ML20238C959
| ML20238C959 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/30/1972 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20238C717 | List: |
| References | |
| DPC-ED-3, NUDOCS 8709100473 | |
| Download: ML20238C959 (364) | |
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1 l FOREWOHD The La Crosse Boiling Water Reactor (LACBWR) is an operating electric power station. It was built as part of the Atomic Energy Commission's second round power reactor demonstration program by Allis-Chalmers Manufacturing Com-pony under a contract with the Commission, signed in June 1962. The site for the reactor was provided by Dairyland Power Cooperative. The reactor was operated initially by Allis-Chalmers for the Commission under a Provisional Operating Authorization No. DPRA-5, issued by the Atomic Energy Commission on July 3, 1967. It has been operated by Dairyland Power Cooperative since October 31,1969 under Provisional Operating Authorization No. DPRA-6 issued to Dairyland Power Cooperative. The purpose of this report is to support the forthcoming application by Dairyland Power Cooperative to the Atomic Energy Commission for the issuance of a full-term operating authorization or license. This report assesses the existing or potential effects that LACBWR has or might have, on the environment. More specifically, the report summarizes the measurable effects to date as well as en-vironmental considerations inherent in the plar.t design. This report has been prepared to meet the intent of the National Environmental Policy Act of 1969 (P.L.91-910, Specific guidance as to the content of the report has benn derived from the draft guide for the preparation of environmental reports j for nuclear power plants issued in March 1971 by the Atomic Energy Commission I l for comment and interim use, and from the revised Appendix D of 10CFR50 issued { by the Atomic Energy Commission. { 1 Since the Atomic Energy Commission's initial actions as to the construction j and operation of LACBWR were made prior to the effective date of Appendix D of ' 10CFR50, no environmental report on the LACBWR has been previously submitted. This report was prepared by Deiryland Power Cooperative and Environmental Analysts, Inc., Garden City, New Y,:k. l h l l 1
l 9 Table of Contents Section Title Page Foreword 1.0 Introduction 1-1 1.1 Description of the Plant and its Site 1-1 1.2 Need for Locating Power Plant at the Site 1-2 2.0 The Site 2-1 2.1 Location 2-1 2.2 Human Activities 2-8 2.3 Historic Significance 2 - 51 2.4 Geology 2-55 2.5 Hydrology 2 - 61 2.6 Meteorology 2-75 2.7 Biota 2-90 2.8 Other Environmental Features 2-111 3.0 The Plant 3-1 3.1 External Appearance 3-1 3.2 Transmission Lines 3-3 3.3 Reactor and Steam-Electric System 3-6 3.4 Water Use 3-21 3.5 Heat Dissipation 3-30 3.6 Radwaste Systems 3-36 3.7 Description of Chemical and Sanitary Discharge to the River 3 - 52 3.8 Other Wastes 3--53 4.0 Environmental Effects of Site Preparation and Plant Construction 4-1 4.1 Construction Peilods and Manpower 4-1 , 4.2 Effects on Human Activity 4--2 4.3 Effects on Terrestrial Vegetation and Wildlife 4-4 4.4 Effects o- idjacent Waters and Aquatic Life 4-4 5.0 Environmental Effects of Plant Operation 5-1 5.1 Effects of Released Heat 5-2 5.2 Effects of Radioactive Releases 5-16 ) 5.3 Effects of Chemical and Sanitary Westes 5-49 ' 5.4 Other Effects 5-52 , 5.5 Assessment of Environmental Effects of Plant l Operation 5-57 6.0 Environmental Elfects of Accidents 6-1 6.1 Scope 6-1 1 6.2 Probability Categorization 6-3 i O 1 I
-O Table of Contents (Continued) Section Title Pcge 6.3 Dose Assessment 6-4 6.4 Class 2 -- Small Release Outside Containment 6-5 6.5 Class 3 -- Radwaste System Failure 6-7 6.6 Class 4 -- Fission Products to Primary System 6--12 6.7 Class 5 - Fission Products to Primary and Secondary Systems 6 6.8 Class 6 -- Refueling Accidents 6-13 6.9 Class 7 -- Spent Fuel Handling Accident 6-17 6.10 Class 8 -- Accident Initiation Events Considered in Design Basis Evaluation in the Safety Analysis Report 6-21 7.0 Unavoidable Adverse Effects 7-1 8.0 Alternatives to the Proposed Change in License 8-1 8.1 Alternatives to Construction 8-2 8.2 Not Providing the Power 8-3 - 8.3 Rodwoste System Alternatives 8-5 ! 8.4 Cooling System Alternatives 8-8 9.0 Lon'g Term Effects of Plant Construction and Operation 9-1 10.0 Irreversible and Irretrievable Commitments of Resources 10-1 11.0 Benefit-Cost Analysis 11-1 11.1 Background Information 11-1 11.2 Benefits from Operation of the LACBWR 11-2 11.3 Evaluation of Subsystem Designs 11 -4 11.4 Alternative Plant Designs 11 -10 12.0 Environmental Approvals and Consultations 12-1 Appendix I O _ - _ - - - - - - - - _ - - - - - - --- b
O Tables Table No. Title Page 1.2-1 Projections of Peak Demand and Generating Capacity for Dairyland Power Cooperative through 1981 1-0 2.1-1 Incorporated Cities, Towns and Villages within 25 Miles of LACBWR 2-3 2.2-1 LACBWR Area Population Distribution,0-5 Miles 2-11 2.2-2 LACBWR Aa:a Population Distribution,5-25 Miles 2-12 i 2.2-3 Population of County Subdivisions within 25 Miles of the LACBWR Site 2-13 2.2-4 Projected LACBWR Area Population for the Year 2010,0-5 Mile Radius 2-19 2.2-5 Projected LACBWR Area Population for the Year 2010,5-25 Mile Radius 2-20 ' 2.2-6 Existing Land Use 2-24 2.2-7 Selected Agricultural Data 2-27 ! 2.2-8 Vernon County Housing Data,1970 2-31 2.2-9 Characteristics of Housing Units in the Village and Town of Genoa 2-32 2.2-10 Schools in the Vicinity of the LACBWR Site 2-34 2.2-11 Selected Data on Employment and Economic Activity in Vernon County, Wisconsin 2-38 2.2-12 Selected Data on Employment and Economic Activity in Houston County, Wisconsin 2-39 2.2-13 Selected Data on Employment and Economic Activity in Allamakee County, Iowa 2-40 2.2-14 Lockages at Dam No. 8, Genoa,1965 .971 2-45 ; 2.2-15 Entry Prents to the Mississippi within Five Miles of the LACBWR Site 2-46 i 2.4-1 Description of Well Cuttings, Prepared by the late f . T. i i l Thwaites, Wisconsin Geological and Natural History l Survey ! i O 2 - 57 j ! l i ! I L _ _ _ _ _ -_ _ i
g i LO-f l Tables'. (Continued) Tchle No. Title Page-2.5 Flood Frequency Analysis 2-64 2.5-2 Minimum and Average Fbws at the Winona Gauging Station 2 2.5-3 Analysis of Water from LACBWR Supply Wells (ppm) 2-69 2.5-4 Records for Selected Wells near the LACBWR Site, Vernon County, Wisconsin 2-72 2.6-1 Meteorological Data for the Year 1971 2-77 2.6 Frequency Distribution of Wind Speeds (%) 2- 83 2.6-3 Inversion Frequency for La Crosse Area 2-87 2.6-4 Frequency of Night Winds of 7 mph or Less (%) 2-88 2.7-1 Day Use by Waterfowl on. Pool 9 of the Mississippi River by 18-Week Periods 2-92 2.7-2 Waterfowl Kill Data by Sportsmen en Pool 9 of the Mississippi River 2-93 2.7-3 List of Common Aquatic Plands found in the Upper Mississippi River 2-96 2.7-4 List of Trees found in the Oak and Bottomland Hardwood Type Forests Adjacent to the LACBWR Site 2-97 2.7-5 ' Check List of Amphibians and Reptiles found in the Upper Mississippi River Wild Life and Fish Refuge 2-98 2.7-6 Check List of Birds found in the Upper Mississippi River Wild Life and Fish Refuge 2-100 2.7-7 Check List of Mammals found in the Upper Mississippi River Wild Life and Fish Refuge 2-108 2.7-8 Species, Composition and Relative Abundance in Fish Samples taken by Electrotishing at Three Locations Below Dam No. 8 for Five Sampling Periods in 1961 2-110 2.8 Preoperational Radiological Survey Samples, Analyses and Sensitivities 2-112 2.8 Gross Beta Activity in Surface Air 2-113
. 2.8-3 Gross Beta Activity in Precipitation 2-114
, LO ! I 1
O Tables (Continued) Table No. Title Page 1 2.8-4 River Water Gross Alpha and Gross Beta Activity, April 1965 through March 1966 2-115 2.8-5 River Water Radioactivity 2 -117 2.8-6 River Water Strontium-90 and Cesium-137 Activities, April 1965 through March 1966 2-118 2.8-7 Top Water Radioactivity, April 1965 through March 1965 2-119 2.0-8 Well Water Radioactivity, April 1965 through March 1966 2-120 2.8-9 River Silt Radioactivity, April 1965 through March 1966 2 -121 2.8-10 Soil Radioactivity 2 -122 2.8-11 Vegetation Samples 2-123A 2.8-12 Fish Samples, April through September 1965 2-124 2.8 ' - Milk Samples, June 1965 through March 1966 2-125 j 2.8-14 Yearly Dose Measurements in the LACBWR Vicinity Calculated from Quarterly TLD Readings 2-126 i 3.3-1 LACBWR General Plant Design 3-17 3.4-1 Subsystems Supplied by the Low-pressure Service Water ! System 3-26 { 3.4-2 Liquid Waste Sources 3-29 1 3.6-1 LACBWR Stock Release Data 3-39 3.6-2 Isotopic Breakdovri of Airborne Releases 3-40 l 3.6-3 LACBWR Liquid Waste Batch Release Data 3-46 3.6-4 Average Concentration of Radionuclides discharged to the I Mississippi River 3 -47 1 3.7-1 intake and Discharge Water Quality 3 -54 i 3.7-2 The Demineralized Regeneration Cycle 3-55 3.7-3 Description of Demineralizers Regeneration Discharge 3-56 5.1-1 Zone A Electrofishing Catch Data, Combined for Monthly Collections from August 1969 to March 1970 5-6 5.1 -2 Commercial Fish Catch on the Wisconsin Side of the I
'O Mississippi River from 1965 through 1970 for Pools i 8 and 9 l
i l
l O Tables (Continued) Table No. Title Page 5.1-3 Use of Mississippi River Water by LACBWR 5-12 5.1-4 Occurrence of Phytoplankton Collected Above and Below the Heated Outfall of the Dairyland Power Cooperative Complex at Genoa, Wisconsin 5-12A j 5.1 -5 Occurrence of Zooplankton Collected Above and Below the Heated Outfall of the Dairyland Power Complex 5-13 5.1 -6 Species and Occurrence of Benthos Collected on Four Transects on the Mississippi River at Genoa, Wisconsin, in June 1972 5-13A 5.2-1 Dilution Factors for LACBWR Effluents 5-20 5.2-2 Individual Dose Rates from the Liquid Discharge 5-22 5.2-3 Bioaccumulation Factors for Radionuclides in Liquid Discharge from the LACBWR 5-23 5.2-4 Doses to the Population from LACBWR Liquid Release in the First Half of 1972 5-27 5.2-5 LACBWR Tritium Releases in Waste Water 5-28 5.2-6 Dose to Biota in the Mising Zone 5-29 5.2-7 Calculated Maximum Hypothetical Individual Off-Site Dose due to LACBWR Stack Releases 5-30 5.2-8 Cumulative Population, Annual Gamma Man-Rem and Average Doses from the Gaseous Effluent Released from LACBWR 5-30A 5.2-9 Environmental TLD Results 5-33 5.2-10 Summary of Environmental Monitoring Program Sampling and Analysis 5-45 5.2-11 Iodine-131 Measured in Milk from Dairies at Genoa and La Crosse 5-35 I 5.2-12 Iodine-131 in Milk from Neighboring Farms in 1972 5-39 5.2-13 Gross Beta-Gamma Activity in Mississippi River Silt 5-42 5.2-14 Radioactivity Measured in Fish taken from the Mississippi River in the LACBWR Vicinity during 1972 5-43 0
L l
=O Tables (Continued)
Table No. Title Page 6.1 - .1 Accident Classification 6-2 6.3-1 Summary of Radiological Consequences of Postulated Accidents 6-6 6.5-1 Isotopic Analysis and Release of 25% of Pressurized Holdup Tank Content 6-8 6.5-2 1sotopic Analysis of Waste Water Storage Tank 6-10A S.5-3 Isotopic Analysis and Release of 100% of Pressurized Holdup Tank Contents 6-14 6.6-1 Source Terms for the Described Class 4 Event 6-16 6.8-1 Estimated Releases for a Fuel Bundle Drop 6-18 i 6.8-2 Estimated Releases for a Heavy Object Drop onto Fuel in Core 6-19A 6.9-1 Estimated Releases for a Heavy Object Drop onto Fuel Rock 6-20 6.9-2 Estimated Releases for a Fuel Cask Drop 6- 22 6.10-1 Estimated Releases for a Small Pipe Break 6-25 6.10-2 Estimated Releases for a Large Pipe Break 6-28 6.10-3 Estimated Releases for a Rod Drop Accident 6 -11 6.10-4 Halogens Released from a Small Steamline Break 6-33 6.10-5 Noble Gases Released from a Small Steamline Break 6-34 f 6.10-6 Halogen Releases from a Large Steamline Break 6-35 11.2-1 Benefits from the Proposed Facility 11-3 11.3 -1 Alternative Radwaste Systems 11 - 5 i 11.4--1 Alternative Plant Design Summary 11-12 j 12.0-1 Permits and Approvals Received for LACBWR 12-3 12.0-2 Current AEC Operating-Personnel Licenses 12-6 A-1 Joint Frequency Distribution of Stability and Wind Speed Conditions A-4 A-2 Plume Rise (meters) computed by Briggs' Formulae for the Dominant Meteorological Conditions in Table A-1 A-5 O
'i l
l 1 i O . Figures Figure No. Title Page 1.2-1 Map of the Dniryland Service Area 1-3 1,2-2 Estimated Load-Generating Capability Data 1-7 2.1 -1 LACBWR Exclusion Area 2-2 2.1 -2 LACBWR Property Map 2-7 i 2.2-1 LACBWR Area Population 1970 Census,0-5 Miles 2-9 2.2-1 LACBWR Area Population 1970 Census,5-25 Miles 2-10 2.2-3 Projected LACBWR Area Population for the Year 2010,0-5 Miles 2-17 2.2-4 Projected LACBWR Area Population for the Year 2010, 5-25 Miles 2-18 2,4-1 Schematic East West Geologic Cross Section Through LACBWR Site Showing Approximate Relation of the Water Table and Piezometric Surface to the Missis-sippi River 2-56 2.5-1 Flood-Frequency Curve for Mississippi at LACBWR 2-65 2.5-2 Stage-Discharge Relation of Mississippi River at Mile 679.02 (Lock & Dam No. 8) Only Annual Floods 1970-1962 Are Plotted 2-67 2.5-3 Portion of U.S.G.S. Stoddard 15-Minute Quadrangle Showing Minor Drainage Features and Location i of Wells 2 - 71 j 2.6-1 Yearly Variation in Surface Winds, La Crosse Munici-pal Airport 2-80 2.6-2 Seasonal Variation in Surface Winds, LACBWR Site 2-80 2.6-3 Wind Rose for LACBWR Stack-Top / L < tion Based on 1968-1970 Data 2 - 82 2.6-4 Yearly Variation in Upper Air Winds, St. Paul, Minnesota 2-85 2.7-1 Aerial View of the Genoa National Fish Hatchery 2-94 2.7-2 Aerial View from the South of the LACBWR 2-95 l -o L l i l
3 e 1 Figures (Continued) Figure No. Title Page l 2.8 -1 LACBWR Environmental Survey Air Mcnitcring and Dose l Assess nent Stations 2-111A l 3.1 -1 Dairyland Power Cooperative, La Crosse Boiling Water Reactor Nuclear Power Plant 3-2 3.2-1 Transmission Lines 3-4 3.2-2 Map of Transmission Lines in Vernon, Houston, La Crosse and Allamakee Counties 3-5 3.3-1 LACBWR Regenerative Cycle - Heat Balance Diagram 3-7 3.3-2 Cross Section thru Reactor Vessel--Its Core and Biological Shield 3-10 3.3-3 LACBWR Fuel Element Details 3-11 3.3-4 LACBWR Fuel Elament Details 3-12 3.4-1 Water Use (River Water) 3-23 3.4-2 Water Use (Well Water) 3-24 3.5-1 LACBWR Intake Structure 3 -31 3.5-2 Circulating Water System Discharge Structure 3-32 3.5-3 Circulating Water Systems for LACBWR (Genoa-2) and Genoa-3 3-34 3.6-1 Schematic Diagram of the Gaseous Radwaste System 3-38 3.6-2 LACBWR Reactor Plant Liquid Waste Flow Diagram 3-45 4.2-1 Photograph of the Public Access Area Provided by Dairyland Power Below the Power Complex 4-3 l 5.1 -1 Upstream View of LACBWR and Genoa 3 5-3 j 5.1-1A Water Temperature Zones in Department of Natural resources Study 5-3A 5.1 -2 Lecations of Aquatic Sampling Transects 5-11 5.2-1 Important Radiation Exposure Pathways for Liquid Releases from LACBWR 5-18 5.2-2 Important Radiation Exposure Pathways for Atmos-pheric P< leases from LACBWR 5-19 9 5.2-3 LACBWR Vicinity Semi-Weekly Air Particulate Acuvity 5-37
3
1.0 INTRODUCTION
1.1 DESCRIPTION
OF THE PLANT AND ITS SITE l The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa 2, is located on the east bank of the Mississippi River at Genoa, Vernon County, Wisconsin. The plant was completed in 1967 and has a capacity of 50 MWe its site is at mile 678.6, approximately 3300 feet below U.S. Lock & Dam No. 8, and about 17 miles south of the city of La Crosse, Wisconsin. The LACBWR shares a 163.5-acre site with two conventional steam plants, the 14-MWe Genoa 1 and the 350-MWe Genoa 3. Cooling water for the LACBWR's once-through cooling system is drawn fru the Mississippi River. The LACBWR shares a common discharge structure with Genoa 3. The location of the cooling system outfall,200 feet downstream from the intake, is such that the heated dis-charge is directed into Thief Slough, a side channel separated from the main channel of the Mississippi by Island 126. O 1-1
I.
,Q l.2 NEED FOR LOCATING POWER PLANT AT THE SITE Dairy 1 cad Power Cooperative is the largest consumer-owned, non-profit generation and transmission system in North America. The Cooperative's forma-tion followed the passage of the Rural Electrification Act of 1936 and subsequent merger of the Wisconsin Power Cooperative and Tri-State Power Cooperative on December 16, 1941.
The Dairyland Cooperative is headquartered at La Crosse, Wisconsin. and has a total generating capability of 705,000 kilowatts. This capacity supplies the total electrical requirements of 27 distribution cooperatives in western Wiscon-sin, southeastern Minnesota, northeastern Iowa and the northwestern tip of Illinois. Annual sales of energy exceed 1.4 billion kilowatt hours. The Dairyland ser6ce area is shown in Figure 1.2-1. Low-cost electricity is transmitted from eight Dairyland Power generating stations by way of 2,900 miles of high voltage transmission lines to 200 trans-mission and distribution substations that cover 40,000 square miles of the Upper Midwest. This electric energy is delivered to 120,000 farmsteads, rural homes and rural businesses by means of distribution power lines built and maintained by the 27 locally-owned rural electric cooperatives. Member-consumers are served by I nineteen distribution cooperatives in Wisconsin, three in Minnesota, four in Iowa ! and one in Illinois. Seven of the eight Doiryland Power generating plants are located in Wiscon-sin. Four fossil-fired steam stations are situated on the east bank of the Mississippi River -- two at Genoa, one <:t Alma and one at Cassville. Genoa is also the site of the La Crosse Boiling Water Reactor (LACBWR). Other generating stations include a hydro-electric installation on the Flombeau River neer Lady-smith, a diesel plant at Chippewa Falls and a diesel-gas plant at Twin Lakes, Minnesota. ' As a major energy producer in the Upper Midwest, Dairyland Power Coopera-tive is a chartar member of two electric power industry groups: the Upper O 1-2
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9 4..; . I t LA CROSSE, WISCONSIN c-a g""". - w..a n. mus yjg 'p 'l_*""1c'% FIG.1.2 - 1 MAP OF THE DAIRYLAND SERVICE AREA
- . 1-3
Mississippi Valley Power Pool and Mid-Continent Area Power Planners. The Upper Mississippi Valley Power Pool is a volunteer organization of five genera-tion and transmission cooperatives and seven investor-owned power companies who have contracted among themselves for the interchange of wholesale power and joint planning of new energy production and bulk transmission facilities. As a result, each member power supplier, through planned interconnections, is able to purchase energy on short-term, long-term, off-peak or emergency conditions, or to sell surplus electricity to other pool members. This, of course, greatly increases the reliability of every pool participant. Participation in the Upper Mississippi Valley Power Pool provides another important benefit to member power producers: substantial savings in production costs. The ability to exchange power at a nearby interconnection fosters the use of generating units close to large loads and thus reduces line losses in the trans-mission of energy. Additional savings for pool members are gained by their ability to function safely with less reserve generating capacities than would be possible by operating without interconnection arrangements. The Mid-Continent Area Power Planners, commonly known as MAPP, is a volunteer organization of 50 power producers -- generation-transmission coopera-tives, investor-owned utilities, municipal electric systems, and public power dis-tricts -- from 10 North Central states and the Canadian province of Manitoba. The U.S. Bureau of Reclamation, although not a formal member, also participates in MAPP activities. Plans have been formulated to inmrporate MAPP into a formal power pool. MAPP plays a maior coordinating role in the planning and construction of large-capacity generating stations and high voltage transmission facilities through-out the widespread service areas of member power suppliers. It also coordinates interconnections of the Upper Mississippi Valley Power Pool with other energy pols in und adjacent to the Upper Midwest. As a member of MAPP, and pursuant to the agreement among the members of the pool, Dairyhnd Power is required to maintain sufficient capacity to meet its peak O l-4 L___ _ _ -__ --
l ! o V demand, plus a reserve capacity of 12% of its peak demand. Due to increased reliance on larger units, this margin will be increased to 15% on May 1,1974. In order to meet such a requirement, a member of the Pool can either install such capacity on its own system or purchase such capacity. Dairyland presently relies entirely on its own capacity. The MAPP reserve criterion is designed to ensure that the probability of loss of load within the Pool is not greater than one day in ten years. The Pool, in determining whether the abov probability will be exceeded, assumes that adequate !
)
interconnections exist to transfer reserves among members. ) Shown on Table 1.2-1 are Dairyland's projections of pesk demand and gener-ating capacity required by the MAPP for the years 1971 through 1981. These pro-jections are illustrated in Figure 1.2-2. The projections are based to a great , 1 extent on predicted increases in population and per capita income within its service area, resulting in an increased use of electric power for various services. As noted, Dairyland has an installed capacity of 705 megawatts. By 1976, based on current load projections, there will be a power deficit in the cooperative of 59 megawatts. By 1981, this deficit will be 296 megawatts. It is apparent that capacity additions will be necessary, either by construction of new units or pur-chase from outside sources. The LACBWR presently constitutes approximately 7% of Dairyland's installed capacity. Further,its generation costs are comparable with the lowest in the Dairyland system. The loss of this unit would have an effect on both the economics and reliability of the Dairyland System. The LACBWR is an essential factor in the supply of power to the service area served by the Cooperative, if this plant were not available, immediate steps would have to be l ' taken to find a substitute energy source. 1 The startup of the LACBWR facility did not allow retirement of any older j units. The growth and age of the Cooperative is such that retirement of older units are not a factor in the current projections. As the site on which the LACBWR is located is an extension of a site that had already been in use for power gencr-O l l 1-5 I j 1 1
O Table 1.2-1: Projections of Peak Dercand and Generating Capacity for Dairyland Power Cocperetive through 1981. l 1 1 Forecast Maximum Sales Generation Year Demand (MW) Obligation Reserve Requirements 1971 368 289 44 701 1972 394 259 47 700 1973 421 229 51 701 1974 450 196 68 714 1975 480 163 72 715 1976 513 174 77 764 1977 549 174 82 805 1978 587 174 88 849 1979 628 174 94 896 1980 672 174 101 947 1981 719 174 108 1001 O I-6
1000 - GENERATION REQUIREMENTS 1 (CAPACITY OBLIGATIONS PLUS SALES ) TOTAL C APACITY OBLIGATION (INCLUDES MAX. DEMAND PLUS RESERVE) 800 - N I '
. /
NET SYSTEM CAPABILITY 600 - (FORECAST MAX. DEMAND 8 RESERVE) O ti S 400 J 200 - M / SALES OBLIGATION O 1971 1973 1975 1977 1979 19 81 YEAR 9 FIG l.2-2 ESTIMATED LOAD-GENERATING CAPABILITY DATA 1-7
Q ation by two fossil fired electric generating units, the location of the LACBWR unit at this site represented a minimal change in local land use patterns. The operation of LACBWR did allow the modification of the operation of smaller fossil units, namely Alma 1,2 and 3, and Stoneman 1 and 2. These units are now cut back during off-peak hours, especially at night, and are used as cycling generation. O j 1-8
O 2.0 THE SITE 2.1 LOCAT10N The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa 2, is on the east shore of the Mississippi River in the Village of Genoa, Vernon County, Wisconsin. The location coordinates are: latitude 43* 13' 35" North, longitude 91* 13' 53" West. The LACBWR and two conventional steam plants are located on a property of 163.5 acres in Section 32, Town 13 N., Range 7W, which is owned in fee by the Dairyland Power Cooperative. The property, shown in Figure 2.1-1, includes:
- all of Government Lot 2 except the rights-of-way of State Highway 35 and of the Burlington Northern Railroad;
- all of Government Lot I lying west of the railroad, and
- all of Government Lots 5,6 and 7.
The LACBWR stands on made land at an elevation of 639 feet MSL, or 19 feet above the normal elevation of Pool 9. The reactor is 300 feet from the river bank and 475 feet west of the railroad. The site is at mile 678.6 above the mouth of the Ohio. U.S. Lock and Dam No. 8 is about 3300 feet upstream. The Wisconsin River joins the Mississippi 40 miles south of the plant, just below Prairie du Chien. The LACBWR is 17 miles south of the City of La Crosse and a mile south of the village of Genoa. The nearest community on the west shore is Reno, Minnesota. Located three miles to the northwest, Reno is an unincorporated hamlet of about 60 people. The nearest community in Iowa is New Albin (pop. 664), five miles south of the plant, but separated from the Mississippi by on expanse of alluvial land at the mouth of the Upper lowa River. Victory, Wisconsin, five miles south of the plant on the east shore, is an unincorporated hamici of about 80 people. The nearest river crossing is 14 miles downstream from the reactor, at Lansing, Iowa (pop.1,218). Table 2.1-1 shows the distance and direction from the site of communities within a 25-mile radius. 9 2-1
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O Table 2.1-1: Incorporated Cities, Towns oud Villages Within 25 Miles of LACBWR. I Distance Direction Community From Site From Site Population Genoa Village 1 N 305 Reno (uninc.) 3 NW 60 New Albin Town 5 S 644 Victory (uninc.) 5 S 80 Stoddard Village 6.5 N 750 Chaseburg Village 9 NE 224 Brownsville Village 9 NNW 417 De Soto Village 10 S 295 Eitzen Village 12.5 WSW 208 Caledonia Village 14 WNW 2,619 Lansing Town 14.5 S 1,218 Hokah Village 15 NNW 697 Coon Valley Village 16 NE 596 Ferryville Village 17 SSE 183 La Crosse City 17 N 51,153 La Crescent Village 18 NNW 3,142 Viroqua City 18 E 3,739 Gays Mills Village 20 SE 623 Westby City 20 ENE 1,568 Spring Grove Village 21 W 1,290 Houston Village 22 NW 1,090 Onalaska City 22 N 4,090 Mount Sterling Village 22 SE 181 Lynxville Village 23 SSE 149 Waukon City 24 SW 3,883 Waterville Town 24 S 158 Readstown Village 24 4 ESE 395 Soldiers Grove Village 25 ESE 514 i West Salem Village 25 NNE 2,180 i Dakota Village 25 MMw 369 ! i Source: 1970 Census of Population (See Table 2.2-3) 0 2-3
9 OL 2.1.1. Environs of the Site The valley'of the Mississippi River in this area is cut deeply into highly dissected upland. ' From La Crosse to Lansing the valley is relatively straight, l trending almost due south, and ranges in width from 2.5 to about 4.5 miles. The valley walls' rise sharply to the upland,500 to 600 feet above the level
<f the river. The action of tributary streams nas cut the walls into a series of distinct bluffs, looming above the highways on either side of the river.
Beyond the bluffs, tributary streams have cut numerous short, steep walled valleys, known as coalees, into the gently rollhg upland surface. The upland areas, as well as the more level coulee floors, r.re cultivated and grazed. A few miles north of the plant, the Mississippi River presents an almost unbroken expense of water, some 2.5 miles wide. At the plant site, however, the river's main channel has narrowed to less than tif) feet. The rest of the valley floor is made up of marshy islands and low-lying sitemland cut by a maze of side channels, sloughs, ponds and backwaters. The adjacent areas to the north, west and south of the Dairyi .ud property are owned by the U.S. Government. Port of the Federal property is used by the Corps of Engineers for Lock and Dam No. 8. The balance is included in the Upper Mississippi River Wild Life and Fish Refuge. l Except for the small upland portion of Lot 2, the DPC property is bounded on the east by the parallel rights-of-way of the Burlington Northern Railroad and
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. State Highway 35. The property on the east si4 of the highway is privately held.
In the narrow area between the highway and the bluffs there are several houses, the nearest of which is 1192 feet from the reactor. The farmstead nearest the site is on the upland approximately one mile east and is separated from the LACBWR site by a 500-foot bluff. A scenic casement held by the State of Wisconsin limits development within 350 feet of Highway 35, which has been designated a part of "The Great River Road" tourist route. O 2-4
I 1 Y O > The LACBWB exclusion area is shown in Figure 2.1-1. The minimum radius ) of the exclusion area is 1109 feet (0.21 miles) which is the creo J access con- l 3 trolled by DPC. It consists of DPC property, highway and railroad right-of way, j and a portion of the river near the reactor. It does not include the houses men ^ioned i 1 above. i 4
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.O 2.1.2 Other Uses on Dairyland Power Cooperative's Genoa Property Approximately 950 feet north of the LACBWR is Genoa 1, a 14-MWe fossil-fueled generating plant, which is currently being converted to oil firing. Genoa 1 is at an elevation of 637.5 feet. The station building is 170 feet long,115 feet wide and 42 feet high, with a stack elevation of 72 feet above grade. Genoa 3, a 350-MWe coal-fired generating facility, is approximately 175 feet south of the LACBWR at an elevation of 642 feet. Tb . main building is 232 feet long,196 feet wide and has a maximum height of 205 feet. The adjacent service i building, which shares the north wall of the main building,is 61.5 feet wide,160 j feet long and 28 feet high. The Genoc 3 stack rises 500 feet above grade elevation. I ApprMmately 160 feet northwest of the LACBWR is a self-supporting, lattice-type transrssion tower,185 feet high. It supports a 161-KV transmission line running to a similar tower on the west shore of the Mississippi. Between the LACBWR and Genoa 1 is a switchyard approximately 600 feet long and 220 feet wide, containing 34.5-KV,69-KV and 161-KV switchgear. The LACBWR substation is connected to the switchyard by a 69-KV transmission line approximately 750 feet long. This was the only transmission line constructed for the LACBWR, whose power is delivered to the Dairyland/ system via trar:smission facilities previously constructed. A large a oc south of Genoa 3, comprising the southern edge of Lot 5, all but ! the southeast cc ner of Lot 6 and a part of Lot 7, has been diked to provide an ash disposal area (c. enoa 3. Approximately 3000 feet south of the LACBWR, on Dairyland property but outside the exclusion area, is a public boat launching ramp with a parking lot that can accommodate over 100 cars with boat trailers. An estimated 30 cars normally use the lot, although it is sometimes fall during peak holiday or weekend { periods. The lot is entered by the river access road, which ruas parallel to and just west of the railroad tracks. The road runs south from thr site entrance for i approximately 1500 feet, then southwesterly to the parking lot. ;%e Figure 2.1-2) ! O ; 2-6 i
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' site --J VERNON COUNTY, N 67a "J BOAT l tAspino d
( WISCONSIN l ISLAND 126 a , f LOT 7 LOT 4
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j NOTE' ISL AND 126 IS UNDER THE r JURISDICTION oF UPPER I / MISSIS $1PPI RIVER WILD 6 tire AN nSH REFUGE. I, l u-sTe INDICATES witEs AsovE THE l wouis or Tat omo Riven. h 1 o l FIG. 2.1-2 LACBWR PROPERTY MAP 2-7 l
4 O 2.2 HUMAN ACTIVITIES 2.2.1 Population in this section, existing (197 Census) and projected population data are presented in terms of distance and direction from the LACBWR site. The area within a 25-mile radius of the site has been divided concentrically into rings and, by compass direction, into 16 sectors of 22 30' each. The sectors are centered on the compass points indicated. Within each sector, population is given by one-mile increments for the first five miles and by five-mile increments for the area between the five-mile and i 25-mile radii, making a total of 144 population zones (Figures 2.2-1 and 2.2-2). Based on 1970 census data, an estimated 122,700 people live v ithin a 25-mile radius of the LACBWR (Tables 2.2-1 and 2.2-2). Of this population,just about half was accounted for by the City of La Crosse and the neighboring com-munities of Onalaska, Wisconsin, and La Crescent, Minnesota (Table 2.2-3), which comprise an urbanized area centered approximately 17 miles north of the reactor site. The immediate vicinity of the LACBWR site is sparsely po'pulated. Only
.t 6,832 people live within a 10-mile radius, and only 1,553 within a five-mile radius. The largest community within the five-mile radius is the Village of Genoa, which has a population of 305. The bulk of its population,270 persons, is located NNE of the site beyond the one-mile radius.
For the pu yose of estimating 1970 population, the zones were divided into two categories. The first category consists of the 80 zones within the initial five- l mile radius. The second consisted of the remaining 64 zones between the five-mile and 25-mile rodii. The zones in the first category are relatively small. Those within a one-mile radius of the plant have on area of approximately 125.6 acres. Those between the four-mile and five-mile ;adii are approximately 1130 acres or 1.8 square miles. ' Since census data on such a fine scale is not available, Dairyland Power Coopera-tive used United States Geological Survey maps and counted the number of homes i O i l, 2 -- 8 I I l 1 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ . _ _ _ ._J
i l l O 1 N . 1 32 12 __ 24 NW - NE , 12 l 24 0 28 94 ; i 60 24 8 0 20 12 32 24 0 12 270 32 l 4 0 12 4 45 i O O 0 8 O 4 W 16 ,2 e o o _ o e ,2 i2 72 E < 0 12 O O 16 16 12 , y, 16 0 16 12 0 8 8 12 12 O l2 24 g 0 3G 8 12 20 3 M. 20 0 40 16 SW 215
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20 s u. j S I FIG.2. 2-1 LAC 8WR AREA POPULATION . 1970 CENSUS I 0-5 MILES I O j i 2-9
O N ! 9571 1314 3291 NE NW ~ 35,518 15 0 4799 2040 871 494 4839 1352 1030 2 019 l 41 4 468 592 1010 1068 1463 194 240 779 i 2234 447 145 242
- i. i W 1904 471 3 19 142 1 7 1 246 493 4581 860 E J
132 359 384 492 su 238 370 443 635 260 - 709 537 299 301 1435 OW 879 13 5 219 1868 364 IS M. 1285 755 448 1271
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314 l SW SE 20M.- 7533 673 814 25 M.~ S FIG.2.21 LACBWR AREA POPULATION 1970 CENSUS 5-25 MILES O 2 - 10
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4 1 Table 2.2-1: LACBWR Area Population Distribution 0-5 Miles Population at Inclusive Distance (Miles) Sector Direction 1 2 3 4 5 Total 1 N 4 12 24 12 32 84 2 NNE 50 270 20 28 24 392 3 NE O 12 12 8 44 76 4 ENE 4 8 4 32 32 80 5 E O 8 12 12 72 104 6 ESE 12 16 16 12 2tt 80 7 SE 16 16 12 20 16 80 J l 8 SSE 58 8 36 tio 24 166 9 S 0 8 12 0 20 40 10 SSW 0 0 0 0 215 215 { 11 SW 0 0 0 8 20 28 12 WSW 0 0 12 12 12 36 1 I 13 W 0 0 8 12 16 36 l 14 WNW 0 0 4 2tl 12 40 j 15 NW 0 0 0 60 2t1 84 16 NNW 0 0 0 0 12 12 l l Total 144 358 172 280 599 1553 O 2 - 11 i
O Table 2.2-2: LACBWR Area Population Distribution ! 5-25 Miles Population at , Inclusive-Distance (Miles) Sector Direction 5 10 15 20 25 Total 1 N 84 1,010 4,839 45,518 9,571 61,022 2 NNE 392 240 2,019 2,040 3,291 7,982 3 NE 76 1116 592 1,352 871 3,307 4 LNE 80 2tl2 447 779 1,068 2,616 , 5 E . '4 246 493 4,581 860 6,284 ) {' 6 ESE 80 359 370 709 1,435 2,953 7 SE 80 238 301 36t1 1,271 2,254 l 8 SSE 166 260 135 448 673 1,682 9 S tt0 332 1,868 314 814 3,368 l 1 10 SSW 215 635 879 755 7,533 10,017 11 SW 28 (192 299 219 1,285 2,323 12 W3W 36 132 38tl 4L13 537 1,532 13 W 36 142 319 Lt71 1,904 2,872 14 WNW tio 145 2,234 1,463 414 4,296 15 NW 104 196 Lt 68 49tt 1,501 2,763 16 NNW 12 19tt 1,030 ti ,7 99 1,31y 7,3y9 Total 1,553 5,279 16,777 64,7 t19 3tl ,3 tl2 122,700 0 2 - 12
O Table 2.2-3: Population of County Subdivisions Within 25 Miles of the LACBWR Site
- County Subdivisions 1970 1960 Percent Change IOWA Allamakee County 17,168 17,636 2.7 Center township 383 496 -22.8 French Creek township 212 31tt -32.5 llanover township 262 291 -10.0 lowa township 873 891 - 2.0 New Albin town 6titt 6tt3 0.2 Jefferson township 6tt6 677 It . 6 Lafayette township L136 457 ti . 6 Lansing township 1,625 1,798 - 9.6 Lansing town 1,218 1,325 - 8.1 Makee township 4,351 ti,255 2.3 Waukon city (part) 3,68 tt 3,576 3.0 i Paint Creek township 518 708 -26.8 Waterville town 158 184 -14.1 Taylor township 481 479 0. Lt Union City township 3ttl 388 -12.1 Union Prairie township 731 623 17.3 Waukon city (part) 199 63 215.9 Waterloo township L106 468 -13.2 Winneshick County 1,299 1,537 -15.5 Glenwood township tt 65 535 -13.1 liighland township 372 tiB 6 -23.5 Pleasant township (162 516 -10.5 lowa Totals 18, tl 67 19,173
_3 . 7 MINNESOTA llouston County 17,556 16,588 5.8 Black llantner township 323 LF35 -25.7 Brownsville township 358 771 -53.6 Brownsville village 417 382 9.2 Caledonia township 585 620 - 5.6 Caledonia village 2,619 2,563 2.2 Crooked Creek township 30tt 359 -15.3 O (Continued) 2 - 13
1 l O ) Table 2.2-3: (Continued) 1 Eitzen village 208 181 lit . 9 liokah township 356 1,027 -65.3 i iiokah village 697 685- 1.8 l Ilouston township L107 41(1 - 1.7 llouston village 1,090 1,082 0.7 Jefferson township 206 207 - 0.5 LaCrescent township 1,486 785 89.3 LaCrescent village 3 , 1112 2, 62 tt 19.7 Mayville township 535 456 17.3 i Money Creek township Lt7 9 tl27 12.2 j Mound Prairie township 432 50tf -14.3 1 Sheldon township 361 366 - 1.4 Spring Grove township 539 582 - 7 . 11 l Spring Grove village 1,290 1,3 tt 2 - 3.9 l Union township 403 385 it . 7 l Wi.bnington township 590 608 - 3.0 l Winnebago township 361 tt32 -16.4 ; Yucatan township 368 til8 -12.0 Winona County 1,953 2,039 11 . 2 Dakota village 369 339 8.8 , Dresden townstip 3tt3 (12 3 -18.9 i New Ilartford township 718 7tI9 - (t ,1 Pleasant 11111 township 523 528 - 0.9 Minnesota Totals 19,509 18,627 + 11. 7
}GSCONSIN l Crawford County 5,023 5,696 -11.8 Clayton town 916 1,099 -16.7 DeSoto village (part) 79 117 -32.5 Ferryville village 183 19tt - 5.7 Freeman town 677 63tt - 1.7 Lynxville village lil9 183 -18.6 Mount Sterling village 181 161 12.4 Seneca town 858 863 - 0.6 Soldiers Grove village 514 663 -22.5 Utica town 8tl3 979 -13.9 (Continued)
O 2 - 14
l
)
l Table 2.2-3: (Continued) O La Crosse County 7tt ,875 67,639 -10.7 Bangor town 569 603 - 5.6 Barre town 521 507 2.8 Campbell town- 3,327 2,296 till . 9 Greenfield town 1,278 966 32.3 Ham.ilton town 1,229 1, tI3 9 -lti . 6 La Crosse city 51,153 47,575 7.5 Medary town 2,333 1,563 49.3 Onalaska city 4,909 3,161 55.3 Onalaska town 2,973 1,711 73.8 Shelby town 3,733 5,458 -31.6 Washington town 670 648 3.4 j West Salem village 2,180 1,707 27.7 1 1 Monroe County 1,336 1,380 - 3.2 I l Leon town 6til 610 5.1 Portland town
- 695 770 - 9.7 Vernon County- 19,004 19,258 - 1.3 Bergen town 1,002 782 28.1 Chaseburg village 224 242 - 7.4 Christian town !
