ML20135J072
| ML20135J072 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 08/31/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19273A537 | List:
|
| References | |
| NUDOCS 8509250191 | |
| Download: ML20135J072 (185) | |
Text
O O
RESAR-SP/90 WASTE MANAGEMENT WESTINGHOUSE O
novanCEo eaEssuRizEo WATER REACTOR O
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O STANDARD PLANT DESIGN AD K
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TABLE OF CONTENTS Reference SAR i
Section Section Title Page Status i
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT 1.1 -1 II 1.1 INTRODUC110N 1.1 -1 11 1.2 GENERAL PLANT 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 7.0 INSTRUMENTATION AND CONTROLS 7.0-1 NA 8.0 ELECTRIC POWER 8.0-1 NA 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 11.1-1 1
11.1 SOURCE TERMS 11.1-1 I
l 11.1.1 Reactor Coolant Activity 11.1-1 1
11.1.1.1 Fission and Corrosion Products 11.1-1 I
1 11.1.1.2 Tritium Production and Release to the l
Reactor Coolant 11.1-1 1
l 11.1.1.3 Activation of Water 11.1-2 1
11.1.2 Secondary Coolant Activity 11.1-2 1
11.1.3 Argon-41 Production in the Containment Atmosphere 11.1-3 1
11.1.4 Volume Control Tank Vapor Space Activity 11.1-3 I
11.1.5 Gaseous Releases to the Environment 11.1-3 I
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TABLE OF CONTENTS (Continued)
Reference SAR Section Section Title Page Status 11.1.6 Radioactive Releases to the Environment by the Liquid Pathway 11.1-4 1
11.1.7 References 11.1-4 I
11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2-1 1
11.2.1 Design Bases 11.2-1 I
11.2.1.1 Capacity 11.2-1 1
11.2.1.1.1 Pump Failure 11.2-2 1
11.2.1.1.2 Filter, Strainer, or Demineralizer Plugging 11.2-2 1
11.2.1.1.3 Waste Evaporator Failure 11.2-2 1
11.2.1.1.4 High Leakage Rate 11.2-3 1
11.2.1.1.5 Refueling 11.2-3 1
11.2.1.2 Controlled Release of Radioactivity 11.2-4 I
11.2.1.2.1 Expected Releases 11.2-5 I
11.2.1.2.2 Off-Normal Operation 11.2-5 I
11.2.1.3 Equipment Design 11.2-5 I
11.2.2 System Descriptions 11.2-5 I
11.2.2.1 Reactor Coolant Drain Tank Subsystem 11.2-7 1
11.2.2.2 Drain Channel A Subsystem 11.2-8 I
11.2.2.3 Drain Channel B Subsystem 11.2-9 I
O' 11.2.2.4 Spent Resin Handling Subsystem 11.2-12 1
11.2.2.5 Liquids From Sources Other Than the Liquid Waste Processing System 11.2-13 I
11.2.2.5.1 Steam Generator Blowdown Processing System 11.2-13 I
s 11.2.2.5.2 Boron Recycle System 11.2-13 III 11.2.2.5.3 Turbine Building Drain System 11.2-13 II 11.2.2.6 Equipment Description 11.2-13 1
11.2.2.6.1 Pumps 11.2-14 I
11.2.2.6.2 Tanks 11.2-16 I
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t TABLE OF CONTENTS (Continued)
Reference SAR Section Section Title Page Status 11.2.2.6.3 Reactor Coolant Drain Taak Heat Exchanger 11.2-19 I
11.2.2.6.4 Demineralizers 11.2-20 I
j 11.2.2.6.5 Filters 11.2-21 1
11.2.2.6.6 Strainers 11.2.22 1
11.2.2.6.7 Waste Evaporator 11.2-22 1
11.2.2.7 Instrumentation Design 11.2-22 1
11.2.2.8 Operating Procedures 11.2-23 I
i 11.2.2.8.1 Reactor Coolant Drain Tank Subsystem Recirculation 11.2-23 1
11.2.2.8.2 Drain Channel A Subsystem Operation 11.2-25 1
11.2.2.8.3 Drain Channel B Subsystem Operation 11.2-26 1
11.2.2.8.4 Spent Resin Handling Subsystem 11.2-27 I
i 11.2.3 Radioactive Releases 11.2-29 I
11.2.3.1 Criteria for Discharge, Recycle, or Further i
Treatment of-Liquid Waste 11.2-29 I
