ML20106E646
ML20106E646 | |
Person / Time | |
---|---|
Site: | 05000601 |
Issue date: | 12/31/1984 |
From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
To: | |
Shared Package | |
ML19269B034 | List:
|
References | |
NUDOCS 8502130375 | |
Download: ML20106E646 (393) | |
Text
W WESTINGHOUSE PROPRIETARY CLASS 3 O
RESAR-SP/90 O
STRUCTURAL / EQUIPMENT DESIGN 4
ADVANCED PRESSURIZED WATER REACTOR
"'O"'e*L**"a"len"e*""*a'l*e*"a".'2",""t,,'e" "*",",2**%*%;;"*";
, *",1" t,""s=:.=::
"=.:"*"2"":":":,";;,-t the written authorization of Westinghouse Electric Corporation, Nuclear f orgy Systems.
s O
'@ ^Ja m
i
- r i s""
ga l
l I O O
STANDARD PLkNT DESIGN
=wama M-PDR
_.. _ ~..
i i
e I
1
! h i
i' O
(
1 l
t I
I 4
1
}
i 4
i i
t i
i I
e i
t e
l l
t i
l i
I l
i L
!O 1
l a
I t
DECEMBER, 1984 i
MAPWR-5/E 4
l 2106e:1d I
I 4
i l
TABLE OF CONTENTS Reference SAR O
Section Section Title Pace Status
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF 1.1 -1 11 PLANT
1.1 INTRODUCTION
1.1 -1 II 1.2 GENERAL PLANT DESCRIPTION
- 1. 2-1 11 1.2.2 Principal Design Criteria
- 1. 2-1 11 1.6 MATERIAL INCORPORATED BY REFERENCE
- 1. 6-1 11 1.8 CONFORMANCE WITH THE STANDARD REVIEW PLAN
- 1. 8-1 11 2.0 SITE CHARACTERISTICS 2. 0-1 NA 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIP-3.1 -1 II MENT AND SYSTEMS 3.1 CONFORMANCE WITH NUCLEAR REGULATORY COMMISSION (NRC) GENERAL DESIGN CRITERIA 3.1-2 11 (GDC) 3.1.1 Overall Requirements 3.1 -1 1
3.1. 2 Protection by Multiple Fission Product 3.1-6 I
Barriers 3.1.3 Protection and Reactivity Control Systems 3.1-18 1
3.1.4 Fluid Systems 3.1-27 1
3 '.1. 5 Reactor Containment 3.1-44 1
l 3.1.6 Fuel and Reactivity Control 3.1 -51 1
3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, 3.2-1 II EQUIPMENT AND SYSTEMS
[
3.2.1 Seismic Classification
~
- 3. 2-1 1
3.2.1.1 Definitions
- 3. 2-1 1
' 3. 2.1. 2 Classifications 3.2-2 1
3.2.2 Classification Systems 3.2-3 1
3.2.2.1 Nuclear Safety Classification l;.2-3 I
[
WAPWR-S/E DECEMBER, 1984 1106e:1d II
TABLE OF CONTENTS (Cont.)
Reference.
SAR Section Section Title Page Status 3.2.2.2 Scismic Classification 3.2-3 1
3.2.2.3 Codes and Standards 3.2-4 1
3.3 WIND AND TORNADO LOADINGS
- 3. 3-1 1
3.3.1 Wind Loadings 3. 3-1 1
3.3.1.1 Design Wind Velocity
- 3. 3-1 1
- 3. 3.1. 2 Determination of Applied Forces 3. 3 -1 1
3.3.2 Tornado Loadings 3.3-2 1
3.3.2.1 Applicable Design Parameters 3.3-2 1
3.3.2.2 Determination of Forces on Structures 3.3-3 1
3.3.2.3 Ability of Category 1 Structures to 3.3-4 I
Perform Despite Failure of Structures Not Designed for Tornado Loads 3.3.3 Design and Analysis Procedures 3.3 1 1
3.3.4 References 3.3-4 1
3.4 WATER LEVEL (FLOOD) DESIGN 3.4-1 1
3.4.1 Flood Protection 3. 4-1 1
3.4.1.1 External Flood Protection 3.4-2 1
3.4.1.1.1 Structural Flood Protection 3.4-2 1
3.4.1.1.2 Surface Drainage System 3.4-3 1
3.4.1.2 Flood Protection for Flooding from 3.4-3 1
Component Failures 3.4.1.3 Permanent Dewatering Systems 3. 4 -4 1
3.4.2 Analysis Procedures 3.4-4 1
3.4.2.1 Analysis Procedures for External Flooding 3.4-4 1
3.4.2.2 Analysis Procedures for Flooding from 3.4-5 1
Component WAPWR-S/E 1jj DECEMBER, 1984 2106e:1d
O TABLE OF CONTENTS (Cont.)
