ML19260E025
| ML19260E025 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 11/30/1979 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19260E021 | List: |
| References | |
| 15004, NEDO-21326C1, NUDOCS 8002130141 | |
| Download: ML19260E025 (46) | |
Text
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November 1979 Consolidated Safety Analysis Report for Morris Operation REVISION INDEX for Revision C, Amendment 1 November 1979 Revision C, Amendment 1 provides demographic data through the year 2000, updated radiological monitor-ing information, and an expanded Table of Contents.
Pages to be Removed New Pages to be Inserted Chapter Page Number Date Chapter Page Number Date Volume 1 Volume 1 Revision Summary 11/79 Table of Contents iii,1v,v 1/79 Table of Contents lii,1v,v, vi,vii,viii, ix/x 11/79 List of List of xi,xii,xiii, Illustrations vi,vii,viii 1/79 Illustrations xiv
'1/79 List of Tables ix,x 1/79 List of Tables xv 11/79 3
3-7,3-8,3-9, 3
3-7,3-0,3-Ga, 3-10,3-11, 3-9,3-9a,3-10, 3-57 1/79 3-10a,3-11, 3-11a,3-57, 3-57a 11/79 7
7-25,7-26, 7
7-25,7-26/
7-27,7-28, 7-28,7-32, 7-32,7-34 1/79 7-34,7-35/
7-36 11/79 Volume 2 Volume 2 Revision Summary 11/79 Table of Contents iii,1v,v
' T)
Table of Contents lii,1v,v, vi,vii,viii, ix/x 11/79 List of List of xi,xii,xiii, Illustrations vi,vii,viii 1/79 Illustrations xiv 11/79 List of Tables ix,x 1/79 List of Tables xv 11/79 1 of 1 h
80021a (1,j j o
Following m terial to be inserted in Volume 1
NEDO-21326C1 November 1979 CONSOLIDATED SAFETY ANALYSIS REPORT FOR MORRIS OPERATION REVISION
SUMMARY
Revision & Amendment Date Summary NEDO 21326C 1/79 Reissue and update filed with licenae renewal application.
Incorporates all "A"-series revisions of original dated 1/77.
NEDO-21326C1 11/79 incorporates demographic data through the year 2000, radiological monitoring update, and expanded table of contents.
Revision Coding Key: New or changed information is indicated by vertical bars in the right-hand margin oppos:te the new or changed information: "N" indicates new information:
"E" indicates editorial changes or corrections.
Document Number Key:
NEDO 213 2 6 C1 e sion Prefix Serial R
on Amendment Series 9
NEDO-21326C1 November 1979 TABLE OF CONTENTS Page 1.
INTRODUCTION AND DESCRIPTION 1-1 1.1 Introduction 1-1 1.1.1 Corporate Entities 1-2 1.1.2 Plant Location 1-2 1.1.3 Existing Facilities 1-5 1.1.4 Fuel Type and Exposure 1-5 1.2 General Plant Description 1-5 1.2.1 Site Characteristics 1-7 1.2.2 Facility Descriptions 1-10 1.3 Fuel Storage Operatione 1-14 1.3.1 Fuel Storage Operations - General 1-14 132 Cask Receipt 1-19 1 3.3 Cask Preparation 1-21 1.3.4 Cask Unloading 1-21 1 3.5 Supporting Systems 1-32 1.3.6 Radiological and Other Monitoring 1-43 1.4 References 1-44 2.
SUMMARY
SAFETY ANALYSIS 2-1 3
SITE CHARACTERISTICS 3-1 3.1 Introduction 3-1 3.2 Geography and Demography of Site 3-1 3 2.1 Site Location 3-1 3.2.2 Site Description 3-5 3.2.3 Population, Distribution and Trends 3-7 3.2.4 Users of Nearby Land and Waters 3-12 3.3 Nearby Industrial, Transportation and Military Facilities 3-18 3.3.1 Nearby Nuclear Facilities 3-18 3.3.2 Industrial and Military 3-18 3.3.3 Transportation 3-19 34 Meteorology 3-21 3.4.1 Regional Climatology 3-21 3.4.2 Local Meteorology 3-26 iii
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 3.4 3 On-Site Meteorological Measurement Program 3-28 3.4.4 Atmospheric Diffusion Characteriatics 3-31 3.5 Surface Hydrology 3-33 3.5.1 Surface Features and Drainage Patterns 3-33 3.5.2 Site Flood Potential 3-35 3.5.3 Surface Water Quality 3-35 3.6 Subsurface Hydrology 3-36 3.6.1 Regional and Area Characteristics 3-36 3.6.2 Site Characteristics 3-39 3.6.3 Groundwater Investigation - 1977 3-41 3.7 Geology and Seismology 3-44 3.7.1 Geologic Studies 3-44 3.7.2 Regional and Trac *. Gei_ogy 3-44 3.7.3 Investigations of Faults 3 48 3 7.4 Earthquake and Seismicity 3-51 3.7.5 Earthquake Design Basis 3-54 3.8 Summary of Conditions Affecting Facility Operating Requirements 3-54 3.8.1 Significant Factors 3-56 3.9 Re ferences 3-57 4.
DESIGN CRITERIA AND COMPLIANCE 4-1 4.1 Introduction 4-1 4.1.1 Material To Be Stored 4-1 4.1.2 Storage Conditions 4-5 4.2 Structural and Mechanical Safety Criteria 4-5 4.2.1 Wind and Tornado Loadings 4-6 4.2.2 Tornado Missile Protection 4-7 4.2.3 Water Level (Flood) Design 4-19 4.2.4 Seismic Design 4-20 4.2.5 Combined Loads 4-37 4.2.6 Subsurface Hydrostatic Loadings 4-41 43 Safety Protection Systems 4 42 4.3.1 General 4-42 4.3.2 Protection by Multiple Confinement Barriers and Systems 4-42 4.3.3 Building Ventilation 4 43 iv
NEDO-21326C1 November 1979 TARLE OF CONTENTS (Continued)
Page 434 Protection by Equipment and Instrumentation 4-43 4.3.5 Nuclear Criticality Safety 4 44 4 3.6 Radiological Protection 4-46 4.3.7 Fire and Explosion Protection 4.49 4.3.8 Fuiel and Radioactive Waste Handling and Storage 4-49 4.4 Classification of Structures, Components, and Systems 4-50 4.5 Decommissioning - General Considerations 4-51 4.6 References 4-52 5.
FACILITY DESIGN AND DESCRIPTION 5-1 5.1 In*.roduction 5-1 5.2 Summary Description 5-1 5.2.1 Exclusion and Protected Areas 5-1 53 Principal Structure 5-4 5.3.1 Fain Building Design Basis 5-4 5.3.2 Fuel Storage Facility Layout 5-4 5.4 Cask Hindling and Fuel Storage Systems 5-7 5 %.1 Cask Receiving Area 5-7 5.4.2 Decontamination Area 5-12 5.4.3 Cask Unloading Basin 5-14 5.4.4 Fuel Storage System 5-22 5.5 Fuel Storage Basins and Systems 5-29 5.3.1 Storage Basin Description 5-29 5.5.2 Basin Water clean-Up System 5-37 5.5.3 Basin Water Cooling System 5-43 5.5.4 Ventilation Exhaust System 5-45 5.5.5 Other Main Building Facilities 5-48 5.6 Waste vaults 5-53 5.6.1 Low Activity Waste Vault (LAW Vault) 5-54 5.6.2 Cladding Vault 5-60 5.7 Supporting Facilities 5-62 5.7.1 Utility and Service Building 5-62 5.7.2 Shop and Warehouse Building 5-64 5.7 3 General Warehouse 5-65 5.7.4 Administration Building 5-65 v
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 5.7.5 Cask Service Facility 5-66 5.8 Utility Systems 5-66 5.8.1 Water supply 5-67 5.8.2 Electrical Supply 5-69 5.8.3 Site Natural Gas Supply 5-73 5.8.4 Sewer Systems 5-73 5.8.5 Rail Transportation Facilities 5-76 5.8.6 Highway Access 5-77 5.8.7 Grading 5-77 5.9 Items Requiring Further Development 5-77 5.10 Re ferences 5-78 6.
