ML20053A547
| ML20053A547 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 04/28/1982 |
| From: | Sherwood G GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| JNF-22-82, MFN-059-82, MFN-59-82, NUDOCS 8205260206 | |
| Download: ML20053A547 (31) | |
Text
GENER AL h ELECTRIC
/-
NUCLEAR POWER SYSTEMS DIVISION JNF 22-82 GENERAL ELECTRIC COM?ANY,175 CURTNER AVE., SAN JOSE, CAllFORNIA 95125 MFN 059-82 MC 682, (408) 925-5040 April 28,1982 U
e U.S. Nuclear Regulatory Commission a
b Office of Nuclear Reactor Regulation f>
pg Washington, DC 20555
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-7' Attention:
D. G. Eisenhut, Director M
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Division of Licensing j
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Gentlemen:
6
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II);
DOCKET NO. STN 50-447 losed please find 3 original copies (transmitted under separate cover i
60 c rmed copies) of Amendment No. 3 to the 238 General Electric dard Safety An sis Report (GESSAR II) for the above numbered applic on.
Amendment No. 3 a s GESSAR II by furnishing updated ng and instrumen-tation diagrams and e rical system logic diagra, y correcting typogra-phical errors and by clarl
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portions of th xt where obvious discre-pancies exist.
It is not the nt to co ct all such errors or omissions within Amendment No. 3.
Rather, mo tions thought to be significant are included.
Other modifications wi e
itted throughout the course of the review both in amandment sponding to iew questions and in similar voluntary submittal a ts, if needed.
Pursuant to Revi n 3 of Regulatory Guide 1.70, three se f large-scale copies of t SSAR II piping and instrumentation and electri system logic d' ams are being transmitted under separate cover.
Each s f
f dra
- gs listed in GESSAR II Table 1.7-1, are callated with respect to clear Island drawing numbers.
l Also transmitted under separate cover are index tabs and two new volumes P
(1Ajnd 23A) for use in future amendments. iflts s'tclud'd 85 TL4/t e/ Ort /NS g
hstuct en fi,$e for Hu,*>f g pa gaolers Sincerely, O
O 1
Cy enn ervo er Nuclear Safety and Licensing Operation g
e GGS:rf:csc/202P eq M3 Attachments o
04 co cc:
R. L. Tedesco (w/o att.)
H. J. Faulkner (w/o att.)
L. 5. Gifford (w/o att.)
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i l-i GESSAR II SSAR HOLDERS 4
Please replace table of contents in front of each GESSAR II i
volume with revised tables contained in cellophane wrapped I
l package.
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1 GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. O i
i
SUMMARY
TABLE OF CONTENTS r
Chapter /
Section Title Volume 1
INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 4
1.1 INTRODUCTION
1 l.1.1 Type of License Required 1.1.2 Identification of Applicant 1.1.3 Number of Plant Units 1.1.4 Description of Location f
1.1.5 Type of Nuclear Steam Supply System
]
1.1.6 Type of Containment l
1.1.7 Core Thermal Power Levels i
1.1.8 Scheduled Completion and Operation Dates 1.2 GENERAL PLANT DESCRIPTION 1
1.2.1 Principal Design Criteria 1.2.2 Plant Description l
i l.3 COMPARISON TABLES 1
s j
1.3.1 Comparisons with Similar Facility Designs 1.3.2 Compariscas of Final and Preliminary Information I
1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1
l 1.4.1 Applicant i
1.4.2 Architect Engineer - Nuclear Island
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Design 1.4.3 Nuclear Steam Supply System Supplier l
1.4.4 Turbine-Generator Vendor I
l 1.4.5 Consultants 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1
l 1.5.1 Current Development Programs l
1.5.2 PSAR Commitment Items 1.6 MATERIAL INCORPORATED BY REFERENCE 1
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 1.7 DRAWINGS AND OTHER DETAILED INFORMATION 1
