ML18191A013
| ML18191A013 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/17/1978 |
| From: | Washington Public Power Supply System |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18191A013 (172) | |
Text
WNP-2 ER LIST OF TABLES (continued)
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Table No.
- 2. 3-19b
- 2. 3-19c 2.3-19d 2.3-19e 2.3-19f 2.3-19g 2.3-19h
- 2. 3-20
- 2. 3-21 (TEMPERATURE CHANGE LESS THAN -1/9 AND GREATER HAN OR EQUAL -2.1 DEGREES F PER 00 FT)
(TEMPERATURE CHANGE LESS THAN i
.6 AND GREATER THAR OR EQUAL -1.9 DEGREES F
ER 200 FT)
(TEMP RATURE CHANGE LESS TP'
-0.5 AND GREATER THAN 0 EQUAL -1.6 DEGREES F PER 200 FT)
(TEMPE TURE CHANGE LES6 TAHN 1.6 AND GREATER THAN OR QUAL -0.5 DEGREES F PER 200 FT)
(TEMPERAT RE CHANG LESS THAN 4.4 AND GREATER THAN OR EQUAL 1.6 EGREES F
PER 200 FT)
(TEMPERATUR CHANGE LESS THAN AND GREATER THAN OR EQUA 4.4 DEGREES F'PER 200 FT)
(TEMPERATU C ANGE IN DEGREES F PER 200 FT UNKNOWN)
COMPARISON OF MO THLY AVERAGE AND EXTREMES OF HOURBY AVERAG AIR TEMPERATURES COMPARISON OF MONT
.Y AVERAGES OF WET BULB TEMP RATURES
- 2. 3-22a
- 2. 3-22b 2 ~ 3 2 3
- 2. 3-24
- 2. 3-25 F
QUENCY OF OCCURREN E OF WET BULB VALUES FUNCTXON OF TIME OF AY BASED ON WNP-2 SXTE DATA
/74 3/75 MONTHLY AVERAGES OF PSYCH OMETRIC DATA BASED ON PERIOD OF RECORD 1950 1970 MISCELLANEOUS SNOWFALL STAT STICS:
1946 1970 AVERAGE RETURN PERIOD (R)
AN EXISTING RECORD (ER)
FOR VARIOUS PRECIPXTATIO AMOUNTS AND INTENSITY DURING SPECIFIED TXME PERXODS T HANFORD
.3-26a
- 2. 3-26b WNP-2 ONSITE JOINT FREQUENCY DI TRIBUTION OF WINDS FOR RAIN INTENSITY CLASSES, RAI INTENSITY GREATER THAN OR EQUAL TO.016 INCHES PER HOUR RAIN INTENSITY GREATER THAN OR EQ AL TO 0.50 INCHES PER HOUR
WNP-2 ER LIST OF TABLES (continued)
Table No.
2.3-26c RAIN INTENSITY GREATER T1IAN OR l,QUAL TO
. 100 INCIIES PER HOUR 2.3-261 RAIN INTENSITY GREATER TIIAN OR l;:QUAL TO
. 0 1 6 1'NCIll'S PER HOUR 2.3-26e RAIN INTENSITY GREATER TIIAN OR 1'.QUAI. TO
. 500 1 NCHl S PER HOUR 2 ~ 3 2 7 2.4-1 MONTHLY AND ANNUAL PREVAILING DIRECTIONS, AVERAGE SPEEDS, AND PEAK GUSTS:
1945 1970 AT HMS (50 FT LEVEL)
COLUMBIA RIVER MILE INDEX 2.4-2
- 2. 4-3
- 2. 4-4 2.4-5 MEAN DISCHARGES IN CFS, OF THE COLUMBIA RIVER BELOW PRIEST RAPIDS DAM, WA MONTHLY AVERAGE WATER TEMPERATURE g IN C g AT PRI EST RAPIDS
- DAM, WA MONTHLY AVERAGE WATER TEMPERATURE I IN C g AT RICHLAND, WA
SUMMARY
OF WATER QUALITY DATA FOR THE COLUMBIA RIVER AT SELECTED SITES 2.4-6 2.4-7a CHEMICAL CHARACTERISTICS OF COLUMBIA RIVER WATER AT 100 Ff--1970 (RESULTS IN PARTS/MILLION)
SUMMARY
OF WATER QUALITY ANALYSES OF THE COLUMBIA RIVER BELOW PRIEST RAPIDS DAM (RIVER MILE 395)
FOR 1972 WATER YEAR 2.4-7b 2.4-7c 2.4-8 1972 WATER YEAR (cont.)
1972 WATER YEAR (cont.)
AVERAGE CHEMICAL CONCENTRATIONS IN THE COLUMBIA RIVER AT PRIEST RAPIDS DAM, OCTOBER 1971 TO SEPTEMBER 1972 2.4-9 2.4-10 DISCHARGE LINES TO COLUMBIA RIVER FROM 11ANFORD RESERVATION TOTAL ANNUAL DIRECT CHEMICAL DISCHARGE FROM HANFORD RESERVATION TO COLUMBIA RIVER
WNP-2 ER LIST OF TABLES (continued)
Table No.
2.4-11 MAJOR GEOLOGIC UNITS IN THE HANFORD RESERVATION AREA AND THEIR WATER BEARING PROPERTIES 3.3-1 3.5-1
- 3. 5-2
- 3. 5-3 3.5-4
- 3. 5-5
- 3. 5-6
- 3. 5-7
- 3. 5'-8 PLANT WATER USE NOBLE GAS CONCENTRATION IN THE REACTOR STEAM NUMERICAL VALUES CONCENTRATXONS IN PRINCIPAL FLUID AVERAGE NOBLE GAS RELEASE RATES FROM FUEL CONCENTRATIONS OF HALOGENS IN REACTOR COOLANT AT REACTOR VESSEL EXIT NOZZLES (pCi/gm)
CONCENTRATIONS OF FISSION PRODUCTS IN REACTOR COOLANT AT REACTOR VESSEL EXXT NOZZLES (pCi/gm)
CONCENTRATIONS OF CORROSION PRODUCTS IN REACTOR COOLANT AT REACTOR VESSEL EXIT NOZZLES
( pCi/gm)
CONCENTRATIONS OF WATER ACTIVATXON PRODUCTS IN REACTOR COOLANT AT REACTOR VESSEL EXIT NOZZLES (pCi/gm)
RADIONUCLIDE CONCENTRATIONS IN FUEL POOL ESTIMATED RELEASES FROM DRYWELL AND REACTOR BUXLDXNG VENTILATXONS SYSTEMS 3.5-9 3.5-10 3.5-11 3.5-12 3.5-13 3.5-14
- 3. 5-15 ESTXMATED RELEASES FROM TURBINE BUILDING VENTILATION ESTIMATED RELEASES FROM RADWASTE BUXLDING ESTIMATED RELEASES FROM MECHANICAL VACUUM PUMP ANNUAL RELEASES OF RADIOACTIVE MATERXAL AS LIQUID RADWASTE OPERATING EQUIPMENT DESIGN BASIS RADWASTE SYSTEM PROCESS FLOW DIAGRAM DATA (9
PAGES)
EQUIPMENT DRAIN SUBSYSTEM SOURCES
WNP-2 ER LIST OF TABLES (continued)
Table No.
3.5-16 3.5-17 3.5-18 3.5-19 3.5-20 FLOOR DRAIN SUBSYSTEM SOURCES CHEMICAL WASTE SUBSYSTEM SOURCES OFF-GAS SYSTEM PROCESS DATA RELEASE POINT DATA NOBLE GAS RELEASE RATE INTO ATMOSPHERE FROM OFF-GAS SYSTEM 3.5-21 3.5-22 3.5-23 ESTIMATED ANNUAL AVERAGE RELEASES OF RADIOACTIVE MATERIALS FROM BUILDING VENTILATION SYSTEMS, GLAND SEAL AND MECHANICAL VACUUM PUMPS EXPECTED ANNUAL PRODUCTION OF SOLIDS SXGNXFICANT ISOTOPE ACTIVITY ON WET SOLIDS AFTER PROCESSING 3.5-24
SUMMARY
OF RADIOACTIVE EFFLUENT MONXTORING AND CONTROL POINTS
- 3. 6-1 3.8-1 3.9-1
- 5. 1-1 5.1-2 WATER COMPOSITION COLUMBIA RIVER, DEMINERALIZER
- WASTE, COOLXNG TOWER BLOWDOWN RADIOACTIVE MATERIAL MOVEMENT 500 KV AND 230 KV LINE ELECTRICAL CHARACTERISTICS TIMING OF SALMON ACTIVITIES IN THE COLUMBIA RIVER NEAR HANFORD FROM L.O.
ROTHFUS TESTIMONY IN TPPSEC 71-1 HEARINGS (EXHIBIT 62)
ESTIMATED ANNUAL PERCENT PERSISTENCE OF ELEVATED VISIBLE PLUME LENGTHS 5.1-3 ESTIMATED ANNUAL PERCENT PERSISTENCE OF ELEVATED VISIBLE PLUME LENGTHS WITH THE AIR TEMPERATURE 0
C OR LESS 5.1-4 MONTHLY ELEVATED VISIBLE PLUME LENGTHS PERCENT PERSISTENCES 5.1-5 PREDICTED VISIBLE PLUME WIDTHS IN METERS AS A
FUNCTION OF MONTH AND DOWNWIND DISTANCE
WNP-2 ER LIST OF TABLES (continued)
Table No.
5.1-6
SUMMARY
OF FOGGING XMPACT ESTIMATES
- 5. 1-7 INCREASE IN RELATIVE HUMIDITY AT POINTS OF MAXIMUM POTENTIAL IMPACT
- 5. 2-1
- 5. 2-2
- 5. 2-3 5.2-4 5.2-5 5.2-6
- 5. 2-7
- 5. 2-8
- 5. 2-'9 5.2-10 RELEASE RATES AND CONCENTRATION OF RADIONUCLIDES IN THE LIQUID EFFLUENTS FROM WNP-2 RELEASE RATES AND CONCENTRATIONS OF RADXONUCLIDES IN THE AXRBORNE EFFLUENTS FROM WNP-2 ANNUAL AVERAGE ATMOSPHERIC DXLUTXON FACTORS (X/Q')
CONCENTRATIONS OF IMPORTANT RADIONUCLXDES IN VARIOUS ENVIRONMENTAL MEDIA ASSUMPTIONS USED FOR BIOTA DOSE ESTIMATED ASSUMPTIONS USED IN ESTIMATING DOSES FROM THE LIQUID PATHWAY ASSUMPTIONS USED IN ESTIMATING DOSES FROM THE GASEOUS PATHWAY ANNUAL DOSE RATES TO BIOTA ATTRIBUTABLE TO THE WNP-2 NUCLEAR PLANT (mrad/yr)
ESTIMATED ANNUAL DOSES TO AN INDIVIDUALFROM THE LIQUID AND GASEOUS EFFLUENTS OF WNP-2 ESTIMATED ANNUAL DOSES TO AN INDIVIDUALFROM THE LXQUID AND GASEOUS EFFLUENTS OF WNP-2, WNP-1g AND WNP-4 5.2-11 FRACTXON OF RADXONUCLIDE PASSING THROUGH WATER TREATMENT PLANTS
- 5. 2-12
- 5. 2-13 ASSUMPTIONS FOR ESTIMATING DOSES FROM CROPS AND ANIMAL FODDER SUBJECT TO DEPOSITION OF RADIOACTIVE MATERIALS RELEASED BY THE PLANT CUMULATIVE POPULATION, ANNUAL POPULATION DOSE/
FROM SUBMERSION IN AIR CONTAINING RADIONUCLIDES FROM THE WNP-2 AND COMBINED RELEASES OF WNP-2 AND WNP-1 AND WNP-4
WNP-2 ER LIST OF TABLES (continue
)
Table No.
5.2-14 5.2-15 5.3-1
- 5. 8-1 6.1-1 6.3-1 ANNUAL DOSES RECEIVED VIA MAJOR PATHWAYS FOR WNP-2 AND FOR WNP-2, WNP-1 AND'NP-4 COMBINED ESTXMATED ANNUAL POPULATION DOSES ATTRIBUTABLE TO WNP-2 AND COMBINED RADIONUCLIDE RELEASES OF WNP-lg WNP-2 AND WNP-4 MAXIMUM POTENTIAL CHANGE IN COLUMBIA RIVER WATER QUALITY RESULTING FROM WNP-2 CHEMICAL DISCHARGES PRELIMXNARY,ESTIMATES OF DISMANTLING AND DECOMMISSIONING COSTS MASS SIZE DISTRIBUTION OF DRIFT DROPLETS ROUTINE ENVIRONMENTAL RADIATION SURVEILLANCE SCHEDULE 1976 6.3-2
- 7. 1-1
- 7. 1-2 7 ~ 1 3
7.1-4
- 8. 1-1
- 8. 2-1
- 8. 2-2
- 8. 2-3
- 8. 2-4
- 8. 2-5
- 8. 2-6 ENVIRONMENTAL RADIATXON SURVEILLANCE NETWORK WASHINGTON STATE DEPARTMENT OF SOCIAL AND HEALTH SERVICESi HEALTH SERVICES DIVISIONi JUNE 1974 CLASSIFICATION OF POSTULATED ACCIDENTS AND OCCURRENCES RADIATION EXPOSURE
SUMMARY
TABLE OF EVENT PROBABILITIES SOME U.S.
ACCIDENTAL DEATH STATISTICS FOR 1971 ELECTRIC POWER REQUIREMENTS BY MAJOR CONSUMER CATEGORIES IN THE PACIFIC NORTHWEST COST COMPONENTS OF WNP-2 INFORMATION REQUESTED BY NRC ESTIMATED COST OF ELECTRICITY FROM WNP-2 POPULATION DATA FOR THE TRI-CITY AREA PROJECTED SHORT-TERM POPULATION GROWTH IN TRI-CITY AREA XMPACT OF'
SUMMARY
ESTIMATE:
EFFECTS OF TOTAL REGIONAL GROWTH
WNP-2 ER LIST OF TABLES (continued)
Table No.
- 10. 1-1
- 10. 1-2
- 10. 2-1
- 10. 2-2 10.9-1 12.1-1 CAPITALIZED TOWER ENERGY CONSUMPTION COST COMPARISON OF MECHANICAL DRAFT COOLING TOWERS INTAKE SCHEMES DIFFERENTIAL COST COMPARISON COMPARISON OF ALTERNATIVE INTAKE SYSTEMS ALTERNATIVE TRANSMISSION ROUTES PERMITS AND APPROVALS REQUIRED FOR PLANT CONSTRUCTION AND OPERATION X3.3. 3.
WNP-2 ER LIST OF ILLUSTRATIONS 1.1-1 1 ~ 1 2
ESTIMATED VERSUS ACTUAL WINTER FIRM PEAK LOADS PNW-WEST GROUP AREA ESTIMATED VERSUS ACTUAL ANNUAL AVERAGE FIRM LOADS PNW-WEST GROUP AREA
- 1. 1-3 1.1-4
- l. 1-5 1.1-6 1
~ 1 7
- 2. 1-1 2 ~ 1 2
- 2. 1-3 2.1-4 2.1-5 2.1-6 2.1-7 2.1-8 U.S.
PNW (WEST GROUP AREA)
PEAK LOADS ELECTRIC ENERGY REQUIREMENTS BY MAJOR CONSUMER CATEGORIES PACIFIC NORTHWEST (WEST GROUP AREA)
FACTORS CAUSING INCREASE IN ENERGY SALES TO DOMESTIC CONSUMERS IN WEST GROUP OF PNW 1950-1973 WEST GROUP AREA LOAD CRITICAL WATER 1981-1982 ESTIMATED CAPACITY RESERVES 1977-1987 SITE LOCATION MAP HANFORD RESERVATION BOUNDARY MAP SITE PLAN SITE PLOT PLAN HANFORD RESERVATION ROAD SYSTEM HANFORD RESERVATION RAILROAD SYSTEM ORIENTATION MAP OF THE AREA WITHIN A 10-MILE RADIUS OF THE SITE FOR WNP-2 POPULATION DISTRIBUTION IN 25 AND 50 MILE RADII AROUND THE SITE GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 1970 POPULATION WITHIN A 10-MILE RADIUS OF WNP-2 GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 1980 POPULATION WITHIN A 10-MILE RAIUS OF WNP-2 2.1-11 2.1-12 GEOGRAPHIC DISTRXBUTION OF THE ESTIMATED 1990 POPULATXON WITHIN A 10-MILE RADIUS OF WNP-2 GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 2000 POPULATION WITHIN A 10-MILE RADIUS OF WNP-2
WNP-2 ER LIST OF ILLUSTRATIONS (continued)
- 3. 5-3
- 3. 5-4
- 3. 5-5
- 3. 5-6 3.5-7
- 3. 5-8 FL'OW DIAGRAM RADIOACTIVE WASTE SYSTEM FLOOR DRAIN PROCESSING FLOW DIAGRAM CHEMICAL WASTE PROCESSING FLOW DXAGRAM PROCESS OFF-GASS SYSTEM LOW TEMPERATURE N-67-1020 FLOW DIAGRAM OFF-GAS PROCESSING SYSTEM RADWASTE BUILDING FLOW DIAGRAM OFF-GAS PROCESSING TURBINE BUILDING FLOW DIAGRAM HVAC-O.G. CHARCOAL ADSORBER VAULT RADWASTE BUILDING
- 3. 5-9
- 3. 5-10 3.5-11 3.5-12 3.5-13
- 3. 9-1
- 3. 9-2
- 3. 9-3
- 3. 9-4 FLOW DIAGRAM HEATING 6 VENTILATION SYSTEM REACTOR BUILDING FLOW DIAGRAM RADWASTE BUILDING HEATING AND VENTILATION SYSTEM FLOW DIAGRAM HEATING 6 VENTILATION SYSTEM TURBINE BUILDING FLOW DIAGRAM RADXOACTIVE WASTE DISPOSAL SOLID HANDLXNG FLOW DIAGRAM FUEL POOL COOLING AND CLEANUP SYSTEM 500 KV, 230 KV, 115 KV POWER LAYOUT CONFIGURATXONS OF BPA TRANSMISSXON TOWERS 230 KV RIGHT-OF-WAY DETAIL MAP BONNEVILLE POWER ADMINISTRATION"S H. J.
ASHE SUBSTATION
- 4. 1-1
- 4. 1-2
- 5. 1-1 CONSTRUCTION PROGRESS
SUMMARY
WNP-2 PERSONNEL ESTIMATE BLOWDOWN PLUME CENTERLINE TEMPERATURES, RIVER FLOW = 36,000 cfs, BLOWDOWN = 4000 gpm
WNP-2 ER LIST OF ILLUSTRATIONS (continued)
CROSS STREAM TEMPERATURE DISTRIBUTIONS g 1 2 5 FT DOWNSTREAM OF OUTFALL, RIVER FLOW = 36,000 cfs, BLOWDOWN 4000 gpm CROSS-STREAM TEMPERATURE DISTRIBUTIONS, 256 FT DOWNSTREAM OF OUTFALL, RIVER FLOW = 36,000 cfsg BLOWDOWN = 4000 gpm BLOWDOWN PLUME ISOTHERMS RIVER FLOW = 36,000 cfs, BLOWDOWN = 4000 gpm BLOWDOWN PLUME CENTERLINE TEMPERATURES, RXVER FLOW = 120,000 cfs, BLOWDOWN 4000 gpm CROSS-STREAM TEMPERATURE DXSTRIBUTIONS, 21 FT DOWNSTREAM OF OUTFALL'IVER FLOW 120~000 cfs, BLOWDOWN 4000 gpm CROSS-STREAM TEMPERATURE DISTRIBUTIONS, 235 FT DOWNSTREAM OF OUTFALL RIVER FLOW 120@000 cfsg BLOWDOWN 4000 gpm BLOWDOWN PLUME ISOTHERMS g RIVER FLOW 1 2 0 g 0 00 cfs g BLOWDOWN = 4000 gpm
SUMMARY
OF TEMPERATURE EXPOSURE AND THERMAL TOLERANCE OF JUVENILE SALMONIDS EQUILIBRIUM LOSS AND DEATH TIMES AT VARIOUS TEMPERATURES FOR JUVENILE CHINOOK SALMON R.
E.