808 866 - 6.9 j Clinton town 830 817 1.6 j Coon town 697 719 - 3.1 l Coon Valley village 596 536 11.2 DeSoto village (part) 216 2tt0 -10.0 franklin town 926 962 - 3.7 i Genoa town 728 559 30.2 l Genoa village 305 325 - 6.2 llamburg town 75t1 663 13.7 llarmony town 712 730 - 2.5 Jefferson town 9119 1,033 - 8.1 Kickapoo town 455 573 -20.6 Liberty town 231 2tl2 - 4.5 Readstown village 395 it69 -15.8 S terling town 664 803 -17.3 Stoddard village 750 552 35.9 Viroqua city 3,739 3,926 - 4.8 Viroqua town 1,5 ti4 1,518 1.7 Webster town 520 69ti -25.1 Westby city 1,568 1,5titt 1.6 Wheatland town . 393 tt63 -15.1 Wisconsin Totals 100,238 93,968 + 6.7
- Includes all subdivisions wholly or partly within a 25-mile radius O f th" r""otor-Source: 1970 Census of Population 2 - 15
O in each zone, multiplying by an occupancy factor of four to determine the approxi-mate population within a five-mile radius of the site. The zones in the second category are five to 25 miles from the plant site. Their areas range from approximately 14.7 square miles for zones between the five and 10-mile radii, to 44 square miles for zones between the 20 and 25-mile rodii. l Because the outermost zones are so large, some villages, towns and cities are entirely located within a single zone. Therefore, the entire population of these communities, taken from the census tables for population of county subdivisions (Table 2.2-3) could be ascribed to these zones. For communities located in more than one zone, the population was assumed to be distributed uniformly. The portion of the community lying within each zone was estimated, and a corresponding portion of its population was then attributed to that zone. , Population projections for the year 2010 have been calculated for each of the 144 zones within the 25-mile radius annular grid and are shown in Figures 2.2-3 and 2.2-4. Projections by zone for the year 2010 are given in Tables 2.2-4 and 2.2-5. Most of the population growth is expected to occur in and around the City of
'- a Crosse. That increase will be largely offset by a continuing decline in the j population of rural areas. The total projected population for the area within 25 miles of the LAC 8WR in the year 2010 is 126,620, an increase of only 4,020. The 2010 pc'pulation within a five-mile radius is expected to be 1,219, a decline of 334 ,
'l persons or 21.5E i County-wide population projections to at least 1990 have been made for counties in Wisconsin, Minnesota and Iowa, by agencies of the respective states.
For this report it was assumed that population in each of the 144 zones will change at the same rate as that of the counties in which they are located. For zones lying in more than one county, it was assumed that the rate of population , change will be the same as that of the county having the larger land aree within O 2 - 16 1 l __.___-_----___I
i l O 1 N-I 9 24 18 NE NW 33 9 19 27 0 6 49 18 0 15
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S' 1 I FIG.2.2-3 PROJECTED LAC 8WR AREA POPULATION FOR THE YEAR 2010 j 0-5 MILES i O 2 - 17
O N 11393 1833 3917 NW
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NE 1231 54187 ~ 3936 2428 1036 405 5760 1609 884 1547 339 383 159 773 183 818 1200 ' 318 596 ; 160 1832 342 ! 1 f N 1561 386 261 188 377 3510 659 ; 116 108 275 355 283 J a u. 182 455 444 410 5C8 307 174 h 543 1099 276 - 230 low.- .. 202 814 1730 90 244 1190 -ic u. - 853 699-290 300
/
SW - 6976 zou- 452 SE 753 25 M. s i FIG.2.2-4 PROJECTED LACBWR AREA POPULATION FOR THE YEAR 2010 5-25 MILES s O . 2 - 18
I O l Table 2.2-4: l 1 Projected LACBWR Area Population for the Year 2010, 0-5 Mile Radius Population at Inclusive Distance (Miles) l Sector Direction 1 2 3 tt 5 Total 1 1 N 3 9 18 9 24 63 2 NNE 38 206 15 21 18 298 i' 3 NE O 9 9 6 33 57 I 11 ENE 3 6 3 24 2tt 60 , i 1 5 E O 6 9 9 55 79 l { 6 ESE 9 12 12 9 18 60 l 7 SE 12 12 9 15 12 60 1 8 SSE 4tt 6 27 30 18 125 ' 9 S 0 6 9 0 18 33 : l 10 SSW 0 0 0 0 176 176 . 11 SW 0 0 0 6 16 22 12 WSW 0 0 9 9 9 27 13 W 0 0 6 9 13 28 lli WNW 0 0 3 19 9 31 15 NW 0 0 0 49 19 68 16 NNW 0 0 0 0 9 9
~
l Total 109 272 129 215 471 1,196 l l o l i I 2 - 19
O Table 2.2-5: Projected LACBWR Area Population for the Year 2010, 5-25 Mile Radius Population at Inclusive Distance (Miles) Sector Direction 5 10 15 20 25 Total 1 N 63 773 5760 54187 11393 72176 2 NNE 298 183 1547 2428 3917 8373 3 NE 57 318 453 1609 1036 3473 4 ENE 60 185 342 596 818 2001 5 E 79 188 377 3510 659 4813 6 ESE 60 275 283 543 1099 2260 7 SE 60 182 230 244 853 1569 8 SSE 125 174 90 300 452 1141 I 9 S 37 307 1730 290 753 3113 1 10 SSW 176 588 814 699 6976 9253 11 SW 22 455 276 .202 1190 2145 12 WSW 27 108 355 410 444 1344 13 W 28 116 261 386 1561 2352 14 WNW 31 118 1832 1200 339 3520 15 NW 68 160 383 405 1231 2247 16 NNW 9 159 844 3936 1833 6781 j Total 1,196 4,289 15,577 70,945 34,554 126,561 i O l 2 - 20
O that zone. Having thus established the 1990 population for each zone, the population for 1980 was interpolated, and population for the year 2000 and 2010 was extra-polated assuming a linear rate of growth or decline between 1970 and 2010. l
.i l
I O l 2 - 21 _ - _ _ _ - - - - _ - - - - - - - - - - _ - - - - - - - - - - - - 1
l O 2.2.2 Governmental Units The area within a 25-mile radius of the LACBWR site includes portions of three states and all or part of eight counties. The area within a five-mile radius is ; predominantly in Vernon County, Wisconsin, and Houston County, Minnesota, but I also includes a small portion of Allamakee County, Iowa. Counties in Wisconsin are governed by a board of supervisors, elected from supervisory districts for four-year terms. The individual towns are also governed by a body of officials known as supervisors. There are three for each town, elected j at large for two-year terms. Villages, such as Genoa, are governed by a board of l l trustees elected at large for two-year terms. Village presidents (mayors) are also elected for two-year terms. Nearly all counties in Minnesota, including Houston, are governed by boards of commissioners who are elected from commissioner districts and serve four-year terms. Towns or townships - the terms are used interchangeably in Minnesota law - are governed by boards of three supervisors who are elected at large for three-year terms. There are no incorporated municipalities in Minnesota within the five-mile radius. Allamakee County is governed by a o' oard of 3 supervisors elected for four-year terms, in Iowa, township government exists only in vestigial form. All local government functions not in the jurisdiction of incorporated municipalities are handled directly by counties. However, each township has a board of three trustees, essentially county officials, who are elected at large from township areas outside of incorporated municipalities and serve four-year terms. Iowa municipalities are classified as cities if they have over 2,000 population; as towns if they have less then 2,000 The town of New Albin, five miles from the LACBWR site, uses the mayor-council form of government. Virtually all chief executives and members of governing bodies in the three counties around the LACBWR work part-time. O 2 - 22
1 4 O 2.2.3 Land Use Agriculture and forestry are the predominant land uses in Vernon County as well as in the neighboring counties on the west side of the Mississippi River. A breakdown of land use in Vernon County is presented in Table 2.2-6. Nearly 94% of the county's gross area is in agriculture and woodlands. About 3.4%, consisting mainly of water area and marshlands, is classified as undeveloped. ; Total developed land accounts for less than 2.8% of the county's gross' area (1). The primary agricultural activity is dairying. Due to Vernon County's distance from large, fresh milk markets (i.e. major urban areas), the dairy industry j i is not as profitable as it might otherwise be. The major cash crop is tobacco, and j Vernon County produces more of this crop than any other county in Wisconsin (2). In recent years, with the consolidation of farms and the increased application of agricultural technology, there has been a marked trend toward the conversion of Vernon County's marginal agriculturalland to woodland. About two-fifths of the totalland in forms is now devoted to woodland. l The forests yield substantial amounts of ook and lesser quantities of maple and other hardwoods. A modest amount of sandstone and limestone quarrying also i takes place at a number of sites throughout the county (3). Developed land accounts for less than 3% of the gross area of the county. I Further,85% of the developed land is in the low intensity use categories of resi-dential and park land. The more intensive land uses (industry, commerce, public, 1 transportation and utilities) account for less than 15% of total developed land and less than 0.3% of gross area. Localindustry consists almost exclusively of oper-l ations related to the processing of agricultural and forest products. One notable exception is the recent growth of non-agriculturalindustries at the industrial park in Viroqua (4). In Houston County, Minnesota, less than 1% of the land is devoted to " urban purposes" and much of that is concentrated in the northeastern part of the county, in and around La Crescent. Forestry accounts for 48% of the county's total area, while agricultural activity.occounts for 43% (5). O 2 - 23 l L_____________________
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l i i O No breakdown of land use is available for Allamakee County, Iowa. ' However, ;
'it is similar to Houston County in size, population and extent of urbanization. The
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1969 Census of Agriculture (see Table 2.2-7) indicates that 88% of Allamakee ) County land is in forms. Of that amount, about 30% is classified as woodland. Land in the vicinity of the LACBWR site is overwhelmingly rural and undevel-oped. Of the area within a five-mile radius, approximately one-third is accounted for by water area and bottomlands included in the Upper Mississippi River Wild Life and Fish Refuge. In Vernon County, the uplands east of Highway 35 are typically pasture and woodland, with a few small quarries scattered through the area. The trend toward forestry on marginal farmland is even more pronounced here than in the eastern por-tions of the county because of the high proportion of steep slopes along the coulees. q The developed portion of the Village of Genoa, the only substantial commu-nity in the immediate vicinity of the site, occupies less than 100 acres. The Genoa National Fish Hatchery occupies 151 acres of bottomland at the mouth of the Bad Axe Hiver. Public and private recreation areas on and near the river in Vernon l County, excluding recreational use of the federal wildlife refuge, total about 750 acres (6). Refuge bottomland and water surface, lying mainly in Minnesota, extend west of the reactor site for 2.5 miles. The upland portions of Minnesota within a five-mile radius are predominantly wooded. Here,'as in Vernon County, margina) farm-land has tended to pass from crop and pasture uses to woodland. Roughly a third i of the area remains under cultivation. The riparian towns of Jefferson and Crooked Creek are included in the Minno-sota Memorial Hardwood State Forest. The designated forest area, approximately 100 miles long and up to 50 miles wide, includes nearly all of Houston County 'and varying proportions of seven other counties in southeastern Minnesota (7). The state is carrying out a long-term land acquisition program within the designated for-est boundaries. Acquisition of 200,000 acres is projected by the year 2000, in-cluding 20,000 to 25,000 acres in Jefferson and Crooked Creek -- the bulk of the land in those towns. The state now owns 3,989 acres in Jefferson and Crooked 'O 2 - 25
.O Creek, most of which is on the riverward side of those towns within the LACBWR five-mile radius (8).
A few dozen residences, including many vacation homes and boat houses are scattered along the shoreline near State Highway 26, and houseboats are moored at several points. The only identifiable community in Minnesota within a five-mile radius of the LACBWR is Reno, a hamlet of about 60 people located 3.5 miles north-west of the reactor. Approximately 3.5 square miles of Iowa are within the LACBWR five-mile radius. Most of it is water area and refuge bottomland, although there is some agri-cultural use on the inshore bottomland. The five-mile radius includes a portion of the incorporated town of New Albin, whose total population is 644. l l l O 2 - 26 --_-__-_a________ . _ _ _ - - - . _ _ _ _ _ - _ _
i O l Table 2.2-7: Selected Agricultural Data i Vernon County Houston County Mlar akee CounV-All Fanns 1969 1964 1969 1964 1969 1964 All f arms . . . . . .nunber 2,503 2,968 1,304- 1.400 1,439 1,557 Land in f anns. .. . acres 407,404 462.975 311,187 321,995 358.210 369.a75 Approximate county land area.. acres 513.088 515.205 361,664 361.605 406,848 408.965 proportion in f arms... percent 79.4 89.8 86.0 89.0 83.0 90.3 Land in f arms according to use Total cropland., ... farms 2,447 2.939 1,261 1,366 1,378 1,502 l -acres 221,017 226,483 168,348 , 152,983 204,226 194,065 i Harvested cropland .... f arns 2,358 2.879 1,214 1,330 1,314 1,424 l acres 142,824 171,525 110,884 114,655 136,275 140,945 Cropland used only for pas ture or grazing...f arms 1,544 1,612 812 781 'I.013 1.081 a:rcs 55,938 37,872 36,170 22,131 49,905 35.346' All other cropland (1)... farms 910 (NA) 607 (NA) 587 (NA) acres 22,255 17,086 21,294 16,197 17,986 17,774 Woodl and i ncl ud ing woodl and pas ture. . . . . . . . . . . . . . f a rms 1.964 2,408 1,064 1,21 5 1.066 1,262 acres 126,511 154,180 105,645 118,958 103,842 115,772 Al l o ther l and ( 2 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . f arms 2,044 (NA) 1,042 (NA) 1,210 (NA) acres 59,876 81,657 37,194 50,032 50,142 59,568 Farm income and Sales: All Farms I;unter of farms by econonic classes Class 1- Sales of $40,000 and over....... 27 14 90 23 117 23 Class 2- "
$20,000 to $39.999... .. *283 59 306 94 382 147 Class 3 "
$10,000 to $19,999..... 142 616 324 372 417 488 Class 4 $ 5,000 to $ 9,999..... 624 1,027 248
- 431 226 456 Class 5- "
$ 2,500 to $ 4,999..... 310 623 157 231 122 207 Other .. ........ ......... 512 629 179 249 175 236 Market value of all agricultural products sold..$ 26,408,883 21,432,500 22,048,229 13,750,500 25,714,642 Crops including nursery products and hay...... farms 1,553 (NA) 759 (NA) 842(NA) dollars 2,947,469 3,392,946 2,005,642 1,133.983 2,338,7691059579 .
Fo res t produc ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . f arms 117 266 58 87 96 117 dollars 97,908 155,145 49,606 41,348 69,691 57,228 Livestock, poultry and their products......... farms 2,223 (NA) 1,201 (NA) 1,356 (NA) dollars 23,363,506 17,866,074 19.992,981 12,578,326 23,306,182 15627.:02 (1) = "all other cropland" includes cropland used for soil improvement, crops, crop failure, cultivated suncer follow. ' and idle crepland. l (2) "all other land" includes pastureland other than cropland and woodland, pasture, rangeland, and land in house lots, barn lots, ponds, roads, wasteland, etc. Source: 1969 Census of Agriculture, Wisconsin County Data
'l O
2 - 27 l
1 1 il I l O 2.2.4 Planning and Zoning Vernon County is one of nine counties in the Mississippi River Basin in Wis-consin that joined to form the Mississippi River Regional Planning Commission (MRRPC)in 1964. (The other counties are Pierce, Pepin, Buffalo, Trempealeau, I La Crosse, Monroe, Jackson and Crawford.) The commission is made up of three members from each county. It conducts a comprehensive planning program for the : 1 L region, coordinates state, federal and local planning activities, and provides technical assistance to local units of government within the region. The MRRPC has been designated an A-95 review agency with respect to various types of projects involving federal action or assistance. The commission's professional { staff is headquartered in La Crosse. Background studies of the region have been carried out under a "701 pro - ject" funded by the Department of Housing and Urban Development (HUD) through the Wisconsii Department of Resource Development (whose planning assistance functions have since been assumed by the Department of Local Affairs and Development). The background studies, covering the region's economy, population, land use, natural resources, general transportation and certain community facilities, were published in 1969. Subsequent reports contained general planning proposals, model subdivision regulations and zoning ordinance guides and other elements re-lated to the implementation of the commission's regional planning program. Addi-tional studies on regional water supply and sewage facilities were carried out with a grant from the Farmers Home Administration. The MRRPC is currently assisting Vernon County in the preparation of a county-wide zoning program. Vernon County has already adopted flood p' lain zoning and subdivision regulations. Apart from the flood plain controls, there are no local zoning or building regulations in the Village of Genoa or the Town of Genoa. A comprehensive plan for Houston County, Minnesota, was developed under a "701" program completed in 1965. Land use plans have been prepared for all cities and villages within the county, and for several unincorporated communities, including Reno. Zoning and subdivision regulations are in effect throughout the O 2 - 28
-O county. Essentially all ruralland is classified as agricultural. Houston County development regulations limit the number of mobile homes units in a given town to 25% of total dwelling units. This is expected to preclude any sudden or sharp increase in populatica in the sparsely populated towns of Jefferson and Crooked Creek, which is opposite the LACBWR site (9). There are no planning programs in effect for Allamakee County, Iowa, Neither the county nor the town of New Albin has zoning, building or subdivision regula-tions (10). I l j O 2 - 29 !
3
'l O
2.2.5 Housing The bulk of the housing units in Vernon County are single family structures built prior to World War II, Of the 8,373 units counted in the 1970 Census of Housing,86% are in single-family dwellings. Of the total units, only 800 were less than 10 years old and 6,369, or 76% had been built before 1940. Mobile homes accounted for 364 units, or 4.35% of the total. q Selected data on housing in Vernon County are given in Table 2.2-8. Speci-fic data on housing units in the Town and Village of Genoa are shown in Table 2.2-9. '
)
l i 1 1 1 1 i o l 2 - 30 l
i I l 0 - Table 2.2-8: Vernon County Housing Data, 1970 l Occupied Total Rural Rural Farm All-year-round liousing 8,37 tt 6,9tl 5 2,621 Units in Structure ) 1 7,192 6,140 2,518 ' 2 5t19 321 , 33 3&4 156 84 -- 5 to 19 105 51 -- 20 or more 8 8 -- Mobile home 364 Stil 70 Year Built 1969 to March 1970 149 lit 3 3tt 1965 - 1968 383 316 58 1960 - 1964 268 206 28 : 1950 - 1959 716 552 123 i 1940 - 1959 IF89 342 107 l 1939 or earlier 6,369 5,386 2,271 Water Source Public system or private company 3,833 2,4 0tf 70 Individual well it,082 tt,082 2,332 Other 467 tt 07 235 Sewage Disposa] Public Sewer 3,827 2,4 3 tl 107 Septic or cesspool 3,579 3,550 2,166 Other 976 969 36t1 Owner Occupied 6,217 5,190 2,420 Renter occupied 1,53tt 1,178 217 No bathroom or shared with anothar household 1,4 t43 1,355 407 I O Source: 1970 Census of Housing, Detailed Housing Characteristics, Wisconsin 2 - 31
1 I O Table 2.2-9: Characteristics of Housing Units in the Village and Town of Genoa 1 Town of Village of Genoa Genoa Total llousing Units 170 102 Total Occupied Housing Unito 166 96 Number of Vacant Units 4 6 Total' occupied with only cold piped water 3 2 Occupied units with no piped
-water to building 6 3 Occupied units with no flushed toilet 10 4 Occupied units with no tub / shower 14 9 Source: Mississippi River Regional Planning Commission i
l 2 - 32 .
1 O-2.2.6 Institutions There are no institutional uses other than day schools within 10 miles of the LACBWR. (The term " institution", as used here, includes schools, hospitals, prisons, asylums and similar uses that entail the presence of groups of students, patients, inmates or other persons under supervision.) The only school within five miles of the LACBWR site is the St. Charles l Elementary School, a Roman Catholic parochial school in the Village of Genoa, j approximately one mile north of the LACBWR. Data on this and other schools with-in a 10-mile radius of the LACBWR are shown in Table 2.2-10. 4 l 1 i i i O 2 - 33 , m______..______
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l 0 - 2.2.7 Agriculture I The land within a 25-mile radius of the LACBWR is overwhelmingly rural. l In 1969, almost 80% of the lund in Vernon County was in forms, as was 86% and 77% of neighboring Houston and Allamakee Counties, respectively. Dairying. ) is the major source of farm income and the principal cash crop is tobacco. The trend in Vernon County has been towards a decrease in the total number l L. of farms, mainly through consolidation, and total form acreage. There were 465 fewer farms in the county in 1969 than in 1964, and 55,571 fewer acres in farms. Thus, the proportion of land in forms decreased from 89.8% in 1964 to 79.4% in 1969. During that time, the number of forms with sales of $2,500 and over decreased from 2,339 to 1,991. Despite this, the market value of all agricultural products sold went up from $21,432,500 in 1964 to $26,408,883 in 1969. The primary agricultural activity in Vernon County, on well as Houston and Allamakee Counties, is dairying. Livestock, poultry and their products accounted l for approximately 88% d the market value of all agricultural products sold by farms in l in Vernon County in 1969, and almost 90% for farms in Houston and Allamakee Counties. Vernon County produces more tobacco than any other county in Wisconsin. Nevertheless, the market value of all crops, including tobacco, accounted for slightly less than 11% of the total value of all agricultural products sold in Vernon County in 1969. Steep slopes are characteristic of much of the farmland in Vernon and neigh-boring sounties, especially the highly dissected " coulee country" near the Missis sippi River. Such slopes limit cropland use, largely bec2use the'y are difficult to cultivate with contemporary mechanized equipment. Whila 24.7% of Vernon County, 29.2% of Houston County and 25.5% of Allamakee County were in forest land in 1969, forest products accounted for less than 1% of farm sales in each county. According to the MRRPC, a third of the county's farms are classified as
" poverty forms" and many farmers must hold other jobs. The planning agency has recommended diversification of farm activities to include other commercial uses O ,
2 - 35
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O such as pet breeding and boarding, gift shops, produce stands and horseback riding. Selected agricultural date for Vernon, Houston and Allamakee Counties is given in Table 2.2-7. l l l 4 i I l O 1 2 - 36 -; l
- - . - - _ . - - . _ _ _ _ _ _ _ - - _ - - _ _ - - - - - - - - - . - _ _ . . . - _ - _ _ . _ _ - . _ _ . _ _ _ . . _ . . - ._ . . , - . . _ -_..----___._..J
O 2.2.8 Commerce and Industry Economic activity in Vernon County is largely tied to the region's agricul-tural base. Total non-farm county employment in 1970 was 2,809 (Table 2.2-11), of which 1,581 was in retail trade and services, including finance, insurance and real estate. Of 470 persons employed in manufacturing,188 worked in food pro-cessing, notably cheese-making. Of 271 employed in wholesale trade,107 worked foi wholesalers of farm product raw materials. At least 100 additional per-sons worked in "ani:nal husbandry services". One of Allamakee County's largest employers is a meat packing plant. How-ever, bth Allamakee and Houston Counties have large manufacturing enterprises not related to agriculture. Houston has a large computer equipment plant. Allama-kee has two large metal products plants, as well as a button factory, located in Lansing, which was the basis of a major shell fishery on ine Mississippian this region. Selected data on employment and economic activity in Vernon, Houston and Allamakee Counties are given in Tables 2.2-11, 2.2-12, 2.2-13. I There are no industries or large commercial enterprises within five miles of the LACBWR site. Business activity in the Village of Genoa is limited to small retail and service establishments. New Albin, five miles south, has a somewhat greater concentration of retail stores and other small commercial establishments. However, the nearest major industrial center is La Crosse,17 ailes north of the LACBWR. t 2 - 37
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O 1 l [ 1 1 (This page intentionally left blank.) l 1 0 2 - 41
O 2.2.9 Rail and Highway Traffic Traffic counts for the portion of Highway 35 east of the reactor site were taken in 1971. They indicate an overage volume of 2450 vehicles per day. The Burlington Northern Railroad tracks east of the LACBWR site are used by on average of 24 trains per day, having an average length of 90 cars per train. The tracks are no longer used by any passenger trains. l j l l l l O 2 - 42 l 1
O 2.2.10 Navigation The Upper Mississippi River is a major waterway for commercial barge traf-fic and is also used by recreational craft. The river is regulated for navigational purposes by a series of 28 locks and dams. These assure a min' mum channel depth of nine feet from Alton, Illinois to Minneapolis. The locks and dams are numbered from north to south. Lock and Dam No. 8 is at Genoa (mile 679.2), about 3300 feet upstream from the LACBWR. Pool No. 8, which is the portion of the riv-er upstream of Dam No. 8, extends 23.3 miles to the next dam upstream; No. 7, which is at Dresbach, Minnesota Lock and Dam No. 9 is 31.3 milca below Genoa, at Lynxville, Wisconsin. Most of the locks in the system, including Nos. 8 through 10, have a width of 110 feet and a usable length of 600 feet. The main commodities carried are grain outbound and coal and petroleum products inbound. The LACBWR's sister station, Genoa 3, is a major destination for coal-borge traffic. The nearest port facilities for barges are at La Crosse. Data on lockages at Lock No. 8 are given in Table 2.2-14. Barges and pleasure craft are locked through separately. Frequently, two or more craft are included in each pleasure boat lockage. The average navigation season for the Upper Mississippi from Rock Island to Minneapolis runs from April 10 to December 1. However, lockages at Lock No. 8 generally commence in early March and extend to about December 10. The 1971 season at Lock No. 8 was March 4 to December 15, a total of 287 days (11). There are numerous boat yards, launching sites and other small boat facili-ties along the river on both Pool 9 and Pool 8. Facilities in the vicinity of the IACBWR are listed in Table 2.2-15. O 2 - 43
O (This page intentionally left blank.) O 2 - 44
i l l 1 O i i Table 2.2-ltt: Lockages at Dam No. 8, Genoa, 1965 - 1971 l Total ) Total Pleasure Boat % Pleasure Boat Pleasure Boats I Year Lockages Lockages Lockages Locked thru 1965 4127 2379 57.6 3694 1 1966 t1026 2395 59.5 3827 l 1967 11111 2433 59.2 39t43 l 1968 3953 2292 58.0 3523 1969 3850 2225 57.8 til59 1970 Ll376 2425 55. t1 tt749 1971 tl726 2518 53.3 5368 - Source: U.S. Army Corps of Engineers, St. Paul, Minnesota j O i 1 2 - 45 E__----------------
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O ' 2.2.11 Reacreation and Tourism i The LACBWR is located in a region that offers major recreational opportuni- J ties for camping, boating, hunting, fishing, skiing, snowmobiling and cycling. The Upper Mississippi Wildlife and Fish Refuge, which includes the bulk of .! the river surface and bottomlands, is the focus of recreational activity in the region. ! Numerous public and private launching ramps provide boating access to the refuge area. Fishing and hunting are permitted, except in designated closed areas. i There are no specific camping areas, but camping is permitted on the refuge's l many islands and sandbars. Since access is only by boat, all camping is of a prim-itive nature. Camping, hunting, hiking and stream fishing are available in the Minnesota Memorial Hardwood State Forest, which includes about 4,000 acres of upland in , the riparian townships of Jefferson and Crooked Creek, immediately opposite the LACBWR site. l Within five miles of the LACBWR, there are eight launching ramps that pro-l vide entry to the Mississippi for small craft. (Table'2.2-16). One of these is the i i boat access on the Dairyland property which is operated by Vernon County. Blackhawk Memorial Park, seven miles south, is the nearest major park facil-ity to the reactor. It is on 337 acres of Federalland and is operated by Vernon County under license from the Corps of Engineers. Activities include camping, fishing, boating and picnicking. Axlen's Marina, a private concession within the park, services smc11 boats. Total annual attendance was estimated in 1968, at ! 25 - 30,000 (12). An estimated 3,000 campers used the park in 1971 (13). Another county park, also on Federal land, is 26-acre Stoddard Landing, seven miles north of the reactor. The only state park in Vernon County is Wildcat Mountain, approximately 35 miles northeast of the LACBWR. There are two state-maintained waysides off State Highway 35, one just south of Stoddard and the other about a half-mile north of the LACBWR opposite Lock No. 8. The MRRPC has identified three potential park sites in the vicinity of the LACBWR in Vernon County. They are at the mouth of the Bad Axe River (1,850 0 2 - 47 . i i E____________________________________.______.________.___ _ _ _ _ _ =_ J
;i l
l I O acres); on the west side of the Bad Axe River, about four miles upstream (2,560 acres); and on the Mississippi River near De Soto (480 acres) (14). Of these, only the area at the mouth of the Bad Axe is within five miles of the reactor. I i The Vernon County Outdoor Recreation Plan, published in 1971, emphasized the potential of the area at the mouth of the Bad Axe. The site adjoins the U.S. Fish Hatchery and is traversed by Highway 35. l Another potential recreation area in the LACBWR vicinity is a farm off High- j way 35 near Genoa recently acquired by the State Department of Transportation. I The site affords views of the Mississippi River Valley, the dam, and the LACBWR. The state intends to develop a scenic overlook and small picnic area there (15). Highway 35, which follows the east shore of the Mississippi, and Highway
]
26 on the west shore, are part of the Great River Road, a 5600-mile system of tourist routes that follows the Mississippi Valley from Canada to the Gulf of Mex-ico. The Great River Road was authorized by Congress in 1954. The program does not involve major construction of new roads, but rather the improvement of designated existing roads - in ten U.S. states and the Canadian provinces of Manitoba and Ontario -- and joint tourist promotion effort. The program is coor- i dinated by the Mississippi River Parkway Commission with the assistance of the Burecu of Public Roads, the National Park Service and other Federal agencies (16). The LACBWR is mentioned as a visitor attraction in Great River Road 1 promotional material and its location is shown on the Wisconsin sectional map of of the Great River Road (17). The Dairyland Power Cooperative has made arrangements to accommodate ) groups of visitors to the LACBWR. More than 10,000 visitors have participated in j conducted tours of the LACBWR plant since its opening. As of June 1972, there j had been 326 group tours, averaging 30 persons per group. U.S. Lock and Dam No. 8, just north of the LACBWR, is also a point of tour-ist interest. To accommodate visitors there, the Corps of Engineers has provided rest rooms and an elevated observation platform overlooking the lock. There is O 2 - 48 i
O also a state-maintained wayside on the east side of Highway 35, about one-half mile north of the plant and just opposite the lower end of Lock No. 8. .The l LACBWR can be seen from both the observation platform and the wayside. Other points of tourist interest in the vicinity of the LACBWR are the U.S. 1
' l Fish Hatchery and the site of the Battle of the Bad Axe, both about three miles j south of the plant, and Blackhawk Memorial Park.
The Mississippi River Regional Planning Commission has proposed the es-tablishment of four " tourist growth centers" where:
" Recreational and tourist activities will be developed in a concentrated ,
i form at selected locati6ns along the Great River Road. Suggested 1 locations are Prescott, Pepin, Fountain City and Genou. All of these communities have attractive scenic locations, water recreation l ! facilities and are close to existing or proposed large riverside l parks." (18)
~
Existing tourist accommodations near Genoa include a small motel and mo-bile home complex, about one-half mile south of the plant on the east side of High-way 35, the camp ground at Blackhawk Memorial Park, about six miles south, and the privately-owned Battle Hollow campground, about a mile inland from the park. Both Wisconsin and Minnesota have state programs for the development of hiking trails. A nationwide trail study conducted by the Bureau of Outdoor Recre-ation identified potential trails following the length of the Mississippi in both states. (19) Two tributaries of the Mississippian the vicinity of the LACBWR, the Root River and the Upper lowa River, as well as the Mississippi itself, have been pro-posed for inclusion in the National Wild and Scenic Rivers System. (20) l O 2 - 49
O REFERENCES
- 1. Condeub, Fleissig and Associates, Mississippi River Region Background -
Report,1969, p. LU-7.
- 2. Wisconsin Department of Natural Resources, Vernon County Outdoor Re-creation Plan,1971, p. 4.
- 3. Ibid,p.4.
- 4. Ibid,p.4.
- 5. Nason, Wehrman, Chapman Associates, Inc., Houston County Sewer and Water Study,1971.
- 6. Wisconsin Department of Natural Resources, op. cit., pp. 9 610.
- 7. UMRCBS Coordinating Committee, Upper Mississippi River Comprehensive Basin Study, Volume VI,1970, p. N-76.
- 8. Personal communication with Dale Peterson, Minnesota State Forester, Caledonia, Minnesota.
- 9. Personal communication with Duane Wohlers, Planning and Zoning Admin-istrator, Houston County. j
- 10. Personal communications with Mr. David Kudei, District Director, U.S.
Department of Agriculture Upper Explorerland Resource Development Project, and Mr. Ray Whalen, New Albins Savings Bank.
- 11. Telephone conversation, U.S. Army Corps of Engineers, St. Paul, Minne-sota.
- 12. Condeub, op. cit., p. CF-44.
- 13. Personal communication with Mr. Chester Erlandson, Chairman, Vernon County Board of Supervisors.
- 14. Candeub, op. cit., Vernon County Development Factors Map.
- 15. Wisconsin Department of Natural Resources, op. cit., p.19.
- 16. UMRCBS, op. cit., p. K-42,
- 17. Great River Road Association, " Travel Guide for the Great River Road,"
Cassville, Wisconsin,1971, pp.17 and 29.
- 18. Mississippi River Regie,nal Planning Commission, Regional and County Plan Summary Brochure for Vernon County, Wisconsin, p. 4-5.
- 19. UMRCBS, op. cit., p. K-48.
- 20. UMRCBS, op. cit., pp. K-44 and K-51.
O 2 - 50
O 2.3 HISTORIC SIGNIFICANCE For the Indians of the upper Mississippi River valley, as for the white traders and colonizers, the river was a route of commerce and warfare, a source of food and a focus of settlement. Burial mounds and other earthworks built by various Indian tribes are found in this region, generally on high ground. (1). The nearest to the LACBWR is the group known as the Fish Farm Mounds, seven miles south of the plant near New Albin, Iowa. European penetration of the upper Mississippi Valley began with the l expedition of Marquette and Joliet, who journeyed down the Wisconsin River in 1 1673. Within a few years, the site of Prairie du Chien had become an important gathering place for fur traders and Indians. The first permanent white settlement , there dates from 1781. Although it remained little more than a fromtier outpost 1 for another half century, it was the base for further trade and settlement in this j recion(2). In 1823, the steamboat Virginia inaugurated the era of steam navigation on j the Mississippi, making the 800 mile journey from St. Louis to Fort Snelling in 20 days. By 1830, there was heavy river commerce between St. Louis and the head of
)
navigation at Minneapolis (3). All along the upper Mississippi, existing settlements grew and new ones were established. J The influx of whites inevitably brought conflicts with the Indians. In 1827, a group of Winnebagos under Chief Red Bird killed two white men to avenge the l rumored murder of two of their tribe. They later attacked two boats that ap-l l proached their encampment near the mouth of the Bad Axe River, killing several ; of the crew. Red Bird finally surrendered to government troops and died in prison ! a few months later (4). i Five years later, at almost the same place, the Battle of the Bad Axe ended ' the protracted Black Hawk War. Pursued by troops and militiamen, the Sauk Chief, Black Hawk and his starving band of warriors, women and children, reached the Mississippi on August 1,1832. There they attempted to send the women and child-0 2 - 51 i __._...______________a
)
.1 i
1 I O ren downriver on boats and rafts, but the steamer Warrior, stationsd in the middle of the river, indiscriminately fired on women, children, warriors and truce parties. !
.1 Black Hawk and a few of his band escaped the massacre, but he was later captured !
and exhibited. He died six years later on a reservation in Iowa. (5) ) With the Indians subdued, settlers came in increasing numbers, not only to trade 1 and to farm, but also for lumbering, fishing and mining. I Nathan Myrick, an 18-year-old from New York, established the first perma- a- j nent settlement at La Crosse in 1841 (6). Wildcat Landing, at what is nowBrowns- ! ville, was established by three trappers who mounted a stuffed wildcat to identify it to passing steamers. (7) At Stoddard, boats would put in to take on fish and wood. According to the Federal Writers Project Guide to Wisconsin,(8) Genoa started .) i' as a fishing settlement, founded in 1848 by a group of Italians who came up the river from the lead mines at Galena, Illinois. However, the fishing community may ] not have been at the site of the present village. A local history published in 1907 i credited David Hastings with building the first house at what is now Genoa in 1853. I 1 A year earlier, however, the site of the present village had been purchased by j i Joseph A. Monti, a Galena businessman who was a native of Switzerland. Monti platted the village in 1854 and opened a general store there in that same year. Another Italian Swiss, Ferdinand Guscetti, moved up from Galena in 1855 and opened a wagon and blacksmith shop, Most of the early settlers were Italian, and even to-day the community is largely of Italian descent. St. Charles Roman Catholic Church i was built in 1862. The village, which was first known as Hastings Landing and then as Bad Axe City, became an important stopping place for river boats. The traffic prompted ; Joseph Monti to open a hotel, which existed for many years. The name of tha village ) was changed to Genoa in 1866. (9) In the 1850's and '60's, settlers from Germany, Norway, Poland and Bohemia, as well as the American Northeast, populated the uplands on either side of the Mis-sissippi. The life and hardships of these "couiee country" farmers was chronicled l by Hamlin Garland, who grew up on a form in West Salem, near La Crosse. O , 2-52
O Within a decade, however, the steamboat and barge operators were seeing i their cargoes diverted to the railroads. A railroad bridge at La Crosse, built in 1876, ) made that city a major rail center within a few years. (10) In 1878, Congress author-ized a comprehensive improvement of the Upper Mississippi between St. Paul and j the Missouri River. The project was designed to secure a depth of 4.5 feet by means of wing dams and the closure of chutes. (11) A six-foot channel was authorized in 1907. Additional wing dams and closing dams were built and banks in many creas protected by riprop. Numerous lights, daymarkers and other navigation aids were j also placed in the river or along the banks. l The preseni nine-foot navigation channel was authorized in 1930. It was ob- .] 1 toined by the construction of a series of 28 locks and dams. (12) One of these, Lock and Dam No. 8, is a half-mile north of the LACBWR site. 1 Another accomplishment of the 1930's was the Coon Valley Soil Conservation 1 Demonstration Project, initiated in 1933 by the U.S. Department of Agriculture in I cooperation with the University of Wisconsin. More than 400 farmers in the hilly watershed of Coon Creek, which flows into the Mississippi at Stoddard, were helped to control erosion in the first project of its kind in the United States. (13) At the conclusion of the five year experiment, the formers took steps to establish a perma-nent Soil Conservation District which now includes all of Vernon County. ! The experiment is commemorated by a state historical marker near Coon Valley, 15 miles northeast of the LACBWR site. j 1 The State of Wisconsin has placed two historical markers along Highway 35 in Vernon County. One of them is about a half-mile north of the LACBWR, over-looking the Federal Lock & Dam. It describes the origin of the present system of locks on the Upper Mississippi. The other marker, about 7.5 miles south of the . plant, commemorates the Battle of Bad Axe. The National Register of Historic Places lists no sites in Vernon. The listed I site closest to the LACBWR is the Emmanuel Evangelical Lutheran Church in Brownsville, Minnesota,9 miles NNW of the plant. (14) O 2 - 53
I l O REFERENCES
- 1. Hulbert, Archer B., Paths of the Mound-Building Indians and Great Game Animals (Frontier Press, Inc., Cleveland,1967) pp. 43-93.
