AP1000 Pre-Construction Safety Report (UKP-GW-GL-732)

501 Pages·2009·3.038 MB·English

F-3.4.1-1 Rev 3
DOCUMENT COVER SHEET
TDC: Permanent File:
DOCUMENT NO. REVISION PAGE ASSIGNED TO OPEN ITEMS (Y/N)
UKP-GW-GL-732 2 1 of 501 W-D. Popp N
DOCUMENT STATUS: PRE CFC CAE DES Westinghouse Acceptance of AP1000
Design Partner Document by:

N/A
(Name and Date)
ALTERNATE DOCUMENT NUMBER: WORK BREAKDOWN #: N/A
ORIGINATING ORGANIZATION: Westinghouse
TITLE: AP1000 Pre-Construction Safety Report
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SIGNATURE / DATE

VERIFIER(S) WEC 6.1.pdf SIGNATURE / DATE Verification Method: Independent Review
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Plant Applicability: All AP1000 plants except:
Only the following plants: UKP
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J. A. Speer Electronically Approved***
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UKP-GW-GL-732
Revision 2
AP1000
Pre-Construction
Safety Report
AP1000 Pre-Construction Safety Report
REVISION HISTORY
Report Description of Change
Revision 1 This document contains numerous editorial improvements and
referenced reports revision updates from Revision 0.
Revision 2 The Pre-Construction Safety Report (PCSR), Revision 2 has
been completely restructured to accommodate general NII
comments on claims, arguments and evidence. The PCSR also
includes a summary of new documents, External Hazards, a
revised European DCD and a revised Environment Report. The
PCSR also refers to the results of new evaluations, submitted in
documents: AP1000 Equivalency / Maturity Study of the
U.S. Codes and Standards, AP1000 UK Safety Categorization
and Classification of Structures Systems and Components, and
AP1000 UK Safety Categorization and Classification
Methodology.

UKP-GW-GL-732 i Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS
Section Title Page
REVISION HISTORY i
TABLE OF CONTENTS ii
ABBREVIATIONS ABB 1-1
1.0 INTRODUCTION 1-1
1.1 Purpose of the Safety Report 1-1
1.1.1 Background of the Generic Design Assessment Process 1-1
1.1.2 Structure of the Generic Design Assessment Process 1-2
1.1.3 Purpose of the Pre-Construction Safety Report in GDA 1-2
1.2 Development of the AP1000 Safety Report 1-2
1.2.1 AP1000 Design Basis 1-2
1.2.2 UK Regulatory Regime 1-4
1.2.3 AP1000 Safety Report 1-4
1.3 GDA Documentation Structure and Interfaces 1-6
1.3.1 AP1000 Generic PCSR 1-6
1.3.2 Topic Reports Supporting the AP1000 Safety Case 1-7
1.3.3 Supporting Technical Documentation to the AP1000 Safety Case 1-9
1.4 Generic PCSR: Structure and Content 1-10
1.5 Quality Assurance Process followed during the Production of the
Generic Pre-Construction Safety Report 1-12
1.5.1 Stakeholders in the PCSR 1-12
1.5.2 Quality Assurance associated with Westinghouse Design and
Technical Information 1-13
1.5.3 Safety Case Review Process 1-14
1.6 Conclusion 1-14
2.0 GENERAL PLANT DESCRIPTION 2-1
2.1 Introduction 2-1
2.2 Evolution of the AP1000 Design 2-1
2.3 Basic Design and Technical Characteristics 2-2
2.4 Layout of the Main Civil Structures 2-3
2.4.1 Site Characteristics 2-3
2.4.2 Site Plan 2-4

UKP-GW-GL-732 ii Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
2.4.3 Plant Arrangement 2-4
2.4.4 Containment/Shield Building 2-5
2.5 Plant Arrangement Considerations 2-8
2.6 Proven Components and Technology in the AP1000 Design 2-9
2.7 Conclusion 2-10
3.0 GENERIC SITE CHARACTERISTICS 3-1
3.1 Introduction 3-1
3.2 Site Design Parameters 3-1
3.2.1 Meteorology 3-2
3.2.2 Geology and Hydrogeology 3-3
3.2.3 Hydrology 3-3
3.3 Strategic Siting Assessment (SSA) 3-4
3.3.1 Exclusionary Criteria 3-4
3.3.2 Discretionary Criteria 3-5
3.3.3 Proximity to Hazardous Industrial Facilities and Operations (D3) 3-7
3.3.4 Proximity Access to Suitable Sources of Cooling (D10) 3-7
3.4 Other Site Specific Criteria 3-8
3.5 Monitoring of Site Specific Parameters 3-9
3.6 Conclusion 3-9
4.0 SAFETY ASPECTS OF DESIGN 4-1
4.1 Introduction 4-1
4.2 Use of Safety Functions 4-3
4.2.1 Key Safety Functions 4-3
4.2.2 Categorisation of Safety Functions 4-5
4.3 Identification of Design Requirements for Safety 4-7
4.3.1 Identification of Design Requirements associated with Normal Operation 4-7
4.3.2 Identification of Design Requirements associated with Fault Conditions 4-7
4.4 Approach to Hazards 4-8
4.4.1 Assessment of Internal Hazards 4-8
4.4.2 Assessment of External Hazards 4-24

