ML20207R966

From kanterella
Revision as of 01:02, 12 January 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys
ML20207R966
Person / Time
Site: 05000601
Issue date: 11/30/1986
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19292G939 List:
References
NUDOCS 8703180365
Download: ML20207R966 (389)
v • d • e


Text

. _ - - - - - - ..

O RESAR-SP/90 0 CONTAINMENT SYSTEMS WESTINGHOUSE O ADVANCED PRESSURIZED WATER REACTOR i

O.

'@n r nu -

iis s--

O STANDARD PLANT DESIGN Dk O b0 01 K PDR

NESTINGHOUSE CLASS 3 O

O O

l O

O i

O O WAPWR-CS g NOVEMBER, 1986 5094e:1d

-,.-.,w-en-,--.nn

Table of Contents SAR Section

,Section Title Page Status 1.0 Introduction and General Description of Plant 1.1-1 1 1.1 Introduction 1.1-1 1 1.2 General Plant Description. 1.2-1 II 1.2.2 Principal Design Criteria 1.2-1 II 1.2.3 Plant Description 1.2-1 II 1.2.3.3 Containment Safeguards System 1.2-4 II 1.2.3.3.1 Safety Features 1.2-4 II 1.2.3.3.1.1 Emergency Core Cooling System 1,2-5 11 1.2.3.3.1.2 Containment Heat Removal System 1.2-5 II 1.2.3.3.1.3 Annulus Air Cleanup System 1.2-6 II

1.2.3.3.1.4 Hydrogen Recombiners 1.2-6 II 1.2.3.8 Auxiliary Systems 1.2-6 II 1.2.3.8.7 Plant Ventilation Systems 1.2-6 II

' 1. 6 Material Incorporated By Reference 1.6-1 II l 1.8 Conformance With the Standard Review

! Plan 1.8-1 II 2.0 Site Characteristics 2.0-1 NA 3.0 Design of Structures, Components, Equipment and Systems 3.0-1 NA 4.0 Reactor 4.0-1 NA 5.0 Roactor Coolant System and Connected Systems 5.0-1 NA 6.0 Engineered Safety Features 6.1-1 II 6.1 Engineered Safety Feature Materials 6.1-1 II 6.1.1 Metallic Materials 6.1-1 II 6.2 Containment Systems 6.2-1 I 6.2.1 Primary Containment Functional Design 6.2-1 I 6.2.1.1 Containment Structure 6.2-1 I 6.2.1.1.1 Design Bases 6.2-1 I 6.2.1.1.2 System Design 6.2-2 I WAPWR-CS ii NOVEMBER, 1986 5094e: 1d

Table of Contents (Cont.)

Reference SAR Section Section Title h Status 6.2.1.1.3 Design Evaluation 6.2-3 I 6.2.1.1.4 Initial Conditions 6.2-5 I

6.2.1.1.5 Heat Removal 6.2-5 I 6.2.1.1.6 Nomenclature 6.2-10 I 1

6.2.1.1.7 Accident Chronology 6.2-11 I 6.2.1.2 Containment Subcompartments 6.2-12 I 6.2.1.2.1 Design Bases 6.2-12 I 6.2.1.2.1.1 Summary of Subcompartment Pipe Break Analyses 6.2-12 I 6.2.1.2.1.2 Design Features 6.2-12 I 6.2.1.3 Mass and Energy Releaso Analyses for Postulated Loss-of-Coolant Accidents 6.2-12 I 6.2.1.3.1 Mass and Energy Release Data 6.2-14 I 6.2.1.3.2 Energy Sources 6.2-15 I 6.2.1.3.3 Blowdown Model Description 6.2-17 I 6.2.1.3.4 Refill Model Description 6.2-17 I 6.2.1.3.5 Reflood Model Description 6.2-17 I 6.2.1.3.6 Post-Reflood Model Description 6.2-18 I 6.2.1.3.7 Single Failure Analysis 6.2-19 I 6.2.1.3.8 Metal-Water Reaction 6.2-19 I 6.2.1.3.9 Additional Information Required for i Confirmatory Analysis 6.2-19 I 6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary Pipe Ruptures Inside Containment 6.2-19 I

,6.2.1.4.1 Significant Parameters Affecting Steare Line Break Mass and Energy Releases 6.2-20 I 6.2.1.4.1.1 Plant Power Level 6.2-21 I 6.2.1.4.1.2 Main Feedwater System Design 6.2-21 I 6.2.1.4.1.3 Emergency Feedwater System Design 6.2-22 I O

WAPWR-CS iii NOVEMBER, 1986 5094e:1d l

Table of Contents (Cont.)