WASTE MANAGEMENT 6-1 6.1 Waste Sources 6-1 6.2 Radioactive Waste Management 6-1 63 Nonradioactive Waste 6-3 6.4 References 6-3 7.
RADIATION PROTECTION 7-1 7.1 Introduction 7-1 7.2 Maintaining Occupational Radiation Exposures as Low as Reasonably Achievable ( ALARA) 7-1 73 Radiation Sources 7-1 731 Irradiated Fuel 7-1 7.3.2 Storage Basin Water 7-2 733 Airborne Radioactive Material Sources 7-8 7.4 Radiation Protection Design Featuras 7-10 7.4.1 Facility Design Feature:
7-10 7.4.2 Shielding 7-11 7.4 3 Ventilation 7-14 7.4.4 Gaseous Effluent Monitoring Instrumentation 7-15 7.4.5 Radiation Monitors 7-17 7.5 Personnel Exposure Assessment 7-23 7.6 Health Physics Program 7-23 vi
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 7.7 Estimated Man-Rem Off-Site Dose Assessment 7-24 7.7.1 Effluent and Environmental Monitoring Program 7-24 7.7.2 Estimated Exposures 7-32 7.7.3 Liquid Releases 7-34 7.8 Re ferences 7-34 8.
ACCIDENT SAFETY ANALYSIS 8-1 8.1 Introduction 8-1 8.1.1 Release Pathways 8-1 8.1.2 Accident Description / Discussion 8-3 8.2 Loss of Fuel Basin Cooling 8-3 8.3 Drainage of Fuel Basins 8-5 8.3.1 Basin Liner Rupture Experience 8-5 8.4 Ef fects of Missile Impact on Basin Structure 8-10 8.4.1 Analysis Bases 8-10 8.4.2 Analysis 8-12 8.5 Cask Drop into the Unloading Basin (Deep Pit) 8-13 8.6 Low Activity Waste (LAW) Vault Leakage 8-14 8.7 Fuel Drop Accidents 8-14 8.7.1 Fuel Bundle Drop Accident 8-20 8.7.2 Fuel Basket Drop Accident 8-22 8.7 3 Recovery Practice 8-24 8.8 Tornado-Generated Missile Accident 8-24 8.8.1 Accident Analysis 8-26 8.8.2 Assumptions 8-27 8.8.3 Dose Rate Calculations 8-28 8.9 Cooling System Leak 8-29 8.9.1 Accident Analysis 8-29 8.10 Criticality Accident 8-30 8.10.1 Fuel Handling Procedures 8-30 8.10.2 Reactivity Calculations 8-31 8.10.3 Missile Impact 8-32 8.10.4 Consequence of a Criticality Accident 8-35 8.11 Re ferences 8-40 vii
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 9.
CONDUCT OF OPERATIONS 9-1 9.1 Introduction 9-1 9.2 Corporate Organization 9-1 9.2.1 Corporate Functions, Responsibilities, and Authorities 9-1 9.2.2 Spent Fuel Services Operation Components 9-3 9.2.3 Morris Operation Organization 9-4 93 Training Programs 9-7 9.4 Normal Operations 9-8 9.4.1 Plant Procedures 9-8 9.4.2 Records and Reports 9-11 9.4.3 Facility Modifications 9-11 9.5 Emergency Plans 9-15 9.
5.1 Purpose and Scope
9-15 9.5.2 Responsibilities 9-18 9.5.3 Action Procedures 9-18 9.5.4 Activation of Emergency Organization 9-19 9.6 Decommissioning 9-21 9.7 References 9-21
- 10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1 10.1.1 De finitions 10-1 10.1.2 Authorized Place of Use 10-2 10.1.3 Quality Assurance 10-2 10.1.4 General Considerations 10-3 10.2 Safety Limits 10-3 10.2.1 Authorized Materials 10-3 10.2.2 Fuel Storage Provisions 10-3 10.3 Limiting Conditions 10-10 10.3.1 Limiting Conditions - Water Shield 10-10 10.3.2 Limiting Condition - Criticality 10-10 10.4 Surveillance Requirements 10-11 10.4.1 Effluent Air Sampling 10-14 10.4.2 Effluent Water 10-14 viii
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 10.4.3 Sealed Sources 10-15 10.4.4 Instrumentation 10-15 10.4.5 Basin Coolers 10-16 10.4.6 Process Steam Bypass 10-17 10.4.7 Cask Liquid Coolants 10-17 10.4.8 Cask Coolant Sampling 10-18 10.4.9 Basin Water Chemica' Characteristics 10-18 10.4.10 Basin Water Radioactivity Sampling 10-19 10.5 Design Features 10-19 10 5.1 Fuel Storage Basin 10-19 10 5.2 Fuel Storage System 10-19 10.6 Administrative Controls 10-21 10.6.1 Responsibility 10-21 10.6.2 Organization 10-21 10.6.3 Plans and Procedures 10-23 10.6.4 Review and Audit 10-24 10.6.5 Action Required For Specification Noncompliance 10-25 10.6.6 Logs, Records, and Reports 10-27 10.7 References 10-27 11.
QUALITY ASSURANCE 11-1 11.1 Introduction and Summary 11-1 11.2 Re ferences 11-1 APPENDICES A.
See Index following divider A-1 B.
