ML20030A333
| ML20030A333 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/14/1961 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8101090309 | |
| Download: ML20030A333 (429) | |
Text
MJGlT21 so -/sg+=w
~qi
/m y
O'<'27"'dT FINAL aw a
HAZARDS
SUMMARY
REPORT a ^ u),
\\
for BIG ROCK POINT PLANT
(
g(
')*
. U'
(
,.2, ',,, ' S '[.
'j' V
..: 1 i~
I D E C i '. ' '
I '
VOLUME ONE PLANT TECHNICAL DESCRIPTION AND l
SAFEGUARD EVALUATION l
6\\II q/in
(
%); _-
l Jb
$N_<y
/. \\,
1a..
om
'( ; -/v ~
,u. y, /@$
, N, /)
o
-\\ N W
\\-
Kf' NOVEMBER 14,1961
' /1g s
-- ms7
{, hij,,. ;,,y,,,i [, 0.; s 1
- Vis sa L i
-- s VOt.UME 1 OF 2 q go 03d c
FINAL HAZA RDS
SUMMARY
REPORT Inclusive Contents TAB VOLUME ONE:
Technical Description & Safeguard Evaluation Introduction & Conclusions 1
i Plant Site & Environment 2
Containment 3
Reactor 4
(
Reactor System Equipment 5
Power System Equipment 6
Instrumentation 7
'(
Nuclear, The rmal, & Hydraulic Characteristics 8
Radioactive Waste Disposal 9
Research & Development Program 10 Operating Procedures 11 Safety Analysis 12 Maximum Credible Accident 13 i
VOLUME TWO:
PART I - ENGINEERING DRAWINGS
(
Plant Site & Layout A'
Equipment Location B
Containment Vessel Details C
(
Process Piping & Instrument Diagrams D
Instrumentation E
Reactor Vessel & Internals F
I Service Systems - Piping & Instrumentation G
Electrical Diagrams H
l Control Diagrams I
i Heat Balance J
J PART II - TOPICAL REPORTS Meteorology, Progress Report No.1 14 Geology and Hydrology 15 Seismoiegy 16 i
y
.w g
-ub se y
e-,
VOLUME ONE Table of Contents PAGE Section 1:
INTRODUCTION & CONCLUSIONS TAB-1 1.1 Purpose of Report 1
- 1. 2 Eackground 1
- 1. 3 ' Scope of Report 2
- 1. 4 Character of Report 2
- 1. 5 Conclusions From Report 2
i Section 2:
PLANT SITE & ENVIRONMENT TAB - 2 2.1 General Features 1
- 2. 2 Immediate Environs 4
g'
. 2. 3 Immediate Population 5
- 2. 4 Meteorology 9
(
- 2. 5 Geology & Ilydrology 10
- 2. 6 Seismology 10 Section 3:
CONTAINMENT TAB-3 3.1 General 1
- 3. 2 Design Criteria 1
3.3 Fire & Flood Protection 5
- 3. 4 Penetrations 5
- 3. 5 Isolation Valves 6
- 3. 6 Mis sile s 8
- 3. 7 Post-Incident Cooling 9
(
- 3. 8 Insulation 10
]
- 3. 9 Construction & Testing 11 l
Section 4:
REACTOR TAB-4 1
4.1 Reactor Vessel
- 4. 2 Reactor Core & Fuel 6
e
- 4. 3 Control Rods 12
- 4. 4 Control Rod Drives 17 i
4.5 Liquid Poison System 24
- 4. 6 Biological Shielding 26 Section 5:
REACTOR SYSTEM EQUIPMENT TAB-5 5.1 General Description of Equipment 1
- 5. 2 Steam Drum 1
- 5. 3 Recirculating Pumps 2
i
- 5. 4 Primary Loop Piping & Valves 4
- 5. 5 Safety Relief Valves 6
- 5. 6 Turbine & Bypass Control Systems 6
- 5. 7 Shutdown Cooling System 8
- 5. 8 Emergency Cooling System 9
- 5. 9 Core Spray Cooling System 10 5.10 Reactor Emergency Electric Power 11
- 5. 11 Reactor Cleanup System 12 5.12 Reactor Servicing Equipment 13
,.,ase
-me e
p 4'-
- 4M e'
r k.
