ML20128P653
| ML20128P653 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 06/30/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19304B384 | List:
|
| References | |
| NUDOCS 8507260473 | |
| Download: ML20128P653 (152) | |
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RESAR-SP/90 O RADIATION PROTECTION WESTINGHOUSE O ADVANCED PRESSURIZED -
WATER REACTOR I
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[ illII fr-STANDARD PLANT DESIGN
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O WAPWR-RP 2997e:1d i JUNE, 1985 I
4 TABLE OF CONTENTS O ,
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Reference SAR Section
/T Section Title Page Status U
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT 1.1 -1 11
1.1 INTRODUCTION
1.1 -1 II
/~ 1.2 GENERAL PLAN 1 DESCRIPTION 1. 2-1 II 1.2.2 Principal Design Criteria 1. 2-1 11 1.6 MATERIAL INCORPORATED BY REFERENCE 1. 6-1 II 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, EQUIPMENT 3. 0-1 NA AND SYSTEMS 4.0 REACTOR 4. 0-1 NA 5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5. 0-1 NA 6.0 ENGINEERED SAFETY FEATURES 6.0-1 NA O 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 10.0 STEAM AND POWER CONVERSION SYSTEM 10.0-1 NA 11.0 RADIDACTIVE WASTE MANAGEMENT 11.0-1 NA 12.0 RADIATION PROTECTION 12.1-1 1 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES 12.1-1 1 ARE AS LOW AS IS REASONABLY ACHIEVABLE (ALARA) 12.1.2 Design Considerations 12.1-2 1 O 12.1.3 Operational Considerations 12.1-6 1 12.2 RADIATION SOURCES 12.2-1 1 12.2.1 Contained Sources 12.2-1 I rs 12.2.1.1 Sources for Full Power Operation 12.2-1 1
' (- 12.2.1.2 Sources for Shutdown 12.2-11 1 12.2.1.3 Sources for Design Basis Accident 12.2-13 1 12.2.2 Airborne Radioactive Material Sources 12.2-14 1 O WAPWR -R P 2997e:1d ii JUNE, 1985
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TABLE OF CONTENTS (Continued)
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- Reference SAR Section Section Title Page Status 12.2.2.1 Model for Calculating Airborne Concentrations 12.2-14 1 12.2.3 References 12.2-16 I f 12.3 RADIATION PROTECTION DESIGN FEATURES 12.3-1 1 12.3.1 Facility Design Features 12.3-1 1 12.3.1.1 Plant Design Description for ALARA 12.3-1 1 12.3.1.1.1 Equipment and Component Designs for ALARA 12.3-1 1 12.3.1.1.1.1 Nuclear Power Block (NPB) Equipment 12.3-1 1 12.3.1.1.1.2 Auxiliary Equipment 12.3-4 I 12.3.1.1.2 Facility Layout ALARA Considerations 12.3-7 1 12.3.1.2 Radiation Zoning and Access Control 12.3-11 1 12.3.2 SHIELDING 12.3-13 1 12.3.2.1 Design Objectives 12.3-13 I
' 12.3.2.2 General Shielding' Design 12.3-14 1 12.3.2.2.1 Reactor Containment Building Shielding Design 12.3-14 I P 12.3.2.2.2 Reactor Containment Building Interior 12.3-15 I Shielding Design 12.3.2.2.3 Reactor External Building Shielding 12.3-17 I 12.3.2.2.4 Fuel Handling Building Shielding Design 12.3-1 B I
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12.3.2.2.5 Radwaste Buildings Shielding Design 12.3-19 I ~
12.3.2.2.6 Turbine Building Shielding Design 12.3-19 1 12.3.2.2.7 Control Room Shielding Design 12.3-19 I 12.3.2.2.8 Miscellaneous Plant Areas and Plant Yard 12.3-20 I Areas 12.3.2.3 Shielding Calculational Methods 12.3-20 I ,
/ 12.3.3 Ventilation 12.3-23 II 12.3.3.1 Design Objectives 12.3-23 1 12.3.3.2 Design Guidelines 12.3-24 I O WAPWR-RP iii JUNE, 1985 2997e:1d
TABLE OF CONTENTS (Continued)
O ; Reference SAR Section Section Title PiULe_ Status 12.3.4 Area Radiation and Airborne Radioactivity 12.3-25 I Monitoring Instrumentation 12.3.4.1 Area Radiation Monitoring 12.3-25 1 12.3.4.1.1 Design Objectives 12.3-25 1 12.3.4.1.2 Criteria for Location of Area Monitors 12.3-26 1 12.3.4.1.3 General System Description 12.3-27 I 12.3.4.1.4 Data Processing Module and Display Console 12.3-28 1 12.3.4.1.5 Local Annunciation 12.3-28 1 12.3.4.1.6 Power Supplies 12.3-28 1 12.3.4.1.7 Redundancy, Diversity, and Interdependence 12.3-28 I 12.3.4.1.8 Area Monitor Description 12.3-29 I 12.3.4.1.9 Range and Alarm Setpoints 12.3-30 1 12.3.5 References 12.3-32 I
,_ 12.4 DOSE ASSESSMENT 12.4-1 1 12.4.1 Exposures Within the Plant Structures 12.4-1 1 12.4.1.1 Direct Radiation Dose Estimates 12.4-1 1 12.4.1.2 Airborne Radioactivity Dose Estimates 12.4-9 I 12.4.2 Radiation Exposure Outside the Plant 12.4-9 I Structures 12.4.3 References 12.4-10 1 12.5.1 Health Physics Program 12.5-1 1 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
/ 16.0 TECHNICAL SPECIFICATIONS 16.0-1 NA 17.0 QUALITY ASSURANCE 17.0-1 II 17.1 QUALITY ASSURANCE DURING DESIGN AND 17.0-1 II CONSTRUCTION 17.
