ML20084H910
| ML20084H910 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 05/31/1984 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML20084H909 | List: |
| References | |
| ENVR-840531, NUDOCS 8405080260 | |
| Download: ML20084H910 (104) | |
Text
WNP-3 ER-OL AMENDMENT 2, MAY 1984 b('h INSTRUCTIONS The following is furnished as a guide for insertion of Amendment 2 sheets into the WNP-3 Environmental Report - Operating License Stage. After inserting Amendment 2, place the transmittal letter and instruction sheets in the front of the Environmental Report to maintain a record of the changes.
REMOVE OLD SHEETS INSERT NEW SHEETS Tables of Contents Page 111 Page 111 Page vii Page vii Page xi Page xi Chapter 2 Pages 2.1-1 thru 2.1-5 Pages 2.1-1 thru 2.1-5 Table 2.1-2 (4 sheets) Table 2.1-2 (4 sheets)
Table 2.1-8 Table 2.1-8 Figure 2.1-1 Figure 2.1-1
-. Page 2.2-1 Page 2.2-1 01 Figures 2.2-1 and 2.2-2 Figures 2.2-1 and 2.2-2 Page 2.3-2
- Page 2.3-2 Table 2.3-15 Table 2.3-15 Page 2.4-1 Page 2.4-1 Tables 2.4-1 thru 2.4-7 Tables 2.4-1 thru 2.4-7 Figure 2.4-11 Figure 2.4-11 i Chapter 3 Table 3.4-1 Table 3.4-1 Pages 3.5-3 thru 3.5-6 Pages 3.5-3 and 3.5-6 Pages 3.5-10 and 3.5-11 Pages 3.5-10 and 3.5-11 Tables 3.5-8 thru 3.5-11 Tables 3.5-8 thru 3.5-11 Table 3.5-16 Table 3.5-16 Tables 3.5-19 and 3.5-20 Tables 3.5-19 and 3.5-20 Figure 3.5-8 (sheet 2) Figure 3.5-8 (sheet 2)
Pages 3.6-1 thru 3.6-4 Pages 3.6-1 thru 3.6-4 l Tables 3.6-1 and 3.6-2 Tables 3.6-1 and 3.6-2 ,
Page 3.9-1 Page 3.9-1 l Figure 3.9-2 Chapter 5 Page 5.1-1 Page 5.1-1 Table 5.1-1 Table 5.1-1
/m Figures 5.1-3 and 5.1-4 Figures 5.1-3 and 5.1-4
\ Table 5.2-8 Table 5.2-8 Page 5.3-1 Page 5.3-1 Table 5.3-1 Table 5.3-1 8405080260 840D01 DR ADOCK 05000
Chapter 6 l Pages 6.1-21 and 6.1-22 Pages 6.1-21 and 6.1-22 l
Table 6.1-7 Table 6.1-7 Chapter 7 Page 7.2-1 Page 7.2-1 Table 7.3-1 Table 7.3-1 Chapter 12 l
Table 12.0-1 Table 12.0-1 I
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TABLE OF CONTENTS (contd.)
Section Title Page 6 EFFLUENT AND ENVIRONMENTAL MEASUREMENT AND MONITORING PROGRAM 6.1-1 6.1 Preoperational Environmental Program 6.1-1 6.1.1 Surface Water 6.1-1 6.1.2 Groundwater 6.1-6 6.1.3 Air 6.1-7 6.1.4 Land 6.1-14 6.1.5 Radiological Environmental Monitoring 6.1-19 6.2 Operational Environmental Program 6.2-1 6.2.1 Water Quality 6.2-1 6.2.2 Aquatic Environment 6.2-1 6.2.3 Meteorological 6.2-1 6.2.4 Land 6.2-1 6.2.5 Radiological 6.2-2 6.3 Related Environmental Measurement and Monitoring Programs 6.3-1 7 ENVIRONMENTAL EFFECTS OF ACCIDENTS 7.1-1 7.1 Station Accidents Involving Radioactivity 7.1-1 7.1.1 Trivial Incidents 7.1-2 7.1.2 Small Releases Outside Containment 7.1-2 7.1.3 Radwaste System Failure 7.1-2 7.1.4 Fission Products to BWR Primary System 7.1-4 7.1.5 Fission Products to PWR Primary and Secondary System 7.1-4 7.1.6 Refueling Accidents 7.1-6 7.1.7 Spent Fuel Handling Accidents 7.1-8 ;
7.1.8 Accident Initiation Events Considered in Design Basis Evaluation in the Safety Analysis Repost 7.1-9 7.1.9 Accidents More Severe Than Design Basis Events 7.1-12 7.2 Transportation Accidents Involving Radioactivity 7.2-1 l2 7.3 Other Accidents 7.3-1 7.3.1 Sodium Hypochlorite 7.3-1 ;
7.3.2 Diesel Oil 7.3-1 '
7.3.3 Sulfuric Acid and Sodium Hydroxide 7.3-1 l 7.3.4 Bulk Gases 7.3-1 7.3.5 Aqua Ammonia 7.3-2 l l
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l iii Amendment 2 (May 84)
WNP-3 ER-0L TABLE OF CONTENTS (contd.)
Section Title Page 8 ECONOMIC AND SOCIAL EFFECTS OF STATION OPERATION 8.1-1 8.1 Benefits of Operation 8.1-1 8.1.1 Employment and Income Benefits 8.1-1 8.1.2 Regional Benefits of an Adequate Energy Supply 8.1-2 8.2 Costs of Operation 8.2-1 8.2.1 Internal Costs 8.2-1 8.2.2 External Costs 8.2-2 9 ALTERNATIVE ENERGY SOURCES AND SITES 9.0-1 10 STATION DESIGN ALTERNATIVES 10.0-1 11 BENEFIT-COST
SUMMARY
11.1-1 11.1 Benefi ts 11.1-1 11.2 Costs 11.2-1 12 ENVIRONMENTAL APPROVALS AND CONSULTATION 12.0-1 App A WATER QUALITY CERTIFICATION AND NATIONAL A-1 POLLUTANT DISCHARGE ELIMINATION SYSTEM PERMIT App B RADIOLOGICAL DOSE CALCULATION PARAMETERS B-1 l
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WNP-3 p ER-OL b
LIST OF TABLES (contd.)
Table No. Title 3.5-6 Liquid Source Terms for Normal Operations 3.5-7 Assuaptions and Parameters Used to Calculate Releases of Radioactive Material in Liquid Effluents 3.5-8 Potentially Radioactive Emissions Release Points l2 3.5-9 Gaseous Source Terms for Normal Operations Including Anticipated Operational Occurrences 3.5-10 Assumptions Used to Calculate Gaseous Radioactivity Releases 3.5-11 Solid Waste System Influent Streams 3.5-12 Solid Waste System Influents from Evaporator Bottoms 3.5-13 Solid Waste System Influents from Spent Resins 3.5-14 Solid Waste System Influents from Spent Filter Cartridges 3.5-15 Solid Waste System Influents from Secondary Particulate Filter Sludge '
3.5-16 Solid Waste System Effluent Volumes 3.5-17 Solid Waste System Effluents from Spent Resins 3.5-18 Solid Waste System Effluents from Filter Cartridges 3.5-19 Solid Waste System Effluent from Precoat and Particulate
( Slurries, Detergent Concentrate, and ICW Conc.entrate 3.5-20 Radionuclide Process and Effluent Monitors 3.6-1 Water Quality Parameters - Intak'e and Discharge 3.6-2 Water Treatment Additives 5.1-1 Predicted Dilution Zone Boundary Temperatures Vs. Water Quality Standard 5.1-2 Thermal Tolerance of Periphyton and Phytoplankton 1 5.1-3 Thermal Tolerance of Aquatic Invertebrates 5.1-4 Critical Temperatures for Selected Salmonids 5.1-5 Acceptable Physiological Limits for Representative Thermally Sensitive Species 5.1-6 Frequency of Cooling Tower Plume Lengths Vs. Direction 5.2-1 Liquid Radionuclide Releases 5.2-2 Gaseous Radionuclide Releases 5.2-3 Average Annual Dispersion Factors (CHI /Q) 5.2-4 Average Annual Deposition Factors (D/Q) 5.2-5 Annual Dose to Biota from WNP-3 Liquid Effluents 5.2-6 Parameters to Calculate Maximum Individual Dose from Liquid Effluents O
%J vii Amendment 2 (May 84)
WNP-3 ER-OL LIST OF TABLES (contd.)
Table No. Title 5.2-7 Parameters to Calculate Individual and Population Doses from Gaseous Effluents 5.2 Estimated Maximum Annual Dose to an Individual from WNP-3 5.2-9 Estimated Annual Population Doses from WNP-3 5.2-10 Total Body Doses from Typical Sources of Radiation 5.2-11 Sumary of Annual Doses 5.3-1 Potential Change in Chehalis River Water Quality Resulting from WNP-3 Discharges 5.3-2 Lethal Concentration of Copper and Zinc for Various Life Stages of Steelhead Trout and Chinook Salmon 6.1-1 Sumary of Water Quality Sampling Program, November 1979 - January 1981 6.1-2 Sumary of Metals Monitoring Program, 1080-1981 6.1-3 Sumary of Periphyton Studies, 1976-1980 6.1-4 Sumary of Benthic Macroinvertebrate Studies, 1976-1980 6.1-5 Sumary of Bulk Precipitation, Foliar Leachate, and Watershed Stream Analysis Methodologies 6.1-6 Cooling Tower Drif t Orop Size Distribution 6.1-7 Radiological Environmental Monitoring Program Sumary of River Electrofishing and Beach Seining,
) l6.1-8 1976-1980 7.1-1 Accident Classification l
7.1-2 Core Inventory and Isotope Properties 7.1-3 Activity Released to the Environment by Accident i Classes 3-7 l 7.1-4 Activity Released to the Environment by a Small Pipe Break Accident 7.1-5 Activity Released to the Environment by a Large Pipe Break Accident 7.1-6 Activity Released to the Environment by a Control Ejection Accident 7.1-7 Activity Released to the Environment by a Steamline Break Accident 7.1-8 Sumary of Offsite Doses from Plant Accidents (Classes 3-8) 7.1-9 Rebaselined RSS PWR Accident Release Categories 1 l 7.1-10 Evacuation Parameters 7.3-1 Chemicals Stored Onsite 8.1-1 Annual Benefits Associated with Operation of WNP-3 viii Amendment 1 (Dec 82)
WNP-3 ER-0L O
LIST OF FIGURES (contd.)
Figure No. Title 3.3-1 Plant Water Flow Diagram ,
3.4-1 Schematic Diagram of Circulating Cooling Water System 3.4-2 Wet Natural-Draft Cooling Tower (Counterflow Type) 3.4-3 Natural-Draft Cooling Tower Performance Curve 3.4-4 . Schematic Cross-Sections of Diffuser 3.4-5 Location of Intakes (Ranney Collectors) 3.4-6 Ranney Groundwater Collector 3.4-7 Plan View of Discharge Diffuser l1 3.5-1 Fuel Pool Cooling and Clean-Up System Block Flow Diagram 3.5-2 Floor Drain System Block Flow Diagram 3.5-3 Detergent Waste System Block Flow Diagram 3.5-4 Inorganic Chemical Waste System Block Flow Diagram 3.5-5 . Secondary High Purity Waste System Block Flow Diagram 3.5-6 Secondary Particulate Waste System Block Flow Diagram 3.5-7 Gaseous Waste Management System Block Flow Diagram 3.5-8 (2 shts) WNP-3 Gaseous Effluent Release Points O 3.5-9 Solid Waste System Flow Diagram C/
3.9-1 Satsop Substation Integration 3.9-2 Plant-to-Substation Transmission Line (500kV) Routing l2 5.1-1 Blowdown Plume Isotherms in January with Two-Unit Operation 5.1-2 Blowdown Plume Isotherms in August with Two-Unit Operation 5.1-3 Blowdown Plume Isotherms in August with One-Unit Operation 5.1-4 Predicted Cooling Tower Drift Deposition Pattern 5.2-1 Exposure Pathways for Organisms Other Than Man 5.2-2 Exposure Pathways to Man 5.3-1 Relationship Between Hardness or Alkalinity and Copper Toxicity 5.3-2 Toxicity of Chlorine to Freshwater Organisms
- 6.1-1 Locations of Water Quality and Aquatic Ecology Sampling Stations 6.1-2 Radiological Environmental Sampling Locations 7.1-1 Block Diagram of Severe Accident Consequence Model 7.1-2 Probability Vs. Acute Fatalities xi Amendment 2 (May 84)
WNP-3 ER-OL LIST OF FIGURES (contd.)
Figure No. Title 7.1-3 Probability Vs. Latent Cancer Fatalities il 7.1-4 Probability Vs. Whole Body and Thyroid Dose 7.1-5 Probability Vs. Total Cost 7.1-6 Probability Vs. Population Whole Body Dose 1
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O xii Amendment 1 (Dec 82)
WNP-3 FO U ER-0L THE SITE AND ENVIRONMENTAL INTERFACES 2.1 GE0 GRAPHY AND DEMOGRAPHY 2.1.1 Site Location and Description 2.1.1.1 Specification of Location The Satsop site is located.in southeastern Grays Harbor County, Washing-ton, approximately one mile south of the Chehalis River near its conflu-ence with the Satsop River. The site is about 26 miles west of Olympia and 16 miles east of Aberdeen (Figure 2.1-3). The central site area lies in Section 17 of Township 17 North, Range 6 West. The Reactor Building is located at latitude 460 57' 33" N and longitude 1230 27' 58" W. The Universal Transverse Mercator coodinates are N52 00, 525m and E4 64, 517m.
2.1.1. 2 Site Area Map Figure 2.1-1 is a map showing the plant property lines and the principal plant features. Figure 2.1-2 is a map showing topography and local trans-(q) portation routes. The land owned by the Supply System in the site proper totals about 1,360 acres. The Supply System also has ownership of miscel- l2 laneous properties in the site area such as the right-of-ways of the ac-cess roads from the east and west.
2.1.1.3 Boundaries for Establishing Effluent Release Limits Boundaries for establishing effluent release limits conform to the plant property boundary and the boundary of properties encompassing the exclu-sion area (see Figure 2.1-1). Table 2.1-1 provides the distance from re-lease points to this boundary in each compass sector.
2.1.2 Population Distribution Table 2.1-2 presents, by compass segment and distance, population esti-mates for 1980 and forecasts by decade from 1990 to 2030. The table may be keyed to Figures 2.1-3 and 2.1-4 which are maps of areas within 10 and 50 miles, respectively, of the site.
Base population within the 10-mile radius of the WNP-3 was estimated by application of 1980 Bureau of Census household size figures to housing counts developed through field surveys. The area within ten miles is a rural section of Grays Harbor County with the exception of a six square mile rural area in the southwestern corner of Mason County. The 1980 pop-ulation of Grays Harbor County was 66,314, more than half of which was lo-(] cated in the Aberdeen-Hoquiam area. This is an increase of 11.4 percent
. U over the 1970 population of 59,553.(l) 2.1-1 Amendment 2 (May 84)
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WNP-3 ER-OL O~
From its early urbanizing period in the late 1800s, the county has experi-enced its major growth as a result of activity in the forest products industries. The growth of the towns within this area has been somewhat erratic following fluctuations in the industries. Trends indicate a "sub-urban shif t" of population from the urban center of the county into the smaller outlying communities and the rural area. Since 1950, Aberdeen and Hoquiam have actually declined in population while the smaller outlying communities have grown significantly. The unincorporated rural population has also grown twice as fast as the county as a whole and four times as fast as all the cities combined. The fastest growing area in the county is the Elma area, followed by the Westport-0 costa area. The north beaches are a close third. The total urban area is growing at a relatively slow pace of 1.1% per year.
The relatively unstable and limited employment in the County has caused a large emigration of people between ages 15-44 to more metropolitan areas in the Puget Sound region where there are more employment opportunities.
This emigration together with the trend of increase in the portion of the populat n) over 65 years of age will tend to stabilize population growth.
For estimating the 1980 base population in the 10-50 mile area,1980 cen-sus division boundary maps were overlaid with an appropriately scaled sec-tor / radii grid. Census data was then allocated relative to the portion of each enumeration district, census tract, block group or block which fell within individual compass sectors. The 1990 to 2030 forecasts presented here are based on several sources: 1981 county population forecasts pro-vided by the Washington State Office of Financial Management (0FM), county forecasts estimated by Bonneville Power Administration, U.S. Bureau of Census population local regional estimates planning and pg ions, and various discussions with agencies.
The 50-mile radius includes Grays Harbor, Pacific, Wahkiakum, Cowlitz, Lewis, Thurston, Pierce, Kitsap, Jefferson, and Mason Counties. Individ-ual county estimates were based on 0FM projections through the year 2000 l in order to provide a conservative and timely assessment. The BPA projec-l tions were used for comparison purposes. The 0FM population projections l were distributed within each county by compass sectors using various l regional tions from planning 2000 tocommission published 2030 relied on Bureau projections and insighM;g Projec-of Census forecasts.
A high growth scenario was applied to the rapid growth areas of Thurston and Pierce Counties, and an average growth scenario was applied to the more slowly growing areas.
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2.1.2.1 Population Within Ten Miles The 1980 population and projections by decade through the year 2030 for each of the sectors within ten miles of the plant site are listed in Table 2.1-2 which may be keyed to sectors shown in Figure 2.1-3.
The nearest incorporated communities with population exceeding 1,000 are the City of Elma, located approximately four miles northeast of the site with a 1980 population of 2,720, and the City of Montesano, ]
miles west-northwest with a 1980 population of 3,247 people.lggated 1 Of the six 80 sectors (22.50 x 1 radial mile areas) within a 5-mile radius of the site, 44 were uninhabited in 1980; it is anticipated that thev will con- l2 tinue to remain uninhabited during the period through 2030.(13,14) 2.1.2.2 Population Between Ten and Fifty Miles Population estimates and projections by decade through the year 2030 for each 22.50 sector between the ten and fifty-mile radii are presented in Table 2.1-2. The 50-mile radius encompasses a ten-county region. The counties vary from a low rural population density to a high urban popula-tion density. The economic basis of the rural counties is primarily the forest products industry. These counties include Grays Harbor, Pacific, (o
') Lewis, Wahkiakum, Mason, Cowlitz, and Jefferson. Most of these counties have experienced a stable or moderate population growth for the last 30-40 years with the exception of the last decade in which higher growth rates have occurred. In the future, it is expected that these.recent nds will continue as the rural counties expand their economic base.(
The urban counties of Pierce, Thurston, and Kitsap have high population densities and diversified economic bases. A substantial portion of indus-trialized Pierce County is located within the 50-mile radius. Pierce County has grown f aster than most of the rural countles during the 1ast ten years and it is projected to continue to grow at a substantial rate.
Thurston County is the location of the State capital. During the last ten years, this county has experienced rapid growth in response to increased government employment. It is projected that growth in Thurston County will continue to respond to activity in the State government.
Kitsap County is less populated than Thurston or Pierce Counties, although it is still considered an urban region. Only a small portion of the county falls within the 50-mile radius of the plant. During the last ten years the county has grown rapidly as a result of construction of the Tri- l1 dent Submarine Support Base. It is expected that Kitsap County will grow at a moderate rate in the future; although probably not to the extent it has in the past decade.
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2.1-3 Amendment 2 (May 84)
l WNP-3 ER-0L l
2.1.2.3 Transient Population The transient population within ten miles is composed primarily of teach-ers and students at public schools, nursing home residents, employees in l logging operations and at industrial facilities, and area hunters and fishermen. l i
Public facilities and institutions within 10 miles of the site where peo- I ple may work or reside temporarily are listed in Table 2.1-3.(16-19) 1 Also listed is the Mark E. Reed Memorial Hospital in McCleary which is I slightly outside the 10-mile radius. In 1981 this institution was li- I censed for 26 beds and had an anverage occupancy of 50% in 22 beds.(18) 1 Excepting the Cities of Elma and Montesano and the public facilities listed in Table 2.1-3, the four largest employers in the vicinity of WNP-3 are:
Employees Employer July 1981 Peak Location Elma Plywood 25 120 8 mi NE Ventron Corporation 50 75 5 mi ENE Anderson Logging Company 35 50 5 mi ENE Elma Cedar Products 20 40 5 mi ENE Logging activity can vary considerably from area to area. The approxi-mately 100,000 acres of commercial forest within the 10-mile radius are shown in Figure 2.1-6. Table 2.1-4 illustrates the number of employees which could be employed in each sector based upon an annual yield esti-mate. Since one logging operation employs approximately 10 persons, it could be assumed that approximately 12 different logging operations (or about 120 persons) could be employed during the course of one year within this 10-mile radius.
Fishing and hunting are also contributors to transient populations.