- 2. Federal Writers Project, Wisconsin (Hastings House, New York, revised edition,1954) pp. 4412.
- 3. UMRBCS, Vol. V, Appendix J " Navigation," p. J-5.
- 4. Federal Writers Project, op. cit., pp. 439-40.
- 5. i 1,b_id, p. 440.
- 6. Ibid, p. 206
- 7. Federal Writers Project, Minnesota (Hastings House, New York, revised edition,1954) p. 408.
- 8. Federal Writers Project, Wisconsin, p. 439.
- 9. Rogers, Earl M., Memoirs of Vernon County, Genoa,1907,and La Crosse Daily Tribune, undated clippings, circa 1954, in possession of Mr. &
Mrs. Joseph D.Pedretti, Genoa, Wisconsin.
- 10. Federal Writers Project, Wisconsin, p. 208.
- 11. UMRBCS, op. cit., p. J-4.
- 12. UMR Cons. Committee, UMR Habitat Classification Survey,1971, p. 2.
l 13. Federal Writers Project, Wisconsin, p. 514.
- 14. " National Register of Historic Places" in the Federal Register, Vol. 37, No. 51, Wednesday, March 15,1972,and Supplement in Vol. 37, No. 85, i
Tuesday, May 2,1972. I i 1 2 - 54
O 2.4 GEOLOGY 2.4.1 Stratigraphy The LACBWR site is underlain by rocks of Cambrian and Quaternary age. East of the site, the Cambrian formations are overlain by additional Cambrian and
'I Ordovician formations that comprise the bluffs. A geologic cross-section through the LACBWR site is shown in Figure 2.4-1. 1 The oldest geologic unit of particular interest at the site is the Mount Simon Sandstone. Other formations ovctlie the Mount Simon in the following order (oldest to youngest): the Eau Claire, Galesville and Franconia Sandstones, and the Trem- l l
pealeau Formation. These are flat-lying to cooise-grained dolomitic sandstones, containing some shale and dolomite beds. The Eau Claire and Franconia are com-monly shaley. Wells located on the valley floor, such as the well supplying the U.S. Fish l \ 1 I and Wildlife Service hatchery, about three miles SSE of the site, penetrate the Mount Simon. A description of rock samples collected from the fish-hatchery well during dr lling provides ' good information on the subsurface geology beneath the reactor site. A detailed description of the well cuttings, prepared by the late E. T. Thwaites of the Wisconsin Geological and Natural History Survey, is summarized in Table 2.4-1. l The geology of the valley fillin the vicinity of the reactor site is known from the records of water wells and foundation borings at Genoa 1. The logs of foundation borings indica 4e that below a 17 to 20 afoot layer of fill the alluvium consists of one or two feet of dark gray silty clay underlain by fine to medium i gray silty sand with occasional small to medium gravel. No information is avail-able on the mineralogic composition of the alluvium.' Material that is locally de-l rived can be reasonably assumed to consist largely of quartz sand. The alluvium probably has a low capacity for the uptake of radionuclides by ica exchange and absorption. Based on records in the Engineering Department, Dairyland Power Coopera-O 2 - 55 1 - -_ - -
Ji{l; 55ho$ z ES! O _ T S E A GH E E N T C A WI O F OT N R U S C E H SE EA C P U O R O I T A I R T E E N O E N O T N O T S E N O T S TF S R I U M G R M T S S D D R S D N E OZ EO F-D N N A A N N A W BI C A S S S CR I H U S C A~PI E E E R N O AT U L A L I M L E D A I N IL A I M L S HO E O V mER I I P M C N S E C T N GZ U E _ A E A L U U OP I R R R A A O R P T F G E M _ HD TN - N A OE I T L
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O Table 2.4-1. Description of Well Cuttings, Prepared by the Late
- f. T. Thwaites, Wisconsin Geological and Natural History Survey l Valley fill Thickness Depth to-(feet) b_ottom (feet)
Sand . . . . .. .. . . . .......... . 5 5 Sand, fine to coarse, some pebbles, dark brown-gray above, light gray below. . . . . . . 50 55 Sand, fine to medium, light gray. . . . . . . . 15 70 Sand, medium to very coarse, some pebbles, light gray. . .... . . . .......... 15 85 Gravel, f.ine, sandy . ... .......... 5 90 Sand, medium to very coarse, light gray . . . . 10 100 Gravel, fine, sandy, light gray.. . . . . . . . 10 110 Sand, medium, light gray. . .......... 25 135 Sand, medium to coarse, light gray. . . . . . . 5 140 Sand, fine, light gray, mainly local. . . . . . 25 165 Sand, very coarse to silty, gray, glacial . . . 5 170 Eau Claire Sandstone Sandstone, very fine to fine, light gray, glauconitic . . .. . . . . . . . . . . . 25 195 Shale, dark gray; sandstone, very fine, dark gray, dolomitic . . . . . . . . . . . . . 5 200 Sandstone, very fine, gray, dolomitic . . . . . 10 210 Shale, green-gray, dolomitic; sandstone, like above. . . . . .. . . . . . . . . . 10 220 Sandstone, very fine, light gray, glauconitic, dolomitic . .. . . . . . . . . . . . . . 45 265 Sandstone, fine, light gray, dolomitic, glauconitic . . . ... . . . . . . . . . 20 285 Shale, gray red, dolomitic. . . . . . . . . . . 10 295 Mount Simon Sandstone Sandstone, fine to medium, light gray, slightly dolomitic. . . . . . . .. . . . 15 310 Sandstone, medium to fine, light gray . . . . . 30 340 Sandstone, medium to coarse, light gray . . . . 50 390 No sample . . . . . . .. . .. . . . . . . . . 5 395 Sandstone, fine to coarse, light gray . . . . . 240 635 0 2 - 57
1 O tive, the valley fill at the reactor site may be somewhat thinner than at the fish hatchery, because a water well at the Genoa 1 is reported to be bottomed in sand-stone at a depth of about 100 feet. Two other wells at Genoa 1 are about 150 feet deep, and one is uneased below 100 feet, so it is presumably finished in sandstone l-rather than alluvium. j i I I l 1 ( O 2 1
O 2.4.2 Seir.micity The earthquake history of the site crea is discussed in several works on the ryeral subject, including some by Heck (1947), and Richter (1959). On his map showing the location of destructive and near destructive earthquakes in the United States, Heck shows several in northern Illinois. However, no major earthquakes have occurred in Wisconsin, Minnesota and Iowa. The most serious earthquake recorder near the site occurred on May 26,1909, about 150 miles southeast of the site, and ". . . was noted over a considerable area from Bloomington, Ill. to Platteville, Wisconsin. Quake was just under point of damage at Aurora where mary chimneys fell" (1). The New Madrid, Mo., earthquake of 1911 was very probably felt in the site area, as shaking was reported over more than half of the United States, excluding-Alaska, and represented on intensity of IX on the Modified Mercalli scale (2). Richter indicates that the maximum probable intensityfor Wisconsin, costern Minne-sota and Northern Illinois is VIII (Modified Mercalli scale). The Uniform Build-ing Code,1970 edition, includes the site in Zone 1 (no damage). The iafluence of the aeology of a site on the recponse of stmeture to earth-I quake shock is well known. Alluvial materials tend to accentuate chort-period vib;ations, and alluvium containing beu or opptciale amounts of tJ1t and clay may respond by suddea differential compaction wnich could result in tiltinq of structures. Inasmuch as the natural alluvial fill ot the site is predominantly sand and gravel, it probably is not susceptible to severe compaction and to the second-ary earthquake damage effects resulting f ci weak yound, The foundatic.; pilings for the reactor rest on undisturbed natura' alluvium. O 2 .- 5?
O REFERENCES
- 1. Heck, N. H.,1947, Earthquake History of the United States, Part 1
-- Continental United States (exclusive of California and Western Nevada) and Alaska: U.S. Coast and Geodetic Survey Serial No.
I 609,83 p. 43.
- 2. Richter, C. F.,1959, Seismic Regionalization: Bulletin of .
1 Seismological Soc. America, V. 49, No. 2, pp.123-62. l s l l l i
,a 1
1 H s i lO \ ( ,s ' l 2 - 60 L . l l l _ _ . _ _ _ _ _ _ _ _ _ _ _
l O 2.5 HYDROLOGY In the reach between La Crosse, Wisconsin, and Lansing, Iowa, the Missis-sippi valley is relatively straight and trends almost due south. The valley floor is made up of marshy land consisting of islands between river channels and ex-tensions of a low-lying flood plain cut by sloughs, ponds, and meandering stream channels. The valley walls rise sharply to the upland,500 to 600 feet above the level of the river. Tributary streams have cut numerous short, steep-sided valleys (coulees) into the flat to gently rolling upland surface. Interstream drainage divides con-sist of narrow, winding ridges. The valley walls of both the Mississippi River and the tributary valleys are wooded. The flat upland creas and the floors of some of the tributary valleys are cultivated and grazed. There is little or no agricultur-al use of the Mississippi River flood plain. l The main channel of the river ranges greatly in width both above and beloc the reactor site. Between Dam No. 8 and the site, the river is 1500 to 2000 feet wide. Above the dam, the river is nearly four miles wide where impounded water covers the flood plain. Below the site, the main channelis relatively narrow for some 20 miles, then gradually widens toward Dam No. 9 as it covers a larger part of the flood plain. Streamflow conditions are greatly influenced by these two dams, which are part of a series of dams built and operated by the U.S. Army Corps of Engineers for navigational purposes. O 2 - 61 1
9 O 2.5.1 Flood Frequency Analysis The Mississippi River provides a copious supply of condenser-cooling water and is available for dilution of any routinely discharged low-activity liquid efflu-i ent. The degree of utilization of the water that can be made for dilution purposes j requires a knowledge of the stream-discharge and water-quality variations. The stream is regulated for navigational purposes for many miles upstream from the site, thus stabilizing the min l mum stage and discharge at the site prior l to construction of the LACBWR. A computation of the magnitude and probable fre-quency M floods of the Mississippi River at the site was made, based on analysis , of the records available at three gauging stations near the site (Table 2.5-1). A comparison of annual peak discharges at these stations during a concur-rent period showed that they deviated from each other by only a small percentage ; and that the earlier discharges observed at La Crosse could be used for this anal- l ysis. The results of a graphical analysis, based on methods generally used by Geological Survey, are shown in Figure 2.5-1 (1). The three highest annual floods since 1873 were ranked on the basis of stage records at La Crosse; annual floods from 1930 to 1962 were ranked on the basis of discharge records at La Crosse, and annual floods from 1930 to 1962 were ranked on the basis of discharge records at La Crosse, Genoa, and McGregor. A conservative extrapolation showed l that a flood with a recurrence interval of 100 years has a magnitude of 220,000 cIs (cubic feet per second). This means that there is a 1% chance that a flood equal-ling or exceeding 220,000 cfs will occur in any one year. Floods of greater mag-nitude will occur, but according to the present analysis, have a smaller than 1% l . chance of occurring in any one year. j The stage that a flood of 220,000 cfs is likely to reach at the site can be com-puted from records at the gauge operated by the U.S. Army Corps of Engineers at Genoa. From information furnished by the Corps a stage-discharge curve was de-veloped (Figure 2.5-2) which indicated a stage of 635.2 feet for a discharge of 220,000 cis. Prior to construction of the LACBWR, the highest flood since 1873 l in this reach of the Mississippi had occurred on April 22,1952, with a stage of O 634.49 feet at the Genoa gauge and a discharge of 200,000 cis. Floods of nearly 2 - 62
i I 1 O l equal magnitude occurred in 1880 and again in 1951. The highest flood of record I ( occurred in 1965, with a stage of 638.40 and a discharge of 274,000 cis. In 1969, I there was a flood with a stage of 635.24 and o discharge of 230,000 cis. The fall of high water between the gauge at mile 679.02,and the site, is estimated to be I 0.1 feet, s l 4 i O ! 2 - 63
i i O Table 2.5-1: Flood Frequency Analysis , 1 The computation of the magnitude and probable frequency of floods of the Mississippi River at the site is based on analysis of the records available at three gauging stations l near the site. l j l Miles Upstream Drainage Area Location from the Ohio Sq.Mi. Records Availab.e La Crosse 697.8 62,800 1873 to 1955 Genoa 697.0 64,700 1930, 1940-62 Site 678.6 64,700 -- McGregor 633.4 67,500 1936 to 1962 ] 1 1 1 i O 2 - 64 I
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l 1 0 2.5.2 Magnitude and Duration of Low Flow Low flow is the hydrologic condition most sensitive to contamination. The low flows on the Mississippi River at the site are subject to a certain amount of control and reguiotion by the eight navigation dams on the river above the site and by several power reservoirs on river tributaries. However, the basic low-flow dis-charge pattern has not been altered, the effect of the regulation being largely tran-sitory and of smallinfluence on average monthly flows. Low flow at the site oc-curs in the fall and winter; the lowest rconthly average flow is most frequently re-corded in February. In periods of drougnt minimum flows have also ocentred in August and September. Minimum and overcqe flows, based on 42-year records of the U.S. Geological I l Survey at the Winona gauging station, are given in Table 2.5-2. Chemical characteristics of shallow ground water at the site, determined from analysis of water from two LACBWR supply wells, are shown in Table 2.5-3. . Both wells are located in Lot 7, in the southern portion of the DPC Genoa property. ] i The chemical constituents of the shallow ground water are not greatly dif- I ferent from those of the river water. This is expected in view of the fact that the wells at the Genoa plant are relatively close to the river and probably draw part of their water from the river through the alluvium. However, the ground water is ' considerably harder than the river. These wells are finished in sandstone, but they are relatively shallow (casing depths of 92 and 129 feet) and apparently do not peneWte the artesian aq-uifer. Conclusive evidence of a hydraulic c ,n between water at shallow depths in the sandstone and water in the alluvium is not available, but tne assump-tion is reasonable, and none of the field data constitutes evidence to the con- ; trary. i It is virtually impossible that a cone of depression resulting from the pump-ing of the more distant of these wells could extend beneath the reactor site and reverse the water table gradient, and it is extremely unlikely that pumping from the nearby wells could produce such an effect. O 2 - 66 l- ,
O 37
/
/
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- Stage and disc large by U. S. Army Corp ; of Engin rers=
30 g ?*
- Stage by U. S. Army Corps of Engineers. Di . charge frc m U.S.G.S.
gage ; at LaCro ,se and Mc( regor. O 29 -
, Datun for gage is 600.o i t. msl .
1 28 s' O o 100 150 zoo 250 Discharge, in thousand cfs FIG. 2. 5-2 STAGE-DISCHARGE RELATION OF MISSISSIPPI RIVER AT MILE 679.02 (LOCK & DAM NO.8). ONLY ANNUAL FLOODS 1970-1962 ARE PLOTTED. 2 - 67
?
I I i I O l li 1 I i Table 2.5-2: Minimum and Average Flows at the Winona Gauging Station j l
)
4 FLOW LI2 year average 25,260 efs I tt2 year maximum 268,000 cfs il/19/65 tt2 year minimum 2,250 efs 12/33 (thru 1967) January avg. 12,700 efs (tlu'u 1967) July avg. 27,200 cfs 7-day, 10-year low flow 5,700 cis l l l i i 1 l l l l l l e 1 4 2 - 68 1 L_____._______.___..____.__ ._
l l O l ( l l Table 2.5-3: Analysis of Water from LACBWR Supply Wells (. ppm) i I Parameter Well No. 3 Well No. ti j
\
pli @ 25 C 7.7 7.7 Alkalinity (HCO 3) 3tio 337 Sulfate (S0y) 15 10 1 Chloride (Cl) 8 7 ) J Nitrate (NO3 ) 5 5 l 1 Silica (SiO2 ) 15 15 i l Phosphate, ortho (Pot,) 0.2 0.2 Phosphate, meta (Pott) < 0.1 <0.1 Hardness (as CACO3 ) 29tl 302 Calcitun (Ca) 65 65 Magnesiwn (Mg) 32 3tt Iron (Pe) 0.05 0.08 l l Manganese (Mn) < 0. 03 < 0.03 l l I Color ( APilA units) .5 .5 COD 1 1 l Suspended sol.* ds (est) 5-10 5 i l 2 - 69
i l
,v, 2.5.3 Downstream Water Use l
Virtually all municipal water supplies for cities and towns along the river downstream from the site for a distance of at least 40 miles are obtained from j ground water. The nearest major city using the Mississippi as a source of water for municipal supply is Davenport, Iowa, about 195 miles downstieam from the reactor site reactor site. According to a canvass made in June 1962 by Dairyland, the only j industrial use made of river water between the reactor site and Prairie du Chien, 40 miles downstream, is at the power plant below Lansing, Iowa. At this plant, ) river water is used for boiler feed and cooling purposes, but ground water is used fo: such purposes as showers and drinking. i 2.5.4 Ground Water ! Information on five domestic wells south of the LACBWR and east of High-way 35 indicates that the water table is near the surface and that the gradient is toward the river. The locations of the wells are shown in Figure 2.5-3. Depths of water range from 20 to 45 feet below the land surface. The elevation of the l water table above mean sea level ranges from about 640 feet in the area south- ! east of the LACBWR to about 620 feet a mile south of the plant. The yield of each of the five wells is about 10 gpm (Table 2.5-4). i l
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2 - 70
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O 2.5.5 Quality of River Water Table 3.7-1, found in section 3.7, lists values for intake water quality parameters as recorded on Corps of Engineer permit application documents. 2.5.6 Site Drainage The LACBWR site is favorably located with respect to drainage from the hills to the east because of two short valleys east of the bluff along Highway l 35, one draining north toward Genoa, and one south below the reactor site. (Figure 2.5-3) The two valleys limit the hill area that contributes runoff across the site and only the precipitation that falls on the bluff and a small upland crea con cross the site. This drainage is channelled along the highway and railroad to prevent interference with traffic. A small amount of other drainage from the railroad right-of-way and nearby hills is channelled to the river via three under-ground culverts i O 2 - 73 1
l i O REFERENCES
- 1. Clebsch, Alfred, Jr. and Eric L. Meyer (1962) Geology and Hydrology of a ,
Proposed Reactor Site Near Genoa, Vernon County, Wisconsin j 4 4 l l 1 i l O 2 - 74 e____--_______-___--_-____---____---___
l 0.. i 2.6 ' METEOROLOGY. ! 2.6.1 Meterological Data 1 The National Weather Service (NWS), formerly the U.S. Weather Bureau, has maintained a station at the La Crosse Municipal Airport since 1950. The station . is currently staffed by FAA personnel. Prior to 1950, weather stations were maintained at various locations in La Crosse. The NWS operates an upper-air wind station at St. Paul, about 132 miles northwest of the LACBWR. Limited meteorological data in the form of wind speed and direction statis-tics are avaliable for the LACBWR site. The wind data were obtained continuously with an aerovane and associated chart recorder and logged hourly by a station operator. The aerovane was originally located on the roof of the old Genoa No.1 steam unit building but is now located at the top of the 350-foot LACBWR stack. It is positioned about two stack diameters away from and west of the stack. Data summaries were compiled for the rooftop location for 1963 and 1964, and for the stacktop location for 1969,1970 and 1971. Data for the period 1965 through 1968 were collected but not summarized. The wind direction data for the stack-top location are likely rather good. l The aerovane would be subjected to stock interference only for east winds which i occur infrequently. The wind speed data, however, are not adequate for disper-l sion analysis since the aerovane has a starting speed of four or five mph. Thus, f 1 the wind speed distribution for the stocktop location is probably shifted to lower i speeds relative to the actual distribu! ion. k i l Aside from the wind speed and direction data, no other meteorological data i i for the LACBWR site are available. ' l 1 I O l 2 - 75 I i
.)
_j
m g l 1 i O ; 2.6.2 General Climatology l General climatological data for the La Crosse area are presented in Table
]
2.6-1. They are based mainly on data collected at the La Crosse' Municipal Air-port and to a lesser extent on data collected at other La Crosse stations (1). Temperatures in the La Crosse region are typical of the extremes of a con- . tinental climate, and the extremes being more marked because of the river-valley location. A'verage temperatures vary from 19*F in the three months of ' winter to 71*F in the summer months. A record maximum temperature of 108'F was re-corded in July,1936; the re. cord low of -43 *F was recorded in January,1873. Monthly precipitation in the area averages two to four inches between March and Octcber, and one to two inches for the rest of the year. Average yearly pre-cipitation is 31.2 inches. Monthly snow and sleet averages between five and 14 inches from November through March, the largest amount normally occurring during March. The normal annual amount of snow and sleet is 43.5 inches. Because the topographical features at the LACBWR site and at the La Crosse Airport are similar, the weather features at each place should be similar. Both locations are on the east side of the Mississippi River Valley, west of bluffs approximately 500 feet high. The major differences are in the width of the river valley and the proximity to the eastern bluffs. The valley is approximately 5 miles wide at the airport and 2.6 miles wide at the site. The valley wall is about two miles east of the airport station and approximately 1000 feet east of the LACBWR reactor. The 500-foot bluffs of the Mississippi River valley channel the winds. Air-port data showed prevailing southerly winds for eight months of the year and pre-valling northwed winds during January, February, March and April (1). Site data show that the wind blows predominately from the north and from the south throughout the year. In both cases channeling effects are apparent. In summer, a tendency toward air stagnation in the river valley accompanies periods of hot, humid weather. In winter, cold air drainage into the valley exacer-bates extremes of cold accompanying Arctic air masses. Inversion conditions s O may be intensified by stagnatior . cold air on the valley floor. i 2 - 76 1
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-O The site area exhibits a typically continental type of climate. Thus, inver-sion frequencies are closely related to the diurnal cycle. Night time inversions occur under conditions of light winds and little sky cover. These inversions tend to be broken up during the day. Inversions occur about 22% to 32% of the time in the spring and summer months and between 27% and 35% of the time in the fall and winter (2). The higher inversion frequency in the fall and winter is due in port to the longer duration of the stable nocturnal periods in winter and to mini-mum storminess in fall (2). The flow of Arctic air masses over the area, with associated subsidence inversions, also tends to increase the depth and intensity of winter inversions.
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I O 2.6.3 Winds Figure 2.6-1 shows wind roses for La Crosse Municipal Airport. Figures 2.6-2 and 2.6-3 show wind roses for the site at the rooftop and stacktop locations. Wind speed distributions for the airport and the two site locations are listed in Table 2.6-2. Four months of the year are used to represent the four seasons for the site at the lower level. Wind speeds at the stock top tend to be highest of allocations but the fre-quency of calms is also greatest there. The observation of so many calms at this location may be real and could be attributed to the fact that the stack-top location near the valley wall may be in the stagnant zone in the nocturnal valley or slope wind systems. It is equally possible that the recording of so many calms is due to the insensitivity of the sensors. Calm frequencies observed at both sitt locations are higher compared to the La Crosse airport station with only 10.4%. The river valley tends to channel the winds. The valley runs almost di- I rectly south from La Crosse but bends northwest north of the city. The prevailing wind at the La Crosse airport is from the south, but in winter tends to be north-l westerly. Predominant winds at the LACBWR site where the river valley runs -; i north-south are from the north and south. The channeling effects of the river valley may also be seen by comparing the surface wind roses (Figures 2.6-1,2.6-2 and 2.6-3) with the upper wind roses at St. Paul (Figure 2.6-4). The upper-air l wind roses show a more uniform wind distribution. l l O 2 - 79 1
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l O 1 2.6.4 Inversions ! The La Crosse area experiences a typical continental type of climate. The tendency for continental areas is low-level stability at night and instability dur'- l ing the day. Inversion frequencies are highest for the La Crosse area during fall and winter. Also, the intensity of inversions is probably greatest during winter. The effects of strong radiation cooling associated with snow cover and of subsi- . dence inversions associated with cold Arctic air masses produce deeper and more intense surface inversions in the winter. During late winter and early spring, es-pecially with snow on the ground, the advection'of warmer air from thesouth I could increase the duration and intensity of low-level inversions. However, this condition precedes cyclones that eventually induce low-levelinstability and mixing. The frequencies of occurrence of inversions for the La Crosse area were taken from two sources and are listed in Table 2.6-3. The first source was a set ) 1 of plots of seasonalinversion frequencies for the entire United States. (2)' The j second source was a " STAR" program analysis of La Crosse Airport Station f records. (5) Values of inversion frequency for the STAR program analysis repre-jl sent the total per cent occurrence of "E" and "F" stability categories by sea-l son. The data from the two independent sources are strikingly comparable. I Inversion frequency at the LACBWR site should not be substantially dif-ferent from that indicated in Table 2.6-3. To some extent, the available data on frequencies of light nocturnal wind speeds afford a basis for evaluation of j inversion frequency. Per cent frequencies of nighttime wind speeds below l seven mph for the general La Crosse area and for the La Crosse Airport Station are listed in Table 2.6-4, together with data from the LACBWR site rooftop loca-tion. Light wind speeds at LACBWR are roughly 20% more frequent than in the general area. On an average basis, this might imply a 10% greater inversion fre-quency than indicated in the table, ! O i 2-84 I
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O 2.6.5 Tornadoes Tornadoes are less likely to occur in Wisconsin than in states to the south-west, south and the immediate southeast. (3) Tornado probability in the area of the site is one of the lowest among the 14 counties in Wisconsin for which the La Crosse Weather Bureau has warning responsibility. (4) Tornado zones have been defined in the U.S. in terms of the number of tornadoes reported in each 50-mile-square area based on data collected between 1920-49,(3) For the some period, the La Crosse area reported approximately 10 tornadoes per 50-mile square. From these data, and from the fact that the overage tornadoinvolves an area of three square miles, there is an annual probability of 1/2000 for a tornado to strike a given square mile in the La Crosse area. The chance that a tornado would pass directly over the reactor site is even smaller. O 2 - 86 e _ _ _ _ _ _ _ - .
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s s . x y O . r N-Table 2.6-3: Invernf oo Freque; icy for La Crosbe Arei. I Inversion Frequency b t s ! ',
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i f o REFERENCES ) 1
- 1. U.S. Depurtment of Commerce, " Local Climatological Data With Comparative 1 Data ", La Crosse, Wisconsin (1958).
- 2. Hosler, Charles R., " Low LevelInversion Frequency in the Continental U.S.", i Monthly Weather Review, Vol. 89 (Sept.1961). )
- 3. Flora, Snowden D., Tornadoes of the United States, rev. ed., University of Oklahoma Press - Norman (Mar.1954).
1
- 4. Wolkenhauer, W. C., " Tornadoes at LACBWR -- Probability & Procedures" (un. ablished document).
- b. STAR Analysis of Wind Speed and Direction by Pasquill Stability Classes, U.S. Dept. of Commerce, NOAA, National Climatic Center, Ascheville, North Carolina, l l
1 1 ; i 1 l O 2 - 89
O 2.7 BIOTA The LACBWR is situated on the eastern bank of Pool 9 about a half mile below Lock and Dam No. 8. The poolis included in the 194,000<cre Upper Mis-sissippi River Wild Life and Fish Refuge, which extends from Wabasha, Minne-sota, to Rock Island, Illinois, a distance of 284 miles. . The Refuge was established by on act of Congress in 1924. It is managed for multiple uses including wildlife preservation and propagation, protection of rare and endangered species of plants and animals, preservation of the wildlands character and natural beauty of the river bottoms, resource management, recreation, education and scientific research. Flooding of pools behind the thirteen dams throughout the refuge has raised water levels to create excellent habitats for waterfowl. Fourteen areas designated as wildlife sanctuaries have been established at intervals along the river. They total approximately 41,000 acres, which are closed for protection of migratcry waterfowl during the hunting season. The LACBWR is 1.6 miles south of one sanctuary area, which extends upstream for about eight miles on the west side of the main chcnnel. On the east, or Wiscon-sin side of the rives, about 11.5 miles north of the LACBWR is another sanctuary. Approximately one square mile in area, it includes part of Goose Island and neigh-boring sloughs and stump fields. The next sar,ctuary downstream is near Lynx-ville, about 23 miles downriver. From 1965 through 1971, day use of Pool 9 by waterfowl ranged from 2,246,975 to 4,128,011 days (Table 2.7-1). Annual harvests of waterfowlin the pool for 1965 through 1971 ranged from 570 to 1,451 birds with an average hunter
)
bag rate of 1.62 (Table 2.7-2). I The Genoa National Hatchery, operated by the U.S. Fish and Wildlife l Service, is located on the east side of the river 4.5 miles below the LACBWR (Figure 2.7-1). The hatchery has 55 ocres of ponds. Northern pike, walleyes, largemouth bass and bluegills, totaling approximately 1,500,000 fish annually, are propagated. Water to supply the hatchery is obtained from wells and the Bad g Axe River. 2 - 90
O To prepare the LACBWR site,126 acret, of bottomlands and shallows were filled with dredged material from the Mississippi River. The filled area was originally bottomland forested by hardwoods, and contained scattered potholes and marsh type habitats. The wooded area south of the plant site, intermixed with potholes, is a continuation of the habitat which was filled (Figure 2.7-2). Pot-hole areas in the Upper Mississippi Valley are rich in aquatic vegetation (Table 2.7-3). In bottomlands adjacent to the site, white and green ash, elms, river birch and cottonwoods comprise more than half the trees. The hillsides east of the site are covered by an oak type forest dominated by red, white and black oaks. Species found in forest types in the LACBWR area are listed in Table 2.7-4. Lists of the wildlife found in the Upper Mississippi River Valley are pro-vided in Tables 2.7-5,2.7-6 and 2.7 7. Fish are quite abundant in the Upper Mississippi River, with 113 species recorded. A check list of fish collected ex-perimentally in the upper part of Pool 9 by Wisconsin Department of Natural Re-sources (DNR) biologists is presented in Table 2.7-8. Creel census data for Pool 9 is limited, but Iowa Conservation Commission personnel estimated for 1967 that 330,550 sport fish were caught in 320,000 hours of fishing by 65,000 anglers. The catch rate of 1.03 fish per hour is considered outstanding. Catches
/ of croppie, bluegill, drum, largemouth bass and sauger were 140,000, 80,000, 40,000,20,000, and 12,000 respectively. For the years 1965 through 1970 annual commercial catches by Wisconsin fishermen in Pool 9 have ranged from 886,595 to 1,485,637 pounds with corp comprising approximately 50% of the catch (Table 5.1-2). Annual commercial catches in Pool 9 could be increased severalfold with-out danger of overfishing.
None of the species of fish or other wildlife known to occur in the Upper ( Mississippi River Wild Life and Fish Refuge appears on the list of endangered species given in Appendix D to 50CFR17. I O 2 - 91
.)
() l l Table 2.7-1: Day Use by Waterfowl on Pool 9 of the Mississippi River by 18-Week Periods Seasonal Days Use Year Spring Summer Fall Total 1965 475,237 316,520 1,794,550 2,586,301 1966 1,203,400 521,040 1,935,340 3,659,780 1967 801,920 473,310 1,299,925 2,575,155 1968 722,610 292,625 1,231,740 2,246,975 1969 792,645 415,530 1,508,470 4,963,620 1970 1,080,930 1,931,665 380,975 3,393,570 1971 903,496 500,045 2,724,470 4,128,011 Source: U.S. Department of the Interior, Fish and Wildlife Service, Bureau of Sports Fisheries and Wild-life, Upper Mississippi River Wild Life and Fish Refuge, Winona, Minnesota. I 2 - 92
O l Table 2.7-2: Waterfowl Kill Data by Sportsmen on Pool 9 of the Mississippi River i Year 'Ifarvest flunters Waterfow]Alunter
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1965 570 495 1.15 l 1966 1,1:51 621 2.34 1967 1,447 698- 2.07 1968 750 607 1.24 1969 8'13 520 1.57 1970 684 471 1.45 1971 1,260 834 1.51 Source: U.S. Depar%,ent of the interior, Fish and Wildlife Service, Bireau of Sports Fisheries and Wild- )
-l life, Upper Mississippi River Wild Life and fish Refuge, Winona, Minnesota.
O 2 - 93 l
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O Table 2.7-3: List of Common Aquatic Plants Found in the Upper Mississippi River Common Name Scientific Name i Pondweed Potamogeton americanus Pondweed Potamogeton pectinatus Pondweed Potamogeton foliosus Pondweed Potamogeton sosteriformis Pondweed Potamogeton crispus Pondweed Potamogeton richardsoni Pondweed Potamogeton epihydrus Horned Pondweed Zannichellia Niad Nias Waterweed Elodea Duckweed Lemno Hornwort Ceratophyllus Water-milfoil Myriophyllum Bladderwort Utricularis Buttercup Ranunculus Lotus Nelumbo Waterlily Nymphaea Source: U.S. Department of the Interior Fish and Wildlife Service, Bureau of Sports Fisheries and Wildlife, Upper Mississippi River Wild Life and Fish Refuge, ; Winona, Minnesota. ( 1 i 1 l l i O 2 - 96
O Table 2.7-4: List of Trees Found in the Ook and Bottomland Hardwood Type Forests Adjacent to the LACBWR Site Common Name Scientific Name i Red Cedar Juniperus Virginiana. Butternut Juglans cinerea Black Walnut Juglans nigra Bitternut Hickory Carya cordiformis Shagbark Hickory Corya ovata Aspen Populus.tremuloides i Largetooth Aspen Populus grandidentata . Blue Beach Carpinus carolinians Ironwood Ostrya virginiana . Paper Birch Betula papyrifera But Oak . Quercus macrocarpa ! Swampy White Oak Quercus bicolor Hackberry Celtis occidentalis j Service Berry Amelanchier canadensis 1 Hawthorn Crataegus sp. Pin Cherry Prunus pennsylvania Chokecherry Piunus virginiana Black Cherry Prunus serotina Red Maple Acer rubrum Black Ash Fraxinue nigra
- White Ash Fraxinus americana
- Green Ash Fraxinus lanceolata-
- Slippery Elm Ulmus rubra
*American Elm Ulmus americana
" River Birch Betula nigra
- Cottonwood Populus deltoides
** Red Oak Quercus rubra
** White Ook Quercus alba
** Black Oak Quercus velutina ;
i
- Comprise in excess of 50% of species in bottomlands. I
** Comprise in excess of 50% of species in ook type forest.
Source: Wilson, F. G., Forest Trees of Wisconsin: How to Know Them, Publication No. 507-70 Wisconsin Department of Natural Resources, Madison, (undated). O 1 2 - 97. l
O Table 2.7-5: Check List of Amphibians and Reptiles Found in the Upper Mississippi River Wild Life and Fish Refuge l Common Name Scientific Name Relative Abundance S Turtles Snapping Turtle Chelydra serpentina Common Wood Turtle Clemmys insculpta - Rare Ornate Box Turtle Terrapene ornata Occasional Map Turtle Graptemys geagraphico Common False Map Turtle Graptemys pseudogeographica Common Painted Turtle Chrysemys picta Common Blanding's Turtle Emydoidea blandingi Common Smooth Softshell Trionyx muticus Common Spiny Softshell Trionyx spinifer Common Lizards Six-Lined Racerunner Cnemidophorus sexlineatus Common l Snakes Northern Water Snake Natrix sipedon sipedon Common Brown (DeKay's) Snake Storeria dekayi Uncommon Red-Bellied Snake Storeria occipitomaculata Uncommon Eastern Garter Snake Thamnophis sirtalis Common Eastern Hognose Snake Heterodon platyrhinos Occasional Ringneck Snake Diodophis punctatus Occasional Blue Racer Coluber constrictor foxi Common Fox Snake Elaphe vulpina Occasional ' Black Rat Snake Elaphe obsoleta obsoleta Common ; Bullsnake Pituophis melanoleucus sayi Common Eastern Milk Snake Lampropeltis doliata triangulum Occasional Massasauga Sistrurus catenatus Rare Timber Rattlesnake Crotalus horridus horridus Rare Salamanders Mud Puppy Necturus maculosus Common Eastern Tiger Salamander Ambystoma tigrinum tigrinum Common Toads American Toad Bufo americanus Common Frogs Blanchard's Cricket Frog Acris crepitans blanchardi Common 2 - 98
4 O Table 2.7-5: Check List of Amphibians and Reptiles Found in the Upper Mississippi River Wild Life and Fish Refuge Common Name Scientific Name Relative Abundance Spring Peeper Hyla crucifer - Common Gray Tree Frog Hyla versicolor Common Western Chorus Frog Pseudacris triseriata triseriata Common Bullfrog Rana catesbeiana Common Green Prog Rana clamitans melanota Common Leopard Frog Rana pipiens Common Pickerel Frog Rana palustris Rare Wood Frog Rana sylvatica Occasional Source: U.S. Department of the Interior, Fish and Wildlife Service, Bureau of Sports Fisheries and Wildlife, Amphibians and Reptiles of the Upper Mississippi River i Wild Life and Fish Refuge, Refuge Leaflet 420, June,1970. l O 2 - 99 ;
O
*?able2.7-6: Check List of Birds Found in the Upper Mississippi River Wild Life and Fish Refuge.
Seasong Abundance Common Name Spring Summer Fall Winter i Common Loon Rare Rare Red-Necked Grebe Rare Rare Horned Grebe Rare Rare ; Pied-Billed Grebe
- Common Common Common White Pelican Occasional- Occasional Double-Crested j Cormorant
- Common Common Common Great Blue Heron
- Common Common Common Rare Green Heron
- Common Common Common Little Blue Heron Rare Common Egret
- Common Common Occasional Snowy Egret Rare Rare Black-Crowned Night Heron
- Common Common Common Yellow-Crowned Night Heron
- Uncommon Uncommon Uncommon Least Bittern
- Occasional Occasional Occasional l American Bittern
- Common Common Common Whistling Swan Common Common Canada Goose
- Common Occasional Common Occasional White-Fronted Goose Rare . Rare 'i Snow Goose Common Common Blue Goose Common Common '
Mallard
- Abundant Common Abundant Common Black Duck
- Common Occasional Common Occasional Cadwall Common Common Pintail Abundant Rare Abundant Rare Green-Winged Teal
- Common Rare Common Rare Blue. Winged Teal
- Abundant Uncommon Abundant American Widgeon Abundant Abundant Shoveler Common Common Wood Duck
- Common Common Common l Redhead Common Occasional Common Rare !
Ring-Necked Duck Abundant Abundant Rare Convasback Common Common Rare Greatcr Scoup Uncommon Uncommon O 2 - 100
O Table 2.7-6: (Continued) I Seasonal Abundance
. Common Name Spring Summer Fall Winter Lesser Scaup Abundant Rare Abundant -Rare 1 Common Goldeneye Common Common Occasional Bufflehead Occasional Occasional Rare 3 Oldsguaw Rare Rare Rare White-Winged Scoter Rare Rare Rare ,
Rare Rare Common Scoter l Ruddy Duck Common Rare Common i Common Occasional Common Rare Hooded Merganser
- l Common Merganser Common Common 1 Red-Breasted Merganser Rare Rare Rare Turkey Vulture Occasional Occasional Occasional Rare q Goshawk Occasional j Sharp-Shinned Hawk Uncommon Uncommon Uncommon Occasional ]
Cooper's Hawk
- Uncommon Uncommon Uncommon Occasional {
Red-Tailed Hawk Common Common Common Common Occasional Occasional Uncommon l Red-Shouldered Hawk Occasional l Broad-Winged Hawk
- Occasional Occasional Rough-Legged Hawk Occasional Occasional Golden Eagle Rare Rare Rare Bald Eagle
- Occasional Occasional Occasional Common Marsh Hawk
- Commen Common Common Occasional Osprey Occasional Occasional Occasional Occasional Peregrine Falcon
- Rare Rare Rare Pigeon Hawk Rare Rare Sparrow Hawk Occasional Occasional Occasiona) Rare Ruffed Grouse
- Common Common Common Com mo..