1.1 REFERENCES
17.0-1 II klAPWR-RP IV .lVNE, 1985 2997e:1d
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TABLE OF CONTENTS (Continued) l KEY TO " REFERENCE SAR SECTION STATUS" COLUMN: ,.
Cateoory 1 O Those sections which are complete and for which no additional information is l
to be provided for the PDA application. l
. Cateaory 11 Those sections which are complete insofar as providing material relevant to this system module but for which additional information will be provided in support of subsequent modules.
Cateaory 111 Those sections for which information on interfacing systems will be provided at a later date.
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+- y Those sections for which categorization is not applicable. Only the section titles are included for clarity.
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WAPWR-RP V JUNE, 1985 2997e:ld l
TABLE OF CONTENTS (Continued)
O LIST OF TABLES -
Number Title PaSe O 1.6-1 Material Incorporated by Reference 1.6-2 1.8-1 Standard Review Plan Deviations 1.8-2 12.2-1 Radiation Sources: Reactor Coolant Nitrogen-16 12.2-17 Activity 12.2-2 Radiation Sources: Pressurizer 12.2-18 12.2-3 Isotopic Composition and Specific Activity of 12.2-20 Typical Out-of-Core Crud Deposits 12.2-4 Radiation Sources: Chemical and Volume Control System 12.2-21 12.2-5 Radiation Sources: Boron Recycle System 12.2-27 12.2-6 Radiation Sources: Liquid Waste Processing System 12.2-32 12.2-7 Radiation Sources: Gaseous Waste Processing System 12.2-38 12.2-8 Radiation Sources: Solid Waste Processing System 12.2-40 12.2-9 Radiation Sources: Spent Fuel Pit Cooling System 12.2-41 12.2-10 Radiation Sources: Steam Generator Blowdown 12.2-42 Processing System ,
12.2-11 Radiation Sources: Residual Heat Removal System 12.2-42 12.2-12 Core Average Gamma Ray Source Strengths 12.2-46 12.2-13 Spent Fuel Gamma Ray Source Strengths 12.2-47 12.2-14 Core Average and Spent Fuel Neutron Source Strengths 12.2-48 12.2-15 Irradiated Sb-Be Secondary Source Rod Source 12.2-49 Strengths 12.2-16 Irradiated Incore Detector and Drive Cable Maximum 12.2-51 Withdrawal Source Strengths 12.2-17 Irradiated Incore Detector Drive Cable Source 12.2-52 Strengths O
d 12.2-18 Irradiated Inconel 600 Flux Thimble Source Strengths 12.2-53 WAPWR RP vi JUNE, 1985 2997e:1d
TABLE OF CONTENTS (Continued)
LIST OF TABLES _
, Number Title Page 12.2-19 Integrated Gamma Ray and Beta Source Strengths 12.2-54 (Following a Maximum Credible Accident) 12.2-20 Source Strength in the Residual Heat Removal Loop 12.2-55 (Following an Equivalent Full Core Meltdown Accident) 12.3-1 Radiation Zone Definitions 12.3-33 12.3-2 Conditions of Service for Area Radiation Monitors 12.3-34 12.3-3 Range and Setponts for Area Radiation Monitors 12.3-35 12.4-1 Collective Dose Sununary for Domestic Westinghouse 12.4-11 Plants 12.4-2 Collective Dose Breakdown 12.4-12 12.4-3 Operations Which May Require Containment At-Power 12.4-13 f Access 12.4-4 Dose Estimate for Reactor Operations and Surveillance 12.4-14 I P 12.4-5 Dose Estimate for Routine Maintenance 12.4-15 12.4-6 Reactor Coolant Pump Maintenance / Inspection 12.4-16 12.4-7 Exposure Estimate for RCP Maintenance / Inspection 12.4-17 12.4-8 Reactor Coolant Pump Dose Sununary 12.4 ,18 12.4-9 Dose Estimate for in-Service Inspection 12.4-19 12.4-10 Exposure Estimates for Various Inspection Activities 12.4-20 12.4-11 Dose Estimate for Special Maintenance 12.4-21 12.4-12 Dose Estimate for Waste Processing 12.4-22 12.4-13 Dose Estimate for Refueling 12.4-23 O
WAPWR-RP Vii JUNE, 1985 2997e:1d
TABLE OF CONTENTS (Continued)
LIST OF FIGURES .
Number Title 12.3-1 Westinghouse APWR Radiation Zones - Plan - El. 72.0M 12.3-2 Westinghouse APWR Radiation Zones - Plan - E1. 77.4M 12.3-3 Westinghouse APWR Radiation Zones - Plan - El. 84.8M 12.3-4 Westinghouse APWR Radiation Zones - Plan - E1. 92.2M O 12.3-5 Westinghouse APWR Radiation Zones - Plan - El.100.0M 12.3-6 Westinghouse APWR Radiation Zones - Plan - El.107.6M 12.3-7 Westinghouse APWR Reactor Building Section A-A 12.3-8 Westinghouse APWR Reactor Building Section B-B 12.4-1 ORE Trend for Domestic Westinghouse Plants O
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WAPWR-RP JUNE,1985 2997e:1d l
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