clinc.h breederreacto.r preimi.nary ii, a safety … · geography and demography site location and...

84.. .. 2. :

CLINC.H ýRIVER

BREEDERREACTO.R PROJECT

ii, APREIMI.NARYSAFETY ANALYSIS

ýREPOR-T

::V:OLUME: .24 "

PROJECT, MANAGEMENT CORPORATION

"'-fr- ,

TABLE OF CONTENTS

Section • ..

O 1.0 INTRODUCTIONAND GENERAL DESCRIPTION OF TIE, PLANT 1.1-1

1.1 INTRODUCTION 1.1 A1

* 1.1.1 General Information 1.1-21.1.2 Overview of Safety Design Approach 1.1-31.1.3 Applicability of Regulatory Guides 1.1-5

1.2 GENERAL PLANT DESCRIPTION 1.2-1

1.2.1 Site 1 .2-41.2.2 Engi neered Safety Features 1.2-21.2.3 Reactor, Heat Transport and Related Systems 12-'21.2.4 Steam:Generator -Turbine and Related Systems 1.2-31.2.5 Offsi~te and OnsItei ower 1.2-5 :1.2.6. Instrumentatlon, Control and Protection 1.2-61.2.7 Auxiliary Systems 1. 2-71.2.8 Refuel Ing System 1.2-81.2.9 Radwaste Disposal System -. 2-91.2.10 Reactor Confinement/Containment System 1.2-91.2.11 Major Structures 1. 2-10

1.3 COPARISON TABLES 1.3-1

1.3.1 Comparisons with Simll ar Designs, 1.3-11.3.2 Detailed Comparison with Fast Flux Test Facility 1.3-2

1.4 IDENTIFICATIONOF PROJECT PARTICIPANTS t1.4-1

1.4.1 Functions, Responsibilities and AuthorItIes ofProject Participants 1.4-2

1.4.2 Description of Organizations 1.4-31.4.3 Interrelationships with Contractors and Suppliers 1.4-21a1.4.4 General QualIfIcatlon Requirement of CRBRP

Project Participants 1.4-22

1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1

1.5.1 Information Concerning the Adequacy of a NewDesign 1.5-21

1.5.2 Information Concerning Margin of Conservatism ofProven Design 1.5-28

1.5.3 References 1.5-47

,- '.Amend. G8.May -1982

i : : ' .7.

TABLE OF CONTENTS (Cont'd.)

1.6

1.6.11 .6.2

MATERIAL INCORPORATED BY REFERENCE

IntroductionReferences

.Appendix 1-A Flow Diagram SymbolsI

2.0

2.1.

2.1.22.1.22 .1,4

2.2

2.2.22.2.3

2.3

2.3.12.3.2

2.3.32.3.4

2.3.5

2.4

2.4.12.4.22.4.3

2.4.4

2.4.72.4.82.4.92.4.102.4.112.4..122.4.132.4. t4

SITE CHARACTERISTICS

GEOGRAPHY AND DEMOGRAPHY

Site Location and LayoutSite DescriptionPopulation and Population DistrlbutqionUses. of Adjacent Lands and,,Wate.rs

NEARBY INDUSTRIAL.. TRANSPORTATION AND MILITARY

Locations, Routes, and DescriptionsEvaluationsNew-Facil.ity/Land Use Requirements

MEIEOROLOGY

Regional ClimatologyLocal ýMeteorology•On-site Meteorological Monltoring.ProgramShort-Term (Acci-dent) Diffusion EstimatesLong-Term (Average) Diffusion Estimates

HYDROLOG IC ENGINEERING

Hydrologic DescriptionFloods.Probable Maximum Flood (PMF) on Streams andRiversPotential Dam Failures (Seismically andOtherwise Induced)Ice FloodingCooling Water Canals and ReservoirsChannel DiversionsFlooding Protection Requirements...Low Water ConsiderationsEnvironmental Acceptance of Effluents

.GroundwaterTechnical Specification and Emergency OperationRequirement.

1 .6-1

-1.6-11 .6-1Il.A-i

2.1-1

2.1-1

2.1-2,2.1-ý42.8 .I

2.2a-1

2.2-1.2.2-32.2-4c

2.3-1

2.3-12. 3--42.3,91

2.3-92. 3 -ý9,2.3-13

2.4-I

2.4-12.4-6

2.4-10

2.4-212.4-312.4-31a2.4-322.4-322.4-332.4-422.4-44

2.4-55

Amend. 68May 1982

IfI

TABLE OF CONTENTS (Contd.)