See Index following divider B-1 ix/x
NEDo-21326C1 November 1979 LIST OF ILLUSTRATIONS Figure Title Page 1-1 General Location - Morris Operation 1-3 1-2 General Electric Tract and Vicinity 1-4 1-3 Map - GE Morris Operation Tract 1-6 1-4 Principal Facilities - Protected Area 1-11 1-5 Schematic - Morris Operation Basin Facilities 1-13 1-6 IF-300 Irradiated Fuel Shipping Cask 1-15 1-7 GE IF-300 Irradiated Fuel Shipping Cask 1-16 1-8 NFS-4 Shipping Cask 1-17 1-9 Truck Cask and Trailer Being Spotted in Receiving Area 1-18 1-10 IF-300 Cask in Receiving Area 1-20 1-11 Cask Decontamination Area 1-22 1-12 IF-300 Cask on Cask Shelf 1-23 1-13 Cask Unloading Basin Deep Pit 1-24 1-14 Fuel Grappling Operations 1-26 1-15 Fuel Removal From Cask 1-27 1-16 Fuel Basket Loading 1-28 1-17 Fuel Basket Transfer 1-29 1-18 Fuel Movement in Storage Basins 1-30 1-19 Fuel Storage Basin Areas 1-31 1-20 Preparing IF-300 Cask for Shipment 1-33 1-21 Low Activity Waste System Sche =atic 1-34 1-22 tentilation System 1-36 1-23 Lasin Filter System 1-37 1-24 Basin Water Cooling System 1-38 1-25 Cask Sampling, Cool-Down, and Flush System 1-40 1-26 Leak Detection, Pump-Out and Sampling System 1 41 1-27 Sewage Systems 1 42 3-1 Aerial Photograph - Morris Operation 3-2 3-2 Topographic Map - GE Tract and Vicinity 3-3 3-3 Contour Map - Morris operation 3-4 3-4 Estimated Population Within a 5-Mile Radius of Morris Operation -
Circa 1970 3-8 3-4A Projected 1980 Population Within a 5-Mile Radius of Morris Operation 3-8a Xi
NEDO-21326C1 November 197','
LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 3-5 Estimated Population Within a 50-Mile Radius of Morris Operation 3-9 3-5A Projected 2000 Population Within a 5-Mile Radius of Morris Operation 3-9a 3-6 Estimated Population Within a 5-to-50-Mile Radiur of Morris Operation - Circa 1970 3-10 3-6A Projected 1980 Population Within a 5-to-50-Mi.e Radius of Morris Operation 3-10a 3-7 Projected 1990 Population Within a 5-to-50-Mile Radius of Morris Operation 3-11 3-7A Projected 2000 Population Within a 5-to-50-M11e Radius of Morris Operation 3-11a 3-8 Annual Wind Rose at 35-ft Level at DNPS Site 3-27 3-9 Major Regional Geollgic Structures 3-46 3-10 Generalized Stratigraphic Column for the Morris Operation Site 3-49 3-11 Correlation of Angle Boring and Trench Data 3-52 3-12 Map of the U.S. Showing Zones of Approximate Equal Seismic Probability 3-55 4-1 Spectra Comparison - 0.10g Ground Acceleration: RG 1.60 versus El* Centro 1940 N-S 4-2?
4-2 Spectra Comr Irison - 0.20g Ground Acceleration:
RG 1.60 versus El Centro 1940 N-S 4-23 4-3 El Centro Accelerogram 4-24 4-4 Response Acceleration Spectrum
. Morris Operation -
Main Building, G~ound Motion, Damping Ratio = 0.005
'4-25 4-5 Response Acceleration Spectrum - Morris Operation -
Main Building, Ground Motion, Damping Ratio = 0.010 4-26 4-6 Response Acceleration Spectrum - Morris Operation -
Main Building, Ground Motion, Damp!.ng Ratio = 0.020 4-27 4-7 Hydrodynamic Constants for Rectangular and Cylindrical Tanks 4-30 4-8 Vertical and Norizontal Design Respense Spectra for Nuclear Power Plants 4-34 5-1 Contour Map - Morris Operation 5-2 5-2 Cask Lifting Yoka 5-9 v.i i
NEDO-21326C1 November 1979 LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 5-3 NFS-4 Cask Being Lowered into Unloading Pit, Showing Use of Extension Hook 5-11 5-4 Low-Level Waste Compactor 5-14 5-5 Unloading Pit Doorway Guard 5-18 5-6 BWR Fuel Grapple 5-19 5-7 PWR Fuel Grapple 5-21 5-8 Morris Fuel Storage System 5-25 5-9 Typical Grid Assembly 5-26 5-10 Details of Storage Basket Lock Mechanism 5-27 5-11 Excavation at Morris Operation 5-31 5-12 7oundation Construction 5-32 5-13 Stainless Steel Basin Liners 5-35 5-14 Technicians " Vacuum Cleaning" Storage Basin Floor Area 5-38 5-15 Pump Room Equipment 5 41 5-16 Water Intrusion 5-55 5-17 LAW Vault Under Construation 5-56 5-18 Arrangement - LAW and Cladding Vault Equipment Pits 5-58 7-1 History of Morris Operation Basin Water Activity 7-7 7-2 Radiation Monitor Locations 7-21 7-3 Monitor and Sampling Locations (within 2 miles of Site) 7-29 7-4 Environs Monitoring Locations (within 5 miles of site) 7-30 7-5 Environ = ental Monitoring Stations (within 5 to 15 miles of Site) 7-31 8-1 Event Diagram for Postulated Accidents 8-4 8-2 Kr-89 Activity as Function of Cooling Time for Different Fuel Exposures (Total Inventory in Fuel Rod) 8-16 6-3 Iodine, Krypton, and Xenon Decay 8-17 8-4 PWR Fuel Bundle Array at 2-inch Separation 8-33 8-5 Close-Packed Array of Four PWR Bundles 8-34 9-1 Corporate Organization Chart - General Electric Company 9-2 9-2 Morris operation Organization 9-5 9-3 Facility Modification Control Concepts 9-12 9-4 Emergency Plan Relationships for Morris Operation 9-16 9-5 Emergency Response Organization 9-20 xiii
NEDO-21326C1 November 1979 LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 10-1 Rod Lattice k. - PWR Fuel k. = k3xCWF x Cpp x CCL 10-7 10-8 10-2 Rod Lattice k. - BWR Fuel k. = kj x CWF x CPD xiv
NEDO-21326C1 November 1979 LIST OF TABLES Table Title Dage 3-1 Cities of Greater Than 1,000 Population Within 30 Miles of Morris Operation 3-15 3-2 Nuclear Reactors Within 50 Miles of Morris Operation 3-19 3-3 Industrial, Transportation, and Military Activities (6-mile radius) 3-20 3-4 Local Temperature Data (oF) for Morris, Illinois 3-23 3-5 Total Precipitation and Total Snowfall (in.) for Morris and Joliet, Illinois 3-24 3-6 Thunderstorm Activity 3-28 3-7 Joint Frequency Distribution of Pasquill Stability Class and Wind Direction, Dresden 150-ft Level (percent of total observations) 3-30 3-8 Stability, Frequency, and Wind Speed 3-32 3-9 Characteristics of the Illinois River at Morris, Illinois 3-37 3-10 Characteristics of the Kankakee River at the Rt 66 Bridge,1971 3-38 3-11 Well Water Analysis - Morris Operation Well 3-42 3-12 Microscopic Particle Size Distribution - Morris Operation Well 3-43 3-13 Morris operation Site Investigations 3-45 4-1 Spent Fuel Fission Product Activity 4-2 4-2 Analyses, Fuel Exposures, and Cooling Times 4-5 4-3 Results of Wind Analyses 4-17 5-1 Typical Isotope Concentrations in Basin Water 5-42
,5-2 Control Room Monitoring of Fuel Storage Functions 5-51 7-1 Fission Product Activity 7-3 7-2 Gamma Spectrum (E) for Fuel in Storage - Volumetric Source (S )
7-5 y
7-3 Morris Operation Radiological Monitoring Program 7-26 8-1 List of Tornado-Generated Missiles 8-25 8-2 Velocities and Kinetic Energies of Postulated Missiles in Water When Entering Fuel Pool in a Vertical Position 8-27 8-3 Prompt Fission Gamma-Ray Spectra 8-37 8-4 Dose, mR per Fission, at Basin Surface 8-39 10-1 Authorized Materials - Instrument, Calibration, and Laboratory Sources 10-5 10-2 Surveillance Requirements Su= mary 10-12 10-3 Summary Requirements System and Equipment Test and Calibration 10-13 xv
NEDO-21326C1 November 1979 3.2.2.4 Boundaries for Establishing Effluent Release Limits The protected area boundary line, as shown in Figure 3-3, is the boundary for establishing effluent release limits as defined in Section 100 3 of the NBC's
" Reactor Site Criteria," Part 100, Title 10, Code of Federal Regulations.