NAKATANI, EXHIBIT 49, TPPSEC 71-1 hearing SALT DEPOSITION PATTERNS OUT TO 0.5 MILE (lb/acre/yr)
SALT DEPOSITION PATTERNS OUT TO 6.9 MILE (lb/acre/yr)
EXPOSURE PATHWAYS FOR ORGANISMS OTHER THAN MAN EXPOSURE PATHWAYS TO MAN HANFORD ENVIRONMENTAL AIR SAMPLING LOCATIONS DURING 1975 RADIOLOGICAL MONITORING STATIONS AT HANFORD BNW (ERDA)
AND WPPSS
WNP-2 ER LIST OF ILLUSTRATIONS (conty.nued)
Fi ure No.
- 6. 3-3 10.2-1 10.2-2 10.2-3 10.2-4" 10.2-5 10.9-1 10.9-2 10.9-3 STATEWIDE SAMPLING LOCATIONS MODIFIED CONVENTIONAL INTAKE PLAN AND SECTION MODIFIED CONVENTIONAL INTAKE GENERAL ARRANGEMENT PLAN INFILTRATION BED INTAKE GENERAL ARRANGEMENT PLAN INFILTRATION BED INTAKE PLAN AND SECTIONS PERFORATED PIPE INTAKE IN OFF-RIVER CHANNEL OVERALL MAP OF ROUTES "A" AND "B" RIGHT-OF-WAY DETAIL MAP ROUTE "A" AERIAL PHOTOGRAPH OF LAND CROSSED BY TRANSMISSION LINES
- 10. 9-4
- 10. 9-5 LAND USE HANFORD RESERVATION RIGHT-OF-WAY DETAIL MAP ROUTE "B"
1 e
WNP-2 ER a part of the Coordinated System resources unless the System constructing such facilities declares them to be outside the Coordinated System and operates then on an isolated basis.
Signing of the Coordination Agreement did not eliminate the NWPP since some members of the Pool do not have generating facilities that are affected by provisions of the Canadian Treaty, and therefore, are not signa-tory to the Coordination Agreement.
The NWPP coordi-nates the resources of its members, including utilities in British Columbia, who are not in the Coordination Agreement with the resources of the Coordinated System and further assists the area by analyzing and, to the extent possible, solving the operating problems of regional interconnected operation as they arise.
r West Grou Area of NWPP NWPP was divided into two groups early in its exis-
- tence, because of technical communication problems
.within the NWPP, mainly due to the inability of the telephone company to set up conference calls between all members.
Utilities in Montana,
- Idaho, Utah and Wyoming became the East Group and those in Washington, Oregon and Northern California, plus BPA, the Corps of Engineers and the USBR became the West Group.
When PNUCC assigned the responsibility for load and resource forecasting to its Subcommittee on Loads and Resources, all NWPP members were requested to submit relevant data to the subcommittee.
The East Group and British Columbia declined.
The PNUCC Forecast there-fore became known as the West Group Forecast.
The West Group Area utilities serve loads in the area comprised of Northern Idaho, Washington, Oregon except for the southeastern part of the state, a portion of Northern California, the area in Western Montana served by BPA and Pacific Power and Light Company and the area in Southern Idaho served by BPA with resources of the USBR located in that area.
- 1. 1-9
WNP-2 ER f)
Western S stems Coordinatin Council (WSCC)
In 1967 management of the major utilities in 13 western states organized the WSCC in order to improve system reliability through coordinated planning and operation and to assess adequacy of power resources to meet forecasted load.
Full membership is open to all utili-ties in the area who have bulk power supply resources or major transmission facilities that could affect bulk power deliveries.
Associate membership is available to all utilities in the area who do not, meet the require-ments of full membership.
Membership is voluntary.
WSCC through its planning and operating committees has formulated and published "WSCC Reliability Criteria" consisting of two parts, namely:
1)
Reliability Criteria for System Design 2)
Minimum Operating Reliability Criteria Systems in the Pacific Northwest have agreed to adopt these criteria.
WSCC was the first reliability council to be formed.
As other areas organized councils, WSCC promoted the formation of the National Electric Reliability Council (NERC) to which all regional councils belong.
NERC coordinates the activities of all regional councils and correlates regional council replies to requests from the FPC for information relative to reliability and adequacy of power resources and reserves.
The
- NWPP, as a subregion, reports on such matters for all member utilities through WSCC.
l.l.l. 2 West Grou Historical Data PNUCC, since it, was organized, has coordinated planning and forecasting for the West Group area and has a long-term record of reliability in forecasting.
The historical winter peak firm load, the historical 12-month average firm load (energy demand),
and the projections of these same values for each year's West Group Forecast from 1966 through 1975 have been summarized in Tables 1.1-1 (a) and (b) and 1.1-2 (a) and (b) respectively.
This information has also been presented graphically in Figures 1.1-1 and 1.1-2.
- 1. 1-10
WNP-2 ER Clark Count PUD The'istrict makes its own forecasts of peak and energy requirements essentially based on the BPA guidelines adjusted to fit the District's needs.
The forecast is then reviewed in detail with BPA both to ensure that data used are reasonably in accord with regional data and to fit that forecast into those of other BPA cus-tomers.
The forecast is updated annually based on the previous year's data.
A completely independent analy-sis and forecast is made whenever there appears to be a
major change in the demographic or industrial trends.
Chelan Count PUD This utility has two separate systems and makes a
separate forecast for each system since the character of the loads in the systems vary somewhat.
These two forecasts are then combined into a single utility forecast to be submitted to PNUCC.
Historical records of monthly and annual energy con-sumption and system load factors are used for forecast purposes.
By means of computer programs, load growth rates by months are established and monthly percentages of annual energy consumption are determined.
This historical annual energy consumption curve is plotted and extrapolated for the forecast period.
Monthly peak requirements are then determined by applying average historical monthly load factors to forecasted monthly energy consumption.
Gra s Harbor Count PUD This utility prepares a load forecast in cooperation with BPA based on the BPA guidelines, modified to meet, the particular needs of the District.
This major load projection is made on approximately four or five year intervals and updated annually.
The methodology used by these utilities has been included to suggest the detail used in developing the Long-Range Projec-tion.
Three points should be emphasized.
The first is that most of the larger utilities look at their load growth in individual segments, considering population and economic growth within their service areas.
Generally they do not rely on straight projections of historical trends but, temper such projections with insight into causative factors.
1,1-15
WNP-2 ER
- Secondly, BPA, in its capacity of providing regional trans-mission facilities, provides an overview of. the independent forecasts, particularly for the smaller utilities.
- Finally, Table 1.1-1 (a) and (b) and 1.1-2 (a) and (b) together with Figures 1.1-1 and 1.1-2 show the degree of accuracy of the PNUCC at predicting peak demand and energy load.
This record shows a general success of the methodology as applied.
1.1.1.5 Accurac of Forecasts The 10-year history of West Group forecasts compared to loads has been presented in Tables 1.1-1 (a) and (b) and 1.1-2 (a) and (b).
The percent accuracy of the forecast is the difference between actual load experienced and the forecasted load, unadjusted for weather, divided by the forecasted load.
For forecasted
- capacity, the percent accuracy ranges overall from +16.7% to -8.4%.
Accuracy for the three operating years next succeeding the date of forecast ranges from +11.8% to
-6.2%.
For the operating year next succeeding the date.of forecast the accuracy ranges from 11.1% to -3.4%.
The range of accuracy for forecasted energy is as follows:
Overall from 12.4% to -7.3%
Next three operating years 6.4% to -2.2%
Next operating year 5.7% to -0.4%
Because.of the rapidly changing conditions relative to energy use, it is difficult to estimate the accuracy that has been achieved in the forecasts recently issued.
There are a number of factors which must be considered in such an estimate.
The operating years 1972-1973 and 1973-1974 (through December 1973) were very dry.
Coupled with the national energy shortage, these dry months caused a severe reduction in area reservoir storage.
All utilities of the area engaged in intensive conservation compaigns and were able to effect, on the average, a
7% to 8% reduction from expected use of electric power.
Because of these reductions, no mandatory curtailment of firm loads was required.
Weather conditions changed radically in January 1974 with rain and snow falling in abundant quantities.
Reservoirs soon returned to normal elevations and surplus power was gene-rated for transmission to California to assist utilities in that state in fuel conservation efforts.
Precipitation continued in above-normal
- amounts, not only assuring reservior
WNP-2 ER forecasts, will increase the period of inadequate capacity and increase the economic impact on the area.
(See Table 1.1-7)
An additional important advantage of WNP-2 is that it will improve the reliability of the area power supply.
The Pacific Northwest's reliance on hydro-electric power has made it uniquely dependent,
-upon nature.
- 1. 3-5
TABLE 1.1-1(a)
PACIPIC NORTHWEST UTILITIES CONFERENCE COMMITTEE WEST GROUP AREA COMPARISON OF ACTUAL WITH ESTIMATED WINTER PEAK LOADS (MEGAWATTS)
Date of Estimate 1965-66 1966-67 1967-68 1/
1968-69 1969-70 1970-71 1965 (Mar. 1) 11,735 12,706 13,545 14,331 15,334 16,398 1971-72 1972-73
- 1973-74 17,317 18,374 19,741 1974-75 20,968 1966 (Mar. 1) 1967 (Jan.
17) 1968 (Feb.
1) 1969 (Feb.
15) 1970 (Jan.
15) 1971 (Jan.
1) 1972 (Feb.
1) 1973 (Feb.
1) 1974 (Feb.
1) 12,609 13,513 13,919 17,902 19i273 19,234 20,587 20,425 20,425 14,638 15,770 16,798 17,701 18,665 19,995 21,163 15'21 16~ 021 16'22 17 427 18 809 20 277 21 g 694 15,032 15,943 16,927 17,377 18,848
.20,476 21,798 15,645 16,634 17,125 18,531 19,846 21,114 16,424 17,061 18,593 19,762 21,139 17,022 18,407 19,741 20,968 Actual Winter Peak 11,173 11,613 13,309 15,540 15,030 15,725 16,876 18,259 18,695 18,158
.1/ Minimum temperatures of record occurred at a number of weather stations in the Pacific Northwest during December 1968
Date of Estimate 1965 (Mar. 1) 1966 (Mar.
1) 1967 (Jan.
17) 1968 (Feb.
1) 1969 (Feb.
15) 1970 (Jan.
15) 1971 (Jan.
1) 1972 (Feb.
1) 1973 (Feb.
1) 1974 (Feb, 1) 7.9 1.5 4.4 (6.2) 4.7 6.4 (3.4) 6.2 7.1 (3.4) 5.7 7.1 4.7 3.2 2.9 2.2 2.9 3.1 1973-74 1974-75 5.3 6.5 7.8 8.7 13.4 14.2 16.3 16.7 4.0 5.5 4.3 1.5 1.1 1.5 5.8 1.8 5.4 14.0 14.1 0.9 0.8 (1.6) 5.3 3.0 2.8 13.4 11.8 11.1 11.1 TABLE 1.1-1(b)
PACIFIC NORTHWEST UTILITIES CONFERENCE COMMITTEE WEST GROUP AREA PERCENT DEVIATION BETWEEN ACTUAL AND ESTZMATED WINTER PEAK FIRM LOADS 1/
1965-66 1966-67 1967-68 1968-69 1969-70 1970-71 1971-72 1972-73 2/
4.8 8.6 1.8 (8.4) 2.0 4.1 2.5
)/ Minimum temperatures of record occurred at a number of weather stations 'n the Pacific Northwest during December 1968 2/ Parentheses
() indicate actual loads.greater than estimated loads
. TABLE 1.1-2(a)
'ACIFIC NORTHWEST UTILITIES CONFERENCE COMMITTEE WEST GROUP AREA COMPARISON OF ACTUAL WITH ESTIMATED 12 MONTHS AVERAGE FIRM (MEGAWATTS) 1 LOADS Date of Estimate 1965-66 1966-67 1967-68 1968-69 1969-70 1970-71 1971-72 1972-73 1973-74 1974-75 1965 (Mar. 1) 1966 (Mar. 1) 1967 (Jan.
17) 1968 (Feb.
1) 1969 (Feb.
15) 1970 (Jan.
15) 1971 (Jan.
1) 1972 (Feb.
1) 1973 (Feb.
1) 1974 (Feb.
1) 10,807 11,688 12,507 11 g 541 12g 375 13,279 13,100 12,409 13,054 12,971 7g 369 8g 015 8 536 8 975 9 615 10g 285 10 779 11 g 381 12g 255 12g 928 7g 934 8g 540 9g 311 10g 104 10g 752 llg260 llg788 12g603 13 279 8 888 9g 562 10 252 10g826 llg056 llg852 12 815 13g663 9g 649 10g 970 10g 970 llg215 12g 112 13g 277 14 081 10,061 10,745 11,020 11,868 12,730 13,565 10,617 10,964 11,988, 12,779 13,681 Actual 12-Mo. Avg.
7,248 7,967 8,722 9,628 10,101 10,537 10,694 11,321 11,703 12,329 Firm loads differ from total loads by the interruptable loads supplied by BPA to large industrial customers Firm loads are us'ed in this comparison because of the high variability to interruptable loads Source:
BPA Requirements
- Section, unpublished data, September 9,
1975
TABLE 1.1-2(b)
PACIFIC NORTHWEST UTILITIES CONFERENCE COMMITTEE WEST GROUP AREA PERCENT DEVIATION BETWEEN ACTUAL AND ESTIMATED 12 MONTHS AVERAGE FIRM LOADS 1
Date of Estimate 1965-66 1966-67 1967-68 1968-69 1969-70 1970-71 1971-72 1972-73 1973-74 2
1965 (Mar. 1)
- l. 6 0.6 (2.2)
(7. 3)
(5.0)
(2. 4) 0.8 0.5 4. 5 1974-75 4.6 1966 (Mar. 1) 1967 (Jan.
17) 1968 (Feb.
1) 1969 (Feb.
15) 1970 (Jan.
15) 1971 (Jan.
1) 1.9 (0.7) 1.5 2.7 0.2 1 ~ 9 3.9 (0.4) 1.9 0.8 (0-4)
(2.1)
(3.4) 2.0 5 '
3.3 4.7 3.0 2.5 1.0 4.0 7.1 4.6 5.6 3.1 8.1 8.4 6.4 4.5 8.7 6.5 11.9 7.1 9.8 12.4 9.1 9.9 7.1 1972 (Feb.
1) 1973 (Feb.
1) 1974 (Feb.
1) 1.9 5.4 5.7 5.9 5.5 4.9 Minimum temperatures of record occurred at a number of weather stations in during December 1968 2Parentheses
() indicate actual loads greated than estimated loads Source:
BPA Requirements
- Section, unpublished data, September 9,
1975.
the Pacific Northwest
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report RAPHIC CALE SITE PIDZ PLAN FIG. 2. 1-4
0'
NNE WSW 10 0
0 0
0 0
0 0
p 0
p 0
0 0
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0 240 240 240 280 ENE ESE SW 6120 SE SSW 10 S
SSE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 2010 POPULATION WITHIN A 10-MILE RADIUS OF WNP-2 FIGHT
, 2.1-13
NNE W
p WSW 0
0 0
0 p
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p 0
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SSE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 2020 POPULATION WITHIN A 10-MILE RADIUS OF WNP-2 FIG. 2.1-14
NNW 17,650 NW 1100 2550 NE WNW 390 550
- 190, 10 760 360 5020 1p 370 360 110 ENE p 60@
0 gS 0
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12, 790 2450 100 0
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SSE 2910 SE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO ~
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 1970 POPULATION WITHIN A 50-MILE RADIUS OF WNP-2 FIG. 2.1-15
NNW 17,850 NNE 1420 880 2850 550 190 760 360 5690 360 370 110 ENE W
14 010 WSW 3330 220 2400 620 70 60 a o',e 0
330 0
c"Q x< ~ - ~ +0 10 510 260 200 2450 100 0
240 110 130 22, 100 20,550 470 1120 780 6330 46, 910 5070 13, 240 20 ESE SW 100 1590 SSW 30 1490 13,550 SSE 2910 SE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 1980 POPULATION~
WITHIN A 50-MILE RADIUS OF WNP-2 FIGHT 2.l-l6
17, 950 NNE 1580 NE 550 570 0
370 1030 110 ENE 3330 110 130 3560 ESE 21,540 850 1120 22O 0
~ g8 620 0
W 14,620 2450 100 0
0 330 510 0
200 200 24O 2080 23, 180 u10 3360 3020 52, 580 WSW 14,300 500 20 SW SSW 40 14,860 50 S
SSE 2910 SE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 1990 POPULATION WITHIN A 50-MILE RADIUS OF WNP-2 FIGHT 2.1-17
910 18, 000 NNE 1660 3070 1360 760 360 5970 190 10 370 10 1310 360 220 p 60@
p 0
Zg 0
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'0 6680 321p 55,420 14,830 20 22,030 30 1750 2280 15,510 W
14, 930 2450 100 0
1890 3590 110 1120 2910 SE 1040 ESE
, ~
SSW 50 S
SSE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOCRAPHIC DISTRIBUTION OF THE ESTIMATED 2000 POPULATION WITHIN A 50-MILE RADIUS OF WNP-2 FIG. 2.l-ls
910 18,050 040 3150 1370 NE 550 360 760 6070 360 370 10 1310 1040 3840 2080 24, 260 5370 WSW 850
.100 640 30 1830 22,530 1120 2910 70 0
4'g 620 0
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0 330 510 700 200 200 0
900 10
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~O 240 dP'I Q 1280 110 6810 3380 3400 58, 250 i5,M '830 500 20 ESE 2510 SSW 40 16, 170 SSE SE GEOGRAPHIC DISTRIBUTION WASHINGTON PUBLIC POWER SUPPLY SYSTEM OF THE ESTIMATED 2010 POPULATION WPPSS NUCLEAR PROJECT NO.
2
'WITHIN A 50-MILE RADIUS OF WNP-2 Environmental Report FIG. 2.1-19
NNW 910 18, 200 NNE 530 1820 WNW 390 670 550 70 6170%
0 370 360 1310 1910 ENE 110 4430 WSW 24,800 5440 850 SW 670 W
15,530 2450 108 0
1360 100 590 16,360 63'910 20 3960 23,030 30 1910 40 0 p 620 0
0
- 330, 51p
~~ I +g 240 10 6940 110 1120 130 2910 SE 500 ESE 2740 SSW 16, 830 50 S
720 SSE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report GEOGRAPHIC DISTRIBUTION OF THE ESTIMATED 2020 POPULATION WITHIN 50-MILE RADIUS OF WNP-2 FIGHT 2.1-20
WNP-2 ER subject to population fluctuations, the causes of which are research subjects.
On the Hanford Reservation, hares are a
. food source for coyotes,
- bobcats, and especially the Golden eagle in winter months when eagles are usually present.
2.2.1.1 Rare and Endan ered S ecies The plants and animals living in the WNP-2 area are widespread and common in steppe vegetation (rangeland) in the dry parts of Eastern Oregon and Eastern Washington.
- However, rangeland acreage diminishes each year primarily as a result of an expanding agricultural use of land through extension of irrigation systems.
As the land is converted from rangeland to irrigated agriculture, native plant and animal populations diminish.
One function of the 100 square mile area of Arid Lands Ecology (ALE) Reserve (Rattlesnake Hills Research Natural Area) on the Hanford Reservation is to provide a
refugium for native plants and animals.(4)
At the present time, the raptorial birds are regarded as the animal group most in need of protection.
The construction and operation of the nuclear facility is not expected to result in the damage or loss of any species presently regarded as endangered.
2.2.2 A uatic Ecolo The basic physical and chemi.'cal characteristics of the Columbia River in the vicinity of WNP-2 were presented in previous sections.
References 5,
6, 7 and 12 present addi-tional nonbiological data as well as comprehensive evaluations of the ecological characteristics of the Columbia River.
Studies concerned with the various aquatic organisms in the Columbia River, relating mainly to influence of reactor operation, were conducted for over 25 years; a bibliography with abstracts of these investigations was recently pub-lished.(8)
The following paragraphs summarize the essential ecological characteristics of the major communities.
Figure 2.2-2 is a simplified diagram of the food-web rela-tionships in selected Columbia River biota and represents probable major energy pathways.
The Columbia River presents a very complex ecosystem in terms of trophic relationships due to its size, the number of man-made alterations, the diversity of the biota, and the size and diversity of its drainage basin.
Streams in general, especially smaller ones, depend greatly upon allocthonous input of organic matter to drive the ener-getics of the system.