2.5 GEOLOGY AND SEISMOLOGY 2.5-1

2.5.1 Basic Geologic and Seismic Information 2.5-12.5.2 Vibratory Ground Motion 2.5-202.5.3 Surface Faulting 2.5-272.5.4 Stability of Subsurface Materials 2.5-322.5.5 Slope Stability -2.5-48a

Appendix 2-A Field Investigative Procedures 2A-1Appendix 2-B Laboratory Test Procedures 2B-1Appendix 2-C Report of Test Grouting.Program 2C-1Appendix 2-D •Report of Engineering Propertles -for Crushed Stone Materials from CommercIalSuppliers 2D-1AppendiX 2-E Extracts from .U.S. AtomicEnergy. Comm:lssion AEC Manual 2E- 1

Supplement 1 to Chapter 2 Deleted

Supplement 2 to Chapter 2 Question and ResponsesRelated to Chapter Two Information and Cri.ticalFor NRC Docketing of GRBRP Environmental Report 1

3.0. DESIGN CRITERIA - STRUCTURES. COMPONENTS EOU.IPMENi~3.1-1

3.1 CONFORMANCE WI-TH GENERAL DESIGN CRITERIA 3.1-1

3.1.1 Introduction and Scope 31-13J1.2 DeflinItions and Explanations 3.1-23.1.3 Conformance with CRBRP General Design Criteria 13.1-8

3.2 CLASSIFICATIONS OF STRUCTURES. SYSTEMS,AND COMPONENTS 3.2-1

3.2.1 Selsm-ic Classifications 3.2-1

3.2.2 Safety Classifications 3.2-2

3.3 WIND AND TORNADO LOADINGS 3.3-1

3.3.1 Wind Loadings 3.3-13-.3.2 Tornado Loadings 3.3-2

3.4 WATER LEVEL (FLOOD) DESIGN 3.4"1

3.4.1 Flood Protection 3.4-13.4.2 Analysis Procedures 3.4-I a

iil Amend. 68MaY 1982

TABLE OF CONTENTS (Cont'd..)

77777

3.5-I3.5

3.5.13.5.23.5.33.5.43.5.5

3.6

3.6.13.61.23.6433.6.43.6.5I3.7

3.7.13.7.23.7%.33.7.43.7.5

@1!3.8

MI.SSILE PROTECT!ON

Missile Barrier and LoadingsMissile SelectionSelected MissilesBarrier Design Procedures-Missile Barrier Features

PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATEDWITH THE-POSTULATED"RUPTURE OF P I PING

Systems in Which Pipe Breaks are Postul'atedPipe. Break CriteriaDesign Loading Comb inati onsDynam Ic Analysis'Protective Measures

SEISMIC DESIGN

Selismic InputSeim I c Sysstem Ana! ysi sSeismic Subsy~stem .AnalysisSeismic lnstrumentatlon ProgramSel smic Design ControlAppendix to Section 3.7 Seismic Design Criteria

DESIGN OF CATEGORY I STRUCTURES

Concrete Contalinment (Not Applicable)Steel Contalnment SystemConcrete and;Structural Steel. InternalStructures of Steel ContainmentOther Seismic Category I StructuresFoundation and Concrete Supports

Appendix 3.8A Buckling Stress CriteriaAppendix 3.8-B Cell Liner Design CriteriaAppendix 3.8-C Catch Pan and Fire SuppressionDeck Design Criteria

3.5-43.5-4a3.5-7

3.5-103.5-13c

3.6-1

3.6-1

3.6-2

3.3i6-3 :3.6-8.

.3.7-1

3.7-1

3.7-4a3.7-113.7-1:63.7-20.3.7-;ýA. 1

3.8-1.

3.8-13.8-1

3.8-83.8-22a3.8-35

3.8A-1

3.8-B. 1

3.8-C. I

3.9-1

3.9-13.9-3a3.9-5

3.10-1

3.10-1

Amend. 68May 1982

3.8013.8.23.8.3

3.8.43.8.5

3.9 MECHANICAL SYSTEMS AND COMPONENTS

I

3.9.13.9.23.9.3

3.10

3.10.1

Dynamic System Analysis and TestingASME Code Class 2 and 3 ComponentsComponents Not Covered by ASME Code

SEISMIC DESIGN OF CATEGORY I INSTRUMENTATIONAND ELECTRICAL EQUIPMENT

Seismic Design Criteria

iv

....................................,~--------


Sect I on

3.10.2

3.11

3.11.13.11.23.11.33.11.43.11.5

3A. 0

Analysis, Testing. Procedures and RestraintMeasures

ENVIRONMENTAL DESIGN OF MECHANICAL ANDEL ECTR I CAL E0U IPMENT

Equipment IdentificationQualification Test and AnalysisQualification Test ResultsLoss of VentillationSpecial Considerations

SUPPLEMENTARY INFORMATION ON.SEISMIC CATEGORY I

Inner Cell SystemHead Access AreaControl BuilIdingReactor Service BuilIding (RSB)Steam Generator Bu I ld:ingDiesel Generator Bu II ding'g.DeletedCell Liner Systems

REACORY

SUMMARY DESC~R1IPTI ON

3.10-3

3.11-1

3.11-13.11-13.11-13.11-2

3:.11-2

3A: 1-1

3A. 1 -13A .2-13A. 3 13A. 4-43A.5-13A. 6-1

3A. 8-1

4.1-1

3A. 13A. 23A.33A. 43A4 53A. 63A. 73A. 8I04.0

4.14.1 -1

4.1.14.1,,24.1.34.1 .44.1.54.1.64,l .17

4.2

Lower InternalsUpper InternalsCore Restraint.Fuel Blanket and Removable Radial Shield RegionsDesign and Performance CharacteristicsLoading Conditions and Analysis TechniquesComputer Codes.

