.3.2Main Control Room Rod Position Indication7.7-107.7.1.3.3Control Bank Rod Insertion Monitoring7.7-12 7.7.1.3.4Rod Deviation Alarm7.7-147.7.1.3.5Rods At Bottom7.7-147.7.1.3.6Bypassed and Inoperable Status Indication System (BISI)7.7-147.7.1.4Plant Control System Interlocks7.7-147.7.1.4.1Rod Stops7.7-147.7.1.4.2Automatic Turbine Load Runback7.7-15 7.7.1.5Pressurizer Pressure Control7.7-157.7.1.6Pressurizer Water Level Control7.7-167.7.1.7Steam Generator Water Level Control7.7-16 7.7.1.8Steam Dump Control7.7-177.7.1.8.1Load Rejection Steam Dump Controller7.7-177.7.1.8.2Plant Trip Steam Dump Controller7.7-18 7.7.1.8.3Steam Header Pressure Controller7.7-187.7.1.9Incore Instrumentation System7.7-187.7.1.9.1Thermocouples7.7-18 7.7.1.9.2Incore Instrumentation System7.7-197.7.1.9.3 Incore Instrumentation System Neutron Signal Processing7.7-197.7.1.10Control Board7.7-19 7.7.1.11Deleted7.7-207.7.1.12Anticipated Transient Without Scram Mitigation System Actuation7.7-207.7.2Analysis7.7-217.7.2.1Separation of Protection and Control System7.7-227.7.2.2Response Considerations of Reactivity7.7-22 7.7.2.3Step Load Changes Without Steam Dump7.7-247.7.2.4Loading and Unloading7.7-25 Table of Contents1-lxxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.7.2.5Load Rejection Furnished By Steam Dump System7.7-257.7.2.6Turbine-Generator Trip With Reactor Trip7.7-267AINSTRUMENTATION IDENTIFICATIONS AND SYMBOLS7A.1IDENTIFICATION SYSTEM7A.1-17A.1.1FUNCTIONAL IDENTIFICATION7A.1-17A.1.1.1 Principal Function7A.1-17A.1.1.2 Measured Variable7A.1-27A.1.1.3 Readout or Passive Functions7A.1-2 7A.1.1.4 Modifying Letters7A.1-27A.1.1.5 Tagging Symbols7A.1-27A.1.1.6 Special Identifying Letters7A.1-2 7A.1.1.7 Pilot Lights7A.1-27A.1.2 SYSTEM IDENTIFICATION7A.1-37A.1.2.1 Identification Numbers7A.1-37A.1.2.1.1 Instruments Common to Multiple Process Systems7A.1-37A.1.3 LOOP IDENTIFICATION7A.1-37A.1.3.1 Instruments Common to Multiple Control Loops7A.1-37A.1.3.2 Multiple Instruments with a Common Function7A.1-37A.2SYMBOLS7A.1-37A.2.1INSTRUMENT SYMBOL7A.1-48.0ELECTRIC POWER
8.1INTRODUCTION
8.1-18.1.1Utility Grid and Interconnections8.1-18.1.2Plant Electrical Power System8.1-18.1.3Safety-Related Loads8.1-2 8.1.4Design Bases8.1-28.1.5Design Criteria and Standards8.1-48.1.5.1Design Criteria8.1-4 8.1.5.2Other Standards and Guides8.1-48.1.5.3Compliance to Regulatory Guides and IEEE Standards8.1-88.2OFFSITE (PREFERRED) POWER SYSTEM8.2-18.2.1Description8.2-1 8.2.1.1Preferred Power Supply8.2-18.2.1.2Transmission Lines, Switchyard, and Transformers8.2-38.2.1.3Arrangement of the Start Boards, Un it Boards, Common Boards, and Reactor Coolant Pump (RCP) Boards8.2-4 8.2.1.4Arrangement of Electrical C ontrol Area (Nuclear Plant)8.2-58.2.1.5Switchyard Control and Relaying8.2-68.2.1.66.9-kV Start Boards Control and Relaying8.2-8 1-lxxxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8.2.1.76.9-kV Unit and RCP Board Control and Relaying8.2-108.2.1.8Conformance with Standards8.2-118.2.2 Analysis8.2-198.3ONSITE (STANDBY) POWER SYSTEM8.3-18.3.1AC Power System8.3-18.3.1.1Description8.3-1 8.3.1.2Analysis8.3-268.3.1.2.1Standby AC Power Systems8.3-268.3.1.2.2Analysis of Vital 120V AC Cont rol Power Systems AC Distribution Boards and Inverters8.3-298.3.1.2.3Safety-Related Equipment in a LOCA Environment8.3-328.3.1.3Physical Identification of Safety-Rel ated Equipment in AC Power Systems 8.3-368.3.1.4Independence of Redundant ac Power Systems8.3-378.3.1.4.1Cable Derating and Raceway Fill8.3-38 8.3.1.4.2Cable Routing and Separation Criteria8.3-388.3.1.4.3Sharing of Cable Trays and Routing of Non-Safety Related Cables8.3-468.3.1.4.4Fire Detection and Protection in Areas Where Cables are Installed8.3-508.3.1.4.5Cable and Cable Tray Markings8.3-518.3.1.4.6Spacing of Power and Control Wi ring and Components Comprising the Class 1E Electrical Systems in Cont rol Boards, Panels, and Relay Racks 8.3-528.3.1.4.7Fire Barriers and Separation Between Redundant Trays8.3-538.3.2DC Power System8.3-53 8.3.2.1Description8.3-538.3.2.1.1Vital 125V dc Control Power System8.3-538.3.2.1.2Non-Safety-Related DC Power Systems8.3-608.3.2.2Analysis of Vital 125V DC Control Power Supply System8.3-618.3.2.3Physical Identification of Safety-Related Equipment in dc Power Systems8.3-66 8.3.2.4Independence of Redundant DC Power Systems8.3-668.3.3Fire Protection for Cable Systems8.3-678AAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System8-18BAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from In-strumentation and Control Power System8-38CDeleted by Amendment 758-58DIEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STANDBY POWER 8-6 Table of Contents1-lxxxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8EProbability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables8-89.0AUXILIARY SYSTEMS9.1FUEL STORAGE AND HANDLING9.1-19.1.1New Fuel Storage9.1-19.1.1.1Design Bases9.1-1 9.1.1.2Facilities Description9.1-19.1.1.3Safety Evaluation9.1-19.1.2SPENT FUEL STORAGE9.1-2 9.1.2.1Design Bases9.1-29.1.2.2Facilities Description9.1-29.1.2.3Safety Evaluation9.1-3 9.1.2.4Materials9.1-49.1.3Spent Fuel Pool Cooling and Cleanup System (SFPCCS)9.1-49.1.3.1Design Bases9.1-4 9.1.3.1.1Spent Fuel Pool Cooling9.1-49.1.3.1.2Spent Fuel