Large rivers, particularly the Columbia because it is a series of lentic reservoirs, contain a
2 '-3
WNP-2 BR significant population of autochthonous primary producers (phytoplankton and periphyton) which contribute the basic energy needs.
The dependence of the free-flowing Columbia River in the Hanford area, upon an authochthonous food base is reflected by the faunal constituents, particularly the herbivores in the second trophic level.
Filter-feeding periphyton grazers such as limpets and some mayfly nymphs are typical forms present.
Shredders and large detrital feeders (such as the large stonefly nymphs) which are typical of smaller streams are absent.
The presence of large numbers of the herbivorous suckers also attests to the presence of a significant periphytic population.
Carnivorous species are numerous, as would be expected in a system of this size.
A list of aquatic organisms identified from the Columbia River is presented in Table 2.2-l.
Diatoms are the dominant algae in the Columbia River, usually representing over 90% of the population.
The main genera include Fra ilaria, Asterionella, Melosira, Tabellaria, and behind the upstream dams are dominant in this section of the river.
The phytoplankton also contain a number of species derived from the periphyton or sessile algae community.
This is particularly true of the Columbia River in the vicinity of WNP-2 because of the fluctuating daily water levels due to operation of Priest Rapids Dam immediately upstream from Hanford.
Periphytic algae exposed to the air for part of the day may dry up and become detached and suspended in the water when the river level rises again.
Peak biomass of net phytoplankton is about 2.0 g dry wt/m3 in May and winter values are less than 0.1 g dry wt/m3.I'9)
Figure 2.2-3 illustrates the seasonal fluctuations in plankton biomass.
A spring increase-with a second pulse in late summer and autumn was observed in the Hanford section of the Columbia River in previous studies.<l01ll)
The spring pulse is probably related to increasing light and warming of-the water rather than to availability of nutrients.
The coincident decrease of P04 and N03, essential nutrients for algae growth, may be partially related to uptake by the increasing phytoplankton populations but, is also highly influenced by the dilution of these nutrients by the increased flows due to high runoff at this time.
The degree of dilution depends upon the concentration of these nutrients in the runoff waters.
- However, these nutrients do not decrease to concentrations limiting to algae growth at any time of the year.
Green and blue-green algae occur mainly in the warmer months but in substantially fewer numbers than the diatoms.
2.2-4
WNP-2 ER 2.3 METEOROL'OGY The Hanford Reservation lies in the Lower Columbia Basin, lowest elevation of any part of Central Washington.
The low elevation assists in creating a relatively mild continental steppe climate, subject to somewhat wide seasonal range in temperature.
Annual precipitation of approximately 6.4 in.
falls mainly during the winter months.
The average summer temperature is 73.7'F, while during the winter months the mean daily'emperature is 32.4'F.
The primary source of meteorological data for WNP-2 is the 240-ft tower with a complete meteorological data
- system, which has been operational since March 1974.
The Hanford Mete-orology Station (HMS) and the 410-ft Hanford Meteorology Tower located about 14 miles northwest of the WNP-2 site provided the data for the construction permit Environmental Report.
A 23-ft temporary meteorology tower was was operated for 2 years previous to the installation of the 240-ft tower for the purpose of evaluating cooling tower orientation.
The meteorological equipment located at these sites is discussed in Subsection 6.1.3.
Table 2.3-1 presents the averages and extremes of various climatic elements at Hanford revised to include data up to and including 1975.
More comprehensive climatological summaries of Hanford data are presented by Stone(l) based on observations up to 1970.
The data for the following subsections are detailed in the tables and figures.
2.3.1 Stabilit
, Wind S eed and Direction Annual average wind roses for the site are given in Figures 2.3-1 to -6.
The wind rose in Figures 2.3-1, -2 and -3 are for onsite data for the three measurement heights (7,
33 and 245 ft).
Figure 2.3-4 gives the onsite wind rose breakdown by four Hanford stability classes at the 33-ft level.
HMS wind roses for the 200-ft level derived from 15 years of data (1955-1970) are given in Figure 2.3-5.
Surface winds at various stations in the region are summarized as 8-point roses in Figure 2.3-6.
The onsite joint frequency of wind speed, direction and stability data for winds at 33 ft are contained in Table 2.3-2 for five classes of Hanford stability criteria while Table 2.3-3 contains the annual summaries for 7, 33, and 245 ft for direction and speed.
Tables 2.3-4 through -15 present joint distributions of wind speed and direction on a monthly basis (April 1974 through March 1975) for the onsite data.
Table 2.3-16 shows the joint distribution of stability, wind speed and direction derived from 15 years (1955-1970) of data taken at the HMS tower.
These seasonal and annual tables are based on winds at 200 ft and stability defined by the tempera-ture difference between the surface and 200 ft.
203-1
WNP-2 ER The climatological representativeness of the year of onsite data used in the diffusion computations is listed in Tables 2.3-17 and -18.
Table 2.3-17 is a month by month comparison of climatic elements at HMS with longer term values.
Average wind speed, insolation, precipitation, and relative humidity were close to the long-term values.
Table 2.3-18 presents a summary comparison of diffusion elements computed from the 1 year of WNP-2 data with similar elements computed from 15 years HMS data.
The difference in the number of recorded calms is primarily the result of the lower threshold of the onsite instruments, these differ-ences may also be partly the result of topogiaphic influences.
The wind direction frequencies cannot be expected to neces-sarily be comparable because of the separation between the stations.
Comparison of the HMS and onsite data demonstrate differences which are readily attributable to local topo-graphical effects such as the orientation of the river valley near the site.
Although the differences in the stability classes are partly the result of the layer used for the stability definition, there is some evidence that part of the greater percentage of stable conditions at WNP-2 may be a
real difference.
Tables 2.3-19a through -19h contain joint frequency summaries of the onsite data grouped by Pasquill stabilities categories.
Table 2.3-20 contains a temperature comparison between the WNP-2 site and HMS.
These onsite temperatures are from the 7-ft level on the new meteorological system.
By assuming an adiabatic lapse rate of 0.548'F/100 ft, over the 283-ft elevation difference between HMS and the WNP-2 site, a tempera-ture difference can be expected of about 1.5'F between the dry bulb temperature data measured at the two sites.
2.3.3 H~umidit Table 2.3-21 gives a comparison of monthly wet bulb tempera-tures from the 1 year of onsite data and HMS.
Table 2.3-22 contains the frequency occurrence of wet bulb values as a
function of time of day based on data from the onsite m'eteoro-logical system.
Figures 2.3-7 to -10'ndicate diurnal and monthly and annual averages and extremes of temperature and humidity at HMS.
Summaries of onsite humidity data have been prepared both on a monthly and annual basis in joint, frequency wind speed direction formats.
Xn addition, computer tapes of hourly summarized operation including humidity data have been generated.
2 ~ 3 2
WNP-2 ER During July 1975 the moisture in the lower atmosphere at HMS was abnormally high.
In the period of record, 1957-1970, hourly wet bulb temperatures in a range 70 to 74'F had occurred an average of three times each July.
In the period July 4 through July 12, 1975, there were 104 hourly observa-tions in the range 70 to 74'F.
On July 9 there were 17 consecutive hours in that range.
Wet bulb temperatures of 75'F have not occurred in the Hanford area until this episode.
On July 8, 9, and 10 there were a total of seven such hourly observations.
The air temperatures were also high during this period.
The HMS average relative humidity for July 1975 was 37.5% compared to the record of 40.5 set in 1955.
Figures 2.3-7 to -10 and Table 2.3-1 and Tables 2.3-23 present additional climatological humidity information from the HMS.
Precipitation data are presented in Figures 2.3-11 and -12, and Tables 2.3-24 and -25.
Tables 2.3-26a through e are joint wind direction and speed summaries of rainfall inten-sities over the year of onsite data.
No deviation from the regional low precipitation pattern was found.
2.3.5 Hi h Velocit Winds Surveys of data on high winds over this region indicate that higher winds tend to occur at the higher, more exposed eleva-tions, although all sites in this region have experienced relatively high winds.
High wind speeds result from squall lines, frontal passages, tight pressure gradients and thunder-storms.
One small tornado has been observed on the Hanford Reservation.
There is indication that this area has been affected by hurricanes, but no complete statistics are readily available that present frequency of occurrence of high winds produced or accompanied by a particular meteorological event.
The highest reported winds produced at HMS by any cause are tabulated in Table 2.3-27.
The Hanford tower is at a slightly higher elevation and hence might be expected to experience higher winds than at the WNP-2 site.
Although based on differ-ent periods this tendency may be inferred from Tables 2.3-17 and 2.3-18.
Figure 2.3-13~2>
indicates the return probability of any peak wind gust at HMS again due to any cause.
The highest recorded peak gust at the 50-ft level at HMS in the period 1945 to the present was 80 mph.
2.3.6 Severe Weather Since the submission and the construction permit Environmental Report the local climatology for thunderstorms and tornados 2 ~ 3 3
WNP-2 ER has not significantly changed.
No additional observations of tornados have been made in the Hanford region.
The frequency of occurrence of thunderstorms has been updated in Table 2.3-1.
2.3-4
WNP-2 ER TABLE 2.3-27 MONTHLY AND ANNUAL PREVAILING DIRECT IONS g AVERAGE SPEEDS g
AND PEAK GUSTS:
1945-1970 AT HMS (50 foot '1'evel)
MONTH PREVIOUS DENSITY AVERAGE SPEED HIGHEST AVERAGE YEAR LOWEST AVERAGE PEAK GUST YEAR SPEED DENSITY YEAR Jan 6.4
- 9. 6*
1953 3.1 1955 65**
1967 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec YEAR WNW WNW WNW NW NW 7.0 8.4 9.0 8.8 9.2 8.6 8.0 7.5 6.7 6.2 6.0 7.6 9.4
- 10. 7
- 10. 5
- 10. 7 9.6 9.1 9.2 9.1 7.9 8.3 8.3 1961 1964 1959 4.6 5.9 7.4 1949 1963 1946 1961 1946 1945 1968 1968+
7.7 6 ~ 8 6 ~ 0 5.4 4.4 2.9 3.9 6.3 1965+
5.8 1963 63 1958 70 1958 60 1957 71 1950+
72 1955 55 1956 66 1957 65 1952 63 1956 64 1963+
71 1957 72**
SW 1965 WSW SSW SW WSW SW SSW SSW SSW SW SW 1969 1948 1957 1968
, 1961 I
1953 1950 1949 1955 1957 (Jun)
SW 1956 T e average speed for January,
- 1972, was 10.3 mph.
On January ll, 1972, a new all-time record peak gust of 80 mph was established.
0 1
2 3
4 5
6 7
WIND SPEED GROUPS (MPH) 0 -3 LINE 4 7 SHADE 8-12 OPEN 13 - 18 SHADE 19 - 24 OPEN 25 UP SHADE WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report WIND ROSE FOR WNP-2 FOR 4-74 TO 3-75 AT 7 FT LEVEL FIG. 2.3-1
WNP-2 ER 2.4 HYDROL'OGY The WNP-2 site is located at an elevation of 441 ft above mean sea level (MSL) about 3 miles west of the Columbia River at River Mile 351.75 and about 8 miles northeast of the Yakima River at Horn Rapids Dam.
The major waters that, could be affected or influenced by plant operation are the Columbia River and the groundwaters of the site and the immediate environs.
2.4.1 Surface Water 2.4.1.1 Columbia River Flows The Columbia River and its tributaries are the dominant water systems in the Pacific Northwest region (Figure 2.4-1).
The main stem of the Columbia River originates at Columbia Lake on the west slope of the Canadian Rockies and flows into the Pacific Ocean near Astoria, Oregon.
The river drains a total area of approximately 259,000 square miles in Canada, Washington,
- Wyoming, and Nevada.
The Columbia River drainage upstream of the WNP-2 site is approximately 96,000 square miles.(1)
Since a large part of the Columbia River originates as runoff caused by snowmelt, high discharges are experienced in late spring or early summer while low discharges occur in winter.
Numerous dams and reservoirs have been constructed in the Columbia River Basin for power production, irrigation, navigation, flood control, and recreation.
Table 2.4-1 lists the major Columbia River tributaries and main stem dams with their location by ri.ver mile above the Columbia River mouth.(>)
The reservoirs maintain approximately 46.7 million acre ft of -active storage gf which 37.5 million acre-ft are upstream of the WNP-2 site.~
)
Arrow and Mica Dams in Canada and Grand Coulee and John Day Dams in the United States are the only main stem projects providing sufficient storage for seasonal flow regulation, while the remaining main stem dams are run-of-river projects providing only daily flow control.
Much of the activities of flood control and hydroelectric power production are presently controlled under the Columbia Treaty between Canada and the United States.(
The Columbia River is tide-affected from the mouth to Bonneville Dam (River Mile 146).
The only other stretch of free flowing river is the 49-mile reach downstream from Priest Rapids Dam (River Mile 397) to the head (approximately River Mile 348) of the reservoir behind M'cNary Dam.(5)
The proposed Ben Franklin hydroelectric dam site on the Columbia 2.4-1
WNP-2 ER River is about 4 miles downstream from the NNP-2 site.
The U.S.
Corps of Engineers advised that this is not a Federally authorized project.(6)
The flows in the Columbia River in the vicinity of the site are highly regulated by Priest Rapids Dam located approxi-mately 45 river miles upstream from the site.
The momentary minimum discharge of the Columbia River at Priest Rapids was recorded to be 4120 cfs in 1936 before the construction of Priest Rapids Dam which was built in 1956.
After the con-struction of the dam; the daily river discharge at Priest Rapids has never been below 36,000 cfs, the minimum flow administra-tively set by the Federal Power Commission License.
The annual average discharge for 55 years measured at the United States Geological Survey gauging station (River Mile 395.5) just below the dam is 120,800 cfs.
)
For the water year of 1972 (October 1971 to September 1972), the mean discharge was 155,800 cfs, while the maximum and minimum daily discharges were 431,000 and 36,100 cfs, respectively.
Monthly discharges below Priest Rapids Dam for the period 1928 through 1958 adjusted for 1970 conditions are presented in Table 2.4-2.
The listed flow values represent measured flows which were adjusted to reflect flow regulation by dams and diversions existing in 1970.
Discharge duration curves derived from these values are shown in Figure 2.4-2.
Because of the regulation, it is estimated that the minimum and maximum mean monthly flows will be 60,000 and 260,000 cfs in the vicinity of the site.
The flow in this reach varies not only due to seasonal floods but also due to daily regula-tion by the power-producing Priest Rapids Dam.
Flows during the late summer, fall, and winter may vary from a low of 36,000 cfs to as much as 160,000 cfs during a single day.
The four largest known floods occurred in 1876,
- 1894, 1948, and 1956.
The 1894 flood was the maximum known flood on the Columbia River near the proposed site and had an estimated discharge of 740,000 cfs.
The largest recorded flood occurred in 1948; a flow of 690,000 cfs was recorded at Hanford.
The maximum possible flood (MPF) under present regulated conditions has been estimated by the U.S. Corps of Engineers to be 1,440,000 cfs at Ringold (River Mile 357).
Figure 2.4-3 shows the exceedance frequency for annual momentary peak flows below Priest Rapids Dam derived from 1913 to 1965 records adjusted for 1970 conditions.
)
The (7) frequency curves for both high and low flows for the period of 1929-1958 adjusted for 1970 conditions are given in Figure 2.5-4.
The minimum 7-day average flow between 1960 and 1972 was 46,000 cfs.
2.4-2
WNP-2 ER 4000 yards downstream, turbulent mixing occurs and the plume becomes well mixed across the river width.
The calculated temperature increment for complete mixing at the minimum river flow rate of 36,000 cfs would be 0.6'C (1.1'F).
Out-side a limited mixing zone, river temperatures would be in compliance with the Washington State Water Quality Stan-dards(21) for incoming river water temperatures up to about 19~C (66.2 F).
All other heat releases from the Hanford Reservation to the river are much smaller and contain only about 1-o of the total releases to the river.
The total heat input is about 470 MW.(25)
During N Reactor operation, a cooling water stream of about 140 cfs with a temperature up to l6'C (28.8'F) above ambient river temperature discharges to the river.
This discharge increases the river temperature by only 0.14'C (0.25'F) at the minimum river flow rate of 36,000 cfs and 0.04'C (0.08'F) at the average river flow rate of 120,000 cfs.(25)
Chemicals are released to the Columbia River at three loca-tions:
- 1) the 100-N Area,
- 2) the 100-K Area, and
- 3) the 300 Area.(2
)
The quantities of chemicals released are shown in Table 2.4-10.
The current primary source of chemicals released to the river is the 100-N Reactor operation.
In addition to these chemicals, impurities removed from the river water by the treatment plants also are returned to the river.
The effect of returning those impurities to the river can be considered to be negligible because almost all of the purified water is returned to the river either in process sewers or as groundwater.
As a result, the average chemical content of the river is essentially unchanged.(2>)
Several of the smaller effluent streams, consisting largely of treated water, may contain free chlorine at concentrations up to a maximum of 1 mg/R.
Other chemical concentrations in treated water are mostly the result of use of alum (aluminum sulfate) and small quantities of proprietary materials in the water filtration plant.
None of these are present in the treated water in toxic concentrations, and the usual small change in pH leaves the treated water well within the State Water Quality Standards.
Filter backwash contains suspended solids, principally an aluminum hydroxide floe plus an accumulation of suspended solids removed from the raw river water during the filtra-tion process.
Although the effluent may be visibly of higher turbidity during the intermittent backwash operation, the daily fluctuation of several feet in river elevation along with the high river velocity and rapid mixing prevent any appreciable buildup of these solids at the discharge points.
2.4-7
WNP-2 ER Trace addition of radioactivity induced by passage of river water through Hanford production reactors with once-through cooling has ended with the shutdown of the reactors.
2.4.2 Groundwater The Hanford Reservation is underlain by three principal rock
- types, from top to bottom:
- 1) unconsolidated silts,
- sands, and gravels;
- 2) semiconsolidated lake and stream sediments (Ringold formation);
and
- 3) dense, hard basalt which forms the bedrock beneath the area. (27)
The lithologic character and water bearing properties of the several geologic units occurring in the Hanford area are summarized in Table 2.4-11.
In general, groundwater in the superficial sediments occurs under unconfined conditions, while water in the basalt bedrock occurs mainly under confined conditions.
In some areas the lower zone of the Ringold formation is a confined
- aquifer, separated from the unconfined aquifer by thick clay
- beds, and possesses a distinct, hydraulic potential.
Figure 2.5-14 shows a simplified geological cross section of the Hanford Reservation.
Wells 699-9-E2, 699-10-E12, 699-14-E6, shown in this figure are located in the vicinity of the project site.
From 1944 through 1972, the Hanford chemical processing plants discharged to the ground over 130 billion gallons (4 x 105 acre-ft) of wastewater and cooling water with a profound effect on the regional water table.
Figure 2.4-15 shows the unconfined water table contours over the area interpreted from measurements in September 1973.
It also indicates the locations of wells.
As shown in this figure, the impermeable aquifer boundaries are the Rattlesnake Hills, Yakima Ridge, and Umtanum Ridge on the west and southwest sides of the Reservation.
Gable Mountain and Gable Butte also impede the groundwater flow.
The current estimate of the maximum saturated thickness of the unconfined aquifer is about 230 ft.
In the vicinity of the project site this thickness is approximately 100 ft to 160 ft.
The depth to the water table varies greatly from place to place depending chiefly on local topography, ranging from less than 1 to more than 300 ft below the land surface.
The ground surface is about 60 to 70 ft above the water table at the WNP-2 site.
The groundwater flows to the Columbia River in a direction perpendicular to the contour lines shown in Figure 2.4-15.
Groundwater flow near the river up to 3 miles inland is affected by seasonal river stage fluctuations.(28)
- 2. 4-8
WNP-2 ER The natural recharge due to precipitation over the low lands of the Hanford Reservation is not measurable.
The major artificial recharge of groundwater to the unconfined aquifer occurs near the 200 East and 200 West Areas.
As is clearly shown in Figure 2.4-15, the large volumes of process water disposed to ponds at this site have caused the formation of significant mounds in the water table.
The points of signifi-cant withdrawals at the present time are for construction purposes at the FFTF site (400 Area) and the WNP-1, -2 and -4 sites.
These are temporary withdrawals of groundwater and affect only the local groundwater flow patterns.