3.2.3 Population, Distribution and Trends The data base for the following sections is founded on information developed by agencies of the States of Illinois and Indiana, as well as information developed N
by General Electric and Commonwealth Edison.1a,1b,1c 3.2.3.1 Population Between 0 and 5 Hiles (Figures 3-4 through 3-5A)
The population in the immediate vicinity of the Morris Operation is very low.
Within a radius of 5 miles the population is about 5,000, including 1,500 in the village of Channahon, about 4 miles to the northeast. Included in this accounting are several residences at the Dresden Lock and Dam. The 1970 pop-ulation figures within a 5-mile radius are based on a 1974 actual house count assuming three persons per house and are not intended to represent 1970 U.S.
census data. The 1980 projections for the O-to 5-mile radius are based on an assumed 5% annual growth in all areas except those in which the tract is located.2 The population within 5 miles of the site is projected to increase to 8830 by the year 2000. Within 10 miles, the existing population is about 32,400 and is projected to reach 68,000 by the year 2000.2a 3.2.3.2 Population Within 50 Miles (Figures 3-4 through 3-7A)
The total population within the 50-mile radius was found to be about 6,251,500 in 1970 and is projected to reach 7,500,600 by 2000 with about 91% of the total beyond the 30-mile radius.3 The 1978 population projections prepared by the State of Illinois and the State of Indiana for counties within a 50-mile radius surrounding the facility antici-N pate relatively minor population growth between 1978 and the year 2005.3a 3-7
NED0-21326c1 November 1979 N
99 4-5 miles.
175 NNW NNE 19 90 so 435 3-4 mih 1558 NW g
NE 125 77 2-3 miles 700 71 310 e1 3
n WNW 1-2 males 13 0
M 0
3 n
6 y,
0 mile o
0 0 n
3 0
0 0
0 19 134 W
32 0
0 0
. 0 29 3
0 3
E J2 0
38 0
0 0
413 7
0 0
0 0
115 3
0 0
0 0
0 0
19 304 ESE WSW g
100 to 214 100 300 0
SSE 25 900 16 22f e-Figure 3-4.
Estimated Population Within a 5-Mile Radius of Morris Operation -
E Circa 1970 3-8
NED0-21326C1 November 1979 69 N
108 44 miles 215 NNW NNE 21 480 2168 NE 21 138 6
94 2-3 miles 975 U
79 342 3
36 12 miles ENE 0
13 15 0
15 24 0
01 8
0 mile 3
37 0 0 0
3 0
0 0
0 21 153 W
35 0
0 0
0 108 37 4
0 4
E
//
35 0
42 0
0 0
491 0 0 o
160 3
0 0
0 0
0 0
26 406 ESE W
835 552 110 12 298 110 331 107 o
SW 6
220 814 110 27 0
993 S
18 22.5*
Figure 3-4A.
Projected 1980 Population 'dithin a 5-Mile Radius of E
Morris Operation 3-8a
NEDO-21326c1 November 1979 75 H
11g 4-5 melet-261 NNW NNE 23 109 98 3 *"
528 2798 h
NW NE 23 I269 2-3 miles 13 1520 376 85 04 1-2 miles
/
0 16 16 4
0 26 0-1 O
3
- m...
40 0
0 0
3 0
0 -
0 0
23 374 W
38 0
0 0
0 to 45 5
0 S
E 38 46) 0 f
0 572 0
0 0
207 0
3 0
0 0
0 0
512 ESE WSW 1008 8
3 121 605 385 13 121 363 o
SSN 1089 S
20 22.5*
-e Figure 3-5.
Projected 1990 Population Within a 5-Mile Radius of N
Morris Operation 3-9
NEDo-21326c1 November 1979 82 N
131 4-5 miles 302 NNW NNE 25 119 118 574 3 4 m.les 3443 NW 5
NE I
1549 2-3 miles I4 409 1870 4
WNW 12 des 95 0
20 18 0
38 18 0
N 13 29 0-1 0
mile
'4 0
0 0
4 0
0 0
0 25 W
41 G
l 0
0 0
130 53 6
0 6
E 41 s
195 0
5 0
0 0
W 9
0 0
0 29 0
4 0
0
/
0 0
42 0
619 ESE WSW 3333 131 14 474
/
131 396 0
8 SW s,
262 1267 131 40 j
/.
S 22 22.5*
-e Figure 3-SA.
Projected 2000 Population Within a 5-Mile Radiua of N
Morris Operation 3-9a
NED0-21326c1 November 1979 318900 N
1133300 64600 40-50 nules NNW NNE 128233 30-40 miles 3255200 NW 85,029 NE 4S95 362,369 7235 20-30 miles 2.466,542 99S52 3.681 10,645 80.634 634.082 10-20 20100 miles 1021900 WNW 10.724 4,656 24.487 ENE 10257 1963 21S98 519,666 4p05 1,587 m$t 126B76 451,331 f
3E66
,a 42D95
~
1,328 8.662 8
o 5
2e3 R
g miles (,e.
g
=
W 35.665 19284 21,166 956 9.043 791 2.547 8,373 18200 75J16 E
49 h i, h 1213 2,540 J,9 4365
[% %
12,015 2.751 1,703 4,376 8,370 21344 1
5,522 1.086 W
WSW 2.328 2.6 56S55 ESE 34500 32500 0'#
3'#3 4B05 1B29 6.134 4215 12S21 3S72 Sw 1E60 SE 83000 5.608 4E09 SDIO SSW SSE 25800 13800 14900
- 22.5 -
g Figure 3-6.
Estimated Population Within a 5-to-50-Mile Radius of E
Morris Operation - Circa 1970 3-10
NED0-21326c1 November 1979 391600 N
is '90 40-50 miles 844200 NNW NNE 153367 22661 457530 30-40 miles 58100 3538900 NW 105098 NE 20389 263371 6018m 37401 20-30 miles 8071 27602 93053 746145 10-20 27000 miles 1626700 WNW 83422 ENE 4697 10520 9529 6573 26103 1104433 6871 6573 m$les 103393 438222 h8 [
63531 4541 5055
- e 16441 m.!es SO 4110 It.J41 27401 32011 118769 W.
30800 15809 13993 3602 1000 E
l 4
",, i,'
<rro 3769 9,
13207 g
4541 35236
~
22026 4001 13207 13209 4001 8894 43428 4191 4314 40316 ESE WSW 39100 109200 0
5573 7601 7181 5485 4082 SW 5050 SE 00 21900 7964 5257 6492 SSW SSE 22400 30500 S
21700
- 22.6*-
g Figure 3-6A.
Projected 1980 Population Within a 5-to-50-Mile Radius of N
Morris Operation 3-10a
NEDO-21326c1 November 1979 465900 N
935800 96000 40 50 m,i,,
NNW NNE 171106 30-40 miles NW 129912 NE 25109 319153 42155 20-30 mdes 2523749 149716 9137 33924 114387 723761 10-20 29100 miles 1619500 WNW 13023 83566 W
5249 10180 7546 33725 1100109 7409 7546 m$les 133585 425076
'Y, 2
4764 67801 5684 0
21242 E
g m.Ses
'082 o
8 a
W 32319 16583 14678 3912 1097 5310 21242 35402 41086 125895 E
gaj1
~i S279
?
e
'O 23078 345 4389 10675 46291 8087 WSW 4399 4647 43783 ESE 41100 126400 3973 8798 10202 5614 5036 7270 5496 4028
.;/,
5170 SE 27400 83800 8140 5126 6648 SSW SSE 23100 33900 5
22600
- 22.6*-
g Figure 3-7.