Pool Dewatering Protection9.1-59.1.3.1.3Water Purification9.1-5 9.1.3.1.4Flood Mode Cooling9.1-59.1.3.2System Description9.1-59.1.3.2.1Component Description9.1-7 9.1.3.3Safety Evaluation9.1-89.1.3.3.1Availability and Reliability9.1-89.1.3.3.2Spent Fuel Pool Dewatering9.1-9 9.1.3.3.3Pool and Fuel Temperatures9.1-99.1.3.3.4Water Quality9.1-119.1.3.3.5Leakage Detection for the Spent Fuel Pool9.1-119.1.3.4Tests and Inspections9.1-119.1.3.5Instrument Application9.1-119.1.3.5.1Temperature9.1-11 9.1.3.5.2Pressure9.1-129.1.3.5.3Flow9.1-129.1.3.5.4Level9.1-12 9.1.4FUEL HANDLING SYSTEM9.1-129.1.4.1Design Bases9.1-129.1.4.2System Description9.1-139.1.4.2.1Refueling Procedure9.1-149.1.4.2.2Component Description9.1-17 9.1.4.3Design Evaluation9.1-209.1.4.3.1Safe Handling9.1-209.1.4.3.2Seismic Considerations9.1-259.1.4.3.3Containment Pressure Boundary Integrity9.1-26 1-lxxxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.1.4.3.4Radiation Shielding9.1-269.1.4.4Tests and Inspections9.1-269.2WATER SYSTEMS9.2-19.2.1Essential Raw Cooling Water (ERCW)9.2-19.2.1.1Design Bases9.2-19.2.1.2System Description9.2-1 9.2.1.3Safety Evaluation9.2-49.2.1.4Tests and Inspections9.2-79.2.1.5Instrument Applications9.2-7 9.2.1.5.1General Description9.2-79.2.1.5.2Pressure Instrumentation9.2-79.2.1.5.3Flow Instrumentation9.2-8 9.2.1.5.4Temperature Instrumentation9.2-89.2.1.5.5Deleted by Amendment 879.2-89.2.1.5.6Control Valves9.2-8 9.2.1.6Corrosion, Organic Fouling, and Environmental Qualification9.2-99.2.1.7Design Codes9.2-109.2.2Component Cooling System (CCS)9.2-10 9.2.2.1Design Bases9.2-109.2.2.2System Description9.2-129.2.2.3Components9.2-15 9.2.2.3.1Component Cooling Heat Exchangers9.2-159.2.2.3.2Component Cooling Pumps9.2-159.2.2.3.3Thermal Barrier Booster Pumps9.2-16 9.2.2.3.4Component Cooling Surge Tanks9.2-169.2.2.3.5Seal Leakage Return Unit9.2-169.2.2.3.6Valves9.2-16 9.2.2.3.7Piping9.2-179.2.2.4 Safety Evaluation9.2-189.2.2.5Leakage Provisions9.2-18 9.2.2.6Incidental Control9.2-199.2.2.7Instrument Applications9.2-199.2.2.7.1General Description9.2-19 9.2.2.7.2Flow Instrumentation9.2-209.2.2.7.3Level Instrumentation9.2-209.2.2.7.4Pressure Instrumentation9.2-20 9.2.2.7.5Temperature Instrumentation9.2-209.2.2.7.6Valves9.2-219.2.2.7.7Conclusion9.2-219.2.2.8Malfunction Analysis9.2-219.2.2.9Tests and Inspections - Historical Information9.2-219.2.2.10Codes and Classification9.2-229.2.3Demineralized Water Makeup System9.2-22 Table of Contents1-lxxxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.2.3.1Design Bases9.2-229.2.3.2System Description9.2-229.2.3.3Safety Evaluation9.2-239.2.3.4Test and Inspection9.2-239.2.3.5Instrumentation Applications9.2-239.2.4Potable and Sanitary Water Systems9.2-24 9.2.4.1Potable Water System9.2-249.2.4.1.1System Description9.2-249.2.4.1.2Safety Evaluation9.2-24 9.2.4.1.3Tests and Inspections9.2-259.2.4.1.4Instrumentation Applications9.2-259.2.4.2Sanitary Water System9.2-25 9.2.4.2.1Design Bases9.2-259.2.4.2.2System Description9.2-259.2.4.2.3Safety Evaluation9.2-26 9.2.4.2.4Tests And Inspections9.2-279.2.4.2.5Instrumentation Applications9.2-289.2.5Ultimate Heat Sink9.2-28 9.2.5.1General Description9.2-289.2.5.2Design Bases9.2-299.2.5.3Safety Evaluation9.2-29 9.2.5.4Instrumentation Application9.2-319.2.6Condensate Storage Facilities9.2-319.2.6.1Design Bases9.2-31 9.2.6.2System Description9.2-329.2.6.3Safety Evaluation9.2-329.2.6.4Test and Inspections9.2-33 9.2.6.5Instrument Applications9.2-339.2.7Refueling Water Storage Tank9.2-349.2.7.1ECCS Pumps Net Positive Suction Head (NPSH)9.2-359.2.8Raw Cooling Water System9.2-379.2.8.1Design Bases9.2-379.2.8.2System Description9.2-38 9.2.8.3Safety Evaluation9.2-409.2.8.4Tests and Inspection9.2-419.3PROCESS AUXILIARIES9.3-19.3.1Compressed Air System9.3-1 9.3.1.1Design Basis9.3-19.3.1.2System Description9.3-19.3.1.3Safety Evaluation9.3-29.3.1.4Tests and Inspections9.3-5 9.3.1.5Instrumentation Applications9.3-59.3.2Process Sampling System9.3-5 1-lxxxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.2.1Design Basis9.3-59.3.2.2System Description9.3-59.3.2.3Safety Evaluation9.3-89.3.2.4Tests and Inspections9.3-89.3.2.5Instrumentation Applications9.3-89.3.2.6Postaccident Sampling Subsystem9.3-89.3.2.6.1System Description9.3-99.3.2.6.2Postaccident Sampling Facility9.3-99.3.2.6.3 Sampling Equipment9.3-9
Liquid Sampling Panel 10Chemical Analysis Panel 10 Containment Air Sampling Panel (CASP) 10
HRSS Control Panels 119.3.2.6.4Sample Points9.3-119.3.2.6.5Postaccident Counting Facilities9.3-119.3.2.6.6Piping, Tubing, and Valves9.3-119.3.2.6.7Safety Evaluation9.3-129.3.2.6.8Tests and Inspections9.3-12 9.3.3Equipment and Floor Drainage System9.3-129.3.3.1Design Bases9.3-129.3.3.2System Design9.3-12 9.3.3.2.1Drains from Lowest Floor Level in the Auxiliary Building9.3-139.3.3.2.2Residual Heat Removal Pump (RHR) and Containment Spray Pump (CSP) Compartments9.3-139.3.3.2.3CVCS Holdup Tank Compartment a nd Tritiated Drain Collector Tank Room9.3-149.3.3.2.4Volume Control Tanks9.3-14 9.3.3.2.5Boric Acid Tanks9.3-149.3.3.3Drains - Reactor Building9.3-159.3.3.4Design Evaluation9.3-15 9.3.3.5Tests and Inspections9.3-159.3.3.6Instrumentation Application9.3-159.3.3.7Drain List9.3-15 9.3.4Chemical and Volume Control