Upon reaching the water table, chemical and radioactive contaminants from the 200 Area disposal sites are convected in the direction of groundwater movement.
Nitrate (N03) In) tritium (3H) ions had reached the project site in 1972.(
However, the plume of gross beta emitters calculated as (iddRu) does not reach the site at Q~ present time and is not likely to do so in the future.(
East of the Columbia River is a very intensive 500,000 acre irrigated farming area (Columbia Basin Project area).
The water table in that region is 40 to 60 ft higher than the river elevation.
The water table in the region between Eltopia and Pasco has risen 40 to 60 ft since 1960(
)
due to an increase in irrigation in the area.
Although no specific studies have been conducted, it is apparent from the water table elevations that the flow of water is into the Columbia River. It is believed that there is a hydrau-lic connection between the unconfined aquifers under the Hanford Reservation and under the Columbia Basin project area.
Groundwater east of the Columbia River may be contaminated by the agricultural activities.
However, the Columbia River acts as a discharge boundary for the uncon-fined aquifers.
An underground disposal site for radioactive wastes is located immediately adjacent to the northwest corner of the WNP-2 site (Figure 2.1-3).
The disposal site covers an area of 8.6 acres and was used between 1962 and 1967 to dispose of a broad spectrum of low-to high-level radio-active wastes, primarily fission products and plutonium.(31)
Cartoned low-level waste was buried in trenches, and medium-to high-level waste was buried in caissons or pipe facili-ties.
The buried wastes are approximately 45 ft above the water table.
Two standby wells with a maximum permitted pumping rate of 5000 gpm can provide potable and cooling tower makeup water to WNP-2 in emergencies should the river water supply fail or be insufficient.
The wells are 234 and 244 ft deep and obtain their water from the unconfined aquifer in the Ringold formation.
2.4-9
WNP-2 ER
'ABLE 2. 4-1 COLUMBIA RIVER MILE INDEX River Mouth Bonneville Dam The Dalles Dam John Day Dam McNary Dam Snake River Descri tion Yakima River WNP-2 Intake and Dischar e
Proposed WNP-1 and 4 Intake and Discharge Existing Hanford Generating Plant Priest Rapids Dam Wanapum Dam Rock Island Dam Wenatchee River Rocky Reach Dam Chel'an River Wells Dam Chief Joseph Dam Grand Coulee Dam Spokane River United States-Canadian Boundary River Mile 0.0 146.1 191.5 215.6 292.0 324.2 335.2 351.75 351.85 380.0 397.1 415.8 453.4 468.4 473.7 503.3 515.6 545.1 597.6 638.9 745.0
E = 342.2MSL Ml LE 352 10 E = 342.0MSL MlLE 351.8 10 E
341.7 MS L MILE 351.5 10 MlLE 351.3 E - 341.5 MSL P
10 COLUMB IA RIVER Q = 36,000 CFS 200 400 600 800 1000 D I STANCE F ROM WEST BANK, ft WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report CROSS SECTIONS OF THE COLUMBIA RIVER IN THE PLANT VICINITY FIGHT 2.4-5
E15500 E16000 E16500 E17000 XMO r.q w 0 Otal g
f WO O Ul 0 Rt ct R W OV N13000 N12500
)
PUMP HOUSE
)
3 P IPES 36" WNP-1 AND 4 24 DISCHARGE PIPE WNP-1 AND WNP-4
- .:."" W a.. ~
~.t"...W
(
330 NP-1 AND WNP-4 INTAKE
R IVER MILE351.86 R I VER M I LE 351.85
//
I-I 0 R 0 M t3 QO R Z I 0 R R I
R v a U
ItV ~
A N12000 N11500 C-
)
WNP2
/
INTAKE (~
370 360 I
EDGE OF RIVER AT 120,000 cfs 350
."..".",.,'NP-2 INTAKE Rl ER M LE 51'75 l
WNP-2 D I SCHARGE P I PE 175 FEET OFFSHORE j
EDGE OF RIVER AT
'6,000 cfs
WNP-2 ER blowdown flow, returned to the Columbia River, will average 2580 gpm.
A detailed discussion of the heat dissipation
'system is given in Section 3.4.. Environmental effects are described in Section 5.1.
3.3.3 Process Water Treatment S stems Process water treatment systems prepare river water for station use, potable and sanitary water use, and miscellaneous water requirements.
River water is first. treated by filtra-tion for the removal of suspended matter.
A maximum of 250 gpm of filtration capacity is provided.
Xt is antici-pated that the average operating demand for filtered water will be approximately 10 gpm.
The makeup water demineralizer provides high quality water for station use including filling of the nuclear steam supply
- system, chemical control solution preparation, the replacement of evaporation and tank vent losses and the water lost in the solids from the radioactive and chemical waste system disposed of off-site.
Virtually all liquid wastes from normal sta-tion operations are treated in the radioactive and chemical waste system.
The full-flow condensate polishing system treats primary steam condensate to maintain feedwater quality.
However, virtually no net loss of makeup water is associated with the operation of the condensate polishing system in that the powdered ion exchange resin used are not regenerated and all associated water is recovered through the radwaste sys-tem.
The makeup water demineralizer has an operating capa-city of 150 gpm but is expected to operate at an average flow rate of about 6 gpm.
Filtered, water will also be used in the potable water and sanitary waste system.
This facility has a capacity of 50 gpm but is expected to operate at an average daily rate of about 2,500 gal/day.
Filtered water will also be used for miscellaneous water requirements.
A demand of 0-50 gpm is anticipated.
3.3.4 Chemical and Radwaste S stems Virtually all chemical waste treatment in this station is combined with the radwaste system.
Consumptive water use is approximately 100 gal/day.
This represents the quantity of liquids used in the solidification process.
Solidified wastes in sealed radioactive waste containers will be removed by a licensed Contractor for storage at a licensed facility.
A detailed discussion of the radwaste system is given in Section 3.5.
3 ~ 3 2
WNP-2 ER 3.3 PLANT WATER USE 3.3.1 Overall Plant Water to meet normal operating requirements is withdrawn from the Columbia River by the cooling tower makeup pumps.
Hydro-logical data for the river are presented in Section 2.4.1.
During periods when the cooling tower makeup pumps are not operating, small quantities of makeup demineralized water and potable water may be produced using the standby well water supply.
The quantity of plant makeup water withdrawn from the Columbia River is primarily dependent, upon water losses from the circulating water system in the form of cooling tower evaporation, drift and blowdown.
Other systems in the plant water balance include:
process water treatment
- system, potable water and sanitary waste
- system, and chemical and radwaste systems.
Figure 3.3-1 is a water use flow diagram for the plant.
Table 3.3-1 lists plant water use when operating at maximum power operation (expected average power operation) and tempor-ary shutdown conditions.
Average consumptive water use, that is, water withdrawn but not returned to the river, at 100%
load factor, is approximately 13,000 gpm which is 0.026% of the annual average Columbia River flow and 0.08% of the mini-mum licensed river flow of 16,200,000 gpm.
3.3.2 Heat Dissi ation S stem A recirculating cooling water system with mechanical draft wet cooling towers will dissipate excess
- heat, from the condens-ing steam in the main condenser and other plant auxiliary heat exchange equipment, to the atmosphere.
The temperature of the closed cycle cooling water is increased by about 28 F
by passing through the main condenser and other plant auxil-iary heat exchange equipment.
The cooling water temperature is reduced in the cooling towers by the evaporation of water and by the transfer of sensible heat to the atmosphere.
The evaporation rates from the cooling towers varies with plant operation power level, ambient air temperature and humidity.
A small quantity of water is entrained in the air passing through the cooling tower and is lost from the system as "drift". Drift eliminators are used in the cooling towers to minimize this loss, which will average about 285 gpm.
Dissolved and suspended solids, originally present in the river water, are concentrated in the cooling towers by the evaporation process.
A small portion of the circulating water is withdrawn, by blowdown, to control the solids level as part of cooling water chemistry management.
When operating at fullpower operation, it is expected that the cooling tower 3 ~ 3 1
~
~
~
~
l
~
4
~ ~
O.
WNP-2 ER TABLE 3.5-11 ESTIMATED RELEASES FROM MECHANICAL VACUUM PUMP
~Ci yr Xe 133 Xe 135 I
131 Cs 134 Cs 136 Cs 137 Ba 140 2300 350 3 x 3 x 2 x 1 x 1.1 10 10 10 10 x 10 (a)
Based on NRC GALE Code (Ref.
2)
WNP-2 ER TABLE 3.5-12 ANNUAL RELEASES OF RADIOACTIVE MATERIAL AS LIQUID NUC? IDE CONCENTRATION XN PRIMARY HALF-LIFE COOLANT (DAYS)
(MjCRO CI/ML)
HIGH PURITY (CURIES)
LOW PURITY (CURIES)
ADJUSTED TOTAL LWS TOTAL (CURIES)
(CX/YR)*
TOTAL (CI/YR)
CORROSION AND ACTIVATION PRODUCTS NA 24 P
32 CR 51 MN 54 MN 56 FE 55 FE 59 CO 58 CO 60 NI 65 CU 64 ZN 65 ZN 69M ZN 69 W 187 NP 239 6.25E-Ol 1.43E-01 2.78E-01 3.03E-02 1.07E-01 9.50E-02 4.50E-01 7.13E-Ol 1.92E-03 1.07E-Ol 5.33E-01 2.45E-02 5.75E-01
~
3.96E-02 9.96E-01 2.35E-OO 8.38E-03 1.96E-04 4.90E-03 5.89E-05 4.08E-02 9.82E-04 2.94E-05 1.96E-04 3.93E-04 2.45E-04 2.77E-02 1.96E-04 1.85E-03 0.0 2.84E-04 6.77E-03
- 0. 00034
- 0. 00001
- 0. 00026 0 ~ 00000
- 0. 00050 0.00005 0.00000 0.00001 0.00002 0.00000 0.00106 0.00001 0.00007 0.00008 0.00001 0.00034
- 0. 00041 0.00002 0.00050 0.00001 0.00032 0.00010 0.00000 0.00002 0.00004 0.00000 0."00122 0.00002 0.00009 0.00009 0.00002 0.00057 0.00075 0.00003 0.00077 0.00001 0.00081 0.00016 0.00000 0.00003 0.00006 0.00000 0.00228 0.00003 0.00016 0.00017 0.00003 0.00090 0.00656 0.00026 0.00671 0.00008 0.00712 0.00136 0.00004 0.00027
- 0. 00055, 0.00004 0.02000 0.00027 0.00139 0.00146 0.00027'.00792
- 0. 00660 0.00026 0.00670 0.00008 0.00710 0.00140 0.00004 0.00027 0.00055 0.00004 0.02000 0.00027 0.00140 0.00150 0.00027 0.00790 FISSION PRODUCTS BR 83 BR 84 PB 89 SR 89 SR 91 Y 91M Y 91.
SR 92 1 ~ 00E-01 2.21E-02 1.07E-02 5.20E-01 4.03E-01 3.47E-02 5.88E-01 1.13E-01 2.31E-03 3.50E-03 3.43E-03 9.81E-05 3.64E-03 0.0 3.93E-05 8.20E-03
- 0. 00003 0.00000 0.00001 0.00001 0.00012 0.00008 0.00000 0.00011
- 0. 00002
- 0. 00000
.0. 00002
- 0. 00001
- 0. 00013
- 0. 00008 0.00001 0.00007
- 0. 00004 0.00000 0.00002 0.00002 0.00025 0.00016 0.00001 0.00017
- 0. 00037 0.00003 0.00021 0.00014 0.00222 0.00139 0.00007 0.00152 0.00037 0.00003 0.00021 0.00014 0.00220 0.00140 0.00007 0.00150
WNP-2 ER TABLE 3.5-12 (Cont'd)
NUCLIDE Y 92 Y 93 NB 98 MO 99 TC 99M TC101 RU103 RH103M TC104 RU105 RH105M RH105 TE1 29M TE129 TE131M-TE131 I131 TE132 I132 I133 I134 CS134 I135
'CS136 CS137 BA137M CS138 BA139 BA140 LA140 LA141 CE141 HALF-LIFE (DAYS) 1.47E-01 4.25E-01 3.54E-02 2.79E-OO 2.50E-01
- 9. 72F.03 3.96E-01 3.96E-02 1.25E-02 1.85E-01 5.21E-04 1.50E-OO 3.40E-01 4-79E-02 1.25F.-OO 1.74E-02 8.05E-OO 3.25E-OO 9.58E-02 8.75E-01 3.67E-02 7.49E-02 2.79E-ol 1.30E-ol 1.10E-04 1.77E-03 2.24E-02 5.76E-02 1.28E-Ol 1.67E-OO 1.62E-01 3.24E-01 CONCENTRATION IN PRIMARY COOLANT (MICRO CI/ML) 5.04E-03 3.65E-03 2.96E-03 1.94E-03 1.76E-02 6.25E-02 1.96E-05 0.0 5.60E-02 1.72E-03 0.0 0.0 3.92E-05 0.0 9.54E-05 0 ~ 0 4.87E-03 9 '1E-06
- 2.30E-02 1.84E-02 5.01E-02 2.95F.-05 1.69E-02 1.95E-05.
6.87E-05 0.0 7.00E-03 7.71E-03 3.92E-04 0.0 0.0 2.94E-03 HIGH PURITY (CURIES) 0.00020 0.00013 0.00001 0.00010 0.00051 0.00000 0.00000 0.00000 0.00000 0.00004 0.00004 0.00001 0.00000
- 0. 00000 0.00000 0.00000 0.00026 0.00000 0.00024 0.00080 0.00010 0.00008 0.00048 0.00005 0.00019 0.00017 0.00021 0.00004 0.00002 0.00000 0.00001 0.00000 LOW PURITY (CURIES) 0.00015 0.00013 0.00000 0.00017
, 0.00051 0.00000 0.00000 0.00000 0.00000 0.00003 0.00003 0.00001 0.00000 0.00000 0.00001 0.00000 0.00047 0.00000 0.00015 0.00110 0.00006 0.00077 0.00042 0.00049
- 0. 00179
- 0. 00167
- 0. 00062 0.00002
'."0004 O.ooooa 0.00001 0.00000 TOTAL LWS (CURIES)
- 0. 00036 0.00026 0.00001 0.00027 0.00102 0.00000 0.00000 0.00000 0.00001 0.00006 0.00006 0.00002
- 0. 00001 0.00000 0.00001 0.00000 0.00073 0.00000 0.00039 0.00190
- 0. 00016 0.00085 0.00090 0.00054 0.00197 0.00184 0.00083 0.00006 0.00006 0.00001 0.00002 0.00000 ADJUSTED TOTAL (CI/YR)*
- 0. 00313
- 0. 00230 0.00008 0.00233 0.00893 0.00002 0.00003 0.00003 0.00006 0.00055 O.OOOS6 0.00018
- 0. 00005
- 0. 00003
- 0. 00010
- 0. 00002
- 0. 00643 0.00001 0.00345 0.01667 0.00144 0.00741 0.00788 0.00473 0.01730 0.01618 0.00724 0.00053 0.00053 0.00011 0.00017 0.00004 TOTAL (CI/YR)
- 0. 00310
- 0. 00230
- 0. 00008 0.00230 0.00890 0.00002 0.00003 0.00003 0.00006 0.00055 0.00056
- 0. 00018 0.00005 0.00003 0.00010 0.00002 0.00640
- 0. 00001
- 0. 00350
- 0. 01700
- 0. 00140 0.00740 0.00790 0.00470 0.01700 0.01600 0.00720 0.00053 0.00053 0.00011 0.00017 0.00004
WNP-2 ER NUCLIDE HALF-LIFE (DAYS)
'S
'TABLE 3. 5-12 (Cont'd)
CONCENTRATION IN PRIMARY COOLANT HIGH PURITY LOW PURITY (MICRO CI/ML)
(CURIES)
(CURIES)
ADJUSTED TOTAL LWS TOTAL (CURIES)
(CI/YR)*
TOTAL (CI/YR)
TRITIUM RELEASE 12 3.89E-03 2.87E-05 3.92E-05 1.32E-02 4.11E-01 Curies per year
- 0. 00003
.:.'. 00002 0.00000 0.00000 0.00000
,0.00000 0.00000.;
0.00000 0.00685
.:~~0.01246, 0.00004 0.00000 0.00001 0.00001
- 0. 00036 0.00003 0.00005 0.00007 0.01931
- 0.16931
- 0. 00036
.0.00003 0.00005 0.00007 0.17000
- Adjusted total includes an additional 0.15 ci/yr with the same isotopic distribution as the calculated source term to account for anticipated occurrences such as operator errors resulting in unplanned releases..
h 4
WNP-2 ER TABLE 3'.'5-24 (Con't 'd)
SUMMARY
OP RADIOACTIVE EFFLUENT MONITORING AND CONTROL POINTS RELEASE POINT Turbine Bldg.
HVAC Exhaust Radwaste Bldg.
(HVAC Exhaust)
Vent LOCATION OP DETECTOR OR SAMPLE PROBE Probe at Elev.
551'n Duct Bet.
Col.
11
& 12 7'-6" North of Col.
K Probes in Bldg.
(HVAC Exhaust)
Vent Fan Discharges TYPE OF MONITOR Continuous Noble Gas Detector (Gamma),
Iodine and Particulate Sampler Cartridge Continuous Noble Gas Detector (Gamma),
Iodine and Particulate Sampler Cartridge ALARM OR SHUTDOWN FUNCTION High Radiation Alarm High Radiation Alarm RELEASE POINT AS SHOWN ON PIG 3.1-6 3@44
+55 @66 7
C88'~9 REMARKS Effluent Monitor Effluent
- Monitor, Probe in Each of the three Fan Set Dis-charges Plant Blow-down Line CBD (1)-l Detector in
.Blowdown Line 24" CBD (1) -1 Detector in Line 4" FDR (7)-1 Dis-charging to Blowdown Line 36" CBD (1)-1 Continuous Liquid High Radiation Radiation Detector Alarm In Line, Gamma Scintillation
-Continuous Liquid High Radation Radiation Detector Alarm in Line Gamma Scintillation Effluent Monitor, D17 RE N008 Process
- Monitor, D17-RE-N006
WNP-2 ER 3.6 CHEMICAL AND BIOCIDE WASTES 3.6.1 General Waste waters discharged to the Columbia River will meet the requirements given in 40 CFR Part 423 "Effluent Limitations,
'Guidelines and Standards.for the Steam Electric Power Gen-erating Point Source Category",
issued by the Environmental Protection Agency, October 8, 1974.
Waste water streams actually and potentially containing radionuclides will be processed in the liquid radwaste system as described in Section 3.5.2.
3.6.2 Chemical Waste Treatment S stem The makeup water demineralizer produces low dissolved solids makeup water by ion exchange, for plant use.
Periodically, the makeup water demineralizing equipment requires regeneration to restore the ion exchange capacity.
The regeneration pro-cess requires a maximum of approximately 180 lbs of 66o Be sulfuric acid and 192 lbs of 100% sodium hydroxide.
Excess regenerant, chemicals are collected along with rinse waters from the regeneration cycle, neutralized and tested before discharge to the heat dissipation system.
The total volume of waste water produced by one demineralizer regeneration cycle, is approximately 9100 gallons, with a typical composition as shown in column D, Table 3.6-1.
-When operating on average composition river water, the makeup water demineralizer will produce approximately 110,000 gallons of demineralized water to service, per cycle.
Normal operating plant demand will require on the order of 5 gallons per minute of demineralized water makeup, so that the regeneration of this equipment will be infrequent.
The total plant is being built "clean" so that conventional chemical cleaning prior to start-up is not anticipated.
In the future, if chemical cleaning is required, cleaning wastes will not be discharged to the Columbia River.
3.6.3 Heat Dissi ation S stem The removal facilities are discussed in Section 3.4.
The evaporation of water in the cooling towers will cause solids concentrations in the circulating water to increase as dis-cussed in Section 3.3.
Control of the cooling water chem-istry is required to preclude reductions in plant efficiency and service life.
This includes adjustment of the pH of the circulating water to maintain a non-scaling and non-corros-ive condition; intermittent chlorination to control biologi-cal growths'uch as slimes, algae and fungi; and the blowdown or withdrawal of a portion of the circulating water to con-3.6-1
WNP-2 ER trol the dissolved solids concentration.