1 PAGE
(
Section 6:
POWER SYSTEM EQUIPMENT TAB-6 f-6.1 Turbine Generator System 1
- 6. 2 Main Turbine Condenser 1
- 6. 3 Condensate & Feedwater System 2
- 6. 4 Auxiliary Cooling Water Systems 4
- 6. 5 Makeup Water System 5
- 6. 6 Instrument & Service Air System 5
- 6. 7 Electrical System 5
- 6. 8 Plant Services Systems 7
Section 7:
INSTRUMENTATION TAB-7 7.1 General Features 1
- 7. 2 Power Control 1
(
- 7. 3 Turbine Protection Devices 1
- 7. 4 Control at Startup 2
- 7. 5 Reactor Safety System 2
- 7. 6 Reactor Neutron Monitor System 10
- 7. 7 Control Rod System Instrumentation 13
- 7. 8 Liquid Poison System Control 14
- 7. 9 Reactor Instrumentation 15 7.10 Steam Supply System Instrumentation 16 7. 11 Fuel Rupture. Detection System 19 7.12 Process Radiation Monitoring 19 7,13 Area & Personnel Monitoring 21 i
Section 8:-
NUCLEAR; THERMAL, & HYDRAULIC CHARACTERISTICS TAB-8 8.1 Introduction 1
- 8. 2 Thermal & Hydraulic Characteristics 1
- 8. 3 Nuclear Characteristics 7
Section 9:
RADIOACTIVE WASTE DISPOSAL TAB-9 9.1 Airborne Wastes 1
- 9. 2 Liquid Wastes 9
9.3 Solid Waste 12 Section 10p RESEARCH & DEVELOPMENT PROGRAM TAB-10 10.1 General Considerations 1
- 10. 2 Development Program - Phase 1 4
10.3 Development Program - Phase II 11 Section 11:
OPERATING PROCEDURES TAB-ll
- 11. 1 Basic Operating Principles 1
- 11. 2 Procedural Safeguards 3
- 11. 3 Disaster Plans 6
- 11. 4 Preoperational Testing 8
- 11. 5 Initial Core Loading & Critical Tests 13
- 11. 6 Power Operation Test Program 16
- 11. 7 Normal Operation 18
- 11. 8 Procedures For R&D Program Testing 22
- 11. 9 Refueling 23 27
- 11. 1 0 Waste Disposal Systems Operation 11.11 Maintenance Principles 28
- 11. 1 2 Storage 29
PAGE S'ection 12:
SAFETY AN LYSIS TAB-12
(.
12.1 Safeguards Considerations 1
12.2 Conclusions 2
12.3-Dynamic Stability of Reactor 2
(
12.4 Analyses of Off-Standard Conditions 4
12.5 Analyses of Equipment Malfunction 6
12.6 Analyses of Operator Errors
-14 12.7 Startup Accident 15 12,8 Cold Water Accident 17 20 12.9 Fuel Loading Accident 21 12.10 Safety Against Fires & Other General Hazards MAXIMUM CRED1BLE ACCIDENT-TAB-13 Section 13:
13.1 General Considerations 1
- 13. 2 Basis For "MCA" Limitations 2
13.3 Basis For Containment Design 4
- 13. 4 "MCA" Pressure Calculations 5
8
- 13. 5 Core Heat-Up Transient
(
- 13. 6 Emission of Fission Products to Containment Vessel 10
- 13. 7 Leakage From Containmr;nt Vessel 12
- 13. 8 Summary of Radiologichi Effects 16
- 13. 9 Direct Radiation From Enclosure 17 13.10 Meteorological Diffusion Evaluation Methods 18 13. 11 External Radiation Dose From Passing Cloud 23
- 13. 12 External Radiation Dose From Ground Deposition 25 13.13 Grcund Deposition of lodine-131 27 13.14 Internal Dose To Thyroid 28 13.15 Interr.a1 Dose To Lur.
28 13.16 Internal Dose To Bone 29 13.17 General Summary 29 f
a P
l
VOLUME ONE LIST OF FIGURES & TABLES PAGE t
f Tab 1 INTRODUCTION & CONCLUSIONS
- Tab 2 PLANT SITE & ENVIRONMENT Figure 2.1 Location Map
_2
- 2. 2.