System9.3-169.3.4.1Design Bases9.3-169.3.4.1.1Reactivity Control9.3-16 9.3.4.1.2Regulation of Reactor Coolant Inventory9.3-179.3.4.1.3Reactor Coolant Purification9.3-179.3.4.1.4Chemical Additions for Corrosion Control9.3-179.3.4.1.5Seal Water Injection9.3-179.3.4.1.6Hydrostatic Testing of the Reactor Coolant System9.3-179.3.4.1.7Emergency Core Cooling9.3-189.3.4.2System Description9.3-189.3.4.2.1Charging, Letdown, and Seal Water System9.3-18 Table of Contents1-lxxxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.4.2.2Chemical Control, Purification and Makeup System9.3-209.3.4.2.3Chemical Shim and Reactor Coolant Makeup9.3-219.3.4.2.4Component Description9.3-249.3.4.2.5System Operation9.3-329.3.4.3Safety Evaluation9.3-369.3.4.3.1Reactivity Control9.3-36 9.3.4.3.2Reactor Coolant Purification9.3-379.3.4.3.3Seal Water Injection9.3-379.3.4.3.4Hydrostatic Testing of the Reactor Coolant System9.3-389.3.4.3.5Leakage Provisions9.3-389.3.4.3.6Ability to Meet the Safeguards Function9.3-389.3.4.4Tests and Inspections9.3-38 9.3.4.5Instrumentation Application9.3-389.3.5Failed Fuel Detection System9.3-399.3.6Auxiliary Charging System9.3-39 9.3.6.1Design Bases9.3-399.3.6.2System Design Description9.3-409.3.6.3Design Evaluation9.3-41 9.3.6.4Tests and Inspection9.3-419.3.6.5Instrument Application9.3-419.3.7Boron Recycle System9.3-41 9.3.8Heat Tracing9.3-419.4AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS9.4-19.4.1Control Room Area Ventilation System9.4-19.4.1.1Design Bases9.4-19.4.1.2System Description9.4-39.4.1.3Safety Evaluation9.4-7 9.4.1.4Tests and Inspection9.4-89.4.2Fuel Handling Area Ventilation System9.4-89.4.2.1Design Bases9.4-8 9.4.2.2System Description9.4-109.4.2.3Safety Evaluation9.4-109.4.2.4 Inspection and Testing9.4-11 9.4.3Auxiliary and Radwaste Area Ventilation System9.4-129.4.3.1Design Bases9.4-129.4.3.2System Description9.4-13 9.4.3.2.1Building Air Supply and Exhaust Systems (General Ventilation)9.4-139.4.3.2.2Building Cooling System (Chilled Water)9.4-149.4.3.2.3Safety Feature Equipment Coolers9.4-159.4.3.2.4Shutdown Board Room Air-Conditioning System9.4-159.4.3.2.5Auxiliary Board Rooms Air-Conditioning Systems9.4-169.4.3.2.6Shutdown Transformer Room Ventilating Systems9.4-179.4.3.2.7Miscellaneous Ventilation and Air Conditioning Systems9.4-18 1-lxxxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.4.3.3Safety Evaluation9.4-199.4.3.3.1General Ventilation System9.4-199.4.3.3.2Building Cooling System9.4-209.4.3.3.3Safety Feature Equipment Coolers9.4-209.4.3.3.4Shutdown Board Room Air-Conditioning System9.4-209.4.3.3.5Auxiliary Board Rooms Air-Conditioning System9.4-219.4.3.3.6Shutdown Transformer Room Ventilating System9.4-229.4.3.3.7Miscellaneous Ventilation and Air-Conditioning System9.4-239.4.3.4Inspection and Testing Requirements9.4-23 9.4.4Turbine Building Area Ventilation System9.4-239.4.4.1Design Bases9.4-239.4.4.2System Description9.4-24 9.4.4.2.1Elevation 755.0 Ventilation9.4-249.4.4.2.2Elevation 729.0 and Elevation 708.0 Ventilation9.4-249.4.4.2.3El. 685.5 Ventilation9.4-24 9.4.4.2.4Cold Weather Building Pressurization9.4-259.4.4.2.5Miscellaneous Ventilating Systems9.4-259.4.4.2.6Coolers9.4-25
Space Coolers 25 Pump Coolers 269.4.4.2.7Building Heating System9.4-269.4.4.3Safety Evaluation9.4-269.4.4.4Inspection and Testing Requirements9.4-279.4.5 Engineered Safety Feature Ventilation Systems9.4-279.4.5.1ERCW Intake Pumping Station9.4-279.4.5.1.1Design Bases9.4-279.4.5.1.2System Description9.4-28 9.4.5.1.3Safety Evaluation9.4-289.4.5.1.4Inspection and Testing Requirements9.4-299.4.5.2Diesel Generator Buildings9.4-29 9.4.5.2.1Diesel Generator Building9.4-29 Design Bases 29 System Description 31
Safety Evaluation 32 Tests and Inspections 339.4.5.2.2Additional Diesel Generator Buil ding (Not required Unit 1 operation) 9.4-33 Design Bases 33 System Description 34 Safety Evaluation 35 Tests and Inspections 36 9.4.5.3Auxiliary Building Safety Features Equipment Coolers9.4-369.4.5.3.1Design Bases9.4-369.4.5.3.2System Description9.4-38 Table of Contents1-lxxxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.4.5.3.3Safety Evaluation9.4-389.4.5.3.4Inspection and Testing Requirements9.4-409.4.6Reactor Building Purge Ventilating System9.4-409.4.6.1Design Bases9.4-409.4.6.2System Description9.4-429.4.6.3Safety Evaluation9.4-44 9.4.6.4Inspection and Testing Requirements9.4-459.4.7Containment Air Cooling System9.4-459.4.7.1Design Bases9.4-45 9.4.7.2System Description9.4-469.4.7.2.1Lower Compartment Air Cooling System9.4-469.4.7.2.2Control Rod Drive Mechanisms Air Cooling System9.4-479.4.7.2.3Upper Compartment Air Cooling System9.4-479.4.7.2.4Reactor Building Instrument Room Air Cooling System9.4-489.4.7.2.5Controls and Instrumentation9.4-489.4.7.3Safety Evaluation9.4-489.4.7.4Test and Inspection Requirements9.4-499.4.8Condensate Demineralizer Wa ste Evaporator Building Environmental Control Sys-tem 9.4-499.4.9Postaccident Sampling Facility (PASF) Environmental Control System9.4-499.5OTHER AUXILIARY SYSTEMS9.5-19.5.1Fire Protection System9.5-19.5.1.1Deleted by Amendment 879.5-19.5.1.2Deleted by Amendment 879.5-1 9.5.1.3Deleted by Amendment 879.5-19.5.1.4Deleted by Amendment 879.5-19.5.1.5Deleted by Amendment 879.5-1 9.5.2Plant Communications