Typical composition of the Columbia River water used for cooling makeup, is shown on Table 3.6-1, (colums A, B, C).'he composition of the water in the heat dissipation system which will be the same as the cooling tower blowdown is shown on Table 3.6-1 (columns E, F, G).
Sulfuric acid is added to the circulating water to maintain the circulating water pH in the range of 6.5-8.5, for scale and corrosion control.
The anticipated sulfuric acid con-sumption will be in the range of 1700-3400 lbs/day.
If the pH of the circulating water, hence the cooling tower blow-down water, should fall below 6.5 or'rise above 8.5, ope-rating alarms within the plant will alert the operating per-sonnel who will initiate corrective action.
It is anticipated that adequate corrosion control in the heat dissipation system can be maintained by pH control by means of the addition of sulfuric acid and the control of the dissolved solids in the system by the means of blowdown.
No other corrosion or scale inhibitors are to be used.
Wood has not been used in the construction of the cooling tower or as a fillmaterial.
Therefore, chemical preserva-tives will not be extracted and discharged to the river.
Biological growths on heat transfer surfaces result in fouling and a loss of efficiency.
Also, algae, slimes and bacterial growths can cause an increase in the corrosion rate of metal surfaces.
Therefore, biological activity in the heat dissipation system will be controlled by chlorination. It is anticipated that about 240 lbs/day of chlorine will be
.injected, intermittently into the circulating water line up-stream of the main condenser.
Chlorine dosage will be automatically controlled so that a
concentration of about, 0.5 ppm will be present after the condenser, in the water going to the cooling tower, during periods of chlorinator operation.
A small portion of this will be dispersed to the atmosphere and the remainder ef-fectively consumed by the small quantities of organic matter present in the circulating water.
During the time the chlo-rine is added, and for a period of 10-20 minutes afterward, the cooling tower blowdown valve will be automatically closed.
The total cumulative operating time of the chlorin-ation system will not exceed 2 hrs/day.
Interrupting the blowdown flow during periods of chlorinator operation and for a short period afterwards, assures compliance with 40 CFR Part 423, "Effluent Limitations, Guidelines and Standards for the Steam Electric Power Generating Source Category,:
issued by the Environmental Protection Agency October 8,
1974.
3.6-2
WNP-2 ER The anticipated composition of the cooling tower blowdown is given in Table 3.6-1.
This discharge flow will be essentially continuous during normal operation, except during periods of chlorinator operation and for a brief period afterwards.
A small portion of the circulating water will be lost from the cooling towers in the form of small droplets.
This "drift" is of the same composition as the circulating water containing some dissolved and suspended solids (Table 3.6-1).
Drift eliminators are incorporated in the design of the cooling towers so as to limit the drfit to a maximum of 285
- gpm, as discussed in Section 3.4.
The total solids contained in the drift will amount to about 520,000 lbs per year, under full load conditions.
The deposition of drift in the vicinity of the cooling towers is discussed in Section 5.1.4.
- 3. 6-3
'ABLE 3'. 6-1 WATER 'COMPOSITION
'COLUMBIA'IVERi'EMINERALIZERWA'STEg COOLING TOWER BLOWDOWN D
Col'umbi'a River AvcC.
Max.
Min.
Demineralizer Was'te '~oolin A~v
~
Tower Max.-
Blowdown Min.
- Calcium, Ca ppm
++
++
Magnesium, Mg ppm
+
- Sodium, Na ppm 23 32 18 309 52 1466 116 21 12 160 34 24 90 10 Bicarbonate, HC03 ppm Carbonate, C03 ppm
- Sulfate, S04 ppm Chloride, Cl ppm 72 15 80 50 2.6 0.2 6
0 28 10 514 3495 56 92 236 92 415 13 92 109
- Nitrate, N03 ppm Phosphate, P04 ppm 0.24 0.62 0
0.03 0.13 0
32 1.24 0.06 3.1
- 0. 63 Total Hardness ppm CaC03 Total Alkalinity ppm CaC03 74 88 63 76 64 41 988 422 375 150 540 150 265 150 pH Silica, Si02 ppm Dissolved Soilds, ppm 8.7 9.1 8-8.5 6
9 3
87 115 72 8.3 76 6022 7.5 30 435 8.5 45 600 6.5 15 360
WNP-2 ER 3.7 SANITARY AND OTHER WASTES 3.7.1 Sanitar Waste The sanitary waste system has been designed on the basis of 100 persons, at 25 gallons per capita per day, producing a
total maximum of 2500 gallons of wastewater per day.
This will be processed and disposed of by means of septic tanks, a
distribution box and a tile field facility located at about N 11.500, W 600 (See Figure 2.1-4).
The invert at the distri-bution box is at elevation 419.83 while the water table is at approximately 379.6.
A septic tank and seepage pit are also located at the makeup water pump house.
The invert will be at elevation 366.5 while the water table is at approximately 341.2.
The septic tank/tile field method of sanitary wastewater disposal is expected to have minimal environmental impact due to the good soil drainage characteristics above the ground water table.
3.7.2 Storm Water and Roof Drains Storm water and roof drains will be collected in a separate drain system and routed to an evaporation-leaching pond area (see Figure 2.1-4).
These drains are from outside areas only.
3.7.3 Filter Backwash Water Periodically, filter backwash water from the makeup demin-eralizer system, must be disposed of.
The filters ac-cumulate and store backwash water that is released at a flow rate of up to 700 gpm for a period of about 5 minutes per week.
The filter backwash water will also be routed to the evaporation-leaching pond area (See Figure 2.1-4).
3.7.4 Gaseous Wastes In normal station operation, fossil fuels will not be required.
- However, standby diesel engine driven generators and a
heating boiler have been provided.
The operation of these will produce gaseous wastes on an intermittent basis.
Three standby diesel engine driven generators will be test run for about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> monthly.
Two of the units consume 340 gph of fuel, each at full load, while the third will use 170 gph at full load.
Assuming normal station operation, with a fuel oil sulfur content of 0.4%, this equipment will exhaust about 1170 lbs of S02, 21,400 lbs of NOxg and 412 lbs of hydrocarbons.
The heating boiler provides building heat and supplies steam to the radwaste
- system, when needed.
It is expected that 3.7-1
WNP-2 ER the equivalent of only 3 months, or less, of full load operation, will be required annually.
The heating boiler, consuming no.
2 fuel oil, containing 0.4% sulfur, at a full load rate of 432 gph, will produce approximately 54,000 lbs of S02, 39,000 lbs of NOx and 1,340 lbs of particulates per year.
3 Q 7 2
WNP-2 ER from existing towers, taken from a BPA line to be removed, will be used for the towers of this line.
The towers will average approximately 80 feet in height with a base 28 feet square and a span length between towers averaging 1,150 feet.
Three conductors will be used for this line with the average conductor ground clearance being 47 feet.
See Table 3.9-1 for this line's electrical characteristics.
3.9.1.3 Howard J.
Ashe Substation The H. J.
Ashe substation, as shown in Figure 3.9-4, is being built by BPA to handle the NNP-2 500 KV transmission line and 230 KV start-up line.
As shown in Figure 2.1-3, the Ashe substation is approximately 1/2 mile due north of NNP-2.
The substation requires about 37 acres of land and an access road about 2,000 feet long for a total land requirement. of about 38 acres.
Construction on the Ashe substation was completed in May, 1976.
3.9.2 Environmental Parameters 3.9.2.1 Non-Electrical A total of 648 acres will be required for the right-of-way for the 500 KV and 230 KV lines.
The land to be crossed by the transmission lines is shown in Figures 10.9-3 and 10.9-4.
A detailed discussion of the 500 KV and 230 KV routes impact on land, vegetation, wild life and their crossings of high-ways, railways, water-bodies, areas of acheological, histor-ical and recreational interest are discussed in Section 10.9.2.1.
Alternative right-of-ways and the rationale for the selection of the proposed rights-of-way is given in Section 10.9.
3.9.2.2 Electrical Radiated electrical interference is insignificant beyond 1000 feet from the rights-of-way and no receptors are antici-pated within this range due to the land classification.
Radiated acoustic noise is insignificant on lines with volt-ages below 345 KV.
The 500 KV lines will be designed to minimize acoustic noise.
Ground currents, in normal operation, both induced and con-ducted are insignificant.
The magnitude of such currents depends on the magnitude and balance of the load current in the conductors.
Procedures for grounding metal structures and equipment, along with other precautions used by BPA substantially eliminates the possible hazard and nuisance from these sources.
Under phase to ground fault conditions the current can reach 23 KA in the immediate vicinity for a maximum of one half second until the line protection devices operate.
3.9-2
High voltage transmission lines exhibit corona discharge which is associated with the formation of ozone.
Because corona discharge represents a power loss, transmission lines are designed to minimize this loss for economic reasons.
The ozone formation per three-phase mile of 500 KV trans-mission line would be approximately 0.9 lb/day, and will be considerably less for the 230 KV line.
The effects of this ozone formation are difficult to evaluate since the natural formation rate is high'n comparison.
Over the rights-of-way the natural ozone generation is one or two orders of magnitude above that caused by corona discharge from trans-mission lines.
Field measurements of ozone concentrations in the vicinity of transmission lines have failed to record any increases that were attributable to the power lines.
For these
- reasons, ozone formation is expected to cause no signi-ficant environmental effect.
3.9-3
WNP-2 ER The construction site is in the early state of recovery from the fire and provides limited food and cover for resident wildlife (including endangered species).
Construction activ-ities, destroying the habitats of small mammals (of which the pocket mouse is the dominant species),
has not, had any meas-urable effect on the transitory wildlife of the large shrub-steppe.
The major disturbance and displacement of fauna in the area occured as a result of the fire.
The more produc-tive shrub-steppe and riparian habitats are remote from the
- site, and construction appears to have had little influence on the wildlife associated with these habitats.
The following discusses precautions taken during site pre-paration and plant construction to minimize adverse environ-mental.impacts.
Following the range fire in 1970, the construction site had a sparse cover of annual vegetation in early successional
- stages, which has partially stabilized the soil and provides only a marginal habitat for resident wildlife.
The exposed area is subjected to wind erosion and consequently blowing dust occurs frequently.
Since the construction activities are not visible to the general public, they have no aesthetic impact with the possible exception of an incremental dust burden to the air.
Rainfall at the Hanford Reservation averages 6.25 inches per year.
The surface soils are very permeable and minimal natural surface runoff occurs.
Erosion control has been suc-cessfully accomplished by proper grading and terracing.
No known historical or archaeological sites are located with-in the WNP-2 site or the transmission corridors.
During" the construction period a competent archaeologist is employed and his expertise has been utilized during excavation activities.
Archaeological sites south of the WNP-2 lease area along the river bank were roped off to avoid disturbance.
A discussion of findings is presented in Section 2.6.
Sanitary wastes have been and will continue to be disposed of through septic tanks and tile fields supplemented by tempor-ary chemical toilets.
The chemical toilets are serviced, when necessary, by an outside contractor.
This is in com-pliance with State of Washington Department of Labor and In-dustries Safety Standards for Construction
- Work, WAC 296 055 Sanitary Facilities.
Separate wash facilities are housed in a heated building, and the waste water is disposed of through a drainage tile field.
Waste flow from these facilities is estimated at 15-30 gallons 4.1-3
WNP-2 ER per day per person.
No adverse affects on the environment have been experienced.
Combustible construction scraps were initially burned in a burn pit approximately 1/4 mile east of the main plant but are currently being buried.
Petroleum wastes are not drained to the ground but have been accumulated in drums and dis-posed of off-site.
Chemical wastes have been and will be accumulated in drums and returned to the manufacturer for disposal or otherwise disposed of in a manner determined to adequately protect the environment.
4.1.2.1.2 Future Construction Effects Future work, off of WPPSS's property, includes the completicn and erection of the transmission lines and their associated access roads.
Section 4.2 describes their construction effects.
Major construction still to be completed at the site includes those major items listed in Figure 4.1-1.
Future work at the WNP-2 site will continue to be controlled by the Construction Impact Control Program (see section 4.5) to ensure mitigation of possible environmental impacts.
4.1.2.2 Water Use 4.1.2.2.1 Past and Present Im acts In accordance with the site certification agreement with the Thermal Power Plant Site Evaluation Council (TPPSEC),
con-struction activities involving work in the Columbia River was to be limited to the period from July 31 thru October 15, 1975.
The reasoning being that during those months the river level and velocity and migrant fish levels were low and 'con-struction impacts would be minimal.
However, additional work to return the river bed to its natural contours required TPPSEC notification and rip rap repair in the vicinity of the intake "T"'s and the cooling tower blowdown line.
This repair was performed during February ll to March 15, 1976.
Some turbidity and sedimentation during excavation is inevit-
- able, however mitigation of construction impacts was accom-plished with a large backhoe and the placing of excavated material just down stream of the trench.
To further reduce possible biotic and water quality impacts during initial work and repair work, the small gravel used for pipeline bedding was screened and rip rap was placed via use of a clam shell.
The water used during construction has been pumped from on-site wells at a combined maximum withdrawal rate of approxi-mately 350 cpm. 'his withdrawal rate has had no measurable effect on the ground-water profile, since ample recharge of the aquifer is available.
4.1-4
WNP-2 ER 4.1.2.2.2 Future Construction Effects There is no further construction or excavation scheduled to take place in the Columbia River.
Well water withdrawal is expected to continue at approximately 350
- gpm, and as experi-ence has
- shown, no adverse environmental effects are expected.
4.1.3 Final Site Construction and Restoration Landscaping will serve both a functional and an aesthetic purpose.
Suitable grasses and hedges will be planted to fa-cilitate erosion and dust control plus the added benefits of the aesthetic appeal.
Landscaping will integrate excess ex-cavated materials (spoils) with the site contours to ensure runoff away from all buildings and auxiliary structures.
In compliance with the WNP-2 security program, no landscaping is to be provided within an isolation area extending 25 feet out-side to 50 feet inside the perimeter security time.
Figures 3.1-2 and 3.1-5 are an artist's conception of the finished plant and makeup water pumphouse showing the landscaping and plant facilities.
- 4. 1-5
Status as or 8 31.76 BURNS ANO ROE. INC.
CONSTRUCTION PROGRESS SUMMARV WPPSS NUCLEAR PROJECT NO. 2 1973 1974 1975 1976 1977 1978 1979 Connect Number/Description 204 Fold Fabricated Tanks Rel.
Act%
Weight Camp
.001 100.0 100.0 M A M J
J A
0 N
D J
F A M A
S 0
N 0 F
M A 0
N 0 J
F M A M J J
A 5 0
~ N 0 J
F M A M J J
A S 0 N
0 J
M J
J S 0 N
D J.F M
~ erI ~ en s
~
sw l
A M J
J A 5: 0 N 0 J
F M A M J
205 208. 221, 224, 226, 230, 232 Completed
.015 100.0 100.0
~d% Comptete 3A 38 10 12 13 14 15 16 17 18 19 21 22 23 2C6 General Construction C6426 I250) General Construction Interim 2064 i2511 General Corntruction 207 Structural Steel 209 n~ing ol Reactor Pressure Vessel 210 Architectural Construction 213 Primary Containment Vessel 214 Turbine trenerator Installation 215 Mechaniosl Equip, Instalk Si Piping 216 HVACSr Plumbing Ihstat4tion 217 Fire Protection System 218 Electric Ihttal4tion 219 Specul Coatktgs 220 lnstfurhehtatiah Illstallatioh 222 Final Site Work 223 Cooling Towers 225 Make Up Water Pumphouse 228 Communications Systems 22g Finnh Painting 231 Security Systems 233 Spray Pond Piping 36 Proouction Si Oetirery af Concrete 74 lanhtehanae Si Mnc. Future TOTALS
.147 100.0
.055 48.4
.I64 0.0
.003 50.8
.006 20.2
.015 4(3
.022 78.6
.021 21.7
.322 17.5
.029 10JI
.003 0.0
.195 10.0
.002 25.2 JTJO 0.0
.006 0.0
.016 99.6
.007 81.2
.001 0.0 ao 0.0
.002 0.0
.006 81.4
.009 14.2 1.00 32.9 100.0 0.0 17.9 12.4 0.0 11.0 20.9 0.0 0.0 0.0 0.0 0.0 0.0 74.9 16.7 17 10 I
I 12 13 Actual er Complete i
I 8
18 I
5 14 21 15 I
I t
I s
I I
~
I
(
I i
~
I i
80 70 10 8
8 4
2 M A M J J
A 1973 ONOJF A M 1974 A
6 0 N 0 J
F M A M J
J 1975 S 0 N
D J
F M A M J
A 1976 S
0 N 0 J
F M A M
J 1977 A
S 0 N 0 J
M J
1978 A
S 0 N
O J
F M
J 1979 A 5 0 N
D J
F M A M J
J WASHINGTON PUBLIC POWER SUPPLY SYSTEIII WPPSS NUCLEAR PROJECT NO.
2 Environmental Report CONSTRUCTION PROGRESS
SUMMARY
FIG. 4.1-1
2000 1500 0
g 1000 0
500
'00 8
Q o
0 rl I
0 s4 0
Q I
I I
I 1973 1974 1975 1976 1977 1978 1979 1980 Year WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report WNP-2 CONSTRUCTION PERSONNEL ESTIMATE~
FIGHT 4'-2
WNP 2
ER 4.2 TRANSMISSION FACILITIES CONSTRUCTION The effects of clearing the rights-of-way and installing transmission towers and conductors, on the environs and the people living in the adjacent
- area, are discussed in this section.
Bonneville Power Administration is constructing the Howard J.
Ashe Substation and the WNP-2 500 KV transmission line and 230 KV start-up line entirely within the Hanford Reservation.
Access to the Hanford Reservation is partially restricted and any construction activities by BPA will not have an effect on the general public.
BPA has submitted an environmental statement~1~discussing the Howard J.
Ashe Substation and the 500 KV and 230 KV lines.
The information for the following sections was taken from that document.
Work on the 230 KV line took place from November 1975 to March 1976.
Work on the 500 KV line is scheduled from January 1977 to January 1978.
Work on the H. J.
Ashe Substation was intiated during November 1975 with the substation to be energized in September 1976.
4.2.1 4.2.1.1 Clearin the Ri hts-of-Wa and the Substation Site For construction purposes, sagebrush will be removed from the rights-of way only at the tower sites in an area of about 20 feet square for the 500 KV towers, 28 feet square for the 230 KV towers, and on main access roads.
The total construction land requirements for the 500 KV and 230 KV lines amounts to approximately 100 acres.
Sagebrush will be removed at tower sites to facilitate tower erection.
Grass will be left grow-ing on all portions of the rights-of-way to the extent possi-ble.
Construction of the substation will remove approximately 51 acres of sagebrush-bunchgrass/cheatgrass vegetation and associated wildlife habitat.
The site is essentially level except for some local microrelief and only minimal grading will be required.
- 4. 2. 1. 2
~Im acts A description of the standard mitigation measures that will be used during construction operations to mitigate impacts to the natural, cultural, and socioeconomic resources can be found in the BPA General Construction and Maintenance Program statement
~2~. In addition to the General Construction and Maintenance Program statement, the publication entitled, "Environmental Criteria for Electric Transmission Systems" jointly published by the Departments of Agriculture and In-
- terior, summarizes the measures that will be used to lessen visual impacts of transmission lines.
4.2-1
WNP-2 ER Where required, clearing will be by bulldozer; no spraying will be used to clear the rights-of ways.
Section 4.2.4.3 discusses the effects of construction on identified endangered
- species, and Section 4.1 gives an estimate of land require-ments during construction.
The corridors do not cross any streams or come near the
-Columbia River and the substation will be located approxi-mately 3000 feet north of WHP-2 and 3 miles east of the Columbia River.
Therefore, no environmental impacts on the river or streams will occur.
Clearing the transmission routes and the substation site will not create noise noticeable to the general public.
Erosion is discussed in Subsection 4.2.4.
4.2.2 Method for Erectin Transmission Line Structures Construction of transmission lines involves establishment of temporary construction access roads for movement of materials and heavy erection machinery to construction areas; clearing vegetation, structures, and other obstructions on the rights-of-way that might interfere with construction of the trans-mission lines; burning or otherwise disposing of cleared veg-etation; leveling areas necessary for tower sites and tower steel storage and staging areas; excavating for and install-ing tower footings; erecting transmission towers; stringing and tensioning conductors; construction of permanent main-tenance access roads on and off the rights-of-way as dictated by terrain and other factors; and reseeding or otherwise re-vegetating disturbed soil areas where appropriate.