UKP-GW-GL-732 iii Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
4.5 Engineering Substantiation 4-38
4.5.1 Safety Classification of Systems, Structures and Components 4-38
4.5.2 Seismic Categorisation of Systems, Structures and Components 4-41
4.5.3 Incredibility of Failure Issues 4-42
4.5.4 Application of Codes and Standards 4-43
4.5.5 Environmental Qualification of Systems, Structures and Components 4-43
4.6 Conclusion 4-44
5.0 SAFETY ASSESSMENT APPROACH 5-1
5.1 Introduction 5-1
5.2 Fault Schedule 5-1
5.2.1 Introduction 5-1
5.2.2 Identification of Initiating Events 5-2
5.2.3 Initiating Event Frequencies 5-3
5.2.4 Provision of Safety Measures 5-3
5.3 Design Basis Analysis 5-5
5.3.1 Introduction 5-5
5.3.2 Selection of Representative Sequences 5-5
5.3.3 Thermal-Hydraulic Analysis Approach 5-5
5.3.4 Radiological Analysis Approach 5-14
5.3.5 Results 5-15
5.3.6 DBA Conclusions 5-30
5.4 Probabilistic Risk Analysis 5-31
5.4.1 Introduction 5-31
5.4.2 Selection of Initiating Events 5-31
5.4.3 Analysis Approach 5-32
5.4.4 Results 5-34
5.4.4.7 Important Common Causes/Modes 5-41
5.4.4.8 Dependence on Operator Action 5-42
5.4.4.9 Treatment of Equipment Reliability 5-42
5.4.4.10 Shutdown PRA 5-43

UKP-GW-GL-732 iv Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
5.4.5 Sensitivity Analysis 5-43
5.4.6 PRA Conclusions 5-44
5.5 Severe Accident Analysis 5-45
5.5.1 Introduction 5-45
5.5.2 Identification of Plant Damage States 5-46
5.5.3 Construction of the Containment Event Tree 5-47
5.5.4 Quantification of Release Frequencies 5-50
5.5.5 Results 5-51
5.5.6 Severe Accident Analysis Conclusions 5-51
5.6 Safety Analysis Conclusions 5-52
6.0 DESCRIPTION OF PLANT SYSTEMS AND THEIR
CONFORMANCE WITH DESIGN REQUIREMENTS 6-1
6.1 Introduction 6-1
6.2 Primary Systems General Operation 6-1
6.3 Reactor 6-3
6.3.1 Reactor System 6-3
6.3.2 Reactor Coolant System 6-18
6.4 Engineered Safety Features 6-25
6.4.1 Containment System 6-27
6.4.2 Containment Isolation System 6-27
6.4.3 Passive Containment Cooling System 6-29
6.4.4 Main Control Room Emergency Habitability System 6-32
6.4.5 Passive Core Cooling System 6-33
6.5 Auxiliary Systems 6-42
6.5.1 Chemical and Volume Control System 6-43
6.5.2 Containment Hydrogen Control System 6-50
6.5.3 Normal Residual Heat Removal System 6-52
6.5.4 Communication System 6-55
6.5.5 Component Cooling Water System 6-55
6.5.6 Compressed and Instrument Air System 6-57
6.5.7 Containment Leak Rate Test System 6-57