MECHANICAL DESIGN

Fuel and Blanket DesignReactor Vessels InternalsReactiVity Control Systems

NUCLEAR DESIGN

Design BasesDescriptionAnalytical MethodsChanges

4.1-14.1-34.1-44.1-44.1-94.1-94.1-10

4.2-1

4.2-14.2-1184.2-228

4.3-1

4.3-14.3-34.3-69

I

4.2.14.2.24.2.3

4.3

4.3.14.3.24.3'34.3.4

/V

Amend. 68May 1982

-~ - -~ -- - ~- .- ,~ ,.,,~ -~-';r~'-~

,.-¾>' t -

- - -- .~--g~,--~7- -- -.- ½ >--~ - c-n<--~~'~-,,' ~VA----- -


Sect Ion

4.4

4.4.14.4.24.4.34.4.44.4.5

5.0

5.1

5,1 .15.1.25.1.35.1 .45.1.55.1 .65.1.75.1 .8

5.2

THERMAL AND HYDRAULIC DESIGN

Design BasesDescriptionEval uati onTesting and VerificationCore Instrumentation

HEAT TRANSPORT AND CONNECTED SYSTEMS

SUMMARY DESCR IPT ION

Reactor Vessel, Closure Head, and Guard VesselPrimary Heat Transport System.Intermedlate Heat Transport-SystemSteam Generator SystemResidual Heat Removal SystemAuxiliary Liquid Metal SystemFeatures for Heat Transport System SafetyPhysical Arrangement

REACTOR VESSEL. CLOSURE HEAD. AND GUARD VESSEL

Design BasisDesign ParametersSpecial Processes for Fabrication and InspectionFeatures for improved Re liabilityQuality Assurance SurveillanceMaterials and InspectionsPacking, Packaging, and Storage

4.4-1

4.4-14.4-44.4-454.4-754.4-80

5.1-1

5.1-la

;5.1-la5.1-2,

5.1-55.1-75. 1-85,1-95.1-105..1..-1

5.2-1

5.2-15.2-4b5.2-75.2-85.22-10d5.2-115.2-11 a

5.2.15.2.25,2.35.2,45.2.55.2.65.2.7

Appendix 5.2.A Modifications to the High Temp-erature Design Rules for Austenitic Stainless Steel 5.2A-1

5.3

5.3.15.3.25.3.35.3.4

5.4

5.4.15.4.25.4.3

PRIMARY HEAT TRANSPORT SYSTEM (PHTS)

Design BasesDesign DescriptionDesign EvaluationTests and Inspections

INTERMEDIATE HEAT TRANSPORT SYSTEM (IHTS)

DesignDesignDesign

BasisDescriptionEvaluation

5.3-1

5.3-15.3-95.3-335.3-72

5.4-1

5.4-15.4-65.4-12

Amend. 68May 1982

vi

p ~ p p~. p p~ - - -Pr 'y''½,- -' - - ~p~ppx - 'pPP-P-pp -'-p ~ p'pp pP - ~'-~'P~'~YP p>- p '~~Y.'PP "~pp'~"~- p p p - - pP PpP PP

TARI F OF MNTFNTSq (ont td-)

SectIon

5.5

5.5.15.5.25.5.3

5.6

5.6.1

5.6.2

5.7

STEAM GENERATOR SYSTEM (SGS)

DesignDesignDesign

BasesDescriptionEvaluation

RESIDUAL HEAT REMOVAL SYSTEMS

Steam Generator Auxiliary Heat RemovalSystem (SGAHRS)Direct Heat Removal Service (DHRS)

OVERALL HEAT TRANSPORT SYSTEM EVALUATION

5.7.15.7.25.7.35.7.4

6.0

6.1

6.2

6.2.16.2.26.2,36.2.46.2.56.2.66.2.7

6.3

Startup and.ShutdownLoad Followilng CharacteristIcsTransient EffectsEvaluation of Thermal Hydraulic

.and Plant Design Heat TransportTransient Summary

ENGINEERED SAFETY FEATURES

Character I sti csSystem Design

GENERAL

CONTAINMENT-SYSTEMS

ConfineMent/Containment Functional DesignContainment Heat RembvalContainment Air Purification and Cleanup SystemContainment Isolation SystemsAnnulus Filtration SystemReactor Service Building (RSB) Filtration SystemSteam Generator Building Aerosol ReleaseMitigation System Functional Design

HABITABILITY SYSTEMS

5.5-1

5.5-15.5-55.5-17

5.6-1

5.6-1b

5.6-20

5.7-1

5.7-15.7-25.7-2a

5.7-6

6.1-1

6.1-1

6.2-1

6.2-1

6.2-96.2-96.2-106.2-146.2-16

6.2-17

6.3-1

6.3-1

6.4-1

6.4-16.4-16.4-16.4-16.4-1

6.3.1

I 6.4

6.4.16.4.26.4.36.4.46.4.5

Habitability System Functional Design

CELL LINER SYSTEM

Design Base.System DesignDesign EvaluationTests and InspectionsInstrumentation Requirements

viiAmend. 68May 1982.