Figure 2.1-5 shows the estimated seasonal totals of big games and upland i
bird hunters within 10 miles of the site. The Chehalis River and its tributaries, the Satsop and Wynoochee Rivers, provide a number of public swimming, boating, hunting and fishing areas. Table 2.1-5 provides esti-mates of peak numbers of fishermen for areas with 10 miles of the plants.
In addition, a total of 1600 waterfowl hunters may use the 25-mile segment
- of the Chehalis River Valley over the course of the hunting season.(20)
All of these sportsmen cannot plausibly be expected to be in the area at the same time.
Table 2.1-6 lists county and state camping and fishing facilities located within 10 miles of the site. Camp Delezene, a year-round Boy Scout camp.
is located at three miles southeast of WNP-3 on Delezene Creek Road. The O
2.1-4 Amendment 1 (Dec 82)
WNP-3 (nv) ER-0L'
' Twin Harbors Boy Scout Council reports a capacity of 150 campers (staying for periods of three weeks per session) during the peak summer months of July and August. There ar in a twelve month period.(e 20)approximately 350 scouts using the facilities The Oaksridge golf course is located approximately three miles north of the plant site and borders the north side of U.S. Highway 12. The facil-ity consists of a clubhouse-restaurant and an eighteen-hole golf course.
Several mobile home parks are present within the 10-mile radius. It is difficult to determine which are considered " transient" type of facili-ties, and which would be considered permanent. With the start of con-struction of WNP-3 numerous mobile home parks have developed. Six
" trailer" parks with 72 mobile homes within the 10-mile Table 2.1-7 shows the status based on 1981 information.(raQius 20; in 1974; Figure 2.1-6 displays the various transient population generators within the 10-mile radius of WNP-3. Symbols are used to denote approximate loca-tions of the various transient populations. There are no major attrac-tants, such as resorts or convention centers, that would draw large num-bers of transients from outside the area. Most of the people involved in p the abcve activities would be included in the estimates of resident Q population .
2.1.3 Uses of Adjacent Lands and Waters As noted in Subsection 2.1.1.2, Supply System land ownership in the site proper totals about 1,360 acres. Miscellaneous properties, primarily for access roads, total about 380 acres. Approximately 450 acres in the site 2 island area were cleared and grubbed for plant construction. The land permanently occupied by the plant facilities (including WNP-5) totals about 150 acres. Land not required for operation will be revegetated to natural habitat. The Supply System has also leased a 68-acre parcel at l2 the confluence of the Satsop and Chehalis Rivers to the Washington Department of Gane to be managed as game huaitat in mitigation of riparian areas disturbed by plant construction. Figures 2.1-1 and 2.1-2 show the location of principal structures and boundaries relative to natural features and transportation routes. Table 2.1-8 provides the distances -
from WNP-3 to various activities in each sector.
The principal land uses in the site area are related timber and agricul-tural production. Virtually all the land uut to ten miles in the SE to WSW sectors is dedicated to timber production. Large areas north of the site are also owned and managed by timber companies (see Figure 2.1-6).
Agricultural activities are concer.trated in the fertile bottom lands and flood plains of the Chehalis and Satsop Rivers. Only a small percentage
. O 2.1-5 Amendment 2 (May 84)
WNP-3 ER-OL of the total land area contains soil suitable for sustained ar.d intensive agriculture. The primary products are livestock, pasture grass, field crops, and vegetable crops. Livestock generally consists of poultry, sheep, hogs, and dairy and beef cattle.
All or part of ten counties lie within 50 miles of WNP-3 (see Figure 2.1 -4 ) . Table 2.1-9 lists the agricultural output from each county. The production numbers were weighted by the fraction of the land area within the 50-mile radius of WNP-3.
Dairy operations in the area ship their milk to Northwest Dairymen's Asso-ciation, Seattle, for distribution through Safeway, Inc. Most of this milk is bottled as whole milk. The volume from dairies within 5 miles of the plant is estimated at 20,000 lbs/ day. Tf total volume produced with-in 10 miles is estimated at 140,000 lbs/ day. d)9 l l Therefore, the dairy-dilution factor for the milk produced within 5 miles of the plant is 20,000/140,000 or 0.14.
Land use in the area has been changing since construction of WNP-3 began in 1977. The rate of residential lot creation in the unincorporated areas of eastern Grays Harbor County increased by 89 percent between 1976 and 1977, and another 45 percent in 1978. Much of the development has in-volved the conversion of agricultural land to residential property. In addition to short-platting and subdivision activity in the County, re-quests for conditional use permits for gravel operations and mobile home parks have increased. Because gravel deposits underlie much of the agri-cultural land along the Chehalis River, the increased gravel extraction has usurped agricultural land uses. Between January 1973 and December 1979, the County granted 47 conditional use permits for gravel extraction on agricultural land. Approximately 55 percent of all rezones in unincorporated parts of the County during the sa q period were conver-sions from agriculture to a higher density zone. 02 /
Salmon and steelhead fishing is a major sport activity in the vicinity of the plant. Washington State Department of Fisheries (D0F) studies indi-cate that pverage sport salmon fishing success runs at about 0.055-0.065 fish / hour.t33) Fish caught range in weight from 1 to 14 kilograms.
Steelhead fishing pressure is lighter and has an even lower fish / hour catch rate. The majority of sport fish taken from the Chehalis are non-resident fish which are migrating through to spawning areas in the tribu-taries. Maximum estimated residence time that these fish spend in waters mixed with the plant discharge is one month. Catch statistics corpiled for 1978 by Washington State Department of Fisheries indicate that 2,900 salmon were taken by fishermen from the Chehaljs 81ver, 1,740 from the Satsop River and 840 from the Wynocchee River.t34) Commercial catch data for various species and water bodies are compiled by 00F. Data for the Chehalis River and Grays Harbor are listed in Table 2.1-10.
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TABLE 2.1-2
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POPULATION WITHIN 50 MILES OF WNP-3 DIRECTION DISTANCE (COMPASS (MILES) SECTOR) 1980 1986 1990 2000 2010 2020 2030 0-1 N 3 3 3 4 4 5 5 ALL OTHERS 0 0 0 0 0 0 0 SUB-TOTAL 3 3 3 4 4 5 5 CUM-TOTAL 3 3 3 4 4 5 5 1-2 N 14 16 16 17 19 20 22 NNE 3 3 3 3 3 3 3 NE 11 12 12 13 14 15 16 ENE-W 0 0 0 0 0 0 0 WNW 32 34 35 38 41 44 47 NW 31 -33 34 38 42 46 50 NNW 12 13 13 14 15 16 17 SUB-TOTAL 103 111 113 123 134 144 155 CUM-TOTAL 106 114 116 127 138 149 160 2-3 N 77 81 84 93 102 111 120 NNE 280 302 317 367 419 474 530 NE 13 14 14 16 18 20 22 ENE 105 111 115 128 140 153 166 tN E 3 3 3 3 3 3 3 (s) ESE SE 0 0 0 0 0 0 0 3 3 3 3 3 3 3 SSE-W 0 0 0 0 0 0 0 WNW 28 30 31 35 39 43 47 NW 84 89 92 103 114 125 136 NNW 204 215 222 246 269 293 316 SUB-TOTAL 797 848 881 944 1,107 1,225 1,343 CUM-TOTAL 903 962 997 1,121 1,245 1,374 1,503 3-4 N 174 183 189 209 229 249 ' 269 NNE 419 456 483 570 660 756 854 NE 716 748 770 841 910 980 1,049 ENE 100 105 109 121 133 145 157 E 20 21 22 24 26 28 30 ESE 6 7 7 8 9 10 11 SE-WSW 0 0 0 0 0 0 0 W 18 19 19 20 21 22 23
. WNW 109 115 120 135 150 165 180 t
NW 477 501 518 572 625 679 732 NNW 116 122 126 139 152 165 178 SUB-TOTAL 2,155 2,277 2,363 2,639 2,915 3,199 3,483 CUM-TOTAL 3,058 3,239 3,360 3,760 4,160 4,573 4,986
() Amendment 2 (May 84)
TABLE 2.1-2 (SHEET 2 of 4)
POPULATION WITHIN 50 MILES OF WNP-3 DIRECTION DISTANCE (COMPASS (MILES) SECTOR) 1980 1986 1990 2000 2010 2020 2030 4-5 N 61 64 66 73 80 87 94 NNE 38 51 62 96 132 172 214 NE 1,955 2,104 2,209 2,555 2,909 3,284 3,664 ENE 129 137 142 159 176 193 210 E 74 78 81 91 101 111 121 ESE 46 48 50 55 60 65 70 SE-WSW 0 0 0 0 0 0 0 W 35 36 37 40 43 46 49 WNW 356 374 387 427 466 506 545 NW 53 56 58 64 70 76 82 NNW 59 62 64 71 78 85 92 SUB-TOTAL 2,806 3,010 3,156 3,631 4,115 4,625 5,141 CUM-TOTAL 5,864 6,249 6,516 7,391 8,275 9,198 10,127 5-10 N 210 221 229 254 279 304 329 NNE 62 67 70 81 92 104 116 NE 1,462 1,552 1,615 1,820 2,027 2,243 2,459 ENE 375 403 423 489 557 629 702 E 562 594 617 690 762 836 910 ESE 267 283 295 332 369 408 447 SE SSE 119 0
128 0
134 0
155 0
176 0
198 O
221g 0
S 0 0 0 0 0 0 0 SSW 17 18 19 21 23 25 27 SW 0 0 0 0 0 0 0 WSW 3 3 3 3 3 3 3 W 1,748 1,945 2,088 2,585 3,138 3,768 4,457 WNW 4,214 4,452 4,618 5,162 5,713 6,291 6,875 NW 0 0 0 0 0 0 0 NNW 259 274 285 320 355 391 427 SUB-T0TAL 9,298 9,943 10,396 11,912 13,494 15,200 16,973 CUM-TOTAL 15,162 16,189 16,912 19,303 21,769 24,398 27,100 10-20 N 410 445 469 522 561 602 636 NNE 499 544 574 637 675 716 744 NE 1,902 2,005 2,173 2,501 2,824 3,177 3,540 ENE 2,292 2,453 2,560 2,817 3,107 3,423 3,725 E 406 430 446 468 496 526 547 ESE 2,491 2,783 2,979 3,322 3,557 3,816 4,029 SE 1,789 2,012 2,160 2,683 3,323 3,621 5,095 SSE 440 442 444 447 454 463 474 S 562 562 562 562 562 562 562 Amendnent 2 (May 84)
O
TABLE 2.1-2 Q
V (SHEET 3 of 4)
POPULATION WITHIN 50 MILES OF WNP-3 DIRECTION DISTANCE (COMPASS (MILES) SECTOR) 1980 1986 1990 2000 2010 2020 2030 10-20 SSW 811 818 824 838 854 871 888 SW 436 438 440 440 451 458 465 WSW 147 160 168 189 213 239 266 W 30,073 30,758 31,215 33,125 34,731 36,109 37,371 WNW 1,107 1,143 1,167 1,259 1,341 1,420 1,490 NW 430 444 453 486 518 549 576 NNW 50 55 58 60 75 85 96 SUB-T0TAL 43,485 45,486 46,692 50,356 53,242 56,637 60,504 CUM-TOTAL 59,007 61,684 63,604 69,659 75,011 81,035 87,604 20-30 N 42 42 42 42 42 42 42 NNE 1,019 1,110 1,172 1,301 1,379 1,448 1,506 NE 8,680 9,461 9,982 11,080 11,745 12,450 12,948 ENE 26,535 32,903 37,149 44,579 49,433 55,421 60,963 E 34,920 43,300 48,888 58,666 65,119 72,934 80,227 ESE 6,231 6,978 7,477 8,224 8,717 9,240 9,610 SE 13,210 15,191 16,512 20,145 21,354 22,635 23,540 SSE 638 676 702 758 803 851 885 S 444 444 444 444 444 444 444 SSW 1,919 1,976 2,014 2,074 2,198 2,330 2,423 SW 4,128 4,462 4,685 4,690 4,961 5,259 5,469 WSW 684 745 785 870 947 1,031 1,096 W 3,937 4,059 4,143 4,462 4,745 5,014 5,254 WNW 869 907 933 1,029 1,119 1,210 1,296 NW 667 695 714 790 859 929 995 NNW 145 146 146 148 148 148 148 SUB-T0TAL 104,068 123,095 135,788 159,378 174,063 191,386 206,846 CUM-TOTAL 163,075 184,779 199,392 229,037 249,074 272,421 294,450 30-40 N 18 18 18 18 18 18 18 NNE 1,577 2,088 2,429 3,158 3,505 3,926 4,319 NE 5,334 7,062 8,214 10,678 11,853 13,275 14,603 ENE 13,321 18,116 21,314 27,708 30,756 34,447 37,891 E 34,345 46,709 54,952 71,438 79,296 88,812 97,693 ESE 2,760 3,174 3,450 4,209 4,462 4,730 4,919 SE 12,560 1,444 15,700 19,154 20,303 21,521 22,382 SSE 1,465 1,553 1,612 1,741 1,845 1,956 2,034 S 396 396 396 396 396 396 396 SSW 269 277 282 290 307 325 338 O
Amendment 2 (May 84)
_ ~ - _ - _ _-. . - _ _ . . .
TABLE 2.1-2 (SHEET 4 of 4)
POPULATION WITHIN 50 MILES OF WNP-3 DIRECTION DISTANCE (COMPASS (MILES) SECTOR) 1980 1986 1990 2000 2010 2020 2030 30-40 SW 1,056 1,141 1,198 1,310 1,389 1,472 1,531 WSW 1,596 1,815 1,962 2,450 2,683 3,738 4,574 W 4,075 4,702 5,173 6,717 8,617 10,987 13,883 WNW 2,255 2,630 2,914 3,853 5,035 6,532 8,402 NW 46 49 51 58 63 68 73 NNW 695 753 794 930 1,075 1,235 1,406 SUB-TOTAL 81,768 91,927 120,459 154,108 171,603 193,438 214,462 CUM-TOTAL 244,843 276,706 319,851 383,145 420,677 465,859 508,912 40-50 N 3 3 3 3 3 3 3 NNE 1,817 2,364 2,750 3,575 3,968 4,444 4,888 NE 15,247 20,186 23,480 30,524 33,882 37,948 41,743 ENE 223,901 249,835 267,125 302,535 335,814 376,112 413,723 E 11,299 12,395 13,125 14,375 15,238 16,152 16,798 ESE 2,438 2,584 2,682 2,897 3,071 3,255 3,385 SE 6,619 7,015 7,280 7,862 8,334 8,834 9,187 SSE 2,741 2,905 3,015 3,256 3,451 3,658 3,805 S 1,111 1,135 1,144 1,184 1,208 1,214 1,263 SSW 1,349 1,458 1,531 1,670 1,770 1,876 1,951 SW 2,213 2,391 2,511 2,750 2,915 3,090 3,214 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 73 81 87 107 135 169 209 NW 749 854 932 1,185 1,489 1,860 2,302 NNW 548 594 627 733 847 973 1,108 SUB-TOTAL 270,108 303,800 326,291 372,656 412,126 459,591 503,587 CUM-TOTAL 514,951 580,506 646,142 755,801 832,803 925,450 1,012,499 O
Amendment 2 (May 64) 1
1 WNP-3 l ER-OL 4
TABLE 2.1-7
! MOBILE HOME PARKS AND SPACES l WITHIN 10 MILES OF WNP-3 i
Distance Direction Number of Number (Miles) (Compass Segments) Mobile Home Parks of Spaces 0-1 ALL 0 0
- 1-2 ALL 0 0 2-3 N 1 19 2-3 NNE 2 84 3-4 NW 1 12 3-4 NNE 1 45 4-5 NE 1 98(a)
! 4-5 ENE 1 19 ID) 5-6 ENE 1 36(b) 5-6 NE 2 30 i 5-6 WNW 4 63 l 6-7 NE 1 45 6-7 NNW 2 20
) 7-8 W 1 8 8-9 N 1 5 8-9 W 3 148(b)
I fD) 9-10 W 1 15 l 9-10 N J 15 4
j Total within 0-10 miles: 24 662 1
i j Source: Reference 2.1-20 1
(a)Primarily RV accommodations.
(b)0ne park divided by sector, i
!O 1
1 I
WNP-3 ER-OL TABLE 2.1-8 DISTANCE (MILES) FROM WNP-3 TO POINTS OF INTEREST Sector Resident Veg. Garden Beef Cattle Milk Cow Milk Goat N 1.0 1.0 1.7 1.2(a) __
NNE 1.5 1.5 1.6 1.5(a) __
t NE 1.6 1.6 1.6 1.7 1.7 ENE 2.3 2.3 2.2 2.6 4.1 2 E 2.7 2.7 4.2 -- --
ESE 3.9 3.9 3.9 --
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SSE -- -- -- -- --
S -- -- -- -- --
SSW -- -- -- -- --
SW -- -- -- -- --
WSW -- -- -- -- --
W 3.7 3.7 3.8 -- --
WNW l.1 1.2 1.5 1.5(a) __
NW 2.0 2.0 3.1 1.8(a) __
2 NNW l.2 1.2 2.6 1.1 4.2 l
l (a) Dairy operations.
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Q 2.2 ECOLOGY 2.2.1 Terrestrial Ecology General descriptions and data collected before 1975 on flora and fauna found in the vicinity of WNP-3 are describe ronmental Report-Construction Permit Stage. 1;n TheSection 2.7discus-following of the Envi-sions of the terrestrial ecology focuses on data collected from 1975 through 1980.
2.2.1.1 Vegetation The vegetation comunities surrounding the site can be divided into three topographic areas: upland areas, river terraces, and riparian areas along the Chehalis River and creek bottoms. In general, the site area is for-ested with some pasture and agriculture usage along the river (Figure 2.2-1). The upper creek bottoms and terraces are populated by conifers 11 and stands of second growth hardwood dominated by red alder (Alnus rubra). Mixed stands of hardwoods and conifers are found on the river terraces. On the steep upper slopes, Douglas fir (Pseudotsuga menziesii) is the dominant timber and above the 300-foot contour, nearly pure stands of conifers have develnped. Bigleaf maple (Acer macrophyllum), vine maple (Acer circinatum), willow (Salix _sy_.), black cottonwood (Populas tricho-carpa), cascara (Rhamnus purshiana), western hemlock (Tsuga heterophylla) and western red cedar (Thuja plicata) are the comon species in the area.
O d Forests in this area are generally managed so that they maintain the earlier stages of succession, because red alder is used for pulpwood and the Douglas fir for saw timber. Most of the vegetation on the site had been harvested once before and represented second growth at the initiation 2 of construction activities.
Table 2.2-1 presents a representative list of 219 plant species identified near the site, representing 165 genera and 65 families. The understories in forested areas are dominated by a dense growth of shrubs, herbaceous species, ferns and bryophytes. The principal shrub is salal (Gaultheria shallon). This straggling plant forms dense tangles in many areas. Red huckleberry (Vaccinium parvifolium), oregon grape (Berberis nervosa), and sword fern (Polystichum munitum) are also common. l1 The approach of the Terrestrial Ecology programs in 1978 through 1980 was to use intensive sampling within four small watersheds as a basis for evaluating potential impacts. The watersheds were selected to be repre-sentative of the two major habitat types surrounding the site (i.e.,
maturing second-growth coniferous forests and recent clearcuts). They were selected in matched pairs so that areas adjacent to the plant site could be compared with areas outside the influence of the plant. Two for-ested watersheds (ca}'9d treatment and control) near WNP-3 were sampled in 1978 (Figure 2.2-2).G1 The dominant species were similar in both forested areas. Sword fern (Polystichum munitum) covered 32 and 17 per-2.2-1 Amendment 2 (May 84)
WNP-3 ER-OL cent of the treatment and control forest plots, respectively. Salal was second to sword fern in cover dominance, with values of about 10 percent in both forests. Deer fern (Blechnum spicant) was third in dominance at over 6 percent in the treatment forest, but covered less than 1 percent in the control forest. Foamflower (Tiarella trifoliata) had a mean coverage of 5 percent in both forests, ranliing third in dominance in the control forest and fourth in the treatment forest. Both salal and foamflower were widely distributed in the forested watersheds. Although low in coverage, Pacific brome grass (Bromus pacificus) and immature grass plants were well-distributed only in the control forest. Seedlings of western red-cedar and western hemlock yielded low coverage and frequency values in both for-ests, but only the control forest contained seedlings of Douglas fir.
Two clearcut watersheds (called treatment and control) near WNP-3 were sampled 1978-1980 (Figure 2.2-2).(2,3,4) The treatment and control clearcut watersheds were similar in plant species coverage and frequency in 1978 through 1980. In 1980, 39 and 41 vascular plant species were 1l found in sampled areas of the control and treatment clearcuts, respec-tively. Approximately 75 percent of the plants were common to both watersheds. Pacific blackberry (Rubus ursinus) was the dominant cover species, with coverage of 40.7 and 28.3 percent in the treatment and con-trol clearcuts, respectively. Other species with relatively high cover values in both watersheds were bracken fern (Pteridium aquilinum) and com-mon velvet-grass (Holcus ar.atus). In the treatment clearcut,13 species had cover values exceeding 2 percent. Predominant among these species were thimbleberry (Rubus parviflorus), Oregon grape, pearly-everlasting (Anaphalis margaritacea), and Douglas fir seedlings. In the control clearcut,12 species had cover values exceeding 2 percent; predominant among these were hairy cat's-ear (Hypochaeris radicata), fireweed (Epilobium augustifolium), and seedlings of Douglas fir, vine maple and bitter cherry (Prunus emarginata).