System9.5-19.5.2.1Design Bases9.5-19.5.2.2General Description Intraplant Communications9.5-1 9.5.2.3General Description Interplant System9.5-49.5.2.4 Evaluation9.5-59.5.2.5Inspection and Tests9.5-7 9.5.3Lighting Systems9.5-89.5.3.1Design Bases9.5-89.5.3.2Description of the Plant Lighting System9.5-8 9.5.3.3Diesel Generator Building Lighting System9.5-99.5.3.4Safety Related Functions of the Lighting Systems9.5-109.5.3.5Inspection and Testing Requirements9.5-109.5.4Diesel Generator Fuel Oil Storage and Transfer System9.5-109.5.4.1Design Basis9.5-10 9.5.4.2System Description9.5-119.5.4.3Safety Evaluation9.5-14 1-lxxxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.5.4.4Tests and Inspections9.5-159.5.5Diesel Generator Cooling Water System9.5-159.5.5.1Design Bases9.5-159.5.5.2System Description9.5-159.5.5.3Safety Evaluation9.5-169.5.5.4Tests and Inspections9.5-16 9.5.6Diesel Generator Starting System9.5-179.5.6.1Design Bases9.5-179.5.6.2System Description9.5-17 9.5.6.3Safety Evaluation9.5-189.5.6.4Tests and Inspections9.5-189.5.7Diesel Engine Lubrication System9.5-18 9.5.7.1Design Bases9.5-189.5.7.2System Description9.5-199.5.7.3Safety Evaluation9.5-20 9.5.7.4Test and Inspections9.5-219.5.8Diesel Generator Combustion Air Intake and Exhaust System9.5-219.5.8.1Design Bases9.5-21 9.5.8.2System Descriptions9.5-219.5.8.3Safety Evaluation9.5-229.5.8.4Tests and Inspection9.5-2210.0MAIN STEAM AND POWER CONVERSION SYSTEMS10.1
SUMMARY
DESCRIPTION10.1-110.2TURBINE-GENERATOR10.2-110.2.1Design Bases10.2-110.2.2Description10.2-1 10.2.3Turbine Rotor and Disc Integrity10.2-510.2.3.1 Materials Selection10.2-510.2.3.2Fracture Toughness10.2-8 10.2.3.3High Temperature Properties10.2-910.2.3.4 Turbine Disc Design10.2-1010.2.3.5 Preservice Inspection10.2-10 10.2.3.5.1Low Pressure Turbine Rotor10.2-1010.2.3.5.2High Pressure Turbine Rotor10.2-1110.2.3.5.3Preoperational and Initial Startup Testing10.2-1110.2.3.6 Inservice Inspection10.2-1110.2.3.6.1Turbine Rotors10.2-11 10.2.3.6.2Turbine Overspeed Protection10.2-1210.2.3.6.3Other Turbine Protection Features10.2-1310.2.4Evaluation10.2-13 Table of Contents1-lxxxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.3MAIN STEAM SUPPLY SYSTEM10.3-110.3.1Design Bases10.3-110.3.2System Description10.3-110.3.2.1System Design10.3-110.3.2.2Material Compatibility, Codes, and Standards10.3-210.3.3Design Evaluation10.3-210.3.4Inspection and Testing Requirements10.3-310.3.5Water Chemistry10.3-4 10.3.5.1Purpose10.3-410.3.5.2Feedwater Chemistry Specifications10.3-410.3.5.3Operating Modes10.3-4 10.3.5.4Effect of Water Chemistry on the Radi oactive Iodine Partition Coefficient 10.3-510.3.6Steam and Feedwater System Materials10.3-5 10.3.6.1Fracture Toughness10.3-510.3.6.2Materials Selection and Fabrication10.3-610.4OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-110.4.1Main Condenser10.4-1 10.4.1.1Design Bases10.4-110.4.1.2System Description10.4-1 10.4.1.3Safety Evaluation10.4-410.4.1.4Inspection and Testing10.4-510.4.1.5Instrumentation10.4-5 10.4.2Main Condenser Evacuation System10.4-510.4.2.1Design Bases10.4-510.4.2.2System Description10.4-5 10.4.2.3Safety Evaluation10.4-610.4.2.4Inspection and Testing10.4-610.4.2.5Instrumentation10.4-6 10.4.3Turbine Gland Sealing System10.4-710.4.3.1Design Bases10.4-710.4.3.2System Description10.4-7 10.4.3.3Safety Evaluation10.4-710.4.3.4Inspection and Testing10.4-810.4.3.5Instrumentation10.4-8 10.4.4Turbine Bypass System10.4-810.4.4.1Design Bases10.4-810.4.4.2System Description10.4-910.4.4.3Safety Evaluation10.4-910.4.4.4Inspection and Testing10.4-10 10.4.4.5Instrumentation10.4-1110.4.5Condenser Circulating Water System10.4-1110.4.5.1Design Basis10.4-11 1-xcTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.5.2System Description10.4-1210.4.5.3Safety Evaluation10.4-1410.4.5.4Inspection and Testing10.4-1510.4.5.5Instrumentation Application10.4-1510.4.6Condensate Polishing Demineralizer System10.4-1510.4.6.1Design Bases - Power Conversion10.4-15 10.4.6.2System Description10.4-1610.4.6.3Safety Evaluation10.4-1810.4.6.4Inspection and Testing10.4-18 10.4.6.5Instrumentation10.4-1810.4.7Condensate and Feedwater Systems10.4-1910.4.7.1Design Bases10.4-19 10.4.7.2System Description10.4-2010.4.7.3Safety Evaluation10.4-2710.4.7.4Inspection and Testing10.4-28 10.4.7.5Instrumentation10.4-2910.4.8Steam Generator Blowdown System10.4-2910.4.8.1Design Bases10.4-29 10.4.8.2System Description and Operation10.4-3010.4.8.3Safety Evaluation10.4-3110.4.8.4Inspections and Testing10.4-32 10.4.9Auxiliary Feedwater System10.4-3210.4.9.1Design Bases10.4-3210.4.9.2System Description10.4-33 10.4.9.3Safety Evaluation10.4-3410.4.9.4Inspection and Testing Requirements10.4-3710.4.9.5Instrumentation Requirements10.4-3811.0RADIOACTIVE WASTE MANAGEMENT11.1SOURCE TERMS11.1-111.1.1Historical Design Model for Radioact ivities in Systems and Components11.1-111.1.1.1Reactor Coolant Historical Design Activity11.1-111.1.1.2Volume Control Tank Historical Design Activity11.1-2 11.1.1.3Pressurizer Historical Design Activity11.1-211.1.1.4Gaseous Waste Processing System Historical Design Activities11.1-211.1.1.5Secondary Coolant Historical Design Activities11.1-211.1.2Realistic Model for Radioactivities in Systems and Components11.1-211.1.3Plant Leakage11.1-311.1.4Additional Sources11.1-311.2LIQUID WASTE SYSTEMS11.2-111.2.1DESIGN OBJECTIVES11.2-1 11.2.2SYSTEMS DESCRIPTIONS11.2-1 Table of Contents1-xciWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.2.3SYSTEM DESIGN11.2-411.2.3.1Component Design11.2-411.2.3.2Instrumentation Design11.2-911.2.4Operating Procedure11.2-1011.2.5PERFORMANCE TESTS11.2-1611.2.6ESTIMATED RELEASES11.2-17 11.2.6.1NRC Requirements11.2-1711.2.6.2 Westinghouse PWR Release Experience11.2-1711.2.6.3Expected Liquid Waste Processing System Releases11.2-1711.2.6.4Turbine Building (TB) Drains11.2-1711.2.6.4.1Purpose11.2-1711.2.6.4.2Description11.2-17