Site Map 3
2.3 Population within Five-Mile. Radius 7
. 2.4 Popu.'ation within Sixty-Mile Radius 8'
Table
- 2. I ~
Statistics of surrounding Area 4
- 2. 2 Immediate Population 5
- 2. 3 Earthquake History 11 Tab 3 CONTAINMENT Figure 3.1 Enclosure Isometric 2
- 3. 2 Containment Vessel Design Pressure 4
Table 3.1 Containment Vessel Design Parameters 3
Tab 4 REACTOR Figure. 4.1 Reactor Vessel Schematic 2
- 4. 2 Typical Core Dimensions 8
4.3 Fuel Bundle 9
i 4.4 Control Rod Drive Mechanism 19 4.5 Control Rod Coupling 21 Table 4.1 Reactor Vessel 1
4.2 Reactor Vessel Penetrations '
1 3
4.3 Fuel & Core Materials 10 4.4 Control Rod Blade Materials 13 1
4.5 Rod Drive Materials 22 I'
4.6 Specific Activitiee in Primary Equipment 29 1
i Tab 5 REACTOR SYSTEM EQUIPMENT Tab 6 POWE.'. SYSTEM EQUIPMENT Tab 7 INSTRUMENTATION Table 7.1 Reactor Safety System Functions 3
7.2 Reactor Safety Controls 4
- 7. 3 Reactor Safety System Bypass 9
l
~~^
PAGE Tab 8 NUCLEAR, THERMAL, & HYDRAULIC CHARACTERISTICS Table 8.1 Design Data For Initial Cors 2
- 8. 2 Nuclear Parameters 11
- 8. 3 Temperature Coefficient 13
- 8. 4 Void Coefficient 14
- 8. 5 Doppler Coefficient 14
- 8. 6 Reactivity Requirements 15 t
- 8. 7 Initial Reactivity, Cold 16
- 8. 8 Most Probable Maximum Rod Worth 16 Tab 9
. RADIOACTIVE WASTE DISPOSAL Table 9.1 Off-Gases From Steam Jet Air Ejectors 2
2
- 9. 2 Rate of Evolution of Activated Gases From Reactor 5
9.3 Summary of Wind Conditions at Big Rock Point
- 9. 4 Summary of Wind Conditions (midnight to 4 a. m. ) at Big Rock 6
Point
- 9. 5 Summary of Wind Conditions (noon to 4 p.m. ) at Big Rock 6
Point Tab 10 RESEARCH & DEVELOPMENT PROGRAM Figure 10.1 Approximate Arrangement of Core 6
10.2 Developmental Fuel Bundle 7
Table 10.1 Test Schedule Typical of Phase I 9
Tab 11 OPERATING PROCEDURES Tab 12 SAFETY ANALYSIS Ta b 13 MAXIMUM CREDIBLE ACCIDENT Figure 13.1 Transients of Big Rock Point Reactor System Rupture For Max. Credible Accident Evaluation 7
- 13. 2 Containment Vessel Vapor Space Fission Product. Inventor.y 13 14
- 13. 3 Leakage Rates of Noble Gases & Halogens
- 13. 4 Leakage Rates of Solid Fission Protiuct Groups 15
- 13. 5 Direct Gamma Radiation Dose Rate From Enclosure at 1/2 and 1 Mile 30
- 13. 6 Direct Gamma Radiation Integrated Dose From Enclosure at 1/2 and 1 Mile 31
- 13. 7 Dose Rate From Passing Cloud at 1/ 2 Mile Downwind 32
- 13. 8 Integrated Dose From Passing Cloud at 1/ 2 Mile Distance 33
- 13. 9 Ground Deposition at 1/2 Mile, Inversion, Unidirectional 34 Wind Speed of 1 Meter /Second 13.10 Ground Deposition at 1/2 Mile, Inversion, Unidirectional 35 Wind Speed of 5 Meters /Second 13. 11 Ground Deposition at 1/2 Mile, Neutral, Unidirectional 36 Wind Speed of 5 Meters /Second 13.12 Ground Deposition at 1/2 Mile, Unstable, Unidirectional Wind Speed of 5 Meters /Second 37 13.13 Continuuus Occupancy 'ntegrated Dose From Grot.nd Deposition at 1/ 2 Mile Downviind 38 13.14 Iodine Deposition Rate in Standard Thyroid From Inhalation on Leakage Plume Centerline at 1/2 Mile Distance 39 13.15 Deposition Rate in Standard Lungs of Insoluble Retained Fraction From Inhalation of Leakage Plume Centerline at 1/2 Mile 40 Distance
4 PAGE Tab 13 (Continued)
Table 13.1 Integrated Air Concentrations of Fission Products as a F.inction of Distance and Diffusion Conditions 19 13, 2 Summary of Wind Speeds and Directions Observed at Big Rock Point, Michigan 21 e
e