In sumary, vegetation near the site can be described as follows: (1)
, within the study site vegetation is highly diverse and is no longer repre-sentative of the former climax vegetation of the Western Hemlock Zone; (2) i much of the vegetation diversity can be attributed to timber and agricul-tural practices; (3) the d:minant vegetation in the lower elevation and 1l moist areas is red alder and on the upper steep slopes and level uplands
( Douglas fir is the dominant species; (4) the forest land produces high-quality timber; (5) forest management techniques (e.g., natural and arti-ficial seeding, thinning, fertilization, etc.) are used to maintain vegetation in a state of intermediate forest succession so yields of the comercially valuable Douglas fir can be sustained; and (6) the early successional stages on the upper terraces and along the creeks result in
, 1l an interspersion of cover types ideal for some wildlife species.
l l 2.2.1.2 Wildlife l
Visual observations and consultations with State game biologists indicate that the characteristic wildlife species of the region are well represented 2.2-2 Amendment 1 (Dec 82) l
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[e ij TREATMENT CLEARCUT l jd TREATMENT FOREST 0 1000 2000 3000 4000 FEET i , , , , , , ,,
Amendment 2 (May 84) 0 500 1000 METERS WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP 3 ER OL l l ADAPTED FROM FIGURE 31 OF REFERENCE 2.2 4 TERRESTRIAL ECOLOGY SAMPLING SITES FIGURE 2.2-2
WNP-3 ER-OL O 2.3 METEOROLOGY 2.3.1 Regional Climatology The climate of the lowlands of western Washington is dominated by two large-scale meteorological f actors: the mid-latitude westerly winds and the pmximity of the Pacific Ocean. The mid-latitude westerly winds are a feature of the global climate from about 300N to 600N. The westerlies -
carry a recurring progression of low-pressure sy~ stems called synoptic storms, which develop, move east, and dissipate in the mid-latitudes. The westerlies and their associated storms are most intense in the winter months; they weaken and shift northward in the sumer months.
The Pacific Ocean moderates the seasonal and daily variability in climate as air masses move eastward over the land. Winters are warmer and sumers cooler than at other locations of the same latitude. Cloudiness and high humidities are also persistent features. The topography of Grays Harbor County does little to obstruct the eastward flow, especially at locations in the west-east trending Chehalis River Valley.
The westerlies and the proximity and exposure to the Pacific Ocean combine to cause a predominance of maritime polar air masses over the region.
Humidities are generally high in these air masses with the morning maxima usually above 90 percent. The passage of storm systems of ten includes the (n) passage of a boundary or front between the subtropical and polar air masses. The fronts are of ten indistinct and are related to broad bands of weather activity.
Winters in Grays Harbor County tend to have the worst weather of any season. The synoptic storms move repeatedly through the area, bringing continuous rain, cloudiness and windy conditions to exposed locations.
Of ten, there is persistent cloudiness for several weeks duration. Heavy snows do occur about once every two or three years. Low temperatures are in the 300F to 400F range, with little daily variation.
The sumer climate in this area reflects the weakening of the westerly winds and storms. Skies are often fair to partly cloudy and precipitation generally comes in the form of brief, rarely intense showers. Stormy cloudy conditions can dominate for several days in a row, but they are generally less pervasive or severe than in the winter months. The sumer climate is generally pleasant and mild, with daily afternoon high tempera-tures in the 700F to 800F range.
2.3.2 Local Meteorology Local meteorological conditions are described by both the onsite monitor-ing program (see Subsection 6.1.3) and longer tenn records for nearby stations. The data recorded between October 1979 and September 1981 are sumarized in this section; additional detail and interpretation are pro-vided in Section 2.3 of the WNP-3 Final Safety Analysis Report.
2.3-1
s WNP-3 ER-OL 2.3.2.1 Temperature and Dew Point 0
The long-term temperatures for the site area can be described by data reported by first-order National Weather Service st i observersatAberdeen,Elma,Oakville,andOlympiapgosandcooperative rW Monthly tem-peratures at these locations are shown in Table 2.3-1. Also listed for comparison are the average monthly temperatures observed onsite during the two-year period anding September 1981. The modersting influence of the ocean noted in Su5section 2.3.1 is obvious when temperatures at Aberdeen are compared with those for the inland locations. Psgarding extremes, the highest tempertture oi. record at Elma is a July reading of 1050F while the lowest is 00F recorded in January. The extremes of record for 2l Olympia are 1030F (July 1941) and -70F (January 1972).
Annual frequency distributions for onsite temperature versus time of day are given in Tables 2.3-2a and 2.3-2b for the two heights (10m and 60m).
Temperatures above 300C (860F) occurred about 0.3 percent of the time.
The National Weather Service Station at Olympia provides a long-term record for regional dew point and humidity data. The monthly mean values of dew point and relative humidity for Olympia are compared with the two-year means recorded onsite in Table 2.3-3. Tables 2.3-4 and 2.3-5 provide the annual frequency distributions versus hour of day for measured dew points and calculated wet bulbs, respectively, for onsite data.
The representativeness of Olympia temperature and dew point data relative to the plant site is illustrated by Table 2.3-6 which compares the monthly means for the twc locations for the same 12-month period. From this data it is seen that the site experiences slightly icwer mean maximums and higher mean minimms than Olympia. Relative hun:idities at the site are lower than those for Olympia.
2.3.2.2 Wind Speed and Direction Composite average wind rose data recordea on site at the 10-meter level from October 1979 through September 1981 are shown in Tables 2.3-7a through 2.3-71. These data illustrate the climatological phenomenon of slightly stronger winds and more frequent calms during the winter months.
The late fall and winter winds have a strong easterly component while the Spring-summer winds are dominated by the SSW direction. The annual sum-maries for each 12-month period are shown in Tables 2.3-8a and 2.3-8b.
The first year (October 1979 - September 1980) had considerably more observations of calms than did the second year. The directional distribu-tions for each year match very closely with the SSW wind predominating.
Tables 2.3-9a and 2.3-9b provide comparison of wind roses for 10m and 60m, respectively, for the two-year monitoring program. Average wind speeds at 10m and 60m were 1.5 and 3.1 m/sec, respectively. In addition to the expected higher winds, the 60m level has directional peaks in the ENE and WSW-W as compared with the singular SSW peak at the 10m level. The ENE &
direction is dominant at the 60m level during the winter months. T 2.3-2 Amendment 2 (May 84)
WNP-3 ER-OL TABLE 2.3-14 MEAN SEASONAL AND ANNUAL MIXING HEIGHTS FOR SEATTLE (a)
Time Mixing Height (m) Percent Mean Wind Speed (m/sec) of day (b) Non-P All Non-Ptc) Non-P All Winter M 626 824 49.8 5.1 6.2 A 585 718 45.8 4.7 5.4 Spring M 611 838 55.2 4.6 5.5 A 1490 1577 56.5 5.7 6.2 Sumer M 532 576 85.1 4.0 4.2 A 1398 1419 89.5 4.8 4.9 Autumn M 476 565 61.5 4.3 5.0 A 898 987 66.3 4.6 5.0 Annual M 578 705 62.8 4.5 5.2 A 1092 1175 64.5 4.9 5.4 O
(a) From Reference 2.3-7.
(b) M = Morning, A = Afternoon (c) Non-P = Non-precipitating cases, All = All cases.
Non-precipitating cases exclude those in which precipitation occurred near time of measurement and exclude those with missing data and those for which no mixing height could be calculated.
O
WNP-3 ER-OL TABLE 2.3-15 MONTHLY A'ID ANNUAL PRECIPITATION (inches) IN THE SITE VICINITY Month Aberdeen (a) Max Mean Oakville(c) Olympia (d)
Ja..uary 12.70 23.61 1.59 10.48 8.49 7.93 2l February 10.23 14.96 2.34 7.95 6.56 5.97 March 9.19 13.16 0.82 7.22 5.70 4.81 April 5.56 8.17 0.48 4.49 3.34 3.14 May 3.43 6.47 0.33 2.56 2.28 1.88 June 2.70 5.53 0.12 1.98 1.86 1.57 July 1.51 3.41 0.02 1.02 0.65 0.70 August 1.79 5.40 0.04 1.53 1.10 1.17 September 3.71 6.21 0.03 2.84 2.25 2.12 October 8.13 14.51 0.97 6.47 5.46 5.28 November 11.09 17.44 1.72 9.36 7.42 7.98 December 14.50 16.67 3.93 10.71 9.44 8.19 Annual 84.54 80.27 41.01 66.51 54.55 50.74 (a) Period of record 1931 - 1960 (b) Period of record 1940 - 1977 (c) Period of record 1931 - 1960 (d) Period of record 1941 - 1970 O
Amendment 2 (May 84)
WNP-3 l
ER-OL i 2.4 HYOROLOGY 2.4.1 Surface Water The WNP-3 project is located on a ridge 1.4 miles south of the confluence of the Chehalis and Satsop Rivers, and approximately 21 river miles (RM) ,
upstream of the Chehalis R1/er's confluence with Grays Harbor. Nominal '
plant grade is 390 ft mean sea level (MSL), about 370 ft above the Che-halis River floodplain. Makeup water for the Circulating Water System is 1 supplied from induced infiltration of surface waters and groundwater with-in the Chehalis River by Ranney collector wells located slightly more than three miles downstream from the Satsop River confluence. Blowdown from the natural-draft cooling tower is discharged to the Chehalis River through a submerged multiport diffuser located 0.5 miles downstream from the confluence (see Section 3.4). The Chehalis River watershed is shown in Figure 2.4-1, and principal hydrologic features of the site vicinity are shown in Figure 2.4-2.
2.4.1.1 Chehalis River Hydrology and Physical Characteristics The Chehalis River basin is a major river basin draining west-central Washington. The river heads in the Willapa Hills in southwestern Washing-ton, flows generally northeastward to Grand Mound, and enters into Grays Harbor at Aberdeen. The higher portions of the river basin, where the q river has an average slope of about 16 feet per mile, are rugged and Q densely forested. The slope flattens to about 3 feet per mile near the city of Chehalis and then 2 feet per mile near Satsop. The river and its tributaries have a drainage area of about 2,115 sq mi; the total area draining to the site is about 1,765 sq mi, of which approximately 300 sq mi is drainage area of the Satsop River.
A stream gage for the Chehalis River was installed and operated at the site by the United States Geological Survey (USGS) in 1977 using tempo-rary facilities (rated up to about 10,000 cfs); permanent facilities were constructed in 1981. There are no long-term gaging station records for the lower reach of the Chehalis River. However, long-term records are available for USGS gaging stations on the Chehalis at Grand Mound (1929-present) (RM 59.9), Porter (1952-1972; 1972-1979)(RM 33.3) and on the Satsop River near Satsop (1929-present)(RM 2.3 upstream from mouth).
River flows near the discharge diffuser are estimated by adding the Satsop l1 River flow to the flow in the Chehalis River at Porter or Grand Mound adjusted to the site by drainage area ratio.
The annual mean flow near the diffuser is 6,633 cubic feet per second (cfs); the monthly mean flow ranges from 806 cfs in August to 14,668 cfs 2 in January. The minimum monthly flow, 526 cfs, occurred in August 1967, while the maximum monthly flow, 40,875 cfs, occurred in December 1934.
Estimated monthly avenge flows in the Chehalis River just below the con- p' fluence of the Satsop are shown in Table 2.4-1. As indicated in the table, the flow in the river is quite variable and reflects the seasonal
/]
U rainfall distribution within the basin. Also listed in Table 2.4-1 are the record minimum monthly flows for each month. l2 2.4-1 Amendment 2 (May 84)
WNP-3 ER-OL The lowest daily flows in the site vicinity are normally expected in August and September. The one percent non-exceedence flows for these two months are 500 and 460 cfs, respectively. The once-in-10-year, 7-day duration low flow for the Chehalis River downstream of the Satsop conflu-ence is 530 cfs based on recorded flow data for the period 1930-1981 (WNP-3 FSAk Appendix 2.4A). The 7-day low-flow frequency curve is shown on Figure 2.4-3.
Floods occur in the region primarily in December and January, but damaging >
floods may occur as early as the beginning of November and as late as the end of April. The estimated momentary maximum flood flow in the Chehalis 1l River below the Satsop, 97,100 cfs, occurred on December 21, 1933. The annual momentary maximum flows from 1930 to 1979 are listed in Table 2.4-2, and a frequency analysis of flood flow data is presented in Figure 2.4-4.
The Chehalis River channel at the site is approximately 250 feet wide and varies in depth from a few feet during low flow to greater than 30 feet during flooding conditions when the entire flood plain is inundated.
Channel geometry varies considerably in the site vicinity. Figure 2.4-5 shows river cross-sections in the vicinity of the blowdown diffuser (see Subsection 3.4.4). River bed elevations near the site are variable, rang-ing from mean sea level just downstream of the Satsop confluence to ap-proximately 19 feet below MSL just upstream of the confluence. The chan-nel gradient or slope from about 10 miles upstream of the site to Grays Harbor (21 miles downstream of the site), is approximately 0.04 percent.
The Satsop River exhibits a much steeper slope which ranges from approxi-mately one percent in the vicinity of its confluence with the Chehalis River to nearly 15 percent'at its head waters in the Olympic Mountains.
The velocity of the Chehalis River is quite variable. During low-flow conditions (< 200 cfs) upstream of the Satsop confluence, velocities of less than 0.2 fps are experienced. For the reach of river downstream of the Satsop confluence, velocities increase to approximately 0.4 fps during low-flow conditions (~400 cfs) due to the 3atsop River inflow. During flood conditions ( > 30,000 cfs) channel velocities reach 6 to 7 fps.
River flow in the site vicinity may also be influenced by tidal action.
The degree of tidal effect depends on the river flow and the height of the ocean tide. The influence is most noticeable during spring high tides and low river flows, which in combination reduce and someties reverse the current velocity. During periods of high streamflow, the tidal effects on the river stage and flow are considerably less pronounced. Natural bathy-metric features also affect river flow and tidal propagation in the river; ,
a riffle area (approximately River Mile 19) reduces the effect of tidal '
propagation near the site area. In a 1975 field survey, the daily average flow ranged from 1,040 to 1,610 cfs; no reversals were observed during high tides above the riffle area, although current velocity at the riffle l was reduced to about 10 percent of its steady flow velocity.(l) In 1977, l when the daily average flow was 570 cfs, the velocity at River Mile 20.5 i was decreased to 15 percent of the steady flow speed during peak high 2.4-2 Amendment 1 (Dec 82) !
)
WNP-3 ER-OL References for Section 2.4 (contd.)
- 13. Mikels, F.C., Feasibility of a Ranney Collector Water Supply, Flink Farm, Lower Chehalis River, Washington Public Power Supply System Nuclear Project No. 3, Ranney Method Western Corporation, Kennewick, Washington, October 7,1975.
- 14. Mikels, F.C., Additional Hydrogeological Studies, Ranney Cellector Water Supply, Flink Farm, Lower Chehalis River, Washington Dublic Power Supply System Nuclear Projects Nos. 3 and 5, Satsop, dashing-ton, Ranney Method Western Corporation, Kennewick, Washingt.on, Uecember 15, 1978.
- 15. Mikels, F.C., Report on Preliminary Test, Ranney Collectar No.1, Washington Public Power Suoply System Nuclear Projects '<os. 3 and 5, Ranney Method Western Corporation, Kennewick, Washington, December 8, 1980.
i k
v l
I 2.4-9
WNP-3 ER-OL TABLE 2.4-1
SUMMARY
OF CHEHALIS RIVER FLOWS BY MONTH (a)
Average Minimum Year Of Monthly Monthly Minimum Month Flow Flow Occurrence (cfs) (cfs)
Jan 14,668 3,318 1977 Feb 13,450 3,813 1977 Mar 10,429 3,873 1941 Apr 6,841 2,707 1939 May 3,437 1,675 1939 Jun 2,039 1,094 1934 Jul 1,127 706 1951 Aug 806 526 1967 Sep 1,111 551 1938 Oct 2,752 578 1952 8,665 Nov 759 1936 g
Dec 14,663 2,913 1976 W (a) Period of record October 1929 - May 1981.
Representative of flows at diffuser location (RM 20.5).
Amendment 2 (May 84)
O
I WNP-3 ER-0L TABLE 2.4-2 ESTIMATED MAXIMUM ANNUAL FLOOD FLOW 0F THE CHEHALIS RIVER NEAR WNP-3(a)
Water Momentary Water Momentary Year Date Max. Q (cfs) Year Date Max. 0 (cfs) 1930 Feb 8, 1930 24190 1955 Nov 18, 1954 43520 1 Apr 1, 1931 38100 6 Dec 23, 1955 42300 2 Feb 26, 1932 52600 7 Dec 10, 1956 50260 3 Dec 3, 1932 42760 8 Dec 28, 1957 31610 4 Dec 21, 1933 97100 9 Jan 26, 1959 33690 5 Jan 22, 1935 81340 6 Jan 13, 1936 70000 1960 Nov 23, 1959 52600 7 Apr 15, 1937 49300 1 Feb 23, 1961 40710 2l 8 Dec 29, 1937 92610 2 Dec 23, 1961 34100 9 Feb 16, 1939 47200 3 Nov 28, 1963 38710 4 Jan 27, 1964 47630 1940 Dec 17, 1939 46110 5 Jan 31, 1965 49100 1 Jan 18, 1941 49660 6 Jan 8, 1966 39030 2 Dec 20, 1941 51720 7 Dec 15, 1966 49030 3 Feb 7, 1943 39900 8 Jan 19, 1968 58220 4 Dec 3, 1943 36750 9 Jan 7, 1969 53100 5 Feb 9, 1945 48670
'J 6 7
Dec 30, 1945 Jan 26, 1947 45250 54200 1970 1
Jan 22, 1970 Jan 26, 1971 67430 86300 8 Jan 3, 1948 39440 2 Jan 22, 1972 76370 9 Feb 23, 1949 73380 3 Dec 16, 1972 59170 4 Jan 17, 1974 72290 1950 Feb 26, 1950 60120 5 Jan 15, 1975 48400 1 Feb 10, 1951 93560 6 Dec 5, 1975 66570 2 Feb 5, 1952 39430 7 Mar 10, 1977 25960 3 Jan 31, 1953 46180 8 Dec 16, 1977 52030 4 Jan 7, 1954 48200 9 Feb 9, 1979 31560 (a) Derived from data of USGS Gaging Station on the Chehalis River at Porter or Grand Mound by the drainage area ratio plus corresponding flow in the Satsop River.
O V Amendment 2 (May 84)
WNP-3 O
ER-OL TABLE 2.4-3 CHARACTERISTICS OF STREAMS AT WNP-3 SITE Total Watershed Area Watershed Area Watershed Within Plant Clearcut from Length Area Construction 1965 - 1977 S tream (feet) (acres) Area (acres) (%) (acres) (%)
Workman 48,000 7,090 60 1.1 2,690 37.9 Stein 6,700 360 40 11.7 40 11.1 Purgatory 7,000 320 120 37.5 130 40.6 Fuller 12,300 720 230 33.3 220 30.6 Hyatt 10,000 540 60 11.1 260 48.1 Elizabeth 21,000 2,730 10 0.4 520 19.0 .