Reference SAR Section Section Title PLqe Status O
3.5 MISSILE PROTECTION 3.5-1 1
- 3. 5.1 Missile Selection and Description
- 3. 5-1 1
3.5.1.1 Internally Generated Missiles (Outside 3.5-2 1
Containment) 3. 5.1.1.1 Rotating Component Failure Missiles 3.5-2 1
3. 5.1.1. 2 Pressurized Component Failure Missiles 3.5-3 1
3.5.1.2 Internally Generated Missiles (Inside 3.5-5 1
Containment) 3.5.1.2.1 Control Rod Drive Mechanisms 3.5-6 1
3.5.1.2.2 Valves 3.5-7 I
3.5.1.2.3 Temperature and Pressure Sensors 3.5-7 I
3.5.1.2.4 Other Missiles 3.5-8 1
3.5.1.3 Turbine Missiles 3.5-9 I
3.5.1.4 Missiles Generated by Natural Phenomena 3.5-9 I
- 3. 5.1. 5 Missiles Generated by Events Near the Site 3.5-10 1
3.5.1.6 Aircraf t Hazards 3.5-10 1
- 3. 5.1. 7 Gravity-Generated Missiles 3.5-10 1
3.5.2 Structures, Systems, and Components to be 3.5-10 1
Protected from Externally Generated Missiles 3.5.2.1 G,eneral 3.5-10 1
3.5.,2.2 Missile Barriers Within Containment 3.5-11 I
-3.5.2.3 Barriers for Missiles Generated Outside 3.5-12 I
of Plant Structures
, (,/
3.5.2.4 Missile Barriers Within Plant Structures 3.5-12 I
Other than Containment WAPWR-5/E iv DECEMBER, 1984 7106e:1d
6 O
TABLE OF CONTENTS (Cont.)
0 Reference SAR Section Section Title Paae Status 3.5.3 Barrier Design Procedures 3.5-13 1
3.5.4 Missile Protection Interface Requirement 3.5-16 1
3.6 PROTECTION AGAINST THE DYNAMIC EFFECTS 3.6-1 1
ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3.6.1 Postulated Piping Failures in Fluid
- 3. 6-1 1
Systems Inside and Outside Containment 3.6.1.1 Design Bases 3. 6-1 1
3. 6.1. 2 Description 3.6-5 1
3. 6.1. 3 Safety Evaluation 3.6-$
1 3.6.2 Determination of Break Locations and 3.6-5 1
Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.2.1 Criteria Used to Define High/ Moderate-3.6-6 1
Energy Break / Crack Locations and Configurations 3.6.2.1.1 High-Energy Break Locations 3.6-6 1
3.6.2.1.2 Types of Breaks / Cracks Postulated 3.6-14 1
3.6.2.1.2.1 ASME Section 111 Piping Ot.1er than RCL 3.6-14 i
Piping - High Energy 3.6.2.1.2.2 Nonnuclear Piping - High Energy 3.6-14 1
3.6.2.1.2.3 ASME Section 111 and Nonnuclear Piping 3.6-15 1
- Moderate Energy 3.6.2.1.3 Break / Crack Configuration 3.6-16 1
3.6.2.1.3.1 High-Energy Break Configuration 3.6-16 1
3.6.2.1.3.2 Moderate-Energy Crack Configuration 3.6-18 1
O HAPWR-S/E y
DECEMBER, 1984 2106e:1d
s O
TABLE OF CONTENTS (Cont.)
