ML20099H959

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RESAR-SP/90 Westinghouse Advanced PWR Module 9, Instrumentation & Controls & Electric Power
ML20099H959
Person / Time
Site: 05000601
Issue date: 11/30/1984
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19269B210 List:
References
NUDOCS 8503190548
Download: ML20099H959 (532)
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Text

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. O INSTRUMENTATION & CONTROLS AND ELECTRIC POWER  :

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O TABLE OF CONTENTS Reference SAR Section Section Title PilLt Status

1.0 INTRODUCTION

AND GENERAL DESCRIPTION OF 1.1 -1 II PLANT

1.1 INTRODUCTION

1.1-1 11 1.2 GENERAL PLANT DESCRIPTION 1. 2-1 II 1.2.2 Princ'ipal Design Criteria 1. 2-1 II 1.2.3 Plant Description 1. 2-1 II 1.2.3.6 Plant Instrumentation and Control Systems 1. 2-1 II 1.2.3.6.1 Integrated Control System 1. 2-1 II 1.2.3.6.2 Integrated Protection System 1.2-3 11 1.6 MATERIAL INCORPORATED BY REFERENCE 1.6-1 II 1.7 1.7-1 O 1.8 DRAWINGS AND OTHER DETAILED INFORMATION CONFORMANCE WITH THE STANDARD REVIEW PLAN 1. 8-1 II 11 2.0 SITE CHARACTERISTICS 2. 0-1 NA 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT 3.0-1 NA i AND SYSTEMS 4.0 REACTOR 4. 0-1 NA S.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.0-1 NA 6.0 ENGINEERED SAFETY FEATURES 6. 0-1 NA O 7.0 7.1 INSTRUMENTATION AND CONTROLS INTRODUCTION 7 .1 -1 7.1-1 I

1 7.1.1 Identification of Safety Systems 7.1 -3 I 7.1.1.1 Protective Functions 7.1-4 I O WAPWR/I&C/EP il NOVEMBER, 1984 j 1 2252e:1d

i

, TABLE OF CONTENTS (Continued)

Reference SAR Section d

i Section Title Pace Status 7.1.1.1.1 Reactor Trip Function

  • 7.1-5 I 7.1.1.1.2 Engineered Safety Feature Actuation Functior:s 7.1 I 7.1.1.2 Integrated Protection System Components 1 7.1-B- I 7.1.1.2.1 . . Sensors of the Integrated Protection System ~7 .1 -10 I 7.1.1.2.1.1 ' Process Sensors 7.1-10 I 7 .1.1. 2 .1. 2 Nuclear Instrumentation Detectors 7.1-11 I 7 .1.1. 2 .1. 3 Nitrogen-16 (N-16) Power Measuring Detectors 7.1-12 I 7.1.1.2.1.4 Equipment' Status Inputs 7.1-13 I s I 7.1.1.2.2 Engineered Safeguards Features Actuation 7.1-14 I Cabinets ,,

7.1.1.2.3 Logic Cabinets.* 7.1-14 I 7.1.Y.2.4 Main Control Beard Multiplexers 7.1-15 I

. 7.1.1.3 IPS Architecture ~

7.1-15 I 7.1.1.3.1 Integ' rated Protection Cabinets (IPC) 7.1-15 I i , 7.1.1.3.1.1 ESF Subsystem 7.1-16 I 7 .1.1. 3.1. 2 Global Trip Subsystem 7.1-17 I

'7.1.1.3.1.3 Trip Enable Subsystem 7.1-18 I 7.1.1.3.1.4 Departure from Nucleate Boiling Ratio 7.1-19 I Subsystem (DNB) (This and FG1 are one subsystem) 7.1.1. '3$ 1. 5 Function Group 1 and 2 Subsystems 7.1-20 I (FG1/FG2) 7.1.1.3.1.6 Nuclea/ Instrumentation System Subsystem.(NIS) 7.1-20 1 (inis and FG2 are one subsystem)

! 7.1.1.3.1.7 Auto Tests and Data Acquisition Subsystem 7.1-21 I (AT/DA) Architecture 7.1.1.3.2 Engineered Safeguards Features Actuation 7.1-23 I Cabinets 7.1.1.3.3 Logic Cabinets 7.1-24 I WAPWR/l&C/EP iii NOVEMBER, 1984 2252e:1d

V  ;

TABLE OF CONTENTS (Continued) e 1

Reference O

v SAR Section Section Title figi Status 7.1.1.3.4 Main Control Board Multiplexers 7.1-24 I O 7.1.1.3.5 Inter Cabinet Comunications (Refer to Figure 7.1-10) 7.1-25 I 7.1.1.3.6 General Hardware Selection Guidelines 7.1-27 I 7.1.1.3.7 Off Normal Operation (Failure Tolerance, 7.1-28 I Maintenance, Test and Bypass)  !