Source: Reference 2.4-3
+
0
WNP-3 ER-OL TABLE 2.4-4 SURFACE WATER AND GROUNDWATER QUALITY NEAR WNP-3 SITE (a)
Discharge Area (b) Intake Area (c) Groundwater (d)
Mean Range Mean Range Mean Range mg mg/l mg/l Calcium 0 6.2 4.2 - 8.2 6.6 4.5 - 8.4 12.1 11.0 -13.1 Magnesium D 1.9 1.5 - 2.2 1.9 1.5 - 2.4 4.3 3.9 - 4.8 Sodium D 4.3 3.0 - 5.4 4.4 3.2 - 5.4 6.0 5.6 - 6.5 Potassium 0 0.48 0.45- 0.50 0.55 0.45- 0.76 0.70 0.65- 0.77 Alkalinity (as CACO 28 20 - 34 28 14 - 38 56 51 -64 Hardness (as 3CACO )3) 29 21 - 36 29 22 - 38 54 49 -60 TSS 14.2 0 -370 1 D0 10.6 8.0 - 13.1 pH 6.5 - 7.4 6.3 - 7.5 6.6 - 7.5 gg/l gg41, ug/l 8arium T(e) 10 6 - 22 4 2 -12 0 7 4 - 12 3 2 -10 Cadmium T < 0.1 < 0.1 - 0.5 < 0.1 < 0.1 - 0.2 D < 0.1 all < 0.1 < 0.1 all < 0.1 Chromium T 1.0 < 0. 5- 2.1 1.2 < 0.5 - 10.8 0.6 < 0. 5 - 1. 2 0 0.9 <0.5- 1.3 0.6 < 0. 5 - 3.3 0.5 < 0. 5 - 1. 2 Copper T 1 1 - 2 2 <1 -
8 <1 <1 -7 0 1 <1 - 1 1 <1 -
3 <1 <1 -4 Iron T 512 200 -1260 8 61 80 -7400 16 -1 -90
/~N D 107 50 - 200 98 12 - 820 8 <1 -80 (j Lead T 0 <1 4 (1 all <
- 36 1
<1
<1
<1 all
-1
<1 Manganese T 29 11 - 80 1 <1 -4 D 9 6 - 19 <1 <1 .3 Mercury T 0.4 < 0.2 - 1.3 ( 0.2 < 0.2 - 0.7 D - -
Nickel T <1 al1 < 1 1 (1 - 14 <1 <1 -10 D <1 al1 < 1 <1 <1 - 3 <1 <1 -5 Zinc T <5 a11< 5 <5 <5 - 37 <5 <S -7 0 <5 a11< 5 <5 <5 -
9 c5 all <5 Sources: References 2.4-5 and 2.4-6 River Mile 20.5 River Mile 18 Sample well near makeup water intake wells T = total. D = dissolved O
WNP-3 ER-OL TABLE 2.4-5
SUMMARY
OF CHEHALIS RIVER TEMPERATURES BY MONTH (a)
Temperature (OF/0C) 1st 99th Month Percentile Mean Percentile January 32/ 0.0 42/ 5.6 48/ 8.9 February 34/ 1.1 42/ 5.6 50/10.0 March 39/ 3.9 45/ 7.2 53/11.7 2l April 41/ 5.0 51/10.6 60/11.7 May 50/10.0 56/13.3 68/20.0 June 52/11.1 63/17.2 75/23.9 July 58/14.a 64/17.8 78/25.6 August 60/15.6 65/18.3 78/25.6 September 53/11.7 61/16.1 72/22.2 October 41/ 5.0 53/11.7 64/17.8 g November 40/ 4.4 47/ 8.3 56/13.3 W December 33/ 0.6 42/ 5.6 49/ 9.4 Annual Mean 52.6/11.4 (a)Mean" temperature is weighted for monthly mean Porter and Satsop flow rates. Representative of temperatures at diffuser location (RM 20.5).
t Amendment 2 (May 84)
O O O
- WNP-3 ER-OL 1
] TABLE 2.4-6
- CHEMICAL ANALYSES OF Gt0VNOWATER IN THE CHEHALIS RIVER BASIN (a)
Own+r Parts Per Million Well Number at Riii.hess Iron :asitate Uniortae Nitrate Dissolved Well i Tenant (CACO3 ) (Fe) (504 ) (C1) (NO3 ) Solids Depth .
1 17/6-101 Chris Wheeler 22 0.04 4.4 3.0 3.5 67 76 I 17/6-401 City of Elma 24 0.00 2.1 4.0 1.9 58 40 17/7-7P1 Weyerhaeuser 92 1.20 -
37.0 - -
201 i Tt1ber Company 17/7-801 "
60 0.50 - 11.0 - -
141 17/7-9N1 51 0.30 -
20.2 - -
160 17/7-9N2 50-54 0.03-0.11 -
9.5-12 - -
102
] 17/7-9P1 50 0.20 -
11.0 - -
153 3
17/7-1181 Earl Richard 62 2.40 0.6 2.8 0.7 106 50 17/7-11El Robert Smith 76 0.73 0.6 3.2 0.2 119 36
- 17/7-11H1 Milton Larson 52 0.19 4.2 3.5 3.5 93 10 1 17/7-11Kl G. W. Stretter 58 0.29 4.0 4.0 0.6 108 51 17/7-11P1 Weyerhaeuser 54 0.6-1.7 -
1.2 - -
188
, Timber Company 1 17/8-14K1 50 0.30 - 12-16 - -
180 18/6-31H1 Erling Olson 52 0.33 2.6 3.5 0.1 100 98 18/12-27F1 Frank Minard 26 0.33 2.9 11.0 0.1 127 358 1
I (a) Source: Reference 2,4-11 I
l i
WNP-3 ER-OL TABLE 2.4-7 MAKEUP WELL WATER QUALITY (a)
Parameter Concentration (b)
Biochemical Oxygen Demand <1 Chemical Oxygen Demand <5 Ammonia (as N) <0.0005 Total Organic Carbon <2 tsromide 0.30 0
Color (Color(MF)
Fecal Caliform Units) (colonies /100ml <2 Fluoride 0.122 Nitrate + Nitrate (as N) 0.54 Total Organic Nitrogen (as N) <0.50 011 and Grease <l Total Phosphorus (as P) 0.240 Sulfate 2.7 Sulfide < 0.10 Surfactants (LAS-mg/l <0.01 Gross Alpha (picocuries/1) < 0.60 Gross Beta (picoeuries/1) <10 Aluminum <0.10 Boron < 0.01 Cobalt <0.001 Molybdenum <0.001 Tin <0.03 Titanium 0.018 Antimony <0.15 Arsenic < 0.001 Beryllium <0.003 Silver <0.0003 Thal 1ium 0.008 Total Cyanide <0.003 Phenol < 0.004 Iron 0.017 Maganese <0.001 Bartum < 0.10 Cadmium < 0.0001 Chromium '
0.0006 Copper <0.001 Lead <0.001 Mercury <0.0002 Nickel 0.002 Selenium <0.002 Zinc 0.005 Magnesium 4.0 fbaUnits Ranney Collector l2 of mg/l or asNo. I test of November 25, 1980.
indicated.
Amendment 2 (May 84)
O
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FLL tECAWAY408s Amte
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600-E PRE CONSTRUCTION GROUND LEVEL (MSLI s00 g00'-
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. _________- ---_______ ~~, l j PIE 20Pt.TRIC LEVEL -
,0, ____ ,,_________ _,~~~______ i ,,___ ____
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0 200' s h0' 6'0' 0 8bO' 10bO' l[00' IIbo' 1600' 1800' 20'00' 2200' 2k00' 2600' 2800' 5000' I
- Amendment 2 (*1ay 84)
.l WASHINGTON PUBLIC NUCLEA PRO E No.3 POST-CONSTRUCTION PIEZ0 METRIC LEVELS AT WNP-3 FIGURE OPERATING LICENSE ENVIRONMENTAL REPORT 2.4-11
O O O WNP-3 ER-OL TABLE 3.4-1 COOLING SYSTEM OPERATING PARAKTERS Discharge (a) Discharge (b)
Temperature Temperature w/ Heat w/ Heat Average (C) Critical (d) l Intake Water Exchanger Exchanger Wet Bulb Wet Bulb Range in AT(e) Maximum (f) Maximum (f) Maximum (f)
Month Temperature Full Time As Needed Temperature Temperature Discharge-River Blowdown Evaporation Makeup
! (OF/0C) (OF/0C) (OF/0C) (O F/
0 C) (OC) (OC) (cfs) (cfs) (cfs) l January 47.5/ 8.6 50.5/10.3 65.0/18.3 36.1/ 2.3 49.4/ 9.7 1.7-15 5.9 29.2 35.1 February 46.5/ 8.1 49.5/ 9.7 66.5/19.2 38.4/ 3.6 51.1/10.6 1.7-15 5.9 29.5 35.4 March 44.5/ 6.9 47.5/ 8.6 67.0/19.4 39.2/ 4.0 54.0/12.2 1.7-15 6.0 30.3 36.3 April 45.0/ 7.2 48.0/ 8.9 68.0/20.0 43.4/ 6.3 56.0/13.3 1.7-15 6.1 30.5 36.6 May 48.5/ 9.2 51.5/10.8 68.0/20.0 48.1/ 8.9 61.0/16.1 0-10 6.3 31.5 37.8 June 52.5/11.4 55.5/13.1 68.0/20.0 53.1/11.7 66.0/18.9 0- 8.9 6.3 32.3 38.7 July 58.0/14.4 61.0/16.1 68.0/20.0 56.1/13.4 65.4/18.6 0- 5.6 6.4 32.3 38.7 August 60.5/15.8 63.5/17.5 68.0/20.0 55.8/13.2 60.9/16.1 0- 4.4 6.3 31.5 37.8 September 62.0/16.7 65.0/18.3 68.0/20.0 52.4/11.3 62.8/17.1 0- 8.3 6.3 31.8 38.1 j October 60.5/15.8 63.5/17.5 68.0/20.0 47.3/ 8.5 56.0/13.3 1.7-15 6.1 30.5 36.6 November 56.5/13.6 59.5/15.3 67.5/19.7 40.5/ 4.7 52.9/11.6 1.7-15 6.0 30.0 30.0 December 52.0/11.1 55.0/12.8 6 6.5/19 .2 38.3/ 3.5 52.1/11.2 1.7-15 5.9 29.8 35.7 i $
(a) Heat exchanger operated to 30F approach to makeup temperature.
5 (b) Heat exchanger used only as necessary to comply with NPDES permit.
(c) Average wet-bulb temperatures at Olympia for 1948-1968.
(d) Daily critical wet-bulb temperatures at Olympia 1952-1977.
g (e) Based on minimum and maximum river temperatures (Table 2.4-5) and assuming possible operation of the supplemental heat exchanger.
Based on 40 percent relative humidity, critical wet-bulb temperatures, and operation at 6 cycles of concentration.
WNP-3 ER-OL O
TABLE 3.4-2 COOLING TOWER DESIGN PARAMETERS Wet-Bulb Temperature (a) 680F Approach to Wet-Bulb 180F Range 340F Water Flow 525,000 gpm(b)
Evaporation (maximum) 14,700 gpm Drift losses 15.8 gpm l Blowdown (maximum) 4,000 gpm (a) This wet-bulb temperature is estimated to be exceeded only 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> per year.
l (b)The maximum cooling capacity by flow rate is 503,750 gpm (15 percent over design).
l O
WNP-3 ER-OL l
m 3.5.1.3 Fuel Pool System The Fuel Pool System is designed to remove decay heat and the soluble and insoluble foreign matter from the spent fuel pool. Figure 3.5-1 presents a simplified block flow diagram of the Fuel Pool System. The detailed piping and instrument diagram is presented in Section 9.1 of the FSAR, along with the principal component design data. The radionuclide concen-trations in the fuel pool during plant operations and refueling are listed in Table 3.5-4.
The values presented in Table 3.5-4 are based on the assumption that, upon shutdown for refueling, the Reactor Coolant System (RCS) is cooled for approximately two days. During this period, the primary coolant is let down through the purification filter, purification ion exchanger, and let-down strainer prior to return to the suction of the low-pressure safety injection pumps. When continuous degassification of primary coolant is desired, the letdown flow is diverted to the gas stripper and then to the VCT prior to return to the RCS. This serves two purposes: removal of noble gases in the gas stripper to avoid large releases of radioactivity to the Reactor Building following reactor vessel head removal, and reduc-tion of dissolved fission and corrosion products in the coolant by ion exchange and filtration. At the end of about two days, the coolant above the reactor vessel flange is partially drained. The reactor vessel head is unbolted and the refueling water cavity is filled with a minimum of 470,000 gallons of water from the refueling water storage tank (RWST). l2 Q
V The remaining reactor coolant volume containing radioactivity is then mixed with water in the refueling cavity and the Fuel Pool System. After refueling, the Fuel Pool System is isolated and the water in the refueling cavity is returned to the RWST. This series of events determines the l2 total activity to the Fuel Pool System. The specific activities of the radionuclides given in Table 3.5-4 are based upon a volume of 260,000 gallons. These values will be reduced by decay during refueling as well as by operation of the Fuel Pool System.
The Fuel Pool System has two basic parts: a cooling subsystem and a cleanup subsystem. The cooling subsystem of the Fuel Pool System is a
- closed-loop system consisting of two full-capacity pumps and heat ex-changers. Water is withdrawn from the fuel pool near the surface and is circulated by pumps through a exchanger that rejects heat to the Component Cooling Water System. From the outlet of the fuel pool heat exchanger, the cooled water is returned to the bottom of the fuel pool through a distribution header.
The clarity and purity of the water in the fuel pool, refueling canal, and refueling water storage tank are maintained by the cleanup subsystem of the Fuel Pool System. The cleanup loop consists of two parallel trains of l2 equipment, which include cleanup pump, ion exchanger, filter, strainers and surface skimmer. Most of the cleanup flow is drawn from the bottom of the fuel pool while a small fraction is drawn through the surface skim-mer. A basket strainer is provided in the cleanup suction line to remove O
3.5-3 Amendment 2 (May 84)
WNP-3 ER-OL any relatively large particulate matter. The fuel pool water is circulat-ed through a filter that removes particulates larger than five microns, then through an ion exchanger to remove ionic material, and finally through a strainer, which prevents resin beads from entering the fuel pool in the unlikely event of a failure of an ion exchanger retention element.
2 The refueling water storage tanks hold a maximum of approximately 970,000 gallons with a usable volume of 826,800 gallons. At the time of refueling a minimum of 470,000 gallons of water are used to fill the reactor canal, fuel transfer canal, and refueling water cavity.
The release rates of radioactive materials in gaseous effluents due to evaporation from the surface of the fuel pool and refueling canals during refueling and normal operation are presented in Table 3.5-4.
3.5.1.4 Ventilation System Exhausts Liquid and steam leakage from various coolant and process streams can result in small quantities of radioactive gases entering the building atmospheres. These systems are described in detail in Subsection 3.5.3.1.
3.5.2 Liquid Radwaste System 3.5.2.1 System Description The Iiquid Radwaste System (LRS) collects all primary and secondary side radioactive liquid wastes and processes the wastes to permit its reuse or
, recycle within the plant. Differences in primary and secondary system l water chemistry must be considered prior to reusing liquids. Untreatable radioactive process wastes, residues and concentrates are sent to the Solid Waste System (SWS) for disposal.
l l
The LRS is divided into five subsystems. The subsystems and the sources of the water processed in each are:
Floor Drain System (FDS)
- 1) Radioactive floor drains
- 2) Component cooling water (if radioactive)
- 3) Decontamination area drains (no detergents)
- 4) Hot chemical lab drains
- 5) Primary sampling panel drains Detergent Waste System (DWS)
Il 1) Hot shower drains
- 2) Decontamination area drains (detergent solutions)
O 3.5-4 Amendment 2 (May 84)
WNP-3
/
V] ER-OL Secondary High Purity Waste System (SHP)
- 1) Turbine Building drains (high purity equipment)
- 2) Low dissolved solids (low particulate) waste Secondary Particulate Waste System (SPWS)
- 1) Low dissolved solids (high particulate) waste
- 2) Turbine Building drains (floor drains)
Inorganic Chemical Waste System (ICW)
- 1) Demineralizer regeneration chemicals
- 2) Cold chemical lab drains
- 3) Secondary sampling panel drains Radioactive liquid wastes are collected from the above subsystems and segregated based on their composition and process requirements. The LRS is capable of processing the design and anticipated off-standard system loads without affecting normal operation or plant availability. This includes leakage or spillage.due to equipment malfunction or failure. The waste quanitities that must be processed by the five subsystems are shown r3 in Table 3.5-5. The subsystems are discussed in the following paragraphs; V more detail is included in Section 11.2 of the FSAR.
Floor Drain System (FDS)
Figure 3.5-2 presents a simplified flow diagram of the FDS. The floor drain tanks accumulate that which is collected in the containment, Reactor Auxiliary Building and Fuel Handling Building floor drain sumps. Addi-tional sources of input to the FDS include the Detergent Waste System, the chemical labs, the Decontamination Sample Tank, and the Component Cooling Water System. This water is processed using filtration, organic scaven-ging, evaporation and ion exchange. Holdup is provided to store waste accumulation for an average of 14 days. The processed water is monitored and used as reactor makeup water. If the water quality does not meet the standards for reactor makeup, the water will be further processed. The radioactive concentrate produced during processing of this water is han-died by the Solid Waste System.
Detergent Waste System (DWS)
Figure 3.5-3 presents a simplified block flow diagram of the DWS. The detergent waste tanks collect water from the hot shower and hot sink l1 drains. In addition, the detergent waste tanks collect water that has been diverted from the decontamination sample tank. This water is pro-cessed by filtration and blended with the regenerative waste solutions from the Inorganic Chemical Waste System.
3.5-5 Amendment 1 (Dec 82)
WNP-3 ER-0L Inorganic Chemical Waste Syst'em (ICWS)
Figure 3.5-4 presents a simplified block flow diagram of the ICWS. The ICWS accumulates wastes from chemical lab drains and chemicals used to regenerate resins of the steam generator blowdown demineralizers and the condensate polishers. Additionally, the ICWS is used to transfer contents of ICW waste tanks to the neutralizing pond provided the tank contents are not radioactive as described in FSAR Subsection 9.2.3.2. The ICWS pro-vides means to adjust pH to expedite processir.g and to sample contents of ICW tanks for radioactivity. The ICWS processes water accumulated in the inorganic chemical waste drain tanks when the waste is radioactive or when processing by the low-volume waste treatment system (see Subsection 3.6.6) is undesirable. Processing is accomplished by filtration, evaporation, and ion exchange. Water whicr. satisfies chemical criteria is transferred to the secondary makeup water system. Water that does not satisfy these criteria will be processed further. The ICWS minimizes the volume of wastes that are handled by the SWS.
Secondary High Purity Waste System (SHP)
Figure 3.5-5 presents a simplified block flow diagram of the SHP. The SHP collects and processes water from the secondary side drains which contain low dissolved solids and particulates. The SHP also accumulates rinse water from the condensate polisher and steam generator blowdown demineralizer. This water is processed by filtration and ion exchange and, after processing, is used as secondary makeup water if chemical criteria are satisfied. If the criteria are not satisfied the water will be processed further. The system provides approximately three days 2
storage capacity. Spent resins from the SHP are processed in the Solid Waste System (Subsection 3.5.4).
Secondary Particulate Waste System (SPWS) j Figure 3.5-6 presents a simplified block flow diagram of the SPWS. The SPWS accumulates water which normally.has a high concentration of particu-l lates including backflush water from the condensate polishers, steam gen-l erator blowdown demineralizers, steam generator blowdown electromagnetic filters, water sent to the Turbine Building drains after being collected in an oil separator or sump and monitored for chemical and radiochemical contamination. Water from secondary particulate waste tanks are processed l using filtration and organic scavenging. Water which meets chemical criteria is used as secondary makeup water. Water which does not meet chemical criteria is reprocessed using the secondary high purity deminer-alizer. The system provides approximately two days storage capacity.
3.5.2.2 Radionuclide Releases i Releases to the environs of liquid radwastes are controlled and monitored to meet the concentration limits of 10 CFR Part 20 and the as low as is reasonably achievable (ALARA) criterion and the numerical guidelines of 10 CFR Part 50, Appendix I. The design release limits are based on normal O
3.5-6 Amendment 2 (May 84)
i l
k!NP-3 ER-OL The gas recombiner system effluent is then returned to the gas surge header where it reenters the system again through the gas surge tank and waste gas compressors. The gas recombiner will process until the gas decay tank pressure reaches a predetermined low level. The gas decay tank which is currently lined up to the waste gas compressors will collect the normal influents plus the hydrogen free gas recombiner effluent. When this gas decay tank is filled the process is repeated.
The gas which is in the isolated gas decay tank is allowed to decay for a period of time to reduce the activity of the gas. Source term generation l1 was conservatively based on a 90-day holdup.
The GWMS provides a means to control the discharge of gaseous waste. The operator in the WS control room discharges the gas decay tanks through a flow meter and recorder, and a radiation monitor, which automatically terminates discharge flow on high activity. The Main Control Room opera-tor must give permission to discharge activity and has overriding switches to terminate the discharge if required. The release of radioactive gases from the GWMS is controlled by the WMS operator by manually lining up the proper gas decay tank to the discharge header after sampling the tank for activity. If the activity released exceeds a predetermined setpoint, the process flow monitor automatically shuts two valves to terminate the re-lease. The procedure of sampling the gas decay tank prior to release and continuous monitoring of the release protects against operator error such as sampling one tank and lining up a different tank for discharge. The
(~3 procedure for sa@ ling and monitoring also protects against radiation V monitor malfunction since the sample prior to discharge will be repre-sentative of tank contents.
The gases which are routed to the recycle subsystem are the nitrogen cover gases in the equipment drain tank (EDT) and the reactor drain tank (RDT).