Reference SAR O
Section Section Title Pigg Status Analytical Methods to Define Forcing 3.6-18 I
O 3.6.2.2 Functions and Response Models 3.6.2.2.1 Forcing Functions for Jet Thrust 3.6-18 1
3.6.2.2.1.1 Time Functions of Jet Thrust Force on 3.6-18 1
Intact Reactor Coolant Loop (RCL) Piping 3.6.2.2.2 Dynamic Analysis of the Reactor Coolant 3.6-21 1
Loop Piping and Equipment Supports 3.6.2.3 Dynamic Analysis Methods to Verify 3.6-21 1
Integrity and Operability 3.6.2.3.1 Dynamic Analysis Methods to Verify 3.6-21 1
Integrity and Operability for Other than RCL 3.6.2.3.2 Dynamic Analysis Methods to verify 3.6-21 1
Integrity and Operability for the RCL 3.6.2.3.2.1 General 3.6-21 1
3.6.2.3.2.2 Large RCS Piping 3.6-23 1
3.6.2.3.2.3 Small Branch Lines 3.6-24 1
3.6.2.3.3 Types of Pipe Whip Restraints 3.6-24 1
3.6.2.3.3.1 Pipe Whip Restraints 3.6-24 I
Analytical Methods 3.6-25 1
O 3.6.2.3.4 3.6.2.3.4.1 Pipe Whip Restraints 3.6-25 1
3.6.2.4 Guard Pipe Assembly Design Criteria 3.6-28 1
3.6.2.5 Material to be Submitted for the 3.6-28 1
Operating License Review 3.6.2.6 References 3.6-28 1
3.7 SEISMIC DESIGN 3.7-1 1
3.7.1 Seismic Input 3.7-1 1
3.7.1.1 Design Response Spectra 3.7-2 1
WAPWR-S/E yt DECEMBER, 1984 2106e:1d
TABLE OF CONTENTS (Cont.)
Reference SAR Section Section Title Page
_ Status 3.7.1.2 Design Time-History 3.7-2 1
3.7.1.3 Critical Damping Valves 3.7-2 1
3.7.1.4 Supporting Media for seismic Category I 3.7-3 1
Structures 3.7.2 Seismic System Analysis 3.7-3 1
3.7.2.1 Seismic Analysis Methods 3.7-4 1
3.7.2.2 Natural Frequencies and Response Loads 3.7-4 1
3.7.2.3 Procedure Used for Modeling 3.7-5 1
3.7.2.4 Soil-Structure Interaction 3.7-5 1
3.7.2.5 Development for Floor Response Spectra 3.7-7 1
3.7.2.6 Three Components of Earthquake Motion 3.7-8 1
3.7.2.7 Combination of Modal Responses 3.7-8 1
3.7.2.8 Interaction of Non-Category I Structures 3.7-8 I
With Seismic Category I Structures 3.7.2.9 Ef f ects of Parameter Variations on Floor 3.7-9 I
Response Spectra 3.7.2.10 Use of Constant vertical Static Factors 3.7-9 1
3.7.2.11 Method Used to Account for Torsional 3.7-9 1
Effects 3.7.2.12 Comparison of Responses 3.7-9 I
3.7.2.13 Methods for Seismic Analysis of Dams 3.7-9 I
3.7.2.14 Determination of Seismic Category I 3.7-10 1
Structure Overturning Moment 3.7.2.15 Analysis Procedure for Damping 3.7-10 1
3.7.3 Seismic Subsystem Analysis 3.7-10 1
3.7.3.1 Seismic Analysis Methods 3.7-10 1
3.7.3.2 Determination of Number of Earthquake 3.7-11 1
Cycles WAPWR-S/E vii DECEMBER, 1984 2106e:1d
(
l TABLE OF CONTENTS (Cont.)
j.