4.2.3 Access and Service Roads A total of 16.4 miles of new access and service roads will be constructed.
Ten and one-half miles of access roads will be on the rights-of-way, 5.5 miles will be off the rights-of-way, and 0.4 miles will be for the substation.
With the total length of the corridors being 20.9 miles, the remainder of the access roads will be comprised of existing access roads from other transmission lines and service roads from existing telephone lines.
For example, through the sand dunes
- area, approximately 3 miles of an existing grav-elled telephone access road will be utilized.
Short, spur roads to the individual tower sites will be necessary.
4.2.4 Environmental Effects 4.2.4.1 Erosion Wind erosion potential of the sandy loam soil in this dry 4.2-2
WNP-2 ER climate is extremely high.
When vegetative cover is removed and soil is disturbed during construction and clearing of access roads and tower sites, wind erosion can be severe.
In most, areas, the fall germination of cheatgrass will re-stabilize the area in a few years.
Blowouts, dunes, and other wind produced features found widely scattered across the area, however, attest to the chronic erosion potential in the absence of control measures.
The lines cross 3 miles of sand dunes.
Some sand dunes are not stable due to lack of vegetation cover and construction will impact on these as well as on stabilized dunes with a high potential for additional erosion.
Sand dunes are up to 30 feet high and capable of moving eastward at a rate of up to 1 foot per year.
In order to minimize wind erosion caused by construction as many existing roads as possible will be used and gravel will be used to cover the principal new access roads.
If possible, spur roads will not be graded.
Existing roads that are well
'ravelled seem to be very stable with little wind erosion.
It has also been found that in a disturbed area such as tem-porary access
- roads, grass will establish itself within 1 to 2 years and again be capable of minimizing wind erosion.
The temporary vegetation recovery study areas near WNP-2 are under investigation for grass and sagebrush regrowth.
(Nineteen thousand acres of its vegetative cover was burned in July 1970. )
4.2.4.2 Loss of A ricultural Productivit The Hanford Reservation is owned and controlled by the Energy Research and Development Administration.
The 500 KV and 230 KV transmission lines will be entirely within the boundaries of the Reservation.
Most of the land (excepting Gable Moun-tain) is a shrub steppe with no other productive (agricul-tural and other) uses planned by ERDA.
Therefore construction activities will have no foreseeable affect on agricultural productivity.
4.2.4.3 Endan ered S ecies Adverse effects upon resident wildlife including the sage grouse will be largely limited to the construction period.
The routes do not cross any streams, therefore, aquatic life will not be affected.
Due to clearing of sagebrush from main access roads and tower
- sites, song birds, birds of prey, and upland birds within the vicinity will be temporarily disturbed and some habitat will be lost.
4.2-3
WNP-2 ER Sage
- grouse, although few in number, have been able to sur-vive on the reservation due to the presence of exclusion areas and the lack of hunting.
The following threatened wildlife species may at times appear along the corridors although their exact ranges are not known.
~secies Ferruginous hawk (Buteo regalis)
American osprey (Pandion haliaetus carolinensis)
Federal Status Undetermined Undetermined Prairie falcon (Falco mexicanus)
Threatened American peregrine falcon (Falco peregrinus anatum)
Endangered Q
The transmission routes do not cross any streams or rivers and the water table of the Hanford Reservation is well below ground level, therefore, construction activities will have no affect on the local water quality.
4.2.4.5 Noise Due to the isolation of the transmission routes and the sub-
- station, construction will create no noise impacts upon the general public.
4.2.4s6 Historical and Archeolo ical Sites Neither the lines nor the substation is near any historical or archeological sites.
4.2-4
WNP-2 ER 4.3 RESOURCES COMMITTED The portion of the Hanford Reservation affected by WNP-2 con-sists of land mostly covered with sagebrush and desert grasses.
This land is not currently being used for any productive pur-pose.
In general, the land has no agricultural value without irrigation.
Approximately 30 of the 1,089 acres originally leased by WPPSS for WNP-2 will be utilized for plant operation.
An addition-al 80 acres on the Reservation will be used as tower sites for power transmission lines, access roads and for a sub-station's land requirements.
Except for concrete (which would be considered lost for any-thing but sanitary landfill or similar use),
much of the un-contaminated materials used for WNP-2 could be salvaged after decommissioning the unit.
However, the cost of retrieving these materials would in some instances, far exceed the pur-chase price of new materials.
Some components of the facility will have become radioactive through activation and/or con-tamination and thus, will essentially be irretrievably lost.
Upon the inevitable decommissioning of WNP-2, the area (app-roximately 3.5 acres) occupied by the reactor facilities may be placed on permanent restricted use because of the residual concentrations of radioactivity that would result from oper-ating the plant.
Air and water are resources which, during the construction of this project, will also be affected, but consumption will be minimal.
Small quantities of liquid and gaseous effluents will be dispersed into, and diluted by, these two natural re-sources.
Neither of these forms of effluents will render the the air and water unsuitable for additional use by man.
In addition, capital resources were committed prior to and dur-ing construction.
This resource should be totally recovered assuming the facility is operated throughout its planned life-time.
Some additional disturbance of the site has been nec-essary to accommodate.materials, construction equipment, and temporary buildings during construction.
This has been kept to a minimum consistent with appropriate safety, reliability, and environmental criteria.
These disturbances do not re-present an irreversible commitment of resources since the temporarily disturbed area will revert to its natural veg-etative state within several years when these facilities are removed.
The characteristics of the land for the site are representative of much of the adjacent underdeveloped land which is covered with sagebrush, bitterbrush, other alien
- weeds, and desert grasses.
The land is not considered un-
- usual, and in all probability would otherwise be undeveloped for many years.
- Thus, the use of this site involves no area of limited supply or unique potential.
Construction of WNP-2
- 4. 3-1
WNP-2 ER is having no significant impact on wildlife.
Native forms of wildlife, which may once have been present in this small area, have not been destroyed; rather they have been displaced to the vast expanses of the Hanford Res-
- ervation, much of which has remained essentially in its na-tural condition.
Thus no net reduction in either the num-bers or diversity of wildlife species has resulted from the construction of WNP-2.
4.3-2
WNP-2 ER 4 ~ 4 RADIOACTIVITY The scheduled start-up time for WNP-2 is June 1980.
WNP-1 and WNP-4 are scheduled for fuel loading during Febru-ary 1981 and August 1982, respectively.
At present the nearest nuclear power plant is the 860 Mwe Hanford No.
1 Generating Project located approximately 18 miles northwest of WNP-2.
No past or future adverse effects of radioactivity from other nuclear power plants has, or is anticipated to affect the WNP-2 construction workers.
- 4. 4-1
WNP-2 ER 4.5 CONSTRUCTION IMPACT CONTROL PROGRAM 4.5.1
, Controls WNP-2 is located in a shrub steppe region, consisting of several shallow rolling hills, with the eastern extremity having a general slope to the river.
Surface drainage is good due to the open and dry nature of the area (average rainfall is 6.25 inches per year) and sandy soil types.
During construction, contractors are 'required to maintain proper drainage and erosion control around the construction areas and especially in areas of excavation. or fill. Con-trols are being employed to insure proper embankment slopes.
These slopes were further recommended not to be cut steeper than one vertical on one and one half. horizontal~1~.
1 Borrow pits are prepared by grading to minimize wind and water erosion and.to'conform, where possible, to the natural topography,.
Any accumulation of precipitation within the, excavation area are allowed to infiltrate, into the permeable soils.
WNP-2 is located on the Hanford 'Reservation and the vast land area serves as a natural barrier to inhibit the impact of dust and noise upon major population centers.
Public use: of the reservation is currently limited to several highways which have further helped to mitigate any indesirable effects of dust and noise upon the public.
Truck traffic, due to construction activities, is largely restricted to the reserv-ation, except for the transportation of supplies to WNP-2.
Throughout the construction period stockpiles, site roadways, and storage areas are watered down by'pecial sprinkler trucks as necessary to decrease the impact of windblown debris.
Combustible construction scraps were initially burned in a burn pit approximately 1/4 mile east of the main plant, but.
are currently being buried.
Petroleum wastes are not drained to the ground but are accumulated and disposed of offsite.
Sanitary wastes are disposed of.through septic tanks and tile fields supplemented by temporary chemical toilets.
The chemical toilets are serviced, when necessary, by an outside contractor.
This is in compliance with State of Washington Department of Labor and Industries Safety Standards for Con-struction Work, WAC 296-40-055 - Sanitary Facilities.
- 4. 5-1
WNP-2 ER The water used during construction is pumped from two on-site wells with an average withdrawal rate of approximately 350 gpm.
This withdrawal rate has no measurable effect on the ground water profile, since ample recharge of the aquifier is available.
In accordance with the site certification agreement with the Thermal Power Plant Site Evaluation Council, initial construc-tion activities, in the river, were limited to the period of July 31, 1975 through October 15, 1975.
During these months river flow and velocity, and fish migration were at a minimum and construction activities had little effect upon aquatic life forms or the river flow.
No blockage to the river or flooding occurred at any time during the construction period.
Landscaping and final site construction will serve both a functional and an aesthetic purpose.
Suitable grasses and hedges will be planted to facilitate erosion and dust control plus the added benefits of the'esthetic appeal.
Landscaping will integrate excess excavated material (spoils) with the site contours to ensure runoff away from all buildings and auxiliary structures.
4.5.2 Nature of Control Im lementation Control of the environmental quality protection requirements are implemented and maintained via two main methods:
a.
written direction to contractors through specifications and correspondence; and b.
routine inspection of the site by an A.E.
representative.
Construction activity impacts are controlled by the Site Cer-tification Agreement between the State of Washington and
- WPPSS, the U. S.
Army Corps of Engineers Construction Permit, the U. S. Atomic Energy Commission Construction Permit (No.
EPPR-93),
the Energy Research and Development Administration, and the State Environmental Policy Act.
The requirements of these legal entities and documents are implemented by the-Supply System through auditable contractual agreements between WPPSS and contractors.
A.E. personnel who represent the Supply System, inspect construction activities to ensure con-tract adherence, and the Supply System in turn audits the A.E. through routine on-site inspection.
- 4. 5-2
WNP-2 ER predicted.
No elevated or ground fogging was predicted for the Pasco airport (known as the Tri-Cities Airport).
The persistences at the Richland airport (18 km south) show no ground fogging and 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of elevated plume occurrences in the annular segment containing the airport.
If the impact in the sector is apportioned to the 2 km square area bounding Richland airport operations, then about 4 and 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per year of elevated fogging and icing are predicted, respectively.
Hence the actual interference is expected to be relatively small.
At distances as qreat as the Kennewick and Pasco airports, the direction estimates cannot be expected to be necessarily
- accurate, so it is reasonable to interpret the results as pre-dicting several hours of fogging out to 30 km, which may or may not hit these targets.
The potential impact on local agricultural operations by the invisible plume was assessed.
The atmospheric cooling tower plume is assumed visible out to the point where the lowest possible saturation point is reached.
The further mixing with ambient air results in the concentrations within the plume being reduced towards the ambient air concentrations.
The invisible plume consists of incremental increases in heat and moisture.
Considering the very dry conditions indigenous to the summer season in this region (Table 2.3-1),
any incre-mental effect of increased moisture is expected to have a
positive effect on plant growth.
The only exception to this is during the grain harvesting when low humidities are desired for drying the crops.
The invisible plumes from WNP-2 were considered in detail during the month of June.
Later months tend to have lower humidities and June was considered a conservative choice of summer months.
The evaluation considered plumes every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in the direction sectors clockwise between 45'nd 135't distances of 8 and 10 km.
These represent the closest impact areas on the top of the bluff on the east side of the Columbia River.
The plumes considered represented about 1/4 of the total plumes.
The maximum plume centerline change in humidity was at 8
km at 0400 PDST.
This is given in terms of ambient humidities in Table 5.1-7.
Even for this highest centerline value in the
- analysis, the increase at high humidities is only slight.
The average centerline value of all cases is also given.
Realis-tically a certain amount of wandering of the plume can be expected and these centerline values are considered conserva-tive estimates.
- Hence, the increase in moisture is no+
believed to be a potential problem.
Based on these results, 5.1-13
WNP-2 ER the impact on local agriculture is expected to be small.
The harvesting period of mid-July to the end of August has lower relative humidities and higher temperatures than any other time of the year.
The above estimates show that even the maximum impact of the plume is only slight.
Therefore, except in rare and very localized situations, the plume from the plant cannot be expected to interfere with harvesting opera-tion.
Effect of Fo in and Icin on Traffic.
The nearest public highway to the site is State Highway 240, which runs about 10 km southwest of the site.
In this sector, no fogging or icing at ground level is expected to occur.
Other roads closer to the site are on the Hanford Reservation and access by the public is controlled.. Workers traveling the project road to the FFTF site, to the Hanford operations, and to the WNP-1 and WNP-4 site will rarely if ever encounter ground level fogging or'reezing.
5.1.4.2 Coolin Tower Drift De osition The potential impact from the cooling tower drift was esti-mated using. methods and assumptions described in Subsection 6.1.3.2.
Table 5.1-8 presents the results obtained.
The first column lists distance from the cooling tower.
The second column presents the gross salt deposition rate per year assuming the wind blows equally as often from all direc-tions.
(The salt deposition in this table refers to salts naturally occurring in the Columbia River water which is used as makeup water.
The contribution of plant, additives is small by comparison.
The third and fourth columns contain estimates of deposition rates based on the observed maximum wind direc-tion frequencies at the WNP-2 site and at the HMS site.
The maximum wind direction frequency at WNP-2 was 9% from the south (drift to the north).
The measurement elevation was 23 ft.
At an elevation of 400 ft at HMS, the maximum direc-tion frequency was 20% from the northwest (drift to the southeast).
The maximum direction frequency observed at the HMS 50-ft elevation (17%) is smaller than that at the HMS 400-ft eleva-tion (20%), but is considerably larger than that at the WNP-2 23-ft elevation (9%).
Since maximum salt deposition would be directly proportional to direction frequency, use of the HMS 400-ft data might be expected to yield an excessively con-servative (high) estimate of salt deposition.
In contrast, since plume heights were presumed to be between 330 and 1300 ft, use of the 400-ft direction frequencies is more reasonable than use of those measured at lower elevations.
5.1-14
WNP-2 ER The deposition rates in Table 5.1.4-6 are put into perspec-tive by comparison to the amount of salt which could be added to soil through irrigation as shown in the last three columns.
- Locally, 48 in. of water is a reasonable annual average irriga-tion requirement.
f The relatively high drift deposition at the 0.25-and 0.3-mile distances as compared to greater distances is due to winter-time high humidities which permit the larger diameter drift droplets to intersect the surface before significant evapora-tion takes place.
Patterns of salt deposition on the surrounding region were estimated using the wind direction frequencies from the onsite meteorology tower.
These are given in Figures 5.4-11 and 5.4-12.
5.1.4.3 Effects of Heat Dissi ation S stems, Salt De osition, and Accumulation in Soil The operation of cooling towers is expected to increase the concentration of salts in the soil profile.
The salts originate in cooling tower drift droplets that are expected to be deposited on the soil surface, mostly in the near vicinity of the cooling tower.
Due to low rainfall, salts are expected to remain in the root zone and with time their concentrations may build up to the point deleterious to the growth of plants.
The operational activities of the WNP-2 station are expected to have little effect upon game bird and mammal populations.
- However, the operation of the cooling towers may have an impact on nesting populations of shrub-steppe birds, espe-cially the horned lark, western meadow lark, and the long-billed curlew.
The postulated impact from operations would occur from salt drift released from the mechanical draft cooling towers, especially from salt buildup in soils which in time may build up in the soil profile in concentra-tions of sufficient strength to prevent the growth of cheatgrass which presently provides the main vegetative cover.
The loss of cheatgrass and other vegetative cover probably would make the habitat unsuitable for the nesting of these birds.
It is likely that vegetation loss, if it occurs, would be a gradual process and effects would not, be notice-able during the early years of operation.
The impacted acreage is likely to be relatively small, but extending beyond the limits.. of construction damaged habitat.
If the postulated impact were detected it could be mitigated by temporary irrigation to flush salts below the root zone.
5.1-15
WNP-2 ER The loss of habitat acreage associated with cooling tower drift, if it occurs at, all, would affect the food chain described in Section 2.2.1 in a deleterious fashion.
The magnitude of the impact is likely to be closely related to the number of acres affected.
5.1-16
WNP-2 ER with river water, and animal products such as meat, eggs and milk from animals who eat irrigated feed or pasture grass.
Exposure via the airborne pathways includes both external exposure to skin and total body from the noble gases and internal exposure from inhalation of tritium, radioiodines and particulates released from the plant.
Also, internal exposures may be received from the consumption of foods produced from vegetation on which radionuclides of plant origin may be deposited.
Such foods include fresh leafy vegetables from local gardens and milk from cows foraging on pasture grass.
Xn addition, direct exposure,may be received from the transportation of fuel and radioactive wastes outside the plant boundary, and from the plant itself.
Figure 5.2-2 shows the exposure pathways to man from WNP-2.
5.2.2 Radioactivit in the Environment Table 5.2-1 lists the amounts and concentration of radio-nuclides that may be released to the river at a flow of 5.76 cfs via the blowdown line.
Also listed in Table 5.2-1 are the associated concentrations in the effluent stream which enters the river.
A few feet downstream from the discharge point, the.effluent will be diluted to 10% of its original concentration, while a few miles downstream the ef'fluent will be entirely mixed in the river with a dilution of 1:20,000, assuming an average river flow of 120,000 cfs.
Table 5.2-2 lists the amounts of radionuclides that may be released to the atmosphere from WNP-2.
Also listed in Table 5.2-2 are the associated concentrations in the effluent of WNP-2 which, are discharged to the atmosphere.
The effluent is then diluted further by prevailing meteorological conditions.
Table 5.2-3 lists the annual average atmospheric dilution factors (X/Q') derived from 1 year of meteorological data collected at the site (see Section 6.1 for a discussion of the methodology and release point assumptions used to determine the X/Q values)
Effluents from WNP-1 and -4 used to calculate radiation doses from those plants in this report were taken from Section 5.2 of the Environmental Report for WNP-1 and -4.
Table 5.2-4 lists concentrations of several radionuclides in various environmental media and foodstuffs.
The nuclides listed were chosen because they may be important in terms of radiation dose to man.
Assumptions used in the calculations of radiation dose to biota and to man are given in Tables 5.2-5, 5.2-6 and 5.2-7.
The models used are outlined in Appendix XI.
5.2-2
WNP-2 ER 5.2.3 Dose Rate Estimates for Biota Other Than Man Using the source terms and assumptions noted above and models in Appendix II, doses were estimated for organisms living in or close to the water such a fish, clams, and crustacea which derive an internal dose from sorption of the water in which they live and from consumption of plankton.
External doses are received from the surrounding water and sometimes from the mud on the river bottom.
Animals and
- birds, which prey on these smaller creatures, derive an internal dose from the radionuclides contained in their diet and external doses from air, water, and shoreline.
Some geese reside near the Hanford Reservation most of the year.
These birds do not consume aquatic food and so receive most of their radiation dose from external exposure to contami-nated water or shoreline.
Animals such as deer,
- coyotes, and field mice that do not consume aquatic food or spend much time at the river bank, will receive their dose through direct radiation from the plant's gaseous effluent plume, ingestion of terrestrial vegetation and external doses due to exposure to contaminated ground.
The dose from inhalation of radionuclides and consumption of terrestrial vegetation will be small.
Animals such as deer may receive an external dose rate of less than 1 mrad/yr from WNP-2 if near the plant boundary 50% of the time.
A slight additional dose may be received by such animals due to grazing.
Table 5.2-8 lists dose rates to biota associated with airborne and waterborne releases of radioactive material from WNP-2.
Numerous investigations have been made on the effects of radioactivity on biota.
No effects have been observed at dose rates as low as those associated with the proposed WNP-2 effluents.
Investigations of Chironomid larvae, bloodworms, living in bottom sediments near Oak Ridge, Tennessee, where they were irradiated at the rate of about 230 to 240 rad/yr for more than 130 generations, have shown no decrease in abundance, even though a slightly increased number of chromosome aberrations have occurred."l~
Studies have shown that irradiation of salmon eggs and larvae from the Columbia River at a rate of 500 mrad/day did not affect the number of adult fish returning from the ocean or their ability to spawn.~2~
Previously, when all the Hanford reactors were operating, studies were made on the effect of their released radionuclides on spawning salmon.