Greater Prairie Chicken Rare Sharp-Tailed Grouse Rare i Bobwhite
- Occasional Occasional Occasional Occasional Ring-Necked Pheasant
- Common Common Common Common Gray Partridge Occasional Occasional Occasional Occasional King Rail
- Uncommon Uncommon )
Virginia Rail
- Uncommon Uncommon Occasional ]
Sora* Abundant Abundant Common Common Gallinule
- Rare Rare American Coot
- Abundant Common Abundant Rare Semipalmated Plover Common Occasional Common j Killdeer
- Common Common Common Rare O
l 2 - 101 i
1 O Table 2.7-6: (Continued) Seasonal Abundance 1 Common Name Spring Summer Fall Winter ') 1 American Golden Plover Occasional Uncommon Black-Bellied Plover Occasional Occasional Ruddy Turnstone Rare j American Woodcock Rare Rare Rare j
' Common Snipe Common Occasional Common Rare I Long-Billed Curlew Rare Upland Plover Occasional Occasional Spotted Sandpiper
- Common Common Common Solitary Sandpiper Common Common Willet Rare Rare Greater Yellowlegs Uncommon Uncommon J Lesser Yellowlegs Abundant Occasional Abundant j Pectoral Sandpiper Occasional Occasional Occasional White-Rumped Sandpiper Occasional Occasional Baird's Sandpiper Occasional Occasional Occasional Least Sandpiper Common Occasional Common Dunlin Occasional Occasional Occasional Long-Billed Dowitcher Occasional Occasional Stilt Sandpiper Occasional Occasional Occasional Semipalmated Sandpiper Ccmmon Common Common Sanderling Occasional Occasional Occasional Wilson's Phalarcpe Occasional Occasional Occasional Northern Phalarope Occasional Occasional Herring Gull Common Occasional Common Uncommon ;
Ring-Billed Gull Common Occasional Common Uncommon l Franklin's Gull Occasional Occasional Bonaparte's Gull Uncommon Uncommon Forster's Tern Common Occasional Common Common Tern Common Occasional Common Least Tern Occasional Occasional Occasional Caspian Tern Occasional Occasional Black Tern
- Common Common Occasional Mourning Dove
- Common Common Common Occasional Yellow-Billed Cuckoo
- Common Common Black-Billed Cuckoo
- Common Common Screech Owl
- Common Common Common Common O
2 - 102 1 L____.____________.__________.__________...____.__ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ . _
y f . 4 O Table 2.7-6 (Continued) Relative Abundance Common Name Spring Summer Fall Winter Great Horned Owl
- Common Common Common Common Snowy Owl Occasional Barred Owl
- Common Common Common Common Long-Eared Owl Uncommon Uncommon Uncommon Uncommon Short-Eared Owl Uncommon Uncommon Uncommon Uncommon Savi-Whet Owl
- Uncommon Uncommon Uncommon Uncommon Whippoorwill
- Common Common j Common Nighthawk
- Abundant Abundant Occasional Chimney Swift
- Abundant Abundant Ruby-Throated Hummingbird
- Common Common Belted Kingfisher Common Common Occasional Uncommon i
Yellow-Shafted Flicker
- Common Common Common Uncommon Pileated Woodpecker
- Occasional Occasional Occasional Occasional Red-Bellied Woodpecker
- Common Common Common Common Redheaded Woodpecker
- Common Common Common Rare Yellow-Bellied Sapsuckr Common Common ;
Hairy Woodpecker
- Common Common Common Common Downy Woodpecker
- Common Common Common Common Eastern Kingbird* Abundant Western Kingbird Uncommon Uncommon Great Crested l Flycatcher
- Common Common Eastern Phoebe
- Common Common Occasional Yellow-Bellied Flycatcher Uncommon Uncommon Uncommon Acadian Flycatcher Occasional Occasional 1 Traill's Flycatcher
- Common Common Occasional Least Flycatcher
- Abundant Abundant Uncommon Eastern Wood Pewee
- Common Common Uncommon Olive-Sided Flycatcher Occasional Occasional >
Horned Lark
- Common Common Common ' Occasional Tree Swallow
- Abundant Abundant Uncommon Bank Swallow
- Common Common Uncommon l Rough-Winged Swallow Occasional Occasional Born Swallow
- Abundant Abundant Uncommon Cliff Swallow
- Occasional Occasional Uncommon Purple Martin
- Abundant Abundant Uncommon 2 - 103 i
l
]
O Table 2.7-6: (Continued) Relative Abundance Common Name . Spring Summer Fall Winter - Blue Jay
- Common Common Common Common '
Common Crow
- Abundant Abundant Abundant Occasional j Black-Capped Chickadee
- Common Common Common Common Tufted Titmouse
- Common Common Common Common White-Breasted Nuthatch
- Common Common Common Common Red-Breasted Nuthatch Rare Brown Creeper Common Common Common l House Wren
- Abundant Abundant Occasional j Winter Wren Occasional Occasional 1 Bewick's Wren Occasional Occasional Carolina Wren Occasional Occasional Occasional Long-Billed Marsh Wren
- Common Common l Short-Billed Marsh Wren
- Occasional Occasional l Catbird
- Common Common Occasional Brown Thrasher
- Common Common Occasional Robin
- Common Common Common Rare Wood Thrush
- Common Common Common j Hermit Thrush Common Common l Swainson's Thrush Common Common Gray-Cheeked Thrush Common Common l Veery Common Common Eastern Bluebird
- Common Common Common Rare Blue-Gray Gnatcatcher Uncommon Uncommon ;
Golden-Crowned Kinglet Occasional Occasional Occasional Ruby-Crowned Kinglet Common Common ' Bohemien Waxweing Occasional Cedar Waxwing
- Common Common Common Occasional Northern Shrike Occasional Occasional Loggerhead Shrike Common Common Common !
Starling
- Abundant Abundant Abundant Abundant White-Eyed Vireo
- Common Common i Bell's Vireo
- Uncommon Uncommon i Yellow-Throated Vireo
- Common Common Common '
Solitary Vireo Occasional Occasional Red-Eyed Vireo
- Common Common Occ asional ~
Warbling Vireo
- Abundant Abundant Abundant Black-and-White Warbler Common Common O
2 - 104
O Table 2.7-6: (Continued) Relative Abundance. Common Name Spring Summer Fall _ Winter Prothonotary Warbler
- Common Common Blue-Winged Warbler
- Occasional Occasional Golden-Winged Warbler Occasional Occasional Tennessee Warbler Common Common Orcnge-Crowned Warbler Occasional Occasional Nashville Warbler Occasional Occasional Parula Warbler Rare Rare Yellow Warbler
- Abundant Abundant Occasional i Magnolia Warbler Common ' Common l Cape May Warbler Occasional Occasional (
Black-Throated Blue Warbler Occasional Occasional l Myrtle Warbler Abundant Abundant Black-Throated . Green Warbler Common Common Cerulean Warbler Rare Blackburnian Warbler Common Common Chestnut-Sided Warbler Occasional Occasional Occasional .I Bay-Breasted Warbler Occasional Blackpoll Warbler Common Common Pine Warbler Occasional Occasional Palm Warbler Common Common Ovenbird Occasional Occasional Occasional j Northern Waterthrush Common Common i Louisiana Waterthrush Occasional Occasional Occasional Kentucky Warbler Rare Rare Connecticut Warbler Rare Rare Mourning Warbler Occasional Occasional Yellowthroat* Abundant Abundant Occasional Yellow-Breasted Chat Rare Rare Hooded Warbler Rare Rare Wilson's Warbler Common Common Canada Warbler Common Common j American Redstart* Abundant Abundant Abundant House Sparrow
- Abundant Abundant Abundant Abundant ;
Bobolink
- Occasional Occasional Occasional l Eastern Meadowlork* Common Common Common Occasional Western Meadowlark
- Occasional Occasional Occasional Occasional Yellow-Headed 8 'kbi'd* " Si "
O " Si " l " Si " l 2 - 105
O-Table 2.7-6: (Continued) Relative Abundance Common Name Spring Summer Fall Winter Red-Winged Blackbird * ' Abundant Abundant Abundant Abundant Orchard Oriole
- Uncommon ' Uncommon Baltimore Oriole
- Commo . Common Rusty Blackbird Common Common Occasional. ..
Occasional Uncommon Rare l Brewer's Blackbird Uncommon Common Grackle
- Abundant Abundant Abundant Uncommon -
Scarlet Tanager
- Occasional Occusional Occasional Cardinal
- Common Common Common Common Rose-Breasted Grosbeck* Common Common Indigo Bunting
- Common Common Occasional Dickcissel* Common Common { '
Evening Grosbeak Occasional Purple Finch Occasional Occasional Occasional Common Redpoll Uncommon Pine Siskin Occasional Occasional Occasional : American Goldfinch
- Abundant Abundant Abundant Common Red Crossbill Rare i Rufous-Sided Towhee
- Abundant Abundant Abundant Common Savannah Sparrow Occasional Occasional Occasional l
Grasshopper Sparrow Occasional Occasional Occasional Henslow's Sparrow Rare Rare Uncommon Le Conte's Sparrow Uncommon Uncommon Uncommon Vesper Sparrow
- Occasional Occasional Lark Sparrow Occasional Occasional Slate-Colored Junco Common Common Common
! Tree Sparrow Common Abundant Abundant Chipping Sparrow
- Abundant Abundant Abundant Clay-Colored Sparrow Uncommon Uncommon Uncommon Field Sparrow
- Common Common Common Rare Harris' Sparrow Common Common White-Crowned Sparrow Occasional Occasional Rare White-Throated Sparrow Abundant Abundant Rare Fox Sparrow Occasional Occasional Lincoln's Sparrow Common Common Swamp Spacrow* Common Common Occasional Song Sparrow Abundant Abundant Common Rare lu O
2 - 106
O i Table 2.7-6i ' (Continued) ) Relative Abundance Common Name Spring Summer Fall Winter Lapland Longspur 0ccasional Occasional Occasional Snow Bunting Uncommon
# Data provided by the Fish and Wildlife Service
- Nests on refuge
.i Source: U.S. Department of the Interior, Fish and Wildlife Service, Bureau of Sports 1 Fisheries and Wildlife, Birds of the Upper Mississippi River Wild Life and Fish !
I Refuge, RL-142-R, Revised, May,1958 and RL-142-Rr, April,1970. 1
)
O 2 - 107 i
t l 1 O . Table 2.7-7: Check List of Mammals Found in the Upper Mississippi River Wild Life and Fish Refuge L I Common Name Scientific Name Relative Abundance
# Virginia Opossum Didelphis marsupialia Common Masked Shrew Sorex cinereus - Common Shorttail Shrew Blarina brevicauda Common l Least Shrew Cryptotis parva Common Eastern Mole Scalopus aquaticus Common Starnose Mole Condylura cristata Rare Little Brown Bat Myotis lucifugus Common j Keen's Bat Myotis keenii Common Eastern Pipistrel Pipistrellus subflavus Uncommon ;
Big Brown Bat Eptesicus fuscus Common Red Bat Lasiurus borealis Common Hoary Bat Lasiurus cinereus Rare Whitetail Jack Rabbit Lepus townsendii Rare Eastern Cottontail Sylvilagus floridanus Common Woodchuck Marmota monax Common Thirteen-Lined Ground Squirrel Citellus tridecemlineatus Common Franklin Ground Squirrel Citellus franklinii Rare Eastern Chipmunk Tamias striatus Common Eastern Gray Squirrel Sciurus carolinensis Common Eastern Fox Squirrel Sciurus niger Common Red Squirrel Tamiasciurus hudsonicus Occasional l Southern Flying Squirrel Glaucomys volans Occasional l Plains Pocket Gopher Geomys bursarius Occasional l Beaver Castor canadensis Common Western Harvest Mouse Reithrodontomys megalotis Uncommon Deer Mouse Peromyscus maniculatus Common White-Footed Mouse Peromyscus leucopus Common i Southern Bog Lemming Synaptomys cooperi Common Meadow Vole Microtus pennsylvanicus Common Prairie Vole Pedomys ochrogaster Common Pine Vole Pitymys pinetorum Occasional Muskrat Ondatra zibethicus Common Norway Rat Rattus norvegicus Common House Mouse Mus musculus Common Meadow Jumping Mouse Zapus hudsonius Common Nutria Myocaster coypus Rare Coyote Canis latrans Occasional Red Fox Vulpes fulva Common O 2 - 108
4 O Table 2.7-7: (Continued) j Common Name Scientific Name Relative Abundance ) Gray Fox Urocyon einereoorgenteus Common J
' Raccoon- Procyon lotor . Common Least Weasel Mustela rixosa Uncommon Mink Mustela vison Erratic Badger. Taxidea taxus Uncommon Spotted Skunk Spilogale putorius Occasional Striped Skunk Mephitis mephitis Common River Otter Lutra canadensis Occasional Lynx Lynx canadensis Rare Bobcat Lynx rufus Rare White-Tailed Deer Odocoileus virginianus Common # Data provided by the Fish and Wildlife Service ,
Source: U.S. Department of the Interior, Fish and Wildlife Service, Bureau of Sports I Fisheries and Wildlife, Upper Mississippi River Wild Life and Fish Refuge, Winona, Minnesota, Refuge Leaflet No. 326, May,1968. O 2 - 109
O Table 2.7-8: Species, Composition and Relative Abundance in Fish Samples Taken by Electrofishing at Three Locations Below Dam No. 8 for Five Sampling Periods in 1961 Immediately below Above Bad Axe Below Bad Axe
- Fish Species Dam No. 8 River Mouth River Mouth No. % No. % No. %
Bluegill 54 18 29 5 11 3 Black Crappie 43 14 23 4 39 11 White Crappie 28 9 .1 . 11 3 White Bass 42 14 392 66 38 11 Walleye 3 1 5 1 10 3 Carp 38 13 59 10 160 44 Smallmouth Buffalo 4 1 1 - 3 1 Northern Pike 2 1 1 - 1 - Largemouth Bass 18 6 22 4 10 3 Smallmouth Bass 2 1 6 1 2 1 Quillback 17 6 2 - 1 - Sauger 6 2 4 1 5 1 Silver Redhorse 6 2 7 1 9 3 Northern Redhorse 7 2 27 5 16 4 River Corpsucker 1 - - - 5 1 Freshwater Drum 1 - 4 1 14 4 Plains Corpsucker 20 7 4 1 6 1 Bigmouth Buffalo 1 - - - - - Channel Catfish 1 - - - 6 1 Golden Redhorse 3 1 - - 8 2 Longnose Gar 1 - - - 1 - Bowfin - - - - 5 1 Mooneye - - 2 - 1 - Lamprey - - 1 - - - Pumpkinseed - - 1 - - - Yellowbass - - 5 1 - - Yellow Perch - - 1 - - - Total 298 98 598 101 362 99
- Data provided by the Wisconsin Department of Natural Resources.
Source: Hubley, Raymond C., Jr., Mississippi River Electrofishing in Pools 9,10,11 and 12 during 1961. Investigational Memorandum No.15, Wisconsin Conservation Dept., Fish Management Division. O 2 - 110
1 1 I O 2.8 OTHER ENVIRONMENTAL FEATURES ] 2.8.1 Background Radiological Characteristics ! Baseline radiological data were obtained for the LACBWR site and environs during several years prior to plant operation. Samples were taken of air, precipi- l 1 tation, river water, ground water, river silt, soil, vegetation, milk, fish and animals, and analyzed for radioactivity. The types of samples, analyses and minimum de- l 1 tectable activity for each are shown in Table 2.8-1. The results of the preopera- l tional survey from April,1965, to April,1966, are reported in Tables 2.8-2 through 2.8-13 as being representative of background levels. (1) Subsequent preopera-tional analyses are reported elsewhere (2,3,4) and provide comparable information. Dose measurements during the preoperational phase were made with dosi- , 1 metry packets which were found to be unreliable and inconsistent. In the third
]
quarter of 1970, new dosimetry packets containing five thermoluminescent dosi-meters (TLD's), were placed in use. They have provided consistent and repro-ducible dose measurements. Since plant originated radiation was far below de- j tectable limits through December 1971 (See Section 3.6), the results of these measurements are representative of the background exposure. The annual dose l estimates, calculated from quarterly TLD readings, are presented in Table 2.8-14 for the locations shown in Figure 2.8-1. A terrestrial radiation survey (5) was conducted during July,1968, for a j square centered about the LACBWR site and measuring 25 nautical miles or, each l side. The Aerial Radiological Measuring System (ARMS) was used to collect gross gamma count and gamma spectral data at a flight level of 300 feet above terrain. Exposure rates three feet above the ground were determined from the gross counts to range from 2 to 10 microroentgens per hour (p R/hr). These ex-posure rates may be converted to roughly 18 and 88 mR/yr and are typical of the range of background radiation levels found throughout the United States. The 2 to 4 p R/hr isoexposure contours are due primarily to cosmic radiation and con-form closely to the boundaries of the Mississippi River. The gamma spectral anal-yses revealed only those radionuclides having photopeaks consistent with natural O background radiation. 2 - 111
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, Sample Analysic Detectlun Limit Analyzed Air P.criculate But2-Gamma 2 X 10-3 pc/m3 10.309 f t.3 (a) a 1
Rain Water Be ta-Gmnma 5 pe/1 $u0ml El River Water Beta-Ganina (Susp) 5 fuv'i (b) 500 ml Alpha (Susp) 0.5 pe/1 (b) 500Drt Beta-Gamma (Diss) 5 pe/l 500 ml Alpha (Diss) 0.5 pc/1 500 ml Sr-90 0.5 pc/1 1,000 ntl Cs-137 1.0 pc/1 1,000 ml f' Tap Water Beta-Gamma 5 pc/1 500 ml Alpha 0.5 pc/1 500 ml Well Water Be ta-Ganyna 5 pe/1 500 ml Alpha 0.5 pc/1 500 ml
' River Silt Beta-Ganina 2 pc/gn (c) 1 gm Alpha 1 pe/g;n c) 1 gm Sr-90 0.1 pc/gn ((c) 10 gms Ce-137 !
0.2 pc/gm (c) 10 gms i g Soil Deta-Ganma 1 2 pc/gm (c) 1 gn Alpha 1 pc/on (c) .t gn i Vegetation Beta-Gamma 0.5 pc/gm (d) 1 gn Fish beta- Ganvna 0.05 pc/gm i 10 gms I Sr-90 0.005 pc/gn 100 gns Cs-137 0.01 pc/gn 100 gms ) i Animal Beta-Canna (carcass) 0.05 pc/gn 10 gns 1 Betal Ganvna (11 er & kidney) 0.05 pc/gn 10 gns Sr,90 (bone) 0.05 pc/gn (e) 10 gms Cs.137 (carcass) 0.01 pc/gn 100 m j i l Milk Csk237 1.0 pc/1 SPD td l Sr-9d 2.0 pc/1 500 ml I-131 20.0 pc/1 1,000 nti a) Ba:md on a sample rate of 1 scu. f t./ min, for one week periods. b) Based on volume of water from which suspended solids originate. ) c) Based on dried (ignited) weight. j d) Based on dried (280 C) weight. e) Error reported with sample are for one sigma counting statistics. Error listed in this column is that for overall procedure at ten times detection limlt. for gross procedures, the error due to variation in nuclides present from the standard used has been t considered on an average rather than for extreme possibilities. i
.O 2 - 112 )
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l (Concentrations in pCi/1) i .' Gross Beta Activity Gross Alpha Activity s s Location & Date Suspended Dissolved Total Suspended Dissolved Total . l.' '
, k'eferenc e l Statio_rj April 61 20 81 1 1 2 May~ If 64 80 1 1 2 l June- 119 16 135 1 1 2 July 5 32 37 1 15 16
[- August 5 18 23 1 4 5 September 6 7 13 1 1 2 October 11 14 25 1 1 2 November 5 28 33 1 1 2 December 8 11 19 1 1 2 l January 3 8 11 1 1 2 February 5 5 10 1 1 2 March 5 9 14 1 1 2 Stoddard April 44 11 55 1 1 2 3 May 3 5 8 1 1 2 j June 5 15 20 1 3 4 July 5 19 24 1 1 2 August 5 19 24 1 1 2 l September 6 38 44 1 6 7 October 11 21 32 1 2 3 Neveuber 7 12 19 1 1 2 December 5 12 17 1 1 2 l January 5 5 10 1 1 2 February 5 5 10 1 1 2 March' 8 5 13 1 1 2 Dam 110. 8 April 39 lin 53 1 1 2 May 12 5 17 1 1 2 June 5 10 15 1 1 2 l July 5 20 25 1 2 3 August 5 15 20 1 1 2 O 8 P**"cer 5 22 27 1 2 3 Octet;e .' 5 11 16 1 1 2 (Continued) 2-115
I- . 1 1 1 l l O-4 Table 2.8-4: (Continued) i November 5 24 29 1 1 2 l
'DLeember 5 16 .21- 1 1 2 January 5 8 13 1 1 2 February 5 5 10 1 1 2 March 5 5 10 1 1 2 Boat Launching Area April 62 27 89 1 1 2 May 54 7 61 1 1 2 June 5 6 11 1 1 2-July 8 18 26 1 1 2 August 5 14 19 1 1 2 September 6 39 45 1 1 2 October 5 8 13 1 1 2 November 5 28 33 1 1 2 December 5 5 10 1 1 2 January 3 9 12- 1 1 2 February 5 9 14 1 1 2 March 8 7 15 1 1 2 Victory April 46 21 67 1 1 2 ;
May 15 111 126 1 1 2 ! June 5 6 11 1 1 2 July 5 32 37 1 35 36 August 5 36 41 1 1 2 September 5 7 12 1 1 2 October 6 44 50 1 1 2
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O REFERENCES
- 1. Tracerlab, "La Crosse Boiling Water Reactor Environmental Radiation Survey Program, Annual Report, April 1,1965 to March 31,1966,"
Tables I-IX.
- 2. Tracerleb, "La Crosse Boiling Water Reactor Environmental Radiation Survey Program, Annual Report, April 1,1966 to March 31,1967."
- 3. Tracerlab, La Crosse Boiling Water Reactor Environmental Radiation Survey Program, Annual Report, April 1,1967 through March 31,1968."
- 4. Tracerlab, "La Crosse Boiling Water Reactor Environmental Radiation l Survey Program, Annual Report, April 1,1968 through March 31,1969."
l 5. E G & G, Inc., "La Crosse Boiling Water Reactor Aerial Measuring System Survey," Las Vegas Division, Las Vegas, Nevada (1971). i l l l l l l L O ; 1 2 - 127
O 3.0 THE PLANT 3.1 EXTERNAL APPEARANCE The principal structures comprising the LACBWR are the containment building, the turbine building, the service building and the stack (Figure 3.1-1). The containment building, which resembles a large silo, is a vertical con-crete cylinder capped by a steel dome. it is 60 feet in diameter and 128 feet high, with an additional 16 feet below grade. The turbine building, immediately west of the containment building, is 75 l feet wide,110 feet long and 63 feet high. Its north wallis shared by the ser-vice building, which is 30 feet wide,110 feet long and 63 feet high. The tur-bine and service buildings form a single architectural unit sheathed in unpainted corrugated aluminum with the main facade -- the front of the service building -- i on the north. The service building facade resembles that of a conventional three-story office building. Just east of the containment building is the LACBWR's free-standing con- i crete stack, which is 350 feet high. The LACBWR appears smallin relation to Genoa 3, whose turbine building is 205 feet high and has a 500 foot stack.
.l
, Just north of the LACBWR, opposite the service building entrance, is a l parking lot for approximately 40 cars. There are lawn areas around the parking lot and the area flanking the service building entrance is landscaped. The developed portions of the DPC property, excluding the boat-launch , 1 facility and its access road, are enclosed by an eight-foot cyclone fence. 1 i i O 3-1 i _ _ _ __ _ - _ ~
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O 3.2 TRANSMISSION LINES No r.:w off-site transmission lines were constructed for the LACBWR. Its electrical output is delivered to the Dairyland Power system via transmission facilities previously constructed. Within the Genoa Station property, a 69 KV line connects the LACBWR with the main switchyard, a distance of about 1,000 feet, as shown in Figure 3.2-1. Dairyland Power transmission lines in Vernon, Houston, La Crosse and . Allamakee counties are mapped in Figure 3.2-2. l l i l l
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O i 3.3 REACTOR AND STEAM-ELECTRIC SYSTEM 3.3.1 General Description The LACBWR is a nuclear power plant of nominal 50 MWe capacity. Its heat source is a forced-circulation, direct-cycle, boiling-water reactor. The reactor operates at a pressure of 1300 psia and produces 165 MWt'(see Figure 3.3-1). Feedwater returning from the turbine-condenser at a temperature of 285* F u is mixed with the recirculating coolant. The coolant enters the bottom of _the core and boils within the core to produce 610,000 pounds of steam per hour. A portion ] of this steam is separated from the coolant at the steam-water interface within ; the reactor vessel and the remainder is removed by 16 centrifugal steam separa-tors inside the reactor vessel. Eteam dryers in the dome of the reactor vessel . remove entrained moisture and the dry saturated steam leaves the reactor vessel { l at 1300 psia and a temperature of 577.5'F. Inlet conditions at the turbine are 1265 psia and 574* F. Steam passes through the high-pressure element of the turbine and, after passing through a i moisture separator and a reheater, enters the intermediate-pressure element and then passes to the low-pressure element. It is exhausted to the condenser at an absolute pressure of one inch of mercury. The design gross electrical output of the turbine-generator is 55.9 MWe. With an auxiliary load of 3.5 MWe, the net electrical output is 52.4 MWe and the net cycle efficiency is 31.8%. Condensate passes through the condensate pumps and demineralizers, feedwater hecters 1 and 2, the feedwater pumps and feedwater heater 3 before returning to the reactor system. O ; 3-6 L __ __
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I O 1 3.3.2 The Reactor The reactor pressure vessel has an internal diameter of 8.25 feet and on i overallinternal height of 37 feet. The vesselis constructed of ferritic steel and is lined with stainless steel. Its design pressure is 1400 psig. Figure 3.3-2 is j a cutaway drawing of the reactor vessel. The reactor core has an equivalent diumeter of 5.09 feet and on active height of 6.92 feet. It contains a total of 72 fuel assemblies, with a nominal i uranium content of 8600 kg. Each assembly is enclosed within a removable sec-tion of shroud. The channels between adjacent shrouds guide the control rods. The startup core used both zirconium shrouds and stainless steel shrouds. 1' However, the stainless steel shrouds in the initial core were replaced part way through first-core life by zirconium shrouds. The use of stainless steel shrouds ! initially reduced the amount of reactivity to be controlled and improved the power distribution within the core. 3.3.3 Fuel Assembly Each fuel assembly consists of a 10 x 10 array of fuel rods 0.396 inches in outside diameter by 83 inches long (active length), on a 0.565-inch pitch. The rods consist of 0.020-inch-thick stainless steel tubing, filled with 0.350-inch uranium dioxide fuel pellets. In the first core, the uranium enriched to 3.6% in uranium-235. Second core enrichment is 3.9%. Figures 3.3-3 and 3.3-4 are diagrams giving fuel element and assembly details. O 3-B
O 3.3.4 Control Rods The core includes 29 cruciform control rode with B4 C pellets as absorber. The pellets are contained in inconel tubes, which are packed cruciform-shaped sheaths of stainless steel; each sheath is 5/16-inch cruciform span and an active length of 83 inches. The effective multiplication factor of the cold, clean core, , loaded for a burnup of 12,700 megawatt days per standard ton of contained urani-um, is 1.198 Total rod insertion in this condition would reduce this multiplica-tion factor by 0.268 (which would make the reactor subcritical by 7.0%A(). Even if the rod of greatest worth were not inserted, the remaining control rods could make the reactor suberitical by 1.3%A{, which exceeds the shutdown margin de-l sign criterion of 0.5%%with one stuck rod. The control-rod extensions penetrate the bottom head of the reactor vessel. i Normally the rods are positioned by electro-mechanical drive mechanisms that withdraw them downward out of the core to increase reactivity and insert them i 1 upward into the core to decrease reactivity. The rods are scrammed upward by hydraulic motors. ; i O 3.-9
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, Reactor power is normally controlled and matched to load demand by con-trolled forced-circulation flow of reactor water through two piping loops external a to the reactor vessel. Flow control is accomplished by two 15,000 gpm, single-stage, vertical centrifugal pumps, one in each piping loop. The loops have com. !
mon inlet and discharge headers so that uniform distribution of flow to the reac- ! tor-vesselinlet nozzles is maintained in the event of reduced power operation with only one pump. A flow of high-pressure demineralized water cools the pump mechanical seals and prevents leakage of primary-system water. The speed of l the recirculation pumps is variable and is controlled by the plant control system, which uses turbine inlet pressure as a primary signal. 1 All portions of the recirculation-loop piping, which is permanently embedded within the primary hiological shield, are of stainless steel. A portion of the piping behind removable portions of the shield is of low alloy steel. Shutoff valves between stainless steel and low alloy steel sections of piping permit isolation of the low alloy sections. l o , l L
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The steam turbine is cn J.Ilis-Chalnr .agh-pressure-condensing, straightJ reaction, tandem-compound machine. It cor.sists of c 3600 rpm, single-flow high' and intermediate-pressure clerant, with a double-flow low 9tessure element or-
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The turbine rotor is connected t'o gt' e genemfor by a rigid coupliig. The,, t generator is connected to the maiu exciter by redw. tion gearing. The turoine- - ;
.> f generator is oriented so that the axis of rotaticn of the rotors would, if exterdei pass through the containment building.
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The turbine condenser is mounted on t$e grade ficor dirretly under the tur2 l bine exhaust. The horizontal axis of the condons$r is parpeadicular to the hori-l zontal axis of the turbine. The expansion betweer. th condmser and the turbine is absorbed by a flexible rubber belt expansion joirt between be condenscr neck and the turbine exhaust flange. The turbine is designed for dry saturated steam at a throttle pressure of' 1265 psic vith a steam flow of 703,lfs9 pounds per hour Izom the reactor and an exhaust pressure of one inch of merecry absolute. "he brbine-generator is espa-ble of producing a gross electrical output of 64,537 KWe and a net e'ectrical out-2 put of 60,000 KWe. The generctor is an Allis-Chalners two-pole,60-cycle, three-phase,13.8 KV, hydrogen-cooled machine, rated nt 76,800 KVA at an 85% power factor w2h thy -
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l drogen pressure of 30 psig. A shaft driven 1207 rpm main exciter, rated at 300 KW, l supplies 250 volts D.C. for field ncitation. A reserve 2300-volt, motec4 riven 1. I' 1190 rpm exciter, similarly rated, ic provided. A rotating amplifier voltage con-trol set is located in the excitation cubiclis on the turb.ine hell' main floor. Cool-ing for the generator is provided by the hydrogen coolbg system. Fans on each end of the rotor shaf t circulate the hydrogen through the stator and rotor windings. 'l Water-cooled heat exchangers in the generator casing cool the hydrogm. I O 3 _.14'
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3 t-9 10 l ,- 3.3.7 The Condenser s 3 The condensing equipment includes c 70,000-square-foot two-pass, divided !s
]
- i. , water box suricce condenser. It is rated ai 4.23 x 108 Btu per hour with a circu- I i
lating water flow of 62,600 grm at 6f F inlet temperature. There are two 32,000 J
)
gpm circulating wat.er pumps two 1500 gpm condensate pumps; full-flow conden-sate demineralizers; a motor-odven dry vacuum pump; and a steam-jet air ejector. ) The vacuum puma . is used during starttp cond the steam-jet air ejector is used l
~ during normal operation. The condenser h supplied with circulating water from
, two punips in the cr}b house i!tlet at the iver. The water is discharged downstream of the crib house. A steam bypass system is provided from the main steam line )
.to the turbine condenser. This system is available if required during reactor startup and shtddown or during turb.ine or generator trip-out. A hydraulically- j operated dump:vslve controls the bypass. The bypass line is designed for 100%
of full-throttle 11ow. The condenser hot well has a 4,000-gallon capacity for con-trol of system water inventory, i i 3.3.8 Off-gas System Noncondensible gases removed from the condenser by the air ejector are j oormnily diccharged 19 tough a holdup tank through air dryers and particulate and charcoal filters to the stack. The off-gases are monitored so that, if the radio-activity excreds permissible levels, the gases are pumped to storage tanks which provide for 72-hout holdup at full power opewtion (Sec. 3.5). In this situation, the gases are passed through a recombiner to eliminate the dissociated hydrogen and oxygen before beuig pumped to the storege tanks. i 4 h l 1 O o ! 3 -15 j
i O ; 3.3.9 Contractors The prime contractor for the LACBWR was the Atomic Energy Division of the Allis-Chalmers Manufacturing Company. The architect-engineer was Sargent and Lundy Engineers; the general contractor was the Maxon Construction Company. Additional detailed data on the LACBWR nuclear and steam-electric systems is listed in Table 3.3-1, 1 l 1 I l l l l O 3 - 16 l _ . _ - - - _ _ = _ _ _ -
O Table 3.3-1: LACBWR General Plant Design Heat Balance The rm al pow e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 164.7 MW t Gross electrical output . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55.9 MWe Net electricol output . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52.4 MWe Net e f ficiency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31.8% Steam leaving reactor vessel: condition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . sa tura ted ma x im um m ois ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.1% pr e s s u r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 1300 psia te mpe ra ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 577. 5* F i f low ra te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 610,233 lb/hr Steam entering turbine: condition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . saturated j pr e s s ure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1265 psia j te mpe ra tu re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 573.9 " F j flow ra t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 529,600 lb/hr Feedwater to reactor: condition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . subcooled pressure........................................ 1350 psia { tempe ra ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 8 5.6 F - l f l ow ra t e * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 610,2331b/hr l
- 1 Core l l
A ctive diame ter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 in A ctive heigh t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 in Active volume . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 980 liters Total uranium content . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8600 kg Initial U-235 enrichment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.63% Water / uranium dioxide volume ratio (unrodded) . . . . . . . . . . . . . . . . . . . . 2.63 Water reflector thickness . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17.0 in l i
*lncludes seal and purification water O
3 - 17 \ ___-__._m___mm__ m.m-
i
)
O j Table 3.3-1: (Continued) ! Fuel Assemblies N 2. of a s s em blie s in core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 No. of fuei rods per assembly . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . 100 Arrangement of rods in assembly . . . . . . . . . . . . . . . . . . . . . . . . . 10 x 10 f Outside rod diameter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.3961n i R od pitch . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.56 5 in l Clodiing material . . . . . . . . . . . . . . . . . . . . . . . . . . Type-348H stainless steel U density . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15. 41 g /c m 1 U O dia me te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.3 50 in A ctive iuel length . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 in End plug material . . . . . . . . . . . . . . . . . . . . . . . . . Type-348H stainless steel Heat flux: average................................... 109,100 Btu /hr-ft maximum at 100% power * . . . . . . . . . . . . . . . . . . . . . . . 434,700 Btu /hr-ft 2-calculated burnout . . . . . . . . . . . . . . . . . . . . . . . . . . . . 810,000 Btu /hr-ft burnout safety factor at 100% power * . . . . . . . . . . . . . . . . . . . . . . . . . 1.86 burnout safety factor at 120% power * . . . . . . . . . . . . . . . . . . . . . . . . . 1.55 UO temperature: 2 ave ra ge o t 100% ,7we r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 930
- F maximum at 100% power * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3850
- F I maximum at 120% power * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4750
- F Reactor Vessel Materials of construction:
vessel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A302B carbon steel cladding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Type-304L stainless steel i Diame ter, inside . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.25 ft Thickness of cylindrical portion (including cladding) . . . . . . . . . . . . . . . . 4 in Thickne ss of cladding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.188 in l I
- Based on data for the preliminary design model of the startup core with a flux ratio of )
3.98 conservative overall peak-to-average. ) 1 I i O 4 3 -18 4
.)
a l O Table 3.3-1: (Continued) Heigh t , insid e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 f t ) Design pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1400 psig Design temperature . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 650 F Vessel closure type . . . . . . . . . . . . . . . bolted, double closure with ; between-seal leckoff time required to open . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6hr time required to c1ose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 hr Inner thermcl shield: material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Type-304 stainless steel thickness . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2 5 in j Weight of contained water and steam I during operation . . . . . . . . . . . . . . . . . . . . . 20.92 tons l l Nuclear Data
- 2 Average thermal flux, initial . . . . . . . . . . . , . . . . . . . 1.5 x 10 13 n/cm .3,c Max / average radial flux ratio . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.43 Max / average axial flux ratio . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.95 Max / average local flux ratio . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.31 !
Overall peak / average flux ratio (100% power) . . . . . . . . . . . . . . . . . . . 3.65 Core burnup: initia l c or e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12,700 Mwd /ST ) equilibrium core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15,000 Mwd /ST ] 3 Multiplication factor of cold, clean core (l(,gg) . . . . . . . . . . . . . . . . . 1.1 9 8 { I Change in multiplication factor ((,gg) of startup core caused by: temperature rise from 68
- F to 577.5'F . . . . . . . . . . . . . . . . . . . . . 0.031 steam void formation and Doppler broadening . . . . . . . . . . . . . . . . . 0.038 xenon and samarium poisoning . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.038 Total amount by which all control rods can change the
']
multiplication factor of the cold, clean core (){ egg) . . . . . . . . . . . . . 0.268 ; Shutdown multiplication factor of cold, clean i core with all rods in ()( 0.930 Shutdown multiplicationwith fEbo) r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . all but the most valuable rod in (8,gg) . . . . . . . . . . . . . . . . . . . . . . 0.987 Maximum reactivity insertion rate for rod withdrawal from a cold, clean core during normal startup (cents /sec) . . . . . . . . . . . . 6 ) i O 3 -19 1
1 l 0 Table 3.3-1: (Continued) { i Heat Transfer and Fluid Flow l Average power density in core . . . . . . . . . . . . . . . . . . . . . . . . 41.4 kw/ liter Max. power density in core * . . . . . . . . . . . . . . . . . . . . . . . 151.1 kw/ liter , Recirculation flowrote . . . . . . . . . . . . . . . . . . 10,750,000 lb/hr (30,000 gpm) Flow-through fuel assemblies . . . . . . . . . . . . . . . . . . . . . . . . . 28,880 gpm Flow-through control-rod channels . . . . . . . . . . . . . . . . . . . . . . . . 745 gpm j Flow area per fuel assembly . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.136 ft2 q Core-inlet velocity: a ve ra ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.4 f t/se c m in im u m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.0 ft/sec { j m a xi m u m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.6 ft/sec { Steam void fractions (based on water volume in fuel assembly shrouds):
)
o v era g e in c ore . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.21 a vera ge exit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.37 f j ma xim um e xit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0.57 3 Inle t s u bcoolin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.5
- F Heat-transfer area per fuel assembly . . . . . . . . . . . . . . . . . . . . . . 71.71 ft2
- Based on final design physics calculations performed for the startup core con-figuration with 36 stainless steel shroud cans and 36 zirconium shroud cons.