Reference SAR t
Section
{
Section Title PLqe Status 3.7.3.3 Procedure Used for the Modeling 3.7-12 1
]
3.7.3.4 Basis for Selection of Frequencies 3.7-14 I
3.7.3.5 Use of Equipment Static Load Method 3.7-14 I
of Analysis 3.7.3.6 Three Components of Earthquake Motion 3.7-15 I
I 3.7.3.7 Combination of Modal Responses 3.7-15 I
3.7.3.8 Analytical Procedures for Piping 3.7-19 I
3.7.3.9 Multiple Supported Equipment Components 3.7-19 I
with Distinct inputs 3.7.3.10 Use of Constant Vertical Static Factors 3.7-21 I
I
'3 7 3 11 Torsional Effects of Eccentric Masses 3.7-21 1
3.7.3.12 Buried Seismic Category 1 Piping Systems 3.7-22 I
and Tunnels I
3.7.3.13 Interaction of Other Pip'1g with Seismic 3.7-22 I
Category I Piping 3.7.3.14 Seismic ' Analyses for Reactor Internals 3.7-22 1
1 (Core, Core Supports, Mechanisms) 3.7.3.15 Analysis Procedure for Damping 3.7-23 1
7 3.7.4 Seismic Instrumentation 3.7-23 I
3.7.4.1 Comparison with Regulatory Guide 1.12 3.7-24 I
3.7.4.2 Location and Description of Instrument 3.7-24 1
3.7.4.2.1 Time-History Accelerograph 3.7-24 1
3.7.4.2.2 Seismic Switch 3.7-26 1
3.7.4.2.3 Triaxial Spectrum Recorder 3.7-26 1
3.7.4.2.4 Triaxial Peak Accelerograph 3.7-27 1
3.7.4.2.5 Criteria for Instrument Location 3.7-28 I
l 3.7.4.2.6 Seismic Instrumentation Control Panel 3.7-28 1
l WAPWR-S/E yjjj DECEMBER, 1984 2106e:1d
?
TABLE OF CONTENTS (Corit.)
Reference SAR Section Section Title Page Status 3.7.4.3 Control Room Operator Nodifications-3.7-28 1
3.7.4.4 Comparison of Measured and Predicted 3.7-29 1
Responses 3.7.4.5 Inservice Surveillance 3.7-30 1
3.7.5 References 3.7-30 1
3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 1
3.8.1 Concrete Containment
- 3. 8-1 1
3.8.2 Steel Containment
- 3. 8-1 1
3.8.2.1 Description of the Containment 3.8-1 1
3.8.2.2 Applicable Codes, Standards, and 3.8-2 1
Specifications 3.8.2.3 Loads and Load Combinations 3.8-3 I
l.
3.8.2.4 Design and Analysis Procedures 3.8-3 1
3.8.2.5 Structural Acceptance Criteria 3.8-4 1
3.8.2.6 Materials, Quality Control, and Special 3.8-4 1
Construction Techniques 3.8.2.7 Testing and Inservice Inspection 3.8-4 1
Requirements 3.8.3 Concrete and Steel Internal Structures 3.8-5 1
3.8.3.1 Description of the Internal Structures 3.8-5 1
3.8.3.2 Applicable Codes, Standards, and 3.8-6 1
Specifications 3.8.3.3 Loads and Load Combinations 3.8-7 1
3.8.3.4 Design and Analysis Procedures 3.8-7 1
3.8.3.5 Structural Acceptance Criteria 3.8-7 1
3.8.3.6 Materials 3.8-7 1
3.8.3.7 Testing and Inservice Inspection 3.0-8 I
Requi re'ments WAPWR-S/E jx DECEMBER, 1984 2106e:1d
TABLE OF CONTENTS (Cont.)
Reference SAR Section Section Title P,,1ge Status 3.8.4 Other Seismic Category 1 Structures 3.8-8 1
3.8.4.1 Description of the Structures 3.8-8 1
3.8.4.2 Applicable Codes, Standards and 3.8-9 1
Specifications 3.8.4.3 Loads and Load Combinations 3.8-9 1
3.8.4.3.1 Loads 3.8-9 1
3.8.4.3.1.1 Normal Loads 3.8-10 1
3. 8. 4. 3.1. 2 Environmental Loads 3.8-11 1
~
3. 8. 4. 3.1. 3 Design Basis Accident Loads 3.8-12 I
3.8.4.3.2 Load Combinations 3.8-13 1
O 3.8.4.4 Design and Analysis Procedures 3.8-13 1
3,G.4.5 Structural Acceptance Criteria 3.8-14 1
3.8.4.6 Materials 3.8-14 1
3.8.4.7-Testing and Inservice Surveillance 3.8-16 1
Requirements 4
3.8.5 Foundations 3.8-16 1
3.8.5.1 Description of the Foundations 3.8-16 I
[
3.8.5.2 Applicable Codes, Standards and 3.8 I' Specifications 3.8.5.3 Loads and Loading Combinations 3.8-16 1
3~8.5.4 Design and Analysis Procedures 3.8-16 1
3.8.5.5 Structural Acceptance Criteria 3.8-17 1
3.8.5.6 Materials 3.8-18 1
3.8.5.7 Testing and Inservice Inspection 3.8-18 1
Requirements i
3.9 MECHANICAL SYSTEMS AND COMPONENTS
- 3. 9-1 3.9.1 Special Topics for Mechanical Components 3.9-1 1
3.9.1.1 Design Transients
- 3. 9-1 1
i WAPWR-5/E x
DECEMBER, 1984 2106e:1d b
-- -- r
=..-w--
,,-v-
,+,,,,--,.w,ve-,,,,,..w-r-.