7.1.1.3.8

. Isolation Devices 7.1-31 I ,

7.1.1.3.9 Microprocessors 7.1-31 1 7.1.1.3.10 Built-In Test Capabilities 7.1-34 I l 7.1.1.4 Protective Action System 7.1-37 I 7.1.1.4.1 Reactor Trip Actuation Trains 7.1-38 I 7.1.1.4.2 Safeguards Trains 7.1-40 I Safety-Related Display Instrumentation 7.1.1.5 7.1-41 I 7.1.1.6 Essential Auxiliary Supporting Functions 7.1-42 I 7.1.1.7 I and C System Designers 7.1-43 I 7.1.1.8 Plant Comparison 7.1-43 I 7.1.2 Identification of Safety Criteria 7.1-43 I 7.1.2.1 Design Basis for Safety Systems 7.1-43 I 7.1.2.1.1 Design Basis, Generating Stations 7.1-44 I Requiring Protective Actions (Paragraph 1 7.1-44 I O 7.1.2.1.2 of Section 3 of IEEE 279-1971)

Design Basis; Variables Required to be 7.1-45 I Monitored for Protection Action and Their Minimum Performance Requirements (Paragraphs 2 and 9 of Section 3 of IEEE 279-1971) 7.1.2.1.3 Design Basis; Spatially Dependent Variables 7.1-45 I (Paragraph 3 of Section 3 of IEEE 279-1971)

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m O

TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7.1.2.1.4 Design Basis; Protection During Various 7.1-45 I Reactor Operating Modes (Paragraph 4 of Section 3 of IEEE 279-1971) 7 .1. 2.1. 5 Design Basis; Determination of Protective 7.1-48 I Action Setpoints (Paragraphs 5 and 6 of Section 3 of IEEE 279-1971) 7 .1. 2 .1. 6 Design Basis; Protection Against Natural 7.1-48 I Phenomena and Universal Events (Paragraphs 7 and 8 of Section 3 of IEEE 279-1971) 7 .1. 2 .1. 7 Design Basis; Protection Against Equipment 7.1-49 I Malfunctions 7.1.2.1.8 Miscellaneous Design Bases 7.1-50 1 7.1.2.2 Conformance of the Safety System Instrumen- 7.1 -51 I tation to Applicable Criteria 7.1.2.2.1 Conformance to General Functional Require- 7.1-52 I ments (Paragraph 4.1 of IEEE 279-1971, GDC-13, GDC-15, Regulatory Guide 1.105) 7.1.2.2.2 Conformance~to the Single Failure Criterion 7.1-54 (Paragraph 4.2 of IEEE 279-1971, IEEE 379-1972, Regulatory Guide 1.53) 7.1.2.2.3 Conformance to the Requirements for Quality 7.1-55 I Components and Modules (Paragraph 4.3 of IEEE 279-1971 GDC-1) 7.1.2.2.4 Conformance to the Requirements for Equipment 7.1-55 I Qualifications (Paragraph 4.4 of IEEE T97-1971, GDC-2, GDC-4, GDC-13, IEEE 323-1974, IEEE 344-1975 Regulatory Guide 1.89, Regulatory Guide 1.100, EICS-10)

O WAPWR/I&C/EP v NOVEMBER, 1984 2252e:1d

O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title EAge Status 7.1.2.2.5 Conformance to the Requirements to Maintain 7.1-56 I Channel Integrity (Paragraph 4.5 of IEEE-1971. GDC-2, GDC-3, GDC-4, Regulatory Guide 1.120) 7.1.2.2.6 Conformance to the Requirements to Maintain 7.1-58 I Channel Independence (Paragraph 4.6 of IEEE 279-1971, GDC>22. IEEE 384-1974, Regulatory Guide 1.75) 7.1.2.2.7 Conformance to the Requirements Concerning 7.1-59 I Control and Protection System Interaction (Paragraph 4.7 of IEEE 279-1971, GDC-24)

O 7.1.2.2.8 Conformance to Requirements Concerning the 7.1-61 I Derivation of System Inputs (Paragraph 4.8 of IEEE 279-1971) 7.1.2.2.9 Conformance to the Requirements to Provide 7.1 -61 I Capability for Sensor Checks (Paragraphs 4.9 of IEEE 279-1971, IEEE 338-1975, Regulatory Guide 1.118) l i

7.1.2.2.10 Conformance to the Requirements to Provide 7.1-62 I Capability for Test and Calibration (Paragraph 4.10 of IEEE 279-1971, GDC-10, GDC-21. IEEE 338-1975, Regulatory Guide 1.22, Regulatory Guide 1.118, EICSE-5, t EICSB-22) l l 7.1.2.2.11 Conformance to Requirements on Channel 7.1-63 I Bypass or Removal from Operation (Paragraph l 4.11 of IEEE 279-1971) 7.1.2.2.12 Conformance to Requirements on Operating 7.1-65 I Bypasses (Paragraph 4.12 of IEEE 279-1971) l O

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O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7.1.2.2.13 Conformance to Requirements to Provide 7.1-66 I Indication of Bypasses (Paragraph 4.13 of IEEE 279-1971, Regulatory Guide 1.47 EISCB-21) 7.1.2.2.14 Conformance to Requirements Controlling 7.1-66 I Access to the Means for Bypassing (Paragraph 4.14 of IEEE 279-1971) 7.1.2.2.15 Conformance to the Requirements on the Use 7.1-66 I of Multiple Setpoints (Paragraph 4.15 of IEEE 279-1971. EICSB-12) 7.1.2.2.16 Conformance to the Requirements for Comple- 7.1-67 I tion of Protective Action Once it is Initiated (Paragras? 4.16 of IEEE 279-1971, Regulatory Guide 1.62 7.1.2.2.17 Conformance to the Requirements for Manual 7.1-67 I Initiation of Protective Functions (Para-graph 4.17 of IEEE 279-1971, Regulatory Guide 1.62) -

7.1.2.2.18 Conformance to Requirements Governing 7.1-68 I Access to Setpoint Adjustments Calibration, and Test Points (Paragraph 4.18 of IEEE 279-1971) 7.1.2.2.19 Conformance to the Requirements on Identi- 7.1-68 I fication of Protective Actions (Paragraph 4.19 of IEEE 279-1971) 7.1.2.2.20 Conformance to the Requirements for Informa- 7.1-68 I tion Read-Out (Paragraph 4.20 of IEEE 279-1971 (Regulatory Guide 1.97)