UKP-GW-GL-732 v Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
6.5.8 Demineralised Water Transfer and Storage System 6-58
6.5.9 Demineralised Water Treatment System 6-58
6.5.10 Fire Protection System 6-58
6.5.11 Gaseous Radwaste System 6-59
6.5.12 Liquid Radwaste System 6-61
6.5.13 Mechanical Handling System 6-63
6.5.14 Plant Gas System 6-66
6.5.15 Potable Water System 6-66
6.5.16 Primary Sampling System 6-67
6.5.17 Radiation Monitoring System 6-69
6.5.18 Radioactive Waste Drain System 6-70
6.5.19 Sanitary Drainage System 6-71
6.5.20 Secondary Sampling System 6-71
6.5.21 Service Water System 6-71
6.5.22 Solid Radwaste System 6-72
6.5.23 Spent Fuel Pool Cooling System 6-73
6.5.24 Standby Diesel Fuel Oil System 6-75
6.5.25 Turbine Building Closed Cooling Water System 6-76
6.5.26 Turbine Island Vents, Drains and Relief System 6-76
6.5.27 Waste Water System 6-77
6.6 Steam and Power Conversion Systems 6-77
6.6.1 Feed and Condensate System 6-77
6.6.2 Main Steam System 6-81
6.6.3 Turbine Bypass System 6-83
6.6.4 Main Turbine-Generator 6-84
6.6.5 Moisture Separator Reheaters 6-85
6.6.6 Condenser Air Removal System 6-86
6.6.7 Gland Seal System 6-87
6.6.8 Main Condenser 6-88
6.6.9 Steam Generator Blowdown System 6-89

UKP-GW-GL-732 vi Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
6.6.10 Circulating Water System 6-91
6.6.11 Auxiliary Steam Supply System 6-92
6.6.12 Turbine Island Chemical Feed System 6-93
6.6.13 Condensate Polishing System 6-93
6.7 Instrumentation and Control 6-93
6.7.1 Description 6-93
6.7.2 Design Requirements 6-94
6.7.3 Substantiation 6-94
6.8 Electrical Power Systems 6-102
6.8.1 Class 1E dc and Uninterruptible Power Supply System 6-103
6.8.2 Non-Class 1E dc and Uninterruptible Power Supply System 6-105
6.8.3 Main ac Power System 6-106
6.8.4 Onsite Standby Power System 6-107
6.8.5 Cathodic Protection System 6-108
6.8.6 Excitation and Voltage Regulation System 6-108
6.8.7 Grounding and Lightning Protection System 6-109
6.8.8 Lighting System 6-109
6.8.9 Plant Security System 6-109
6.8.10 Special Process Heat Tracing System 6-109
6.9 HVAC Systems 6-109
6.9.1 Annex/Auxiliary Building Nonradioactive Ventilation System 6-110
6.9.2 Central Chilled Water System 6-110
6.9.3 Containment Air Filtration System 6-111
6.9.4 Containment Recirculation Cooling System 6-112
6.9.5 Diesel Generator Building Ventilation System 6-112
6.9.6 Health Physics and Hot Machine Shop HVAC System 6-113
6.9.7 Hot Water Heating System 6-114
6.9.8 Nuclear Island Nonradioactive Ventilation System 6-114
6.9.9 Radiologically Controlled Area Ventilation System 6-120
6.9.10 Radwaste Building HVAC System 6-120

UKP-GW-GL-732 vii Revision 2
AP1000 Pre-Construction Safety Report
TABLE OF CONTENTS (cont.)
Section Title Page
6.9.11 Turbine Island Building Ventilation System 6-121
6.10 Conclusion 6-122
6.11 References 6-123
7.0 DESCRIPTION OF THE CIVIL WORKS AND STRUCTURES
AND THEIR DESIGN REQUIREMENTS FOR SAFETY 7-1
7.1 Introduction 7-1
7.2 Nuclear Island Structures 7-1
7.2.1 Design Requirements for Safety during Normal Operations 7-5
7.2.2 Design Requirements for Safety during Fault Conditions 7-5
7.2.3 Internal Hazards 7-6
7.2.4 External Hazards 7-6
7.3 Non-Nuclear Island Structures 7-6
7.4 Conclusion 7-7
8.0 ALARP ASSESSMENT OF THE DESIGN OF THE AP1000 8-1
8.1 Introduction 8-1
8.1.1 Purpose 8-1
8.1.2 Scope 8-1
8.1.3 Content 8-2
8.2 Use of Relevant Good Practice 8-3
8.2.1 Application of Standards Defining Good Practice 8-3
8.2.2 Relevant Good Practice in Design 8-10
8.3 Use of the PRA Risk Model to Inform Design 8-16
8.3.1 Background to the PRA Work 8-16
8.3.2 System and Function Reliability 8-17
8.3.3 Human Reliability 8-17
8.3.4 Core Damage Frequency for Internal Initiating Events at Power 8-18
8.3.5 Large Release Frequency for Internal Initiating Events at Power 8-19
8.3.6 Core Damage Frequency and Large Release Frequency for Plant
Initiating Events while Shutdown 8-20
8.3.7 Review of Defence in Depth Systems 8-21

UKP-GW-GL-732 viii Revision 2