1.7.1 Electrical, Instrumentation, and Control Drawings 1.7.2 Piping and Instrumentation Diagrams 1.7.3 Abbreviations and Symbols 1.8 CONFORMANCE TO NRC REGULATORY GUIDES 1
1.8.1 Compliance Assessment Method 1.9 STANDARD DESIGNS 1
1.9.1 Interfaces 1.9.2 Exceptions APPENDIX 1A RESPONSE TO TMI-RELATED MATTERS 1A APPENDIX 1B UNRESOLVED SAFETY ISSUES 1A APPENDIX 1C RESPONSE TO NRC ADDITIONAL GUIDANCE lA 0
iv 2
a GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued) 1
(
Chapter /
Section Title Volume 2
SITE CHARACTERISTICS 2.0
SUMMARY
1A
)
2.1 GEOGRAPHY AND DEMOGRAPHY 1A
]
3 2.1.1 Site Location and Description 2.1.2 Exclusion Area Authority and Control 2.1.3 Population Distribution 2.2 NEARBY INDUSTRIAL, TRANSPORTATION AND MILITARY FACILITIES lA 2.2.1 Location and Routes 2.2.2 Descriptions 2.2.3 Evaluation of Potential Accidents 2.3 METEOROLOGY 1A 2.3.1 Regional Climatology 2.3.2 Local Meteorology 2.3.3 Onsite Meteorological Measurements Program 2.3.4 Short-Term Atmospheric Diffusion Estimates 2.3.5 Long-Term Atmospheric Diffusion Estimates 2.4 HYDROLOGIC ENGINEERING 1A 2.4.1 Hydrologic Description 2.4.2 Floods 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4.4 Potential Dam Failures, Seismically Induced 2.4.5 Probable Maximum Surge and Seiche Flooding 2.4.6 Probable Maximum Tsunami Flooding 2.4.7 Ice Effects 2.4.8 Cooling Water Canals and Reservoirs 2.4.9 Channel Diversions t
2.4.10 Flooding Protection Requirements v
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume t
i 2.4.11 Low Water Considerations 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents in Surface Waters 4
2.4.13 Ground Water 2.4.14 Technical Specifications and Emergency Operation Requirements 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING 1A 2.5.1 Basic Geologic and Seismic Information 2.5.2 Vibratory Ground Motion 2.5.3 Surface Faulting 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 2.5.6 Embankments and Dams vi
GESSAR II 22A7007 238 NUCLEAR ISLAND Rav. 3
SUMMARY
TABLE OF CONTENTS (Continued)
(
Chapter /
Section Title Volume 4
REACTOR 4.1
SUMMARY
DESCRIPTION 9
4.1.1 Reactor Vessel 4.1.2 Reactor Internal Components 4.1.3 Reactivity Control Systems 4.1.4 Analysis Techniques 4.1.5 References 4.2 FUEL SYSTEM DESIGN 9
4.2.1 Design Bases 4.2.2 Description and Design Drawings 4.2.3 Design Evaluation 4.2.4 Testing, Inspection and Surveillance Plans 4.2.5 References
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4.3 NUCLEAR DESIGN 9
4.3.1 Design Bases 4.3.2 Description 4.3.3 Analytical Methods 4.3.4 Changes 4.3.5 References 4.4 THERMAL - HYDRAULIC DESIGN 9
4.4.1 Design Basis 4.4.2 Description of Thermal Hydraulic Design of the Reactor Core l
4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System 4.4.4 Evaluation 4.4.5 Testing and Verification 4.4.6 Instrumentation Requirements 4.4.7 References
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rnv. 3
SUMMARY
TABLE OF CONTENTS (Continued) f Chapter /
Section Title Volume 4.5 REACTOR MATERIALS 9
4.5.1 Control Rod System Structural Materials 4.5.2 Reactor Internal Materials 4.5.3 Control Rod Drive Housing Supports 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS 9
4.6.1 Information for Control Rod Drive System (ChDs) 4.6.2 Evaluations of the CRDs 4.6.3 Testing and Verification of the CRDs 4.6.4 Information for Combined Performance of Reactivity Systems 4.6.5 Evaluation of Combined Performance 4.6.6 References APPENDIX 4A CONTROL ROD PATTERNS AND ASSOCIATED POWER DISTRIBUTION FOR TYPICAL BWR 9
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GESSAR II 22A7007 238 NUCLEAR ISLAND R v. O
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 6