Condensate Polishing Demine ralizer System Drains 18 Other Turbine Building Drainage 18 Oil and Oily Water Drainage 18 11.2.6.5Estimated Total Liquid Releases11.2-1811.2.7RELEASE POINTS11.2-1811.2.8DILUTION FACTORS11.2-19 11.2.9ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS11.2-1911.2.9.1Assumptions and Calculational Methods11.2-19 11.2.9.2Summary of Dose from Radionuclides in Liquid Effluents11.2-2111.3GASEOUS WASTE SYSTEMS11.3-111.3.1Design Bases11.3-111.3.2SYSTEM DESCRIPTIONS11.3-111.3.3SYSTEM DESIGN11.3-311.3.3.1Component Design11.3-3 11.3.3.2Instrumentation Design11.3-311.3.4Operating Procedure11.3-411.3.5Performance Tests11.3-6 11.3.6Deleted by Amendment 7711.3-611.3.7Radioactive Releases11.3-611.3.7.1NRC Requirements11.3-6 11.3.7.2Westinghouse PWR Experience Releases11.3-611.3.7.3Expected Gaseous Waste Processing System Releases11.3-711.3.7.4Releases from Ventilation Systems11.3-7 11.3.7.5Estimated Total Releases11.3-711.3.8Release Points11.3-711.3.9Atmospheric Dilution11.3-911.3.10Estimated Doses from Radionuclides in Gaseous Effluents11.3-911.3.10.1Assumptions and Calculational Methods11.3-911.3.10.2Summary of Annual Population Doses11.3-12 1-xciiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.4PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYS-TEM11.4-111.4.1Design Objectives11.4-111.4.2Continuous Monitors11.4-211.4.2.1Liquid Monitors11.4-211.4.2.1.1Waste Disposal System Liquid Effluent Monitor11.4-211.4.2.1.2Essential Raw Cooling Water Effluent Monitors11.4-211.4.2.1.3Component Cooling System Liquid Effluent Monitors11.4-311.4.2.1.4Steam Generator Blowdown Effluent Monitor11.4-311.4.2.1.5Condensate Demineralizer Regenerant Effluent Monitor11.4-311.4.2.1.6Turbine Building Sump Effluent Monitor11.4-311.4.2.2Gaseous Monitors11.4-411.4.2.2.1Waste Gas Holdup System Effluent Monitor11.4-411.4.2.2.2Condenser Vacuum Air Exhaust Monitors11.4-411.4.2.2.3Spent Fuel Pool Accident Radiation Monitors11.4-511.4.2.2.4Ventilation Monitors and Containment Atmosphere Monitors11.4-511.4.2.2.5Main Control Room Air Intake Monitors11.4-711.4.2.2.6Containment Purge Air Exhaust Monitors11.4-811.4.2.2.7Main Steamline Radiation Monitors11.4-811.4.3SAMPLING11.4-811.4.4CALIBRATION AND MAINTENANCE11.4-911.5SOLID WASTE MANAGEMENT SYSTEM11.5-111.5.1Design Objectives11.5-1 11.5.2System Inputs11.5-111.5.3Systems Description11.5-1 11.5.3.1Wet Active Waste Handling11.5-111.5.3.2Dry Active Waste Handling11.5-311.5.3.3Miscellaneous Waste Handling11.5-4 11.5.4Equipment Operation11.5-411.5.4.1Mobile Solidification System (MSS)11.5-411.5.5Storage Facilities11.5-4 11.5.5.1Inplant Storage Area11.5-411.5.5.2Outside Radwaste Storage11.5-411.5.6Shipment11.5-511.6Offsite Radiological Monitoring Program11.6-111.6.1Expected Background11.6-2 11.6.2Critical Pathways to Man11.6-211.6.2.1Doses from Gaseous Effluents11.6-311.6.2.2Internal Doses from Liquid Effluents11.6-3 11.6.3Sampling Media, Locations, and Frequency11.6-411.6.4Analytical Sensitivity11.6-411.6.5Data Analysis and Presentation11.6-4 Table of Contents1-xciiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.6.6Program Statistical Sensitivity11.6-411ATRITIUM CONTROL11A.1SYSTEM SOURCES11A.1-111A.1.1The Fission Source11A.1-111A.1.2Control Rod Source11A.1-1 11A.1.3Boric Acid Source11A.1-111A.1.4Burnable Shim Rod Source11A.1-211A.2Tritium Releases11A.1-211A.3 Design Bases11A.1-211A.4Design Evaluation11A.1-211A.5Tritium Lead Test Assembly (This section to be provided at a later date)11A.1-311A.6Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only)11A.1-312.0RADIATION PROTECTION12.1Assuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable (ALARA)12.1-112.1.1Policy Considerations12.1-112.1.2Design Considerations12.1-112.1.3ALARA Operational Considerations12.1-112.2RADIATION SOURCES12.2-312.2.1Contained Sources12.2-3 12.2.1.1Primary System Sources12.2-3 12.2.1.1.1Sources Shielded by Primary Shield Concrete12.2-312.2.1.1.2Sources Shielded by Secondary Shield Concrete12.2-412.2.1.2Auxiliary Systems Sources12.2-4 12.2.1.2.1Chemical and Volume Control System - Mixed-Be d Demineralizers 12.2-412.2.1.2.2Chemical and Volume Control System - Cation Bed Demineralizer12.2-412.2.1.2.3Chemical and Volume Control System - Volume Control Tanks12.2-512.2.1.2.4Chemical and Volume Control System - Reactor Coolant Filter12.2-512.2.1.2.5Chemical and Volume Control System - Seal Water Return Filter12.2-512.2.1.2.6 Chemical and Volume Control System - Seal Wate r Injection Filters 12.2-612.2.1.2.7Chemical and Volume Control System - Holdup Tanks12.2-612.2.1.2.8Chemical and Volume