11.2.3.2 Estimated Releases 11.2-30 1
i 11.2.3.2.1 Boron Recycle System (BRS) 11.2-31 I
i 11.2.3.2.2 Liquid Waste Processing System (LWPS) 11.2-31 1
11.2.3.2.3 Steam Generator Blowdown Processing System i
(SGBPS) 11.2-33 III 11.2.3.2.4 Condensate Cleanup System 11.2-33 III 11.2.3.2.5 Turbine Building Floor Drains 11.2-33 III 11.2.4 References 11.2-34 1
O 11.3 GASEOUS WASTE PROCESSING SYSTEM (GWPS) 11.3-1 I
i 11.3.1 Design Bases 11.3-1 1
11.3.1.1 Source Terms 11.3-1 1
11.3.1.2 Expected Releases and Doses 11.3-2 I
l 11.3.1.3 Accommodation of Surges 11.3-2 I
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TABLE OF CONTENTS (Continued)
Reference SAR Section Section Title Page Status 11.3.1.4 System Leakage 11.3-3 1
11.3.1.5 Monitoring Releases 11.3-3 1
11.3.1.6 Control of Releases due to Operator Error or Equipment Malfunction 11.3-3 1
11.3.1.7 Protection from Explosion 11.3-3 1
11.3.1.8 Component Design Parameters 11.3-4 1
11.3.1.9 Seismic and Safety Classification 11.3-4 I
11.3.2
System Description
11.3-4 I
11.3.2.1 System Operation 11.3-6 1
11.3.2.1.1 Normal VCT Purge Flow Processing 11.3-6 I
11.3.2.1.2 Equipment Vent Gas Processing 11.3-8 I
11.3.2.1.3 Startup 11.3-9 I
11.3.2.l.4 Shutdown and Degassing of the RCS 11.3-9 1
11.3.2.2 Component Description 11.3-9 I
11.3.2.2.1 Ref rigerated Waste uas Dryer 11.3-10 1
11.3.2'2.2 Charcoal Guard Beds 11.3-10 1
11.3.2.2.3 Charcoal Adsorption Tanks 11.3-11 I
11.3.2.2.4 Charcoal Fines Filter 11.3-11 I
11.3.2.2.5 Gas Surge Tank 11.3-11 1
O 11.3.2.2.6 Recycle Holdup Tank Vent Compressor 11.3-11 1
11.3.2.2.7 Recycle Line Compressors 11.3-12 1
11.3.2.3 Instrumentation and Control 11.3-12 I
Flow Instrumentation 11.3-13 1
O 11.3.2.3.1 11.3.2.3.2 Pressure Instrumentation 11.~ 3-13 I
11.3.2.3.3 Gas Analysis Instrumentation 11.3-16 I
11.3.2.3.4 Radiation Instrumentation 11.3-17 I
11.3.3 Radioactive Releases 11.3-17 I
O 11.3.3.1 Discharge. Requirements 11.3-17 I
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TABLE OF CONIEN15 (Continued)
I Reference SAR Section Section Title Page Status 11.3.3.2 Estimated Releases 11.3-17 I
11.3.3.3 Release Points for Determination of Dilution Factors 11.3-18 I
11.3.3.4 Effluent Concentration and Dilution Factors 11.3-18 1
11.3.3.5 Estimated Doses from Atmospheric Releases 11.3-18 I
I 11.4 SOLIO WASTE PROCESSING SYSTEM 11.4-1 III 11.4.1 Design Bases 11.4-1 III 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5-1 1
11.5.1 Design 8ases 11.5-1 1
6 11.5.2
System Description
11.5-2 I
11.5.2.1 Digital Radiation Monitoring System 11.5-2 1
11.5.2.2 Monitor Description 11.5-3 1
11.5.2.3 Monitor Functions 11.5-4 1
11.5.2.4 Alarm Setpoints 11.5-15 1
11.5.2.5 Inservice Inspection, Calibration, and Maintenance 11.5-16 1
11.5.3 Effluent Monitoring and Sampling 11.5-16 I
11.5.3.1 Plant Sampling System 11.5-16 I
p 11.5.3.2 Sampling Requirements for Process and Effluent Radiation Monitoring and Sampling 11.5-18 1
11.5.5 Post-Accident Radiation Monitoring (PAMS) 11.5-18 I
RADIATION PROTECTION 12.0-1 NA O
12.0 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 11 16.0 TECHNICAL SPECIFICATIONS 16.0-1 NA O
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l TAELE OF CONTENTS (Continued) l Reference SAR Section Section Title Page Status 17.0 QUALITY ASSURANCE 17.0-1 11 17.1 QUALITY ASSURANCE DURING DESIGN AND 17.0-1 11 CONSTRUCTION 17.