Reference SAR Section Section Title P_ age Status 4 6.2.1.4.1.4 Postulated Break Type, Size, and Location 6.2-23 I 6.2.1.4.1.5 Availability of Offsite Power 6.2-25 I i

6.2.1.4.1.6 Safety System Failures 6.2-26 I 6.2.1.4.1.7 Steam Generator Reverse Heat Transfer and Reactor Coolant System Metal Heat Capacity 6.2-26 I 6.2.1.4.2 Description of Blowdown Model S.2-27 I 6.2.1.4.3 Containment Response Analysis 6.2-27 I 6.2.1.4.3.1 Initial Conditions 6.2-27 I .

6.2.1.4.3.2 Mass and Energy Release Data 6.2-27 I 6.2.1.4.3.3 Containment Pressure-Temperature Results 6.2-28 I 6.2.2 Containment Heat Removal System 6.2-172 II 6.2.2.1 Containment Fan Cooler System 6.2-172 I 6.2.2.1.1 Design Bases 6.2-173 I 6.2.2.1.1.1 Safety Design Bases 6.2-173 I 6.2.2.1.1.2 Power Generation Design Bases 6.2-173 I 6.2.2.1.2 System Description 6.2-174 I 6.2.2.1.2.1 General Description 6.2-174 I 6.2.2.1.2.2 Component Description 6.2-174 I 6.2.2.1.2.3 System Operation 6.2-175 I 6.2.2.1.3 Codes and Standards 6.2-175 I 6.2.2.1.4 Safety Evaluation 6.2-176 I 6.2.2.1.5 Inspection and Testing Requirements 6.2-177 I t

6.2.2.1.6 Instrumentation Application 6.2-178 I i 6.2.2.2 Containment Spray System 6.2-179 11 6.2.2.2.1 Design Bases 6.2-179 II 6.2.2.2.2 System Design 6.2-180 II 6.2.2.2.3 Design Evaluation 6.2-183 II 6.2.2.2.4 Test and Inspections 6.2-183 II 6.2.2.2.5 Instrumentation Requirements 6.2-185 II WAPWR-CS iv NOVEMBER, 1986 5094e:1d

Table of Contents (Cont.)

Reference SAR Section Section Title Page Status 6.2.3 Secondary Containment Functional Design 6.2-190 I 6.2.3.1 Design Bases 6.2-190 I 6.2.3.1.1 Secondary Containment 6.2-190 I p 6.2.3.1.2 Annulus Air Cleanup System 6.2-191 I ,

6.2.3.2 System Design 6.2-191 I 6.2.3.2.1 ' Secondary Containment 6.2-191 I 6.2.3.2.2 Features in Support of the Secondary Containment ' 6.2-192 I-6.2.3.2.3 Annulus Air Cleanup System 6.2-192 I 6.2.3.2.4 Reactor Building Annulus Bypass Leakage 6.2-193 I 6.2.3.3 Design Evaluation 6.2-193 I 6.2.3.4 Tests and Inspections 6.2-194 I q 6.2.3.5 Instrumentation Requirements 6.2-194 I V 6.2.4 Containment Isolation System 6.2-194 I 6.2.4.1 Design Bases 6.2-195 I 6.2.4.1.1 Safety Design Bases 6.2-195 I 6.2.4.1.2 Power Generation Design Basis 6.2-197 I 6.2.4.2 System Description 6.2-197 I l ~6.2.4.2.1 General Description 6.2-197 I 6.2.4.2.2 Component Description 6.2-200 I i 6.2.4.2.3 System Operation 6.2-200 I i