Control System - Evaporator Feed Mixed-Bed Ion 1-xcivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle PageExchangers12.2-612.2.1.2.9Chemical and Volume Control System - Evaporator Feed Cation Bed Ion Exchanger12.2-712.2.1.2.10Chemical and Volume Control System - Ion Exchange Filters12.2-712.2.1.2.11Gas Stripper and Boric Acid Evaporator Package12.2-712.2.1.2.12Spent Fuel Pool Cooling System Demineralizer and Filters12.2-812.2.1.3Sources During Refueling12.2-1012.2.1.4Maximum Hypothetical Accident (MHA) Sources12.2-1012.2.1.5Condensate Demineralizer Waste Evaporator12.2-11 12.2.2Airborne Radioactive Material Sources12.2-1112.3RADIATION PROTECTION DESIGN FEATURES12.3-112.3.1Facility Design Features12.3-112.3.2Shielding12.3-312.3.2.1Design Objectives12.3-312.3.2.2 Design Description12.3-3 12.3.3Ventilation12.3-1512.3.3.1Airflow Control12.3-1512.3.3.2Typical System12.3-15 12.3.3.3Additional Radiation Controls12.3-1612.3.4Area Radiation and Airborne Radioactivity Monitoring Instrumentation12.3-1712.3.4.1Area Radiation Monitoring Instrumentation12.3-1712.3.4.1.1Objectives and Design Basis12.3-1712.3.4.1.2Operation Characteristics12.3-17 Area Monitor Detector 17
Main Control Room Rateme ter (0-M-12, 1-,2-M-30) 18Local Indicator-Alarm Panel 18 Multipoint Recorders (Main Cont rol Room 0-M-12, 1-,2-M-31) 18 Monitor Sensitivity and Range 1812.3.4.1.3Area Monitor Calibration and Maintenance12.3-1812.3.4.2Airborne Particulate Radioactivity Monitoring12.3-1912.3.4.2.1Design Basis12.3-1912.3.4.2.2Airborne Monitoring Channels12.3-2012.3.4.2.3Operational Characteristics12.3-20 12.3.4.2.4Component Descriptions12.3-2112.3.4.2.5Sensitivity, Range and Set Point12.3-2212.3.4.2.6Calibration and Maintenance12.3-22 12.3.4.3Deleted by Amendment 84.12.3-2312.3.4.4Special Radiation Monitors12.3-2312.3.4.4.1Portal Monitors12.3-2312.3.4.4.2Personnel Contamination Monitors12.3-2312.3.4.4.3Deleted by Amendment 84.12.3-2312.4DOSE ASSESSMENT12.4-1 Table of Contents1-xcvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page12.5RADIATION PROTECTION PROGRAM12.5-112.5.1Organization12.5-112.5.2Equipment, Instrumentation, and Facilities12.5-212.5.3Procedures12.5-413.0CONDUCT OF OPERATIONS13.1ORGANIZATIONAL STRUCTURE OF APPLICANT13.1-113.1.1Corporate Organization13.1-113.1.1.1Design Responsibilities13.1-1 13.1.2Nuclear Power13.1-213.1.2.1Offsite Organizations13.1-213.1.2.2Onsite Organization13.1-2 13.1.3Qualification Requirements for Nuclear Facility Personnel13.1-213.2TRAINING PROGRAMS13.2-113.2.1Accredited Training Programs13.2-113.2.2General Employee and Fitness for Duty Training Programs13.2-113.2.3Other Training Programs13.2-213.3Emergency Planning13.3-113.4REVIEW AND AUDIT13.4-113.4.1Onsite Review13.4-113.4.2Independent Review and Audit13.4-113.5SITE PROCEDURES13.5-113.5.1SYSTEM OF SITE PROCEDURES13.5-1 13.5.1.1Conformance with Regulatory Guide 1.3313.5-1 13.5.1.2Preparation of Procedures13.5-113.5.1.3Administrative Procedures13.5-213.5.2Operating and Maintenance Procedures13.5-2 13.5.2.1Operating Procedures13.5-213.5.2.1.1General Operating Instructions13.5-213.5.2.1.2System Operating Instructions13.5-2 13.5.2.1.3Abnormal Operating Instructions13.5-313.5.2.1.4Emergency Instructions13.5-313.5.2.1.5Alarm Response Instructions13.5-313.5.2.1.6Fuel Handling Instructions13.5-313.5.2.2Other Procedures13.5-3 13.5.2.2.1Maintenance Instructions and Modification Procedures13.5-313.5.2.2.2Instrument Maintenance Instructions13.5-313.5.2.2.3Surveillance Instructions and Technical Requirement Instructions13.5-413.5.2.2.4Technical Instructions13.5-4 1-xcviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page13.5.2.2.5Miscellaneous Procedures13.5-413.5.2.2.6Power Escalation Tests13.5-413.6PLANT RECORDS13.6-113.6.1Plant History13.6-113.6.2Operating Records13.6-113.6.3Event Records13.6-113.7NUCLEAR SECURITY13.7-113.7.1Physical Security and Contingency Plan13.7-113.7.2Personnel and Program Evaluation13.7-1 13.7.3Physical Security of TPBARs13.7-114.0INITIAL TEST PROGRAM14.1SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORT14.1-114.2TEST PROGRAM14.2-114.2.1Summary of Test Program and Objectives14.2-114.2.2Organization and Staffing14.2-3 14.2.2.1Startup and Test Organization14.2-314.2.2.1.1Startup Manager14.2-314.2.2.1.2Section deleted by Amendment 8414.2-414.2.2.1.3System Test Engineers14.2-414.2.2.2Plant Operating Organization14.2-514.2.2.2.1Technical Support Manager14.2-514.2.2.2.2Power Ascension Test Engineers14.2-514.2.2.2.3Operations14.2-614.2.2.2.4Maintenance14.2-6 14.2.2.3Nuclear Assurance14.2-614.2.2.4Major Participating Organizations14.2-614.2.2.4.1Nuclear Engineering14.2-6 14.2.2.4.2Construction14.2-714.2.2.4.3Westinghouse Electric Corporation14.2-714.2.2.5Joint Test Group14.2-7 14.2.2.5.1JTG Membership14.2-814.2.2.6Test Review Group14.2-814.2.2.6.1TRG Membership14.2-814.2.2.7Personnel Qualifications14.2-914.2.3Test Procedures14.2-9 14.2.3.1General14.2-914.2.3.2Development of Procedures14.2-1014.2.3.3Review and Approval of Test Procedures14.2-1014.2.3.4Format of Test Procedures14.2-10 Table of Contents1-xcviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page14.2.3.5Test Procedure Revisions/Changes14.2-1114.2.4Conduct of Test Program14.2-1214.2.4.1Administrative