7-7


P6.5 CAICH• PAN 6.5-1

6.5.1 Design Base 6.5-16.5.2 System Design Description and Evaluation 6.5-16.5.3 Tests and Inspections 6.5-16.5.4 Instrumentation Requirements 6.5-1

7.0 INSTRUMENTATION AND CONTROLS 7.1-1

7.1 INTRODUCTION 7.1-1

7.1.1 Identification of Safety Related Instrumentationand Control Systems 7.1.-1

7.1.2 Identification, of Safety Crijter:i a 7.1-1

7.2 REACTOR SHUTDOWN SYSTEM 7.2-1*

7.2.1 Description 7.2-17.2.2 Analysis 7.2-13

7.3 ENGINEERED SAFETY FEATURE INSTRUMENTATION AND

ci 7.3.1 Containment Isolation System 7.3-17.3.2 Analysis 7.3-3

7.4 INSTRUMENTATION AND. CONTROL SYSTEMS REQUIRED FORSAFE SHUDOW ;.7.4-1

7.4.1 Steam Generator Auxiliary Heat RemovalInstrumentation and Control Systems 7.4-1

7.4.2 Out.let Steam Isolation Instrumentation andControl System 7.4-6

7.4.3 Remote Shutdown System 7.4-8a

7.5 INSTRUMENTATION AND MONITORING SYSTEM 7.5-1

7.5.1 Flux Monitorlng System 7.5-17.5.2 Heat Transport Instrumentation System 7.5-57.5.3 Reactor and Vessel Instrumentation 7.5-137.5.4 Fuel Failure Monitoring System, 7.5-147.5.5 Leak Detection Systems 7.5-187.5.6 Sodium-Water .Reaction Pressure Relief System

(SWRPRS-) Instrumentation and Controls 7.5-307.5.7 Containment Hydrogen Monitoring 7.5-33b7.5.8 Containment Vessel Temperature Monitoring 7.5-33b7.5.9 Containment Pressure Monitoring 7.5-33b7.5.10 Containment Atmosphere Temperature 7.5-33c( 7.5.11 Post Accident Monitoring 7.5-33c

O VilllAmend. 68

May 1982


SectIon

7.6

7.6.1

7.6.27.6.3

7.6.4

7.6.5

OTHER INSTRUMENTATION AND CONTROL SYSTEMS REQUIREDFORSAETY.

Plant Service Water and Chilled WaterInstrumentation and Control SystemsDeletedDirect Heat Removal Service (DHRS)Instrumentation and Control SystemHeating, Ventilating, and Air ConditioningInstrumentation and Control SystemSGB Floodlng Protection Subsystem

INSTRUMENTATION AND CONTROL SYSTEMS NOT.REUIIRED

PlantlControl System DescriptionDesign Analysis

PLANT DATA:HANDLING AND DISPILAY SYSTFM

7.6-1

7.6-1

7.6-3

7.6-3e7.6-31f

7.7

7.7.17.7.2

7.8

7.8.17.8.2

7.9

7.9.17,9.27.9.37.9.47.9.5

8.0

8.1

8.1.18.1.28.1.3

8.2

8.2.18.2.2

8.3

8.3.18.3.2

Design DescriptionDes.gn AAnalysis

OPFRATING. CONTROL. STATIONS

Design BasisControl RoomLocal, Control StationsCommun I cationsDesign Evaluation

ELECTRIC POWER

INTQRODUCTION

UtIlIty Grid and InterconnectionsPlant Electrical Power SystemCriteria and Standards

OFFSITE POWER SYSTEM

7.7-1

7.7-17.7 -116

7.8-1

7.8"1

7.8-2

7.9-1

7.9-!1.7 i.,9417. 9"67.9-6:7..9-'6

8.1-1

8.1-1

8.1-18.1-18.1-3

8.2-1

8.2-18.2-4

8.3-1

8.3-18.3-44

Amend. 68May. 1982

DescriptionAnalysis

ON-SITE POWER SYSTEMS

I

AC Power SystemsDC Power System

Ix

.7,777.


Section

9.0

9.1

9*1 .I19.1.29.1.39.1.4

AUXILIARY SYSTEMS

FUEl STORAGE AND HANDLING

I 9.2

9.2.19.2.29.2.39.2-49.2-5

9.3

New Fuel StorageSpent Fuel StorageSpent Fuel Cooling and Cleanup SystemFuel Handling System

NUCLEAR ISLAND GENERAL PURPOSEMAINTENANCE SYSTEM

Design BasisSystem DescriptionSafety EvaluationTests and InspectionsInstrumentatilon AppI ications

AUXILIARY LIQUID METAL SYSTEM

Sodium -and NaK.Receivi.ng SystemPrimary Na Storage and Process.IngEVS Sod.ium Pr.ocessingPri mary Cold Trap NaK Cooling SystemIntermedilate Na Processing System

PIPING AND:EQUIPMENT ELECTRICAL HEATING

Design Bases.Systems Description.Safelty EvaluatlonTests and InspectionsInstrumentation Application