These tanks contain an initial nitrogen cover at a preset positive pres-sure. When liquid leakage enters either or both tanks it will raise the pressure of the cover gas. When the pressure reaches a specified upper limit the recycle compressor is actuated. The compressor discharges to l the nitrogen recycle tank until the pressure in the equipment drain tank and reactor drain tank reduces to the normal operating pressure. Con-versely when liquid is removed from either or tioth tanks, the cover gas pressure will drop to a lower limit. A pressure regulator valve then opens allowing nitrogen to flow into either or both tanks from the nitro-gen recycle tank. The nitrogen recycle tank is periodically sampled by the gas analyzer. In the event of hydrogen or oxygen instrusion into the
! cover gas, the nitrogen recycle tank can be manually lined up with the gas i recombiner system. The nitrogen recycle tank gas flows through a regula-tor valve into the gas recombiner system. The effluent, essentially t nitrogen, from the gas recombiner system is returned by the gas recombiner j
cogressor into the nitrogen recycle tank.
i l
3.5-9 Amendment 1 (Dec 82)
WNP-3 ER-OL Gas Collection Header (GCH)
The GCH receives low activity gases containing oxygen from aerated tanks, ion exchangers, and concentrators. Detail on the sources and volumes to the GCH is provided in Table 11.3-6 of the FSAR.
Ventilation and Exhaust Systems The major sources of building ventilation and exhaust include:
a) Reactor Building Heating, Ventilation, Air Conditioning (HVAC)
System b) Reactor Auxiliary Building HVAC System l c) Turbine Building HVAC System d) Fuel Handling Building HVAC System.
e) Exhaust from the Steam Generator Blowdown System, Condenser Vacuum System and Gland Seal System i
The Reactor Building HVAC System includes an internal containment recircu-lation system, known as the Airborne Radioactivity Removal System (ARRS).
2l The ARRS includes two separate systems, each with a 12,000 cubic feet per minute (cfm) capacity. The system is designed to reduce airborne particu-late and iodine activity within the Reactor Building and reduce discharge rates at times of purging the Reactor Building. The ARRS includes HEPA and charcoal filter beds.
During plant operation, the Reactor Building will be isolated or vented via eight-inch lines. Airborne activity can accumulate due to primary i coolant leakage. Leak rates from the coolant to the Reactor Building l atmosphere of 1.0 percent per dgy day of the iodines are assumed.U)of the Some of noble gases and the activity will 0.001 be re-percent per leased to the environment at times when the Reactor Building is vented.
Such venting is assumed to be continuous at 2500 cfm. It is also assumed that during venting the Reactor Building atmosphere is passed through the ARRS continuously. During venting the release passes through HEPA and charcoal filters prior to discharge to the plant vent stack.
During shutdown, the containment is assumed to be continually purged
! through 48-inch purge lines. The radionuclide release rate from purging during shutdown is processed through HEPA and charcoal filters prior to discharge to the plant vent stack.
The HVAC exhaust from the RAB is discharged through the RAB exhaust fil-ters. The Turbine duilding and the Fuel Handling Building HVAC exhaust are normally released unfiltered due to their very small potential for contamination from radioactivity. Capability for filtration of Fuel Handling Building exhaust, in the event of an accident, is provided.
O 3.5-10 Amendment 2 (May 84)
WNP-3 l ER-OL 1
O Additional potential sources of airborne radioactivity are: the non-condensible gases exhausted from the Steam Generator Rlowdown System, Con-l 1
denser Vacuum System, and Gland Seal System. Non-condensible gases from the main condenser and from the Gland Seal. System are removed by the Con-denser Mechanical Vacuum Pumps and passed through a demister, prefilter, charcoal adsorber, and an after-filter at a rate of 60 scfm (holding), and 5500 scfm (hogging).
The release points for all sources of gaseous effluents described above are shown in Figure 3.5-8. For the radioactive release points, more i specific information, including vent elevation, diameter, flow rate, 2 temperature, and area or system ventilated, is given in Table 3.5-8. r 3.5.3.2 Radionuclide Releases 9
The numerical design objectives for gaseous releases from the plant during normal operations, including anticipated operational occurrences, are based on 10 CFR Part 50, Appendix I which mandates:
a) The calculated annual air dose due to gama radiation at or beyond the site boundary is not to exceed 10 millirads.
b) The calculated annual air dose due to beta radiation at or beyond the site boundary is not to exceed 20 millirads.
A c) The calculated annual total quantity of radioactive gaseous V effluent will not cause an estimated annual dose te any individ-ual in an unrestricted area in excess of 5 mrem to the whole body.
i
' d) The calculated annual total quantity of all radioactive iodine and radioactive material in particulate form will not result in an annual dose to any individual in an unrestricted area from all
! pathways in excess of 15 mrem / year to any organ.
i i
Compliance with these criteria, and the cost-benefit criteria of Appen- ,
dix I was provided as testimony at the June 1975 Environmental Hearings
, and additional material was provided in Supplement No. 6 to the ER-CP. ,
This material demonstrated that individual dose criteria were limiting.
The results of the GALE code analysis for gaseous source terms are pro-vided in Table 3.5-9. Assumptions and parameters used as input to the GALE code is provided in Table 3.5-10. An evaluation of compliance with the Appendix I criteria is included in Section 5.2.
l ,
I 3.5.4 Solid Waste System i
[ The Solid Waste System (SWS) collects, processes, packages, and stores
! prior to transport to an offsite burial facility any disposable wet or dry i solid radwaste generated in the operation of the plant. Types of wastes, ,
l quantities (maximum and expected volumes), activities, and radionuclide '
!O
- 3.5-11 Anendment 2 (May 84) f
WNP-3 ER-OL distributions are given in Tables 3.5-11 through 3.5-15. Figure 3.5-9 is a simplified block flow diagram of the SWS. Additional detail on the system is included in Section 11.4 of the FSAR.
The SWS handles liquids and slurries to be solidified and packaged by col-lecting them in the appropriate treatment tanks. These liquids and slur-ries (wet solid wastes) are processed and pumped to a mixer where they are combined with a solidification agent and are discharged into liners or 55-gallon drums. Solid disposable wastes are compressed into 55-gallon drums by a hydraulic compactor. The liners and drums are then stored in the onsite temporary storage area. After sufficient decaying time has elapsed, the liners or drums are shipped offsite to a burial f acility.
Spent filter cartridges are transferred to the drumming station in a cask especially designed for this purpose. At the druming station each car-tridge is transferred into a liner and solidified with waste and the solidification agent.
The concentrate storage tank receives and stores concentrate from the floor drain evaporator. Concentrate from the boric acid evaporator is collected in the concentrate storage tank only if the concentrate is not suitable for recycle to the Chemical and Volume Control System (CVCS).
Exhausted resins from ion exchangers in the CVCS, the Fuel Pool Cooling and Cleanup System, and the LRS are sluiced to the spent resin tank. The concentrate storage tank and the spent resin tank both transfer their waste to the dewatering tank. The dewatering tank feeds, by means of the resin metering pump, the cement-solidification agent waste mixer at fill-head station B. The secondary particulate pre-treatment hopper receives the secondary particulate filter discharge and suitable quantities of inorganic chemical waste evaporator bottoms (concentrate) and/or detergent waste. The resultant waste mixture is transf erred to the cement-solidifi-cation agent-waste mixer at fillhead station A by means of the particulate metering pump. The Volume Reduction System (VRS) collects and concen-trates the inorganic chemical concentrator bottoms and detergent wastes.
The waste is fed to the cement-solidification agent-waste mixer at fill-head station A by means of.the VRS hopper metering pump. There is a ,
cross-tie between the trains feeding stations A and B before the cement-solidification agent-waste mixers. Thus flexibility of controlling the final volume and activity of the solidified waste is provided.
The spent resin dewatering tank, the secondary particulate pre-treatment hopper and the VRS hopper are used primarily for waste processing and not for waste storage. Desired volumes of resins, concentrates, and sludges can be transferred to these process tanks and the waste conditioned for processing and solidification. The volume per batch depends on the size of the container used and the number of containers to be filled, however, the batch size is normally limited by the size of the soent resin de-watering tank or the secondary particulate filter pre-treatment hopper and VRS hopper. After producing a desirable mixture of wastes, the operator can set the total amount and rate of feed for both the waste and solidi-fying agent.
3.5-12
j o o o WHP-3
- ER-OL TABLE 3.5-8
, POTENTIALLY RADI0 ACTIVE EMISSIONS RELEASE POINTS Release Eleva tion Inside Flow jl Point (ft MSL) Diamet_er (f t) , Rate (cfm) Temperature (*F) Systems / Components Exhausted 1 501.0 8.50 76,200 (min) 60 (min) RAR Main Ventilation, DG Area Ventilation, 199,550 (max) 115 (max) RR Ventilation, Shield Building Annulus
! Vacuum Maintenance Containment Purge, Mechanical Vacuum Pumps 2 483.3 5.50 4,800 (min) 60 (min) Control Room Ventilation, Electric Battery 50,200 (max) 104 (max) Room Ventilation 3 483.3 5.50 4,800 (min) 60 (min) Control Room Ventilation, Electric Battery l
50,200 (max) 104 (max) Room Ventilation 4 502.8 9.17 76,310 (min) 60 (mfn) RAB Main Ventilation, DG Area Ventilation.
228,355 (max) 104 (max) Shield Building Annulus Vacuum Maintenance,
- FHB Ventilation b
0 l l 1 :
i N
^
i 1
x f
i
)
i I
l
WNP-3 ER-OL TABLE 3.5-9 GASEOUS SOURCE TERMS FOR NORMAL OPERATIONS INCLUDING ANTICIPATED CPERATIONAL OCCURRENCES (a)
Release Rate (Ci/yr)
Primary Secondary Blowdown Air Coolant Coolant Gas Stripping (b) Building Ventilation Vent Ejector Nuclide (uCi/gm) (uCi/gm) 3hutdown Continuous Reactor Auxiliary Turbine Offgas Exhaust Total Kr-83M 1.937E-02 4.671E-09 0.(c) 0. 2.0E+00 0. O. O. O. 2.0E+00 Kr-85M 8.500E-02 2.091E-08 0. O. 1.4E+01 2.0E+00 0. O. 1.0E+00 1.7E+01 Kr-85 2.347E-03 5.737E-10 1.0E+00 2.7E+02 2.0E+00 0. O. O. 0. 2.7E+02 Kr-87 5.798E-02 1.350E-08 0. O. 3.0E+00 1.0E+00 0. O. O. 4.0E+00 Kr-88 1.721E-01 4.133E-08 0. O. 2.0E+01 4.0E+00 0. O. 2.0E+00 2.6E+01 Kr-89 5.354E-03 1.309E-09 0. O. O. O. O. O. O. O.
Xe-131M 6.065E-03 1.492E-09 0. O. 4.0E+00 0. O. O. O. 4.0E+00 Xe-133M 4.270E-02 1.051E-08 0. O. 2.5E+01 0. O. O. O. 2.5E+01 Xe-133 1.803E+00 4.373E-07 0. O. 1.2E+03 3.8E+01 0. O. 2.4E+01 1.3E+03 Xe-135M 1.367E-02 3.304E-09 0. O. O. O. O. O. O. O.
Xe-135 2.073E-01 5.017E-08 0. O. 5.8E+01 4.0E+00 0. O. 3.0E+00 6.5E+01 Xe-137 9.629E-03 2.335E-09 0. O. O. O. O. O. O. O.
Xe-138 4.617E-02 1.099E-08 0. O. O. O. O. O. O. O.
Total Noble Gases 1.7E+03 I-131 3.089E-01 7.072E-06 0. O. 2.1E-02 4.9E-03 3.8E-04 0. 3.1E-03 2.9E-02 I-133 4.263E-01 9.301E-06 0. O. 1.8E-02 6.8E-03 5.0E-04 0. 4.2E-03 3.0E-02 Tritium Gaseous Release 1400 Ar-41 25 C-14 8 O O O
l l
WNP-3 ER-OL TABLE 3.5-9 (contd.)
Release Rate (Ci/yr) l Waste Gas Building Ventilation Nuclide System Reactor Auxiliary Total Airborne Particulate Mn-54 4.5E-05 2.2E-04 1.8E-04 4.5E-04 Fe-59 1.5E-05 7.4E-05 6.0E-05 1.5E-04 Co-58 1.5E-04 7.4E-04 6.0E-04 1.5E-03 l1 Co-60 7.0E-05 3.3E-04 2.7E-04 6.7E-04 Sr-89 3.3E-06 1.7E-05 1.3E-05 3.3E-05 l
Sr-90 6.0E-07 2.9E-06 2.4E-06 5.9E-06
- Cs-134 4.5E-05 2.2E-04 1.8E-04 4.5E-04 Cs-137 7.5E-05 3.7E-04 3.0E-04 7.5E-04 (a)At 0.12% failed fuel as derived from Reference 3.5-1.
l (b)The actual gas release point is the waste gas decay tanks.
l (c)0. indicates release is less than 1.0 Ci/yr for j noble gas, 0.0001 Ci/yr for iodine.
l l
l Amendment 1 (Dec 82) l 0
WNP-3 ER-OL TABLE 3.5-10 ASSUMPTIONS USED TO CALCULATE GASEOUS RADI0 ACTIVITY RELEASES Continuous stripping of full letdown flow 2l Flow rate through gas stripper (gpm) 74 Holdup time for Xenon (days) 90 Holdup time for Krypton (days) 90 Fill time of decay tanks for the gas stripper (days) 90 Primary coolant leak to Auxiliary Bldg (lb/ day) 160 Auxiliary Building leak Iodine partition factor 0.0075 Gas Waste System Particulate release fraction 0.0100 Auxiliary Building Iodine release fraction 0.1000 Particulate release fraction 0.0100 6
2l Containment volume (10 cuft) 3.405 Frequency of primary coolant degassing (times /yr) 2 Primary to secondary leak rate (lb/ day) 100 There is a kidney filter Containment atmosphere cleanup rate (thousand cfm)
Cleanup filter efficiency Iodine 11.5 0.9000 g
Particulate 0.9900 Cleanup time of containment (hours) 16 Iodine partition factor (gas / liquid) in steam generator 0.0100 Frequency of containment high-volume purge (times /yr) 4 Containment high-vol purge Iodine release fraction 0.1000 Particulate release fraction 0.0100 Containment low-volume purge rate (cfm) 2500 Iodine release fraction 0.1000 Particulate release fraction 0.0100 Steam leak to Turbine Bldg (lb/hr) 1700 Fraction of Iodine released from blowdown tank vent 0.0 Fraction of Iodine released from main condenser ejector 0.1 No cryogenic off-gas system Amendment 2 (May 84)
WNP-3 ER-OL TABLE 3.5-11 l
SOLID WASTE SYSTEM INFLUENT STREAMS Source Form Ouantity(a)
(ft3 /yr)
Spent Resins CVCS(b)C(bihgmical and Volume Control Dewatered 180 Fuel Pool Dewatered 180 Floor Drain System (c) Dewatered 80 Secondary Liquiq Treatment Systems (c) Dewatered 80 Organic Traps (c; Dewatered 60 Condensate Polishers (d) Dewatered 500 Riowdown DemineralizersId) Dewa tered 100 Evaporator Bottoms Floor Drainsie) 12 percent Na2B047 2,930 ICW (Inorganic Chemical Waste)f f) 15 percent Na2SO4 5,000 CVCS (Boric Acid Concentrator)(9) 12 percent H 3B03 1,800 l2 Fil ters Sludge Precoat and Particu- 120 O Cartridges lates in slurry 43 cartridges 101 Compressible Solids Plastic, Rags, Paper,11,000 etc.
Detergent Waste (h) Laundry Waste 40,000 Non-Compressible Solids Tools, etc. 3,000 l2 (a) Bases for Values: Maximum annual volumes; normal operation, in-cluding anticipated operational occurrences. Expected annual volumes are inputs from the primary side treatment systems excluding the 12 percent boric acid concentrate.
(b)Normally changed during annual refueling.
(c)Normally changed twice per year.
(d) Reference 3.5-3.
(e) Based on volume reduction ratio of 50.
If) Based on volume reduction ratio of 20.
(9) Assuming five percent of the boric acid concentrator thoughput is concentrated to twelve percent boric acid for disposal.
(h) Total volume collected in Detergent Waste System.
Amendment 2 (May 84)
l WNP-3 ER-0L 1
TABLE 3.5-12 SOLID WASTE SYSTEM INFLUENTS (CURIES / YEAR)
FROM EVAPORATOR BOTTOMS Ol 1
Floor Drain Boric Acid l Nuclide Evaporator .ICW Evaporator Evaoorator H-3 4.23E-00 1.46E-00 5.1E+01 Br-84 ** ** 1.3E-05 l
'. -129 4. 90E-06 ** **
I-131 1.72E+02 3.78E-00 2.3E-01 I-132 2.84E-03 4.68E-04 2.1E-03 I-133 1.88E+01 7.08E-01 6.5E-02 I-134 ** ** 3.8E-04 I-133 9.26E-01 5.14E-02 1.1E-02 Rb-88 ** ** 2.7E-04 Rb-89 ** ** **
Sr-89 4.55E-01 7.01E-03 5.1E-04 Sr-90 2.37E-02 3.34E-04 1.7E-05 Sr-91 3.86E-03 1.79E-04 5.5E-05 Y-90 9.79E-04 3.05E-06 1.2E-04 Y-91 2.26E-01 3.46E-04 3.4E-03 Zr-95 6.73E-01 8.29E-03 4.2E-03 Mo-99 4.51E-01 1.39E-01 1.7E+00 Ru-103 7.51E-01 1.18E-02 6.2E-05 Ru-106 1.90E-01 2.71E-03 4.9E-05 Te-129 1.34E-00 2.15E-02 1.7E-05 Te-132 7.53E-00 2.22E-01 1.3E-02 Te-134 ** ** **
Cs-134 3.45E+01 4.89E-01 1.4E-02 Cs-136 2.03E+01 3.85E-01 5.2E-03 Cs-137 1.39E+02 1.97E-00 1.0E-02 Cs-140 ** ** **
Ba-140 5.30E-01 1.02E-02 2.3E-04 La-140 6.85E-02 2.34E-03 4.6E-05 l Pr-143 4.06E-01 7.67E-02 5.3E-05 Ce-144 4.49E-01 6.45E-03 5.3E-05 l Cr-51 5.37E-02 8.81E-05 2.5E-04 Mn-54 1.48E-03 2.12E-06 5.1E-05 l Co-58 1.23E-01 1.86E-04 2.3E-03 Co-60 1.51E-02 2.14E-05 3.3E-04 Fe-59 7.08E-04 1.10E-06 1.4E-04
- Denote nuclide activity less than 1.0E-06 Curies / year.
O
l l WNP-3 l ER-OL O TABLE 3.5-15 SOLID WASTE SYSTEM INFLUENTS (CURIES / YEAR) FROM SECONDARY PARTICULATE FILTER SLUDGE Nuclide Activity Cr-51 3.36E-05 Mn-54 7.42E-07 ,
Co-58 6.68E-05 l Co-60 7.44E-06 !
Fe-59 4.04E-07 Zr-95 3.45E-07 O .
1 4
e 1
i
]
4 J
4
=-e -, ,-v _. . w = m ye n w m w-ree
WNP-3 ER-OL TABLE 3.5.16 SOLID WASTE SYSTEM EFFLUENT VOLUMES Ouantity (ft /yr)
Type of Waste Form Expected Maximum Spent Resins Solidi fied 650 1760 Evaporatcr Bottoms Floor Drain Solidi fied 4395 4395 ICW Solidi fied 7500 7500 2l CVCS Solidi fied 2700 Fil ters Backflush Solidi fied 180 180 Cartridges Solidi fied 162 162 Compressible Solids Compressed in drums 2750 2750 (Compaction factor = 4)
Detergent Concentrates Solidified (a) 1200 1200 2l Non-Compressible Solids Packed in drums 3000 3000 (a) Based on a volume reduction factor of 50 for volume reduction unit.
O Amendment 2 (May 84)
WNP-3 ER-0L TABLE 3.5-19 SOLID WASTE SYSTEM EFFLUENT (MICR0 CURIES / GRAM)(a) FROM PREC0AT AND PARTICULATE SLURRIES, DETERGENT CONCENTRATE, AND ICW CONCENTRATE Nuclide Normal Operation Nuclide Design Basis Br-83 *(b) Br-84
- Br-84
- I-129 1.64E-12 l2 I-130
- I-132
- I-133
- I-133
- I-134
- I-134
- I-135
- I-135
- Rb-88
- Rb-86 4.33E-12 Rb-89
- Rb-88
- Sr-89 1.62E-08 Cs-134 1.27E-05 Sr-90 6.09E-09 Cs-136 3.29E-11 Sr-91
- Sr-89 1.28E-09 Y-91 3.22E-09 Sr-90 4.35E-10 Zr-95 5.94E-08 s Sr-91
- Ru-103 1.60E-08 Y-91M
- Ru-106 4.73E-06 Y-91 3.27E-10 Te-129
- Y-93
- Te-132
- Zr-95 2.12E-08 Te-134
- Nb-95 5.44E-08 Cs-134 3.49E-05 Mo-99
- Cs-136 1.54E-10 Tc-99M
- Cs-137 7.93E-05 Ru-103 5.84E-09 Cs-138
- Ru-106 1.81E-06 .Ba-140 1.19E-11 Ru-103M
- La-140
- Te-125M 1.43E-10 Pr-143 2.93E-12 Te-127M 3.66E-09 Ce-144 8.92E-06
- Te-127
- Cr-51 9.37E-10 Te-129M 1.31E-09 Mn-54 1.92E-07 Te-129 * . Co-58 3.05E-07 l Te-131M
- Co-60 2.45E-06 Te-131
- Fe-59 2.80E-06 l2 Te-132 Fe-55 6.38E-08 Total 1.31E-04 O Amendment 2 (May 84) d
l t
f WNP-3 ER-OL TABLE 3.5-19 (contd.)