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O TABLE OF CONTENTS (Continued)

- j Reference l O Section Title Pace SAR Section Status l

7.1.2.2.21 Conformance to the Requirement to Facilitate 7.1-69 I System Repair (Paragraph 4.21 of IEEE 279-1971) 7.1.2.2.22 Conformance to the Requirements for Identifi- 7.1-69 I cation of Redundant Safety System Equipment (Paragraph 4.22 of IEEE 279-1971) 7.1. 3 References 7.1-70 I 7.2 REACTOR TRIP 7. 2-1 I 7.2.1 Description 7. 2-1 I 7.2.1.1 Functional Description 7.2-3 I 7.2.1.1.1 Nuclear Startup Trips 7.2-4 I 7.2.1.1.2 Nuclear Overpower Trips 7.2-5 I 7 . 2.1.1. 3 Core Heat Removal Trips 7.2-7 I 7.2.1.1.4 Primary Overpressure Trips 7.2-14 I 7.2.1.1.5 Loss of Heatsink Trips 7.2-15 I 7 . 2.1.1. 6 Excessive Cooldown Trips 7.2-16 I 7.2.1.1.7 Reactor Trip / Turbine Trip 7.2-16 I 7.2.1.1.7.1 Reactor Trip on a Turbine Trip (Anticipatory) 7.2-16 I

( 7.2.1.1.7.2 Turbine Trip on a Reactor Trip 7.2-17 I 7.2.1.1.8 Reactor Trip on Safety Injection 7.2-18 I 7.2.1.1.9 Manual Reactor Trip 7.2-18 I 7.2.1.1.10 Reactor Trip System Interlocks 7.2-19 I 7.2.1.1.11 Bypasses of Reactor Trip Functions 7.2-20 I 7.2.1.2 Design Basis for Reactor Trips 7.2-20 I 7 . 2 .1. 2 .1 Design Basis; Generating Station Conditions 7.2-21 I Requiring Reactor Trip (Paragraph 1 of Section 3 of IEEE 279-1971)

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O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7.2.1.2.2 Design Basis,; Variables, Levels, Ranges and 7.2-21 I Accuracies Used in Reactor Trip Functions (Paragraphs 2, 5, 6, and 9 of Section 3 of IEEE 279-1971) 7.2.1.2.3 Design Basis; Spatially Dependent Parameters 7.2,22 I Used in Reactor Trip (Paragraph 3 of Section 3 of IEEE 279-1971) 7.2.1.2.4 Design Basis; Operational Limits for variables 7.2-22 I in Various Reactor Operating Modes (Paragraph 4 of Section 3 of IEEE 279-1971) 7.2.1.2.5 Design Basis; Reactor Trips for Malfunctions, 7.2-23 I Accidents, Natural Phenomena, or Credible Events: (Paragraph B of Section 3 of IEEE 279-1971) 7 . 2 .1. 3 Final System Drawings 7.2-24 I 7.2.2 Analyses 7.2-24 I 7.2.2.1 Failure Mode and Effects Analysis (FMEA) 7.2-24 I 7.2.2.2 Conformance of the Reactor Trip Function 7.2-24 I to Applicable Criteria 7.2.2.2.1 Conformance to the General Functional 7.2-25 I Requirement for Reactor Trip (Paragraph 4.1 of IEEE 279-1971, GDC-13, GDC-20) 7.2.2.2.2 Conformance to the Single Failure Criterion 7.2-26 I for Reactor Trip (Paragraph 4.2 of IEEE 279-1971, IEEE 379-1972) 7.2.2.2.3 Conformance to the Requirements Covering 7.2-27 I Control and Reactor Trip Interactions (Paragraph 4.7 of IEEE 279-1971, GDC-24)

WAPWR/I&C/EP ix NOVEMBER, 1984 O

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O i TABLE OF CONTENTS (Continued)

Reference O. SAR Section Section M Pace Status 7.2.2.2.4- Conformance to Requirements on the Deriva- 7.2-27 I vation of System Inputs for Reactor Trip (Paragraph 4.8 of IEEE 279-1971) 7.2.2.2.5 Conformance to Requirements on Bypassing 7.2-28 I of Reactor Trip Functions (Paragraph 4.11, 4.12, 4.13, and 4.14 of IEEE 279-1971) 7.2.2.2.6 Conformance to Requirements on Multiple 7.2-28 I Setpoints Used for Reactor Trips:

(Paragraph 4.15 of IEEE 279-1971) 7.2.2.2.7 Conformance to the Requirement for Comple- 7.2-29 I tion of Reactor Trip Once it is Initiated:

(Paragraph 4.16 of IEEE 279-1971, Regulatory Guide 1.62) 7.2.2.2.8 Conformance to the Requirement to Provide 7.2-29 I for Manual Initiation of Reactor Trip:

(Paragraph 4.17 of IEEE 279-1971, Regulatory l Guide 1.62) 7.3 ENGINEERED SAFETY FEATURES (EST) 7.3-1 I 7.3.1 Description 7 . 3-1 I 7.3.1.1 Functional Description 7.3-3 I 7.3.1.1.1 Engineered Safety Features Actuated on a 7.3-4 I Safety Injection (SI) Signal (see Figure 7.2-1, Sheet 12) 7 . 3 .1.1. 2 Engineered Safety Features Actuated on a 7.3-6 I Steamline Isolation Signal (see Figure 7.2-1, Sheet 10) 7.3.1.1.3 Engineered Safety Features Actuated on a 7.3-6 I Containment Spray Signal (see Figure 7.2-1, Sheet 13)