ENGINEERED SAFETY FEATURES 6.0 GENERAL ll 6.1 ENGINEERED SAFETY FEATURE MATERIALS 11 6.1.1 Metallic Materials 6.1.2 Organic Materials 6.2 CONTAINMENT SYSTEMS 11 6.2.1 Containment Functional Design 6.2.2 Containment Heat Removal System 6.2.3 Secondary Containment Functional Design 6.2.4 Containment Isolation System 6.2.5 Combustible Gas Control in Containment 6.2.6 Containment Leakage Testing 6.2.7 Suppression Pool Makeup System 6.2.8 References 6.3 EMERGENCY CORE COOLING SYSTEMS 11 6.3.1 Design Bases and Summary Description 6.3.2
System Design
6.3.3 ECCS Performance Evaluation 6.3.4 Tests and Inspections 6.3.5 Instrumentation Requirements 6.3.6 References 6.4 HABITABILITY SYSTEMS 11 l
6.4.1 Design Basis 6.4.2
System Design
i 6.4.3 Systems Operational Procedures 6.4.4 Design Evaluations 6.4.5 Testing and Inspection 6.4.6 Instrumentation Requirements 6.4.7 Nuclear Island / BOP Interface
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f GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 11 6.5.1 Engineered Safety Feature Filter Systems
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6.5.2 Containment Spray Systems 6.5.3 Fission Product Control Systems 6.5.4 Ice Condensers as a Fission Product Control System 6.5.5 References 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 11 6.6.1 Components Subject to Examination 6.6.2 Accessibility 6.6.3 Examination Techniques and Procedures 6.6.4 Inspection Intervals 6.6.5 Examination Categories and Requirements 6.6.6 Evaluation of Examination Results 6.6.7 System Pressure Tests 6.6.8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures 6.7 MAIN STEAM POSITIVE LEAKAGE CONTROL SYSTEM (MSPLCS) 11 6.7.1 Design Bases 6.7.2
System Description
6.7.3 System Evaluation 6.7.4 Inspection and Testing 6.7.5 Instrumentation Requirements 6.8 PNEUMATIC SUPPLY SYSTEM ll 6.8.1 Design Bases 6.8.2
System Description
6.8.3 System Evaluation 6.8.4 Inspection and Testing Requirements 6.8.5 Instrumentation Requirements APPENDIX 6A IMPROVED DECAY HEAT CORRELATION FOR LOCA ANALYSIS ll xvi
GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 14 7.7.1 Description 7.7.2 Analysis 7.7.3 References
-RPV Instrumentation
-Leak Detection
-Rod Control &
-Rod Block Trip Information
-Fire Protection
-Recirculation Flow
-Drywell Chiller &
Control Cooling
-Feedwater Control
-Plant Instrument Air
-Performance Moni-
-Neutron Monitoring toring System
-Radwaste 14 7.8 NI/ BOP INTERFACES 7.8.1 Essential Service Water (Supply)
System Instrumentation and Controls 7.8.2 Diesel Generator Fuel Oil Transfer System APPENDIX 7A I&C ELEMENTARY DIAGRAMS 15,16,17 )
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued) 1 Chapter /
Section Title Volume 8
ELECTRIC POWER
8.1 INTRODUCTION
18 8.1.1 Utility Grid Description l
8.1.2 Onsite Electric Power System 8.1.3 Design Bases 8.2 OFFSITE POWER SYSTEM 18 8.2.1 Description 8.2.2 Analysis 8.2.3 Nuclear Island - BOP Interface 8.3 ONSITE POWER SYSTEMS 18 8.3.1 AC Power Systems 8.3.2 DC Power Systems 8.3.3 Fire Protection of Cable Systems 1
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 9
AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 19 9.1.1 New Fuel Storage (High Density) 9.1.2 Spent Fuel Storage (High Density) 9.1.3 Fuel Pool Cooling and Cleanup System 9.1.4 Fuel-Handling System 9.1.5 References 9.2 WATER SYSTEMS 19 9.2.1 Essential Service Water (ESW) System 9.2.2 Closed Cooling Water System 9.2.3 Demineralized Water Makeup System 9.2.4 Potable and Sanitary Water Systems 9.2.5 Ultimate Heat Sink 9.2.6 Condensate Storage Facilities and Distribution System 9.2.7 Plant Chilled Water Systems 9.2.8 Heated Water Systems 9.2.9 Nuclear Island / BOP Interfaces 9.3 PROCESS AUXILIARIES 19 9.3.1 Compressed Air Systems 9.3.2 Process Sampling System 9.3.3 Floor and Equipment Drainage Systems 9.3.4 Chemical and Volume Control System (PWR) 9.3.5 Standby Liquid Control System 9.4 AIR CONDITIONING, HEATING, COOLING AND VENTILATION SYSTEM 19 9.4.1 Control Room HVAC System 9.4.2 Fuel Building HVAC System 9.4.3 Auxiliary Building HVAC Systems 9.4.4 Turbine Building Area Ventilation System 9.4.5 Reactor Building HVAC System i