,,v,-
-,.-,e-w-ve+-y-.-,.,ww.~,o,.%,,,---,
wee-,...e
.w-p.,m.w-.m.-...wvs,.v,,,.,+m,mm,.9,,e,.<+e.
TABLE OF CONTENTS (Cont.)
Reference SAR Section Section Title Pace Status 3.9.1.1.1 Level A Service Conditions (Normal 3.9-3 I
Conditions) 3.9.1.1.2 Level B Service Conditions (Upset 3.9-19 I
Conditions) 3.9.1.1.3 Level C Service Conditions (Emergency 3.9-29 I
Conditions) 3.9.1.1.4 Level D Servcie Conditions (Faulted 3.9-31 1
Conditions 3.9.1.1.5 Test Conditions 3.9-35 1
3.9.1.2 Computer Programs Used in Analysis 3.9-37 I
3.9.1.2.1 NPB Systems and Components 3.9-37 I
3.9.1.3 Experimental Stress Analysis 3.9-38 I
l 3.9.1.4 Consideration for the Evaluation of the 3.9-38 I
Faulted Condition 3.9.2 Dynamic Testing and Analysis 3.9-38 11 3.9.2.1 Piping Vibration, Thermal Expansion, 3.9-38 I
and Dynamic Effects 3.9.2.2 Seismic Qualification Testing of Safety-3.9-42 I
Related Mechanical Equipment 3.9.2.3 Dynamic Response Analysis of Reactor 3.9-45 I
Internals Under Operational Flow Transients and Steady-State Conditions 3.9.2.4 Preoperational Flow-Induced Vibration 3.9-45 I
Testing of Reactor Internals 3.9.2.5 Dynamic System Analysis of the Reactor 3.9-45 I
Internals Under Faulted Conditions 3.9.3 ASME Code Class 1, 2, and 3 Components, 3.9-45 I
Component Supports, and Core Support Structures WAPWR-S/E DECEMBER, 1984 2106e:1d Xi
s O
TABLE OF CONTENTS (Cont.)
Reference O
SAR Section Section Title Pa3q Status 3.9.3.1 Loading Combinations, Design Transients, 3.9-45 I
O and Stress Limits 3.9.3.1.1 ASME Code Class 1 Components and Supports 3.9-46 1
3.9.3.1.1.1 Analysis of the Reactor Coolant Loop 3.9-46 I
Piping and Supports 3.9.3.1.1.2 Class 1 Auxiliary Branch Lines 3.9-55 1
3.9.3.1.1.3 Loading Combinations and Stress Limits 3.9-58 1
3.9.3.1.2 ASME Code Class 2 and 3 Components 3.9-58 I
and Supports 3.9.3.1.3 Analysis of Primary Components and Valves 3.9-58 1
3.9.3.2 Pump and Valve Operability Assurance 3.9-60 1
3.9.3.2.1 Pumps 3.9-60 I
3.9.3.3.2 Valves 3.9-62 1
3.9.3.2.3 Pump Motor and Valve Operator 3.9-64 I
Qualification 3.9.3.2.4 Active _ASME Code Class 2 and 3 Pumps 3.9-64 1
3.9.3.3 Design and Installation Details for 3.9-66 I
Mounting of Pressure Relief Devices 3.9.3.3.1 Pressure Relief Devices on NPB Components 3.9-66 I
n 3.9.3.3.2 Other Pressure Relief Devices on 3.9-68 1
v Components 3.9.3.4 Component and Piping Supports 3.9-69 1
l 3.9.3.4.1 ASME Code Class 1 Component Supports 3.9-70 1
3.9.3.4.1.1 Primary Component Supports Models 3.9-70 1
and Methods 3.9.3.4.2 ASME Code Class 2 and 3 Supports 3.9-71 1
3.9.3.4.3 Snubbers Used as Component Supports 3.9-72 1
i OO WAPWR-5/E 2106e:1d xjj DECEMBER, 1984
TABLE OF CONTENTS (Cont.)