I l
\
l 3 - 20
.I 1
1 4 i f O ; 3.4 WATER USE Cooling water for the LACBWR comes from the Mississippi River. Two wells located within the site boundaries provide water for other plant needs. Figures 3.4-1 and 3.4-2 are water-use diagrams for the stations showing major plant usage. The individual water supply systems for the plant are discussed in the fol-lowing subsections. 3.4.1 Well Water System Wells supply water to the plant and office for sanitary and drinking pur-poses, and to the generator wash-down stations. Water supplied by the system is used at personnel decontamination stations, at three emergency showers and at two eyewash stations. It is used as cooling water for the two air conditioning units and in the boiler blowdown flash tank. The well water is also used for the plant makeup demineralized system. Water is supplied from two deep wells. Well No. 4 is located 115 feet southeast of the containment vessel center and well No. 3 is located 205 feet northeast of this centerline. The wells are 12 inches in diameter, with eight-inch pump casings and piping. The upper 40 feet of casing is set in concrete. The sealed submersible pumps take suction through stainless steel strainers and dis-charge into pressure tanks. i I i O l 3 - 21 I 11
-----,-----.---------_--_---w- - - - _ - - - - - - - - . - . . - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 o 3.4.2 Demineralized Water System To provide chemically-pure water for various plant uses, the system includes facilities for demineralizing, storing and distributing the water as well as appro-priate instrumentation for monitoring purity, pressure levels, etc. Well water enters the makeup demineralized through an isolation valve and on integrating flowmeter. The meter will alarm the control room when a preset number of gallons has passed through. From the meter, w6ter enters the top of the cation resin tank through a . i stainless steel mesh distribution header. The mesh on this and all other internal J headers is fine enough to catch any resins and to prevent them from entering the w l 1 water systems. The water then flows down through the cation resin bed, out the l bottom through an outlet header, and enters the top of the decarbonator through a level control valve. The float of this valve is located in the bottom tank portion of the decarbonator and it regulates flow into the top of the column to maintain the desired levelin the bottom tank portion. Water entering the top of the column flows downward through a pecked bed of plastic saddle-type packing. Air from a blower blows upward through the pack-ed bed. The packing breaks up the water flow into a thin film-like spray, ex-posing the water to the blower air. The air scrubs the CO ut of the water. 2 Air and CO2 both pass up the stack to the roof. The water draining from the col-umn collects in the bottom tank portion. Water is then pumped from the bottom of l the decarbonator tank to the top of the anion tank. The water flows downward through the anion resin bed and out the bottom to two two-inch lines, one of which goes to the virgin water tank and the other to the condensate storage tank. -; The condensate storage tank and the virgin water tank are actually two sec-tions of an integral aluminum tank located on the office building roof. The lower section is the condensate storage tank. It has a capacity of 19,100 gallons. The upper, or virgin water section holds 29,780 gallons. Both tanks have high and low level alarm protection, and each tank level is transmitted to and shown on levelindicators in the control room. O 3 - 22 l
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O 3.4.3 Low-Pressure Service Water System The low-pressure service water system supplies various heat exchangers and auvillary equipment located in the generator plant and waste treatment build-ing. The system is supplied by two centrifugal pumps located in the crib house. Water is piped underground to the turbine building, entering in the turbine oil storage room. The main line then divides in the area above the service air com-pressors to provide various subsystems with cooling water. These subsystems are listed in Table 3.4-1. I l l i i O 3 -25
i
),
l O Table 3.4-1: Subsystems Supplied by the Low-pressure Service Water. System High-pressure service water system (s pply only) Circulating water pump bearings Component cooling heat exchangers (two units) Generator hydrogen coolers (four units) 3 Condenser vacuum pump l Turbine lube oil coolers j Air conditioning units (backup supply) ) (a) Office building I (b) Control room l Heating boiler relief volve flash tank (backup supply) j j Reactor feed pumps lube oil and CPLC water coolers (two units) Waste gas system (a) Waste gas compressor (b) Waste gas compressor inner and after coolers (c) Recombiner condenser Contaminated liquids disposal system (a) Concentrated waste tank (b) Spent resin tank (c) Evaporator condenser I (d) Drumming station area j Turbine condenser discharge water radiation monitor eductor I O l l 3 -26 1
0 3.4.4 High-Pressure Service Water System The high-pressure service water system supplies the fire protection system, the high-pressure core spray system backup, the alternate core spray system, cir-culation water out-fall contamination monitor eductor (backup supply) and the crib house screen wash system. The high-pressure service water pump takes a positive suction at about 65 psig from the low-pressure service water system. It discharges into a header that divides into two main loops. One loop serves the turbine building, contain-ment building, waste treatment building and gas vault; the other loop supplies the outside fire protection system and the crib house. During normal operation, system pressure is maintained between 100 and 140 psig. The pump is protected against a low suction pressure by a 35 psig suction pressure trip. Backup protection for the system is provided by one of two diesel driven auxiliary service water pumps that will maintain system pres-sure between 60 and 150 psig. A fire protection sprinkler system for the oil storage room and for the tur-bine oil reservoir is supplied by the high-pressure service water system. 3.4.5 Condenser Cooling Water System Circulating water is drawn into the crib house intake flume at 64,000 gpm by two pumps located in separate open suction bays. Each pump discharges into a 42-inch pipe. The pipes join a common 60-inch pipe leading to the main. I condenser in the turbine building. At the condenser, the 60-inch pipe branches into two 42-inch pipes feeding the top section of the divided water boxes. The main condenser is a two-pass divided water box type. Circulating water enters the top section of the condenser tube side and is discharged from the bottom sec-tion tube side. The 42-inch condenser circulating water lines again join in a common 60-inch line to the seal well, which is on the river bank,200 feet downstream of the intake flume. This location insures that discharge water will not be drawn O into the intake flume and be recirculated through the ' condenser. 3 - 27
O 3.4.6 Water Collection and Disposal The main condenser cooling water is returned directly to the rivet. The remainder of the water wastes are disposed of as follows. Low level liquid wastes are collected, discharged on a batch basis through a radiation monitor to the main condenser circulating water system. If necessary, a radwaste ion exchange unit is available to reduce the radio-activity levelin low conductivity liquid wastes. The liquid con be transferred to the main condenser hot well for reuse or is discharged through a radiation moni-tot directly to the river after being diluted with main condenser circulating water. High solids-content wastes can be concentrated by evaporation, if neces-sary. These concentrated liquid wastes are then packaged by mixing them with cement and absorbent in drums, and allowing the contents to solidify. The pack-aged waste is then shipped off-site for final disposal. ; Depleted ion exchange resins are sluiced into a spent resin tank in the waste treatment building. The resins may be stored for decay, immediately mixed in concrete within drums to form a solid package for final disposal, or placed di- I rectly in shipping casks for off-site disposal. The system is designed to operate in a batch manner. The radioactive wastes are maintained as distinct batches throughout treatment between individ-ual samplings and operations. The details of the liquid radwaste system are pre-sented in Section 3.6.2. Liquid waste sources and quantities are presented in J Table 3.4-2. l O l i 3 - 28 ; i
I l i O-Table 3.4-2: Liquid Waste Sources 1 Source Maximum (gal / day) Average gal / day ~ J Reactor building . ( Floor drains and sump 1,000 300 l J Process drains 12,000 '730 Turbine building Floor drains and sump 1,000 133 j Process drains 3,000 300 l Regenerant solution 4,500 400 i l Hot change room drains 150 --- l 1 1 1 1 3 - 29 ,
O 3.5 HEAT DISSIPATION Cooling water for the main condenser of the plant is withdrawn from the Mississippi River through the intake structure shown in Figure 3.5-1. The 1965 i 1 maximum high water elevation of 638.5 feet and the flat pool elevation of 620 ' feet are shown in relation to the intake and crib house structures. Two 32,000 gpm circulating water pumps, located in separate suction boys in the crib house, supply water to the condenser. The intake water velocity at 64,000 gpm is 0.670 feet per second. Bar grilles and traveling screens are located in the crib house upstream of the circulating water pumps. The screen baskets are Number 10 W and M, galvanized square open mesh. Each screen is equipped with high-pressure water spray nozzles which wash debris from the baskets and into a trough which discharges downstream of the intake flume. I 8 The surface condenser is rated at 4.23 x 10 Btu /hr for a flow rate of 64,000 gpm at a 60 F inlet temperature. The operating ATis 15'F. The sea-sonal temperature variation of the river is approximately 32* F to 80*F. The condenser transit time is 12 seconds. The discharge line from the LACBWR condenser joins the discharge from l the Genoa 3 plant in the structure shown in Figure 3.5-2. The Genoa 3 line is the 90-inch pipe and the LACBWR line is the 60-inch pipe. The two circulating water pumps of Genoa 3 are each rated at 95,000 gpm as contrasted with the 32,000 gpm rating of the LACBWR pumps. Hence, during operation, the combined discharge can vary from 32,000 gpm with one LACBWR pump on line to a maximum of 254,000 gpm. Even at this flow rate, the combined discharge is a small frac-tion of even the lowest river flow rate (see Table 2.5-2). Use of a common dis-charge for the two plants has the advantage of reducing the probability of ther-mal shock to biota in the river during refueling or shutdown. The total transit time for the LACBWR cooling water from intake to dis-charge is 2.14 minutes. The main condenser circulating water system for the two plants is shown schematically in Figure 3.5-3. The combined discharge enters Thief Slough downstream of the two intakes. A rock closing dam extending O toward the discharge in a northeasterly direction from Island 126 constricts the 3 - 30 l
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4' river ficw as it enters the slough. The resulting current velocity (5 to 10 feet Per second) and water turbulance in the area of the outfallinsure rapid thermal mixing and prevent significant stratification. During a recent study (1) the heated effluent did not raise slough temperatures more than 2 F after mixing. i l l l I l l C 3 - 33
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O REFERENCES
- 1. Hanthum, Richard G., "The Effects of Heated Effluent From the Dairyland j Power Pbnt at Genoa on Water Temperatures and Fish of the Mississippi j River", Wisconsin Department of Natural Resources, Division of Forestry, Wildlife and Recreation, Bureau of Fish Management, Management Report Number 48, September 1,1971. I i
1 l l I J i 1 3 - 35 l
3.6 RADWASTE SYSTEMS The purpose of the radioactive waste handling system is to ensure control-led and safe handling of all radioactivity generated as a : ., ult of plant operation. Wastes are generally classified by form, i.e., gaseous, liquid and solid, and are handled in appropriate subsystems described in the following sections. i I l l l l l i i l 18 1 1 3 - 36
l 9 3.6.1 Gaseous Radwaste System The gaseous radwaste system is designed to: (1) collect and contain radioactive waste gases generated or released in plant components; (2) transport collected waste gases to the stack-release point; ; (3) monitor wasb gas activity before final release to the stack; (4) control the rate of release to the environment; ] (5) store radioactive gases for decay, when necessary, in order to maintain low release levels. Figure 3.6-1 is a schematic diagram of the gaseous radwaste system. Table 3.6-1 summarizes the operating experience to date in terms of released radio-activity. As can be seen from Table 3.6-1, the most recent twelve-month period has had the largest releases of radioactive materials in the plant's history. This is I i as would be expected since the core is reaching the end of its design life. j Table 3.6-2 breaks down the releases during this period by isotope. It can be expected that releases with the second core will be similar to releases with the first. Thus, Table 3.6-2 represents a probable maximum release to be expected in normal operatl.on, and is used to predict dose impacts described in Section 5.2. Waste gas is collected (Figure 3.6-1) from all components that may contain i radioactive gases. A four-inch vent header routes gases from the air ejector vents in the main condenser and the shutdown condenser to the 150-cubic-foot holdup tank. The holdup tank allows decay of short-lived isotopes. i i From the holdup tank the waste gas is rou'ad through dryers and high ef-l ficiency air particulate and charcoal filters to the base of the stack, or, if a mon-l itor downstream of the holdup tank records excessive activity, to the gas storage l tanks. In the latter case, the gases would be drawn from the holdup tank and mixed with steam from a steam ejector, thus reducing the hydrogen concentration l to below the explosive limit. The inlet of the ejector receives steam at 50 - 55 psig. Gases and steam would then flow through a recombiner, where hydrogen p. l Q 3 - 37 E _ a
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C . Table 3.6-1: LACBWR Stack Release Data l l Jan-June July l 1969 1970 1971- 1972 1972 l Total Release (Ci) 483 670 528.88 8873.9 6209 Avg. Yearly Release Rate 15.3 21.2 16.8 561.6 2361 L' ) (pCi/sec) Percentage of Allowable Avg. Yearly Release Rate 0.10% 0.14% 0.11% 3.67% 15.43% Max. 24-Hr. Release Rate Ll61.7 255.8 151.0 3099 .8236 (pCi/sec) O 3 - 39
/
4 I Table 3.6-2: Isotopic Breakdown of Airborne Rsleases (pCi/sec)
~ . . . . - -
Jan-June Ju_r.y Isotope 1969 1970 1971 1972 1972 l Kr-85m 2.5 42.5 153.0, Kr-87 0.72 0.72 0.41 48.5 207.1 Kr-88 0.15 0.15 0.15 45.2 207.8 ' Xe-133 0.13 0.13 0.26 28M 124.4 i Xe-135m 115.8 627.3 Xe-135 0.15 0.13 2.4 161.3 669.6 Xe-137 37.1 108.4 3 Xe-138 0.22 0.22 2.1 85.1 263.5 I-131 Not De- Not De- Not De- i tectable tectable tectable 0.0112 0.0050 Total { Particulate 0.573 2.36 8.72
\ j O
3 - 40
-u-_ a
o and oxygtn in the waste gas are recombined. The hydrogen and oxygen thus removed lessen the storage load of the waste gas system and eliminate the problems of handling combustible gas mixture in a compressed gas system. In the recombiner condenser the steam would be condensed, and the gases are vented to the compressor, where they would be compressed to a minimum of 300 psig and charged to the storage tanks. Af ter sufficient decay, a controlled release of waste ' gas in the storage tanks would be allowed by c remotely operated control Eb. As of August 1,1972, waste gas quantities have been so low that the re-combiner system operation has not been required. The stack is 350 feet high (240 bet higher than any adjacent structure). The two 35,000 cfm stack blowers normally operate together through a common suction header, taking gas from a pknw.m in the base of the stack and discharging it into the stock. Motor operated dampers are in the suction and discharge ducts of the stock blowers. Outside air ehters the stock-blower suction header upstream of the dampers on the suc-tion side of each stack blower. Stock monitors are in the stack, downstream of the outside air line tie-in. Stack exit velocities are maintained at 70 fps. In addition to the main vent lines, other vent headers collect off-gases from the other plant components. A four-inch vent header collects gases from ! Wactor plant equipment in the turbine building. This equipment includes the sluice water storage tank, the condensate demineralized vessels, and the vessels of the resin regeneration system. Two three-inch vent lines from the two waste water storage tanks connect to the four-inch header, which goes directly to the plenum in the base of the stock. Before entering the stock it receives two other vent headers, a three-inch vent header from the containment building equipment and the waste disposal building vent header. The vent header from the waste treatment building collects the gases from ,, the evaporator feed tank, the spent resin tank, the water collection tank and the e' concentrated waste tank. The vent header from the containment building normal-ly collects gases from the purification cooler, the regenerative cooler, the shield
-O cooling and component cooling surge tank, and the retention tanks. It can also I
3 - 41
mm,- ' i' e > {*
< s e ?r. ,
1 j q o < \
, v collect gases from the reactor cavities and the !uel element all, but such gases ;
l normally are routed through another four-inch vent header to the suction side of j the reactor containment exhaust fans. The scate gas vent headers are routed te' j the stock through a tunnel that also serves ayhe vedilation exhaust duct fu [ ,
!h 9 the turbine building and the reactor containment'exhnust fans. l i
Two 1G01 cubic-foot (1h000 gallon) gas storage tanks are in the u.ide j around vault. 'ihis undergrourid vault is connected to the plenum in the basdf
~ l the stock. The waste treatment building exhadt fan di; charges into thn/nder-l ground vou?t through a 20-inch duct. J '(,
The system piping is in two basic groups -- loypressure off gas piping, , and high pressure off-gas piping. The first, group consists of seamless carbon steel piping (ASTM Type 40106, Grade A or B) designed for a maximum working i pressure and temperature ci 30 psig an t 2000F The second group'coIsists of 1
,,~
piping of the same material buLdesh;ned for a maxhaum working phssure and temperature of 300 psig and 250*F. All piping has welded joints (butt-welded for pipe 2.5 inches and larger, ord socket-weided for pipe of 2 inch 3s or smalbr). The piping is designed for maxiuum system pressure, temperati.re and flow coa $- tiora.. All piping that may carry off gas from the main condenser i$ dasigned for . ' j 300 psig and 250 F. Piping tlat rray contain compressed gas at up to $00 psig is also designed for 300 psig and 250*F M1 other viet piping is designed fer ' l 30 psig and 200 F. There is a separate six-inch line from the mechanical vacuum pump to 1 ' stack. The line is sized to trensport air ficks connected with statup ct the main condenser. With both the recombiner and the ges pressurizer in operution, radioactive s gases can be held up for 72 houm Obier' wise, the 150-cubic. foot tank delays gases for a minimum of 10 minutes. The reactor containment' building ventilation system and the waste dhposd ventilation system are equipped with Cadidgpaholute filters (Model1/{-9T-1), each complete with a filter box und geskets. Unit bffici-ncy it dasigned at 10.9% O 3 - 42 a 1 % L__- .
. . .. . . b
7 3: f s,
-O for particles irrger then R3 microns.
There aie radiation mcliitors for the following: (1) the' effluent froa the off-gas system for gaseous activity (2) reacier containment buildirig ventilation fan discharge for particulate
,, and; gaseous activity
? ,
(3) s!cek effluent for particulate and caseous activity. Items 1 '2 and 3 are recorded in the control room. High radiation alarms
, f are in the control room for all three items.
l I Two particulate monitors and a gaseous monitor in the reactor building ventilation e,:ibcust line, just upstream of the exhaust fan, produce signals to close the afrioperated ventilation systere dampers in the event of excessive par- ; ticulate ar gaseous activity. These dan.pys will also close automatically if l there is high vapor containment pressure or high reactor pressure. The four-inch t vent header from the containment building contains a diaphragm on-off-type con-
, trol valve, opeiuted by instrument air, which is also closed by redundant signals to separate p9ct solenoid valves in the event of high reactor or containment -
b/ilding pressure. Isolation of the coriainment building atmosphere is thus as-sured L
)
I.m 1 3-.13 i- , y ;. f7..- J
i i j 1 O- , 3.6.2 Liquid Radwaste System The functions of the liquid radweste collection and treatment system are: ) (1) to collect and store radioactive liquid waste and resins generated i in the plant during operation, and 1 1 (2) to process the collected waste as required for safe and economical disposal. , Figure 3.6-2 is a simplified diagram of the liquid radwaste system. Table -) i l 3.6-3 summarizes the operating release experience to date and Table 3.6-4 gives - an isotopic breakdown of the releases during the same operating period. As of August 1,1972, the highest releases during the life of the plant were recorded during July of 1972 and they are representative of the maximum releases to be expected from the second core. Consequently, these releases are used in the l radiological dose assessments presented in Section 5. l The liquid waste generated within the reactor building is collected and stored in two 6000-gallon retention tanks located in the reactor building. The liquid waste from the turbine building, the waste treatment building, the waste gas storage vault and the tunnel area is collected in two storage tanks - one of 4500 gallons and the other of 3000 gallons -located in the tunnel between the reactor building and the turbine building. The liquid wastes are recirculated in the storage tanks to obtain a homogeneous mixture and then sampled. The sample is analyzed, and the waste is either transferred to the waste treatment building for processing when necessary or discharged through the liquid waste ! and service water radiation monitor to the main condenser circulating water dis-charge line. In the condenser water discharge, the waste is diluted, monitored again for radioactivity by the turbine condenser circulating water radiation moni-4 tor, and then discharged to the river. 1 1 The system is designed to operate in a batch manner. The radioactive wastes are maintained as distinct batches throughout treatment between individ-l ual samplings and operations. All waste tanks are sampled and analyzed prior to any discharge. If radio- l O 1 3 - 44 j i 1 f w____-___-___---___-----_------------------------------------ . _ _ _ _ __. _----_-a
O i
, WASTE TREATMENT GAS STORAGE TURBINE BLOG. l BLOG. VAULT l SUMP DOMESTIC DRAINS SUMP S b M'S lfRAtNS l l MISC. DRAINS l 1 l pgk#[pgikg _l q l l I 1
I
' WASTE ,
TREATMENT j FACILITIES i, " HOLDING I I TANK l i i r j I 3'r s . l C C C TUNNEL AREA m> b A n
- +
3 SUMP g i l s i 4500 GAL. I jg , , 3000 GAL. l[ b ~ h i. REACTOR BLOG. l ALL DRAINS i , 2 l8 SUMPS l 8 3 SAMPLING 8 VALVE . 6000 GAL. 6000 GAL, o _ l o -
=o j
__ _ _ . __ q l 4, MONITOR j
; 4 i ,
i, 1 TURBINE yan,,oa ~ O GONDENSER 1 u I I l l RIVER RIVER 1 1 O FIG.3.6-2 LAC 8WR REACTOR PLANT LIQUID WA$TE FLOW DIAGRAM i 3 - 45
j 1 0: Table 3.6-3: LACBWR Liquid Waste Batch Release Data Jan-June July 1969 1970 1971 1972 c1972 Waste Water (gal. x 10 5) 11.0 6.34 10.13- 3.88 .964 Dilution Water (gal. x-1010) 6.78 8.49 9.'20 3.96 .649 Gross B,7 Activity Released excluding Tritium (C1) 8.52 6.41 17.065 15.02 12.02 Volume Avg. Conc. at Outfall (pCd/cc x 10-8) 3.36 1.99 5.31 10.08 48.9 Percentage of RCG 0.11% 0.07% 0.18% 0.33% 1.60% pie x b~) 34.7 101 145 541 188 Tritium Released (Ci) 24.8 19.8- 91.44 58.99~ 12.296 Volume Avg. Conc. at Outfall(pCi/cc x 10-8) 9.66 6.16 24.96 39.62 50.02 l Percentage of RCG 0.003% 0.002% 0.008% 0.013% 0.016% l O 3 - 46
I l 1 () 1 1 Table 3.6-4: Average Concentration of Radionuclides I Discharged to the Mississippi River l 1 (pCi/ml) Jan-June July Isotope 1969 1970 1971 1972 1972 ) Na 24 4.40(-11) Cr 51 0.131(-11)* 0.78(-12) 6.51(-11) 3. 7 8 (-9) 1. 3 7 (- 8) Mn 52 4.74(-11) Mn 54 0.360(-11) 2.13(-11) 6.29(-11) 9.13 (-10) 1.47 (-9) Co 56 7.76(-11) Co 57 3.58(-10) 4.89(-10) Co 58 1. 20 (- 8) 0.71 (- 8) 1. 24 (-8) 5. 06 (-8) 3. 37 (-7) , Co 60 0.642(-10) 0.38(-10) 7.80(-10) 5. 99 (-9) 1.17 (-8) i Fe 59 6.40(-10) 1. 71(- 9) Cu 64 7.10 (- 9) Zn 65 {; 0.454(-11) 0.268(-12) 9.19 (-11) 1. 24 (-9) 3. 67 (- 9) Y 88 5.74(-11) { Zr 88 1.03(-10) 6r 95 5.60(-10) Nb 95 4.91(-10) Nb 95m 1.70(-10) Mo 99 7.81(-10) Te 99m 9.53(-11) j Sb 122 3. 06 (-9) Sb 124 2.74 (-10) l Sb 125 6.31(-10) Sb 126 1.00(-10) Sn 125 3. 38 (-9) I 131 1.19 (-8) 2. 59 (- 8) I 132 1.27 (-10) Te 132 2.28(-10) Cs 134 1. 06 (-9) 3.18 (-8) Cs 137 2.12 (- 9) 5. 3 8 (- 8) Ba 140 1. 09 (-9) La 140 1.27 (-10) 2. 93 (- 9) Hf 181 2.33(-10)
- The figures in parentheses denote exponentiation, e.g. 0.131(-11) =
l 0.131x10-ll l O l 3 - 47
l O ; activity. levels are high, the waste can be passed to the evaporator for treatmer.t. Otherwise, it would be released. All release lines to the discharge canal have monitors which would alarm the control room if an unanticipated release were to occur at levels of 10 times the maximum permissible concentration levels specified in 10CFR20. A backup monitor checks radioactivity in the discharge line to the river. l { l 1
)
l l l I O l \ 3 - 48 i
O 3.6.3 Solid Waste Disposal Reu.s and ' :om the primary purification system and the rodwaste ion exchanger are the maior sources of solid wastes. Resins are sluiced to the 1000 gallon spent-resin tank and packaged in drums for shipment to an authorized dis-posal site. Contaminated solid wastes are also packaged in drums for off-site disposal and temporarily stored on-site in a dry-storage pit. A cement mixer and "ansfer pump are used for packaging the solid wastes. The drumming opercun precludes direct contact between the operaior and the concentrated waste piping. The basic container is a 55 gallon drum. Normally, l the ligtad waste is mixed with cement and absorbent within the entire 55 gallon drum. However, if the radiation level of the liquid waste is above what the cement i l self-shielding can keep within 10CFR20 limits, shielding cement is poured into an I annulus formed by a 35 gallon drum within the 55 gallon drum. Empty drums are stored in an outside storage fucility. The ground floor of the waste treatment building is kept free of cement and sawdust. l The drum, containing dry cement and absorbent, is lowered from the ground floor through a hatch into the basement and onto a dolly within a concrete-block box immediately below the hatch. The hatch is approximately 13 feet inside the double doors of the east corner. The concrete-block box is high enough to contain any splashing during filling and mixing of waste. A monorail chain hoist over-head of the ground floor is used for handling the drums, which weigh 650 pounds filled. l The drum is clamped in position on the dolly by a screw jack that has a handle extension through the concrete-block bo::. The dolly is positioned beneath , the mixer with the jack handle, and the dry cement and absorbent are mixed with the drilling machine. After the dry cement mixture is homogeneous, the evaporator residue is either drained into the drum or pumped intc, the drum from the concentrated-waste storage tank. The pipeline that carries the evaporator residue to the drum is heated and shielded where exposed to operating personnel. A manually-operated, quick-O 3 - 49
i l
.o ;
i closing volve with an extended handle is at the end of the tubing that opens into l' the drum. When cement has been mixed with radioactive liquid waste, the barrelis lifted I frem the box to the grade level floor, where it stands until the cement sets. 1 After final checks of activity and labeling, the top of the barrelis sealed in place. The capped barrelis then removed for outside storage in a controlled area. Resins whose ion exchange capacity has been depleted are sluiced to the I spent resin tank from the radwaste ion exchanger, the primary purification system cation exchanger and the primary purification system mixed-bed ion exchanger. Condensate demineralized resin that is fouled or otherwise not regenerable is also sluited to the spent-resin tank. The spent resin storage tank is sized to accept one complete condensate de-mineralized charge of resin and its accompanying sluice water. The resins can be stored in the tank for short-lived decay. The spent resin tank has an overflow which drains to the waste treatment l building sump. The spent resin tank outlet to this line is protected with a fine screen to retain the resin in the tank if excessive sluice water is added and over- -j flows. The overflow line has a loop sealin the normally dry pipe run. The loop has a level switch and alarm. If sluice water overflows the spent resin tank, the level rises in the loop seal, triggers the level switch and activates alarms locally l and on the condensate demineralization system control board. The spent-resin tank has sufficient sluice water to carry out the contained resin. The tank is pressurized with plant air and the resin is discharged to drums ! or a shielded shipping container. Drumming is controlled in accordance with spent resin activity level, i Low-level solid radioactive wastes were shipped from the LACBWR site in October,1970, and May,1972. Approximately 100 drums are shipped at a time in a sole-use vehicle according to Department of Transportation (DOT) regulations I for such shipments. These wastes are handled under a contract with the Nuclear 1 O i 3 - 50
9 i .O ! l Engineering Company and are buried in an AEC-approved site in Sheffield, Illinois. 1 Spent resins were shipped for the first time in January of 1969 and in the I spring of 1972. The shipments consisted of about 100 cubic feet of resin. Again, the shipment was made according to DOT regulations via a sole-use vehicle for burialin the AEC-approved site in Moorehead, Kentucky. 3 i i 1 l I I i l 1 i l 1 i 1 i l 1 I i 1
)
i O 3 - 51
.I i
O 2 1
3.7 DESCRIPTION
OF CHEMICAL AND SANITARY DISCHARGE TO THE RIVER I The discharge to the river comes primarily from two sources, the plant cooling water and demineralized regeneration backwash. Table 3.7-1 shows the water quality parameters of the untreated intake cooling water and the discharged cooling water after it has passed through the condenser. No chlorine is used in the LACBWR cooling water system and therefore none is discharged to the river. Table 3.7-2 details the demineralized regeneration cycle while Table 3.7-3 de-scribes the demineralizers regeneration discharge. .i I l l 4 1 O 3 - 52 1
l l O : 3.7.1 Other Discharges Chromium salts in the forms of MgCr04 , Kfrt 7O and NatCr04.are used as i l rust inhibitors in the forced-circulating-pump cooling system, the component ; l cooling system, the shield cooling system and the plant heating boiler. j The cooling water for the forced-circulating-pump cooling system is not dis- I charged to the river, except on occasions when the system is drained for mainte-nonce. During 1971,25 pounds of MgCr04 were discharged to the river. In the past, the component cooling system contained 30 pounds of N2 Cr09 . This system is rarely drained and loss to the river was due to slow leakage.
]
The shield cooling system utilizes K Cr 0 at 800 ppm as Cr. Discharge 7 77 to the river from this system during 1971 was 2.6 pounds. The loss was due to draining as there is little or no leakage in the system. During 1971,100 pounds of Na Cr0 pwos discharged to the river from the 2 heating boiler. The use of N 2Cr0 has 4 now been discontinued in this system to prevent such discharge. 3.7.2 Sanitary Waste Discharge i No sanitary wastes are discharged to the river. All of the waste from toilets are discharged to underground septic tanks located on the plant property. All water from the emergency showers is directed to the liquid radwaste system (see Section 3.6 and 3.4). Plant shower discharges are drained into the septic system. 3.8 OTHER WASTES The nonradioactive solid wastes from LACBWR may be classified as com- ; bustible and noncombustible. Roughly one cubic foot of combustibles are burned each day in an on-site incinerator. The noncombustibles are buried on-site in the lagoon for the Genoa 3 plant. 4 O 3 - 53
-O Table 3.7-1: Intake and Discharge Water Quality Intake Discharge Untreated for Cooling . Discharge ! Parameter- mg/1? mg/l Alkalinity 142 133 B0D 2 3 C0D 7 14 Total Solids 225 280 Total Dissolved Solids 220 250 Total Suspended Solids 34 30 Total Volatile Solids 100 80 Ammonia (as N) 0.10 0.10 Kjeldahl Nitrogen 1.0 1.10 Nitrate (as N) 1.24 1.1 1 Phosphorous (as P) 0.20 0.21 Turbidity 7* 7* Organic Nitrogen 0.9 1.0 Sulfate 14. 12. Sulfite 5.0 5.0 Chloride 10 7 Chromium 0.05 0.05 Potassium, total 2.30 2.90 Sodium, total 7 13 Zinc, total 0.10 0.05 Phenols 0.001 0.001 Surfactants 0.05 0.05 O
- Jackson Units 1 3 - 54
I I LO - 4
-j Ll Table ~3.7-2: The Demineralized Regeneration Cycle ,
.I
)
Flow Time ' Step (gpm) (Min). Total Gallons Cation Backwash (H2O) 28 16 448 Acid Injectionf (H S0y) 2 25 37 925 Rinse (H 2O) 25 10 250-Rinse (H 2O) 40 30 1200
. Anion Backwash (H2O) 11 10 110
.J Caustic Injection (Na OH) 3' 75 225
.l Anion Rinse (H 2O) 3 60 180 l I
1 Total - 238 3338 i 1 1 i j O i 3-55 l 4
O. i Table 3.7- 3: . Description of Demineralizers Regeneration Discharge -] 1 l ;- Parameters ' Maximum Concentration l , mg/l' { l Alkalinity 133 C.O.D. 37. Total Solids 4335 4480. d Total Dissolved Solids
' Total Suspended Solids <5 Total Volatile Solids 3670 .,
~'
Ammonia -(as N) .25 Kjeldahl Nitrogen .40
. Nitrate (as N) ' 4. .05 j Phosphorus, Total- (as P) 4. 1 )
Turbidity 1* i
' Acidity . (as Caco 3) 330 Total Organic Carbon 8.0 J Total Hardness 559. j Organic Nitrogen .2 '3 Sulfate 1250.
Sulfate 4, 2 Chloride 7 Calcium, Total 150. Chromium, Total 4.0.05 Magnesium, Total 46 l Potassium,. Total 1.9 .; 12. l Sodium, Total Zinc, Total 0.10 Phenols 4, 0.001 Surfactants <,0.05
- Jackson Units ;
i O 3-56 i
O 4.0 ENVIRONMENTAL EFFECTS OF SITE PREPARATION AND PLANT CONSTRUCTION - Since the LACBWR is complete and in operation, this section is limited to a brief review of the effects of site preparation and plant construction. No construction or site restoration activities remain to be performed. 4.1 CONSTRUCTION PERIODS AND MANPOWER Site preparation for the LACBWR began in 1961. Dredging and filling opera-tions were completed in December 1965 with the site raised to an elevation of 639 feet above MSL The plant was completed and achieved criticality for the first time on July 11,1967, and full power was first attained in August 1969. The LACBWR was declared commercially available on February 1,1971 Genoa 3, although planned and constructed after the LACBWR, began commer-cial operation on June 17,1969. The maximum number of construction personnel on the site was approximately 400 during the peak period of construction activity for LACBWR in January and February 1966. I I O 4-1 1
O 4.2 EFFECTS ON HUMAN ACTIVITY Site preparation and construction did not impair navigation by commercial river traffic. The main channel to Lock No. 8 was to the west of the dredge and fill area, so that there was no interference with passage of vessels. Flood con-trol precautions to protect the LACBWR site were not necessary because the 639 MSL elevation of the filled area is well above high water level for the Mississippi ! River. As a result of plant construction, about 1500 feet of river bank were re-moved from public use. To compensate for use of lowlands for construction of the LACBWR and Genoa 3, Dairyland Power constructed a river access site downriver from the nu-clear plant (Figure 4.2-1). A boat-launching facility and a public parking lot I were established. Provision of the public area affords sportsmen easier entry to l the preferred fishing area immediately below the dom. in effect, increased utili- i zation of the fishery has occurred because of improved river access by the public. The LACBWR is visible to persons traveling on Route 35 for about 4 miles from the north and for about 3 miles from the south. The Dairyland Genoa 3 plant was completed in 1969. Transmission lines t from the LACBWR were connected to existing lines from Genoa 3 and no addi-tional transmission line rights-of-way were required for the LACBWR (Figure j 3.2-1 ). i i l 1 l l i O i 4 -- 2 1 3
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~ . . . . . . . - . . . - - . . . . . . . . . .- . . - . . . . . - . . - . . . . . . . . . - . . IO 4.3 EFFECTS ON TERRESTRIAL VEGETATION AND WILDLIFE i i Prior to site preparation, the crea on which the LACBWR was built con-i sisted of lowland hardwood forest interspersed with pond-type habitats (Figure 2.7-2). The low area was filled with dredge material taken from the Mississippi .] River off the construction site. Approximately 26.8 acres of lowland and water ) 1 area were filled to an elevation of 639 feet above MSL, using 600,000 cubic yards j of fill material. The fill operation entailed no major loss of wildlife nesting or. breeding areas, and no known rare or endangered species of flora or fauna were affected. Prior to filling, waterfowl production in the lowland was insignificant. ] Ponds in the hardwood forest were subjected to fluctuating water levels which ) precluded successful nesting of aquatic birds. In addition, as a wildlife habitat, I the site was atypical because of the presence of Genoa 1, a 14 MWe steam unit owned by Dairyland Power Cooperative, the proximity of the Lock and Dam No. 8,
.l with its high level of human activity, and the continual disturbance of the area by fishermen as they traversed the zone to gain access to the riverbank.
4.4 EFFECTS ON ADJACENT WATERS AND AQUATIC LIFE ] The ponds in the forested area that were filled, and the portions of the ! riverbed disturbed by dredge and fill operations are not known to have been spawn-ing or rearing areas important for maintenance of normal fish populations. The temporary destruction of aquatic habitat associated with dredging resulted in lo- l calized damage to benthic organisms in the dredged area. However, damage was l i transitory. It has been established by aquatic ecologists that bottom-dwelling l l biota recover quickly once environmental stresses terminate. Dredging of the- i river temporarily disturbed some localized fish spawning and feeding areas and ' increased turbidity of the water immediately downriver from the dredge zone. Construction of the LACBWR intake and discharge structures did not im-pose unusual environmental stresses on the aquatic ecosystem. Vertical traveling I screens are set back in the cooling water intake and the mouth of the discharge ! O C n I W S Pl aced flush with the edge of the site. Extensive disturbance of the I river bottom was not required. I 4-4
I D. 5.0 ENVIRONMENTAL EFFECTS OF PLANT OPERATION This section describes the environmentalimpacts resulting from' the opera-
. tion of the LACBWFL The principal sources of impact are the heat released by '
the plant's cooling water system, radioactive releases and chemical wastes. Other effects (Section 5.4) include those of noise, th'e transport'otion of radioac-tive materials, and the creation of nonradioactive solid wastes. ' Also covered in
.Section 5.4 ore the effects of the physical presence of the plant. Discharges from ' the LACBWR meet applicable State of Wisconsin water quality and radiation . standards as discussed in Sections 5.1,5.2 and 5.3.
l l 1 T i l O i 5-1 l
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O 5.1 EFFECTS OF RELEASED HEAT The heated water enters the Mississippi River as a surface discharge via the outlet cimmon with Genoa 3 (Figure 5.5-3) and flows into Thief Slough (Figure
~ 5.1-1). The cooling water from the LACBWR is discharged at the rate of 71 or 142 cfs depending on whether one or two pumps are in operation. The AT of the effluent at full power compared to temperatures of intake water, ranges from 11 to 33*F, with higher temperatures for winter months resulting from recirculation of discharge water to de-ice the intake structure. Temperature profiles were measured -
by personnel of the Wisconsin Department of Natural Resources (DNR). (1) l Downstream themal patterns resulting from the cooling water effluents were designated as Zones A, B and C in the DNR study (Figure 5.1-1A). Zone A was delineated as extending from a point 100 feet above the discharge to a point 500 feet below it. The closing dam and its mouth served as the western boundary of l Zone A. The turbulence caused by the dam, as well as river velocities of 5 to 10 ) fps, promote rapid mixing of the heated water in Zone A and prevent stratification. 1 Zone B was the remaining part of Thief Slough, a distance of one mile. With the LACBWR operating alone or in combination with Genoa 3, temperatures in Zone B were not elevated by more than 2 F. Water temperatures in Zone C, I l the zone below in which the waters from Thief Slough and the main river channel ' combine, also were not elevated more than 2*F above ambient when either the ' LACBWR or Genoa 3, or both plants, were in operation. In Zone C, tenmeratures ranged from 1 to 2 F above ambient on the Wiscon-sin side of the river and at times contacted the edge of Twin Island, which is one mile below the plant and within the boundary of Minnesota. No heated effluent is i detectable beyond the mouth of the Bad Axe River, a distance of 4.5 river miles below the LACBWR. This is attributable to increased dilution with water from the main channel and heat loss to the atmosphere. ; Section 3-a-1 of Water Quality Standards for Wisconsin (effective date Sep-tember 1,1968) applies to surface waters where fish reproduction is of primary importance. For waters of this type, temperatures are not to exceed 84 F, and O 5-2 ' 1 t _ _ _____________ _ . _ _ _ _ _ _ _ . _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ >
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O- e Location OF RYAN RECORDING THERMOORAPHS MILES
--- WATER TEMPERATURE ZONE BOUNDARIES FIG.5.1-IA WATER TEMPERATURE ZONES IN DEPARTMENT OF NATURAL RESOURCES STUDY 5-3A
_ _ _ - _ _ . _ = -
LO temperatures are not to exceed ambient temperature by more than 5*F outside a
" zone of mixing". Section 3-b-1 of the standards, applicable to surface waters where fishing is desirable in conjunction with other uses, stipulates that temper-atures'shall not exceed 90 F and temperatures outside the zone of mixing also shall not be elevated in excess of 5 F.