INERT GAS RECEIVING AND PROCESSING SYSTEM

9.3.19.3.29.3.39.3.49.3-.5

9.4

9.4.1.9.4.29.4.39.4.49.4.5

9.5

Page

9.1-1

.9. 1-1

9.1-39.1-59.1-209.1-33

9.2-1

9.2.-1,

9. 2-3,9.2-39.2-4

9.3-1

9.3-l a9,3 2:

9.31-2'9.3-.9a9.3:-10

9.3-12

9.4-1

9,4-19.4-29.4-3,9.4-3b9.4-3 b

9.5-1

9.5-29.5-69.5-109.5-129.5-12

9.6-1

9.6-19.6-129.6-259.6-379.6-409.6-45

9.5.19,5.29.5.3

9.5.49.5.5

9.6

9.6.19.6.29.6.39.6.49.6.59.6.6

Argon Distribution SubsystemNitrogen Distribution SystemSafety EvaluationTests and InspectionsInstrumentation Requirements

HEATING. VENTILATING AND AIR CONDITIONING SYSTEM

Control Building HVAC SystemReactor Containment BuildingReactor Service Building HVAC SystemTurbine Generator Bulldlng HVAC SystemDiesel Generator Building HVAC SystemSteam Generator Building HVAC System

J

xAmend. 68May 1982

- -,

-- A AA- A ~------- A A A< A~

TABLE OF CONTENTS (Cont'd;)

\- / Sect I on ''PAW•g ".

9.7 CHILLED WATER SYSTEMS 9.7"1

9.7.1 Normal Chilled Water System 9.7-19.7.2 Emergency Chilled Water System 9.7-49.7.3 Prevention of Sodium or NaK/Water Interactions 9.7-99.7.4 Secondary Coolant Loops (SCL) 9.7-12

9.8 IMPURITY MONITORING AND ANALYSIS SYSTEM 9.8-1

9.8.1 Design Basis 9.8-19.8.2 Design Description 9.8-i2. "9.8.3 Design Evaluati.on -9859.8.4 Tests and inspection 9.8-79.8.5 Instrumentation Requirements 9.8-8:

9.9 SERVICE WATER SYSTEMS 979-1

9.9.1 Normal Plant Servilce .Water System 019919.9.2 Emergency Pllant ServicevlWater System 9.9-29.9.3 Secondary ServiceP Clo,,sedi, Co01ing Water System 9.9-4,9.9.5 River Water Serv ice 9:"91.94-1

9.10 COMPRESSED GAS SYSTEM 9.10-1

9.10.1 Serv Ice Air ýand Instrument Air Systems 9.10-19.10.2 Hydrogen System 9.10-3a9.10.3 Carbon Dioxide System 9. 10-4

9.11 COMMUNICATIONS SYSTEM 9.11-1

9.11.1 Design Bases 9.11-19.11.2 Description 9.11-3

9.12 LIGHTING SYSTEMS 9.12-1

9.12.1 Normal Lighting System 9.12-19.12.2 Standby Lighting Systems 9.12-29.12.3 Emergency Lighting System 9.12-39.12.4 Design Evaluation 9.12-4

9.13 PLANT FIRE PROTECTION SYSTEM 9.13-1

9.13.1 Non-Sodium Fire Protection System 9.13-19.13.2 Sodium Fire Protection System (SFPS) 9.13-139.13A Overall Fire Protection Requirements-- CRBRP

Design Compared with APCSB 9.5-1 & ASB 9.5-1 9.13A-1

9.14 DIESEL GENERATOR AUXILIARY SYSTEM 9.14-1

9.14.1 Fuel Oil Storage and Transfer System 9.14-1

xi Amend. 68

May 1982


-•" ~Sect I on ' -

9.14.2 Cool Ing Water System 9.14--!'29.14.3 Starting Air Systems 9.14-49.14.4 Lubrication System 9.14-5

9.15 EQUIPMENT AND FLOOR DRAINAGE SYSTEM 9.15-1

9.15.1 Design Bases 9.15-19.15.2 System Description 9.15-19.15.3 Safety Evaluation g.15-29.15.4 Tests-and Inspections 9. 15-29.15.5 Instrumentation Applicatlon 9.15-2

9.16 RECIRCULATION'GAS;COOLING SYSTEM 9.16-6

9.1.6.1 Design Basis 9.16..9.16.2 System Description 9.16 1-9.16.3 Safety Eva l uatlon 9.16-69.16.4 Tests and I nspecion 9 .167...9.16.5 Instrumentation and Control 9.16-7

10.0 STEAM AND POWER CONVERSION SYSTEM 10.1-1

10.1 SUMMARY DESCRIPTION 10..1-1

10.2 TURBINE: GENERATOR 10.2-1

10.2.1 Design Bases 10.2-110.2.2 Description 10..2-1a10.2.3 Turbine Missiles 10,2-510.2.4 Evaluation 10.2-9

10.3 MAIN STEAM SUPPLY SYSTEM 10.3-1

10.3.1 Design Bases 10.3-110.3.2 Description 10.3-110.3.3 Evaluation 10.3-210.3.4 Inspection and Testing Requirements 10.3-210.3.5 Water Chemistry 10.3-3