Nuclide Normal Operation Ba-140 4.74E-13 La-140
- Ce-141 6.19E-11 Ce-143
- Ce-144 3.41E-06 Pr-143 2.06E-13 Pr-144
- Np-239
- Cr-51 9.37E-10 Mn-54 7.96E-08 Fe-55 6.38E-08 Fe-59 2.80E-09 Co-58 1.94E-07 Co-60 9.92E-07 Total 4.56E-05 (a) Based on 6-months decay of input activities and mixed with (b) one-third volumeless
- denotes activity of solidification than 1.0E-20.material.
Amendment 2 (May 84)
O
O O O WNP-3 ER-0L TABLE 3.5-20 RADIOLOGICAL PROCESS AND EFFLUENT MONITORS Monitor Function Component Cooling Water Monitor (2 ea)' Detect leakage into component cooling water system.
335-ft (elev) level 'of Fuel Handling Bldg (FHB) Diagnostic, indicating need for addition surveys.
Service Water Monitor (2 ea) Detect leakage from component cooling water system.
335-ft level of FHB Diagnostic, indicating need for addition surveys.
Steam Generator Blowdown Monitor Detect small primary to secondary leakage through
] 402-ft level of RAB steam generators. Diagnostic tool.
i CVCS Preholdup Monitor Indicates activity reactor coolant from gas stripper 362-ft level of RAB before routing to holdup tanks. Exceedence of set-points indicates need for additional surveys.
CVCS Letdown Monitor Detect increased activity in reactor coolant.
I 373.5-ft level of RAB Exceedence of setpoints indicates need for addi-tional surveys.
! FHB Airborne Radiation Monitor Detects activity in FHB indicating need for verifica-2] 417-ft level of RAB tion or additional surveys on set point exceedence.
p Containment Atmosphere / Purge Detect activity in either containment atmosphere m Airborne Radiation Monitor (2 ea) or containment purge to identify leakage sources.
- j. 21 362.5-ft level of RAB k Steam Generator Blowdown Area Mcnitors (2 ea) Detect primary ta secondary leakage. Setpoint ,
j m 417.5-ft level of RAB exceedence indicates need for additional surveys.
l -
Indicates need to isolate steam generator with high j [ leak rate.
i I
~
Refueling Pool Area Monitors (4 ea) Provides alarm for evacuation of refueling pool area i on walls of refueling pool and automatically isolates containment purge lines.
l l
WNP-3
, ER-OL TABLE 3.5-20 (contd.)
l Monitor Function Spent Fuel Pool Area Monitors (4 ea) Provides alarm for evacuation of spent fuel pool area 425-ft level of FHB and isolates FHB ventilation system.
Plant Vent Radiation Monitors Sample and monitor particulates, sample halogens 1 for each of 4. plant vents (iodine), and monitor radioactive gases in effluent i air. Alarm setpoints to prevent concentrations in x excess of 10 CFR 20 limits. Alarm indicates need for additional surveys.
Administration Building Discharge Monitor Same as vent radiation monitors.
2l 40S-ft level of Admin Bldg Condenser Mechanical Vacuum Pump Discharge Monitor Samples for particulates and halogens and monitors 390-ft level of Turbine Bldg radioactive gas content. Alarm setpoints to prevent concentration in excess of 10 CFR 20 limits.
Waste Gas Discharge Monitor Provide record of activity released during waste gas 362.5-ft level of RAB discharge. High alarm terminates discharge. Set-points established to prevent concentrations in excess of 10 CFR 20 limits.
Auxiliary Condensate Flash Tank Monitor Detect in-leakage to auxiliary steam system and alert
$" to the need for additional sampling.
E i Waste Management System Discharge Monitor Provide record of activity released from waste
@ 390-ft level of TB management system. If activity exceeds setpoint,
- established to prevent concentrations in excess of
" 10 CFR 20 limits, discharge is automatically 2 terminated.
O m Connon Plant Effluent Monitor Provides record of radioactivity in common liquid 8 outside building effluents. Alarm indicates need for additional analyses and/or cessation of discharge.
O O 9
O O O WNP-3 ER-OL TABLE 3.5-20 (contd.)
Monitor Function l'
Sump and Secondary High Purity Discharge Monitor Provides record of activity in Sumps Nos. 2 and 10 outside building and the secondary high purity water discharge.
Alarm setpoints established to prevent concentra-tions from exceeding 10 CFR 20 limits.
Neutralization Pond Influent Monitor Provides record of activity in discharge to 362.5-ft level of RAB neutralization pond. Alarm, with setpoints to prevent concentrations in excess of 10 CFR 20 limits, indicates need for additional sampling.
High radiation alarm terminates discharge to pond.
Groundwater Drain Area Monitor Provides record of activity in the RAB foundation
, drain. Setpoints as close as practicable to natural background. Alarm indicates need for additional samples to determine reason for alarm.
Steam Generator Blowdown Flash Tank Provides indication and record of contamination of Vent Monitor the Secondary Steam System due to in-leakage of primary coolant and the potential for release through the Flash Tank Vent. Setpoints as close as i
E practicable to plant background. Alarm indicates j
need for additional sampling and further action.
2 l f+ Steam Seal Gland Steam Condenser Provides indication and record of contamination of m Exhaust Radiation Monitor the Secondary Steam System due to in-leakage of j gin primary coolant and the potential for release 1
- through the steam seal gland steam condenser vent.
! Setpoints as close as practicable to plant back-2
~
I ground. Alarms indicate need for additional l sampling and further action.
j
WNP-3 ER-OL TABLE 3.5-20 (contd.)
Monitor Function Auxiliary Condensate Flash Tank Monitor Provides indication and record of contamination of the Auxiliary Steam System due to in-leakage of various radioactive systems and the potential for release via various vents in the Auxiliary Steam and Condensate System. Setpoints as close as practic-able to plant background. Alarm indicates need for 2
additional sampling and further action.
Hot Machine Shop Discharge Sampler Provides representative sample of particulates and halogens (iodine) entrained in air discharged from the Hot Machine Shop. Samples are available for later laboratory analysis.
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I Releas2 Point N:rmal Rel:ase E11vaticn Flow Rat 2 l Point (Ft. MSL) (cfm) Systems / Components Exhausted l
1 501.0 76,200 to RAB Main Ventilation System, Diesel Generator
,o 199,550 Area Ventilation System. (ECCS/FHB Filtered i j
( ) exhaust, SBVS) l 2 483.3 4,800 to Control Roan and Electric Battery Room Air Con-50,200 ditioning Vent Train B j
3 483.3 4,800 to Control Room and Electric Battery Room Air Con-50,200 i ditioning Vent Train A 4 502.8 76,310 to RAB Main Ventilation System, Fuel Handling Bldg 228,355 Ventilation System, Diesel Generator Area Vent 11a-tion Systen (ECCS/FHB Filtered Exhaust, SBVS) -
5 497.7 140,000 Turbine Building Ventilation System 6 497.7 140,000 Turbine Building Ventilation System 7 470.0 1.565 Administration Building Air Condttioning Vent 8 470.0 5,165 Administration Building Air Conditioning Vent 9 425.0 19,600 Adninistration Building Vent (CU-51) 10 497.0 1,510 Vent from the Main Turbine Lube Oil Reservoir 11 497.0 100 (each) Feed Pump Lube Oil System Vent (2 release points next to each other) 12 497.0 70 Turbine Generator Loop Seal Tank 13 497.0 Natural Lube Oil Batch Tank Vent Ventilation 14 435.0 Natural Refueling Water Storage Tanks A and B
['] Ventilation 15 432.0 Natural Reactor Makeup Storage Tank Ventilation 16 485.0 79,300 Diesel Generator Exhaust-B (Normal Path) 17 409.3 79,300 Diesel Generator Exhaust-B (Alternate Path) 18 409.3 79,300 Olesel Generator Exhaust-A (Alternate Path) 19 485.0 ,
79,300 Diesel Generator Exhaust-A (Normal Path) 20 429.0 Natural Diesel 011 Storage Tank A Ventilation 21 429.0 Natural Diesel Oil Storage Tank 8 Ventilation 22 413.0 Natural Diesel Generator Day Tank A Ventilation 23 413.0 Natural Diesel Generator Day Tank 8 Ventilation 24 404.3 Natural Diesel Generator Lube Oil Tank A Ventilation 25 404.3 Natural Diesel Generator Lube Oil Tank 8 Ventilation
- Amendment 2 (14ay 84)
WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-3 GASE0US EFFLUENT RELEASE POINTS FIGURE NUCLEAR PROJECT No. 3 .
OPERATING LICENSE (SHEET 2 0F 2) a.5-8 ENVIRONMENTAL REPORT
WNP-3 ER-OL 3.6 CHEMICAL AND BIOCIDE SYSTEMS This section discusses the sources and treatment of chemical wastes resulting i
from plant operation. The anticipated water quality of the makeup and dis-charge is described in Table 3.6-1 and water treatment additives used in plant systems are listed in Table 3.6-2. The applicable discharge limitations are i stipulated by the NPDEt Permit included in Appendix A.
3.6.1 Makeup Demineralizer System The Makeup Demineralizer System processes raw water from the plant Makeup Water System to produce high quality demineralized water. The demineralized water is required for Primary and Secondary System makeup and other miscel-laneous plant uses.
I The Makeup Demineralizer System consists of two cross-connected demineralizer trains, each with a normal capacity of 250 gpm and a maximum capacity of 375 gpm. Each demineralizer train consists of a cation exchange unit, an anion exchange unit, and a mixed-bed ion exchange unit. The cation exchange units are followed by a forced-draft deaerator.
The demineralizer trains are regenerated on the basis of ionic exhaustion or throughput. Each train is expected to have a throughput of about 280,000 gal-j O lons. The resins are first backflushed to remove suspended material. Cation resin is regenerated with dilute sulfuric acid (2 to 4 weight percent). Anion resin is regenerated with dilute sodium hydroxide (4 weight percent). After regeneration the resins are rinsed to remove excess regenerant solution. The backflush water, spent regenerant solution, and rinse water are transferred to the low volume waste treatment system. The waste will contain suspended mater-f al, fonic inpurities originating from the plant makeup water and excess regen-eration reagents. The low-volume waste treatment system is described in Sub-section 3.6.7 belcw.
j 3.6.2 Condensate Demineralizer System j The Condensate Demineralizer System processes secondary system feedwater to remove suspended material and tonic impurities. The system consists of 12 mixed-bed demineralizer units with 10 in service and 2 in standby as spares.
The demineralizer units are removed from service based on throughput, pressure drop across the beds, or ionic exhaustion. The resins are transferred to a separate facility for regeneration. In the cation regeneration tank the resins are first backflushed to remove suspended matter. The anion resin is sepa-rated from the cation resin by classification and transferred to the anion i
regeneration tank for regeneration. The cation resin is regenerated with dilute sulfuric acid, and the anion resin is regenerated with dilute sodium hydroxide. The resins are then rinsed to remove excess regenerant solution.
Following regeneration the resins are transferred to the resin mixing tank l2 where they are mixed and stored until required.
O
- 3. 6-1 Ivnendment 2 (May 84) s
_ . _ _ _ . _--_.e_. ...-___m--.-- . . , . - . . - - . -
(
WHP-3 ER-OL The waste will contain suspended material, consisting primarily of corrosion products from plant heat transfer surfaces, excess regenerants and rinse water. The waste is nomally transferred to the low-volume waste treatment system for treatment and subsequent disposal. During nomal operations por-tions of the waste including the backflush and the rinse water, can be pro-cessed in the SHP and SPWS (see Subsection 3.5.2.1) for reuse in the plant.
Additionally, when primary to secondary system leakage occurs resulting in radioactive contamination of the condensate demineralizer system the waste is processed in the radwaste system.
3.6.3 Corrosion Control Hydrazine is used in several plant systems to remove residual oxygen and as a corrosion inhibitor. During nomal operation the concentration of hydrazine in the Secondary System feedwater is maintained in the range of 10 to 50 ppb.
1l Hydrazine reacts with oxygen to yield nitrogen and water. l'ydrazine decom-poses to nitrogen and ammonia at higher temperatures. Essentially all of the hydrazine reacts or decomposes such that only trace quantities are released from the system.
Hydrazine is similarly used in the Primary System and the Auxiliary Boiler.
The hydrazine concentration in the primary coolant is maintained in the range of 30 to 50 ppm at any time the temperature of the coolant is less than 150'F.
Most of the hydrazine utilized in the above applications decomposes or is oxidized. Any hydrazine released from these systems as a result of leakage or other mode of release is removed by subsequent treatment in the radwaste or secondary high purity waste treatment systems. Since hydrazine is a strong reducing agent its residual time is limited.
2l Ammonia is used to control pH in the Secondary Feedwater System and the Aux-iliary Boiler System. The corrosion rate for steel is less at higher pH. In the Auxiliary Boiler System, ammonia provides the required conductivity for proper operation. As with hydrazine, any leakage from these systems is re-moved by subsequent treatment.
Sodium chromate is used as a corrosion inhibitor in the Component Cooling Water Sy stem. To provide effective corrosion control, the concentration is main-2 tained in the range of 300-500 ppm. Portable storage tanks are used to con-tain the coolant during maintenance of system equipment. Leakage is processed in the Liquid Radwaste System by evaporation and ion exchange. There is no liquid release of sodium chromate.
3.6.4 Biocide Control Biocide control for the plant circulating water systems is provided by the addition of sodium hypochlorite. Sodium hypochlorite solution is injected at the intake to the circulating water pumps to produce a maximum concentration of 3 ppm (as chlorine) in the circulating water. Treatment periods vary from 20 to 30 minutes in duration. The treatment may be repeated up to twice daily O
3.6-2 Amendment 2 (May 84)
{
WNP-3 ER-OL depending on the biological activity in the cooling tower and the circulating water system. The maximum daily requirements for sodium hypochlorite will be approximately 800 pounds (as chlorine). The estimated average daily require-ments will be less than 200 pounds (as chlorine).
Any residual chlorine (from sodium hypochlorite) remaining in the cooling tower blowdown is neutralized with sulfur dioxide before discharge from the pl an t. Since the residual chlorine concentration is expected to be about 0.02 ppm the contribution of sulfate to the blowdown will be minimal.
3.6.5 Scaling Control Sulfuric acid is added to the Circulating Water System (cooling tower) makeup, to prevent scaling. The acid injection system includes two positive displace-ment acid injection pumps, each with a maximum capacity of 35 gallons per hour.
The quantity of acid required will depend upon the analysis of the makeup wate r.
Sulfuric acid is also used to control scaling in the HVAC cooling towers.
Blowdown from the HVAC cooling towers is transferred to the Low-Volume Waste Treatment System for additional treatment prior to disposal. The combined blowdown from the HVAC cooling towers is approximately 15 gpm.
3.6.6 Low-Yolume Waste Treatment The Low-Volume Waste Treatment System receives regeneration waste from the Makeup Demineralizer System. Small quantities of waste may also be received 2
from the radwaste system. During normal operation treated liquid radwaste is recycled for use in the primary system. This waste is treated by filtration, demineralization, and evaporation to produce high quality water. Infrequently, because of excess plant water inventory, small quantities of this waste water along with secondary high-purity waste may be discharged to the Low-Yolume Waste Treat 2nent System.
The low-volume waste is treated in the neutralization basin where the waste is neutralized to a pH in the range of 6 to 8.5, by the addition of sodium hydrox-ide or sulfuric acid. A substantial amount of sedimentation also occurs in the l2 neutralization basin. The waste is discharged to the cooling tower blowdown line at a rate of approximately 300-400 gpm.
i 3.6.7 Miscellaneous Chemicals Released i
l During construction, stonn drainage and construction water runoff was treated l by flocculation and sedimentation prior to discharge from the. site. The pH of l the drainage and runoff was adjusted with sulfuric acid. Flocculation and i sedimentation was aided by the addition of polyelectrolyte flocculation reagen ts. It it expected that use of the equalization and sedimentation basins will not be needed during the plant operation phase.
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3.6-3 Amendment 2 (May 84)
I
WNP-3 ER-OL Prior to startup, plant piping and equipment is cleaned by flushing with plant makeup or demineralized water. Flushing water will contain small quantities of hydrazine, metal oxides (rust), and other suspended material. Following any required treatment and analysis, the waste is pumped to the equalization basin and released through the sedimentation basin.
Chemical reagents used in plant laboratories are routed from the laboratory drains to the Radwaste System for processing. The drains are segregated as follows: primary sample drains, secondary sample drains, hot laboratory drains, and cold laboratory drains. There are no normal releases from the l Radwaste System which is discussed in Section 3.5.
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3.6-4 Amendment 2 (May 84)
p WNP-3 ER-OL TABLE 3.6-1 WATER QUALITY PARAMETERS - INTAKE AND DISCHARGE Intake Well(a) Total Combined DischargeIDI Ave Max Ave Max mg/1 mg/l Calcium 12.0 13.1 72.0 97.1 Magnesium 4.3 4.8 25.8 35.4 Sodtwa 6.0 6.5 36.0 164 Potassium 0.70 0.77 4.20 5.70 l2 Chloride 4.2 4.2 25.2 31.7 Fluoride 0.113 0.122 0.68 0.90 Sulfate 2.8 2.8 300 560 Phosphorus 0.142 0.240 0.85 1.66 Amonia N 0.014 0.028 0.08 0.19 NO3 and NO2 N 0. 51 0.54 3.06 4.02 011 and Grease < 1.0 < 1.0 1.0 1.0 Chlorine (total residual) 0.05 Alkalinity (as CACO3 ) 56 64 76 86 Hardness (as CACO3 ) 54 60 324 360 TOS 96(C) 735 883 l2 TSS 1 6 8 pH 6.9 7.5 7.1 8.5 O ug/l Ltg/l 8ariwn 4.0 -12.0 24.0 78.2 Cadmium < 0.1 0.2 0.6 1.4 Chromium 0.6 1.2 23.1 28.4 Copper < 1.0 7.0 21.5 61.3 Iron 16.0 90 183 655 Lead < 1.0 < 1.0 6.0 7.5 Manganese 1.0 4.0 8.2 27.8 Mercury < 0.2 0.7 1.2 4.5 Nickel < l .0 10.0 18.6 74.6 I2 Zinc < 5.0 7.0 31.2 56.9 1
(a) Compiled from Metals Monitoring Program report (Reference 2.4 6) and Ranney Well
! Test of November 25, 1980 i
(b) Includes concentrated makeu water, corrosion products, treatment additives and I low-volume waste. Where ma eup constituents are below detection, the calcuIation assumed the less-than value. l2 I
t (c)From Table 2.5-10 of ER-CP (Reference 2.2-1).
Amendment 2 (May 84) i
WNP-3 ER-OL TABLE 3.6-2 O
WATER TREATMENT ADDITIVES Annual Quantities Additive Systems Served Purpose (lbs/yr)
Ave Max Hydrazine Primary Coolant Oxygen Scaverging and 10,000 .16,000 Condensate and Feedwater Corrosion Inhibitor 2 l (As 35 wt % solution) Auxiliary Boiler System Ammonia Condensate and Feedwater pH Control and Cor- 300,000 400,000 2l (As 29 wt % solution) Auxiliary Boiler rosion Inhibitor Sodium Hydroxide Makeup Demineralizer Resin Regeneration 175.000 250,000 (As 50 wt % solution) Condensate Polishing pH Control and Low Volume Waste Treatment Adjustment Cnemical and Volume Control Radwaste System Sulfuric Acid Makeup Demineralizer Resin Regeneration 2,700,000 3,000,000 (As 93 wt % solution) Condensata Polishing pH Control and Circulating Water System Adjustment Stann and Construction Runoff Polyelectrolyte Storm and Construction Flocculation and 20,000 42,000 (Magnafloc 573C liquid) Runoff Sodimentation Sodium Hypochlorite Circulatina Water Biocide Treatment 160,000 250,000 (As 15 wt % solution) Potable Water Sulfur Dioxide Circulating Water Chlorine Neutralization 10,000 12,000 (CompressedCas)
Hydrogen Primary System Oxygen Scavenger 3,000 4,000 (Liquefied Gas) Turbine-Generator Coolant Nitrogen Chemical and Volume Cover Gas 15,000 20,000 (Liquefied Gas) Control Purge Gas Gaseous Waste System Carbon Dioxide Turbine-Generator Purge Gas 4,000 6,000 (Liquefied Gas) Fire Protection Fire Retardant Boric Acid Primary Coolant Chemical Shim 1,000 2,000 (Crystalline Powder)
Sodium Chromate Component Cooling Water Corrosion Inhibitor 100 200 2 (Crystalline Powder)
Amendment 2 (May 84)
O
WNP-3 ER-OL 3.9 TRANSMISSION FACILITIES 3.9.1 Transmission Line Description 3.9.1.1 Location Two transmission lines will be constructed between WNP-3 and the Bonne-ville Power Administration (BPA) Satsop substation. System requirements beyond the Satsop substation are evaluated, designed and built by BPA.