Projected 1990 Population Within a 5-to-50-Mile Radius of N
Morris Operation 3-11
NED0-21326C1 November 1979 543700 N
118800 40-50 miles 1003200 NNW NNE 192690 34381 463184 3393900 75700 NW 151432 NE 31432 359656 2437942 48671 20-30 miles 181422 10607 42306 132309 699153 31600 miles 1607500 WNW gggi 8 @ 09 -
M 15646 10974 8693 41481 1092225 5-10 8070 410623 8693 miles 164309
- g hf 4987 72039 6404 fo 26127
96 6
. m es :
n n
6531 W
33819 17363 15368 4229 1196 n
26127 43544 50258 132567 E
G (c{o S,
3 i
4450 op 63 20199 4987 52054 4784 0199 24165 14861 4784 12295 WSW 4665 4965 45359 ESE 142300 43200 4185 91W 5828 10623 5236 8208 7592 5766 4279 5340 SE y
24100 8591 5484 6864 SSW SSE 24500 37700 23600
_ 22.5* -
g Figure 3-7A.
Projected 2000 Populat'a 1 Within a 5-to-50-Mile Radius of N
Morris Operation 3-11a
NED0-21326C1 November 1979
3.9 REFERENCES
1.
See Appendix A.1 for document list.
la. State of Illinois, Bureau of the Budget, Illinois Population Projections N
(Revised 1977), Springfield, September 1977.
1b. State of Indiana, State Board of Health, Indiana County Population Projec-tions, Indianapolis,1978.
ic. Northeastern Illinois Planning Commission, Regional Data Report, Chicago, June 1978.
2.
The 5% growth in the 0-5 mile area was developed from the assumption that farmland will not experience growth (urbanization) except in a few selected areas. This growth was estimated and the overall area growth integrated.
Most people working in local industries live in the Western Joliet and Morris areas; there has been little growth in smaller communities.
2a. Beyond the 5-mile area, population data totals on charts have been rounded N
off to the nearest 100.
3 The USNRC staff reported an adjusted estimated 1980 population for th E
area within the 50-mile radius of about 9,169,337 (Environmental Impact Appraisal, Docket 70-1308, NR-FM-002),
3a. During research for these data, differences were noted between (for example) the Northeastern Illinois Planning Commission data and Federal census figures.
N In general, however, the data appear mutually supportive, particularly at the county levels.
4 Within 5 miles of the site the total school population is 800, but at slightly more than 5 miles it increases to about 2,140; the larger number is shown.
5.
Correctional institution (juvenile) at Channahon, 3 miles WNW.
3-57
NED0-21326c1 November 1979 6.
Climatography of "he United States, No. 60-11, revised and reprinted June 1969.
7.
H. E. Landsberg, "Clit.ates of North America," World Survey of Climatology, Vol. 11, edited by Bryson, et al., Elsevier Scientific Publication Co.
(1974).
8.
S. S. Visher, Climatic Atlas of the United States, Harvard University Press, Cambridge (1966).
9 U.S. Department of Commerce, Climatography of the United States No. 86-9,
" Decennial Census of United States Climate," for Illinois, Washington, D.C. (1964).
3-57a
NEDO-21326c1 November 1979 radiation dose rates in the populated areas around the Dresden-Morris Operation sites and in 13 central Illinois counties. Findings from 1971 to 1976 show N
that there is no significant difference in radiation exposure between the two
- a. Peas even though the joint site now consists of three reactors and a fuel storage facility.2a N
The specifications for the current environs monitoring program are shown in Table 7-3 and the locations of the sampling points are shown in Figures 7-3 through 7-5.
Samples are collected at these points adjacent to the Morris Operation, where concentrations would be expected to be the highest if a release should occur, and are compared to samples which have been collected simultaneously at points where the concentration of effluents is expected to be negligible. The reference samples provide a running background which will make it possible to distinguish significant radioactivity introduced into the environment by the operation of the Morris Operation from that introduced by nuclear weapons testing and other sources.
The sampling frequencies are established so that changes in the environmental radioactivity can be detected. The materials which first show changes in radio-activity are sampled most frequently. Those which are less affected by transient changes but show long-term accumulations are sampled less frequently. However,
the specific sampling dates are not crucial, and adverse weather conditions or equipment failure may on occasion prevent collection of specific samples.
Particulate radioactive material in the air is dominated by fallout from weapons testing, reaching a beta emitter peak of 1.3 x 10-11 pCi/cc in June 1963 compared to about 1 x 10-12 uCi/cc in late 1964. By mid-1971 the concentration was down to about 1 x 10-13 pci/cc. Cosmic and background sources result in an exposure rate of 2 to 3 mrem / week and is not significantly altered by weapons testing.
River water ccncentrations show a natural background of 1 x 10-8 to 5 x 10-8 uCi/cc due to natural racium, uranium and radiopotassium, and displayed an order of magnitude increase during the 1963 peak weapons testing fallout.
7-25
NED0-21326C1 November 1979 Table 7-3 MORRIS OPERATION RADIOLOGICAL MONITORING PROGRAM Sample Medium Collection Sites Analysis Frequency 1.
Particulates in air a.
Near field:
I k Filter gross S Weekly Collins Road Bennitt farm I
Pheasant trail
,1 b.
Far f' eld:
Clay p oducts T
Prairie Park Coal City j
Goose Lake Village y Filter exchange Weekly Morris j
only Minooka Channahon l
Joliet
/
2.
Exposum by TLD a.
Near field:
see la j
Y radiation Quarterly b.
Far Tield:
see Ib 3
Milk Davidson, Dorin Iodine-131 Weekly
& Mather farms 4.
Water a.
Site waste ponds (2 samples)
Gross et, S Monthly b.
Corps of Engineers j pump station c.
Illinois River f Gross 3,H3 Quarterly at Rt. 47 d.
Thorsen well e.
LAW vault well f.
West pond 7-26/7-28
NED0-21326C1 November 1979 Well water alpha radioactivity concentrations average about 0.3 x 10-8 pCi/ce, lE the same as for surface water. Beta concentrations in well water fluctuate as a function of weapons-testing fallout. The range of fluctuations has been from 1.5 x 10-8 pCi/cc in 1961 to 4 x 10-8 pci/cc in 1964. Levels in 1971 were about 0.1 x 10-8 pCi/cc for alpha and about 10-8 pCi/cc for beta emitters. Biological E
samples from the river, and vegeration and milk samples also reflect trends ascribable to weapons testing.
The overall findings have been in general agreement with other local programs and with the national fallout sarveillance network results.
The program is responsive to the recommendations of the Fish and Wildlife Service and the Bureau of Radiological Health of the United States Department of Health, Education and Welfare and meets the requirements of the USNRC.
7.7.2 Estimated Exposures Estimated exposures from radioactive material released in the stack effluents of the facility are based on identification of all exposure paths for each type of radio-active material and on the evaluation of the possible exposure paths. The exposure path that results in the maximum radiation dose potential for a specific isotope is then determined. Thus, regardless of where the radionuclide shows up in the environs, it will not result in excessive exposure.
The only normal release of radioactive material from the Morris Operation is that present in the effluent from the main stack. Potential sources and release rates have been identified and discussed earlier in this chapter, Section 7.3.2.
Atmospheric diffusion characteristics, including joint stability-frequency and wind speed data, method and conditions used in the calculations of ground-level radiation doses, are discussed in Chaptr e 3 The population distribution around the plant is given in that chapter.
7-32
NEDO-21326C1 November 1979 For comparison, the guideline value for compliance to Appendix I of 10 CFR Part 50 is 15 mrem /yr to any organ (Regulatory Guide 1.109).