The waters of the Mississippi River in the Genoa crea have been classified by Wisconsin DNR water quality personnel as an interstate water. (2) Assuming that the mixing zone is defined as Thief Slough to the lower end of Island 126, the combined discharge from the LACBWR and Genoa 3 is well within even the more stringent standard. The discharge has no significant effect on Minnesota waters. The closest point at which the discharge water might mix with Minnesota waters is more than a mile below the plant. At that point, the water temperature muld not exceed the ambient by more than 2* F. Moreover, there would almost certainly be additional dilution and cooling of the water before it actually reached the Minnesota bound-ary. Thus, there would be no significant effect on Minnesota waters. Heated water does not contact important waterfowl nesting or marsh areas _j l on either side of the river. The heated effluent is not detectable in the Iowa section of the Mississippi River during the warm months. In winter,it elevates the temperature sufficiently to keep the river ice-free for some distance below the Iowa boundary,4.5 miles 1 south of the plant. However, an increase of a fraction of a degree above freezing is sufficient to prevent the formation of ice. As a result of thermal studies downstream of the Genoa site and of related public hearings, Wisconsin state thermal reporting requirements for the Genoa L complex are limited to intake and discharge temperatures. l In conjunction with temperature studies, the influences of heated effluents on fish species composition and relative abundance in Zone A were evaluated ; l monthly from August,1969, through March,1970, by DNR biologists. (i) Data on samples which were obtained by electrofishing are presented in Table 5.1-1. The Q greatest number of fish (468 speciments) were taken during the period of warmest l 5-4 I 1
1
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o j water temperature in August and September. Only 17 fish were collected in mid and late winter, which may reflect the difficulty of winter sampling rather than l actual fish population densities. 1 The following sport fish species collected are ranked according to per cent ) by number of the total catch: walleye (19%), white bass (13%), souger (11%), bluegill (10%), black crappie (6%) and largemouth bass (2%). The most common l ' nonsport fish were corp (12%), gizzard shed (8%), mooneye (6%), northern red-horse (4%) and freshwater drum (4%). Walleye and souger were collected most frequently in spring and fall samples; white bass, bluegill, black croppie and i f largemouth bass were most common in summer. Relative numbers of sport and q 1 nonsport fish in the catch were comparable to samples collected from habitats in the river not subjected to heated effluents. Heated effluents did not promote con-centration or exclusion effects for specific species of fish during any period j when sampling was conducted. After mixing in Zone A, the combined LACBWR and Genoo 3 discharges did not elevate winter temperatures beyond the tolerance limits for fish in the Mi ,issippi River. (1) Biologists familiar with the Genoa area indicate that fishing in the upper portion of Thief Slough has improved for winter months. This is attributed to the heated effluents from the LACBWR and Genoa 3. Plant operations have not ad-versely affected commercial fishing in Pool 9. Records of commercial catches by Wisconsin fisnermen show no decline following start-up of the LACBWR or of ; Genoa 3 in 1967 (Table 5.1-2). Should the LACBWR be shut down for refueling or other purposes, it is highly unlikely that fish residing in Zone A or other areas would be subjected to cold-shock, since a shutdown of Genoa 3 would normally not occur simultaneously and temperatures would not decrease to criticallevels. Concern has been expressed about lethaleffects of the LACBWR on fish eggs and larvae entering Thief Slough with water from the Mississippi River. These forms would be exposed to temperatures in excess of 2 to 6* F above am-bient levels for approximately 30 to 60 seconds, and sometimes less, depending O s-s
O Table: 5.1-1: Zone A Electrofishing Catch Data, Combined Data for Monthly Collections from August 1969 to March 1970 Total Relative Species Total Caught Abundance-Sport Fish Northern Bike 3 0.5. White Bass 72 12.8 Rock Bass 3 0.5 i Warmouth 1 0.2 Pumpkinseed 1 0.2 Bluegill 55 9.8 Smallmouth Bass 7 1.2
]
Largemouth Bass 11 2.0 White Crappie if 0.7 Black Crappie 31f 6.1 i Sauger 59 10.5 Walleye 105 18.8 Total Nwnber of Sport Fish Combined 355 63.0 Nonsport Fish Shovelnose Sturgeon 1 0.2 Longnose Gar 1 0.2 Shortnose Gar 1 0.2 Gizzard Shad 14 3 7.7 Mooneye 35 6.3
' (Continued) 5-6
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Nonsport Fish Total Caught Abundance Carp . 65 11.6 I White Sucker 1 0.2 Bigmouth Buffalo.- 1 0.2 Spotted Sucker 1 0.2 Northern Redhorse 24 4.3 Channel Catfish 4 0.7 Flathead Catfish 2 0.4 Burbot 1 0.2 Trout Ferch 1 0.2 Freshwater Drum 23 4.1 Total Nonsport Fish , 204 37.0 Total Sport and Nonsport Fish 559 l Source: Ranthum (1) i I 4 O 1 i i 1 5.- 7 ] 1 l _..__..__.___.J
O' on river flow conditions and seasonal temperatures. It is highly unlikely that such exposures would have any detectable influence on adult fish populations in adjacent or more distant portions of the Mississippi River. No problem of fish cropping by impingement on the verticalintake screens at the LACBWR has been recorded by Dairyland Power personnel. The intake velocity of 0.67 fps is slow enough to permit larger fish to escape screen impinge-sent. Moreover, the scieen is positioned near the edge of the river, which permits fish to escape more easily than with intake designs involving long intake canals. The LACBWR uses a rather small percentage of river water for cooling pur-poses (Table 5.1-3). In the last ten years, the lowest river flow rate was 6,400 cis. At this rate, with two circulating water pumps operating,2.219% of the total flow I would be utilized by the LACBWR. Entrainment time is approximately 128 sec-onds. Phytoplankton, zooplankton and benthic populations have not been routinely sampled in the LACBWR area. However, in June,1972, Dr. Thomas 0. Claflin, a consultant for Dairyland Power, sampled these organisms on four transects near the power complex. (3) Transect A was approximately 400 feet above Genoa 1 and extended from the Wisconsin to the Minnesota Bank; Transect B was 250 feet below the effluent discharge point, extending from the plant site to the tip of Island 126; Transect C was perpendicular to the public access crea and extended to the eastern edge of Island 126; and Transect D was in the lower end of Thief Slough, bounded by the Wisconsin bank and the eastern edge of Island 126 (Figure 5.1-2). For phytoplankton, Dr. Claflin concluded that there were no extreme dif-ferences among the four transects in species diversity (Table 5.1-4). Ulothrix was the dominant green algae at all stations. Diatoms were represented mainly by Stephanodiscus, Melosira and Asterinella. No large standing crops of undesir-able blue-green algae were found. Inter-transect differences for zooplankton were also not evident (Table 5.1-5). It has been established that algae have inherent species-specific responses to temperature; there is an optimum temperature for growth, survival and reproduc. O 5-8
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l l l O 1 - 3 L Table 5.1-2: Commercial Fish Catch on the Wisconsin Side of the Mississippi River from 1965 thniugh 1970 for Pyols 8 and 9 i
! o ,c Fool #8 Pool #9 t ,
Year Founds Caught $ Value Pound;1_C_au ght, fi j[jl[ue_
- 1965 860,506 53,467 963,711 71;635 l
1966 790,769 56,582 941,070 ,77,231 a
.9
**1967 860,265 67,902 . 998,461 85,955 1968 679,758 >
is ,504 886,595 8.0,868 c 1969 553,622 5 ,35 6' ' 1,009,014 70,667
/
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^
1970 82,504 1,'fB5,637 104,370 l
**LACBWR and Genoa 3 were started in 1967 ,
r Source: Wisconsin Department oI Natural h ources, Fisheries Division, Madison, Wisconsin t >
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Jl l OL I tion. The up;er limit for survival !ur nony species in temperate regions is in the range frem P 9A 113* F, with the dual lethai point being near 111* F. (4) In field ec' aments with phytoplankton sulle'chd to condenser transport under normal piant opercHng ;onditions, photosynthetic rates have commonly increased at plants swhite effluent water temperatures did not exceed ide range from the high eighties to }
)
11e bw ainetiau. 3-Dur.9g perieds of high ambient water temperatures, in the late summer or early fail, efflueat temperatures do exceed this range. Some phytoplankton damage and decrease in photosynthetic votes may occur 'as a result of entrainment. However, the effect of such damage on phytoplankton populations due to entrainment is more j than compensated by the not increase in photosynthetic activity consed by the ther-mal enrichment of the receiving waters. In the immediate'outfall area (Zone A) photosynthetic activity would be enhanced most of the year. Because of the lower l
. volume of flow through Thief Slough if comparison to flow in the main river channel, it is unlikely that measurement of phytoplankton parerreters aboie the intake zone i and below Zone B would reveal demonst:able adverse differences. Also, based on l
r?sulte of studierconducted at power plants on th Ohie River (5) where heated 7 affluents are released, obnoxious blooms of'undesdoble algae groups are not ex-pected to occur. No inter-trensect differences in species composition or abundance for zoo-plankton were found by Dr. Claflin Zoopiqukton population densities rarige from 0.2 to 16.3 organisms per liter ; of wates sieved through a #20-mesh net. Eucyclops agilis, a copepod, was the most common form. Biomass, expressed as milligrams of dry weight per liter of phyto- , plankton and zooplanuon combined, ranged from 4.025 to 5.392. Because of the complexity of life cycles with variable temperature tolerances, q zooplan'tton could seasonally experience high mortality rates resulting from entrain- ! heut at the l> C5Wfd However, lecause less thanL2.5% of the total ficw from the Missithippi River is nornully used for cooling purposes by the LACBWR (Table 5.1-3), sven u 10U'% mortility sote of entrained zooplankton would have no overall O odverse effects on densities of adult populations of fish or invertebrates in areas t
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BENTHIC AND PLANK r0N SAMPLING STATION , FIG. 5.1 - 2 LOC ATIONS OF AQ U ATIC SAMPLING TRANSECTS 5 - 11 m._---.-_-_-----_____---_-_-__________.-... . _ - _ _ . . _ _ _ _ - - _ ._ _ _ - _ _ . _ .
O Table 5.1-3: Use of Mississippi River Water by LACBWR, Percentages of Total Flows Based on Total LACBWR Demand of 142 cfs. Max Percent Min Percent 1929-1967 Percent Stream- LACBWR Stream- LACBWR Average LACd%R
-Month flow Use flow Use Streamflow Use October 1969 19,100 0.74 10,800 1.31 17,100 0.83 November 1969 18,800 0,75 12,700 1.12 17,000 0.83 December 1969 18,500 0.77 8,400 1.69 14,000 1.01 January 1970 15,900 0.89 12,000 1.18 12,700 1.01 February 1970 15,700 0.90 11,100 1.28 13,000 1.09 March 1970 22,500 0.63 13,900 1.02 26,000 0.55 April 1970 D1,100 0.23 21,500 0.06 .55,300 0.26 May 1970 63,600 1 0.22 40,200 0.35 43,000 0.33 June 1970 57,000 0.25 24,800 0.57 36,900 0.38 i
July 1970 25,600 0.55 12,000 1.18 27,200 0.52 l August 1970 14,800 0.96 8,000 1,77 17,800 0.80 ' September 1970 15,400 0.92 6,700 2.12 18,000 0.79 I Streamflow data from USGS ' l l O 5-12 ________.--_u_.-- .-
O Table 5.1-4: Occurrence of Phytoplankton Collected Above and Below , the Heated Outfall of the Dairyland Power Cooperative l Complex at Genoa, Wisconsin .) l ORGANISM ORGANISMS / liter LOCATIONS Tran. A Tran. B Tran. C Tran. D Ulothrix nequalis, Kuctz 18,581 35,325 15,65.1 25,t688 Ulothrix variabilis, Kuctz 4,940 7,957 3,803 7,213 ' Scenedesmus quadricauda, (Turp.) de Brebisson (180 524 3t19 568 Scenedesmus dimorphus, (Turp.) Kuetz 568 3t19 262 306 Pediastrum boryanum, (Turp.) Meneghini 262 87tl 306 437-Pediastrum duplex, Meyen 174 131
- Golenkinia radiata, (Chod.) Wille 43 Selenastrum west 11, Smith 306 Tetraedon trigonum, (Nacz.) Hansgirg 131 Pandorina morum (Muell.) Bory (63 Glococystis gigas (Kuetz.) Lagerheim 174 Actinastrum hantzchu, Lagerheim 87 393 43 262 Staurastrum paradoxum, Meyen 87 87 Coelastrum microporum, Naegell 43 14 3 Chlamydomonas sp. 87 87 Ankistrodesmus falcatus (Chod.) Lenin , t63 Anabaena circinalis, Rabenhorst 218 131 87 87 Oscillatoria sancta. (Kuetz.) Gomont 918 612 349 306 Gomphosphaeria lacustris, Lenvn 43 tt3 43 87 l Nodularia spumigena Mertens 393 87 16 3 Marismopedia elegans, Braun 16 3 Dactylococcus fascicularis, Lemm L43 131 Chroococcus minor, (Kuetz.) Naegeli 218 Phormidium retzii, (Ag.) Gomont 17t1 43 131 Microcystis aeruginosa, Kuetz, emend, ;
Elenkin 87 ! Euglena sp. t43 43 Dinobryon sertularia, Ehrenberg 43 : l Navicula sp. 306 218 393 , Synedra delicatissima, W.Sm. 918 393 306 1480 Stephanodiscus astraca, Grun. 5,246 568 1,7t48 3,104 ; frag 111 aria crotonensis, Kitton 480 830 524 1,0t69 - Melouira distans, Kutz. 1,136 7,476 131 480 ' Asterinella formosa, Hass. 4,109 5.333 2,229 3,93t1 {' Asterinella ralfsil, W.Sm. 743 524 87 262 Gyrosigma acuminatum, Rabenhorst 87 l 1 0 5-12A i
O 1 Table 5.1-5: Occurrence of Zooplankton Collected Above and Below the - Ileated Outfall of the Dairyland Power Complex Number of Organisms Organisms Per Liter , l Upstream l Transect Downstream Transects A B C D { Eucyclops agilis 16.3 ltt . 6 16.0 15.2 l Cyclops vernalis 2.2 .3 .1 .7 Diatomus ashlandi .5 .7 .3 . tf l Diaptomus sg .3 . it .1 .2 l l l Daphnia pulex 1.3 1.7 .8 .7 Daplulia longispina 2.0 .9 3.9 1.9 Bosmina longirostris .3 .6 .5 .4 i Biomass * (mg. dry wt./1.) 4.686 5.069 tt.025 5.392
*Phytoplankton and zooplankton combined.
Source: Claflin (3) O 5 - 13 L-___-______-_____________________
R I i 4 O l Tabic 5.1-6: Species and Occurrence of Benthos Collected on Four Transects 1 on the Mississippi River at Genoa, Wisconsin in June 1972 (organisms per square meter) Upstream Transect Downstream Transects A B C D Species 1 l Amphipoda 60 23 63 Hyallella azteca Insecta Tendipedidae J 132 40 21 92 Tendipes plumosus Tendipes tentans 441 159 928 219 l Tendipes sp. , 3 t} lt6 l 267* 536 333 lleleidae l Palpomyia sp. 266 3tl2 Unidentified 76 Cuelicidae Chaeoborus sp. 11 12 ; Plecoptera lti Trichoptera l ifydrosichidae Clematopsyche sp. 3t6
^
Oligochaeta 110 49 201 211 . Total /m 2 1445 627 1698 918 Biomass mg/m2 457. t6 172.2 600.8 19tl . 7 expressed as wet weight
*rirst instar larvae O source: C1arun m 5- 13A
l 1
,1 O
downstream from the plant. Based on the relatively slight temperature differentials between transects, and assuming that these temperatures are representative for all operating condi-tions for the LACBWR and Genoa 3, it is unlikely that heated effluents from the l I LACBWR or Genoa 3 would cause measurable damage to the benthic community, especially outside Zone A. However, more definite conclusions about possible 3 effects of heated effluents on the benthic community could not be made on the 1 basis of the ten samples collected on each transect (Table 5.1-6). Biomass of q benthos expressed as milligrams per square meter (wet weight) ranged from 1 172 to 660. Occurrence, expresseci as number of organisms per square meter, ranged
]
from 627 to 1,445. Bottom types for all transects consisted principally of medium
]
to fine sand, which is an unproductive substrate. Sediment temperatures on Tran- l sects A, B, C and D were 15.6 to 1S.0 C,17.7 to 18.5*C,17.8 to 18.1 C and 17.0 to 18.2 C, respectively. 3 I i l l l l 1 l 1 0 5 -14 __-_-____-__ ____- _ - ~
q o REFERENCES l '. Ranthum, Richard G.,The Effects of Heated Effluent from the Dairyland Power Plant at Genoa on Water Temperatures and Fish of the Mississippi River, Wisconsin Department of Natural Resources, Division of Forestry, Wildlife and Recreation, Bureau of Fish Management, September 1,1971.
- 2. State of Wisconsin, Water Quality Standards for Interstate Waters with a Report on Implementation and Enforcement, Dept. of Resource Develop-ment, Mad .;on, Wisconsin, June,1967.
- 3. Claflin, Thomas O., Untitled report to Dairyland Power Cooperative, June 6,1972.
- 4. Patrick, Ruth, "Some Effects of Temperature on Fresh Water Algae", in Biological Aspects of Thermal Pollution, Vanderbilt Univ. Press, Nashville,1969.
- 5. Anonymous, Effect of Temperature on Aquatic Life in the Ohio River, WAPORA, Inc., G. J. Lauer, Technical Director, Report to the Ohio Electric Utility Institute and other Sponsoring Companies,1971.
i k l \ l l i j O : 5 -15 I f
--- - -- - _ -- - _ -- - - - J
O 5.2 EFFECTS OF RADIOACTIVE RELEASES
' The LACBWR has over 16,000 hours of criticality since 1967. During opera-tion, small quantitit. t ,f mdioactive material are released to the air and water in compliance with the Technical Specifications (Appendix A) in the Provisional Operating Authorization. These materials are a potential source of radiation doses to the general population. The principal exposure pathways by which these doses con occur are shown in Figures 5.2-1 and 5.2-2 for liquid and airborne releases.
They include:
- 1. External exposure to people from radionuclides in water and air, t ad
- 2. Internal exposure to people from the inhalation of air, ingestion of foods and drinking wcter and milk containing radionuclides.
Since man is not the only receptor in the environment, consideration is also given to:
- 1. Exposure of fish and primary producer and consumer species in water, both from radionuclides in water and those internally deposited, and
- 2. Exposure of plants and animals directly from radionuclides discharged to air and from deposition.
l Each of these modes of exposure is considered in detailin the following sections as they apply to the liquid and air-borne radionuclides releases. i o 1 5 - 16 i
O 5.2.1 Liquid Releases 5.2.1.1 Doses to Individuals The liquid releases from LACBWR are summarized in Table 3.6-3 covering the period from 1969 to July 1972. The average concentrations of the radionuclides in water at the outfall, are also shown in Table 3.6-4 for this period. Marked changes in the magnitude and composition of the radioactive effluent were observed in the first six months of 1972. Before this period, the activation products Co-58 and Co-60 accounted for over 90% of the released activity. As of July 1972, their contribution remains significant, constituting approximately 50% of the total. However, other isotopes have become more important from the stand-point of dose. The plant effluent is diluted by mixing with the Genoa 3 discharge and with the waters of Thief Slough. The changes in water temperature downstream from the discharge are indicative of the dilution which occurs in this " mixing zone". Based on measurements performed by the Wisconsin Department of Natural Re-sources (1), the average annual dilution with LACBWR and Genoa 3 in simulta-neous operation is at least 10 at a distance of 500 feet downstream of the dis-charge. The stretch of river in the slough is considered to be a mixing zone. The waters of the slough mix with the main stream of the Mississippi and affect further dilution. The influx of surface waters to the river results in addi-tional dilution downstream. The dilutions expected at various locations down-stream are presented in Table 5.2-1. They are based on the ratio of the average flow rate of the river at the location of interest to the average flow rate from the combined LACBWR and Genoa 3 discharge structure. Individuals engaged in recreational pursuits, such as swimming or boating, could receive direct external exposure from the beta and gamma radiation emitted from the radionuclides in the water. I'or example, an individual spending 200 hours per year swimming, and 400 hours per year fishing in Pool 9 would receive a whole body dose of approximately 0.005 mrem based on the highest concentrations dis-charged from the plant. O 5 - 17
1 .O l l I i AO U ATIC R E LE ASES l l I V POTABLE S U BM ERSION FI S H WATER , j U MAN O FI G. 5.2 - 1: IMPORTANT RADIATION EXPOSURE PATH W AY S FOR LIQUID RELEASES FROM LACBWR 5-18
r._____-_-__ _ __ 0-ATMOSPH ERE . f
- f 1
E INH AL ATIO N PASTURAGE- IMMERSION 1 V DAIRY { ANIM A LS l q l l I U FRESH FLUID MI L.K i 4 V / ; MAN s FIG. 5.2- 2 IMPORTANT R A DI ATION EXPOSURE PATHWAYS FOR ATMOSPHERIC R EL EASES FROM L AC B WR 5-19 i
1 O Table 5.2-1: Dilution Factors for LACBWR Effluents
- i
/
Location Flow Rate (cfs) Dilution Factor ' LACBWR Outfal.1 406 1 l Mississippi River at Pool 9 28,000 69 i McGregor, Iowa 32,310 80 Davenport, Iowa 45,320 112
- dilution factor = flow rate at location flow rate at LACBWR outfall 1 .
l I l l i 1 I O i 5 - 20
O McGregor, Iowa, is 40 miles downstream from the LACBWR. While most of the potable water used is derived from wells, McGregor is the nearest location downstream which 'could use any Mississippi River water for drinking. An adult drinking 2.2 liters per day of water would receive the doses indicated in Table 5.2-2. The doses are provided for the years from 1969 to 1971, and for the first seven months in 1972. The doses given in Table 5.2-2 are estimated from the ratio of the concentra- ! tion of the radionuclides in water to the maximum permissible concentration (MPC) 3 in water recommended by the International Commission on Radiological Protection (ICRP). (2) Exceptions occur in the case of the radioisotopes of iodine and stron-tium, for which the guidelines of the Federal Radiation Council (FRC) are em-played. (3) In either case, these dose estimates are applicable to a hypothetical ; person. Fish and biota exposed to these same concentrations may tend to concentrate ; radionuclides to levels higher than those encountered in the water. Estimates of j dose to man from the consumption of fish require a knowledge of the quantity of radionuclides expected to be present in the edible portions of the fish. The concen-tration factors of Chapman et 91(4) which appear in Table 5.2-3, are assumed to be representative for this purpose. Using the measured releases since 1969, the dosen to the whole body and organs of an individual who eats 20 grams per day of fish that have lived year-round and were caught in Pool 9, are shown in Table 5.2-2. These estimates are all below I mrem per year and are substantiated by measure-ments of radioactivity in fish (Sec. 5.2.4). It is apparent from Table 5.2-2 that the critical path can change during the life of the plant. Prior to 1972, the dose to the gastrointestinal (GI) tract from eating fish containing radiocobalt was lim-iting. The increase during 1972 in the quantity of iodine released has resulted in an estimated dose to the thyroid from drinking water comparable to the GI tract dose from eating fish. O 5 - 21
O .
) ) _
2 2 d ( ( ti 6 5 9 2
)lo 9 dy ur D.
D. 1 4 D. h .AhT N N N 0 0 _ s _ io FN fl ) ) ) oo 1 1 1 o - - - nP .tc ( ( ( o Ia 9 3 3 0 8 im.r 0 4 0 1 3 e g tcGT pr 4 2 4 1 4 mf 0 0 0 0 0 r u a sy na h od ) ) ) ) 4 c 3 4 3 1 - - s C/gle y ( ( ( (
- 0 -
i 1 D 0 od 4 4 1 5 0 1 x - 2 ho 5 0 5 5 9 - (hB 1 9 1 1 4 2 d 6 . i 0 0 0 0 0 u q 0
=
i d ) i 6 6 4 L to . . . 8 0 - lr 1 4 ( h e ) t uy D. dh N N N D. D. 0 0 9 2 t r a AT 6 _ /y r ) ) ) ) ) 0 _ m m e 2 2 2 1 1 - o e t r .t ( ( ( ( ( r r c t g h'ago I. a f (m 1 9 0 7 8 n . e gr eGr T 5 4 e _ 7 6 7 s 7 4 7 1 8 u nG l , e ic 0 0 0 0 0 f n t kM n f o a i e i R r
)
4
)
5
)
4
)
2
)
1 R t a e D e ( ( ( W i ly ( ( B t s od 6 8 4 5 9 C n o ho 5 2 5 8 9 A e D WB 1 9 1 1 3 I n o l 0 0 0 0 0 e p a h x u t e
) ) ) )
d ) 4 4 3 2 n e i l 4 - - - - i t v ae (
- ( ( ( ( o i t s 2 6 6 e n d 9 oo
, #TD 4
2 3 1 3 1 n e 7 5 9 5 i d n d I l 1 0 1 0 0 o s o I e o s
- P g r ) ) ) ) ) e e 4 4 4 3 l 2 n n /y (
( ( ( 2
- b h
t
- iir ( a n 2 th 9 1 5 7 5 t e na 0 6 4 4 4 c r 5 oo0 6 3 7 4 2 e a iB0 t p e t 4 0 0 0 0 0 e a d n l e i b r cgy r ) )~ ) ) ) o a en/
4 4 4 3 2 N s e T Rir ( (\ ( ( (
- r mh 9 1 8 9 1 u m 2 7 6 8 7 . g i0 6 3 7 4 2 i w0 D. F S2 0 0 0 0 0 N
- e n
d u2 2 o O e. r i r ir 9 6 0 7 1 7 J7 n1 9 y9 l1 7 Te 9 9 9 a u P 1 1 1 J J n t[w lIll!!ll
O Table 5.2-3: Bioaccumulation Factors for Radionuclides in Liquid Discharge from the IACBWR Isotope Fish Invert. Plants Cu-64 200 1000 1000 Na-24 31.7 27 159 Cr-51 200 2000 4000 Fe-59 300 3200 5000 Co-58 500 1500 1000 Zn-65 1000 40000 40C0 Co-57 500 1500 1000 Mn-54 25 40000 10000 Co-60 500 1500 1000 I-132 1 25 100 Tc-ggm 1 25 100 La-140 100 1000 10000 Mo-99 100 100 100 ) Te-132 - - - l I-131 1 25 100 l Ba-140 10 200 500 ; i Nb-95 30000 100 1000 Zr-95 100 1000 10000 Cs-134 1000 1000 200 Cs-137 1000 1000 200 i O ; 5 - 23 i 4 I i L __ _- -- _ _ i
O 5.2.1.2 Doses to the Population The pathways of population dose considered are essentially the same as those for the individual. The absence of nearby bathing areas eliminates this particular route from consideration. Based on available data (5), some 5,000 persons used the area of Pool 9 visible from Lock and Dam No. 8, for boating between the hours of 10 AM and 3 PM in 1970. Assuming each person spends 10 hours on the water and is exposed to radiation at the levels resulting from the radionuclides concentrations in the mixing zone, the population exposure is approximately 0.004 man-rem per year. The population dose from drinking water is estimated for Davenport, Iowa some 195 miles downstream from the LACBWR. It is the nearest large population center deriving most of its potable water supply from the Mississippi River. The dose to an individual was calculated assuming a consumption of 2.2 liters per day and using the effluent radionuclides concentrations for the first half of 1972 and the dilution factor in Table 5.2-1. No credit was taken for radioactive decay during travel. The product of individual dose and the 1970 population of 98,500 is the population dose in man-rem. These results are presented in Table 5.2-4. During 1970 there were 1,485,637 pounds of fish taken commercially from Pool 9 (see Section 2.7). Dose estimates were made by assuming these fish were exposed to the average mixing zone concentrations and that all the radionuclides reached the equilibrium values indicated by the concentration factors. Further, assuming that the edible portions are represented by half of the total weight l caught, the doses to the population from eating fish are summarized in Table 5.2-4. O 5 - 24
O 5.2.1.3 Tritium Releases Releases of tritium in liquid effluents are summarized in Table 5.2-5. There are no known biological accumulation processes for tritium which would lead to higher tritium to hydrogen ratios in fish than in water. Hence, drinking water is the critical path for internal exposure. . The whole body Jose to an individual in McGregor, Iowa,from drinking water at the levels of tritium released over the sev-eral years of plant operation are presented in Table 5.2-5. These doses are.triv-l ial and insignificant. t l ( O 5 - 25 \- - -------------_u
O 5.2.1.4 Doses to Biota Fish and primary producer and consumer species living in the vicinity of the discharge will be exposed to the radiation emitted from the radionuclides in water and those internally deposited. The dose to biota residing year round in the mixing j zone would be approximately 1.5 mrad per year as shown in Table 5.2-6 if releases based on the first 6 months of 1972 were characteristic of long term values.
)
Using the radionuclides concentrations in the mixing zone and the concen- 1 l tration factors of Chapman et al (4), the quantity of radionuclides present in biota l can be estimated. The primary producer and consumer species considered range in size from algae to smallinvertebrates. For purposes of dose estimates, the j larger of Chapman's concentration factors for aquatic plants and invertebrates is used. It is further assumed that only beta radiation contributes to this dose be- l cause of the size of the organisms involved. The dose to primary producers and , consumers from internally deposited radionuclides, as shown in Table 5.2-6, is
]
13 mrad per year based on the tabulated 1972 releases. ) Since fish are considerably larger than the phytoplankton and zooplankton ) already considered, they will receive a dose from gamma as well as beta radiation. For a fish of 2 kg mass and flat ellipsoidal shape having the radionuclides uni-formly distributed throughout its mass, approximately 20% of the gamma radiation will be absorbed. (6) The dose to fish from internally deposited radionuclides, i based on the foregoing assumptions is 22 mrad per year. Smaller fish would re-ceive somewhat smaller doses. At dose rates below 1000 mrad per day, there should be no discernible effects on aquatic organisms. (7) Since the largest esti-mated dose is equivalent to only 0.06 mrads per day, no demonstrable radiation effects on biota are expected from the radionuclides released to the river from the LACBWR. O 5 - 26
O Table 5.2 Lf: Doses to the Population From LACBWR Liquid Release in the First Half of 1972 (man-rem /yr) Whole Body Gastrointestinal Thyroid External - Pool No. 9: Fishing (5000 people /yr) 0.386(-2) Internal - Pool No. 9: Eating Fish (20 g/ day) 0.722 5.12 0.913(-1) Internal - Davenport Drinking water 0.130 1.25 13 Natural Background Population within 25 mile radius from the IACBWR 10,750 0 5 - 27
l 5 ) ) i 6 8 t4 r2 . (
- X (
p7 1 0 A9 3 1 1 6
- 1 3 0 5 n .
a 1 0 5 J 3 t
)
ti 8 ) r 1 t. - % 11 e 7 1 ( 8 - t 9 9 6 0 ( a 1 9 0 0 W . . tl 0 5 e 2 t s a W 8 ) ) n 8 t+ i 0 9 - % - 7 1 ( 2 ( s 9 6 0 5 . e 1 1 0 2 n s . . o a 6 0 1 i e t l a e i R t n m 8 ) ) e u 8 t+ n i 9 t4 - % - o t 6 2 ( 3 ( p i 9 6 0 8 x r 1 6 0 8 e T . . 9 0 1 e R t W B a c C i A ) d L e n c i
/i
- s 5 C e
- u s 2 ( ) e r h 5 l y t l / n e a m e l f e r b t r a a u m p T ) O (
i C n C ( t P r i a M o g s e n f e e s o o r r a i G u e t e g c g l a M i e r a F R t t t n n a l e e : a c c e e t n r s t o o e o o T C P D N O wId E
O Table 5.2-6: Dose to Biota in the Mixing Zone (mrad per year) External Internal Fish 1.5 22. Primary Producers and Consumers 1.5 13 O 5 - 29
O Table 5.2-7: Calculated Maximum Hypothetical Individual-Off-Site Dose Due to IACBWR Stack Releases (mrom for the time period considered) Noble Cases Infant dose Time Whole Body Deta Skin Particulate
- Inhalation from drinking milk Period Dose Dose Inhalution of I-131 (nearest pasture) 1969 0.95 0.77 'N. I.** 0*** ' 0 1970 0.95 0.77 N. I. 0 0 1971 0.85 0.57 N. I. 0 0 Jan. '72 0 . 4 16 0.27 3. 0 (-5) 0.03tl 9.11 ****
reb. '72 0.80 0. tt 8 3. 0 (-5) 0.065 18 **** Mar. '72 3. li 2.1 3. 0 (-5) 0.26 70 **** Apr. '72 2.5 1. tl 8.8 ( ti) 0.017 ti.9 **** May '72 3.2 1.8 7.5(ti) 0. 0ti2 12 **** Jun. '72 3.0 1.6 8. 6 ( ii) 0.083 22 Jul. '72 8.8 4.9 0.22 81 Dased on particulate with half lives greater than eight days.
** N.I. - Isotopes not identified.
No detectabic quantities of Iodine were released during this period. l
**** Based on the unrealistic asstoption of cows on pasture during these months.
Notes rigures in parentheses indicate exponentiation, j l l l 1 i
~
O 5 - 30
O Table 5.2-8: Cumulative Population, Annual Gamma Man-Rem and Average Doses from the Gaseous Effluent Released from LACBWR Cumulative Radius Cumulative Dose Average Dose (miles) Population (man-rem) (mrem) 1 144 0.862 (-1) 0.599 2 502 0.309 ( 1) 0.616 (1) 3 674 0.336 ( 1) 0.499 (1) 4 954 0.358 ( 1) 0.375 (1) 5 1,553 0.383 ( 1) 0.247 (1) 10 0,832 0.557 ( 1) 0.815 15 23,609 0.841 ( 1) 0.356 20 88,358 0.165 ( 2) 0.187 25 122,700 0.202 ( 2) 0.165 Note: Figures in parentheses indicate exponetiation, e.g., 0.862 (-1) = 0.862x 10-1 0 5 -30 A
O 5.2.2 Gaseous Releases 5.2.2.1 Doses to Individuals The gaseous releases from the LACBWR are summarized in Table 3.6-1. The isotopic mix and release rates for noble gases,-iodine and particulate are shown in Table 3.6-2. These values have been used for the purpose of estimating dose. The exposure of an individual due to these releases depends on the release rates of the various radionuclides, t! e effective height of the release, and the meso and micrometeorological conditions governing the dispersion of the radionuclides after release. The largest annual average whole body dose to a hypotheticalindi-vidual offsite occurs 2600 feet to the NE of the release point. The whole body-dose to such an individual spending 24 hours per day at this location was calcu-lated to be approximately 22 mrem for the first half of 1972. The dose to the skin of this individual from beta radiation was 13 mrem for the same time period. These values were estimated by means of the ICRP Submersion dose method and the techniques described in Appendix B. Estimates of the doses to an individual from noble gases and other airborne releases are shown in Table 5.2-7 for the period from 1969 to June,1972. An individual would also receive a dose to the thyroid from the inhalation of iodine, and to the whole body from inhaled particulate. For a continous release at at rate of 3.63 x 10 Ci/sec. of I-131, the highest thyroid dose to an adult would be 4.1 mrem per year. The inhalation whole body dose for identified particulate having half-lives in excess of eight days is insignificant in comparison to that - from halogens. A monthly breakdown of inhalation doses is presented in Table 5.2-7. The released iodines can enter the food chain in milk through deposition on pasture and ingestion by grazing cows. The nearest pasture is 2000 feet east of the release point. Assuming a ground level release, the annual overage )'/Q is 0.696 x 10'5 sec/m3. Using the factor of "700" suggested by Burnett (8), the dose to an infant drinking one liter per day of milk from cows grazing at this lo-cation can be calculated. The values presented in Table 5.2-8 are based on the O 5 - 31
, ~
Q i O average monthly release rate. Assuming the releases from January to July are re-preventative of the long term values, u.e annual dose to an infor.d thyroid wo.31d be 338 mrem. Since cows are normally only on pasture from May thru September, a more realistic estimn?o of annual dose to an infant's thyroid from drinking milk is 141 mrem. Further, as is discussed in Section 5.2.4, no iodine has been mea-sured in milk during this period. Thus, the actual dose must be less than this value The dose rates to individuals from particulate radionuclides deposited on surfaces or on leafy vegetables consumed by man are negligible compared to those already discussed. l l l u l .i l 1 s )
'l
- D
,. 1 t .i -
O i
~l 5 - 32: ,,
.a 3 .,
"i 'N
1
'O Table 5.2-9: Environmental TLD Results (mrem /yr) l l
lst Quarter 2nd Quartee 1/1/72 to 4/1/72 to Location 4/1/72 7/5/72 l Control 81.6 97.6 1 110.4 108.8 2 AIR M0NITORING 0NLY 3 173.6 118.4 4 97.6 80 5 109.6 97.6 6 102.4 105.6 7 88 81.6 8 93.6 102.4 9 112 114.4 10 108.8 115.2 l 11 107.2 112.8 12 95.2 123.2 13 102.4 87.2 14 116.8 104.8 15 108 137.6 16 103.2 125.6 17 104.8 132.8 18 Lost 100.8 I 19 108 116 O 20 116.8 88.8 5 - 33
'l .
l
.V > +
l p , .
'p .
- l O' -
5.2.2.2 Doses to the Population , The primary exposure pathways for the gennol population frca the LACBWH gaseous releases are direct exposure from the radionuclides in the plume and from drinking milk. The population distributions within a 5 and 25-mile radius of the site are shown in Figures 2.2-1 and 2.2-2 respectively. Based on observed' meteorological conditions, the annual overage X/Q war col:ulated foithe radius to thp center of = , each consecutive zone. The assumptions fer these calculations are pecen%d in Appendix B. Using the Submersion Dose method suggested by the ICRP, ths.' gamma f dose to an individual was calculated. The product of dose rate and population for. I 1 each zone provides man-rem per year. The cumulative population, annual man-rea j i and average dose to an individual appear in Tcble 5 2-8 for distances from 1 to 25 i 1 miles from the site, j The population dose estimates for the consumption of n. ilk are also based
)
on the annsal average t/Q computed at the center of ecch political sedivision l within a 25-mile radius of the site. The grounJ level' iodine ecccentration was .; determined from the overage release rate, and the amount of iodine in milk deter-mined from the " factor cf 700". Additional factors considered in the estimate are: i
.)
l 1. The fraction of the year (5/12) when cows are normally on pasture, i
- 2. The number of cows per political subdivision within a 25-mile
' i radius from the site, t
- 3. The average milk yield per etw and the fraction consumed as. i l fluid milk, l 4. The population distribution as a function of age, and the milk l
consumption and thyroid mass for the age group relative to the.- consumption of an infant having a thyroid mass of two grams.
- 5. A dose conversion factor in terms of mrem per year per pCi of iodine ingested.
The dose to the population from drinking milk was then estimatM 4 ba 44, e man-rem per year, if it .is assumed that Januaq through July,1972, rehuses of I 131 O cre representative of the long-term overcge. ', ,
,O
.f 5- 34 ,
/
0 '
=
hble S.2-11: Iodine 131 Measured in Milk from Dairies at Genoa and La Crosse (pCi/ liter) I Location und Date .l Locatica nnd Date Location and Date Genoa Genoa Genoa July 1969 4$ July 1970 3.4 July 1971 4.5 August 1969 :s i August 1970 --- August 1971 3.5 Se}tember 1969 6 September 1970 4.9 September 1971 -0.77 October 1509 6 October 1970 c.1 October 1971 15.0 November 1569 8 Novembu 1970 -. November 1971 7.0 December 1909 10 December 1970 3. 8 ' December 1971 8.0 January 1970 3 January 1971 14.9 January 1972 4.0 rebraary 1970 - February 1971 4.9 February 1972 3.3 March 1970 -- March 1971 0.0 March 1972 4.4 l April 1970 2 April 3971 12.0 April 1972 -1.5 May 1970 3 May 1971 14.0 May J972 1,8 June 1970 12 June 1971 3.4 June 1972 6.0 i AVERACE (12-month) 5 AVERAGE (12-month) 6.6 AVERAGE (12-month) 4.H J W I La Crosse La Crosse July 1969 4 July 1970 3.4 August 1969 4 August 1L70 6.3 September 1969 3 Septembc t 1970 4.3 Detober 1969 6 October .1370 3.8 { l November 1969 ! 9 November 1970 4.2 December 1969 3 December 1970 { 4.6 1 January 1970 S January 1971 4.5 February 1970 4 february 1971 2.8 March 1970 3 &.rch 1971 5.4 l April 1970 4 April 1971 5.2 May 1970 8. May 1971 8.5 June 1970 30,0 June 1971 7.2 AVERAGE (12-month) AVERA 7. (12-month) 5.1 l - . - - . . _ l Source: LACUWR Env.irornental Radiation Si cvey Ain'ual Rcports (10) i
- t. -
J f i O l 5 - 35 , t
1 l l f 1 i O 1 5.2.2.3 D'oses to Animals I The dose to an animalin the vicinity of the plant from noble gases would be the same as that to man. The maximum dose to an animal then would not be expect- , ed to exceed the values presented in Table 5.2-8 or 38 mrod per year if the releases . through July 1972 are representative of long term operation.