The substation (Elev 310 ft MSL) is located approximately 3000 feet north of WNP-3 and adjacent to the BPA Olympia-Aberdeen transmission corridor.
One transmission line will be a 500kV line from the 500kV disconnect switches on the plant island to the 500kV bus in the substation. The other line will be a 230kV line from the substation to the 230kV discon-nect switches at the plant. The 230kV line will be an underground low-pressure oil-filled cable. Figure 3.9-2 shows the relative locations of the plant, the BPA substation, and the 500kV line. The right-of-way lies 2 completely within the project boundaries and crosses no public roads.
3.9.1.2 Routing The transmission lines between the plant and BPA's Satsop substation will satisfy the requirements of NRC General Design Criteria 17 These lines and their interconnection with the BPA system are shown schematically in O Figure 3.9-1 l2 V
The 500kV line for WNP-3 will be connected, via the 500kV switchyard bus, to a new 500kV BPA transmission line which will extend approximately 46 miles to BPA's Paul switchyard. This line will parallel the existing Aberdeen-Olynpia-Paul corridor. It will be single-circuit except for a six mile double-circuit section located west of Olympia. The double-circuit section will be shared with the Satsop-Olympia 230kV #2 line (see Figure 3.9-1).
The two existing Olympia-Aberdeen 230kV lines will be looped into the Satsop 230kV switchyard and connected in a modified breaker and a half bus configuration to the 230kV lines feeding each plant. The length of each of these lines from Satsop to Olynpia is approximately 27 miles (see Figure 3.9-1).
The Olympia-Aberdeen corridor, which passes north of the plant, will con-tain the following transmission facilities:
the Cosmopolis - South Elma 115k/ line the Satsop - Olynpia No. 2 230kV line the Satsop - Olynpia No. 3 230kV line the Satsop - Aberdeen No. 2 230kV line the Satsop - Aberdeen No. 3 230kV line the Satsop - Paul 500kV line A
U 3.9-1 Anendment 2 (May 84)
WNP-3 ER-OL Although there will be crossings of the transmission lines and some multi-O ple circuits, no single contingency will leave less than two power sources feeding the Satsop substation. This is due to the routing and the spacing of the transmission lines. Further reliability is provided by intercon-nection through an auto transformer of the 500 and 230kV buses in the Satsop substation.
3.9.1.3 Struc tures The transmission line structures between the plant and the Satsop substa-tion will be constructed of lattice steel in a single circuit delta con fi guration. The towers will be about 120 feet high and 40 feet wide.
Land requirements for each tower will average 400 square feet.
- 3. 9.2 Environmental Parameters The environmental parameters associated with the transmission system beyond the Satsop substation have been evaluated by BPA as owner /
operator.(1) The environmental effects of a transmission sy9tqm were also evaluated generically by the BPA in its Draft Role EIS.(21 The following discussion addresses principally the lines between the plant and the substation.
- 3. 9.2.1 Land Use The transmission lines are located in a previously forested area which was O cleared to make laydown area for plant construction. Because the lines are within the project boundaries, use of the land will continue to be limited to activities associated with plant operation.
3.9.2.2 Aesthetics That portion of transmission lines on higher ground near th5 plant may be visible from State Route 12. However, the transmission structures will not be seen in isolation from the much larger plant structures.
3.9.2.3 Corona Effects Corona loss is the loss of energy to the atmosphere caused by localized electrical discharges from an energized conductor; these usually result from small irregularities or foreign particles (e.g., dust or water drop-lets) on the conductor surf ace. The result is a breakdown of the air immediately adjacent to the conductors and effects associated with this highly stressed air include audible noise, radio interference, and ozone produc tion.
Audible noise due to the corona phenomenon may be evident in the area immediately beneath and adjacent to the 500kV line. It will be most noticeable in fog or drizzling rain, however, it will not be detectable off-site. Electrical noise causing radio and television interference may 3.9-2
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WASHINGTON PUBUC
.s POWER SUPPLY SYSTEM PLANT-T0-SUBSTATION FIGURE NUCLEAR PROJECT No. 3 OPERATING LICENSE TRANSMISSION LINE (500kv) ROUTING 3.9-2 ENVIRONMENTAL REPORT
WNP-3 ER-OL ENVIRONMENTAL EFFECTS OF STATION OPERATION 5.1 FFFECTS OF OPERATION OF HEAT DISSIPATION SYSTEM The heat dissipation system is described in Section 3.4. This section discusses the physical and biological effects of system operation.
5.1.1 Effluent Limitations and Water Quality Standards The Water Quality Standards of the State of Washington (l) classify the reach of the Chehalis River in the vicinity of the plant as " Class A (Ex-cellent)". The standards specify that the increase in water temperature outside a specified mixing zone shall not exceed t = 28/(T + 7), where t is the permissible increase and T is the existing water temperature in OC. When the ambient water temperature exceeds 18.00C the maximum permissible increase is 0.30C.
Discharges from WNP-3 are controlled to comply with the National Pollutant Discharge Elimination System (NPDES) Permit (see Appendix A) issued by the State of Washington in compliance with Chapter 155, laws of 1973 (RCW 90.48), as amended, and the Clean Water Act (PL 95-217), as amended. This permit incorporates the Water Quality Standards and establishes a dilution zone with longitudinal boundaries 50 feet upstream and 100 feet downstream from the diffuser and lateral boundaries 25 feet from the midpoint of the diffuser. Vertically, the dilution zone extends from the surface to the (pj river bottom. Consistent with the applicable guideline of 40 CFR Part 432, the permit limits the temperature of the blowdown to the lowest tem-perature of the recirculated cooling water prior to the addition of makeup water. In addition, the permit specifies that when ambient river tempera-tures are 200C or less, the discharge temperature shall be 200C or less and shall not exceed the ambient temperature by more than 150C; and when the ambient river temperatures are greater than 200C, the discharge temperature shall be equal to or less than the ambient temperature. No discharge is permitted when downstream velocities are less than 0.3 feet per second (fps).
5.1.2 Physical Effects The thermal dispersion characteristics of the multiport bl wqlown 9 diffuser were studied using a hydraulic model with a scale of 1:12. W The studies were conducted to support the dilution zone definition in the NPDES Permit and, consequently, focused on abnormal conditions. These conditions included minimum daily flowrates estimated from data recorded at upstream gaging stations and river temperatures which are exceeded 99 percent of the time. These conditions are shown in Table 5.1-1 and may be compared with the average data listed in Tables 2.4-1 and 2.4-5. It 2 should be noted that the August - October low flows which were used are less than the once-in-10-yr, single-day low flow of about 500 cfs (WNP-3 FSAR Figure 2.4-33). The plant operating parameters (discharge temper-ature and blowdown flow) that were modelled are shown in Table 3.4-1.
O 5.1-1 Amendment 2 (May 84)
WNP-3 ER-OL Additional conservatism is provided by the fact that the above-mentioned model tests were conducted primarily for two-uait (both WNP-3 and WNP-5) operation. Some results are shown in Figures 5.1-1 through 5.1-3. Fig-ures 5.1-1 and 5.1-2 are for two-unit operation in January and August, respec tively. Figure 5.1-2 can be compared with Figure 5.1-3 which de-picts the August isotherms with only a single unit operating. A critical period for meeting water quality standards is expected to be October when the flows are low and the initial temperature differences are greatest.
However, as shown in Table 5.1-1, dilution zone boundary temperatures are predicted to meet water quality standards in every month.
The river reach in the vicinity of the discharge is subject to flow stag-nation and reversal during the infrequent coincidence of low river flow and extreme high tides. Several cases (e.g., river flow @ 440 cfs, Aber-deen tide @ 5.6 ft MSL) resulting in the stagnation or reversal phenomena were studied using the hydraulic model. However, the results are not dis-cussed here because, as noted in Subsection 5.1.1, the NPDES Permit pro-hibits discharges when downstream river velocities go under 0.3 fps.
The unidirectional flow examples discussed above provide predictions of the seasonal variation of blowdcwn plume temperatures under severe condi-tions (low river flow, large initial temperature differences). The near-and intermediate-field temperatures of the dilution zone are seen to com-ply with water quality standards (see Table 5.1-1). Bulk river tempera-tures in the far-field will be increased no more than 0.05 0C in any sea-son due to the maximum incremental addition of approximately 10,000 Btu /sec of heat in the blowdown from WNP-3.
5.1.3 Biological Effects 5.1.3.1 Intake Structure Effects Two subsurface infiltration-type intake structures (Ranney collector wells) located on the south bank of the Chehalis River near River Mile 18 will supply makeup water for WNP-3. Impingement and entrainmen organisms is precluded by the use of the collector wells.lj)of Lossaquatic of aquatic habitat and benthic macroinvertebrates due to drawdown of the I river channel (0.1 ft or less in an area with tidal fluctuations of 2 or more ft) will be negligible. Nearby Elizabeth Creek may become dry in the i fall blocking the stream to both anadromous and resident fish. The number of annual juvenile coho and chum that would be lost as a result of this blockage was estjmgted to be 0.1% of the total run and is considered an acceptable loss.13 1 The actual inpact on coho and chum is probably less than Creekpreviously watershed estimated during 1973because to 1976. of(p/ This has increased siltation,earcutting in the upp and along with numerous other obstacles (eg. fallen trees), has decreased the spawning potential from approximate 1968-1964 to 15 in 1
1977-1978, at the most recent estimate. )65 redds in O
5.1-2 Aruendment 1 (Dec 82)
WNP-3 g ER-OL V
References For Section 5.1 (contd.)
- 24. Brett, J. R., " Temperature Tolerance in Young Pacific Salmon, Genus Oncorhynchus," Journal of the Fisheries Research Board of Canada, IX(6):265-323, November 1952.
- 25. Junod, A., R. J. Hopkirk, D. Schmeiter, and D. Haschke, "Meteorologi-cal Influences of Atmospheric Cooling Systems as Projected in Switzer-land," In: Cooling Tower Environment-1974, S. Hanna and J. Pell, (ed.),1974 ERDA Synposium Series, CONF-740302, NTIS, U. S. Dept. of Commerce, Springfield, Virginia, 1974, 638 pp.
- 26. Thompson, D. W., J. M. Norman, T. N. Chin, and K. L. Miller, Airborne Studies of Natural Draft Cooling Tower Plumes: Meteorological Pro-files and a Suntnary of In-Plume Turbulent Temperature and Velocity Fluctuations, Dept. of Meteorology, Pennsylvania State University, University Park, Pennsylvania,1977.
- 27. Coleman, J. H. and T. L. Crawford, " Characterization of Cooling Tower Plumes from Paradise Steam Plant," In: Cooling Tower Environment-1978. Maryland Dept. of Natural Resources, University of Maryland, NTTege Park, Maryland,1978.
13 V 28. Hanna, S. R., " Predicted and Observed Coaling Tower Plume Rise and Plume Length at the John E. Amos Power Plant," Atmospheric Environ-ment, 10:1043-1052, 1976.
- 29. Operational Ecological Monitoring Program for the Trodan Nuclear Plant, Annual Report,1980, PGE-1009-80, Dept. of Enytronmental i Sciences, Portland General Electric Co., Portland, Oregon, February 1981, p. III-9.
O 5.1-11 Amendment 1 (Dec 82)
WNP-3 ER-OL TABLE 5.1-1 PREDICTED DILUTION ZONE B0UNDARY TEMPERATURES VS. WATER QUALITY STANDARD Temperatures (OC)
Month River Flow River Discharge Dilution Zone (a) was(b)
(cfs)
January 1,698 0.0 10.3 0.9 4.0 February 1,739 1.1 9.7 1.9 4.3 March 2,410 3.9 8.6 4.3 6.5 April 2,164 5.0 8.9 5.3 7.3 May 1,308 10.0 10.8 10.1 11.6 2
June 821 11.1 13.1 11.3 12.5 July 540 14.4 16.1 14.6 15.7 August 418 15.6 17.5 15.8 16.8 September 399 11.7 18.3 12.4 13.2 October 397 5.0 17.5 6.1 7.3 November 539 4.4 15.3 5.4 6.9 December 674 0.6 12.8 1.7 4.3 (a) Two units operating. Peak surface temperature 100 ft downstream from diffuser, from Reference 5.1-2.
(b) Water quality standards from Reference 5.1-1.
See Subsection 5.1.1.
Amendment 2 (May 84)
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Amendment 2 (May 84) wASuiNGTON Puatic POWER SUPPLY SYSTEM BLOWD0tJH PLUME IS0 THERMS (OC) IN AUGUST tlITH FIGURE 1
NUCLEAR PRO 4CT No. 3 SINGLE-UNIT OPERATION l
OPEHATING LICENSE i
ENVmONMENTAL REPORT 5.1-3 i
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l Amendment 2 (May 84)
WASHINGTON PUBLIC POWER SUPPLY SYSTEM FIGURE
! NUCLEAR PROJECT No. 3 PREDICTED COOLING TOWER DRIFT DEPOSITION PATTERN (Ib/ acre-yr)
OPERATif.G LICENSE 5.1-4 ENVIRONMENTAL REPORT I
O O O WNP-3 ER-OL TABLE 5.2-8 ESTIMATE 0 MAXIMlM ANNUAL DOSE TO AN INDIVIDUAL FROM WNP-3 Annuil Dose (mrem) to an Adult Annual Dilution Iotal Pa th way Exposure Location Factor Skin Body GI-LLI Thyroid Bone Liquid Drinking Water 730 1 2.0 mile downstream 1/1100 2.3E-03 2.0E-03 2.1E-02 3.9E-04 Fish 21 kg 2.0 mile downstream 1/1100 3.0E-02 2.2E-03 9.4E-03 2.1E -02 i
Shoreline 12 hr 2.0 mile downstream 1/1100 2.3E-05 2.0E-05 2.0E-05 2.0E-05 2.0E-05 Food Products Vegetables 520 kg 2.0 mile downstream 1/1100 1.4E-03 1.3E-03 1.3E-03 1.1E-04 Leafy Vegetation 64 kg 2.0 mile downstream 1/1100 1.7E-04 1.6E-04 1.6E-04 1. 3E-05 Milk 310 1 2.0 mile downstream 1/1100 9.5E-04 7.6E-04 3.4E-03 1.5E-04 Nat 110 kg 2.0 mile downstream 2.9E-04 3.0E-04 3.5E-04 1. 7E-05 Invertebrate Seafood 5 kg 2.0 mile downstream1/11000(b) 1/1100 1. 3E-04 4.5E-03 1.9E-04 1.4E-03 Swimming 40 hr 2.0 mile downstream 1/1100 2. 3E-06 2.3E-06 2. 3E-06 2. 3E-06 Boating 200 hr Downstream 1/1100 5.8E-06 5.8E-06 5.8E-06 5.8E-06 I Total (a) 2. 3E-05 3.5E-02 1.1E-02 3.6E-02 2. 3E-02 Aif-Submersion 8766 hg 1.0 mile N 3.0E-06 1.6E-01 5.2E-02 5.2E-02 5.2E-02 5.2E-02 Inhalation 8000 m3 1.0 mile N 3.0E-06 1. 7E -01 1. 7E-01 1. 7E-01 2.4E-01 ~2.7E-04 Ground Contamination 8766 hr 1.0 mile N 3.0E-06 5.0E-03 4.3E-03 4.3E-03 4. 3E-03 4. 3E-03 1
Food Products vegetables 520 kg 1.5 mile NNE 3.1E-06 5.0E-01 5.0E-01 5.0E-01 6.0E-01 6.5E-01 y 310 1 1.5 mile NNE 3.1E-06 1.9E-01 2.0E-01 1.9E-01 9.4E-01 2.9E-01 l Cow Milk (d)
Infant 330 1 1.5 mile NNE 3.1E-06 9.7E-01 9.8E-01 9.7E-01 6.6E+00 2.6E+00 310 1 1.7 mile NE 1.4E-06 1.5E-01 1.5E-01 1.5E-01 5.2E-01 1. 3E-01 Goat Milk )
Infanttd 330 1 1.7 mile NE 1.4E-06 6.4E-01 6.4E-01 6.4E-01 2.8E+00 1.2E+00 kat 110 kg 1.6 mile NNE 2.8E-06 1.0E-01 1.0E-01 1.0E-01 1. 2E-01 2. 4E -01 f Total (c) 1.1E-00 1.0E-00 1.0E-00 2.0E+00 1. 2E-00 l2 E.
j $ (a) Person assumed to drink Chehalis River water, eat fish caught in the river, consume crab caught in Grays Harbor, eat 3
" food grown with river irrigation, and use the river for recreation.
1 bl Harvested in Grays HarDor.
N c? Adult cumulative dose from all pathways, excluding goat milk.
- dj Consumption of goat milk by an infant is assumed to be the same as the consumption of cow milk. It is also assumed
,g that inf ant milk consumption is the same as child consumption.
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WNP-3 ER-OL TABLE 5.2-9 ESTIMATED ANNUAL POPULATION 005ES FROM WNP-3 Tnyroid Total Body Dose Dose Pathway (tnyroid-rem) (man-rem)
Air Submersion 1.4E-01 1.4E-01 Ground Contamination 8.7E-03 8.7E-03 Inhalation 1.5E+00 1.lE+00 Farm Products Milk 2.lE+00 1.0E +00 Meat 1.3E-01 1.2E-01 Vegetation 6.lE-01 4.7E-01 Total: 4.6E +00 2.9 E +00 Water Drinking Water 1.4E-05 1.lE-06 Aquatic Foods (a) i Fish 7.4E-03 3.9E-02 Inverteorates 6.5E-05 5.5E-05 Water Recreation (D) 4.6E-05 4.6E-05 Farm Products Milk 1.2E-01 3.0E-02 Meat 1.2E-02 9.4E-03 1 Vegetation (c) 6.6E-03 7.0E-03 Total: 1.6E-01 8.6E-02 (a) Sport and comnercial fishing.
(0) Shoreline activities, swimming and coating comoined.
(c) Vegetation and leafy vegetaoles combined.
Amendment 1 (Dec 82)
WNP-3 ER-OL O
V 5.3 EFFECTS OF LIQUID CHEMICAL AND BIOCIDAL DISCHARGES The expected impacts of chemical and biocidal discharges at the construction permit stage were presented in the ER-CP in Subsections 5.4.3 and 5.4.4 and in the NRC Final Environmental Statement (FES). Since that time additional water quality data have been collected and are presented in Sections 2.4 and 3.6.
The expected chemical releases to the Chehalis River via the cooling tower blowdown are described in Section 3.6 and sumarized in Table 3.6-1. This section covers the effects of such discharges on aquatic life.
Table 5.3-1 presents the potential discharge concentrations and changes in concentration of chemical constituents in the Chehalis River at the downstream mixing zone boundary (see Subsection 5.1.1) for the low river flow condi-tion.tal The table shows that the expected discharge concentrations are less than the effluent limitation guidelines (40 CFR Part 423) and the NPDES Permit limitations. An exception is the maximum value for nickel which re-sults primarily from a high concentration (10 99/l) in the makeup water (see Table 3.6-1).
A comparison betygen the present Environmental Protection Agency (EPA) water quality criteria (1,2) and the chemical concentrations at the edge of the mixing zone reveals that all parameters for which criteria exist are less than the criteria.with the exception of average values (at 440 cfs river flow) for cadmium, lead and mercury and the maximum value for cooper. In regard to the concentration of cadmium, lead and mercury, operation of WNP-3 does not in-O' clude the chemical addition of these parameters; however, they may be present due to concentration of the makeup aater. Moreover, the average upstream ambient Chehalis River values for these metals may exceed water quality cri-teria (Table 5.3-1). In f act, the concentrations of average cadmium, lead and mercury at the edge of the mixing zone are all less than 0.2 pg/l above ambient levels upstream of the discharge.
5.3.1 Copper Some of the WNP-3 auxiliary heat exchangers (totaling 90,000 sq f t) are made with copper and nickel alloy tubes. Therefore, copper and nickel releases in the discharge come from two sources: the makeup water, and corrosion and/or erosion of the heat-exchange tubes. Copper levels in the Chehalis River up-stream of the intake wells range from <1.0 to 8.0 pg/l(see Section 2.4). The l2 discharge level for copper may range from 21.5 to 61.3 ug/l (Table 5.3-1).