7.7.2 3 Man-Rem Calculations Man-Rem calculations were done only for the estimated annual thyroid exposure because it is the maximum dose. Averages of thyroid exposures were calculated for concentric circles with radii of multiples of 10 miles. These average values were multiplied by tae population within each area which gives an average annual man-thy roid-Rem. The sum of these values for each area out to a radius of 50 miles (1970 population) gives a total of less than five man-thyroid-Rem /yr.
E For comparison, the population thyroid exposure from normal background radiation in the same area is about 39,610,000 man-thyroid-Rem per year. The radiological impact from the Morris Operation is insignificant.
7 7.3 Liquid Releases There are no planned releases of liquid wastes from the site. Furthermore, there is no mechanism under normal operating conditions for injection of contaminated water into the waste water treatment system.
7.8 REFERENCES
1.
RESSAR-41 Reference Safety Analysis Report, Vol. 6, Westinghouse, December 1973 and Amendments.
2.
K. J. Eger, Operating Experience - Irradiated Fuel Storage - Morris, Operation, Morris, Illinois, General Electric Company, May 1978 (NEDO-20969B).
2a. State of Illinois, Department of Public Health, Monitoring and Regulation of N
Nuclear Facilities in Illinois, Springfield, Illinois (1977). The report shows slightly higher levels of radioactivity in the control counties.
3 A proprietary product of the Norton Co.
7-34
NEDO-21326C1 November 1979 4.
The average of 111 pCi gross beta is based on data from 1974 through mid-1976.
This " average" has decreased as 1977-1978 data has been incorporated; see E
NEDO-20969B, May 1978. The 111 pCi gross beta value is used in the off-site analysis.
5.
Based cn Morris Operation experience over more than 6 years.
6.
T. Rockwell, Reao*.or Shielding Design Manual, VanNostrand, 1956.
7.
R. O. Gumprecht, Mathematical Basis of Computer Code RIBD, June 1968 (DUN 4136).
8.
Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, March 1976.
7-35/7-36
Following material to be inserted in Volume 2
NEDO-21326c1 November 1979 CONSOLIDATED SAFETY ANALYSIS REPORT FOR MORRIS OPERATION REVISION
SUMMARY
Revision & Amendment Date Summary NEDO-21326C 1/79 Reissue and update filed with license renewal application.
Incorporates all "A"-series revisions of original dated 1/77.
NEDO-21326C1 11/79 incorporates demographic data through the year 2000, radiological monitoring update, and expanded table of contents.
Revision Coding Key: New or changed information is indicated by vertical bars in the right-hand margin opposite the new or changed information: "N" indicates new information: "E indicates editorial changes or corrections.
Document Number Key:
NEDO 21328 ewson Prefix Serial
' Revison Amendment Senes
NEDO-21326Ci November 1979 TABLE OF CONTENTS Page 1.
INTRODUCTION AND DESCRIPTION 1-1 1.1 Introduction 1-1 1.1.1 Corporate Entities 1-2 1.1.2 Plant Location 1-2 1.1 3 Existing Facilities 1-5 1.1.4 Fuel Type and Exposure 1-5 1.2 General Plant Description 1-5 1.2.1 Site Characteristics 1-7 1.2.2 Facility Descriptions 1-10 1.3 Fuel Storage Operations 1-14 1.3.1 Fuel Storage Operations - General 1-14 1.3.2 Cask Receipt 1-19 1.3.3 Cask Preparation 1-21 1 3.4 Cask Unloading 1-21 1 3.5 Supporting Systems 1-32 1.3.6 Radiological and Other Monitoring 1-43 1.4 References 1-44 2.
SUMMARY
SAFETY ANALYSIS 2-1 3
SITE CHARACTERISTICS 3-1 3.1 Introduction 3-1 3.2 Geography and Demography of Site 3-1 3 2.1 Site Location 3-1 3.2.2 Site Description 3-5 3.2.3 Population, Distribution and Trends 3-7 3.2.4 Users of Nearby Land and Waters 3-12 3.3 Nearby Industrial, Transportation and Military Facilities 3-18 3 3.1 Nearby Nuclear Facilities 3-18 3.3.2 Industrial and Military 3-18 3.3.3 Transportathn 3-19 34 MeteoroloSY 3-21 3.4.1 Regional Climatology 3-21 3.4.2 Local Meteorology 3-26 iii
NEDO-21326C1 Novemtcr 1979 TABLE OF CONTENTS (Continued)
Page 3.4.3 On-Site Meteorological Measurement Program 3-28 3.4.4 Atmospheric Diffusion Characteristics 3-31 3.5 Surface Hydrology 3-33 3.5.1 Surface Features and Drainage Patterns 3-33 3.5.2 Site Flood Potential 3-35 3.5.3 Surface Water Quality 3-35 3.6 Subsurface Hydrology 3-36 3.6.1 Regional and Area Characteristics 3-36 3.6.2 Site Characteristics 3-39 3.6.3 Groundwater Investigation - 1977 3-41 37 Geology and Seismology 3-44 3.7.1 Geologic Studies 3-44 3.7.2 Regional and Tract Geology 3-44 3.7.3 Investigations of Faults 3-48 3.7.4 Earthquake and Seismicity 3-51 3.7.5 Earthquake Design Basis 3-54 3.8 Summary of Conditions Affecting Facility Operating Requirements 3-54 3.8.1 Significant Factors 3-56 39 References 3-57 4.
DESIGN CRITERIA AND COMPLIANCE 4-1 4.1 Introduction 4-1 4.1.1 Material To Be Stored 4-1 4.1.2 Storage Conditions 4-5 4.2 Structural and Mechanical Safety Criteria 4-5 4.2.1 Wind and Tornado Loadings 4-6 4.2.2 Tornado Missile Protection 4-7 4.2.3 Water Level (Flood) Design 4-19 4.2.4 Seismic Design 4-20 4.2.5 Combined Loads 4-37 4.2.6 Subsurface Hydrostatic Loadings 4-41 4.3 Safety Protection Systems 4 42 4.3.1 General 4-42 4.3.2 Protection by Multiple Confinement Barriers and Systems 4 42 4.3.3 Building ventilation 4 43 iv
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 434 Protection by Equipment and Instrumentation 4-43 4.3.5 Nuclear Criticality Safety 4-44 4.3 6 Radiol ~ogical Protection 4-46 4 3.7 Fire and Explosion Protection 4-49 4.3.8 Fuiel and Radioactive Waste Handling and Storage 4-49 4.4 Classification of Structures, Components, and Systems 4-50 4.5 Decommissioning - General Considerations 4-51 4.6 References 4-52 5.