1.1 REFERENCES
17.0-1 II O
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TABLE OF CONTENTS (Continued) i I
KEY TO " REFERENCE SAR SECTION STATUS" COLUMN:
' O Category 1 i
Those sections which are complete and for which no additional information is to be provided for the PDA application.
l Category II i
Those sections which are complete insofar as providing material relevant to l
1 i
this system module but for which additional information will be provided in 4
support of subsequent modules.
l Category III I
i Those-sections for which information on interfacing systems will be provided at.a later-date.
N. A l
Those sections for which categorization is not applicable.
Only the section titles are included for clarity.
1 i O 1
I i
I J
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TABLE OF CONTENTS (Continued)
LIST OF TABLES Number Title Page
- 1. 6 -1 Material Incorporated by Reference 1.6-2 11.1-1 Parameters Used to Describe the Reactor System-Realistic Basis 11.1-5 11.1-2 Specific Activities in Principal Fluid Streams-Realistic Basis 11.1-7 11.1-3 Tritium Production 11.1-10 11.1-4 Volume Control Tank Vapor Space Activities 11.1-11 11.2-1 Parameters Used in the Calculation of Estimated Activity in Liquid Wastes 11.2-35 11.2-2 Equipment Design Parameters 11.2-38 11.2-3 Range of Measured Decontamination Factors for Selected Isotopes 11.2-4B 11.2-4 Parameters Specified by Regulatory Guide 1.112 Appendix B 11.2-49 11.2-5 Calculated Releases of Radioactive Materials in Liquid Effluents Assuming Expected Fuel Leakage 11.2-53 11.2-6 Radioactive Liquid Releases from Westinghouse-Designed PWR Plants (Zircaloy Fuel Cladding) 11.2-56 11.3-1 GWPS Component Design Parameters 11.3-20 Expected Annual Average Release of Airborne 0
11.3-2 Radionuclides 11.3-23 11.3-3 Comparison of Calculated Maximum Offsite Airborne Concentration with 10CFR20 Assuming Expected Fuel Leakage 11.3-24 O
11.3-4 Estimated Annual Doses to an Individual From Gaseou! Effluents Assuming Continuous Presence at the Site Boundary 11.3-25 O
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TABLE OF CONTENTS (Continued)
LIST OF TABLES i
Number Title P_a_g e i
I 11.5-1 Design Parameters for Process and Ef fluent Radiation Monitors 11.5-22 11.5-2 Detector Requirements for Process and Ef fluent Radiation Monitors 11.5-28 11.5-3 Conditions of Service for Process and Effluent Radiation Monitors 11.5-32 l
11.5-4 Alarm Setpoints for Process and Effluent Radiation Monitors 11.5-36 11.5-5 Airborne Radiological Sampling Requirements for PERMS 11.5-37 11.5-6 Liquid Radiological Sampling Requirements for PERMS 11.5-40 11.5-7 Design Parameters for Post-Accident Radiation Monitors 11.5-42 11.5-8 Detector Requirements for Post-Accident Radiatio'n 3
f Monitors 11.5-44 i
11.5-9 Conditions of Service for Post-Accident Radiation Monitors 11.5-45 j
11.5-10 Alarm Setpoints for Post-Accident Radiation Monitors 11.5-46 i
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i-j TABLE OF CONTENTS (Continued) t i
LIST OF FIGURES i
i i
f Number Title i
I 11.2-1 Liquid Radioactive Waste Processing System Flow Diagrams (Sheets 1-4) 11.2-2 Liquid Waste Management Systems Process Flow l
Diagrams (Sheets 1-6) l 11.3-1 Charcoal Adsorption Waste Processing System (Gas)
Flow Diagrams (Sheets 1-2) l 11.5-1 Radiation Monitoring System Block Diagram 1
l 11.5-2 Safety Subsystem Block Diagram 11.5-3 PERMS Communication Console i
11.5-4 Three-Channel Airborne Monitoring Assembly l
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