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O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Page Status 7 . 3 .1.1. 4 Engineered Safety Features Actuated on a 7.3-7 I Containment Isolation Signal (see Figure 7.2-1, Sheet 13) 7 . 3 .1.1. 5 Engineered Safety Features Actuated on a 7.3-8 I Feedwater Isolation Signal (see Figure 7.2-1, Sheets 2, B,10) 7 . 3.1.1. 6 Engineered Safety Features Actuated on a 7.3-8 I Signal to Actuate the Emergency Feedwater System (see Figure 7.2-1, Sheets 7. B) 7 . 3.1.1. 7 Engineered Safety Features Actuated on a 7.3-9 I Signal to Block Boron Dilution (see Figure 7.2-1, Sheet 3) 7 . 3.1.1. 8 Blocks, Permissives, and Interlocks for ESF 7.3-10 I Actuation 7 . 3.1.1. 9 Bypasses of Engineered Safety Features 7.3-11 I Actuations '

7.3.1.1.10 Sequencing of ESF Loads 7.3-11 I 7 . 3.1. 2 Design Bases for Engineered Safety Features 7.3-11 I Actuation 7 . 3 .1. 2 .1 Design Basis; Generating Station Condition 7.3-11 I Requiring ESF Actuation (Paragraph 1 of Section 3 of IEEE 279-1971) 7 . 3 .1. 2 . 2 Design Basis; Variables, Ranges, Accuracies 7.3-12 I and Typical Response Times Used in ESF Actuation (Paragraphs 2, 5, 6 and 9 of Section 3 of IEEE 279-1971) 7 . 3.1. 2 . 3 Design Basis; Spatially Dependent Variables 7.3-13 I Used for ESF Actuation (Paragraph 3 of Section 3 of IEEE 279-1971)

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TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pagi Status 7.3.1.2.4 Design Basis; Limits for ESF Parameters in 7.3-13 I in Various Reactor Operating Modes (Paragraph 4 of Section 3 of IEEE 279-1971) 7.3.1.2.5 Design Basis; ESF Functions for Malfunctions, 7.3-14 I Accidents, Natural Phenomena, or Credible Events (Paragraph 8 of Section 3 of IEEE 279-1971) 7.3.1.3 Final System Drawings 7.3-15 I 7.3.2 Analysis for Engineered Safety Features 7.3-15 I Actuation 7.3.2.1 Failure Mode and Effects Analyses 7.3-15 I O 7.3.2.2 Conformance of Engineered Safety Features to the Requirements of IEEE 279-1971 7.3-15 I 7.3.2.2.1 Conformance to the General Functional 7.3-16 I Requirements'for Engineered Safety Features Actuation (Paragraph 4.1 of IEEE 279-1971) 7.3.2.2.2 Conformance to the Single Failure Criterion 7.3-16 I j for Engineered Safety Features Actuation (Paragraph 4.2 of IEEE 279-1971) 1 7.3.2.2.3 Conformance to the Requirements for Channel 7.3-16 I Independence of the Engineered Safety Features Actuation (Paragraph 4.6 of IEEE l 279-1971) l 7.3.2.2.4 Conformance to the Requirements Governing 7.3-17 I l

' Control and Protection System Interaction l- w of the Engineered Safety Features Actuation i (Paragraph 4.7 of IEEE 279-1971) i

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O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7.3.2.2.5 Derivation of System Inputs for Engineered 7.3-17 I Safety Features Actuation (Paragraph 4.8 of IEEE 279-1971) 7.3.2.2.6 Capability for Sensor Checks and Equipment 7.3-17 I Test and Calibration of the Engineered Safety Features Actuation (Paragraph 4.9 and 4.10 of IEEE 279-1971 7.3.2.2.7 Conformance to Requirements on Bypassing 7.3-20 I of Engineered Safety Features Actuation Functions (Paragraph 4.11, 4.12, 4.13 and 4.14 of IEEE 279-1911) 7.3.2.2.8 Conformance to the Requirement for Completion 7.3-20 I of Engineered Safety Features Actuation Once Initiated (Paragraph 4.16 of IEEE 279-1971) 7.3.2.2.9 Conformance to the Requirement to Provide 7.3-21 I Initiation at the System-level for All ESF Actuations (Paragraph 4.17 of IEEE 279-1971) 7.3.2.3 Summary 7.3-22 I 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4-1 I 7.4.1 Description 7.4-3 I 7.4.1.1 Monitoring Indicators 7.4-3 I 7.4.1.2 Controls 7.4-3 I 7.4.1.2.1 General Considerations 7.4-3 I 7.4.1.2.2 Pumps and Fans 7.4-4 I 7.4.1.2.3 Emergency Generators 7.4-5 I

7.4.1.2.4 Valves and Heaters 7.4-5 I 7.4.1.3 Control Room Evacuation 7.4-6 I l HAPWR/I&C/EP xiii NOVEMBER, 1984 2252e:1d l

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O TABLE OF CONTENTS (Continued)

Reference O Section Title ,P_qge SAR Section Status 7.4.1.4 Equipment and Systems Necessary for Cold 7.4-6 I Shutdown 7.4.1.5 Other Considerations 7.4-8 I 7.4.2 Analysis 7.4-8 I

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7.5 INSTRUMENTATION IMPORTANT TO SAFETY 7.5-1 I 7.5.1 Introduction 7. 5-1 I 7.5.2 Variable Classifications and Requirements 7.5-1 I 7.5.2.1 Definitions 7.5-3 I 7.5.2.1.1 Design Basis Accident Events 7.5-3 I