FACILITY DESIGN AND DESCRIPTION 5-1 5.1 Introduction 5-1 5.2 Summary Description 5-1 5.2.1 Exclusi.on and Protected Areas 5-1 5.3 Principal Structure 5-4 5.3.1 Main Building Design Basis 5-4 5 3.2 Fuel Storage Facility Layout 5-4 5.4 Cask Handling and Fuel Storage Systems 5-7 5.4.1 Cask Receiving Area 5-7 5.4.2 Decontamination Area 5-12 5.4 3 Cask Unloading Basin 5-14 5.4.4 Fuel Storage System 5-22 5.5 Fuel Storage Basins and Systems 5-29 5.5.1 Storage Basin Description 5-29 5.5.2 Basin Water Clean-Up System 5-37 5.5.3 Basin Water Cooling System 5 43 5.5.4 Ventilation Exhaust System 5-45 5.5.5 Other Main Building Facilities 5-48 5.6 waste vaults 5-53 5.6.1 Low Activity Waste Vault (LAW Vault) 5-54 5.6.2 Cladding Vault 5-60 5.7 Supporting Facilities 5-62 5.7.1 Utility and Service Building 5-62 5.7.2 Shop and Warehouse Building 5-64 5.7.3 General Warehouse 5-65 5.7.4 Administration Building 5-65 v
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 5.7.5 Cask Service Facility 5-66 5.8 Utility Systems 5-66 5.8.1 Water Supply 5-67 5.8.2 Electrical Supply 5-69 5.8.3 Site Natural Gas Supply 5-73 5.8.4 Sewer Systems 5-73 5.8.5 Rail Transportation Facilities 5-76 5.8.6 Highway Access 5-77 5.8.7 Grading 5-77 5.9 Items Requiring Further Development 5-77 5.10 References 5-78 6.
WASTE MANAGEMENT 6-1 6.1 Waste Sources 6-1 6.2 Radioactive Waste Management 6-1 6.3 Nonradioactive W' ste 6-3 a
6.4 References 6-3 7.
RADIATION PROTECTION 7-1 7.1 Introduction 7-1 7.2 Maintaining Occupational Radiation Exposures as Low as Reasonably Achievable ( ALARA) 7-1 7.3 Radiation Sources 7-1 731 Irradiated Fuel 7-1 7.3.2 Storage Basin Water 7-2 7.3.3 Airborne Radioactive Material Sources 7-8 7.4 Radiation Protection Design Features 7-10 7.4.1 Facility Design Features 7-10 7.4.2 Shielding 7-11 7.4.3 Ventilation 7-14 7.4.4 Gaseous Effluent Monitoring Instrumentation 7-15 7.4.5 Radiation Monitors 7-17 7.5 Personnel Exposure Assessment 7-23 7.6 Health Physics Program 7-23 vi
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 7.7 Estimated Man-Rem Off-Site Dose Assessment 7-24 7.7.1 Effluent and Environmental Monito.'ing Program 7-24 7.7.2 Estimated Exposures 7-32 7.7.3 Liquid Releases 7-34 7.8 Re ferences 7-34 8.
ACCIDENT SAFETY ANALYSIS 8-1 8.1 Introduction 8-1 8.1.1 Release Pathways 8-1 8.1.2 Accident Description / Discussion 8-3 8.2 Loss of Fuel Basin Cooling 8-3 8.3 Drainage of Fuel Basins 8-5 8.3 1 Basin Liner Rupture Experience 8-5 8.4 Effects of Missile Impact on Basin Structure 8-10 8.4.1 Analysis Bases 8-10 8.4.2 Analysis 8-12 8.5 Cask Drop into the Unloading Basin (Deep Pit) 8-13 8.6 Low Activity Waste (LAW) Vault Leakage 8-14 8.7 Fuel Drop Accidents 6-14 8.7.1 Fuel Bundle Drop Accident 8-20 8.7.2 Fuel Basket Drop Accident 8-22 8.7.3 Recovery Practice 8-24 8.8 Tornado-Generated Missile Accident 8-24 8.8.1 Accident Analysis 8-26 8.8.2 Assumptions 8-27 8.8.3 Dose Rate Calculations 8-28 8.9 Cooling System Leak 8-29 8.9.1 Accident Analysis 8-29 8.10 Criticality Accident 8-30 8.10.1 Fuel Handling Procedures 8-30 8.10.2 Reactivity Calculations 8-31 8.10.3 Missile Impact 8-32 8.10.4 Consequence of a Criticality Accident 8-35 8.11 References 8-40 vii
NEDO-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 9
CONDUCT OF OPERATIONS 9-1 9.1 Introduction 9-1 9.2 Corporate Organization 9-1 9 2.1 Corporate Functions, Responsibilities, and Authorities 9-1 9.2.2 Spent Fuel Services Operation Components 9-3 9.2.3 Morris operation organization 94 9.3 Training Programs 9-7 9.4 Normal Operations 9-8 9.4.1 Plant Procedures 9-8 9.4.2 Records and Reports 9-11 9.4.3 Facility Modifications 9-11 9.5 Dnergency Plans 9-15 9.
5.1 Purpose and Scope
9-15 9.5.2 Responsibilities 9 18 9.5 3 Action Procedures 9-18 9.5.4 Activation of Emergency Organization 9-19 9.6 Decommissioning 9-21 9.7 References 9-21
- 10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1 10.1.1 Definitions 10-1 10.1.2 Authorized Place of Use 10-2 10.1 3 Quality Assurance 10-2 10.1.4 General Considerations 10-3 10.2 Safety Limits 10-3 10.2.1 Authorized Materials 10-3 10.2.2 Fuel Storage Provisions 10-3 10.3 Limiting Conditions 10-10 10.3.1 Limiting Conditions - Water Shield 10-10 10.3.2 Limiting condition - Criticality 10-10 10.4 Surveillance Requirements 10-11 10.4.1 Effluent Air Sampling 10-14 10.4.2 Effluent Water 10-14 viii
NEDC-21326C1 November 1979 TABLE OF CONTENTS (Continued)
Page 10.4.3 Sealed Sources 10-15 10.4.4 Instrumentation 10-15 10.4.5 Basin Coolers 10-16 10.4.6 Process Steam Bypass 10-17 10.4.7 Cask Liquid Coolants 10-17 10.4.8 Cask Coolant Sampling 10-18 10.4.9 Basin Water Qaemical Characteristics 10-18 10.4.10 Basin Water Radioactivity Sampling 10-19 10.5 Design Features 10-19 10.5.1 Fuel Storage Basin 10-19 10.5.2 Fuel Storage System 10-19 10.6 Administrative Controls 10-21 10.6.1 Responsibility 10-21 10.6.2 Organization 10-21 10.6.3 Plans and Procedures 10-23 10.6.4 Review and Audit 10-24 10.6.5 Action Required For Specification Noncompliance 10-25 10.6.6 Logs, Records, and Reports 10-27 10.7 References 10-27 11.
QUALITY ASSURANCE 11-1 11.1 Introduction and Summary 11-1 11.2 References 11-1 APPENDICES A.
See Index following divider A-i B.