'I The diet of animals in the plant vicinity may contain radioactive materials as a result of deposition. The iodines are important con +ributors to the dose to man y via the milk chain because of the transfer that occurs in the food chain. Since the concentration of lodine in milk is generally less than that in the cow's thyroid, it is expected that the dose to this organ provides a good estimate of the upper limit of internaliodine dose. The assumptions employed for calculation include dis-tance from the release point to the nearest pasture and the annual average ground level;0'Q, the deposition velocity of iodine,, the area grazed by a cow each day and the fraction of the year spent on posture, the effective half-time of iodine on gross and in cattle, transfer from feed to thyroid and the mass of the cow's thyroid, i The resulting dose based on 1972 iodine release data is approximately 400 mrod per year.
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O 5.2.3 Direct Radiation The operation of the LACBWR results in the accumulations of radwaste and the production of N-16, a short lived radionuclides which emits high energy gamma radiation. Direct radiation exposure from the plant is due primarily to these two sources. An indication of this exposure may be obtained from the TLD readings at the dose assessment locations near the plant. The measurements for 1972 ar' presented in Table 5.2-9 and the locations are shown in Figure 5.2-3. There is no obvious pattern to these exposures attributable to proximity to the plant, and apportionment among the various natural and manmade sources is not possible with this information. In order to assess the direct radiation exposure, a radiation survey was con-ducted on April 25 and 26,1972. During this survey the plant was operating at 50 MWe with an average off-gas release rate of 613 gCi/sec. The rodwaste stor-age held an accumulation of radioactive materials from the previous 18 months of operation. The principalinstrument used for measuring exposure rates was a pressurized ) ionization chamber. A MOSFET electrometer measures the ionization current pro-duced in the detector gas by the gamma radiation. This current is related to the q l exposure rate from cosmic and terrestrial sources. At the plant elevation, the average cosmic exposure rate was 32.8 mR/yr. The total exposure rates measured beyond the exclusion distance varied from a low of 38 mR/yr to a high of 85 mR/yr. Using exposure rates measured at distances beyond the influence of, and in different directions from, the plant, the net exposure rates at the exclusion dis-tance were determined to be in the range of approximately 5 to 20 mR per year. I The background exposure rates measured in the site vicinity in 1968 (see Section 2.8.1) varied from 2 to 10gR per hour or on an annual basis, from roughly 20 to 90 mR per year. These values are in good agreement with the range of 38 to 85 mR/yr measured in 1972. The significance of the net exposure rates attributed to plant operations however, requires statistical verification since they are well , within the observed range of background variation. ! I Q i l 5 - 38 l
O Table 5.2-12: Iodine 131 'in Milk from Neighboring Farms 'in 1972 (pCi/1) Site Number
- Collection Date 16 19 20 June 6 -
< .053 . 023 -
July 14 < 16 < 16 < 16 July 18 < 16 < 16 23 August 1 < 16 < 16 < 16 August 11 -
<l -
August 15 < 16 .<' 16 < 16 August 21 < 10.9 < 10.9 22.4 August 23 <1 < .1 < 1
- See Figure 2.8-1 0
5 - 39
7 O 5.2.4 Environmental Radiation Monitoring The environmental survey program for LACBWR consists of three phases:
- a. Pre-operational
- b. Operational-Investigative
- c. Operational - Surveillance
.The pre-operational phase began in April,1965 and was carried out for three ;
years. This phase is discussed in detailin Section 2.8. The baseline radiological data obtained during this phase were consistent with the results published in Radio-logical Health Data for the corresponding time periods and geographical area. The reactor went critical in 1967 and first produced power in the Dairyland system in 1968. Full power testing and the 28-day warranty run were completed in 1969 and the plant was declared commercial effective February 1,1971. With com-mercial plant operations, two different phases of environmental surveillance are i conducted. The distinction between these phases results from the extent of effort necessary to substantiate initial calculations, as opposed to routine surveillance after confirmation is obtained. Therefore, the operationalinvestigative phase is in-tended to:
- a. Determine the sensitivities to which radiation doses from station effluents can be measured.
)
- b. Substantiate, if possible, the relationship between off-site doses and station releases,
- c. Determine the scope and type of monitoring appropriate to the surveillance phase.
Tne program is graded in terms of plant releases relative to the technical spe-cifications and calculated off-site dose rates. The samples taken, and analyses per-formed, are listed in Table 5.2-10 (pp. 5-45, 5-46, 5-47). The analytical sensitivities and minimum detectable doses are also contained in the table. There are twenty dose assessment locations and seven air monitoring locations, as shown in Figure 2.8-1. A published report (9) summarizes the results of the program through June 30,1971. The annual exposure rates for the second half of 1970 and all of 1971 are summa-O 5 - 40
O rized in Table 2.8-14 and for the first half of 1972,in Table 5.2-9 as calculated from quarterly TLD readings. Particulate air sampling results are presented in Figure 5.2-3 for the locations shown in Figure 2.8-1. The cyclic form of the curve is characteristic of the seasonal variation in activity of naturally occurring radioactive particulate in air. The Wisconsin Department of Health and Social Services samples milk from a dairy in Genoa in '2e plant vicinity and another in La Crosse some 18 miles north. The milk is anal zed f for 1-131. The results of these analyses are presented j in Table 5.2-11 and do not indicate significant differences in iodine levels for milk from the two dairies. (10) Milk is pooled at each of these dairies, from a number of forms covering a large area. Only a fraction of this milk reaches the fluid market ! as whole milk. An evaluation of the contribution of the LACBWR to these levels is difficult from this data. A better assessment of the possible contribution of the . LACBWR to iodine levels in milk is obtained from the routine samples taken from ! the farms nearest the site. The results of sample analyses are presented in Table 5.2-12 and in general, have indicated no detectable iodine activity. Even those samples taken during periods of high release rate and analyzed by a more sensi- ) tive method than routinely used have not had detectable I-131 activity. An infant daily drinking a liter of milk at the detectable limit of 16 pCi/1 would receive 80 mrem per year. Since cows are on pasture only five months per year, this estimate would have to be reduced to 33 mrem per year. At a detection limit of 1 pCi/ liter, t with cows on pasture for five months per year, the dose to an infant would be only ' slightly more than 2 mrem per year. I Samples of river silt were taken from the locations indicated in Figure 5.1-2
)
in May 1972 and analyzed for gross radioactivity. The results shown in Table 5.2-13 do not indicate any build-up of discharged radionuclides in these sediments. Fish were taken above and below Lock and Dam Number 8. The analyses revealed only one fish with detectable levels of radionuclides, specifically Co-58 and Co-60. ., As indicated by the results in Table 5.2-14, this fish was taken from above the dem upstre.m of the plant. Assuming on irdividual received 1/5 of his minimum daily 0 5 - 41 l
O I I Table 5.2-13: Gross Beta-Gamma Activity in Mississippi River Silt Location Concentration (uCi/gm) I i A-1 8. 05 (- 6) l { A-2 6.903(-6) l l A-3 7.806(-6) B-1 2.816(-5) ; 1 B-2 8.073(-6) . i B-3 6.105(-6) C-1 6.977(-6) C-2 5.052(-6) C-3 6.874(-6) D-1 1.565(-5) D-2 6.141(-6) D-3 5.069(-6) ) I ( Note: l'igures in parentheses indicate exponentiation. I I l O 5 - 42 ;
O Table 5.2-14: Radioactivity Measured in Fish Taken from the Mississippi River in the IACBWR Vicinity During 1972 l Collection Isotopic Activity (PCi/ gram of dry flesh) Date Co-58 Co-60 Cs-137 I-131 Pool 8 May 17 #1 < l .1 1 02 .855 1 02 < 011 i . 02
#2 .258 1 007 <.011 1 02 <. 011 i . 02 * !
#3 .601 1 007 < . 011 1 02 <.011 1 02
- q i
August 4 #1 < . 256 1 011 <.2201 011 < . 210 i . 011 < 145 .
#2 .259 1 011 <. 220 1 011 < . 210 i . 011 < .145 l
Pool 9 May 18 #1 < .011 1 02 < . 011 + . 02 <. 011 1 02 *
#2 .708 1 02 .828 1 02 <.011 1 02
- August 7 #1 <.185 1 007 < .180 1 007 .196 1 007 T.12 1 01 l l
- Not analyzed O
5 - 43
O protein requirement, e.g. 50 grams, from fish containing activity at this level, the ; annual dose to the gastrointestinal tract would be less than one mrem per year. The results of the environmental monitoring program to da.e have served generally to indicate the absence of detectable levelt, of radionuclides in the .
~
environment. Further, the TLD dose measurements are not significantly different ! at locations adjacent to the plant and as far as 20 miles away. The Submersion Dose estimates presented previously are based on stack release rates, and appear to be conservative in light of measured values. 1 I 1 I i I 1 O 5 - 44
l I l i O Table 5.2-10: Summary of Environmental Monitoring ; Program Sampling and Analysis d 1 Sample Type Sampling Sites Sampling Methods Air Particulate 8 Samples Constant Flow 'I
- 1) La Crosse Sampler and Filter l
- 2) Farm on Ridge to North j
- 3) Lock & Dam #8 4
- 4) Crib House l
- 5) Boat Launch Area i
- 6) Farm on Ridge to East
- 7) Trailer Court to South
- 8) Farm on Ridge to South Rain Water Same as for Air Particu- Collection Container late River Water 4 Sites Rinse Bucket with !
- 1) La Crosse River Water Pull in
- 2) Lock & Dam #8 Sample making sure t
- 3) Boat Launch Area bucket doesn't scrape
- 4) Genoa Fish Hatchery bottom Tap and Well Lock and Dam #8 Flush line for one i Water Genoa Fish Hatchery minute, collect LACBWR sample River Silt Lock & Dam #8 Scrape sediment from ;
Boat Launch shoreline drop dredge t Fish Hatchery or scoop in river ! Soil La Crosse Use trowel to gather Chaseburg grass and rock free Stoddard sample Genoa - Victory New Albin, Iowa q Minn. Hwy #25 & 26 l Wis. Hwy #35 & 56 Milk La Crosse Farm From Proprietor Genoa Creamery or Plant Worker
]
Vegetation La Crosse City Collect Above ] Genoa Farm Ground Vegetation l In Sample Bottle l l 0 Fish Above and below Catch by line l Dam #8 or net 5 - 45 1
1 I Table 5.2-10: Continued Sample Type Sampling Duration Sampling Frequency Air Particulate Continuous Weekly Rain Water Continuous Monthly
)
River Water Grab As dictated by Plant j Releases Tap and Well Water Grab Yearly
)
l River Silt Grab As dictated by Plant Releases Soil Grab As dictated by Plant i Releases Milk Grab bi-monthly Vegetation Grab As dictated by milk results Fish Grab As dictated by liquid discharges l l l l O 5 - 46
O l I ,. Table 5.2-10: Continued { Sensitivity Sample Type Analysis Performed Analyt.ical Procedure Detection Limit Air Particulate p-1 Count Immediately and 2.65x10-2pC1/N3* after it hour decay 8.70x10-3pC1/M3*** Rain Water p7 Dried and Counted 7 nCi/M3 ...
)
River Water p-7 (Suspended Solids) Alcohol - burn off 15 pC1/1
- l or air-dry c . ,'l *** j
- a. (Suspended Solids) Methods 8x10~2 {/1 ***
p-7 (D is ~olved) Dried 15 pCi/1
- And ***
( (Dissolved) Counted 8x10~gpCi/l pCi/l *** Sr-90 R/C Separation 5 pC1/1 *** Cs-137 R/C Separation 7.1 pCi/1 ***
~
T.1p and Well p- 7 Dried and Counted *** l Weter 8x10gpCi/l pC1/1 *** River Silt p- / Ashing 16.5 pC1/g
- Method **
4 2.1pgi/g Sr-90 2x10 pqi/g *** R/C Separation *** Cs-137 R/C Separation 9.5x10'{pci/g 1.tix10~ pCi/g *** l Soll E-7 Ashing Method
- ti.5 pCi/g 4
2.L pC1/g ** 2.0 pCi/g *** Milk Sr-90 fon-exchange 5 pC1/1 *** I-131 16 pCi/l *** Cs-137 7.1 pCi/1 *** Vegetation J1 Y Ashing Method 11.5 pC1/g
- 2.1 pCi/g **
rish 7-scan
- Counting Time 10 min.
** Coun ting Time 50 min.
*** Counting Time 100 min.
O 5 - 47 l
.1 O
REFERENCES ! 1. Ranthurn, R. G., "The Effects of Heated Effluent from the Dairyland Power Plant at Genoa on Water Temperatures and Fish of the Missis- I sippi River," Wisconsin Department of Natural Resources, Management j Report Number 48,1971. j
- 2. International Commission on Radiological Protection, " Report of Committee 11 on Permissible Dose for Internal Radiation,1959," Health Physics, Vol.
3,1960.
- 3. Federal Radiation Council, " Background Material for the Development of Radiation Protection Standards Report No. 2," Sept.1961.
- 4. Chapman, W. H.; Fisher, H.; and Pratt, M. W.; " Concentration Factors of Chemical Elements in Edible Aquatic Organisms," UCRL-50569,1968.
- 5. Personal Communication, Lockmaster, U.S. Army Corps of Engineers, Lock !
and Dam Number 8, Genoa, Wisconsin,1972.
- 6. Brownell, G. L.; Ellett, W. H.; and Reddy, A. R.; " Absorbed Fractions for :
I Photon Dosimetry," J. Nuclear Medicine Supplement 1,1968, p. 27.
- 7. Auerbach, S. l.; Nelson, D. T.: Kaye, S. V.; Rechle, D. E'; amd Coutant, C. C.; " Ecological Considerations in Reactor Power Plant Siting,"
Environmental Aspects of Nuclear Power Stations, IAEA-SM-146/53, Vienna,1971, pp. 805-820.
- 8. Burnett, T. J., "A Derivation of the ' Factor of 70G' for #1," Health Physics, Vol. 13,1970, pp. 73-75.
- 9. Dairyland Power Cooperative," Environmental Monitoring Associated with l Radioactive Effluent Discharges from the La Crosse Boiling Water Reactor from January 1,1969 to June 30,1971," DPC-851-31,1972.
- 10. Section of Radiation Protection, Wisconsin Department of Health and Social Services, Annual Reports, Environmental Radiation Survey, La Crosse Boiling Water Reactor, July 1969-June 1970 and July 1970-June 1971.
i O 5 - 48
-_j
y i O 5.3 EFFECTS OF CHEMICAL AND SANITARY WASTES Chemical effluents from the LACBWR are released from two discharge points-plant cooling water discharge and makeup demineralized regeneration backwash dis-charge. No sanitary wastes are discharged to the river. A comparison of the chem- l ical parameters of intake and discharge water (see Section 3.7) indicates that the r quality of the effluent water is unaltered and that adverse effects on aquatic or-gonisms in the receiving water do not occur. The State of Wisconsin has not adopted discharge standards for most chemical effluents. General standards of water quality have been established for waters used for specific uses in the state. (1) The Mississippi River in the Genoa area has been classified for: fish and other aquatic life, recreational use and industrial and cooling water use. Chemical discharges from the LACBWR must therefore be evaluated in relation to the ap-plicable standards for these uses. For dissolved solids, the concentration is not to exceed 750 mg/l as a monthly average, nor exceed 1000 mg/l at any time, in waters designated for industrial and cooling water use. The pH may range from .! 6.0 to 9.0, except in waters having a pH of less than 6.5 or higher than 8.5, where effluent discharges may not reduce the low value or increase the high value of i the pH by more than 0.5 standard units. When demineralizers are recharged -- there were 31 cycles in 1971 -- approximately 3,338 gallons of effluents are released with a total dissolved solids concentration of 4,480 mg/1. Demineralized wastes range in pH between 0.6 and 12.1 units, which exceeds the 6.0 to 9.0 standard range. However, because of rapid mixing of water in Thief Slough, dissolved solids are rapidly diluted to acceptable levels and hydrogen ion concentrations are diluted or buffered to levels within the standard pH range. To put dilution potentialin perspective, average monthly flows of the Mis-sissippi River for the 1970 water year ranged from 17,100 to 55,300 cfs (Table 5.1-3). It is unlikely that pH or total dissolved solid alterations resulting from LACBWR operation, even at minimum flows, can be detected at the upper end of O Islana 126, even though approximately one-fifth of the total Mississippi River flow 5 - 49
l O enters Thief Slough. Certainly, no measurable adverse effects on aquatic biota as a result of demineralized waste discharge would occur. With respect to metal discharged with demineralized wastes, no alteration of water quality is evident. However, because of maintenance of slow leakage from the cooling system, chromium compounds do enter the river. All releases of chro-mium compounds are diluted to less than 0.05 ppm as chromium before discharge. In 1971,127.6 pounds of compounds in the form of MgCr0 4 , No,Cr04 and K3 Crg 0,, were released. Approximately 80% of the material was released as Na 2 Cr0 . 4 This discharge has since been curtailed. As with pH and dissolved solids, dilu-tions of chromium by the receiving water mass will prevent adverse effects on
. aquatic organisms.
No chlorination is used in the LACBWR cooling water system and no chlorine l is discharged. In summary, effluents from the LACBWR are not expected to alter water l quality, and adverse effects on biota will not occur. No wetland or surface w:ters ; will be impaired by chemical discharges, nor will chemical waste adversely affect water quality to inhibit recreational use, 1 1 O l 5 - 50 I l
- . . . .= . - - - . - . .
l O , I REFERENCES
- 1. Wisc'onsin Water Quality Standards, adopted as Interstate Standards April ,
26,1967, effective June 1,1967, adopted as Intrastate Standards June 14, i 1968, effective September 1,1968. ) l l
\
l l o , l l 5 - 51 l
i O 5.4 ' OTHER EFFECTS 5.4.1 Transmission Lines i Power generated by the LACBWR is delivered to the Dairyland system via i previously-constructed transmission lines. The only line constructed for the LACBWR, as described in Section 3.2, is entirely within the Dairyland Genoa property. It has had no significant environmental effects, n l l l 4 O 5 - 52 ,
O 5.4.2 Shipment of Radioactive Materials Shipments of radioactive materials to and from the LACBWR are made in accordance with all cpplicable AEC and DOT regulations. The only measurable effect of normal shipment of radioactive materials is the dhect radiation exposure to persons along the shipping route. The maximum permitted level of exposure from radioactive material in transport is 10 mrem per hour at six feet from the nearest accessible surface. At this rate, an individual 100 feet from the shipping vehicle would receive 0.2 mrem per hour, while a per-son at 300 feet would receive approximately 0.01 mrem per hour. Since the shipping vehicle is normally in motion, and shipping routes avoid urban areas where the vehicle might be delayed in traffic, the actual periods of exposure for individuals are very brief, and the doses experienced are insignificant. The containers and packaging procedures used in the shipment of new fuel, spent fuel and radioactive wastes are such that there is no release of radioactive materials from the containers in normal shipment.
)
Even under the most severe accident conditions, the release of radioactive material would be minimal. In the case of fuel, either new or spent, the mechani-
)
cal characteristics of the fuel and the fuel assembly, as well as the integrity of ) l the shipping container, make it highly unlikely that any fission products would be {d released from the fuel assembly. In the case of radioactive wastes, the integrity i of the container virtually precludes the release of radioactive materials. The excellent safety record of the nuclear shipping industry supports the I conclusion that a significant release of radioactive material in a shipping accident is highly unlikely. The AEC has maintained records of incidents involving ship-ments of nuclear material over the last 20 years. These documents (AEC U/3613, TID-16764, including supplements 1 and 2) show that there have been very few incidents and that most of those resulted in little or no radioactive releases. 1 0 5 - 53
p 1. l l i I O 5.4.3 Noise j The only sounds created by the LACBWR that are audible at the site bound-ary are those of the turbines and the transformer. Neitner sound is loud enough to- q interfere with normal conversation, even within the site boundary. The sounds are barely discernible at the perimeter of the exclusion area, which is at a distance of 1109 feet from the center of the reactor. The noise associated with the operation of the LACBWR has not had any ef-1 feet on the natural environment or human activity in the vicinity of the plant and no effect is expected. 5.4.4 Interaction With Neighboring Fossil Plants The LACBWR and Genoa 3 share a common discharge, a fact that has a num-ber of positive implications for the environment. Since it is highly unlikely that both the LACBWR and Genoa 3 would be shut down simultaneously, the possibility - of a fish kill due to a sudden cooling of the thermal plume is minimal. There are ' also positive environmental effects from the reciprocal dilution of the LACBWR and Genoa 3 discharges. The discharge from the larger fossil-fueled plant provides rapid dilution for the low-level radionuclides discharged with the LACBWR cooling water effluent, while the LACBWR discharge assists the rapid dilution of the re-sidual chlorine released by the condenser chlorination system of Genoa 3. Chlori-j nation is used at Genoa 3 twice daily and only from May through September. Re- I sidual chlorine downstream of the Genoa 3 condenser, prior to mixing with the LACBWR discharge, is 1 ppm. No chlorination is used in the LACBWR itself, i l O. 5 - 54
\
O 5.4.5 Disposal of Miscellaneous Solid Wastes The miscellaneous solid wastes generated at the LACBWR include office wastes, machine-shop scraps, lunchroom wastes and similar wastes generated by the activities of operating and administrative personnel. Approximately one cubic foot of combustibles are incinerated each day in on on-site incinerator. The noncombustibles are landfilled in the Genoa 3 ash disposal area on-site, which is comparable to disposal in a sanitary landfill. Apart from the negligible volume occupied by the wastes in the disposal area, the burial of wastes there has no effect on the environment. 5.4.6 Changes in Site Land and Water Use The LACBWR stands on made land. Its operation has not and will not cause any changes in site land or water use beyond those entailed by development of the site, the effects of which were covered in Section 4. 5.4.7 Impact of the Physical Presence of the Plant on Land Use and Human Activities in the Plant Vicinity The physical presence of the LACBWR, i.e., its proximity to and visibility from surrounding areas, has had no known adverse effects on neighboring human activities or land uses. On the contrary, because the LACBWR is a point of in-terest for tourists, its presence has probably contributed to the income of tourist-service businesses in the vicinity of Genoa. The Mississippi River Regional Planning Commission has recommended Genoa as the location for one of four " tourist growth centers" in the region (see Section 2.2.11). The numerous islands of the Upper Mississippi River Wild Life and Fish ! 6 Refuge are open to primitive comping. The proximity of the plant has not dis-couraged such use along the shores of islands near the plant. Further, the crea involved - perhaps a few hundred acres -- is so small in relation to the total Refuge area available for primitive camping that any effect can be considered neg-lible. There are no other parks, historic sites or other visually-ser sitive land uses O sufficiently close to the plant to be adversely affected by its presence. 5 - 55
O 5.4.8 Impact on Historic Sites Neither the operation of the plant nor, as indicated above, its physical pres- 3 ence has any effect on any historic or archeological site. The nearest site listed in the National Register of Historic Places is in Brownsville, Minnesota, approximatriy nine miles north of the LACBWR. The only Wisconsin State historical marker within sight of the plant is approximately one-half mile away, opposite U.S. Lock o'nd Dam No. 8, at a wayside on the east side of Highway 35. It refers to the entire series of federal dams on the Mississippi. Given the nature of the marker's subject matter, large-scale human works, the proximity of the LACBWR and of the entire Genoa generating complex is not in-consistent with public appreciation and enjoyment of this historical marker. 5.4.9 Impact of Underwater Structures The underwater structures associated with the Genoa generating facilities have had no adverse effects on navigation. They do not interfere in any way with navigation in the main channel of the Mississippi River. Navigation in Thief Slough is essentially limited to recreational craft, many of which use the access ramp on the Dairyland property, and to the barges that deliver co:1 to Genoa 3. The presence of the underwater structures has imposed no significant limitations in the movement either of borges or of recreational craft. 5.4.10 Exclusion Area The LACBWR exclusion area has a radius of 1109 feet (see Figure 2.1-1). Approximately 90% of the area within this radius is either Dairyland property or within the boundaries of the Federal Wildlife and Fish Refuge. The balance of the exclusion area cone.ists of railroa6 and highway right-of-way and of land on the steep faces of the Mississippi bluffs. The land on the bluffs which is not Dairyland property is subject to a scenic casement held by the State of Wisconsin. Thus, the creation of the exclusion area has entailed no alteration in land use that would not have occurred without the existence of the LACBWR. O 1 l 5 - 56 l
l I i O 5.5 ASSESSMENT OF ENVIRONMENTAL EFFECTS OF PLANT OPERATION The various effects associated with the operation of the LACBWR have been described in Sections 5.1 through 5.4. The environmental studies and programs which have been and are being conducted to evaluate the impact of the plant are reviewed in this section. 5.5.1 Aquatic Studies The influence of the circulating water system discharge on water tempera-tures in Thief Slough and the Mississippi River were investigated by the Wisconsin Department of Natural Resources (DNR). Downstream thermal patterns resulting from the individual and combined effluents from the LACBWR and Genoa 3 were observed from July 1969 through December 1970. DNR biologists also observed the types and numbers of fish utilizing the area of Thief Slough on a monthly basis from August 1969 through March 1970. ' A more complete picture of the influence of the thermal effluents was ob-toined as a result of a June 1972 study. Dr. Thomas O. Claflin, a consultant to Dairyland Power, determined the occurrence of phytoplankton, zooplankton and benthic organisms at locations upstream and downstream of the discharge. These works are detailed in Section 5.1. The concentrations of chemicals present in the LACBWR discharge have been measured. Based on these measured values, neither water quality nor biota l are expected to be affected.
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wo ..; s 5, i s 3 g O " 5.5.2 Radiological Studies , The preoperational and operational environmental monitoring programs con-ducted for the LACBWR are dotoiled in Sections 2.8 and 5.2, respectively. The 1968 ARMS study (see Section 2.8) evaluated the natural gamma exposure rate. Gamma radiation surveys were conducted in April and August 1972 to deter-j, mine the exposure rates resulting from plant operation at the exclusion distance. The results of these surveys are teportefelsewhere. (1) Ths Wisconsin Department oi Heahh and Social Services conducts an en-vironmental radiation monitoring program in addition to that carried out by Dairyland Power. Samples of air, precipitation, river and well water, silt, soil, vegetation and milk are collected and unalyzed for radioactivity. The results of these surveys for the periods July 1969 to Jtne 1970, and July 1970 to June 1971, have been com-piled in annual reports. (2,3) The results have been consistent with those t.btained by Dairyland Power. j, f s t 5 - 58 a_ - _ _ - _ _ _ _ _ _ - -
p l l O REFERENCES l
- 1. Environmental Analysts, Incorporated,1972, " Operational Radiation Survey at the La Crosse Boiling Water Reactor,"~(work in progress).
- 2. Wisconsin Department of Health and Social Services, Division of Health,
" Annual Report, Environmental Radiation Survey, La Crosse Boiling Water Reactor, July 1969 - June 1970".
-3. Wisconsin Department of Health and Social Services, Division of Health,
" Annual Report, Environmental Radiation Survey, La Crosse Boiling Water Reactor, July 1970 - June 1971".
1 i i 1 i 1 5 - 59 l 4
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O 6.0 ENVIRONMENTAL EFFECTS OF ACCIDENTS 6.1 SCOPE s A complete analysis of the potential environmentalimpact of a particular nuclear facility must consider the contribution from various abnormal and/or ac- ; cident conditions which may arise during the facility'c lifetime. To provide a j manageable framework within which such conditions can be discussed, tl.e AEC has defined nine categories of accidents to be considered and has proposed various assumptions to be employed in evaluating their consequences. (1) Table 6.1-1 , lists the various categories proposed by the AEC together with examples of ac-/
/
cidents considered in each category for the LACBWB. Class 1 events are included and evaluated under routine releases in accordange with applicable regulcidas. The probability of the pestulated successive faildes for Class 9 occgences are sufficiently small that their environmental risk is extremely low. No' further con-sideration is given to either class of event. Many of the accidents considered bare were previously discussed in the ', Safeguards Reports. The analysis presented at that time assumed extremely con-servative conditions in an effort to define the extreme limit of anticipated effects. The present analysis, however, attempts to provide a; realistic on account as possible for these potential situations. Plant design incorporates accident prob- ,5 ability and the probability of most accidents is so remote that they are not ex- - pected to occur during the operating life of J.e plant. The accident descriptions presented follow the assumptions specified by the AEC except in cases where features specific to the LACBWR result in signif-icantly different conditions. These features may relate to the plant equipment or to the operating experience that has bt.en acquired since the plant began operation in July 1967. In particular. measured primary coolant concentration values, off-gas release rates and liquid radwaste tank concentrations have been used rather than the assumptions proposed by the AEC for a number of the accident cases. . /, '
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O 6.2 PROBABILITY CATEGORIZATION In evaluating the effects of the various accident situations, some weight must be given to the probability of occurrence of a particular event. Because of the many interacting systems and actions that are involved in a particular situation, it is difficult to assign a precise probability to each accident or category of acci-dents. One approach involves discussing probabilities in terms of descriptive plant conditions which correspond roughly to probability categories of about two orders of magnitude. Consideration of the various accidents, even disregarding the prob-ability issue, results in reasonably low radiological consequences, and the acci-dent categories are more representative of similar effects rather than probabilities of occurrence. The probability categorization is derived from Section III of the ASME Boiler
& Pressure Vessel Code (2) and has been used in design safety analyses. The categories are described as:
- 1. Normal Condition (P = 1)
A normal condition is any planned and scheduled event that is the result of deliberate plant operation according to prescribed procedures. I
- 2. Upset Condition (1>P>2.5 x 10^)
An upset condition is a devistion from normal conditions that has a moder-ate probability of occurring during a 40-year plant lifetime. These conditions typically do not preclude subsequent plant operation. 3 )P>2.5 x 10 )
- 3. Emergency Condition (2.5 x 10 An emer9ency condition is a deviation from normal plant operation that has a low probability of occurring during a 40-year plant lifetime. Emergency condition events are typified by transients caused by a multiple valve blow- I down of the reactor vessel or a pipe rupture of an auxiliary system.
- 4. Fault Condition (2.5 x 10">P22.5 x 10 )
A fault condition is a deviation from normal conditions that has an ex-tremely low probability of occurring during a 40-year plant lifetime. These postulated events include, but are not limited to, the most drastic event con-O sidered in design (the limiting design basis). l 6-3 1 b
I 1 l i O ! 6.3 DOSE ASSESSMENT ; The most descriptive method of evaluating the dose to the population from accidental releases is through use of the " man-rer" unit. These values were determined by calculating the dose to an individual as a function of distance and i direction from the release point anh multiplying the dose by the number of persons I living at that distance. The cumulative man-rem to a distance of 25 miles is based , i on the assumptions in the Annex tb Appendix D,10CFR50 (1), estimated accidental ! I releases of radionuclides and population data from the 1970 census (see Section q 2.2.1). The results of these calculations for the various categories are summarized in Table 6.3-1. Also included in the table is the largest dose to an individual from either submersion in a cloud of radioactive gases or from inhalation of radio-nuclides. Measurements at the LACBWR site have indicated the gamma exposure rate from natural sources to be as much as 10,R/ hour (see Section 2.8). Assuming s this is representative of the exposure to the population within 25 miles, the cumu-lative man-rem per year would be 10,750 from cosmic and terrestrial sources alone. { 3 Even without considering medical exposure to radiation and the dose from naturally
)
occurring radionuclides in the diet, it is obvious that the calculated man-rem from accidents would be only a small fraction of that from background radiation. 1 I 1 l 6-4 i
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u O l 6.4 CLASS 2 -- SMALL RELEASE OUTSIDE CONTAINMENT l A variety of leakage paths may exist in an operating power plant. Releases f associated with such leaks will depend upon the type of leak. ' Activity released from the primary system through these leaks will be routed either to the building drains, in which case no release to the environment occurs, or to the building ventilation. The accident considered typical of this category is the leakage of steam equivalent to 0.1 gpm of liquid, measured by tritium balance, in the turbine building and the release of the associated activity to the stack. Measured values of I-131 l in the primary coolant and of noble gas release rates are used to define the plant. condition. Assuming a water / steam partition factor of 10 and a plateout/conden-sation factor of two, release to the atmosphere is 8.05(-5)aci/sec I-131. The average off-gas release rate for the first quarter of 1972 was ^'450aCi/ see with a 10-minute holdup. An equilibrium spectrum of gases has been observed and the corresponding release rate et t = 0 is *1040a Ci/sec. Based on the' ratio ' of leak flow to total steam flow, approximately 0.85aCi/sec of noble gases would l be released. Because this release is so low, no further spectral breakdown of the gases was felt to be necessary. As is indicated in the Annex to Appendix D, these releases have been con- l sidered routine and evaluated in accordance with applicable regulations in Section 5. Leakage of the type considered here is not uncommon. Experience with i mechanical equipment shows that small, sometimes even undetectable, steam leaks ' occur from time to time. This class is considered to be an " upset" condition. ' O 6-5 l
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. Il O
Table 6.3-1: Summary of Radiological Consequences of Postulated Accidents Estimated Fraction Estimated Dose to Population (4) of 10 CFR Part 20 in 25-Mile Radius (man-rem) Limit at Site Class Event Boundary (1) . Submersion Integrated Thyroid 1 Trivial Accidents (2) (2)- (2) l 2 Small Releases Outside Containment (2) (2) (2) ) 3 Desorption of Iodine Not from Charcoal 0.0005 Applicable 0.03 i Release of 25% of Gaseous Waste Tank 0.0007 0.02 0.004 Release of 25% of Liquid Waste Tank Negligible (5) Negligibic 0.03 Release of 100% of Gaseous Waste Tank 0.003 0.1 0.02 4 Off-Design Transient 0.001 0 02 0.06 5 Not Applicable to liWR's -- -- -- 6 (A) Fuel Bundle Drop 0.001 0.009 0.08 (D) lleavy Object Drop 0.02 0.1 1.0 7 (A) lleavy Object Drop onto Fuel Rack 0.002 0.004 0.1 (B) Fuel Cask Drop Negligible Negligible Not Applicable i 8 (A) Loss of Coolant Accident i I Small Break Negligible Negligible Negligible I II Large Break 0.002 0.03 0.07 (D) Rod Drop Accident 0 002 0.02 0.08 i (C) Steam 11ne Breaks I Small Break 0.002 0.01 0.08 II Large Break 0.002 0.01 0.1 ; I 9 Conditions more severe than Design Basis (3) (3) (3) Natural Background 0.2 10,750 10,750 I (1) Represents the calculated whole body dose as a fractf on of 500 mrem (or the equivalent dose to an organ). i (2) These releases will comply with applicable standards and are treated in Section 5. (3) " ' '""1""'"" "" * "*'"'*"1x 1 " v" b"'l'l'Y f ' """"" "- O (4) Based on 1970 population of 122,706. (5) Negligible denotes less than 0.001 man-rem or .1% of the appropriate limit. 6-6
O 6.5 CLASS 3 -- RADWASTE SYSTEM FAILURE Three representative situations for this category were listed in the Annex. They are: (1) equipment leakage or malfunction; (2) release of waste gas storage tank contents; and (3) release of liquid waste storage tank contents. 6.5.1 Equipment Leakage or Malfunction In this category, three events are considered. They are: (1) the desorption of iodine from the charcoal filter in the off-gas line; (2) release of 25% of the gases contained in the waste storage tanks and (3) release of 25% of the average inventory in the largest liquid waste storage tank. 6.5.1.1 Desorption of lodine from Charcoal Filter The measured average release rate of 1-131 from the LACBWR during the first 6 months of 1972 was 0.011x Ci per second. The highest monthly average i during this period occurred in March and was 0.034 qCi per second. The latter
]
release rate,0.034 4Ci per second, was chosen for the accident considered. l l Assuming that the charcoal filter is 90% efficient, some 0.0034 curies of i 1-131 will be present on the filter at equilibrium. Desorption of the iodine could result from passage of a slug of water vapor through the charcoal filter. The dose estimates appearing in Table 6.3.1 for this accident condition are based on the assumption that 25% of the iodine inventory is desorbed over a time span of 10 i minutes equivalent to a release rate of 5.6 4Ci per second for the duration of the ! event. This event is considered to be an " upset" condition. l l O 6-7 ,
- - - - _ . - - - _ - - - J
1 I I l () ;l j i l Table 6.5-1: Isotopic Analysis and Release of 25% of Pressurized. I Holdup Tank Content { l i Tank Inventory Release Rate Isotope Af ter 36 hours (Ci) Curies Released (pCi/sec) , 1 I-131 0.0042 0.001 6.1 I-133 0.0017 0.00044 2.6-Kr-85m 3.47 0.868 5,106 Kr-87 1.36 0.340 2,000 i Kr-88 3.03 0.758 4,459 j l Xe-133 14.7 3.68 21,647 i i Xe-135m 0.845 0.211 1,241 Xe-135 29.6 7.40 43,529 I Xe-137 0.0364 0.00910 53.5 Xe-138 0.399 0.0998 587
)
Total 53.4 13.4 78,824 I i l 1 6-8 I
O 6.5.1.2 Discharge of 25% of Gaseous Waste Tank The two gaseous waste storage tanks of the LACBWR are each capable of holding up to 36 hours of gaseous effluents at full power operation. Each tank has a capacity of 1600 cubic feet and may be used individually or in series to store gases at pressures of 300 psi. Operator error could result in the inadvertent re-lease to the stack of 25% of the average inventory of one of these tanks. Since these tanks had never been used before August 1,1972, typical radionuclides inventories are not available. It is assumed for estimating the inventory that the airborne radionuclides build up in storage for 36 hours prior to the accident. The source terms shown in Table 6.5-1 are based on the highest measured monthly average release rates, i.e., those measured in July 1972. The total release and release rates are also listed. The radiological effects of these releases are sum- I marized in Table 6.3-1. An accident of this type is considered an " emergency" condition. 1 1 1 0 6-9
O 6.5.1.3 Discharge of 25% of Waste Water Storage Tank There are a few different circumstances which might result in an inadvertent liquid release through operator error. They are: (1) the operator commences pumping without taking a batch sample, thereby violating procedures; (2) a batch sample is incorrectly' analyzed or the results of the analysis are incorrectly communicated to j the operator; or (3) the operator, having been notified of an acceptable batch sam- ! ple, pumps the wrong tank by mistake. .This type of accident was selected based on the greater probability of human error than equipment malfunction in the rod-waste system. The isotopic analysis of the waste water storage tank in Table 6.5-2 was performed on April 20,1972, and is representative of tank concentrations on April 15, 3 1972. It has been selected as representative of normal tank inventory. The concentration in the discharge canal was determined by considering the relative flow rates of the waste water pumps and the condenser cooling water. A dilution j factor of 1252 between the waste tank and the discharge canal was determined. Since the Annex specified a release of 25% of the tank contents, the tank capacity is 4500 gallons and the pump rate is 50 gpm, the total release would consist of' 1 j 1125 gallons of waste water in 22.5 minutes. During this tirne about .0175 Ci of l 1 activity would be released. The results of the dose assessment for this release ! are presented in Table 6.3-1. Recent data on operator errors of the types considered suggest that such an occurrence would constitute an " emergency" condition. i 1 i l 0 6 -10
1 l 0 Table 6.5-2: Isotopic Analysis of Waste Water Storage Tank Waste Tank Discharge Canal Isotope pCi/ml pCi/ml I-13 L 3. 28 (-4)
- 2. 6 (-7) i Ba-llo 2.56( 5) 2. 0 (- 8)
Ba-140 1. 69 (-5) 1.3 (-8) Co- a8 1. 48 (-3) 1. 2 (- 6) Cs-60 1. 66 (-4) 1. 3 (-7) Na-24 1. 73 (-5) 1. 4 (- 8) Cr-51 7 . 71 (-5) .6.2(-8) Mn-52 4. 35 (- 6) 3. 5 (-9) Mn-54 2. 43 (-5) 1. 9 (-8) Fe-59 1. 3 5 (- 5) 1.l (-8) Co-56 3. 43 (- 6) 2.7 (-9) I Co-57 7. 89 (- 6) 6. 3 (- 9) Zn-65 2. 82 (-5) 2. 3 (- 8) Y-88 2. 51 (- 6) 2. 0 (- 9) Zr-88 4. 52 (- 6) 3. 6 (-9) Zr-95 2. 50 (-5) 2. 0 (-8) Nb-95 2. 2 9 (-5) 1. 8 (- 8) Cu-64 <l .11(-3) 4 8. 9 (-7) 3 Nb-95m 7 . 21(- 6) 5. 8 (-9) 1 Mo-99 1.15 (-4) 9. 2 (-8) Tc-99m 1. 4 (-5) 1. l(- 8) Sn-125 2. 06 (-4) 1. 6 (- 7) Sb-125 2. 68 (-5) 2 . l (- 8) Sb-122 2 . 94 (-4) 2. 3 (-7) Sb-124 1. 23 (- 5) 9. 8 (- 9) St 146 5. 61(- 6) 4. 5 (-9) it-132 2. 81(-5) 2. 2 (-8) 1-132 <5 . 71 (- 6) <4. 6 (-9) Cs-134 8. 54 (- 6) 6. 8 (- 9) Cs-137 3 .14 (- 5) 2. 5 (- 8) Hf-181 1. 07 (-5) 8. 5 (- 9) Total (Excl. H-3) 4.12 (-3) 3 . 3 (- 6) H-3 1. 0 (-1) 8. 0 (- 5)
- Numbers in parentheses denote exponentiation, eg.,
- 3. 28 (-4) means 3. 28 x 10-4 O
6 - 10 A
l O 6.5.2 Release of Weste Gas Storage Tank Contents The entire contents of one of the gas storage tanks is assumed to be released to the stcck through the relief valve line over a time period of 45 minutes. The total activity in storage af ter 36 hours of use is as presented in Table f 6.5-1. The expected release rates, based on the tabulated inventory and the time f period of the release, are presented in Table 6.5-3. Dose estimates for this ac-cident are presented in Table 6.3-1. The situation might arise from the failure of release valves and rupture discs and is considered an " emergency" condition. 6.5.3 Release of Liquid Waste Storage Tank Contents ! Release of the total contents of a liquid waste storage tank within the build-ing would result in essentially no radioactivity release to the environment. The facility is dengned to contain any such spillage and subsequently treat the spilled water. For this reason, no further consideration is given this event. l 1 3 l 1 O 6 - 11
O 6.6 CLASS 4 -- FISSION PRODUCTS TO PRIMARY SYSTEM The conditions recommended to be evaluated in this category are: (1) fuel cladding defects and (2) off-design tranrients that induce fuel failures above those expected. Fuel claddi% cefects are treated under normal operation and therefore will not be considered further in this section. The occurrence of off-design transients resulting in fuel failures is felt to be an almost incredible situa-tion. While there are no realistic cases in this category, for the sake of complete-ness, the assumptions of the Annex have been used and a hypothetical release resulting from an off-design transient has been computed. The following assumptions were specified in the Annex: (a) 0.02% of the core inventory of noble gases and 0.02% of the core inventory of halogens released to the coolant; (b) 1% of the released halogens shall be assumed to be in the steam; (c) radioactivity shall be assumed to carry over to the condenser where 10% of the halogens shall be assumed to be available for leakage from the condenser at 0.5%/ day for the course of the accident (24 hours). l The core inventory of halogens and noble gases which was used as the basis ; for the MCA computations in the Safeguards Report has been used in these calcu-lations (Table 14-8 ACNP 65544). Core activity is assumed to be evenly distri-buted among assemblies and among rods within assemblies. The source terms for dose assessment appear in Table 6.6-1 and the associated doses in Table 6.3-1. This situation is considered to be totally hypothetical. O 6 - 12
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i o i 6.7 CLASS 5 -- FISSION PRODUCTS TO PRIMARY AND SECONDARY SYSTEMS This category pertains solely to PWR's and is therefore not applicable to , 4 this facility. 6.8 CLASS 6 -- REFUELING ACCIDENTS i Two situations in this category have been specified in the Annex. The following discussion considers both of them and employs the Annex assumptions as a basis. 6.8.1 Fuel Bundle Drop The following assumptions, as specified in the Annex, are used in this situa-j tion: (a) Gap activity of noble gases and halogens in one row of fuel pins shal! be assumed to be released into the water (Gop activity is 1% of total activity l in a pin); 1 (b) One week decay time before the accident occurs shall be assumed; (c) lodine decontamination factor in water shall be 500; l l (d) A realistic fraction of the containment volume shall be assumed to ; leak to the atmosphere prior to isolating the containment. Tne fuel assemblies used in the La Crosse Boiling Water Reactor are in a 10 x 10 array. The releases shown in Table 6.8-1 would occur for the above assumptions. The activity release to the atmosphere assumes that the normal building ventilation flow of 5000 cfm continues for a 15-minute period subsequent to the ac-cident at which time isolation occurs. Complete mixing is assumed within the build-ing. The 15-minute period is felt to be a reasonable period for isolation either automatically or manually from the control room. No credit has been taken in this analysis for iodine removalin charcoal filters in the off-gas system since they are bypassed by the normal ventilation flow through the stack. Leakage subsequent to isolation (0.1%/ day) is negligible compared to the first 15-minute release. The O dose estimates for this event are presented in Table 6.3-1. 6 - 13 u
O Table 6.5-3: Isotopic Analysis and Release of 100% of Pressurized Holdup Tank Contents Tank Inventory Release Rate Isotope After 36 hours (Ci) Curies Released (pCi/sec) I-131 0.0042 0.0042 1.53 I-133 0.0017 0.0017 0.64 Kr-85 5 3.47 3.47 1,274 Kr-87 1.36 1.36 499 Kr-88 3.03 3.03 1,113 Xe-133 14.7 14.7 5,398 Xe-135m 0.845 0.845 310 Xe-135 29.6 29.6 10,870 Xe-137 0.0364 0.0364 13.4 Xe-138 0.399 0.399 147 l l l Total 53.4 53.4 19,611 l O 6 - 14
L O This situation, which would arise from the failure of the fuel hoist or its supporting equipment, is considered to be at the lower end of probability of the
" emergency" condition. Since it is planned to change 32 assemblies per refueling, this situation remains in the " emergency" condition.