~7.5.2.1.2 Hot Standby 7.5-4 I 7 . 5. 2.1. 3 Cold Shutdown 7.5-4 I O~ 7 . 5. 2 .1. 4 Controlled Condition 7.5-4 I

7. 5. 2.1. 5 Critical Safety Functions 7.5-4 I
7. 5. 2.1. 6 Immediately Accessible Information 7.5-5 I 7.5.2.1.7 Primary Information 7.5-5 1 7.5.2.1.8 Contingency Actions 7.5-5 I 7.5.2.1.9 Key variables 7.5-5 I 7.5.2.1.10 Backup Information 7.5-5 I 7.5.2.2 Variable Types 7.5-6 I

-7.5.2.2.1 Type A 7.5-6 I 7.5.2.2.2 Type 8 7.5-7 I 7.5.2.2.3 Type C 7.5-7 I 7.5.2.2.4 Type D 7.5-8 I 7.5.2.2.5 Type E 7.5-8 I

% 7.5.2.3 Variable Categories 7.5-8 I 7.5.2.5.1 Category 1 7.5-9 I 7.5.2.3.1.1 Selection Criteria for Category 1 7.5-9 I 7.5.2.J.1.2 Qualification Criteria for Category 1 7.5-9 I 7.5.2.3.1.3 Design Criteria for Category 1 7.5-9 I WAPWR/I&C/EP xiv NOVEMBER, 1984 2252e:1d

O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7.5.2.3.1.4 Information Processing and Display Inter- 7.5-11 I f ace Criteria for Category 1 7.5.2.3.2 Category 2 7.5-12 I 7.5.2.3.2.1 Selection Criteria for Category 2 7.5-12 I 7.5.2.3.2.2 Qualification Criteria for category 2 7.5-12 I 7.5.2.3.2.3 Design Criteria for Category 2 7.5-12 I 7.5.2.3.2.4 Information Processing and Display Inter- 7.5-14 I face Criteria for Category 2 7.5.2.3.3 Category 3 7.5-14 I 7.5.2.3.3.1 Selection Criteria for Category 3 7.5-14 I 7.5.2.3.3.2 Qualification Criteria for Category 3 7.5-14 I 7.5.2.3.3.3 Design Criteria for Category 3 7.5-15 I 7.5.2.3.3.4 Information Processing and Display Inter- 7.5-15 I face Criteria for Category 3 7.5.2.3.4 Extended Range Instrumentation Qualification 7.5-16 I Criteria 7.5.3 Description of variables 7.5-16 I 7.5.3.1 Type A Variables 7.5-16 I 7.5.3.2 Type B Variables 7.5-17 I 7.5.3.3 Type C Variables 7.5-18 I 7.5.3.4 Type D Variables 7.5-19 I 7.5.3.5 Type E Variables 7.5-20 I 7.5.4 Bypassed and Inoperable Status Indication 7.5-21 I for Engineered Safety Features Systems 7.5.4.1 Description 7.5-21 1 7.6 ALL OTHER SYSTEMS RE0'JIRED FOR SAFETY 7. 6-1 I 7.6.1 Instrumentation and Control System Power 7.6-1 I Supplies 7.6.1.1 Description 7. 6-1 I l WAPWR/I&C/EP xv NOVEMBER, 1984 l

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O TABLE OF CONTENTS (Continued)

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. Reference SAR Section Section Title Pgjte, Status 7.6.1.2 Analysis 7.6-2 I 7.6.2 Residual Heat Removal Isolation Valves - 7.6-2 I Interlocks and Actuation 7.6.2.1 Description 7.6-2 1 7.6.2.2 Analysis of Residual Heat Removal Valves - 7.6-4 I Interlocks and Actuation 7.6.3 Critical Function Isolation Motor 7.6-5 I Operated Valve Interlocks 7.7 CONTROL AND INSTRUMENTATION SYSTEMS 7.7-1 I 7.7.1 Description 7.7-3 I 7.7.1.1 Automatic Power Control System (APCS) 7.7-4 I O 7.7.1.2 7.7.1.3 Rod Control System Control Rod Position Monitoring 7.7-6 7.7-9 I

I 7.7.1.4 Control Rod Insertion and Withdrawal 7.7-10 I Limits 7.7.1.5 Control Rod Stops and Turbine Runbacks 7.7-11 I l

7.7.1.6 Boron Control System 7.7-11 I 7.7.1.7 Gray Rod Control System 7.7-12 I 7.7.1.8 Pressurizer Pressure Control System 7.7-13 I 7.7.1.9 Pressurizer Level Control System 7.7-14 I 7.7.1.10 Steam Generator Water Level Control System 7.7-15 I 7.7.1.11 Steam Dump Control System 7.7-16 I 7.7.1.12 Signal Selector 7.7-18 I 7.7.2 Analysis 7.7-20 I 7.7.2.1 Performance 7.7-20 I l \ 7.7.2.2 Availability / Operability 7.7-22 1 7.7.2.3 Safety 7.7-22 I l

O WAPWR/I&C/EP xvi NOVEMBER, 1984 2252e:1d

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O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 7A INTERFACE INFORMATION 7A-1 I 7A.1 CIRCUIT AND INSTRUMENT LINES SEPARATION 7A-1 I INTERFACE CRITERIA 7A.1.1 Separation of Class 1E and Non-Class 1E 7A-1 I Circuits 7A.1.2 Separation of Channel Set and Protective 7A-2 I Signals 7A.1.3 Separation of Post Accident Monitoring 7A-3 I (PAM) Signals 7A.1.4 Separation by Potential 7A-4 I 7A.1.5 Separation of Instrument Impulse Lines 7A-4 I Sensor Connections) 7A.2 REDUNDANT CIRCUIT AND EQUIPMENT IDENTIFICA- 7A-5 I TION 7A.2.1 Redundant Channel Identification 7A-6 I 7A.3 PROTECTION 0F NSS I&C equipment 7A-6 I 7A.3.1 Operating Environments for Protection System 7A-6 I Equipment 7A.3.2 Protection Against Hazards (sprays, missiles, 7A-7 I

pipe whip, etc.)