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3 I
SUMMARY
TABLE OF CONTENTS (Continued) i Chapter /
Section Title Volume 9.4.6 Radwaste Building HVAC System I
9.4.7 Diesel-Generator Buildings HVAC Systems 9.5 OTHER AUXILIARY SYSTEMS 19 9.5.1 Fire Protection System 9.5.2 Communications Systems 9.5.3 Lighting Systems 9.5.4 Diesel-Generator Fuel Oil Storage and Transfer System 9.5.5 Diesel-Generator Cooling Water System 9.5.6 Diesel-Generator Starting Air System 9.5.7 Diesel Engine Lubrication System 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5.9 Suppression Pool Cleanup System 9.5.10 Nuclear Island - BOP Interface APPENDIX 9A FIRE HAZARD ANALYSIS 20 l
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 10 STEAM AND POWER CONVERSION SYSTEM 10.1
SUMMARY
DESCRIPTION 21 10.2 TURBINE GENERATOR 22 10.2.1 Design Bases Functional Limitations by Design or Operational Charac-teristics of the Reactor Coolant System 10.2.2
System Description
10.2.3 Turbine Disk Integrity 10.2.4 Evaluation 10.3 MAIN STEAM SUPPLY 23 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 24 10.4.1 Main Condensers 10.4.2 Condenser Air Removal System 10.4.3 Main Condenser Evacuation System 10.4.4 Turbine Bypass System 10.4.5 Circulating Water System 10.4.6 Condensate Cleanup System 10.4.7 Condensate and Feedwater System 10.4.8 Steam Generator Blowdown System (PWR) 10.4.9 Auxiliary Feedwater System (PWR) l l
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
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Chapter /
Section Title Volume 11 RADIOACTIVE WASTE MANAGEMENT
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11.1 SOURCE TERMS 21 11.1.1 Fission Products 11.1.2 Activation Products 11.1.3 Tritium 11.1.4 Fuel Fission Production Inventory and Fuel Experience 11.1.5 Process Leakage Sources 11.1.6 Radwaste System 11.1.7 Radioactive Sources in the Gas Treatment System 11.1.8 Source Terms for Component Failures 11.1.9 Other Releases 11.1.10 References 11.2 LIQUID WASTE MANAGEMENT SYSTEM 21 11.2.1 Design Basis 11.2.2 System Descriptions 11.2.3 Estimated Releases 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS 21 11.3.1 Design Bases 11.3.2 Main Condenser Steam Jet Air Ejector Low-Temp RECHAR System Description 11.3.3 RECHAR System Operating Procedure 11.3.4 Radioactive Releases 11.3.5 References 11.4 SOLID WASTE MANAGEMENT SYSTEM 21 11.4.1 Design Bases 11.4.2
System Description
i Xxiv
GESSAR II 22A7007 238 NUCLEAR ISLANE-Rev. 3
SUMMARY
TABLE OF CCNTENTS (Continued)
Chapter /
Section Title Volume 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 21 11.5.1 Design Bases 11.5.2
System Description
11.5.3 Effluent Monitoring and Sampling a
11.5.4 Process Monitoring and Sampling i
11.5.5 Calibration and Maintenance d
11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 21 1
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22A7007 GESSAR II 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 12 RADIATION PROTECTION 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES
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ARE AS LOW AS REASONABLY ACHIEVABLE (ALARA) 21 12.1.1 Policy Considerations 12.1.2 Design Considerations 12.1.3 Operational Considerations 12.2 RADIATION SOURCES 21 12.2.1 Contained Sources 12.2.2 Airborne Radioactive Material Sources 12.2.3 References 12.3 RADIATION PROTECTION DESIGN FEATURES 21 12.3.1 Facility Design Features 12.3.2 Shielding 12.3.3 Ventilation 12.3.4 Area Radiation and Airborne Radioactivity Monitors 12.3.5 References 12.4 DOSE ASSESSMENT 21 12.5 HEALTH PHYSICS PROGRAM 21 xxvi
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 13 CONDUCT OF OPERATIONS 21