These studies have shown that these salmon have not been affected by dose rates in the range of 100 to 200 mrad/
week.
~3~
5.2-3
the site continuously occupied is more than 3 miles away from any one plant, and the point occupied intermittently by a fisherman is more than 2 miles.
The annual population dose from all sources attributable to all three plants operating simultaneously is 18 man-rem.
By comparison the background radiation dose rate from natural sources in this region is approximately 105 mrem/yr,(a) resulting in an annual dose of 28, 000 man-rem to the same population.
Therefore, routine operations of the WNP-l, WNP-2 and WNP-4 operating simultaneously at this site, will contribute a very small increment to'the total-body dose already received as a result of the natural background radiation.
Construction workers at WNP-1 and WNP-4 will receive some radiation dose due to the operation of WNP-2. If an indi-vidual were to work 0.5 mile from WNP-2, he would receive total-body dose of 2.5 mrem/yr from N-16 turbine shine.(
This worker would also receive about 0.7 mrem/yr due to the airborne release of radioactive material from WNP-2.
When WNP-2 begins operation, approximately 3200 construction workers will be building WNP-1 and WNP-4. If these workers are located an average of 1 mile from WNP-2, the total-body radiation dose to those workers would be 4.4 man-rem/yr.
/
25 mrem/yr from internal sources (mostly K-40)(8) 5.2-12
WNP-2 ER TABLE 5. 2-1 RELEASE RATES AND CONCENTRATION OF RADIONUCLIDES IN THE LIQUID EFFLUENTS FROM WNP-2
~Isoto e
H-3 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-65 Cu-64 Zn-65 Zn-69m Zn-69 Br-83 Br-84 R6-89 Sr-89 Sr-90 Sr-,91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Mo-99 Release
~(ci/
12.0 6.6E-3 2.6E-4
- 6. 7E-'3,
- 8. OE-5 7.1E-3 1.4E-3 4.0E-5 2.7E-4
- 5. 5E 4.0E-5 2.0E-2 2.7E-4 1.4E-3 1.5E-3 3.7E-4 3.0E-5 2.1E-4 1.4E-4 7.0E-5 2.2E-3 1.5E-3 7.0E-5 1.4E-'3 7.0E-5 3.1E-3 2.3E-3 2.3E-3 Concentration in Plant Effluents
( Ci/-").
2.3E+3 1.3 5.1E-2 1.3 1.6E-2 1.4 2.7E-1 7.8E-3 5.2E-4 1.1E-1
,7.8E-3 3.9
- 5. 2E-2 2.7E-l 2.9E-1 7.2E-2 5.8E-3 4.1E-2 2.7E-2 1.4E-2 4.3E-l 2.9E-1 1.4E-2 2.7E-1 1.4E-2 6.0E-1 4.5E-l 4.5E-l
WNP-2
, ER Isoto e
Tc-99m Tc-101 RQ-130 Ru-105 Rh-105 Te-129m Te-129'e-131m Te-131 Te-132 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 La-140 La-141 La-142 C-141 Ce-143 Pr-143 W-187 Np-239 TABLE Release
~(ci/
)
8.9E-3 2.0E-5
'3.0E-5 5.5E-4 1.8E-4 5.0E-5 3.0E-5 1.0E-4 2.0E-5 1.0E-5 6.4E-3 3.5E-3 1.7E-2 1.4E-3 7.9E-3 7.4E-3
- 4. 7E-.3 1.7E-2 7.2E-3 5.3E-4 5.3E-4 1.1E-4 1.7E-4 3.6E-4 4.0E-5 3.0E-5 5.0E-5 2.7E-4 7.9E-3
- 5. 2-1 2 of 2)
Concentration in Plant Effluents
( Ci/R) 1.7 3.9E-3 5.8E-3 1.1E-l 3.5E-2 9.7E-3 5.8E-3 1.9E-2 3.9E-3 1.9E-3 1.2 6.8E-1 3.3 2.7E-1 1.5 1.4 9.1E-1 3.3 1.4 1.0E-1 1.0E-1 2.1E-2 3.3E-2 7.0E-2 7.8E-3 5.8E-3 9.7E-3 4.7E-2 1.5
WNP-2 ER TABLE 5. 2-2 RELEASE RATES AND CONCENTRATIONS OF RADIONUCLIDES IN THE AIRBORNE EFFLUENTS FROM WNP-2 Cr-51 Nn-S4 Fe-59 Co-58 Co-60 Zn-65 Kr-85m Kr-85 Kr-87 Kr-88 Sr-89 Sr-90 Zr-95 Release Rate 68 1.3E-2 4.1E-3 1.1E-3 1.3E-3 1.3E-2 2.2E-3 76 270 200 240 6.1E-3 2.8E-S 5.1E-4 Concentration in Plant Effluent 8.3 1.6E-3 5.0E-4 1.4E-4 1.6E-4 1'. 6E-3 2:7E-4 9.3 3.3E+1 2.5E+1 2.9E+1 7.5E-4 3.4E-6 6.2E-S
~Zsoto e
Sb-124 I-131 1-133 Xe-131m Xe-133 Xe-135m
.Xe-135 Xe-138 Cs-134 Cs-136 Cs-137 Ea-140 CQ-141 Release Rate tci
)
5.0E-4 4.6E-1 1.7 5.0 2700 740 1100 1400 4.4E-3 3.6E-4 6.3E-3 1.1E-2 7.6E-4 Concentration in Plant Effluent 6.1E-5 5.6E-2 2.1E-l 6.1E-1 3.3E+2 9.1E+1 1.4E+2 1.7E+2 5.4E-4 4.4E-S 7.7E-4 1.4E-3 9.3E-S
GASEOUS EFFLUENTS NUCLEAR FACILITY O
0 0
c) o 0(/I C
C.
Cc C
V Cd Ql 5
0 0o 4~
G Direct Irradiation LIQUID EFFLUENTS
. figigj.
~ re )
,.o..r w 4+1, 4r eg, "~e
~
~ '>N~<~ ef oe
,gavon ee on
,.~.-,'QQg, Qg,e SAN she~&
trrigation tng':"'
0 0)
C Ch
~4 pO FUEL TRANSPORT Shorehne pooatrre Vp oe
/c 5
(0 O
0 Cr
~Q Wate, I ron eo~
, ef
~
e,S or)ece WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report EXPOSURE PATHWAYS TO MAN FIG. S.'-2
WNP-2 ER 5.3 EFFECTS OF CHEMICAL AND BIOCIDE DISCHARGES 5.3.1 Li uid Discharges The expected impacts of chemical and biocide discharges were presented in the AEC Final Environmental Statement (December 1972) as prepared at, the construction permit, stage.
The basic data and conclusions presented in that statement have not changed and are included herein by reference.
- However, supplemental discussion follows.
WNP-2 liquid effluent discharges will comply with the condi-tions of the Site Certification Agreement Between the State of Washington and the Washington Public Power Supply System for Hanford No.
2 (May 17, 1972) as amended (September 25, 1975).
This incorporates a National Pollutant Discharge Elimination System Waste Discharge Permit (in compliance with the provisions of Chapter 90.48 RCN as amended and the Federal Water Pollution Control Act Amendment of 1972, Public Law 92-500) and applicable State of Washington Water Quality Criteria or Standards contained in Washington Administrative Code 173-201.
The State criteria or standards appear in Chapter 12.
Since the construction permit application, the requirement that total dissolved gas not exceed ll0% of saturation has been added.
Nitrogen and oxygen are considered the gases of potential biological concern.
The concentrations of these
-gases in water are controlled by the temperature.
Due to its elevated temperature, the blowdown concentrations will be subsaturated with respect to river temperatures and will therefore comply with the supersaturation limitation.
Even though the blowdown will be subsaturated with respect to river temperatures at the discharge point, the State dis-solved oxygen standard will be met within a few feet, of the discharge due to rapid dilution with the river water which normally has an oxygen content ranging from 9.5 to 14.0 mg/R.
The NPDES permit (No. WA-002515-1) is contained in Appendix IV wherein discharge and monitoring conditions are given.
Table 5.3.1 lists the maximum potential increase of chemical concentrations of the Columbia River water which could result from the WNP-2 discharges.
The basic information is not changed from that reported at the construction permit stage, but is presented in a format that more directly defines the impact on river concentrations.
The maximum potential change was computed assuming a maximum chemical waste stream of 150 gpm and a maximum blowdown of 6,500
- gpm, and complete mixing with the minimum regulated Columbia River flow of 5.3-1
WNP-2 ER 36,000 cfs.
The table indicates that the increases in river concentrations are very small in comparison to ambient concentrations.
Storm water and roof drains will be collected in a separate sewer system and forwarded to an evaporation pond area.
No
- radwaste, chemical wastes or sanitary wastes will enter this system.
Trash and solid nonradioactive wastes generated by the plant will be disposed of offsite by an independent contractor.
The environmental concentrations and effects of drift are discussed in Section 5.1.4.
5.3-2
WNP-2 ER TABLE 5. 3-1 MAXIMUM POTENTIAL CHANGE IN COLUMBIA RIVER WATER QUALITY RESULTING FROM WNP-2 CHEMICAL DISCHARGES
- Calcium, ppm Ca ++
++
Magnesium, ppm Mg
- Sodium, ppm Na+
Bicarbonate, ppm HC03
- Sulfate, ppm S04
- Chloride, ppm Cl
- Nitrate, ppm N03 Phosphate, ppm P04 Total Hardness, ppm CaC03 Total Alkalinity, ppm CaC03
- Silica, ppm Si02 Dissolved Solids, ppm Maximum Concentrations Change in River
- 0. 066
- 0. 014
- 0. 01
- 0. 038
- 0. 171
- 0. 005
- 0. 0012
- 0. 003
- 0. 222
- 0. 062
- 0. 019
- 0. 247 Maximum Concentrations in River Upstream of WNP-2 32 80 28 2.6 0.62 0.13 88 76 9
115
WNP-2 ER 5.4 EFFECTS OF SANITARY WASTE DISCHARGES The amount. of sanitary waste processed at the plant is quite small relative to the capacity of the" soil to accommodate these wastes.
'Consequently, the environmental effects of sanitary waste discharge due to the operation of WNP-2 aie negligible.
Less than 2 gpm of sanitary-waste will be generated at maximum operation of the facility.
By compari-
- son, WNP-1 "and -4 will generate about 3 gpm.(1)
The disposal of the sanitary wastes to a septic tank and subsequent discharge-to tile fields will have no measur-able effect on the water quality or biota ofthe Columbia River.
The arid climate and porous ground result in satis-factory drainage without the waste surfacing due to ground saturation or plugging.
Proper design of the tile fields results in ample disinfection before the liquids enter the water table and eventually the Columbia River.
The maximum nutrient loading to the river under steady conditions would be 0.6 lb/day of nitrogen and 0.5 lb/day of phosphorus.
This waste loading would cause an increase in concentration for these constituents of less than 0.003 ppb for the lowest river flow.
This compares with ambient concentrations of from 20 to over 1000 ppb.
Much of the liquid will not enter the water table because the moisture in the ground at the shallow depths of the leach lines moves toward the surface due to evaporation and evapo-transpiration.
Contamination of the groundwater by patho-genic bacteria, if it occurs, will be restricted to within a few feet of the tile field where saturated flow conditions exist.
All of the plant water for normal operation of WNP-2 comes from the Columbia River rather than groundwater sources.
A well could supply makeup to the makeup water filters in an emergency, but this mode of operation would not be normal.
Because of the limited use of groundwater at the site and because of the limited zone of potential contamination of groundwater by tile field drainage, the operation of the sanitary tile fields will have no measurable effect on the overall groundwater resources outside the plant boundary.
The sanitary waste disposal system will conform to applicable State and County regulations, and.will comply with the Washington State Site Certification Agreement which requires that sanitary wastes not enter State waters.
- 5. 4-1
WNP-2 ER 5.5 EFFECTS OF OPERATION AND MAINTENANCE OF THE TRANSMISSION SYSTEM Effects of operating and maintaining the transmission lines are expected to be as described in the FES for the construc-tion permit stage.
However, the )i.-J. Ashe substation which is being constructed by the Bonneville Power Administration to handle the WNP-2 k00 KV transmission line and 230 KV start-up line has not been described and assessed previously.
The Ashe substation is located about 1/2 mile due north of WNP-2.
The substation requires about 37 acres of land with a 2000-ft long access road requiring about 1 acre.
The Ashe substation is scheduled to be completed just prior to the startup of WNP-2.
NEPA requirements for the construction and operation of the Ashe substation and transmission lines serving WNP-2 are being addressed by the Bonneville Power Administration.(>)
- 5. 5-1
WNP-2 ER The downstream river velocity is assumed to be known a priori from river velocity transect data, and secondary (transverse and vertical) flow effects are masked by mainstream turbulence.
In accordance with the definition of this regime, downstream velocity perturbations caused by the discharge effluent are also assumed to be insignificant compared to the mainstream flow.
Considerable simplication may be achieved if the turbulent behavior of the mainstream dominates buoyant effects.
This behavior is typical of shallow, swiftly moving streams such as the river reach which will be influenced by the WNP-2 blowdown discharge.
Also, steady flow can be assumed for the analysis of selected blowdown and river flow conditions which do not vary rapidly with time.
The advection-diffusion equation for Regime 2 can then be written:
'I BT 3 T 8 T K
+ K ax ya2 z
2 3y az where k
Ky u
k Kz ur and T = temperature x = downstream coordinate y = cross-stream coordinate z = vertical coordinate ur = downstream velocity component k
, k
= eddy diffusivities for heat, in the y and z
directions, respectively z
~In this equation downstream diffusion has been eliminated because the contribution is small compared to downstream advection.
The following summarizes assumptions used in deriving Equation (1):
1.
The downstream velocity distribution, u
, is known.
a ~riori from field data.
r'.
Buoyancy effects are insignificant.
6.1-5
WNP-2 ER 3.
Vertical and lateral velocity components are insignificant.
4.
Eddy diffusivities are homogeneous, but possibly anisotropic.
5.
Downstream diffusion is insignificant compared to downstream advection.
6.
The flow is steady in time (i.e.,
8T/St
= 0).
7.
Atmospheric effects are insignificant.
Equation (1) has the form of the classical transient heat conduction equation and may be easily solved for any desired boundary condition using well-tested numerical techniques.
For application to WNP-2, an alternating direction implicit finite difference solution was used.
Regime 3 is identified as the far field, where the effluent is moving downstream passively and is fully mixed in the vertical dimension.
Atmospheric effects, i.e.
heat, transfer across the air-water interface may become significant.
The approximate beginning of this region is ascertained by the calculation procedure outlined for Regime 2.
Regime 3 was not modeled since Regime 2 assumptions were adequate to encompass the mixing zone.
6.1.1.2 Ecolo ical Parameters Aquatic Studies at the Hanford Works for more than 30 years have resulted in a substantial amount of qualitative and quantitive information useful for impact assessment.
ln addition, the Applicant has conducted a preliminary preoperational program including literature studies(14>
and field studies of the Columbia River since 1973.(15i16)
These historic and pre-liminary studies have resulted in the knowledge of the composition, structure and function of the aquatic ecosystem that establishes the basis for the design of the preoperational monitoring program.
The preoperational program will concentrate on obtaining baseline data, from which impacts of plant operation can most probably be measured if they should occur.
Accordingly, the portion of the river immediately adjacent to the plant site will receive the most attention as will the biota most likely affected.
Monitoring of those aquatic populations unlikely to be affected by plant operation has been retained in the program, but with a lower level of effort.
The major pre-operational monitoring program tasks include benthic biota, fish, and'plankton monitoring.
6.1-6
WNP-2 ER The seasonal cycles found in ecosystems may require long-term studies to detect perturbations.
Therefore, the preoperational program will collect field data for two years prior to fuel
- load, and these data plus the preliminary data will constitute a continuous data series back to 1973.
These studies will provide additional information on the natural variations in the seasonal occurrence and abundance of important aquatic species near the WNP-2 site.
This knowledge of the extent of natural variations will permit evaluation of changes in the abundance of important. aquatic species in the vicinity of WNP-2 before and after operation.
A comparison of changes in species abundance in the vicinity of the intake and discharge in relation to changes in control areas outside the influence of the plant will also be made before and after operation.
Benthic Or anisms.
Alterations of the Columbia River aquatic biota due to the influence of the plant effluent should be most, readily indicated by changes in the structure of the benthic community in the immediate vicinity of the discharges.
The Applicant's preliminary aquatic ecological program has characterized the composition, density and seasonal abundance of the benthic fauna near WNP-2 using the same methods as those to be used in the preoperational program.
The pre-operational benthic program will focus on the benthic flora and fauna in the area of expected discharge impact.
One control station above and one below the area influenced by the discharge plume and two stations in the plume will be established.
These stations will be sampled six times per year (in January, March, May, July, September and November) to establish baseline information on community composition and abundance.
For benthic fauna, rock-filled baskets will be incubated on the bottom for two months.
On recovery, species composition, biomass and community dominance will be determined.
For benthic flora, glass microscope slides will be incubated at the same sites as the rock-filled baskets and sampled on the same frequency.
Qualitative species
- analysis, chlorophyll-a and biomass measurements will be made.
Replicate benthic flora and fauna samples will be taken to allow for statistical analysis of community changes.
Fish.
Identification of the species present in the Hanford stretch of the river is essentially complete.
The Applicant's preliminary program has examined the spatial, and temporal distribution, species relative abundance, age structure and feeding habits of fish found near the WNP-2 site.
In the preoperational
- program, emphasis will be placed on fish found in the immediate vicinity of the intake and the discharge plume.
Species and numbers of fish residing seasonally near the plant will be examined with particular attention given to anadromous outmigrants.
Samples will be 6.1-7
WNP-2 ER obtained using one or more of the following sampling methods:
hoop-nets, electroshocking, gill netting or beach seining.
A tag and release program will be used in an attempt to determine population size and-time of residence within the study areas.
Fish sampling will be conducted monthly with additional samples in the months of June., July, August and September for a total of 16 sample periods per year.
SCUBA diver observations of fish populations will routinely be recorded during benthic sampling dives to the extent permitted by the visibility characteristics of the Columbia River.
Plankton.
Some fraction of the river's plankton will be drawn into the plant with the cooling water and another fraction will be exposed to the effects of entrainment in the discharge plume.
The numbers so affected are an extremely small fraction of the population passing the plant.
Studies conducted by the Applicant on the Columbia River indicate that planktonic algae and microcrustaceans in the aquatic system near WNP-2 do not have a major role in energy transfer pathways.
No significant impact on the plankton community is expected because of the small volume of water withdrawn by WNP-2, and the small volume influenced by the discharged water compared to the total river flow.
Nonetheless, phyto-and zooplankton studies will be conducted, although on a limited basis.
Previous investigations by the Applicant indicate that samples representative of the river plankton population may be obtained from any one station and depth.
Therefore, during the preoperational program monthly plankton samples will be taken at one station and one depth.
These samples will be used to determine phyto-and zooplankton species relative abundance and baseline biomass.
This program will provide a continuous indicator of changes in the plankton population.
6.1.2 Groundwater The Energy Research and Development Administration (ERDA) through its contractors has drilled about 1,500 wells on the Hanford Reservation.~17~
More than 20 wells are located within 5 miles of the project site and 6 wells are installed in the immediate vicinity of the site;~18~
see Figure 2.4-15.
Extensive environmental monitoring programs concerning the
- physical, chemical and radiological characteristics of ground-water have been conducted under the ERDA auspices.
These 6.1-8
WNP-2 ER monitoring programs and investigations have already accumu-lated quite comprehensive information on groundwater characteristics and are expected to be continued routinely as part of the ERDA program.
However, the Applicant will undertake a limited groundwater monitoring program in the vicinity of the site as described in the construction permit stage FES.
6.1.3 Air 6.1.3.1 Local Meteorolo Onsite meteorological data have been collected at the WNP-2 site.
The meteorological data collection system consisted of a 245-ft tower, an auxiliary 7-ft instrument mast, sensors with associated electronics and recording devices, and a
meteorological building.
A temporary meteorological system began collecting data at the same location in March 1974 and was discontinued (September 1974) once the satisfactory operation of the new system was verified.
The temporary.meteorological system consisted of a 23-ft mast with an aerovane wind sensor.