7A.3.3 Protection Against Abnormal Events (fire, 7A-7 I flood,etc.)

7A.4 POWER REQUIREMENTS FOR PROTECTION SYSTEM 7A-8 I EQUIPMENT 7A.5 BYPASS INDICATION SYSTEM 7A-8 I 7A.6 THERMAL OVERLDAD PROTECTION 7A-8 I 7A.7 COMPLETION OF FROTECTIVE ACTION ONCE 7A-8 I INITIATED O

j HAPWR/I&C/EP xvii NOVEMBER, 1984 2252e:1d l

(

l i

l O l TABLE OF CONTENTS (Continued)

Reference

{ SAR Section Section Title h Status 7A.8 SEQUENCING OF SAFEGUARDS LOADS ONTO THE 7A-8 I O 7A.9 DIESEL GENERATORS TESTING OF ENGINEERED SAFETY FEATURES 7A-9 I ACTUATION OF COMPONENTS ON-LINE AT POWER 7 A.10 REGULATORY AND INDUSTRY GENERIC CRITERIA 7A-9 I 7A.11 FIRE PROTECTION CONSIDERATIONS IN THE 7A-9 I CONTROL ROOM 7B WESTINGHOUSE DESIGN APPROACH FOR SOFTWARE 7 B-1 I DEVELOPNENT FOR THE INTEGRATED PROTECTION SYSTEM

78.1 DESCRIPTION

OF MODULARITY CONCEPT 78-1 I O\ 78.2 CONTROL OVER NESTING AND INTERRUPTS 78-3 I 7B.3 SYSTEM SOFTWARE ORGANIZATION 7B-5 I 78.4 PROGRAMMING LANGUAGE 7B-6 I 78.5 SOFTWARE TEST AND VERIFICATION 78-7 I B.O ELECTRIC POWER 8.1 -1 1

8.1 INTRODUCTION

8.1 -1 I 8.1.1 Utility Grid Description 8.1 -1 I Q 8.1. 2 Onsite Power System Description 8.1-1 I 8.1.3 Safety-Related. Loads 8.1-2 I 8.1.4 Design Bases 8.1-2 I 8.1.4.1 Of f site Power System 8.1 -2 1

-t 8.1.4.2 Onsite Power System 8.1-2 I 8.1.4.2.1 Safety Design Bases 8.1-2 I 8.1.4.2.2 Power Generation Design Bases 8.1-4 I

8.1.4.3 Design Criteria, Regulatory Guides, and 8.1-4 I IEEE Standards l

l l WAPWR/I&C/EP xviii NOVEMBER, 1984 2252e:1d i ._ _ _ _ _ _ .

1 I

O TABLE OF CONTENTS (Cont %ued)

Reference SAR Section Section Title Page Status 8.2 0FFSITE POWER SYSTEM 8.2-1 I 8.3 ONSITE POWER SYSTEMS 8 . 3-1 I 8.3.1 AC Power Systems 8.3-1 I 8.3.1.1 Description 8.3-1 I 8.3.1.1.1 Non-Class 1E AC System 8.3-1 I 8.3.1.1.2 Class 1E AC System 8.3-2 I 8.3.1.1.3 Standby Power Supply 8.3-8 I 8.3.1.1.4 Control Rod Drive Power Supply 8.3-16 I 8.3.1.1.5 Vital Instrument AC Power Supply 8.3-17 I 8.3.1.1.6 Nonvital Instrument AC Power Supply 8.3-17 I 8.3.1.1.7 Electric Equipment Layout 8.3-17 I 8.3.1.1.8 Design Criteria for Class 1E Equipment 8.3-18 I l 8.3.1.1.9 Cable Derating and Cable Tray Fill 8.3-20 I l 8.3.1.2 Analysis 8.3-21 I

8. 3.1. 2 .1 Compliance with General Design Criteria 17 8.3-21 I

! and 18 and Regulatory Guides 8.3.1.2.2 Safety Related Equipment Exposed to Hostile 8.3-21 I Environment-8.3.1.3 Physical Identification of Safety-Related 8.3-21 I Equipment 8.3.1.4 Independence of Redundant Systems 8.3-23 I 8.3.1.4.1 Separation Criteria 8.3-23 I 8.3.1.4.1.1 Raceway and Cable Routing 8.3-23 I 8.3.1.4.1.2 Hostile Environments 8.3-25 I 8.3.1.4.1.3 Electrical Penetration Areas 8.3-26 I 8.3.1.4.1.4 Cable Tray Crossover Areas 8.3-26 I 8.3.1.4.2 Seismic Requirements 8.3-26 I O-WAPWR/I&C/EP xix NOVEMBER, 1984 2252e:1d

O TABLE OF CONTENTS (Continued)

O Reference SAR Section Section Title PARE Status 8.3.1.4.3 Administrative Responsibilities and Controls 8.3-26 I

'O for Assuring Separation Criteria During Design and Installation 8.3-26 I 8.3.2 DC Power Systems 8.3-27 I 8.3.2.1 Description 8.3-27 I 8.3.2.1.1 Safety Related DC Loads 8.3-28 I 8 . 3 . 2.1. 2 Class 1E Station Batteries and Battery 8.3-28 I Chargers