Reference SAR Section Section Title Page Status 3.9.4 Control Rod Drive Systems 3.9-73 II 3.9.5 Reactor Vessel Internals 3.9-74 11 3.9.5.1 Loading Conditions 3.9-74 1
3.9.5.2 Reactor Vessel and Internals Modeling 3.9-75 I
3.9.5.3 Analytical Methods 3.9-76 1
3.9.6 Inservice Testing of Pumps and Valves 3.9-77 1
3.9.6.1 Inservice Testing of Pumps 3.9-77 1
3.9.6.2 Inservice Testing of Valves 3.9-77 1
3.9.6.3 Relief Request 3.9-78 1
3.10 SEISMIC QUALIFICATION OF SEISMIC CATEGORY 3.10-1 1
I INSTRUMENTATION AND ELECTRICAL EQUIPMEN7 3.10.1 Seismic Qualification Criteria 3.10-1 1
3.10.2 Methods and Procedures for Qualifying 3.10-2 I
Electrical Equipment and Instrumentation 3.10.2.1 Seismic Qualification by Type Test 3.10-3 1
3.10.2.2 Seismic Qualification by Analysis 3.10-4 1
3.10.2.3 Combined Analysis and Testing 3.10-5 I
3.10.3 Methods and Procedures of Analysis or 3.10-5 1
Testing of Supports of Electrical Equipment and Instrumentation 3.10.4 Operating License Review 3.10-6 1
3.10.5 References 3.10-6 I
3.11 ENVIRONMENTAL DESIGN OF MECHANICAL 3.11-1 I
AND ELECTRICAL EQUIPMENT 3.11.1 Equipment Identification and Environmental 3.11-1 1
Conditions 3.11.2 Qualification Tests and Analyses 3.11-2 1
3.11.2.1 Environmental Qualification Criteria 3.11-2 1
MAPWR-S/E xiij OECEMBER, 1984 2106e:1d L
~__
O TABLE OF CONTENTS (Cont.)
f Reference SAR j
s Section Section Title PA2e Status k
3.11.2.2 Performance Requirements for Environmental 3.11-2 1
O Qualification 3.11.2.3 Methods and Procedures for Environmental 3.11-3 1
Qualification 3.11.3 Qualification Test Results 3.11-3 I
3.11.4 Loss of Ventilation 3.11-3 1
3.11.5 Estimated Chemical and Radiation 3.11-3 1
Environment l
I 3.11.6 References 3.11-3 1
4.0 REACTOR 4.0-1 NA
[
5.0 REACTOR COOLANT SYSTEM AND CONNECTED 5.0-1 NA SYSTEMS 7.0 INSTRUMENTATION CONTROLS 7. 0-1 NA 8.0 ELECTRIC POWER 8.0-1 NA 9.0 AUXILIAR,Y SYSTEMS 9.0-1 NA 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 l
-13.0 CONDUCT OF OPERATIONS 13.0-1 NA 14.0 INITIAL TEST PROGRAM 14.0-1 NA O
15.0 ACCIDENT ANALYSES 15.0-1 NA i
i 16.0 TECHN! CAL SP6.!FICAT10NS 16.0-1 NA 17.0 QUALITY ASSURANCE 11.0-1 11 17.1 QUALITY ASSURANCE DURING DESIGN AND 17.0-1 CONSTRUCTION l
17.1.1 References 17.0-1 11 j
s WAPWR-S/E xjy DECEM8ER, 1984 2106e:Id
\\
TABLE OF CONTENTS (Cont.)