6.2.4.3 Design Evaluation 6.2-201 I 6.2.4.4 Tests and Inspections 6.2-206 I ,

~

6.2.4.5 Instrumentation Application 6.2-206 I 6.2.5 Cembustible Gas Control in Containment 6.2-215 I 6.2.5.1 Design Bases 6.2-215 I 6.2.5.1.1 Electric Hydrogen Recombiners 6.2-215 I 6.2.5.1.2 Containment Hydrogen Purge System 6.2-216 I 6.2.5.1.3 Hydrogen Igniters 6.2-216 I -

6.2.5.1.4 Containment Hydrogen Monitoring System 6.2-217 I O 6.2.5.1.5 Containment Hydrogen Mixing 6.2-218 I WAPWR-CS v NOVEMBER, 1986 5094e:1d

Table of Contents (Cont.)

Reference ,

SAR Section Section Title P_ age Status 6.2.5.2 System Design 6.2-218 I 6.2.5.2.1 Electric Hydrogen Recombiners 6.2-218 I 6.2.5.2.2 Containment Hydrogen Purge System 6.2-220 I i 6.2.5.2.3 Hydrogen Ignition System .(HIS) 6.2-220 I 6.2.5.2.4 Containment Hydrogen Monitoring System 6.2-221 I 6.2.5.2.5- Containment Hydrogen Mixing 6.2-222 I 6.2.5.3 Design Evaluation 6.2-223 I 6.2.5.3.1 Hydrogen Production and Accumulation 6.2-223 I 6.2.5.3.1.1 Zirconium-Water Reaction 6.2-223 I 6.2.5.3.1.2 Radiolysis of Core and Sump Solutions 6.2-223 I 6.2.5.3.1.3 Corrosion of Metals and Paint:; in Containment 6.2-226 I 6.2.5.3.1.4 Hydrogen in the Primary Coolant 6.2-227 I 6.2.5.3.1.5 Hydrogen Mixing 6.2-228 I 6.2.5.3.1.6 Conclusions 6.2-228 I l 6.2.5.4 Tests and Inspections 6.2-229 I 6.2.5.4.1 Electric Hydrogen Recombiners 6.2-229 I 6.2.5.4.2 Containment Hydrogen Purge System 6.2-229 I 6.2.5.4.3 Hydrogen Ignition System 6.2-230 I 6.2.5.4.4 Post-Accident Hydrogen Monitoring System 6.2-230 I 6.2.5.5 Instrumentation Requirements 6.2-230 I i

6.2.5.5.1 Electric Hydrogen Recombiner 6.2-230 I 6.2.5.5.2 Hydrogen Ignition System 6.2-230 I 6.2.5.5.3 Containment Hydrogen Monitoring System 6.2-230 I 6.2.5.6 Materials 6.2-231 I 6.2.5.7 References 6.2-231 I l 6.2.6 Containment Leakage Testing 6.2-241 II 6.2.6.1 Containment Integrated Leakage Rate Test (Type A Test) 6.2-241 II 6.2.6.1.1 ILRT Pretest Requirements 6.2-242 II 6.2.6.1.2 ILRT Test Method 6.2-244 II WAPWR-CS vi NOVEMBER, 1986 5094e:1d l . -- -

l l Table of Contents (Cont.)

Reference SAR Section Section Title Page Status s) 6.2.6.2 Containment Penetration Leakage Rate Tests (Type B Tests) 6.2-245 II 6.2.6.3 Containment Isolation Valve Leakage Rate Tests 6.2-246 II O- 6.2.6.4 Scheduling and Reporting of Periodic Tests 6.2-150 II 6.2.6.5 Special Testing Requirements 6.2-250 II 6.5 Fission Product Removal and Control Systems 6.5-1 II 6.5.1 Engineered Safety Features Filters 6.5-1 II 6.5.1.1 Design Bases 6.5-2 II 6.5.1.2 System Design 6.5-2 II 6.5.1.3 Design Evaluation 6.5-2 II 6.5.1.4 Tests and Inspections 6.5-2 II 6.5.1.5 Instrumentation Requirements 6.5-2 11