Procedures14.2-1214.2.4.2Component Testing14.2-1214.2.4.3Preoperational and Acceptance Testing14.2-1314.2.4.4Power Ascension Testing14.2-13 14.2.4.5Test Prerequisites14.2-1314.2.4.6Phase Evaluation14.2-1314.2.4.7Design Modifications14.2-14 14.2.5Review, Evaluation, and Approval of Test Results14.2-1414.2.6Test Records14.2-1414.2.7Conformance of Test Programs with Regulatory Guides14.2-1514.2.8Utilization of Reactor Oper ating and Testing Experience in Development of Test Pro-gram 14.2-2914.2.9Trial Use of Plant Operating and Emergency Procedures14.2-3014.2.10Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Pow-er Ascension14.2-3014.2.10.1Fuel Loading14.2-30 14.2.10.2Postloading Tests14.2-3314.2.10.3Initial Criticality14.2-3314.2.10.4Low Power Tests14.2-34 14.2.10.5Power Ascension14.2-3414.2.11Test Program Schedule14.2-3414.2.12Individual Test Descriptions14.2-35 14.2.12.1Preoperational Tests14.2-3514.2.12.2Power Ascension Tests14.2-3615.0ACCIDENT ANALYSES15.1CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS15.1-115.1.1Optimization of Control Systems15.1-215.1.2Initial Power Conditions Assumed In Accident Analyses15.1-315.1.2.1Power Rating15.1-315.1.2.2Initial Conditions15.1-3 15.1.2.3Power Distribution15.1-415.1.3Trip Points And Time Delays To Trip Assumed In Accident Analyses15.1-415.1.4Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux15.1-515.1.5Rod Cluster Control Assembly Insertion Characteristic15.1-515.1.6Reactivity Coefficients15.1-615.1.7Fission Product Inventories15.1-715.1.7.1Radioactivity in the Core15.1-715.1.7.2Radioactivity in the Fuel Pellet Clad Gap15.1-815.1.8Residual Decay Heat15.1-915.1.8.1Fission Product Decay Energy15.1-9 1-xcviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.1.8.2Decay of U-238 Capture Products15.1-1015.1.8.3Residual Fissions15.1-1115.1.8.4Distribution of Decay Heat Following Loss of Coolant Accident15.1-1115.1.9Computer Codes Utilized15.1-1115.1.9.1FACTRAN15.1-1115.1.9.2Deleted by Amendment 72.15.1-12 15.1.9.3 MARVEL15.1-1215.1.9.4LOFTRAN15.1-1315.1.9.5LEOPARD15.1-14 15.1.9.6TURTLE15.1-1415.1.9.7TWINKLE15.1-1415.1.9.8Deleted by Amendment 80.15.1-15 15.1.9.9THINC15.1-1515.1.9.10LOFTTR15.1-1515.2CONDITION II - FAULTS OF MODERATE FREQUENCY15.2-115.2.1Uncontrolled Rod Cluster Control Asse mbly Bank Withdrawal from a Subcritical Condition 15.2-215.2.1.1Identification of Causes and Accident Description15.2-2 15.2.1.2Analysis of Effects and Consequences15.2-315.2.1.3Conclusions15.2-515.2.2UNCONTROLLED ROD CLUSTER C ONTROL ASSEMBLY BANK WITH-DRAWAL AT POWER15.2-515.2.2.1Identification of Causes and Accident Description15.2-515.2.2.2Analysis of Effects and Consequences15.2-7 15.2.2.3Conclusions15.2-915.2.3ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT15.2-915.2.3.1Identification of Causes and Accident Description15.2-9 15.2.3.2Analysis of Effects and Consequences15.2-1115.2.3.3Conclusions15.2-1315.2.4UNCONTROLLED BORON DILUTION15.2-13 15.2.4.1Identification of Causes and Accident Description15.2-1315.2.4.2Analysis of Effects and Consequences15.2-1415.2.4.2.1Method of Analysis15.2-14 15.2.4.2.2Dilution During Refueling15.2-1415.2.4.2.3Dilution During Startup15.2-1515.2.4.2.4Dilution at Power15.2-15 15.2.4.3Conclusions15.2-1615.2.4.3.1For Dilution During Refueling15.2-1615.2.4.3.2For Dilution During Startup15.2-1615.2.4.3.3For Dilution Following Reactor Shutdown15.2-1615.2.4.3.4For Dilution During Full Power Operation15.2-1615.2.5PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW15.2-1715.2.5.1Identification of Causes and Accident Description15.2-17 Table of Contents1-xcixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.2.5.2Analysis of Effects and Consequences15.2-1815.2.5.3Conclusions15.2-1915.2.6Startup of an Inactive Reactor Coolant Loop15.2-1915.2.6.1Identification of Causes and Accident Description15.2-1915.2.6.2Analysis of Effects and Consequences15.2-1915.2.6.3Conclusions15.2-21 15.2.7LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP15.2-2115.2.7.1Identification of Causes and Accident Description15.2-2115.2.7.2Analysis of Effects and Consequences15.2-22 15.2.7.3Conclusions15.2-2415.2.8LOSS OF NORMAL FEEDWATER15.2-2415.2.8.1Identification of Causes and Accident Description15.2-24 15.2.8.2Analysis of Effects and Consequences15.2-2515.2.8.3Conclusions15.2-2815.2.9COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES15.2-2815.2.10EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SY STEM MALFUNC-TIONS 15.2-2815.2.10.0.1Identification of Causes and Accident Description15.2-2815.2.10.1Analysis of Effects and Consequences15.2-2815.2.10.2Conclusions15.2-31 15.2.11Excessive Load Increase Incident15.2-3115.2.11.1Identification of Causes and Accident Description15.2-3115.2.11.2Analysis of Effects and Consequences15.2-3215.2.11.3Conclusions15.2-3315.2.12ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM 15.2-3315.2.12.1Identification of Causes and Accident Description15.2-3315.2.12.2Analysis of Effects and Consequences15.2-3315.2.12.3Conclusions15.2-34 15.2.13ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM15.2-3415.2.13.1Identification of Causes and Accident Description15.2-3415.2.13.2Analysis of Effects and Consequences15.2-3615.2.13.3Conclusions15.2-3815.2.14Inadvertent