10.4 OTHER FEATURES OF STEAM AND POWER CONVERSIONSYSTEMI 10.4-1

10.4.1 Condenser 10.4-110.4.2 Condenser Air Removal System 10.4-210.4.3 Turbine Gland Sealing System 10.4.310.4.4 Turbine Bypass System 10.4-410.4.5 Circulating Water System 10.4-510.4.6 Condensate Cleanup System 10.4-7

xilAmend. 68May 1982


10.4.710.4.8

11.0

11.1

11.1.111.1.211.1.311.1.411.1.5

11.1.6

11.2

11.2.111.2.211.2.31 1.2.411.2.511.2.611.2.711 .2.8

11.3

Condensate and-Feedwater SystemsSteam Generator Blowdown System

RADIOACTIVE WASTE MANAGEMENT

SOURCE TERMS

Modes of Radioactive Waste ProductionActivation Product Source Strength ModelsFission Product and Plutonium Release ModelsTritium Production SourcesSummary of Design Bases for Deposltion ofRadioactivit in Primary Sodium on 'Ractor and

Primary Heat Transfer Surfaces :andý,W Ith.InReactor AUxiliary Systes"Leakage Rates

LIQUID WASTE SYSTEM

Design ObjectivesSystem DescriptIonSystem DesignOperating Procedures and Performance TestsEstimated ReleasesRelease PoIntsDilution FactorsEstimated DosesAppendlx 11.2A Dose Models: Liquid Effluents

GASEOUS WASTE SYSTEM

10.4-91-0.4-14

11.1-1

11.1-1

11.1-1

11 .1-211. 1-511 .1-7

11.;1-7

.11.1-.Zo

11.2-;1

i11.2-11 1.2-21t-.2-;411-.2-511.2-6:

11.2-611,2-711..2-8

11.2A41

11.3-1

11.3.111.3.211.3.311.3.411.3.511.3.611.3.71 .3.8

11.4

Design Base 11.3-1System Descrlptlon 11-.3-ISystem Design 11.3-10Operating Procedures and Performance Tests 11.3-11aEstimated Releases 11.3-14Release Points 11.3-15Dilution Factors 11.3-17Dose Estimates 11.3-17Appendix 11.3A Dose Models: Gaseous Effluents 11.3A-1

PROCESS AND EFFLUENT RADIOLOGICAL MONITORING SYSTEM 11.4-1

Design Objectives 11 4-1Continuous Monitoring/Sampling 11.4-2Sampling 11.4-3

xIll Amend. 68

May 1982

I11.4.111.4.211.4.3


11.5 SOLID WASTE SYSTEM 11.5-1

11.5.1 Design Objectives 11.5-111.5.2 System Inputs 11.5-111.5.3 Equipment Description 11.5-111.5.4 Expected Volumes 11.5-311.5.5 Packaging 11.5-411.5.6 Storage Facilities 11*5-411.5.7 Shipment 11,5-4

11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 11.6-1:

11.6.1 Expected Background 11.6-111.6.2 Critical Pathways to Man 11.6-2-11.6.3 Sampl ing MedIa, Locati.ons and Frequencies 11.6-411.6.4 Analytical Sensltlvixty 1.6-4

611.5 Data Analysis and Presentation 11.6-411o6.6 Program Statistical Sensitivity 1.1-6-5

12.0 RADIATION'-PROTECTION 12.1-1

12.1 S I'ELDI 12.1-

1.2. 1. 1 Des ign Objecti ves 12.1-112.1.2 Design Description 12.1-312.1.3 Source. Terms s121-1312.1.4 Area'. Radiiati on Mon I tori ng 1-2.1 -2312.1.5 Est•m'ates of Exposure 12.1-24

Appendix to Section 12.1 12.,1A-1

12.2 YVELh]TTJ..T 12.2-1

12.2.1 Design Objectives 12.2-112.2.2 Design Description 12.2-112.2.3 Source Terms 12.2-312.2.4 Airborne Radioactivity Monitoring 12.2-312.2.5 Inhalation Doses 12.2-5

12.3- HEALTH PHYSICS PROGRAM 12.3-1

12.3.1 Program. Objectives A12.3-112.3.2 Facilities and Equipment 12.3-312.3.3 Personnel Dosimetry 12.3-612.3.4 Estimated Occupancy Times 12.3-7

Appendix 12A - Information Related to ALARA for I2A-1Occupational Radiation Exposures

xiv

Amend. 68May 1982

TABLE OF CONTENTS C(Contfd.)