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13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1.1 Management and Technical Support Organization 13.1.2 Operating Organization 13.1.3 Qualifications of Nuclear Plant Personnel 13.2 TRAINING 13.2.1 Plant Staff Training Program 13.2.2 Replacement and Retraining 13.2.3 Applicable NRC Documents 13.3 EMERGENCY PLANNING 13.3.1 Preliminary Planning 13.3.2 Emergency Plan 13.3.3 BOP Interface 13.4 REVIEW AND AUDIT 13.4.1 On-Site Review 13.4.2 Independent Review 13.4.3 Audit Program 13.5 PLANT PROCEDURES 13.5.1 Administrative Procedures 13.5.2 Operating and Maintenance Procedures 13.6 INDUSTRIAL SECURITY 13.6.1 Preliminary Planning 13.6.2 Security Plan 13.6.3 BOP Interface xxvii
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 14 INITIAL TEST PROGRAM 14.1 TEST PROGRAM 22 14.1.1 Administrative Procedures (Testing) 14.1.2 Administrative Procedures (Modifications) 14.1.3 Test Objectives and Procedures 14.1.4 Fuel Loading and Initial Operation 14.1.5 Administrative Procedures (System Operation) l 14.2 SPECIFIC INFORMATION TO BE INCLUDED IN SAFETY ANALYSIS REPORTS 22 14.2.1 Summary of Test Program and Objectives 14.2.2 Organization and Staffing 14.2.3 Test Procedures 11.2.4 Conduct of Test Program 14.2.5 Review, Evaluation and Approval of Test Results i
14.2.6 Test Records 14.2.7 Conformance of Test Programs with Regulatory Guides 14.2.8 Utilization of Reactor Operating and Testing Experiences in the Develop-ment of Test Program 14.2.9 Trial Use of Plant Operating and Emergency Procedures 14.2.10 Initial Fuel Loading and Initial Criticality 14.2.11 Test Program Schedule 14.2.12 Individual Test Descriptions xxviii
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
.Section Title Volume 15 ACCIDENT ANALYSES 15.0 GENERAL 23 15.0.1 Nuclear Safety Operational Analysis 15.0.2 Analytical Objective 15.0.3 Analytical Categories 15.0.4 Event Evaluation 15.0.5 Identification of Causes and Frequency Classification 15.0.6 References 15.1 DECREASE IN REACTOR COOLANT TEMPERATURE 23 15.1.1 Loss of Feedwater Heating 15.1.2 Feedwater Controller Failure -
Maximum Demand l
15.1.3 Pressure Regulator Failure - Open 15.1.4 Inadvertent Safety / Relief Valve Opening 15.1.5 Spectrum of Steam System Piping Failures Inside and Outside of Containment in a PWR 15.1.6 Inadvertent RHR Shutdown Cooling Operation 15.2 INCREASE IN REACTOR PRESSURE 23 15.2.1 Pressure Regulator Failure - Closed 15.2.2 Generator Load Rejection 15.2.3 Turbine Trip 15.2.4 MSLIV Closures 15.2.5 Loss of Condenser Vacuum 15.2.6 Loss of Offsite AC Power 15.2.7 Loss of Feedwater Flow 15.2.8 Feedwater Line Break 15.2.9 Failure of RHR Shutdown Cooling 15.2.10 References t
XXiX
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE 23
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15.3.1 Recirculation Pump Trip 15.3.2 Recirculation Flow Control Fai3ure -
Decreasing Flow 15.3.3 Recirculation Pump Seizure 15.3.4 Recirculation Pump Shaft Break 15.3.5 References 23 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 15.4.1 Rod Withdrawal Error - Low Power 15.4.2 Rod Wi.thdrawal Error at Power 15.4.3 Control Rod Maloperation (System Malfunction or Operator Error) 15.4.4 Abnormal Startup of Idle Recirculation Pump 15.4.5 Recirculation Flow Control with Increasing Flow 15.4.6 Chemical and Volume Control System Malfunctions 15.4.7 Misplaced Bundles Accident 15.4.8 Spectrum of Rod Ejection Assemblies 15.4.9 Control Rod Drop Accident (CRDA) 23 15.4.10 References 15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5.1 Inadvertent HPCS Startup 15.5.2 Chemical Volume Control System Malfunction (or Operator Error) 15.5.3 BWR Transients Which Increase Reactor Coolant Inventory XXX
GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 15.6 DECREASE IN REACTOR COOLANT INVENTORY 23 15.6.1 Inadvertent Safety / Relief Valve Opening 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment 15.6.3 Steam Generator Tube Failure 15.6.4 Steam System Piping Break Outside Containment 15.6.5 Loss-of-Coolant Accidents (Resulting from Spectrum of Postulated Piping Breaks Within the Reactor Coolant Inside Pressure Boundary)