8. 3. 2.1. 3 Separa^1on and Ventilation 8.3-29 I 8.3.2.2 Analysis 8.3-29 I 8.3.3 Fire Protection For Cable Systems 8.3-29 I 8A ELECTRIC PDWER-INTERFACES 8 A . 2-1 I EA.2 0FFSITE PDWER SYSTEM 8A.2-1 I 9.0 AUXILIARY SYSTEMS 9. 0-1 NA 10.0 STEAM AND POWER CONVERSION SYSTEM 10.0-1 NA 11.0 RADI0 ACTIVE WASTE MANAGEMENT 11.0-1 NA E'

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 I O

WAPWR/I&C/EP xx NOVEMBER, 1984 2252e:1d

O TABLE OF CONTENTS (Continued)

Reference SAR Section Section Title Pace Status 15.0.2 Classification of Plant Conditions 15.0-1 I 15.0.2.1 Condition I - Normal Operati)n and Opera- 15.0-2 I tional Transients 15.0.2.2 Condition II - Faults of Moderate Frequency 15.0-4 I 15.0.2.3 Condition III - Infrequent Faults 15.0-6 I 15.0.2.4 Condition IV - Limiting Fau.ts 15.0-7 I 15.0.3 Optimization of Control System: 15.0-8 I 15.0.4 Plant Characteristics and Initial Conditions 15.0-9 I Assumed in the Accident Analyses 15.0.4.1 Design Plant Conditions 15.0-9 I 15.0.4.2 Initial Conditions 15.0-9 I 15.0.4.3 Power Distribution 15.0-10 1 15.0.5 Reactivity Coefficients Assumed in the 15.0-11 I Accident Analyses 15.0.6 Rod Cluster Control Assembly Insertion 15.0-12 I Characteristics 15.0.7 Trip Points and Time Delays to Trip Assumed 15.0-13 I in Accident Analyses 15.0.8 Instrumentation Drift and Calorimet 15.0-14 I Errors - Power Range Neutron Flux 15.0.9 Plant System and Components Available for 15.0-15 I Mitigation of Accident Effects 15.0.10 Fission Product Inventories 15.0-16 I 15.0.10.1 Inventory in the Core 15.0-16 I 15.0.10.? Inventory in the Fuel Pellet Clad Gap 15.0-16 I 15.0.10.3 Inventory in the Reactor Coolant 15.0-16 I 15.0.11 Residual Decay Heat 15.0-17 1 15.0.11.1 Total Residual Heat 15.0-17 I O

WAPWR/I&C/EP xxi NOVEMBER, 1984 2252e:1d

j l l TABLE OF CONTENTS (Continued)

O Reference SAR Section Section Title P_ age Status 15.0.12 Computer Codes Utilized 15.0-17 I O 15.0.12.1 15.0.12.2 FACTRAN LOFTRAN 15.0-17 15.0-12 1 I

15.0.12.3 TWINKLE 15.0-19 I 15.0.12.4 THINC 15.0-19 I 15.0.13 References 15.0-19 I 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 15.4-1 II 15.4.3 Rod Cluster Control Assembly Misalignment 15.4-1 I (System Malfunction or Operator Error) 15.4.3.1 Identification of Causes and Accident 15.4-1 I Description 16.0 TECHNICAL SPECIFICATIONS 16.0-1 NA 17.0 QUALITY ASSURANCE 17.0-1 I 17.1 QUALITY ASSURANCE DURING DESIGN AND 17.0-1 I CONSTRUCTION 17.1.1 References 17.0-1 I O

O i O

MAPk'R/I&C/EP xxii NOVEMBER, 1984 2252e:1d

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O TABLE OF CONTENTS (cont)

KEY TO ' REFERENCE SAR SECTION STATUS

  • COLUMN: ,

Category I o

Those sections which are complete and for which no additional information is to be provided for the PDA application.

Category II Those sections which are complete insof ar as providing material relevant to this system module but for which additional information will be provided in support of subsequent modules.

Category III Those sections for which information on interf acing systems will be provided at a '.ater date.

!LA.

Those sections for which categorization is not applicable. Only the section titles are included for clarity.

O l

EAPWR-!&C/EP NOVEMBER, 1984 i.xiii 1476e:ld

O TABLE OF CONTENTS (Continued)

LIST OF TABLES Number Title Page

, 1. 6 -1 Material Incorporated by Reference 1.6-2 l

1. 7 -1 Electrical, Control and Instrumentation Diagrams 1.7-2
1. 8 -1 Standard Review Plan Deviations 1.8-2 7 .1 -1 Listing of Applicable Criteria 7.1-71 7 . 2-1 Reactor Trips 7.2-30 7.2-2 Reactor Trip Permissives and Interlocks 7.2-32 7.2-3 System-level Manual Inputs to the Reactor Trip Functions 7.2-34 7.2-4 Reactor Trip Variables, Limits, Ranges, and Accuracies 7.2-35

[ Design Basis for Reactor Trip) 7.2-5 Protective Functions for Condition II, III, and IV 7.2-38 Events 7 . 3 -1 Engineered Safety Features Actuation Signals 7.3-26 7.3-2 ESFAS Variables, Limits, Ranges and Accuracies 7.3-30 7.3-3 Interlocks for Engineered Safety Features Actuation 7.3-35 System