' 6.5.1.6 Materials 6.5-2 II 6.5.2 Containment Spray System (Fission Product Removal) 6.5-2 II 6.5.3 Fission Product Control Systems 6.5-3 II 6.5.3.1 Primary Containment 6.5-3 II l

6.5.3.2 Secondary Containment 6.5-4 II 7.0 Instrumentation and Controls 7.0-1 NA 8.0 Electric Power 8.0-1 NA 9.0 Auxiliary Systems 9.0-1 NA l 10.0 Steam and Power Conversion System 10.0-1 NA 11.0 Radioactive Waste Management 11.0-1 NA 12.0 . Radiation Protection 12.0-1 NA 13.0 Conduct of Operations 13.0-1 NA 14.0 Initial Test Program 14.0-1 NA 15.0 Accident Analyses 15.0-1 II 15.0.1 General 15.0-1 II WAPWR-CS vii NOVEMBER, 1986

. 5094e:1d

Table of Contents (Cont.)

Reference SAR Section Section Title M Status 15.0.2 Classification of Plant Conditions 15.0-1 II 15.0.2.1 Condition I - Normal Operation and Operational Transients 15.0-2 II 15.0.2.2 Condition II - Faults of Noderate Frequency 15.0-4 II 15.0.2.3 Condition III - Infrequent Faults 15.0-6 II 15.0.2.4 Condition IV - Limiting Faults 15.0-7 II 15.0.3 Optimization of Control Systems 15.0-8 II

! 15.0.4 - Plant Characteristics and Initial Conditions Assumed in the Accident Analyses 15.0-8 II

15.0.4.1 Design Plant Conditions 15.0-8 II 15.0.4.2 Initial Conditions 15.0-8 II q(/ ,

15.0.4.3 Power Distribution 15.0-9 II 15.0.5 Reactivity Coefficients Assumed in the Accident Analyses 15.0-10 II t 15.0.6 Rod Cluster Control Assembly Insertion Characteristics 15.0-11 II 15.0.7 Trip Points and Time Delays to Trip Assumed in Accident Analyses 15.0-12 II 15.0.8 Instrumentation Drift and Calorimetric Errors - Power Range Neutron Flux 15.0-14 II 15.0.9 Plant Systems and Components Available for Mitigation of Accident Effects 15.0-14 II 15.0.10 Fission Product Inventories 15.0-15 II 15.0.10.1 Inventory in the Core 15.0-15 II 15.0.10.2 Inventory in the Fuel Pellet Clad Gap 15.0-15 II 15.0.10.3 Inventory in the Reactor Coolant 15.0-16 II q

l 15.0.11 Residual Decay Heat 15.0-16 11 15.0.11.1 Total Residual Heat 15.0-16 II 15.0.12 Computer Codes Utilized 15.0-16 II WAPWR-CS viii NOVEMBER, 1986 5094e:1d i

Table of Contents (Cont.)

Reference SAR Section Section Title Pm Status 15.0.12.1 FACTRAN 15.0-17 II 15.0.12.2 LOFTRAN 15.0-17 II 15.0.12.3 TWINKLE 15.0-18 II 15.0.12.4 THINC 15.0-19 II 15.0.13 References 15.0-19 II 16.0 Technical Specifications 16.0-1 NA 17.0 Quality Assurance 17.0-1 II O

1 O .

h

. y

?

O WAPWR-CS ix NOVEMBER, 1986 5094e:1d

_ . . ._J

i t

i-TABLE OF CONTENTS (Cont.)