~
LIST OF TABLES Number Title PAR'
- 1. 6 -1 Material Incorporated by Reference 1.6-2
- 1. 8-1 Standard Review Plan Deviations 1.8-2 3.2-1 Classification of Structures, Components and Systems 3.2-2 Principal Codes and Standards 3.5-1 Summary of Control Rod Drive Mechanism 3.5-19 Missile Analysis 3.5-2 Valve-Missile Characteristics 3.5-20 3.5-3 Piping Temperature Element Assembly 3.5-21
- Missile Characteristics
~
3.5-4 Characteristics of Other Missiles Postulated 3.5-22 O-Within Reactor Containment
- 3. 6-1 Essential or Non-essential; High-Energy, or i
3.6-29 Moderate - Energy Systems 3.7-1 Regulatory Guide 1.61 Damping Values for 3.7-32 Structures and Components 3.7-2 Seismic Monitoring Instrumentation Requirements 3.7-33 3.8-1 Containment Load Combinations and Load Factors 3.8-19 3.8-2 Stress Intensity Limits for Steel Containment 3.8-20 3.8-3 Load Combinations and Load Factors for 3.8-21 Category 1 Concrete Structures O
3.8-4 Load Combinations and Load Factors for 3.8-25 Category 1 Steel Structures 3.9-1 Sunnery of Reactor Coolant System Design Transients 3.0-79 3.9-2 Loading Combinations for ASME Class 1 Components 3.9-83 and Supports 3.9-3 Stress Criteria for ASME 8&PV Code Section !!!
3.8-84 Class 1 Components and Supports PWR-5/E xy DECEM8ER, 1984 06e:1d
I O
TABLE OF CONTENTS (Cont.)
LIST OF TABLES (Cont.)
O Number Title Paae 3.9-4 Loading Combinations for ASME Code Class 2 and 3 3.9-86 Components and Supports for the NPB 3.9-5 Stress Criteria for ASME B&PV Code 3.9-87 Section 111 Class 2 and 3 Components 3.9-6 Load Combinations and Acceptance Criteria 3.9-88 for Pressurizer Safety and Relief Valve Piping
- Upstream of Valves 3.9-7 Load Combinations at.d Acceptance Criteria for 3.9-89 Pressurizer Safety and Relief Valve Piping Seismically Designed Downstream Portion 3.9-8 Definitions of Load Abbreviations 3.9-90 3.9-9 Load Combinations for Pressurizers Safety and 3.9-91 Relief Valve Nozzles and Support Brackets 3.9-10 Pump Starting / Stopping Conditions 3.9-92 3.10-1 Seismic Category i Instrumentation and Electrical 3.10-7 Equipment 3.11-1 Safety-Related Equipment 3.11-4 O
O O
WAPWR-5/E xvt DECEMBER, 1984 2106e:1d
O TABLE OF CONTENTS (Cont'd)
LIST OF FIGURES Number Title
- 3. 6-1 Analysis Criteria for Mechanistic Pipe Break Approach Os Loss of Reactor Coolant Acc.ident Boundary Limits 3.6-2 3.6-3 Typical U-Bar Restraint 3.6-4 Typical EAM Restraint 3.7-1 Safe Shutdown Earthquake Horizontal kesponse Spectra 3.7-2 Safe Shutdown Earthquake Vertical Response Spectra 3.7-3 Operating Basis Earthquake Horizontal Response Spectra 3.7-4 Operating Basis Earthquake Vertical Response Spectra 3.7-5 Comparison of Design Response Spectra - Horizontal Direction 1 3.7-6 Comparison of Design Response Spectra - Horizontal Direction 2 3.7-7 Comparison of Design Response Spectra - Vertical Direction 3.7-8 Westinghouse Position on Damping 3.7-9 Analytical Model - Seismic System 3.7-10 Seismic Analysis of Soil-Structure Systems 3.7-11 Enveloped Floor Response Spectra - Operating Deck (N-5) 3.7-12 Enveloped Floor Response Spectra - Operating Deck (E-W) 3.7-13 Enveloped' Floor Response Spectra - Operating Deck (Vertical) 3.7-14 Enveloped Floor Response Spectra - RPV Support (N-5) 3.7-15 Enveloped Floor Response Spectra - RPV Support (E-W) 3.7-16 Enveloped Floor Response Spectra - RPV Support (Vertical) 3.7-17 Enveloped Floor Response Spectra - Control Room (N-5)
\\
3.7-18 Enveloped Floor Response, Spectra - Control Room (E-W) 3.7-19 Enveloped F1 gor Response Spectra - Control Room (Vertical) 3.7-20 Post Seismic Event Data Utilization
- 3. 9 -1 Reactor Coolant Loop Supports System, Dynamic Structural Model
'm O
WAPWR-S/E xvif DECEM6ER, 1984 2106e:1d-
.