I ~ ~Sect I on "••". . _•gi

13.0 CONDUCT OF OPERATIONS 13.1-1

13.1 ORGANIZATIONAL STRUCTURE OF THE APPLICANT 13.1-1

13.1.1 Project Organization 13.1-113.1.2 Operating Organization .13.1-5.13.1.3 Qualification Requirements for Nuclear Plant13:-

13.2 TRAINING 'PROGRAM 13.2-

13.2.1 Program Description 13.2-113.2.2 RetraI.ni ng .Program 1.2-613.2.3 Replacement Tra:I-ning 13.2-6...13.2.4 Records 1-.-3.2-6

13.3. EMERGENCY PLANNING 13.3-' 1

13.3.1 General- 13.3-13.3.2 Emergency. Organization 13.3-213.3.3 CoordiUnation: with Offsite Groups 13..3,-5.13.3.4 Emeirgency Action..Leves 133-613,.3.-5 Ppro e t ective Me .asur es 13 .,3 -77•13.3.6 Review and Updating

13.3-713.3.7 Medical Support 13.3-713.3.8 Exercises and Drills 13.3-813.3.9 Training 13.3-813.3.10 Recovery and Reentry 13,3-913.3.11 Implementation 13.3-9Appendix 13.3A 13.3A-1

13.4 REVIEW AND AUDIT 13.4-1

13.4.1 Review and Audit - Construction 13.4-113.4.2 Review and Audit - Test and Operation 13.4-1

13.5 PLANT PROCEDURES 13.5-1

13.5.1 General t3.5-113.5.2 Normal Operating Instructions 13.5-113.5.3 Abnormal Operating Instructions 13.5-213.5.4 Emergency Operating InstructIons 13.5-213.5.5 Maintenance InstructIons 13.5-3

C Amend. 68May 1982

::•/ :• :s:; •: :::::!•-;,-;-:•!•".:;S

TABLE OF CONTENTS (Cont'd.)• ~ ~Sect ion , ..

13.5.6 Survel-Ilance Instructions 3. 5-413.5.7 Technical Instructions 13.5-413.5.8 Sections Instruction Letters 13. 5-413.5.9 Site Emergency Plans 13.5-413.5.10 Radiation Control Instructions- 13.5-4

13.6 P 13.6-1

13.6.1 Plant History 13.6-113.6.2 Operating Records 13.:6-113.6.3 Event Records 13.6,-i.

13.7 RADIOLOGICAL SEOURITY 13.7-1

13.7.1 Organization -and Personnel 13.7-113.7.2 Plant Desi-gn 13.7T313.7.3 Security Plan 13-.76

14.0 INITIAL TESTS AND OPERATION: 14.-1

14.1 DESCRI.PTION OF TEST PROGRAMS 14.1-1

14.1.1 Preoperatlonal Test Programs 14.1-214.1.2 Startup TestProgram 14.- 1-2.14.1.3 AdmInIstratIon of Test Program 14.1-314.1.4 Test Objectives of Firstý-of-a-Kind Principal

Design Features 14.41A-6

14.2 AUGMENTATION OF OPERATOR'S STAFF FOR INITIAL TESTSAND OPERATIO 14.2-1

15.0 ACCIDENT ANALYSES 15.1-1

1 5.1 I NTRODUCT ION 1 5.1-1

15.1.1 Design. Approach to Safety 15.1-115.1.2 Requirements and Criteria for Assessment of Fuel•

and Blanket Rod Transient Performance 15.1-5015.1.3 Control Rod Shutdown Rate and Plant Protection

System Trip Settings 15.1-9315.1.4 Effect of Design Changes on Analyses of Accident

Events 15.1-105

15.2 REACTIVITY INSERTION DESIGN EVENTS- INTRODUCTION 15.2-1

15.2.1 Anticipated Events 15.2-515.2.2 Unlikely Events 15.2-3415.2.3 Extremely Unlikely Events 15.2-51

. ~xv IAmend. 68

May 1982

<,-, 7A

TABLE OF -CONTENTS (ont'd.)

I

Sect I on

15.3

15.3.115.3.215.3.3

15.4

15.4.115.4.215.4.3

15.5

15.5.115.5 .215.5.3

15.6

15.6.1

15.7

15.7.115.7.215.7.3

15. A.

16.0

16.1

16.1.116.1.216.1.316.1.416.1.516.1.616.1.716.1.816.1.9

UNDERCOOLING DESIGN EVENTS INTRODUCTION"

Anticipated EventsUnlikely EventsExtremely Unlikely Events

LOCAL FA ILUREEVENTS - INTRODUCTION

Fuel AssemblyControl AssembliesRadial Blanket Assembly

FUEL :HANDLING AND ::STORAGE: EVENTS-m -JINTRODUCTION

AntIcIpat4ed Event s (None)Unlikely -EventsExtremely Unlikely Events

SODIUM SPILLS - INTRODUCTION

Extremely UnlIkely Events

OTHER EVENTS- INTRODUCTION

Antlici;pated EventsUnllkely Events

Extremely Unlikely Events.Appendix .15,A.- Radiological Source Term forAssessment of Site Suitability

TECHNICAL SPECIFICATIONS

Reactor Operating ConditionReactor CorePlant Protection System InstrumentationSafety LimitLimiting Safety System Setting (LSSS)Limiting Conditions for Operation (LCO)Surveillance RequirementsContainment IntegrityAbnormal Occurrence

15.3v-6.15.3-29.15.3-"38

15.4-1,

15.4-215.4-4215.4-51

15.5-1

.15.5-415.5-41-15,.5-23

15.6-1

1-5.7-14

1:5:.7-3

15 .7-9"

15.7-18

15.A-1i

16.1-1

16.1-1

16.1-116.1-216.1-316.1-516.1-516.1-616.1-616.1-616.1-6

xvI I

Amend. 68May 1982

A ,.-~....- - .. "-. . . .-.--.. ~.........-.