O LIST OF TABLES Number Title h 1.6-1 Material Incorporated by Reference 1.6-2 1.8-1 Standard Review Plan Deviations 1.8-2

. 6.2-1 Containment Peak Pressure and Temperature 6.2-32 6.2-2 Assumptions for Containment Analysis - Part 1 6.2-33 6.2-3 Assumptions for Containment Analysis - Part 2 6.2-34 6.2-4 Design Basis Accident Chronology of Events 6.2-35 6.2-5 Containment Heat Sinks 6.2-36 6.2-6 Thermophysical Properties of Containment Heat Sinks 6.2-38 6.2-7 APWR/ Double Ended Pump Suction Guillotine Min SI Blowdown Mass and Energy Releases 6.2-39 6.2-8 APWR/0.6 Double Ended Pump Suction Guillotine Min

~SI Blowdown Mass and Energy Releases 6.2-40 [

2 6.2-9 APWR/3 ft Pump Suction Split Break MIN SI Blowdown Mass and Energy Releases 6.2-41 6.2-10 APWR/ Double Ended Pump Cold Leg Min SI Blowdown Mass and Energy Releases 6.2-42 6.2-11 APWR/ Double Ended hot Leg Min SI Blowdown Mass and l Energy Releases 6.2-43 6.2-12 APWR/ Double Ended Pump Suetidn Guillotine Max SI l

Reflood Mass and Energy Releases 6.2-44 I

6.2-13 APWR/ Double Ended Pump Suction Guillotine Min SI Reflood Mass and Energy Releases 6.2-45 6.2-14 APWR/0.6 Double Ended Pump Suction Guillotine Min SI Reflood Mass and Energy Releases 6.2-46 6.2-15 APWR/ Double Ended Cold Leg Min SI Reflood Mass and Energy Releases 6.2-47 7

6.2-16 APWR/ Double Ended Pump Suction Guillotine Max SI i Post-Reflood Mass and Energy Releases 6.2-48 I 6.2-17 APWR/ Double Ended Pump Suction Guillotine Min SI Post-Reflood Mass and Energy Releases 6.2-49 WAPWR-CS x NOVEMBER, 1986 5094e:1d

TABLE OF CONTENTS (Cont.)

LIST OF TABLES Number Title M ll O 6.2-18 APWR/0.6 Double Ended Pump Suction Guillotine Min SI Post-Reflood Mass and Energy Releases 6.2-50 6.2-19 APWR/ Double Ended Pump Suction Guillotine Min SI 6.2-51 6.2-20 APWR/ Double Ended Pump Suction Guillotine Max SI 6.2-51 6.2-21 APWR/0.6 Double Ended Pump Suction Guillotine Min SI 6.2-53 6.2-22 APWR/ Double Ended Cold Leg Min SI 6.2-54 6.2-23 APWR/ Double Ended Hot Leg Min SI 6.2-55 6.2-24 APWR/ Double Ended Pump Suction Guillotine Max SI 6.2-56 i 6.2-25 APWR/ Double Ended Pump Suction Guillotine Min SI 6.2-57 6.2-26 System Parameters 6.2-58 l

i 6.2-27 Spectrum of Secondary System ripe Ruptures 6.2-59 6.2-28 Summary of Results for MSLB Containment Analysis 6.2-60 2

6.2-29 Case 1: 1.4 Ft Double-Ended Rupture at 102 PC Power 6.2-61 1 6.2-30 Case 2: 1.4 Ft Double-Ended Rupture at 75 PC Power 6.2-69 2

6.2-31 Case 3: 1.4 Ft Double-Ended Rupture at 50 PC Power 6.2-78 2

6.2-32 Case 4: 1.4 Ft Double-Ended Rupture at 25 PC Power 6.2-87 6.2-33 Case 5: 1.4 Ft 2Double-Ended Rupture at Hot Zero Power 6.2-98 2

{ 6.2-34 Case 6: 1.1 Ft Split Rupture at 102 PC Power 6.2-109 i 6.2-35 Case ?- 1.1 Ft' Split Rupture at 75 PC Power 6.2-116 2

6.2-36 Case 8: 1.1 Ft Split Rupture at 50 PC Power 6.2-124 I 2

6.2-37 Case 9: 1.1 Ft Split Rupture at 25 PC Power 6.2-132 6.2-38 Case 10: 1.0 Ft Split Rupture at Hot Zero Power 6.2-141 2

6.2-39 Case 11: 1.4 Ft Double-Ended Rupture at Hot Zero Power MSIV Failure 6.2-149 2

6.2-40 Case 12: 1.0 Ft Split Rupture at Hot Zero Power MSIV Failure 6.2-161 6.2-41 Sequence of Events for Case 5 Double-Ended Rupture From HZP 6.2-170 l

O

! WAPWR-CS xi NOVEMBER, 1986 L 5094e:1d

TABLE OF CONTENTS (Cont.)