6.8.2 Heavy Object Drop Onto Fuel In Core l This situation is assumed to occur at some point during the refueling opera- l tion. The only possible event which might be applicable would be dropping of a fuel element onto the core (refueling accident). The assumptions specified in the Annex were used to determine the activity released. (a) Gap activity of halogens and noble gases in one average fuel assembly shall be assumed to be released into the water (gap activity shall be 1% of total activity in a pin); (b) 100 hrs of decay time is assumed before the object is dropped; (c) Iodine decontamination factor in water is 500; (d) A realistic fraction of the containment volume shall be assumed to leak to the atmosphere prior to isolating the containment. The estimated releases for this event are presented in Table 6.8-2 and the expected doses in Table 6.3-1. Conditions of complete itxing and containment isolation within 15 minutes, as described in the fuel rod drop case, are also assumed here. Both releases would occur through the plant stack. The probability of this situation occurring is less than that for the fuel rod drop incident because of the numbers of fuel rods moved and the possibility of their falling without striking the core. It is doubtful that any other heavy object would be available to be dropped onto the core resulting in this type of release. O 6 - 15
I (1 Table 6.6-1: Source Terms for the Described Class 4 Event Core Coolant Condenser Release Rate Isotope Curies Curies Curies Ci/see pCi/sec ; I-131 4.16 (6)
- 8.32(2) 8.32(0) 4. 82 (-7) 4. 82 (-1)
I-132 6.17 (6) 1.23(3) 1.23(1) 7.14 (- 7) 7.14 (-1) , I-133 9.18(6) 1.84(3) 1.84(1) 1. 06 (- 6) 1.06(0) l 1.59(1) I-134 7.96(6) 1.59 (3) 9. 20 (- 7) 9. 20 (-1) I-135 7.81(6) 1.56(3) 1.56(1) 9. 04 (-7) 9. 04 (-1) Xe-131m 4.18(4) 8.4 (0) 8.4 (0) 4. 87 (- 7) 4. 87 (-1) ; Xe-133 9.22(6) 1.85(3) 1.85(3) 1. 07 (-4) 1.07 (2) I Xe-135m 2.33(6) 4.66(2) 4.67 (2) 2. 7 0 (-5) 2.70(1) Xe-135 8.28(6) 1.66(3) 1.66(3) 9. 6 (-5) 9. 6 (1) Kr-83m 7.74(5) 1.55(2) 1.55(2) 9. 04 (- 6) 9.04(0) { Kr-85m 14.0(6) 2. 8 (2) 2. 8 (2) 1. 62 (-5) 1.62(1) j Kr-87 3.77(6) 7.54(2) 7.54(2) 4. 38 (-5) 4.38(1) i Kr-88 5.33(6) 1.06(3) 1.06(3) 6.17 (-5) 6.17 (1) i j
- Numbers in parentheses denote exponentiation.
O 6 - 16
l l I l O 6.9 CLASS 7 -- SPENT FUEL HANDLING ACCIDENT Three situations are described in the Annex as representative of this cate-gory: (1) fuel ocsembly drop in fuel storage pool; (2) heavy object drop onto fuel rock; and (3) fuel cask drop. The assumptions listed for the fuel assembly drop in the fuel storage pool are identical to those used in the analysis of the fuel as-sembly drop during refueling. Since the spent fuel storage poolis also located within the containment building, the results of this accident will also be identical to the previous case and it will not be discussed further here. Release fractions from the containment to the atmosphere are the same for this category as they were for the Category 6 accidents. 6.9.1 Heavy Object Drop Onto Fuel Rack The following assumptions were used, as specified in the Annex: ! (a) Gap activity of noble gases and halogens in one average fuel assembly is released into the water; (b) 30 days' decay time prior to the accident is assumed; (c) Iodine decontamination factor in water is 500. The releases to the atmosphere shown in Table 6.9-1 assume complete mixing and building isolation in 15 minutes as discussed previously. Dose estimates are presented in Table 6.3-1. The probability of this incident is considered to be approximately equal to that of a fuel assembly drop during refueling. Thus, it is considered an " emergency" condition. O 6 - 17
O Table 6.8-1: Estimated Releases for a Fuel Bundle Drop i Rod Release Release to Release to Activity from Fuel Containment Atomosphere Isotope @ l wk. (Ci) (Ci) (Ci) pCi/sec' Tot. Ci , l I-131 3.17 (2)
- 3.17(1) 6. 34 (-2) 2.0(1) 1. 8 (-2)
I-133 5.12(0) 5.12 (-1) 1. 02 (-3) 3 . 2 (-1) 2. 9 (-4) 1-135 3.13 (-5) 3.13 (-6) 6. 26 (-9) 2. 0 (- 6) 1.8 ( 9) ] Xe-131m 3.83(0) 3. 83 (-1) 3 . 83 (-1) 1. 2 (2) 1. l(-1) Xe-133 5.13(2) 5.13 (1) 5.13 (1) 1. 7 (4) 1. 5 (1) Xe-135 3.11 (-3) 3.11(-4) 3.11 (-4) 9. 8 (-2) 8. 8 (-5) ! I
- Numbers in parentheses denote exponentiation.
l O 6 - 18
~
l
)
O , 6.9.2 Fuel Cask Drop I No specific cask has been selected to date for transfer of spent fuel from j
\
the plant site. It is anticipated, however, that the spent fuel shipments will l consist of 6 to 10 assemblies per cask. For purposes of this report, it has been assumed that 10 assemblies will be shipped in a fully loaded cask and that the assumptions specified in the Annex are valid. These include: (a) 10 assemblies per cask; (b) Release of noble gas gap activity from one fully-loaded cask; (c) A decay period of 120 days. The expected releases and associated doses appear in Tables 6.9-2 and j 6.3-1, respectively.
.l In discussing this type of accident, Dairyland Power h'as stressed that the -
l cask transfer equipment is weight-tested immediately prior to removing the cask I l from the spent-fuel storage pool. The possibility of this equipment failing in so I severe a manner as to permit the cask to drop just after a successful test is con-sidered low in itself. As a backup, the cask is designed to withstand severe shocks without loss of integrity and it is believed that the design limits would not be ex-ceeded in this situation since the U.S. DOT specifies that a cask must withstand a 30-foot drop onto un unyielding surfoce. The maximum drop possible during fuel cask transfer is about 25 feet and the transfer equipment is not an unyielding sur- { face. Because the probability of the cask drop and loss of integrity are so low individually, their simultaneous occurrence resulting in the noble gas releases postulated above is considered to be a fault condition. a O 6 -19 l
l O .. ) {
)
Table 6.8-2: Estimated heleases for a lleavy Object Drop Onto Fuel in Core j Rod Release Release to Release to l Activity from fuel Containment Atmosphere I Isotope 0100 hr (C1) (Ci) (Ci) uCi/sec Tot. C1. ] l I-131 4. 05 (2)
- L1. 05 (2) 8.1(-1) 2. 6 (2) 2. 3 (-1) i I-133 4.74(1) Lt.74 (1) 9. t68 (- 2) 3.0 (1) 2.7 (-2)
I-135 3. 56 (-2) 3. 56 (-2) 7.12 (-5) 2. 2 (- 2) - 2. 0 (-5) Xe-131m 4.53(0) 11 . 5 3 ( 0 ) 4.53(0) 1.4 (3) 1.3 Xe-133 7.itit (2) 7.4tl (2) 7.Litt (2) 2. 3 (5) 2.l(2) Xe-135 5. 52 (-1) 5. 52 (-1) 5. 52 (-1) 1. 8 (2) 1. 6 (-1) : Kr-85m 2. 72 (-5) 2. 72 (-5) 2. 72 (-5) 8. 6 (3) 7.7 '
- Numbers in parentheses denote exponentiation.
i O 6 - 19 A l - - _ _ _ . _ - - - _ _ _ -
i l l
^
Q ll Table 6.9-1: Estimated Releases for a Heavy Object Drop Onto Fuel Rack ! I Assembly Release Release to Release to i Activity from Fuel Containment Atmosphere i Isotope O 30 days (C1) (Ci) (Ci) pCi/see Tot. Ci l I-131 4. 45 (3)
- 4.45(1) 8. 9 (-2) 2. 8 (1) 2. 5 (-2)
Xe-131m 9.70(1) 9. 7 0 (-1) 9. 7 0 (-1) 3.l(2) 2. 8 (-1) Xe-133 2.52(3) 2.52(1) 2.52(1) 8. 0 (3) 7.2
- Numbers in parentheses denote exponentiation.
l J l l 6 -20 l
-)
1 0 6.10 CLASS 8 -- ACCIDENT INITIATION EVENTS CONSIDERED IN DESIGN BASIS EVALUATION IN THE SAFETY ANALYSIS REPORT There are a number of differences between accident conditions considered in current Safety Analysis Reports and those discussed for the LACBWR. In part, these differences reflect the change in matters of concern to regulatory authorities, vendors and owners over the years in light of accumulated operating experience. I Also, the facility is unlike current boiling water reactors in its use of a secondary containment building. The following accident descriptions attempt to balance the AEC assumptions in the Annex with the actual conditions of the facility. 1 i o i O 6 - 21 I
O Table 6.9-2: Estimated Releases for a Fuel Cask Drop Isotope Cask Activity @ 120 days (Ci) Release from Cask (Ci) Xe-131m 4.47 (0)
- 4. 47 (-2)
Xe-133 1. 92 (-1) 1. 92 (-3) -
- Numbers in parentheses denote exponentiation.
l 1 1 l O 6 - 22
O 6.10.1 Loss of Coolant Accident 6.10.1.1 Small Pipe Break (6" or less) j I This condition may arise through a break in a number of small pipes pene trating the bottom head, such as the in< ore flux monitors. For small breaks, the makeup capability of the core spray systems is greater than the flow through the break. These systems will operate intermittently to maintain reactor water level. No fuel damage will occur and the activity available for release to the atmosphere is that contained in the amount of primary coolant released. The average primary coolant inventory at 0.5% failed fuelis assumed as specified in the Annex. Credit ! l is taken for the pressurized secondary containment building by assuming 100% mixing. A constant leakage rate of 0.1% per day has been used in previous analyses rather than taking credit for pressure decrease at longer times after the accident. A reduction factor of 0.2 for interaction within containment was used. l The distinction between large and small breaks :or the LACBWR facility is based upon the makeup capability of the emergency systems. Thus, any break l resulting in a flow of less than 1000 gpm is considered small. As is noted in the discussion of the large break, about 571,000 pounds of fluid is released before flow stops due to building flooding. The principal difference between the two breaks 1 from the point of view of releases is the time scale during which this flow occurs. l In the large break situation, flow essentially stops in 80 seconds. For the small break at 1000 gpm, a total of 4100 seconds or 68.4 minutes elapses before 571,000 1 I pounds of fluid are released. Because release time from the primary system is smallin comparison to the release times of interest for dose calculations, the source term considered is an instantaneous release of the primary coolant. The following conditions are assumed: (a) Primary coolant activity corresponds to operation with 0.5% failed l fuel release from containment; (b) Building mixing of 100% occurs; (c) A reduction factor of 0.2 is assumed for plateout, core sprays, containment sprays, etc.; (d) The containment building leaks at 0.1% per day. 6 - 23
O The majority of the fission and activation products will remain in the water and only the halogens will be available for leakage. When concentration-dose relationships are considered, iodine-131 is seen to be the most restrictive isotope present. The activation and noble gases evolved will be small compared to normal operation and, therefore, have not been included here. The release rates are shown in Table 6.10-1 and the corresponding doses are shown in Table 6.3-1. l Information is available primarily on the probability of a large break in the l primary coolant system. It is felt, however, that although the number of potential breaks is different for small and large breaks, it is reasonable to consider the small break, like the large break, to represent on " emergency" condition. 1 l i 4 I O 6 - 24
-- r-I h__ e n,
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i a j Table 6.10 1: Estimated Icf2 ases for a Small Pipe Break Release Rate (Ci/sec) I Isotope 0-8 hr 8 - 2 Li hr 1 ti days (1-30 days I-131 8.09(-12)* 6.75 (-12) 6.29(-12) 2.19(-12) . 1-133 6.25(-12) ti. 36 (-12) 1. tl2 (-iti)
- 1. 2 ti (-12 )
Total 1.43(-11) 1.11 ( 11'j- 7.53(-12) 2. 2 0 ('-12)
]
- Numbers in parentheses denote exponentiation. l 1
l i. b
.\
1 0 , 6 i 6 - 25
'^ --- - _---__ _ - _ _
O 6.10.1.2 Large Pipe Break The large break for the La Crosse facility is considered to be one in which the break flow exceeds the makeup capability of the emergency core cooling systems (~1000 gpm). In this case, the systems continue to supply water to the reactor un-til the containment building is flooded to a point slightly higher than the core mid-plane. This results in a situation where the water level outside the reactor is above l the break and steam generated by decay heat is condensed by the shutdown con-denser system. Noncondensables are vented to the waste gas system where they will probably be held up in the gas decay tanks. If it is necessary for them to be released, the system is equipped with high efficiency filters as well as charcoal filters. Because of the pressurized containment building at this facility,100% mixing is assumed rather than the 50% specified in the Annex. Primary coolant inventory at 0.5% failed fuel is considered as a base line. Blowdown analyses for the double ended rupture of a recirculation line show that essentially all of the fluid flow occurs within 2 minutes and that 571,000 pounds of coolant would be released in 80 seconds. In accordance with the Annex, there are two components to the activity available for release in this situation -- that found in the coolant itself and that resulting from some postulated fuel cladding failures equivalent to 0.2% of the core. The following conditions are assumed: (a) Primary coolant activity corresponds to operation with 0.5% failed fuel; ( b) 0.2%of the core inventory of halogens and noble gases is released to the coolant; (c) Building mixing of 100% occurs; (d) A reduction factor of 0.2 is assumed for plateout, core sprays, containment sprays, etc.; and (e) The containment building leaks at 0.1% per day. The activity released from containment during a specified time period is determined from the equation: O Q"=Qc.M1} (1"-Ar9 Ar 6 - 26
l j 1 O j r where Qr = curies released during time t. l Qe = curies in containment available for release. A1 = containment leakage rate,1.16 x 10'# seed. < I A e = radiological decay constant. ,I , i Qr is determined and the releases for the periods 0-8 hours,8;24 houn/,1 -4 days, I l l 4-30 days are divided by the respective time periods to compute the release rates shown in Table 6.10-2. The contribution to the release from the postuhted fuel ; failure is negligible in comparison to the activity found in the coolant. The doses l from these releases are shown in Table 6.3-1. I l Based upon estimates of pipe failure rates contained in the literature and 1 1 upon the number of pipes which might constitute a large break, this accident repre-sents an " emergency" condition. 6.10.1.3 Instrument Line Break l There are no lines from the primary system which penetrate tile containment building and which are not provided with isolation capability inside the containment. There! ore, this accident situation is not applicable to the La Cro=se facility. 1-
-p e
- y i
I 4 sl l l 1 l r l 0 1 6 - 27
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( . sf ' ' f , [ g I , ,, ( . .'Q , i q. f e
,f Table 6.10-2: Estimated Releases for a Large Pipe Break
( . Release--Rate (Ci/ste)
, Isotope , 0-8 hr 8-24 he 1 t1 days 4-30 days I.131 2.01(-7) 1. 68 (-7) 1.58 (-7) 5.47 (-8) 1-.132 1. 08 (-7) 5. 38 (-9) - -
'I-133 3. 68 (-7) 2. 57 (-7) 7. 34 (- 8) 8. 0 (-10)
, I-134 5. 87 (-8) - - -
/ I-135 2. 45 (-7) 7. 88 (- 8) 3.86(-11) -
< .- Xe-131m 9. 7 6 (-7) 9. 7 6 (-7) 8.15 (-7) 3. 89 (-7) 1 Xe-133 1. 9', (- 4) 1. 98 (-4) 1. 58 (-4) 3. 5 6 (-5)
Xe-135m . 2.6D (-6) - - - J Xe.135 ( l.45 (-4) 5. 99 (- 5) 5. 6 (- 6) - Kr-83m ' E. 7 3 (- 6) 1. 56 (-7) - Kr-SSm 1. 9 (- 5) 3 . 42 (-6) 5. 79 (- 8) - Kr-87 2. 03 (-5) 1. 04 (-7) - - Kr-88 5. 38 (-5) 4. 51 (- 6) - - s _-. - L f l lc 2 0 ! 1 6 - 2)> l l'
O 6.10.2 Rod Drop Accident The potential rod drop accident has been discussed in Section 14.3.3 of the Safeguards Report for Operating Authorization (ACNP 65544) and in response to various questions posed by the Regulatory Staff (1-4,111-9, V-9). These analyses indicate that few, if any, fuel cladding failures will result from cny such accident, in addition, a support assembly for the rod drive mechanism housing thimbles has been incorporated as an engineered safeguard to prevent rod ejection. The control . rod drop accident is assumed to result from the separation of the rod from its drive mechanism, the removal of the drive mechanism to its fully withdrawn position with the rod remaining fully inserted in the core and falling freely frcm this position at some later time possibly due to jarring. Since cladding failures resulting from the rod drop accident are considered to be highly improbable, it is felt that use of the Annex assumptions will be a con-servative method of calculating the amount of activity released in this situation. These assumptions are as follows; (a) 0.025% of the core inventory of noble gases and halogent,are released into the coolant; (b) 1% of the hologens in the reactor coolant are released into the condenser; l (c) the mechanical vacuum purnp is automatically isolated by a high radiation signal on the steamline; and (d) radioactivity is carried over to the condenser where 10% of the halogens are available for leakage to the environment at 0.5%/ day for 24 hours. The estimated releases and associatcd doses appear in Tables 6.10-3 and 6.31, respectively. I The possibility of a rod drop accident is dependent upon the simultaneous occurrence of a number of different situations: detachment from the drive mechanism, the lodging of the rod in the core and the subsequent free fall of the rod. Although i there are a number of opportunities for detachment, there are also detection op- i O portunities and mechanisms. General Electric has reviewed actual operating experi-ence and has conservatively considered this accident as an " emergency" condition. 1 6 - 29
O ) 6.10.3 Steamline Breaks ) 6.10.3.1 Small Pipe Breaks (0.25 ft* ) The main steamline is assumed to suffer a small break (0.25 ft*) outside the l containment building. Release to the atmosphere will occur via the turbine building ventilation system through the plant stack for the 24-hour duration of the accident. The following conditions are assumed: (a) Primary coolant activity corresponds to operation with 0.5% failed fuel; i (b) A 10-second closure time for the main steam isolation valve (as in-cluded in the Tech Specs) is appropriate. This is a conservative assump-tion since purchase orders specify a 2-second closing time for these valves, and (c) Released fluid (a steam-water mixture) contains halogens at 10% of the primary coolant concentrations. A total of 7820 pounds of primary system fluid will be released prior to the j isolation valve closure. This fluid is assumed to exit totally as steam, releasing all the corresponding halogens as shown in Table 6.10-4. All no'ule gases generated during this time will also be released at the rates shown in Table 6.10-5. Other fission products are assumed to remain in the water. As noted in Category 2, a zero time noble gas release rate of 1040.pCi/sec j i is representative of about 0.1% failed fuel. Therefore, at 0.5% failed fuel as assumed l in this case, the noble gas source term is 5200 pCi/see in an equilibrium spectrum. ! The doses fiom halogen and noble gases are shown in Table 6.3-1. 1 The probability of the steamline break accident has been assigned to an ; i
" emergency" condition. The basis for this choice is the work on pipe ruptures done by General Electric Company at San Jose. (3)
O 6 - 30 l
l i i i 1 O i Table 6.10-3: Estimated Releases for a Rod Drop Accident l i s Release Rate l Isotope Core Curies Coolant Curies Condenser Curies (Ci/see) (pCi/sec) j I-131 4.16(6) 1.04(3) 1.0tt(1) 6. 07 (-7) 6. 03 (-1) j I-132 6.17 (6) 1.5tt(3) 1.54(1) 8. 93 (- 7) 8. 93 (-1) 1 I-133 9.18(6) 2. 3 (3) 2. 3 (1) 1. 33 (- 6) 1.33(0) l I-134 7.96(6) 1.99(3) 1.99(1) 1.15 (- 6) 1.15(0) I I-135 7.81(6) 1.95(3) 1.95(1) 1.13 (- 6) 1.13 (0) Xe-131m 4.18 (tt) 1.05(1) 1.05(1) 6. 09 (-7) 6. 09 (-1) Xe-133 9.22(6) 2.31(3) 2.31(3) 1. 34 (-4) 1.34(2) Xe-135m 2.33(6) 5.83(2) 5.83(2) 3. 3 8 (-5) 3.38(1) ) Xe-135 8.28(6) 2.07(3) 2.07 (3) 1. 20 (-4) 1.20(2) Kr-83m 7.74(5) 1.94(2) 1.94(2) 1.13 (-5) 1.13(1) Kr-85m 1.40(6) 3.50(2) 3.50(2) 2. 03 (-5) 2.03(1) Kr-87 3.77(6) 9.43(2) 9.43(2) 5. 47 (-5) 5.47(1) Kr-88 5.33(6) 1.33(3) 1.33(3) 7. 71 (-5) 7 71(1) I I
!1 O
6 - 31
O 6.10.3.2 Large Break The main steamline is assumed to rupture outside the containment building, releasing primary system steam to the atmosphere prior to closure of the reactor building steam isolation valve. The fMlowing conditions are assumed to occur: (a) Primary coolant activity corresponds to operation with 0.5% i failed fuel; l (b) A 10-second closure time is appropriate for the main steamline isolation valve; and I (c) 0.5% of the halogens in the' fluid exiting the break are released to the atmosphere. 4 A total of 21,720 pounds of primary system fluid is released in 10 seconds due to the rupture of the 10-inch main steamline. As discussed previously, the halogens in the fluid are assumed to be at 10% of the primary coolant concentration. Because of the larger flow, not all o: S.e released fluid is assumed to flash to steam. Therefore, only one-half of the halogens are available for release to the atmosphere as shown in Table 6.10-6. l The noble gas release rate for the large break is the same as that listed for the small break in Table 6.10-5 since the total off-gas release is assumed to es-cape through each break. Doses for these releases are summarized in Table 6.3-1. This situation is also considered on " emergency" condition as previously discussed. ; 1 O 6 - 32
Table 6.10-4: llalogens Released from a Small Steamline Break Isotope Primary Coolant Released to Turbine Release Rate * (pCi/ml) Bldg. in 10 see (pCi) (pCi/sec) I-131 1. 28 (-3) 4.54(2) 9. 08 (-1) I-133 1. 20 (-3) ' 4.26(2) 8. 52 (-1) 1 l
- Turbine Building release rate is computed as follows:
Ventilation Rate = 5 (4) efm Free Air Volume 416,255 ft 3= 2.0 (-3) see -1 I i i l 1 I 1 l i i O 1 1 6 - 33
O Table 6.10-5: Noble Gases Released from a Small Steamline Break i l Isotope Total Release Release Rate to Turbine Bldg. (pCi/sec) (pCi) i Xe-143 it. 0 (1) 8. 0 (- 2) Kr-94 9. 0 (1) 1. 8 (-1) j Kr-93 4.1(2) 8. 2 (-1) { l Xe-141 1.13(3) 2.26(0) i Kr-92 1.60(3) 3.20(0) Kr-91 2. 9t1 (3) 5.88(0) Xe-140 3.24(3) 6.48(0) Kr-90 4.26(3) 8.52(0) l Xe-139 4.60(3) 9.20(0) Kr-89 3.92(3) 7.84(0) Xe-137 5.12(3) 1.02(1) Xe-138 5.0tt(3) 1.01(1) Xe-135m 1.54(3) 3.08(0) Kr-87 2.13(3) 4.26(0) Kr-83m 4. 4 (2) 8. 8 (-1) Kr-88 2.96(3) 5.92(0) Kr-85m 1.11(3) 2.22(0) Xe .135 5.38(3) 1.08(1) Xe-133m 1.50(2) 3. 0 (-1) Xe-133 5.65(3) 1.13 (1) I Xe-131m 2. 0 (1) 4. 0 (-2) Kr-85 2.30(2) 4,6 (-1) Total 5. 2 (4) 1. Ott (2) O 6 - 34
O - l Table 6.10-6: Halogen Releases from a.Large Steamline Break l Isotope Primary Coolant Released to Turbine Bldg. Release Rate j (pCi/ml) in 10 seconds (pCi/sec) ) (pCi) l l 1-131 1. 28 (-3) 6.30(2) 1.26(0) I-133 1. 20 (-3) 5.90(2) 1.18(0) 1 J 1 l
)
1 i 1 4 1 l l 1 j l l l l O 6 - 35 l l
a I o i REFERENCES ,.
- 1. Federal Register,36FR22851, Annex to 10CFR50, Appendix D, December 1,1971. 1
- 2. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, f I Section III, (1971).
- 3. Vandenburg, S. R., " Reactor Primary Coolant System Rupture Study", Quarterly Report #22, July-September 1970, GEAP 10207-22, General Electric Company, San Jose, California. ,
l l I 1 l l
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6 - 36
--- ---^------m____._m__
O 7.0 UNAVOIDABLE ADVERSE EFFECTS The LACBWR has been in operation since 1967. There are five general ways in which this station affects the environment. All but the second of these are com-mon to any thermal generating station:
- 1. Discharge of quantities of warm turbine condenser cooling water.
- 2. Controlled release of small amounts of radioactive material to the air and water.
- 3. Discharge of some chemicals into the water.
- 4. Physical presence, i.e., aesthetics, structures, traffic, noise, etc.
- 5. Land use.
There are also the possible effects of accidents in operation and transportation of nuclear fuels and wastes. All of these possible effects, in addition to those listed above, have been described in the preceding sections of this report. In the operation of the LACBWR, heat is discharged to the waters of the Mis-sissippi River. This discharge raises the temperature of the river as is described in Section 5.1. This rise could cause a variety of changes in the species, move- . ments and diversity of aquatic life in this area. Additionally, floating aquatic - orgardsms that are transported through the condenser with the cooling water are l destroyed and small numbers of fish may be killed by impingement on intake screens. i To date, none of these possible effects has had a discernible impact on aquatic j life; there have been no changes in number and diversity of species and no fish i kills of any significance on intake screens. Thus, it must be concluded that any effects which are occurring are so small as to be undetectable and of no conse- ' quence to the nearby fishery. Radiological doses calalated for the actual releases from LACBWR are presented in Section 5.2. These calculated numbers in themselves represent an effect so small that they have no public health significance. Further, doses of the magnitude of the calculated numbers have not been detected in the environ-ment. Therefore, it would seem probable that the calculations are conservatively high since some of the numbers should be detectable. In any event, the calculated O 7-1 ! l __ ____J
'O numbers, as is pointed out above, are small and of no significance.
Chemicals 3re also released from LACBWR via the cooling water discharge. These releases are described in Section 5.3. The amounts of the chemicals re-leased are small and well within oli applicable water quality standards. The ef-fect, if any, is so small as to be undetectable. Other effects of the operation of LACBWR are inevitable. There is a certain amount of land removed from public use and there is the aesthetic intrusion of a building and transmission lines. All of these effects are described in preceding i i sections. ' i in summary, all of the effects described above are " adverse" only insofar as they are not positive. On the other hand, they are so small as to be far outweighed by the benefits of the power produced by LACBWR. If, in the future, any adverse effects attributable to plant operations are re-vealed by environmental monitoring programs or other sources, appropriate steps will be taken to correct the situation. i l I l l O 7-2
O 8.0 ALTERNATIVES TO THE PROPOSED CHANGE IN LICENSE
' The La Crosse Boiling Water Reactor is an existing station. It is evident that there are fewer feasible alternatives to the proposed change of licensing than would be available for a unit in the preconstruction phase. These alternatives include: not providing the power, purchasing power from other utilities and using alternative means of generating the required power. The environmental considera-tions entailed in these various alternatives, and the associated costs, are dis-l cussed in detail in Section 11, Benefit Cost Analysis. l Although the plant is built and in operation, it is reasonable to consider alteration of existing systems as a condition of the proposed change in license.
A discussion of alternative systems with an evaluation of their associated environ-rnental and economic costs is also contained in Section 11. ' i: i O 1 1 1 8-1
1 i
)
o , 8.1 ALTERNATIVES TO CONSTRUCTION i The LACBWR facility began operation in July of 1967. Since that time, the reactor has been critical for over 16,00r hours. The initial application for con- { i struction was filed nearly 10 years ago in October 1962. - 1 It is apparent that LACBWR is an operating facility for which there cre no ! alternatives to construction. 1 1 I I l l l 1 i O 8-2 l
\
l i O-8.2 NOT PROVIDING THE POWER As described previously, Dairyland Power Cooperative is a member of the Mid-Continent Area Power Planners (MAPP), which is a coordinating group of power producers. At present, in the MAPP group and in the Dairyland system ) there is a limited capacity in base-load units such as the LACBWR. The LACBWR is a 50 MWe installation which is interconnected to utilities i outside the Dairyland system. This is done through the Upper Mississippi Valley Power Pool (UMVPP), of wnich Dairyland Power Cooperative is a member.' Shut . j ting down the LACBWR and buying power from the poolis not a feasible alterna- ~I tive since longorm base load surplus is not available in the pool. Within Dairyland there is no surplus capacity due to Dairyland consumers, power demand and commitments to sell power to othe; pool members. After 1975, Dairyland will have insufficient capacity to meet its own power demands and must l
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buy power from some source until new generating capacity becomes available. Although the MAPP group includes., among others, all UMVPP members, it is not a formal power pool. Power may be purchased from members on an indivi-dual basis when available. No base load surplus is available now or in the fore-seeable future in the MAPP group. Even if it were, costs would be greater than l Dairyland's generation cost and would be prohibitive. l Building a new facility to replace LACBWR has been considered. A 50 MWe 1 l base load, coal-fired unit would cost approximately $25,000,000. In addition to j these costs, there would be the cost of decommissioning LACBWR. Although I decommissioning costs have not been accurately estimated, they could be as high as $1,000,000. I The loss of LACBWR would leave the Dairyland system completely without reserves and completely dependent on other members of the pool for reserve supply. It is conceivable that Dairyland could refuse to honor its selling commitments to make up for this reserve. However, since the pool does not have surplus power, this would only shift the burden to another area. It is apparent that not providing the power or ceasing to operate LACBWR O 8-3 '
l l 1 O is not a pratical alternative under present circumstances. The plant exists and represents considerable investment and development. Te cease its operations j in the absence of significant environmental effects would serve no purpose. The only other possible alternatives to the cessation of operations that can be considered are modifications of existing systems which interact with the en-vironment. These alternatives apply to radioactive releases and thermal dis-charges and are discussed in the following sections. l l l 1 l l l l \ l l I 1 l i O 8-4 i _________________j
O 8.3 RADWASTE SYSTEM ALTERNATIVES 8.3.1 Gaseous Releases Gaseous radioactive releases from the station stack do not give significant doses to hypotheticalindividuals in the environment (see Section 5.2). However, it is possible to further reduce these dose figures by modification and more ex-tensive use of the gaseous radwaste system. For example, use of the recombiner with the tanks in an unpressurized mode extends the holdup to at least three hours and reduces the dose by a factor of six. Use of the gaseous release system in a l pressurized mode increases the holdup to 72 hours and decreases the dose a factor of 50. To date, noble gas releases from LACBWR have been so low as not to war-rant use of the extended holdup. This system is intended primarily as a backup precaution against less favorable fuel operating conditions in the future. If the system were to be used continually, some redundant features such as an extra re-combiner might have to be considered for the system. The cost of the extra recom-biner would be about $ 50,000. The principal gaseous release of concern is iodine in both the off-gas and the turbine building ventilation air. As described in Section 5.2, this constitutes the critical pathway of exposure via the air-grass-milk-child thyroid exposure route. A 99% reduction of iodines from the off-gas system can be accomplished at a cost of $100,000 by tha addition of charcoal. Normally over 95% of the iodine released comes from the off-gas system. On occasion, however, the turbine building release rate has exceeded 30% of the total. The much greater volume of air discharged from i the turbine building makes iodine removal more difficult and costly. Two means of reducing this release are practical: Filtration of Ventilation Air -- This alternative would require the in-stallation of sufficient charcoal filters to handle approximately 70,000 cfm with an iodine decontamination factor of 100. Installation would be at some location before the air enters the stock. The initi:1 cost estimate for this type of an instal-lation at LACBWR is $626,500. Air-Conditioning System -- This system would involve air conditioning, O B-5 ' } i q . I
O recycling and filtering in charcoal the tu.bine building air. The design decon-tamination factor for iodine would also be 100. The approximate cost estimated for such a rystem is $422,800. Another alternative would not only result in lowered doses from the total iodine release, but also would reduce the noble gas whole body dose. This alternative is : Release of Ventilation Air from Genoa 3 Stock -- The Genoa 3 stack is 500 feet tall versus 350 for LACBWR. Use of this extra effective stack height would reduce dose by approximately a factor of 10 for noble gases and a factor of 100 for iodine. Cost of this modification is estimated to be approximately
$325,000.
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O 8.3.2 Liquid Radwaste System Alternatives Releases from the liquid radwaste system do not cause significant doses in the environment (see Section 5.2). However, it is feasible to reduce the releases further by certain system modifications. Replacement of Demineralized Resins -- The principal source of liquid radweste is water from the regeneration of demineralized resins. An alternative to regeneration is replacement. The resin used is packaged in a disposable con-toiner which is removed to storage and replaced with fresh resin. The contaminated resin cartridge is shipped off-site for burial and storage. The estimated cost of such replacement is $57,000 per year without waste solidification. On-site solidi-fication could cost as much as an additional $5,000 per year. A reduction by 75% in i liquid radwaste activity release is probable by this process. Recycling of Low-Conductivity (High Purity) Waste -- By proper segre+ gotion of radwaste piping, it is possible to segregate high-purity primary water from the radwaste streams. This segregation would allow recycling of the high-purity water back into the primary system. The resultant releases would be re-duced by on additional 10% above that accomplished by replacement of resins. Recycling is usefulin terms of waste reduction only when replacement of resins is also adopted. The cost of the necessary modifications is expected to be around l 550,000. Other Methods -- It is possible to add evaporators and/or demineralizers to the liquid radwaste system. These modifications are extensive and costly. They are not justified by the calculated doses in the environment and, hence, are not considered as an alternative. l
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O i 8.4 COOLING SYSTEM ALTERNATIVES The LACBWR facility has a common discharge with tne Genoa 3 facility. To date there have been no observable effects on the aquatic environment from the operation of both stations, it is possible to reduce the thermal effluents from the Genoa site by the ad-dition of cooling towers, either mechanical or hyperbolic. However, the costs of such towers, on the order of several millions of dollars, cannot be justified on the basis of any demonstrable benefit. Therefore, there is no necessity to consider cooling system alternatives. I l}}