A. :A.A.A.~ A. 9 ~. 99 ~ . .A.~


Sect I on

16.2

16.2.116.2.2

16.3

16.3.116.3.216.3.316.3.416.3.516.3.616.3.716.3.816.3.916.3.1016.3.1116.3.1216.:3 .13

16.4

16.4.116.4.216.4.316.4'416.4.516.4.616.4'.716.4.8

16.4.9

16.5

16.5.116.5.216.5.316.5.416.5.5

16.6

16.6.116.6.216.6.316.6.4

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

Safety Limit, Reactor CoreLimiting Safety System Settings

LIMITING CONDITIONS FOR OPERATION

16.2-1

16.2-116.2-1

16.3-1

Reactor Operating ConditionsPrimary :Heat Transport System (PHTS)Intermediate Heat Transport Coolant SystemSteam Generation System (SGS)Aux I I Iary Liqu id Metal 'SystemInert Gas System Cover Gas. Purif ication SystemAuxIlIary Coo:i ng Sys tem ,Containment IntegrityAuxillary-E!ectrical SystemRefuel ingEffluent ReleaseReactivity and.Control Rod LimitsPKant Protection System

SURVEILLANCE REQUIREMENTS

Operational Safety ReviewReactor:Coolant System SurveillanceContainment TestsHVAC and Radioactive EffluentsEmergency Power System Periodic TestsInert Gas SystemReactivity AnomaliesPressure and Leakage Rate Test of RAPS ColdBox CellPressure and Leakage Rate Test of RAPS NobleGas Storage Vessel Cell

16.3-116.3-2

16.3-64

16.3-2116.3-1216 243116.-.3-416.3-23116.3-2314

16 .3-2416 ,.3-27

16,34311.16.34-34.

16.4-1 516.4-1316.4-116.4-15

16.4-15a

16.5-1DESIGN FEATURES

SiteConfinement/ContainmentReactorHeat Transport SystemFuel Storage

ADMINISTRATIVE CONTROLS

16.5-116.5-116.5-216.5-516.5-7

16.6-1

16.6-116.6-116.6-4

16.6-6I

OrganizationReview and AuditInstructionsActions to be Taken In the Event of ReportableOccurrence In Plant Operation

xviII

Amend. 68May. 1982

.*. .. ~*.

TABLE OF CONTENTS (Conttd.)

16.6..5

16.6.616.6.716.6.8

17.0

17.0.117.0.217.0.317.0.417.0.15

17.1

17.1.117.1.217.1.317.1.4

Action to be Taken In the Event a Safety: Limit.Is .Exceeded .Station Operatlng RecordsReportlng:RequirementsMinimum Staffing

QUALITY'ASSURANCE- INTRODUCTION

ScopeQuality PhilosophyParticipantsProject Phase ApproachApplIcabili:ty

QUALITY ASSURANCE DURING, DESIGN AND CONSTRUCTION

OrganizationQual ity.:Assurance: PrograMReferences Referred to In the TextAcronyms Used In Chapter 17 Text.and Appendices

(N

:1 6.6-6,.16i,6.--;6

16.6-716.'6-8

17.0-1

17.0-117.0-117.07217.0-3.

17.- 1"217.1-117.1-2•17.1-6a

Amend. 68May 1982

Cxix

-1 -,


C'Appendix 17A

Appendix 17B

Appendix 17C

Appendix 17D

Appendix 17E

Appendix 17F

Appendix 17G

Appendix 17H

Appendix 171

Appendix 17J

A Descrl.ptiton:of. the ONner QualiltyAssurance:Program

A Description of the Fuel SupplIer QualItyAssurance Program

A Description of the Balance of PlantSupply Quality.Assurance Program

A Description of the 'ARD Lead ReactorManufacturer Quality[ Assurance ProgramA Descr i ption ,o-f the Aith]ect-Eng:ineer

Qual.ity Assurance Progran.. -

A- Descripticon. of the Constructor Q'ua~l Ity.Assurance Program

RDT Standard F2-2, 1973, QUality AssuranceProgra mRequil rements

A Description of: the% ARD Reactor ManufacturerQuadl i:ty .Assurance Program

A Descrlptlon of the GE-ARSD-RM QualltyAssuranceb :Program

A Descrlption of the ESG-RM Qual ityAssurance Program

-Computer Codes

General Plant Transient Data

Safety Related Reliability Program

Deleted

Deleted

Deleted

Plan for Inservice and Preservice Inspections

Post TMI RequIrements

1 7A-1'!

171B-i

17C-1

C17D -1

17Fi

171+-i:

17 I-I

17J-I1

A"I

B-i

C.!.1-

G-11

H-i

C

Appendix

Appendix

Appendix

Appendix

Appendix

Appendix

Appendix

Appendix

A

B

C

D

E

F

G

H

Cxx

Amend. 68May 1982

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