.7.3-4 System-Level Manual Inputs to the Integrated Logic 7.3-39 Cabinets (ILC) 7.5-1 Post-Accident Monitoring Instrumentation 7.5-22 g 7.5-2 Summary of Selection of Criteria 7.5-33 U 7.5-3 Summary of Design, Qualification, and Interface 7.5-34 Requirements 7.5-4 Summary of Type A Variables 7.5-35 7.5-5 Sunmary of Type B variables 7.5-36 7.5-6 Summary of Type C Variables 7.5-37 7.5-7 Summary of Type D Variables 7.5-39 7.5-8 Summary of Type E Variables 7.5-43

8. 3 -1 Class lE DC System Loads 8.3-30 f 8.3-2 lwo Train Emergency Electrical Load Requirements 8.3-32
and Diesel Generators WAPWR/I&C/EP. xxiv NOVEMBER, 1984 2252e
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d TABLE OF CONTENTS (Continued)

LIST OF TABLES (Continued)

O Number Title Page 15.0-1 Nuclear Steam Supply System Power Ratings 15.0-1 15.0-2 Values of Pertinent Plant Parameters Utilized in 15.0-22 Accident Analyses 15.0-2a Values of Pertinent Plant Parameters Utilized in 15.0-23 Accident Analyses 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 15.0-27 Accident Analyses 15.0-5 Determinatior, of Maximum Overpower Trip Point - Power 15.0-28 Range Neutron Flux Channel - Based on Nominal Setpoint Considering Inherent Instrument Errors 15.0-6 Plant Systems and Equipment Available for Transient 15.0-30 l and Accident Conditions l 15.0-7 Fuel and Rod Gap Inventories, Core (Ci) 15.0-34 l

l'5.0-8 Reactor Coolant Iodine Concentrations for 1 pCi/ Gram 15.0-35 and 60 pC1/Gramof Dose Equivalent I-131 i

15.0-9 Reactor Coolant Noble Gas Specific Activity Based on 15.0-36 One Percent Defective Fuel 15.0-10 Iodine Appearance Ri es in the Reactor Coolant (Curies /

t 15.0-37 sec)

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l O MAPWR/I&C/EP XXV NOVEMBER, 1984 2252e:1d l

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TABLE OF CONTENTS (Continued)

LIST OF FIGURES Number Title 7.1 -1 Integrated Protection System Architecture 7.1-2 IPS System Block Diagram 7.1-3 N.I.S. Detector Locations 7.1-4 Integrated Protection Cabinet - Cabinet / Subsystem Conceptual Arrangement 7.1-5 IPC - Functional Block Diagram 7.1-6 IPC - ESF Subsystem Block Diagram 7.1-7 IPC - Global Trip Subsystem Block Diagram (GT) 7.1-8 IPC - Trip Enable Subsystem Block Diagram 7 .1 -9 IPC - Typical RT Group Subsystem Architecture 7.1-10 Comunication Subsystem Architecture 7.1-11 Automatic Tester Subsystem Architecture 7.1-12 ESFAC Equipment Arrangement Sketch (Train A Shown - Typical of all trains) 7.1-13 ESFAC Architecture 7.1-14 Front-Mounted Equipment Skektch 7.1-15 Logic Cabinet Architecture 7.1-15 Example of Reactor Trip Voting logic Showing Channel Partial Trips and Channel Set Trips 7.1-17 Reactor Trip Switchgear ,

7.1-18 Alternative Methods - Optical Isolation 7.2-1 MAPWR Functional Diagrams 7.2-2 Generation of a Typical Reactor Trip Function 7.2-3 Block Diagram of DNBR Calculations 7.2-4 Block Diagram of High Kw/Ft Calculatiort 7.6-1 Typical I&C Electrical Power Distribution System - 118 VAC O- 7.6-2 Logic Diagram for Interlocks of RHR Cooldown Suction ' Isolation Motor Operated Valves MAPWR/I&C/EP xxvi NOVEMBER, 1984 2252e:1d Si _ . _ - . _ _ . . . _ . _ . . _ _ _ _ . _ . - _ - - - _ . - - - _- _ _ ..- ,_ ._ _ __ _ _ _ - _ _ _ . _ . _ _ _ _ - - -

TABLE OF CONTENTS (Continued)

LIST OF FIGURES Number Title 7.6-3 Logic Diagram for Motor Operated Valve Interlocks for Accumulator and Core Reflood Tank Discharge Isolation Valves 7.6-4 Logic Diagram for Critical Function Valve Alarm 7.7-1 Low Power Rod Control System 7.7-2 High~ Power Rod Control System 7.7-3 Pressurizer Heater Control 7.7-4 Pressurizer Spray Control 7.7-5 Pressurizer Water Level Control

't . 7 -6 SG Level Control - Normal Power 7.7-7 SG Level Control - Low Power 7.7-8 SG Level Control - Startup/ Shutdown 7.7-9 Steam Dump - Power Imbalance Control 7.7-10 Steam Dump - Pressure Control 7 B-1 Software Generator Block Diagram 7B-2 Sof tware Nesting Diagram 78-3 System Software Organization 78-4 IPS Data Bus 8.3-1 WAPWR AC Main Single Line Diagram 8.3-2 WAPWR DC and 120 VAC Oneline Diagram 15.0-1 Illustration of Core Thermal Limits and DNB Protection (N Loop Operation) 15.0-2 Doppler Power Coefficients Used in Accident Analysis 15.0-3 RCCA Position vs. Time to Dashpot l 15.0-4 Normalized RCCA Reactivity Worth vs. Fraction Insertion 15.0-5 Normalized RCCA Bank Reactivity Worth vs. Normalized Drop Time O

WAPWR/I&C/EP xxvii NOVEMBER, 1984 O

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