See Index following divider B-1 ix/x
NEDO-21326C1 November 1979 LIST OF ILLUSTRATIONS Figure Title Page 1-1 General Location - Morris Opceation 1-3 1-2 General Electric Tract and Vicinity 1-4
.1-6 1-3 Map - GE Morris Operation Tract 1-11 1-4 Principal Facilities - Protected Area 1-5 Schematic - Morris Operation Basin Facilities 1-13 1-15 1-6 IF-300 Irradiated Fuel Shipping Cask 1-16 1-7 GE IF-300 Irradiated Fuel Shipping Cask 1-17 1-8 NFS-4 Shipping Cask 1-9 Truck Cask and Trailer Being Spotted in Receiving Area 1-18 1-20 1-10 IF-300 Cask ic Receiving Area 1-11 Cask Decontamination Area 1-22 1-12 IF-300 Cask on Cask Shelf 1-23 1-13 Cask Unloading Basin Deep Pit 1-24 1-26 1-14 Fuel Grappling Operations 1-15 Fuel Removal From Cask 1-27 1-28 1-16 Fuel Basket Loading 1-17 Fuel Basket Transfer 1-29 1-18 Fuel Movement in Storage Basins 1-30 1-19 Fuel Storage Basin Areas 1-31 1-20 Preparing IF-300 Cask for Shipment 1-33 1-21 Low Activity Waste System Schematic 1-34 1-22 Ventilation System 1-36 1-23 Basin Filter System 1-37 1-24 Basin Water Cooling System 1-38 1-25 Caek Sampling, Cool-Down, and Flush System 1-40 1-26 Lesk Detection, Pump-02t and Sampling System 1-41 1-27 Sewage Systems 1-42 3-1 Aerial Photograph - Morris Operation 3-2 3-2 Topographic Map - GE Tract and Vicinity 3-3 3-3 Contour Map - Morris Operation 3-4 3-4 Estimated Population Within a 5-Mile Radius of Morris Operation -
Circa 1970 3-8 3 4A Projected 1980 Population Within a 5-Mile Radius of Morris Operation 3-8a xi
NED0-21326C1 November 1979 LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 3-5 Estimated Population Within a 50-Mile Radius of Morris Operation 3-9 3-5A Projected 2000 Population Within a 5-Mile Radius of Morris Operation 3-9a 3-6 Estimated Population Within a 5-to-50-Mile Radius of Morris Operation - Circa 1970 3-10 3-6A Projected 1980 Population Within a 5-to-50-Mile Radius of Morris Operation 3-10a 3-7 Projected 1990 Population Within a 5-to-50-Mile Radius of Morris Operation 3-11 3-7A Projected 2000 Population Within a 5-to-50-Mile Radius of Morris Operation 3-11a 3-8 Annual Wind Rose at 35-f t Level at DNPS Site 3-27 3-9 Major Regional Geologic Structures 3-46 3-10 Generalized Stratigraphic Column for the Morris Operation S_Le 3-49 3-11 Correlation of Angle Boring and Trench Data 3-52 3-12 Map of the U.S. Showing Zones of Approximate Equal Seismic Probability 3-55 4-1 Spectra Comparison - 0.10g Ground Acceleration: RG 1.60 versus El Centro 1940 N-S 4-22 4-2 Spectra Comparison - 0.20g Ground Acceleration: RG 1.60 versus El Centro 1940 N-S 4-23 4-3 El Centro Accelerogram 4-24 4-4 Response Acceleration Spectrum - Morris Operation -
Main Building, Ground Motion, Dampinh Ratio = 0.005 4-25 4-5 Response Acceleration Spectrum - Morris Operation -
Main Building, Ground Motion, Damping Ratio = 0.010 4-26 4-6 Response Acceleration Spectrum - Morris Operation -
Main Building, Ground Motion, Damping Ratio = 0.020 4-27 4-7 Hydrodynamic Constants for Rectangular and Cylindrical Tanks 4-30 4-8 Vertical and Horizontal Design Response Spectra for Nuclear Power Plants 4-34 5-1 Contour Map - Morriz Operation 5-2 5-2 Cask Liftir.g Yoke 5-9 xii
NEDO-21326c1 November 1979 LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 5-3 NFS-4 Cask Being Lowered into Unloading Pit, Showing Use of Extension Hook 5-11 5-4 Low-Level Waste Compactor 5-14 5-5 Unloading Pit Doorway Guard 5-18 5-6 BWR Fuel Grapple 5-19 5-7 PWR Fuel Grapple 5-21 5-8 Morris Fuel Storage System 5-25 5-9 Typical Grid Assembly 5-26 5-10 Details of Storage Basket Lock Mechanism 5-27 5-11 Excavation at Morris Operation 5-31 5-12 Foundation Construction 5-32 5-13 Stainless Steel Basin Liners 5-35 5-14 Technicians " Vacuum Cleaning" Storage Basin Floor Area 5-38 5-15 Pump Room Equipment 5-41 5-16 Water Intrusion 5-55 5-17 LAW Vault Under Construction 5-56 5-18 Arrangement - LAW and Cladding Vault Equipment Pits 5-58 7-1 History of Morris Operation Basin Water Activity 7-7 7-2 Radiation Monitor Locations 7-21 7-3 Monitor and Sampling Locations (within 2 miles of Site) 7-29 7-4 Environs Monitoring Locations (within 5 miles of Site) 7-30 7-5 Environmental Monitoring Stations (within 5 to 15 miles of Site) 7-31 8-1 Event Diagram for Postulated Accidents 8-4 8-2 Kr-85 Activity as Function of Cooling Time for Different Fuel Exposures (Total Inventory in Fuel Rod) 8-16 8-3 Iodine, Krypton, and Xenon Decay 8-17 8-4 PWR Fuel Bundle Array at 2-inch Separation 8-33 8-5 Close-Packed Array of Four PWR Bundles 8-34 9-1 Corporate Organization Chart - General Electric Company 9-2 9-2 Morris operation Organization 9-5 9-3 Facility Modification Control Concepts 9-12 9-4 Emergency Plan Relationships for Morris Operation 9-16 9-5 Emergency Response Organization 9-20 xiii
NEDO-21326C1 November 1979 LIST OF ILLUSTRATIONS (Continued)
Figure Title Page 10-1 Rod Lattice k. - PWR Fuel km = k1 x Cwp x CPDxCCL 10-7 10-2 Rod Lattice k. - BWR Fuel k. = k1 x Cwp x Cpp 10-8 xiv
e..
NEDO-21326C1 November 1979 LIST OF TABLES Table Title Page 3-1 Cities of Greater Than 1,000 Popul' tion Within 30 Miles of a
Morris Operation 3-15 3-2 Nuclear Reactors Within 50 Miles of Morris Operation 3-19 3-3 Indrstrial, Transportation, and Military Activities (6-mile radius) 3-20 34 Local Temperature Data (CF) for Morris. Illinois 3-23 3-5 Total Precipitation end Total Snowfall (in.) for Morris and Joliet, Illinois 3-24 3-6 Thunderstorm Activity 3-28 3-7 Joint. Frequency Distribution of Pasquill Stability Class and Wird Direction, Dresden 150-ft Level (percent of total observations) 3-30 3-8 Stability, Frequency, and Wind Speed 3-32 3-9 Characteristics of tne Illinois River at Morris, Illinois 3-37 3-10 Characteristics of the Kankakee River at the Rt 66 Bridge,1971
-30
?-11 Well Water Analysis - Morris Operation Well 3-42 3-12 Microscopic Particle Size Distribution - Morris Operation Well 3-43 3-13 Morris operation Site Investigations 3-45 4-1 9 pent Fuel Fission Product Activity 4-2 4-2 Analyses, Fuel Exposures, and Cooling Times 4-5 4-3 Results of Wind Analysee 4-17 5-1 Typical Isotope Concentrations in Basin Water 5-42 5-2 Control Room Monitoring of Fuel Storage Functions 5-51 7-1 Fission Product Activity 7-3 7-2 Gamma Spectrum (E) for Fuel in Storage - Volumetric Source (S )
7-5 y
7-3 Morris Operation Radiological Monitoring Program 7-26 8-1 List of Tornade-Generated Missiles 8-25 8-2 Velocities and Kinetic Energies of Postulated Missiles in Water When Entering Fuel Pool in a Vertical Position 8-27 8-3 Prompt Fiesion Gamma-Ray Spectra 8-37 8-4 Dose, mR per Fission, at Basin Surface 8-39 10-1 Authorised Materials - Instrument, Calibration, and Laboratory Sources 10-5 10-2 Surveillance Requirements Summary 10-12 10-3 Summary Requirements System and Equipment Test and Calibration 10-13 15004 Xv