Containment 15.6.6 Feedwater Line Break - Outside Containment 15.6.7 References 15.7 RADIOACTIVE RELEASE FROM SUBSYSTEMS AND COMPONENTS 23 15.7.1 Radioactive Waste System Leak or Failure 15.7.2 Liquid Radioactive System Failure 15.7.3 Postulated Radioactive Releases Due to Liquid Radwaste Tank Failure 15.7.4 Fuel-Handling Accident I
15.7.5 Spent Fuel Cask Drop Accidents I
15.7.6 References APPENDIX 15A PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS 23 APPENDIX 15B BWR/6 GENERIC ROD WITHDRAWAL ERROR ANALYSIS 23 APPENDIX 15C FAILURE MODES AND EFFECTS ANALYSES 23A APPENDIX 15D SEVERE ACCIDENTS 23A
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
)
Chapter /
Section Title Volume 16 STANDARD TECHNICAL SPECIFICATIONS FOR GENERAL ELECTRIC BOILING WATER REACTORS i
16.1 DEFINITIONS 24
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16.1.1 Action 16.1.2 Average Planar Exposure 16.1.3 Average Planar Linear Heat Generation Rate 16.1.4 Channel Calibration 16.1.5 Channel Check 16.1.6 Channel Functional Test 16.1.7 Core Alteration 16.1.8 Critical Power Ratio 16.1.9 Dose Equivalent I-131 16.1.10 E-Average Disintegration Energy 16.1.11 Emergency Core Cooling System (ECCS)
Response Time 16.1.12 Frequency Notation 16.1.13 Identified Leakage 16.1.14 Isolation System Response Time 16.1.15 Limiting Control Rod Pattern i
16.1.16 Linear Heat Generation Rate 16.1.17 Logic System Functional Test 16.1.18 Maximum Total Peaking Factor 16.1.19 Minimum Critical Power Ratio 16.1.20 Operable - Operability 16.1.21 Operational Condition (Condition)
I 16.1.22 Physics Test 16.1.23 Pressure Boundary Leakage 16.1.24 Primary Containment Integrity 16.1.25 Rated Thermal Power 16.1.26 Reactor Protection System Response Time 16.1.27 Recirculation Pump Trip System Response Time xxxii I
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rnv. 3
SUMMARY
TABLE OF CONTENTS (Continued)
Chapter /
Section Title Volume 16.1.28 Reportable Occurrence 16.1.29 Rod Density 16.1.30 Secondary Containment Integrity 16.1.31 Shutdown Margin 16.1.32 Staggered Test Basis 16.1.33 Thermal Power 16.1.34 Total Peaking Factor 16.1.35 Unidentified Leakage 16.2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 24 16.2.1 Safety Limits 16.2.2 Limiting Safety System Settings 16.B2 SAFETY LIMITS 24 16.B2.1 Bases 16.B2.2 Limiting Safety System Settings 16.3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 24 16.3/4.0 Applicability 16.3/4.1 Surveillance Requirements 16.3/4.2 Power Distribution Limits 16.3/4.3 Instrumentation 16.3/4.4 Reactor Coolant System 16.3/4.5 Emergency Core Cooling Systems 16.3/4.6 Containment Systems 16.3/4.7 Plant Systems 16.3/4.8 Electrical Power Systems 16.3/4.9 Refueling Operations 16.3/4.10 Special Test Exceptions
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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3
SUMMARY
TABLE OF CONTENTS (Continued)
)
Chapter /
Section Title Volume 16.B3/4.0 Applicability 16.B3/4.1 Reactivity Control Systems 16.B3/4.2 Power Distribution Limits 16.B3/4.3 Instrumentation 16.B3/4.4 Reactor Coolant System 16.B3/4.5 Emergency Core Cooling System 16.B3/4.6 Containment Systems 16.B3/4.7 Plant Systems 16.B3/4.8 Electrical Power Systems 16.B3/4.9 Refueling Operations 16.B3/4.10 Special Test Exceptions 16.5 DESIGN FEATURES 24
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16.5.1 Site 16.5.2 Containment 16.5.3 Reactor Core 16.5.4 Reactor Coolant System 16.5.5 Meteorological Tower Location 16.5.6 Fuel Storage 16.5.7 Component Cyclic or Transient Limit xxxiv
GESSAR II 22A7007 238 NUCLEAR ISLAND Rav. 3 l
SUMMARY
TABLE OF CONTENTS (Continued)
.'tapte r/
4 Section Title Volume 17 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 24 17.2 QUALITY ASSURANCE DURING THE OPERATING PHASE 24 1
i l
l t
XXXV/XXXVi
..