LIST OF TABLES Number Title Pm O 6.2-42 Sequence of Events for Case 6 1.1 Ft 2 Split Rupture From 102 Percent Power 6.2-171 6.2-43 Containment Fan Cooler System Single Active Failure Analysis 6.2-186 6.2-44 Containment Spray System Component Parameters 6.2-188 6.2-45 Failure Mode and Effects Analysis - Integrated Safeguard System (ISS) Containment Spray Function 6.2-189 6.2-46 -

Containment Penetration Valve Arrangement 6.2-208 6.2-47 Plant Parameters Used to Calculate Post-Accident Hydrogen Production 6.2-234 6.2-48 Core Fission Product Energy After 650 Full-Power Days 6.2-238 6.2-49 Fission Product Decay Deposition in Sump Solution 6.2-239 6.2-50 Post-Accident Containment Temperature Transient for Hydrogen Generation Analysis 6.2-240 15.0-1 Nuclear Steam Supply System Power Ratings 15.0-21

! 15.0-2 Values of Pertinent Plant Parameters Utilized in

Accident Analyses 15.0-22 15.0-2a Values of Pertinent Plant Parameters Utilized in l Accident Analyses 15.0-23

! 15.0-3 Summary of Initial Conditions and Computer Codes Used 15.0-24 15.0-4 Trip Points and Time Delays to Trip Assumed in Accident Analyses 15.0-27 15.0-5 Determination of Maximum Overpower Trip Point - Power Range Neutron Flux Channel - Based on Nominal Setpoint l Considering Inherent Instrument Errors 15.0-28 l 15.0-6 Plant Systems and Equipment Available for Transient and Accident Conditions 15.0-30 15.0-7 Fuel and Rod Gap Inventories, Core (Ci)(a) 15.0-34 15.0-8 Reactor Coolant Iodine Concentrations for 1 uCi/ Gram and 60 uCi/ Gram of Dose Equivalent I-131 15.0-35 WAPWR-CS xii NOVEMBER, 1986 5094e:1d

..-- .-_ . - . - . - . - - ...- . -.-..- _ - ...-_.-. - . . _ , - _ _ = . .

i

, TABLE OF CONTENTS (Cont.)

l

LIST OF TABLES '

Number Title P_aage 1 15.0-9 Reactor Coolant Noble Gas Specific Activity Based on One Percent Defective Fuel 15.0-36

! 15.0-10 Iodine Appearance Rates in the Reactor Coolant ,

f (Curies /sec) 15.0-37 i

l l

4 i l l

O i

l l l

l t

l O l O i i

i WAPWR-CS xiii NOVEMBER, 1986 I 5094e:1d I t

TABLE OF CONTENTS (Cont.)

LIST OF FIGURE 3

' Number Title O

V 6.2-1 Double Ended Pump Suction Break Max SI 6.2-2 Double Ended Pump Suction Break Min SI i

6.2 3 0.6 Double Ended Pump Suction Break Min SI 6.2-4 3 Ft 2Pump Suction Split Break Min SI 6.2-5 Double Ended Cold Leg Break Min SI 6.2-6 Double Ended Hot Leg Break Min SI 6.2-7 Double Ended Pump Suction Break Max SI 6.2-8 Double Ended Pump Suction Break Min SI 6.2-9 0.6 Double Ended Pump Suction Break Min SI 6.2-10 3 Ft 2Pump Suction Split Break Min Si 6.2-11 Double Ended Cold Leg Break Min SI 6.2-12 Double Ended Hot Leg Break Min SI 6.2-13 Heat Transfer Coeficient vs. Time Double Ended Pump Suction, Max SI 6.2-14 APWR Containment Integrity Case 1: Double-Ended Break at 102 PC Power 6.2-15 APWR Containment Integrity Case 1: Double-Ended Break at 102 PC Power 6.2-16 APWR Containment Integrity Case 2: Double-Ended Break i at 75 PC Power 6.2-17 APWR Containment Integrity Case 2: Double-Ended Break at 75 PC Power 6.2-18 APWR Containment Integrity Case 3: Double-Ended Break i