Operation of Emergency Core Cooling System15.2-3815.2.14.1Identification of Causes and Accident Description15.2-3815.2.14.2Analysis of Effects and Consequences15.2-3915.2.14.3Conclusions15.2-4215.3CONDITION III - INFREQUENT FAULTS15.3-115.3.1Loss of Reactor Coolant From Small Ruptured Pipes or From Cracks in Large Pipes Which Actuate the Emergency Core Cooling System15.3-115.3.1.1Identification of Causes and Accident Description15.3-1 1-cTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.3.1.2Analysis of Effects and Consequences15.3-215.3.1.3Reactor Coolant System Pipe Break Results15.3-315.3.1.4Conclusions - Thermal Analysis15.3-415.3.2Minor Secondary System Pipe Breaks15.3-515.3.2.1Identification of Causes and Accident Description15.3-515.3.2.2Analysis of Effects and Consequences15.3-5 15.3.2.3Conclusions15.3-515.3.3Inadvertent Loading of a Fuel Assembly Into an Improper Position15.3-515.3.3.1Identification of Causes and Accident Description15.3-5 15.3.3.2Analysis of Effects and Consequences15.3-615.3.3.3Conclusions15.3-715.3.4Complete Loss of Forced Reactor Coolant Flow15.3-7 15.3.4.1Identification of Causes and Accident Description15.3-715.3.4.2Analysis of Effects and Consequences15.3-815.3.4.3Conclusions15.3-9 15.3.5Waste Gas Decay Tank Rupture15.3-915.3.5.1Identification of Causes and Accident Description15.3-915.3.5.2Analysis of Effects and Consequences15.3-10 15.3.6Single Rod Cluster Control Assembly Withdrawal at Full Power15.3-1015.3.6.1Identification of Causes and Accident Description15.3-1015.3.6.2Analysis of Effects and Consequences15.3-11 15.3.6.3Conclusions15.3-1115.4CONDITION IV - LIMITING FAULTS15.4-115.4.1Major Reactor Coolant System Pipe Ru ptures (Loss of Coolant Accident)15.4-115.4.1.1Thermal Analysis15.4-315.4.1.1.1Westinghouse Performance Criteria for Emergency Core Cooling System 15.4-315.4.1.1.2Method of Thermal Analysis15.4-315.4.1.1.3Containment Analysis15.4-315.4.1.1.4Results of Large Break Spectrum15.4-4 15.4.1.1.5Effect of Containment Purging15.4-515.4.1.1.6Conclusions - Thermal Analysis15.4-615.4.1.2Hydrogen Production and Accumulation15.4-615.4.1.2.1Method of Analysis15.4-615.4.1.2.2Typical Assumptions15.4-715.4.1.2.3Core Solution Radiolysis15.4-9 15.4.1.2.4Sump Solution Radiolysis15.4-1115.4.1.2.5Results15.4-1215.4.2Major Secondary System Pipe Rupture15.4-1215.4.2.1Major Rupture of a Main Steam Line15.4-1215.4.2.1.1Identification of Causes and Accident Description15.4-1215.4.2.1.2Analysis of Effects and Consequences15.4-1415.4.2.1.3Conclusions15.4-19 Table of Contents1-ciWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.4.2.2Major Rupture of a Main Feedwater Pipe15.4-1915.4.2.2.1Identification of Causes and Accident Description15.4-1915.4.2.2.2Analysis of Effects and Consequences15.4-2015.4.2.2.3Conclusions15.4-2215.4.3Steam Generator Tube Rupture15.4-2315.4.3.1Identification of Causes and Accident Description15.4-23 15.4.3.2Analysis of Effects and Consequences15.4-2615.4.3.3Conclusions15.4-3215.4.4Single Reactor Coolant Pump Locked Rotor15.4-32 15.4.4.1Identification of Causes and Accident Description15.4-3215.4.4.2Analysis of Effects and Consequences15.4-3215.4.4.3Conclusions15.4-35 15.4.5Fuel Handling Accident15.4-3515.4.5.1Identification of Causes and Accident Description15.4-3515.4.5.2Analysis of Effects and Consequences15.4-35 15.4.6Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)15.4-3515.4.6.1Identification of Causes and Accident Description15.4-35 15.4.6.1.1Design Precautions and Protection15.4-3515.4.6.1.2Limiting Criteria15.4-3815.4.6.2Analysis of Effects and Consequences15.4-39 15.4.6.3Conclusions15.4-4315.5ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS15.5-115.5.1Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil-iaries 15.5-115.5.2Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture15.5-2 15.5.3Environmental Consequences of a Postulated Loss of Coolant Accident15.5-215.5.4Environmental Consequences of a Postulated Steam Line Break15.5-1915.5.5Environmental Consequences of a Postulated Steam Generator Tube Rupture15.5-2015.5.6Environmental Consequences of a Po stulated Fuel Handling Accident15.5-2115.5.7Environmental Consequences of a Postulated Rod Ejection Accident15.5-2315A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL CONSEQUENC-ES OF ACCIDENTS15A.1INTRODUCTION15A-115A.2ASSUMPTIONS15A-115A.3GAMMA DOSE AND BETA DOSE15A-115A.4THYROID INHALATION DOSE15A-2 1-ciiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page16.0TECHNICAL SPECIFICATIONS16.1PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)16.1-116.2PROPOSED FINAL TECHNICAL SPECIFICATIONS16.2-116.3RELOCATED SPECIFICATIONS16.1-116.3.1Discussion16.1-116.3.2Document Control16.1-116.3.3Changes to the Relocated Specifications16.1-117.0QUALITY ASSURANCE17-117.1Quality Assurance During Design and Construction17-117.1.1TVA Organization17-117.1.2Quality Assurance Program17-1 17.1AWESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSURANCE PLAN17-217.2QUALITY ASSURANCE FOR STATION OPERATION17.2-117.2.1Identification of Safety-Related Features17.2-1 Table of Contents1-ciiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page 1-civTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page