The copper concentrations at the edge of the mixing zone are greatly reduced by dilution; the concentration ranges from 3.9 to 13.3 pg/l at the edge of the mixing zone with the river at the very low flow of 440 cfs.
(a) Thermal and chemical dilution studies assumed a once-in-10-yr, 7-day low flow of 440 cfs as reported in Subsection 2.5.1 of the ER-CP. Reanalysis, including the most recent flow data for the site area, has shown this flow to be 530 cfs as noted in Subsection 2.4.1.1.
O 5.3-1 Amendment 2 (May 84)
WNP-3 ER-OL A literature review on the biological ef ments was prepared in 1978 by Chu et.al.QQts W1 In of copper inthe assessing aquatic environ-impacts of chemical discharges the salmonids are the most important species economically and recreationally. A review of copper toxicity data indicates that the salmonids, particularly steelhead/ rainbow trout (Salmo the most sensitive and most frequently tested species.(gairdneri),
J1 are among Most toxicity studies on salmonids have been performed with the early life stages, ranging from egg to juvenile. However, the discharge plume from the WNP-3 cooling tower blowdown does not intersect any kncwn spawning areas.
Therefore, the discharge is not expected to affect the incubation success of salmonids in the Chehalis River. Nevertheless, the toxicity studies of the early life stages are described below.
Shaw and Brown (4) observed that rainbow trout eggs could hatch af ter fertilizationinasolutioncontaining1000ug/l(gqpper;however,thisex-posure level increased time to hatching. Grande 1, in studying the effects of copper sulf ate on eggs and fry in the yolk-sac stage for rainbow trout, brown trout (Salmo trutta), and Atlantic salmon (Salmo salar), found that cop-per reduced egg hatching. Furthermore, copper inhibited egg development at ^
1l about the same concentration as was toxic to fry--40 to 60 ug/l at 21 days.
Concentrations as low as 20 ug/l appeared to have a sublethal effect (i.e.,
unwillingness to f In another study that compared eggs and yolk-sac fry, Hazel and Meith(6)eed).
concluded that eggs were more resistant than fry to the 1l toxic effects of copper. From a continuous-flow bioassay using chinook g salmon, the authors reported that copper concentrations of 80 ug/l had little W effect on the hatching success of eyed eggs; acute toxicity to fry was observed at 40 ug/1, while increased mortality and inhibition of growth was shown at 20 ug/1.
Chapman (7), also using a continuous-flow bioassay method, tested the rela-tive resistance to copper, zinc, and cadmium of newly-hatched alevins, swim-up fry, parr and smolts of chinook salmon and steelhead trout. Chapman found that steelhead trout were consistently more sensitive to these metals than were chinook salmon. His results are summarized in Table 5.3-2.
Finlayson and Verrue(8) determined an 83-day LC10 (lethal concentration to 10 percent alevins of the organisms) and swim-up of studies fry. Similar 64 ug/l by copper for chinook Finlayson salmon (gggs, and Ashuckian W determined a 60-day LC10 of 33 ug/l copper for steelhead trout eggs, alevins, and swim-up fry.
A number of studies have demonstrated that copper toxicity is related to water hardness and alkalinity. o proportional to water hardnessIn g egl 3.ppertoxicityisroughlyinversg)
The work of Lloyd and Herbert illustrates the relationship between lethality and total hardness or alka-linity (see Figure 5.3-1). When hardness increases over a range of 15 to 320 mg/1, a corresponding increase in the LC50 is observed with rainbow trout and chinook salmon.
5.3-2 Amendment 1 (Dec 82)
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{ WNP-3 .
! ER-OL 4
References for Section 5.3 (contd.)
i
, 34. Becker, C. D. and T. O. Thatcher, Toxicity of Power Plant Chemicals to Aquatic Life, Battelle, Pacific Northwest Laboratories, Richland, Washington, 1973, 221 pp.
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WNP-3 ER-OL TABLE 5.3-1 POTENTI AL CHANGE IF CHEHAll5 RIVER WATER QUALITY RESULTING FROM WNP-3 DISCHA3GES (a) Edge of Mixing Zone Effluent (b) Water (c)
River Ambient Discharge (River 9 440 cfs) Limitations Quality Criteria Ave Max Ave Max Ave Max Ave Max Ave Max Cnemical in ppm Calcium 6.6 8.4 72 0 97.1 13.1 17.3 Mapesium 1.9 2.4 25.8 35.4 4.3 5.7 Sodium 4.4 5.4 36.0 154 7.6 21.3 21 Potassium 0.55 0.76 4.20 5.70 0.91 1.25 Chloride 5.6 7.9 25.2 31.7 7.6 10.3 Fluoride -- -- 0.68 0.90 Sulfate 4.0 5.1 300 560 33.6 60.6 Phosphorus 0.039 0.073 0.85 . 1.66 0.12 0.23 5.0 5.0 Ammonia N 0.016 0.026 0.08 0.19 0.02 0.04 N01 and NO2 -N 0.63 1.15 3.06 4.01 0.87 1.44 Oil and Grease 2.5 14.0 1.0 1.0 2.3 12.7 T.R. Chlorine -- -- 0.05 0.005 0.05 0.002 Alkalinity (as CACO ) 28 38 76 86 33 43 Hardness (as CACO 3 )3 29 38 324 360 58 70 21 TDS 75 89 735 883 141 168 TSS 18 370 6 8 16.8 334 pH 7.0 7.5 7.1 8.5 6.5-8.5 mtals in ppb Barium 10.0 22.0 24.0 78.2 11.4 27.6 2 Cadmium 0.1 0.5 0.6 1.4 0.2 0.6 0.007 1.0 3 Chromium 1.2 10.8 23.1 28.4 3.4 12.6 100 a
Copper 2.0 8.0 21.3 61.3 3.9 13.3 30 65 5.6 8.5 a Iron 860 7400 18 3 665 792 6726 1000 e Lead 4.0 36.0 6.0 7.5 4.2 33.1 0.2 49.5 3
" Manganese 29.0 80.0 8.2 27.8 27.0 74.8 Mercury 0.4 1.3 1.2 4.5 0.5 1.6 0.2 4.1 N
2l Nickel 1.0 14.0 18.6 74.6 2.7 20.1 65 36 849
-- Zinc 5.0 37.0 31.2 56.9 7.6 39.0 75 47 138
?
(,a) Complied from 1980 Environmental mnitorin9 Program (Reference 2.2-4) and 1930-1981 retals Monitoring Program (Reference 2.4-6)
$ LD}From EPA Ef fluent Guidelines (40 CFR Part 423) cr WNP-3 NPDES Permit (see Appendix A)
Lc; References 5.3-1 and 5.3-2 9 O O
i WNP-3 ER-OL O sensitivity of detection, radiochemical procedures will be used. Radio-chemical procedures in this type of program serve mainly to separate or concentrate the radionuclide of interest from the inorganic or organic matrix in preparation for counting.
The following paragraphs describe the general program to be instituted, including the expected types of samples, collection frequency, and analy-sis to be accomplished on each sample type. The preoperational (i.e.,
, prior to loading of fuel) phase of the REMP is summarized in Table 6.1-7.
Planned sample locations are shown in Figure 6.1-2. Final details of the program will not be determined until just prior to implementation.
6.1. 5.1 Airborne Radiation Airborne fodine and particulates will be sampled by continuous low volume air samplers with a flow rate of approximately 1 ft /3 min. Radiofodine
. will be collected via charcoal canisters fitted in series with a glass
] fiber filter for particulate collection.
The particulate filters will be changed weekly and analyzed for gross beta (beta analysis will occur no sooner than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of collection to allow for radon and thoron daughter decay). Filters composited quar-terly by location, will be analyzed for gamma emitting nuclides. Individ-ual weekly filters will have gamma isotopic analysis performed only if gross beta results are ten times the mean o Char-l coal canisters will be analyzed weekly for ghe I. control location.
< The air sampling network will consist of at least five stations indicated Particulate sampling will be initiated at least one year on Table 6.1-7.
before fuel load and radiofodine analysis will begin at least six months before fuel load.
6.1.5.2 Direct Radiation, Direct radiation levels will be measured by a TLD (thermoluminescent dosimeter) system consisting of at least 40 stations. Tt
- TLDs will be located on an inner ring at a radius of approximately one mile and an t
outer ring at a radius of about four to five miles. Other stations will be at controls and special areas of interest.
Duplicate TLD sets will be placed at each location. One set will be ex-changed on a quarterly basis; the other set of dosimeters will be col-1ected annually. At least two years of preoperational TLD data will be collected.
i l
l 6.1-21 Amandment 2 (May 84)
WNP-3 ER-OL 6.1.5.3 Waterborne Radiation 2l River water will be sampled upstream and downstream of the discharge.
These water samples will be collected using an automatic sampler; small volumes will be collected intermittently and composited over a one-month period. The composite sample will receive a gamma isotopic analysis monthly and will be composited for tritium analysis quarterly. Water monitoring will begin at least one year before fuel loading.
Groundwater will be sampled on a quarterly grab-sample basis from a domes-tic well of a nearby resident south of the Chehalis River. This sample will receive gamma isotopic and tritium analysis.
Sediment samples will be collected semi-annually from a fishing area on 2l the north bank of the Chehalis River about 1 to 3 miles downstream from the discharge diffuser. Gamma isotopic analysis will be performed on the samples.
6.1.5.5 Ingestible Products 2
Milk samples will be collected from four locations. Three will be at milk animal locations having the highest dose potential. A control sample will be collected from a milk animal in the vicinity of Chehalis, Washington.
The milk samples will be collected twice a month during pasture season and once a month during the remainder the year. Gama isotopic analysis will be perfonned on all samples; gI I analysis will be performed by radiochemical separation on all samples collected during the pasture season. Milk sampling will begin one year prior to WNP-3 operation, and analyses of 131 I will start six months before operation.
Three fish samples will be collected semi-annually. Two will be taken 2l near the plant discharge and one at a control location (possibly on the Wynocchee River or Wishkah River). Gamma isotopic analysis will be per-formed on the edible portions of the fish.
! One sample of each principal class of food products (fruit, root vege-2l table, leafy vegetable) from areas downstream (which are irrigated by sur-face water from the Chehalis River) will be taken monthly or at harvest I times when available. A control sample of a similar fruit / vegetable will
! be collected in the community of Chehalis.
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O 6.1-22 Amendment 2 (May 84)
i O
tR-3 ER-OL TABLE 6.1-7 RADIOLOGICAL EWIRONENTAL MONITORING PROGRAM 1
] Analysis
- Sample mdf a Location Sampling Frequency (a) Type r reguency l Airborne 1
Radiolodine(b) Samples from 5 lo-Particulates(C) cations: 3 samples Continuous sampling Radiciodine; Weekly from offsite in 3 with weekly collection 131g dif ferent sectors having highest calcu-lated annual average 2 gr undlevel D/Q 3 1 in the vicinit Particulat i
community (Elma)y of having Gross Beta h Weekly j, highest calculated an-nual average ground-
- 1 eve! D/Q Gamma Weekly Isotopic I8) Composite I control in Chehalls, by location.
l 30 miles SE of the site quarterly f Direct Radiation (f) A minimum of 40 sta- Quarterly and Ganna dose Quarterly and t
i tions as follows: Annually Annually l An inner ring of sta-1 tions in each of 16 sectors in the general vicinity of the site boundary.
) An outer ring of 16 sta.
4 e
tions in each sector in the range of four to I E 3
2 five miles from the site.
@ The balance of the sta-e+ tions (8) in areas of 1
m special interest (e.g.,
population centers,
)
Qne schools) including 2 controls. One control j N near Chehalis approx-
! co inately 30 miles SE 1 8 and one near Aberdeen I approminately 17 miles I west.
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WNP-3 .
ER-OL TABLE 6.1-7 (contd.)
Analysis Sample >bdia Location Sampling Frequency (a) lype t reguenc y Waterborne River Water (C) Upstream and Composite (9) for month 3g Quarterly downstream of canposite the discharge Gama Isotopic (e)
GroundwaterIC) Nearby resident Quarterly grab san.ple 3H Quarterly domestic well Gama Isotopic Quarterly 2 Sediment (f) 1-3 miles downstream Semi-annually Gamma Isotopic Semi-from discharge annually Ingestion Milk (h) 4 locations as follows. Semi-monthly during Gama Semi-Samples from 3 dif- grazing season; monthly Isotopij(c) monthly; ferent locations at other times 131g tu monthly within 3 miles dis-tance having highest calculated dose potential A control to be collected near Chehalts
> Fish (f) 2 in vicinity of Semi-annually Gama Isotopic Semi-g disch arge. (edible portion) annually 5.
$ 1 control - Wynoochee s or Wishkah River ro Fruit and 1 sample of each prin- Monthly during growing Gamma Isotopic Monthly m VegetablesII) cipal food product from season 2 g areas irrigated down-4 stream and a control in the vicinity of
$ Chehalis O O O
( O idNP-3 ER-OL TABLE 6.1-7 (contd.)
J (a) Deviation may be required if samples are unobtainable due to hazardous conditions, seasonal avall-ability, malfunction of automatic sampling equipment, or other legitimate reasons. All deviations will be documented in the annual report.
l
] (b) Minimum six months preoperational sampling.
I (c) Minimum one year preoperational sampling. '
(d) Particulate sample filters will be analyzed for gross Beta af ter at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay. If gross j Beta activity is greater than 10 times the mean of the control sample, gamma isotopic analysis should be i performed on the individual sample.
I'}Ganna isotopic means identifications and quantification of gassia emitting radionuclides that may be attributable to the effluents of the facility.
II) Minimum of two years preoperational monitoring.
3 (9} Composite samples will be collected with equipment which is capable of collecting an aliquot at time g intervals which are short relative to the compositing period.
(h) Milk samples will be obtained from farms or individual milk animals which are located in sectors with j g the higher calculated annual average ground-level D/Q's. If Cesium-134 or Cesium-137 is measured in an !
individual milk sample in excess of 30 pCi/1, then Strontium-90 analysis should be performed.
[
w 2 II} Fruit and vegetables will be obtained, if possible, from farms or gardens which use Chehalis River water within ten miles of the discharge for irrigation and different varieties will be obtained in season.
g One sample each of root food, leafy vegetables, and fruit should be collected each period, a
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WNP-3 ER-OL TABLE 6.1-8
SUMMARY
OF RIVER ELECTR0 FISHING AND BEACH SEINING, 1976-1980 Month Station Year J F M A M J J A S 0 N D Fuller Bridge 1976 ES ES ES ES ES 1976 ES ES ES S ES E 1978 E E ES E E E E E E E E 1979 E E E E E E E E E E 1980 E E E E E E E E E E E E Satsop River 1976 S E ES ES ES ES S 1977 S S S S ES E 1978 E ES S E E E E E 1979 E E E E E E 1980 E E E E E E Holding Area 1976 ES ES ES ES ES ES 1977 E ES ES ES ES S ES E 1978 E ES ES ES ES E ES E 1979 ES ES ES ES ES ES ES ES E E 1980 E E E E E E E E E E E E Upstream 1977 E E E E E E Discharge Area Discharge 1978 E E E E E E E E E h
1977 E E ES ES ES ES ES 1977 ES ES ES ES S ES E 1978 E E ES ES ES ES E ES E E 1979 ES ES ES ES ES ES ES ES ES E 1980 E E E ES ES ES ES ES ES ES E E Downstream 1977 E E E E E E Discharge Area 1978 E E E E E E E E E Intake 1976 ES ES ES ES ES ES Area 1977 E ES ES ES ES S ES E 1978 E ES ES ES ES ES E ES E 1979 ES ES ES ES ES ES ES ES E E 1980 E E E E E E E E E E E E Greenbanks 1976 ES ES ED ES ES ES Area 1977 ES ES ES S ES 1978 E E E E E E E E E E E = Electrofishing S = Seining O
Amendment 1 (Dec 82)
WNP-3 ER-OL 7.2 TRANSPORTATION ACCIDENTS INVOLVING RADI0 ACTIVITY l2
- The transportation of cold fuel to the reactor, irradiated fuel from the reactor to a reprocessing plant, and solid radioactive wastes to waste burial grounds is within the scope of 10 CFR Part 51.20(g). The environmental risks of the transportation of radioactive materials to
{ and from WNP-3 are as described by Table S-4 of 10 CFR Part 51.20.
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7.2-1 Amendment 2 (May 84) i l
O O O WNP-3 ER-OL TABLE 7.3-1 CelEMICALS STORED ONSITE Type Ouantity Storage Location Sodiun Hypochlorite Solution Two 7,500 gallon containers Near Cooling Towers (outside)
Diesel Oil 88,000 gallons Reactor Auxiliary Building 2
1,100 gallons Underground adjacent to Fire Pump House Structure Sulfuric Acid one 10,000 gallon container Outside Water Treatment one 5,000 gallon container Building Sodium Hydroxide one 10,000 gallon container Inside Water Treatment Building Bottled Hydrogen Gas 8,000 gallons Outside Northeast Wall of Turbine Building Nitrogen Gas 20,000 ft3 Outside Northeast Wall of Turbine Building E
@ Oxygen Gas 12,000 ft3 Outside Northeast Wall of
,& Turbine Building 2l Carbon Dioxide 3 tons liquid Outside Northeast Wall of
] Turbine Building Aqua Annonia 15,000 gallons Outside Reactor Auxiliary k
e
WNP-3 ER-OL
. i ENVIRONMENTAL APPROVALS AND CONS'JLTATION The 1970 Washington State Legislature adopted an act creating a Thermal Power Plant Site Evaluation Council (TPPSEC) to consolidate state ap-proval and oversight of thermal power plant siting and operation. In 1976 the authority of this council was extended to all energy sources and '
facilities and it was renamed the Energy Facilities Site Evaluation Coun-cil(EFSEC). The Council consists of the Directors (or their designees) of the various departments of State government which have an interest in or are affected by the construction of energy facilities. The legisla-tion creates a means by which a utility proposing to build and operate a generating plant with capacity in excess of 250 MWe can, through one pro-ceeding, obtain certification from the State for a proposed site of such ,
a generating facility. The issuance of the certificate is in lieu of any ;
permit, license or similar document required for any department, agency, commission or board of the State and has therefore been termed a "one stop" licensing procedure for energy facilities. The original statute i and amendments are codified in the Revised Code of Washington. The regu- r lations adopted to implement the legislation are in Chapter 463 of the '
Washington Administrative Code. ,
As an initial step in obtaining the required approvals the Supply System filed a Site Certification Application for WNP-3 with TPPSEC in December of 1973. This application was amended in July 1974 to include a dupli-O cateunit(WNP-5). Site Certification hearings were commenced in April 1975 and the Site Certification Agreement was signed by the Governor on October 27, 1976. ;
Federal licensing began with the docketing of the Construction Permit .
applications for WNP-3 and WNP-S in August 1974 A Limited Work Authort- I zation was issued for both units in April 1977 and Construction Permits !
were issued in April 1978. As noted in Chapter 1, construction of WNP-S was terminated in January 1982.
Table 12.0-1 lists the permits and approvals required relative to the I protection of the environment. The Bonneville Power Administration is -
constructing the transmission lines and will operate the Satsop Substa- !
tion serving the plants. BPA has responsibility for all approvals and NEPA requirements associated with the transmission facilities. l-i l
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12.0-1 l
WNP-3 ER-OL TABLE 12.0-1 ENVIRONMENTAL PERMITS A'iD APPROVALS REQUIRED FOR CONSTRUCTION AND OPERATION OF WNP-3 Agency Authority Permit / Approval Date of Approval Nuclear Regulatory Com. 42 U.S.C. 2131 et seq., Construction Permit No. CPPR-154 4/78 42 U.S.C. 4321 Operating License (6/85)
Corps. of Engineers 33 U.S.C. 403 (Sec. 10) Construction Permits Nos.
33 U.S.C. 1251 (Sec. 404) 071-0YB-4-003881 4/77 071-0YB-4-003880 5/77 071-0YB-4-004456 3/80
-071-0YB-2-004359 5/80 071-0YB-2-006179 7/80 071-0YB-2-006180 9/80 071-0YB-2-007109 5/81 071-0YB-2-008561 6/83 l2 Washington State Energy Chap. 80.5 R.C.W. Site Certification 10/76 Facility Site Evaluation Council (EFSEC)
EFSEC 33 U.S.C. 466 et seg. Certification of Compliance
> Chap. 463-38 W.A.C. with Water Quality Regula-g tions (401)
=
k National Pollutant Discharge 9/81 a .
Elimination System Permit (402) 2 State Department of EFSEC Cert. Agreement Public Land Leases Nos.
3 Natural Resources Article II.A.2 11660 9/80 x 11661 9/80 2
11687 10/80 11753 7/81 O O O ;