at 50 PC Power

6.2-19 APWR Containment Integrity Case 3
Double-Ended Break

, at 50 PC Power l 6.2-20 APWR Containment Integrity Case 4: Double-Ended Break at 25 PC Power 6.2-21 APWR Containment Integrity Case 4: Double-Ended Break at 25 PC Power WAPWR-CS xiv NOVEMBER, 1986 l 5094e:1d i

i

. = . . _ - _ _ _ .-_ .._ .. -_-_ , . ,...- _... - ..-._- - _ - -_- -____-._-____.

TABLE OF CONTENTS (Cont.)

LIST OF FIGURES Number Title 6.2-22 APWR Containment Integrity Case 5: Double-Ended Break at Hot Zero Power 6.2-23 APWR Containment Integrity Case 5: Double-Ended Break O\ at Hot Zero Power 6.2-24 APWR Containment Integrity Case 6: 1.1 Ft2Split Break at 102 PC Power 6.2-25 APWR Containment Integrity Case 6.: 1.1 Ft2Split Break at 102 PC Power 6.2-26 APWR Containment Integrity Case 7: 1.1 Ft2Split Break at 75 PC Power 6.2-27 APWR Containment Integrity Case 7: 1.1 Ft2Split Break at 75 PC Power 6.2-28 APWR Containment Integrity Case 8: 1.1 Ft2Split Break at 50 PC Power 6.2-29 APWR Containment Integrity Case 8: 1.1 Ft2Split Sreak at 50 PC Power 6.2-30 APWR Containment Integrity Case 9: 1.1 Ft2Split Break at 25 PC Power 6.2-31 APWR Containment Integrity Case 9: 1.1 Ft2Split Break at 25 PC Power 6.2-32 APWR Containment Integrity Case 10: 1.0 Ft2Split Break at Hot Zero Power 6.2-33 APWR Containment Integrity Case 10: 1.0 Ft2Split Break at Hot Zero Power 6.2-34 APWR Containment Integrity Case 11: Double-Ended Break MSIV Failure HZP 6.2-35 APWR Containment Integrity Case 11: Double-Ended Break MSIV Failure HZP 6.2-36 APWR Containment Integrity Case 12: 1.0 Ft2Split Break MSIV Failure HZP WAPWR-CS xv NOVEMBER, 1986 5094e:1d

i l

TABLE OF CONTENTS (Cont.) ,

LIST OF FIGURES Number Title O 6.2-37 APWR Containment Integrity Case 12: 1.0 Ft2 Split Break i.

MSIV Failure HZP i

l 6.2-38 ContainmentSprayNozzle(1713ANozzle) '

6.2-39 Containment Spray Nozzle Capacity Curve

! 6.2-40 Mean Droplet Size Distribution

) 6.2-41 Nozzle Spray Pattern (Vertical)

! 6.2-42 Nozzle Spray Pattern (Horizontal)

)

6.2-43 Nozzle Spray Pattern (Downward) 15.0-1 Illustration of Core Thermal Limits and DNB Protection '

(N Loop Operation) l 15.0-2 Doppler Power Coefficient Uwd in Accident Analysis 15.0-3 RCCA Position Vs. Time to Dashpot 15.0-4 Normalized RCCA Reactivity Worth Vs. Fraction Insertion 15.0-5 Normalized RCCA Bank Reactivity Worth Vs. Normalized Drop Time

! I i

!O

o lO l

!O i

i WAPWR-CS xvi NOVEMBER, 1986 f 5094e:1d l

i

.,e_ . . ~ . . - . - _ _ . . .

, .._..__.._ _..__. _-- - ~__ __- ,_ _ _ _ _ _ _. __ , . - . ~ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20207R966&oldid=3083200"