Data was recorded on chart paper.
Air temperature and rela-tive humidity were recorded by use of a hygrothermograph in an adjacent weather screen.
The current meteorological system consists of a primary tower 240 ft high with an extending 5-ft mast.
The primary tower is triangular in shape and of open lattice construction to minimize tower interference with meteorological measurements.
Wind and temperature measurements on the main tower were made at the 245-ft and 33-ft levels.
At the 33-ft level the instruments (wind, temperature, and dewpoint) were mounted on an S-.ft horizontal boom extending west-northwest of the tower.
Wind and temperature measurements were also made at the top of the 7-ft mast which is located approximately 80 ft to the southwest, of the 245-ft tower.
Wind speed measurements were made using conventional cup anemometers (Climet Instruments, Model 01101 Wind Speed Transmitter).
The instruments have a response threshold of about 0.6 mph and a distance constant of less than 5 ft.
Over a calibrated range of 0.6 to 90 mph, the accuracy of these instruments is
+1% or 0.15 mph (which-ever is greater).
Wind direction measurements were made using lightweight vanes (Climet Instruments, Model 012-10 Wind Direction Transmitter).
The response threshold of these vanes is about 0.75 mph, and their damping ratio and distance constant are approximately 0.4 and 3.3 ft, respectively.
Dual potentiometers in the 6.1-9
WNP-2 ER Wind Direction Transmitter produce an electrical signal covering 540'n azimuth with an accuracy of within +2'.
In addition, electronics have been included to provide signals which are proportional to the standard deviation (ag) of the wind direction fluctuations at each level.
Temperature instrumentation provided measurements of both the ambient air temperature at the 245, 33, and 7-ft levels and the temperature differences between these levels.
The ambient air temperature and the temperature difference sensors are independent of each other to provide reli-ability. All temperature measurements for both systems are made in aspirated temperature shields (Climet Instruments Model 016-1 or -2) using platinum resistance temperature devices (Rosemount Engineering Co., Model 104 MB6ABCA).
These instruments provide an ambient temperature range from -40'F to +120'F and a temperature difference range of
+15'F.
The accuracy of the instruments exceeds
+0.9'F in the measurement of temperatures and +0.18'F in tEe measure-ment of temperature differences.
The dewpoint temperature was measured at the 33-ft level of the tower using a lithium chloride dewpoint sensor (Climet Instruments, Model 015-12) housed in an aspirated tempera-ture shield (Climet Instruments, Model 016-2).
The accuracy of this measurement in the normal range of measurement is better than +0.9'F.
Precipitation was measured at, ground level using a tipping bucket rain gage (Meteorology Research, Model 302) located about 40 ft west. of the main tower.
This instrument is accurate to within +1% at rainfall rates up to 3 in./hr and has a resolution of 0.01 in.
The instrument building provided a climate-controlled environ-ment near the tower to house the instrument electronics and record the data.
Both digital magnetic tape and analog strip chart recorders were used providing redundant data recording capability.
The primary data recording system is a 7-track digital magnetic tape recorder (Kennedy, Model 1600) that uses 1/2-in. tape.
Logarithmically, time-averaged wind
- speed, wind direction, temperature, temperature difference, and dewpoint temperature signals were recorded at 5-minute intervals.
The time constant of the averaging process is 5 to 15 minutes.
The standard deviation of wind direction fluctuations during the preceding 5 minutes at each level and the total precipitation were recorded along with the wind and temperature information.
All data, except the wind direction standard deviations, were recorded on strip 6.1-10
WNP-2 ER charts.
Besides enhancing data retrievability, the strip chart records provided a rapid means of identifying instru-ment malfunctions and were useful in system calibration.
Strip charts and magnetic tapes were changed weekly.
To ensure the quality of the meteorological data collected by the monitoring system, an extensiv'e quality'ssurance program was instituted.
This program covered all phases of meteorological monitoring from the initial instrument acquisition through the analysis of data.
Periodic checks and calibration of the instrument systems and individual components were instituted.
These periodic checks ranged from daily inspection of the strip charts to semi-annual calibration of the complete system.
All checks, calibrations, and maintenance were fully documented includ-ing traceability of test and calibration equipment to the National Bureau of Standards where necessary.
The data, once collected, were protected from loss to the maximum extent possible.
The digital tapes were examined to identify possible instrumentation malfunctions.
The data were then copied onto two master tapes.
The original weekly tape and one master tape were stored in vaults; The second master tape was used in the preparation of data summaries.
Finally, to ensure proper operation of computer hardware and software, all computer programs used to summarize or analyze the data were checked quarterly.
These checks were performed using a
standard data input.
The computer output from these tests was saved to document computer operation.
6.1.3.2 Models Dis ersion Estimates.
Short-term diffusion estimates were made in accordance with applicable documents(
9
) using data from the 245-ft meteorology tower at the WNP-2 site.
The basic Gaussian diffusion model for a groundlevel release is e'mployed using lateral (ay) and vertical (az) spread parameters determined experimentally at Hanford.'(22)
For long-term diffusion estimates, the Hanford speed para-meters are used in the Gaussian diffusion model for a ground-level release.
Assumptions in the calculation are reflection of the plume at the ground, no plume depletion by surface deposition or washout, and uniform occurrence of the plume within each sector.
The appropriate form of the Gaussian model is 2n (2m) a u
(2)
WNP-2 ER where
~ = normalized air concentration Q
n = number of sectors u = mean wind speed Sixteen sectors were used.
The values of ay and az used for stable atmospheric conditions pere determined experimen-tally at Hanford and are given by:<
2 a
=At-Y A
2 1-exp 2 (o>u) 2 (a<u) t, (3)
A = 13.0
+ 232a u
8 (4) a
= a 1-exp(-k t
)
+ bt 2
2 2
z (5)
= x/u (6) where t '= time x = downwind distance o
= horizontal wind-direction standard deviation e
=
and the coefficients are given as:
Moderately Stable Ver Stable b
k 97 m2 0.33 m /sec 2.5 x 10 sec 34 m
0.025 m /sec 2
4
-2 8.8 x 10 sec For neutral and unstable formulations 2
g 2
C 2
2 z
0 z 2
(2-m) x (7)
(2-m) x (8) atmospheric conditions the Sutton 6.1-12
WNP-2 ER used where the coefficients for a groundlevel release are given as:
Wind Speed m/sec Unstable Neutral CY C
0.10(11<2.0 2.0 <G<7.0 7.0
<u 0.22<u<2.0 2.0 <U<7.0 7.0
.ll Class hT hz (OF/200 ft)
<-2.1 Re ulator Guide 1.23 Class bT hz
'F 200 ft)
Unstable
<-1.5 Definition for Hanford Diffusion Parameters
-2.1 to -1.9
-1.9 to -1.6 Neutral
-0.5 to -1.5 D
-1.6 to -0.6
-0.6 to 1.6 Moderately 3.5 to -0.5 Stable 1.6 to 4.4
>4.4 Very Stable
>3.5 The above described model is consistent with standard methods with the exception that the plume growth rates used are those 6.1-13
WNP-2 ER determined to be most appropriate for the Hanford area based upon many diffusion experiments at Hanford.
To demonstrate the effect of dilution in the building wake cavity on estimates of sector-averaged values (crosswind integrated),
az was replaced by B '~'
+-
z, vr (9) where c = empirical coefficient, conservatively taken as 0.5 B = cross-sectional area of building normal to wind Hourly 30-minute averages of a and hT were used to determine the plume growth parameters, as discussed
- above, and X/9 for e
each hour of the year for each sector and selected distances.
For calm wind conditions, a speed of 0.22 mph was assumed (threshold of the instrument); for a> less than 1',
a value of 1'as assumed.
Methods Used for Modelin Cooling Tower Atmos heric Plumes.
A computer program, utilizing diffusion and cumulus cloud models was used to estimate the environmental effects of the circular'echanical draft, evaporative cooling tower.
One year of onsite meteorological hourly data from the temporary meteorological system was combined with hourly stability data from the Hanford meteorology tower for the analysis.
Indi-vidual plume characteristics are calculated and the results summarized in monthly and annual tables.
The plume rise from the circular mechanical draft cooling towers of WNP-2 are calculated using a modified heat input term in the Briggs plume rise equations.(23)
This heat input term was calculated based on the Weinstein and Davis(24 '5j cumulus cloud model at 0400 and 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> each day.
The cumulus cloud model and the Briggs model predictions were compared and correction factors calculated for the heat input to the Briggs model.
The correction factors were then linearly interpolated for other hours and applied to the Briggs model predictions for those hours.
The plume rise estimates were used to define the centerline of the plume, while the prevailing wind direction defined the direction of movement.
It was assumed that for a given set of design and meteoro-logical conditions, vapor leaving a cooling tower diffuses 6.1-14
WNP-2 ER elevation at the Hanford Meteorological Station were used in the calculations.
It was assumed that the period 0600 to 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> daily was thermally unstable or neutral, and that the nighttime period, 1800 to 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, experienced stable atmospheres.
Mean 400-ft wind speeds associated with these periods were 9.5 mph for winter days, and 10.9 mph for winter nights.
Roffman and Van Vleck show that the state-of-the-art (28) of predicting the salt deposition from drift droplets is such that the values obtained by various methods vary by a factor of +10.
The present estimates are considered a
maximum as a result of the choice of generally conserva-tive assumptions for the calculation.
6.1.3.3 Air Quality As a result of the small quantities of nonradiological air pollutants to be released, the Applicant does not propose to initiate a nonradiological preoperational air quality monitoring program.
An independent system is operated by the Hanford Environmental Health Foundation.
This program includes measurement at, several locations in the Hanford area of airborne particulates, SO2 and N02.
These measure-ments as well as other air quality aspects of the site have been discussed in the PSAR (Section 2.3.1).
6.1.4 Land Much applicable land-monitoring information related to the WNP-2 site has been collected over the years by ERDA.(17)
Research field studies, particularly of soils and terres-trial ecology, were carried out on the Hanford Reservation by ERDA contractors.
- Thus, the data base in this case is substantial with regard to land monitoring information.
6.1.4.1 Geolo y and Soils The Hanford Project, including the WNP-2 site, has been the object of many geologic studies, mainly of a topical nature.
McHenry(30) characterized the chemical and physical proper-ties of soils of the project from drilling samples collected from approximately 40 wells spaced about the project.
Hajek(31) classified the soils of the project on an agri-cultural basis.
Earlier topical geology studies, related primarily to aspects of radioactive waste disposal, included subsurface geology of the Hanford area, identification of stratigraphic units, correlation of volcanic flows, and aquifer descriptions.(32 37) 6.1-17
WNP-2 ER Additional and detailed information on geologic studies, soil boring patterns, and analytical and testing methods used are contained in the Final Safety Analysis Report.
Although research studies have been carried out over a
number of years concerning terrestrial ecology on the Hanford Reservation, none of these studies have been aimed at assess-ing impacts of cooling tower drift.
Cooling tower drift will be a new kind of environmental stress for Hanford Reservation ecosystems.
The vegetative cover growing in the near vicinity of the cooling towers consists primarily of cheatgrass, Bromus tectorum.
This grass provides the main biotic protection agarnst soil erosion.
Because the climate is dry, salt dissolved in drift droplets is expected to accumulate in the soil profile.
Salt accumulation is expected to be most concentrated near the base of the cooling tower and rapidly decrease with increasing distance from the tower.
The longer the cooling towers are operational, the more intense the salt accumulation.
Although it is expected that cheatgrass will be tolerant of moderate increases in soil salt and pH values, there are no data presently available to judge the magnitude of increased soil salt concentrations needed to significantly impair the germinability of cheatgrass seeds.
This is an important point because cheatgrass is an annual grass and the stand originates from seed each year and there is no known plant that is as successful in this habitat as is cheatgrass.
The preoperational monitoring program will obtain data concerning plant species composition and canopy-cover pro-vided by the natural vegetation in the vicinity of the cooling towers and a measurement of existing soil salt concentrations and soil pH.
Vegetation analyses will be done according to the proce-dures developed by Daubenmire.(38)
Each study site will be permanently marked so that the same plots can be examined systematically during post-operational monitoring studies.
Soil samples will be collected from sites adja-cent to but not on the plant study plots and analyzed for salt content, electrical conductivity of soil extract and pH (soil paste).
Study sites will be spaced at intervals in the two predomi-nant downwind directions (SE and N to ENE) at distances ranging from 100 to 1000 meters from the plant.
In addition, a site will be selected at a location sufficiently removed from the plant to serve as a control plot.
6.1-18
WNP-2 ER Terrestrial animal populations are not expected to be signi-ficantly altered by cooling tower drift unless plant cover is altered.
6.1.4.2 Land Use and Demo ra hic Surve s
Land use in the immediate vicinity of the WNP-2 site is under the control of ERDA, and the staff of the Richland Operations Office provided the source material required for land use descriptions of Hanford Project facilities.
Addi-tional information related to off-project land uses was obtained primarily from the Bureau of Reclamation Regional Office, which is responsible for much of the land develop-ment in surrounding areas, from the Soil Conservation
- Service, and from the Washington State Department of Agriculture.
Some information was provided by the County Planning Offices in adjacent counties; however, this was generally related to county zoning rather than actual current land use.
The collected published data were supplemented with information obtained from personal conversation with county planning and other local, county, State and Federal agency officials and through reconnaissance surveys of those areas where missing or questionable data were concerned.
Demographic data for the latest census year (1970) were obtained from Bureau of the Census publications.
Informa-tion for population projections was available from the Washington State Office of Program Planning and Fiscal Management,(39) the Portland State University Center for Population Research and Census,(40) the Bonneville Power Administration,(
) the Pacific Northwest River Basins Commission,(4>)
Pacific Northwest Bell,(43) and the Tri-City Nuclear Industrial Council.(44)
Rural population trends were based also on estimates developed for the Columbia Basin Development League.(45)
Information from these sources were used by the Applicant to project population for future census years over the expected life of the plant.(46i47)
In conjunction with the construction of WNP-1 and -4, the Applicant is conducting a program to monitor the socioeconomic effects.
The results of this study will be partially appli-cable to WNP-2.
The purpose of the study is to document,
- assess, and project the primary and secondary socioeconomic effects and impacts of construction and operation of WNP-1 and -4.
Two phases are defined in implementing the study.
The first phase will emphasize measurement and documentation of socioeconomic effects during the first 3 years of con-struction of the WNP-1 and WNP-4 projects.
Preliminary reports will be on an annual basis for each of these 3 years.
The second phase of the study will be to prepare a final report which will:
1) make an evaluation of the accuracy 6.1-19
WNP-2 ER
/
of a previously conducted impact projection report and 2) make new projections, if found necessary, independent of the previous study, based on updated information developed in the preliminary reports.(46.47)
The important socioeconomic factors expected to be studied in detail are listed below:
in-migrant workers and families resident workers and families the relationship between contract construction on WNP-1 and -4 and secondary employment tax revenues accruing as a result of WNP-1 and -4
~
economic conditions in the study area
~
schools
~
housing
~
government services and facilities
~
traffic flow and transportation
~
social and health services
~
police and fire protection 6.1.4.3 Terrestrial Ecolo The important local flora and fauna are being identified to the species
- level, and the relationships of the fauna to the vegetation and to the salient climatic and soil features of the local environment are being described.(48)
Special attention is being given to the occurrence of species that are believed to be rare or in danger of becoming extinct.
Recommendations will be made to preserve special habitats necessary for the continued existence of such species should they occur in the local area.
The important shrub-steppe food chains are also being identified.
Ve etation Studies.
Aerial photographs in natural and infrared color of the site and adjacent area were made by the Applicant to provide a basis for mapping the extent of existing plant communities between the plant site and the Columbia River.
- 6. 1-20
WNP-2 ER Study plots were established in each major plant community to provide a record of the plant species that comprise each community.
A measure of the relative abundance of each species is being made using conventional field ecology methods of determining density and/or canopy cover for each species encountered in the study plots at appropriate seasons of the year.
Plant species that are potentially import'ant as forage for wildlife or domestic livestock are being identified.
The expected pattern of secondary plant succession following the destruction of existing vegetation by fire or mechanical means will also be described.
The chemical and physical properties of a representative soil profile will be analyzed to provide a basis for recommending the kinds of plants that would be useful in revegetating soils disturbed by construction activities.
Animal Studies.
Estimates of the density of small mammals are being made by live trapping in conjunction with conven-tional mark and release techniques.
Live traps were set in a grid pattern to allow an assessment of home territories of individual animals.
Trapping is being conducted periodically throughout the year to obtain information concerning the seasonal appearance of young animals.
The weights,
- age, sex, general health, and the occurrence of external parasites on each captured animal are being recorded and stored in computer compatible format.
An aerial census of the larger mammals, i.e., deer and coyote is being made twice each year to obtain an estimate of the use of the local areas made by these kinds of animals.
A census of bird populations is being made by walking along pre-arranged transect lines and counting birds with the aid of binoculars.
Special attention is being paid to the birds that use the local plant communities as nesting habitat and birds that are ordinarily hunted as game or are regarded as being in danger of extirpation.
Observations are being made as to the abundance of other species of vertebrate animals, especially jackrabbits,
- lizards, snakes, and the occurrence of important invertebrates, such as ground-dwelling darkling beetles and grasshoppers that are impor-tant items in food chains.
6.1.5 Radiolo ical Monitorin A radiation measurement program will be conducted for a period of approximately two years prior to plant fuel loading and 6.1-21
WNP-2 ER continue for one year after plant start-up.
It is expected that no significant changes due to plant operation will be detected.
If verified, both the frequency and scope of the measurements will decline.
Details of the radiological monitoring program are described in the FES* for the construc-tion permit stage.
The FES statement that ground water samples will be taken from "private" wells is in error.
The wells identified for sampling are all on the Federally owned Hanford Reservation.
6.1-22
WNP-2 ER
'TABLE '6. 1-1 MASS SIZE DISTRIBGTION OF DRIFT DROPLETS (Mechanical Draft Tower)
- Diameter, m
Percent of Mass 0- 50 50-100 100-150 150-200 200-250 250-300 300-350 ll 20 16 13 ll
WNP-2 ER 6.2 OPERATIONAL ENVIRONMENTAL PROGRAM The scope and general content of the operational environ-mental monitoring program and special topical studies are described in the following subsections.
In all cases these programs may be modified based on the results of the preo-perational programs and the first year of operational data.
Program details, including administrative controls and reporting plans, are contained in the Environmental Techni-cal Specifications in Appendix,I.
6.2.1 Surface Water Thermal Monitorin Continuous recordings will be made of the temperature of the blowdown and the makeup water.
These measurements will be made in the circulating water pumphouse and in the make-up water pumphouse, and will be representative of blowdown discharge temperatures and ambient river temperatures near the intake.
Intake temperatures will not be representative of ambient conditions during those periods when make-up water is not being withdrawn.
Columbia River temperatures will be measured monthly approx-mately 300 feet downstream and immediately upstream of the discharge.
Chemical Monitorin Blowdown water will be sampled for the following:
Parameter Quantity Dissolved pHTurbidity Chlorine Coliform Dissolved Oxygen Solids Continuous recording Once per day Continuous recording Continuous recording Continuous recording Once per week Once per week Total residual chlorine will be measured continuously only during chlorination and for two hours after blowdown dis-charge commences, or until it reaches undetectable levels.
6.2-1
WNP-2 ER The following environmental measurements will be made approxi-mately 300 feet downstream and immediately upstream of the discharge:
Parameter Dissolved Oxygen pHTurbidity Chlorine (Total Residual)
Coliform Dissolved Solids Once per month Once per month Once per month Once per month Once per month Once per month Thermal and chemical monitoring data will be correlated with river flow and blowdown conditions.
To ical Studies Blowdown dispersion characteristics will be determined in a field study by injecting a tracer into the blowdown system prior to actual fuel load or plant startup.
The study will define the eddy diffusivity effective for plume dilution for low and average river flow conditions.
Chlorination requirements will be studied during the first year to determine the minimum daily discharge duration of free available and total residual chlorine which w'ill allow the plant to operate efficiently.
River velocity and flow patterns will be monitored in the vicinity of the intake and discharge structures for one year for a range of flow conditions.
6.2.2 Ground Water Annual ground water measurements will include temperature, pH, coliform, and water table elevation.
6.2.3 A atic Environment The operational aquatic monitoring program will be designed based upon results of the preoperational program described in 6.1.1.2.
Until that time, it is assumed that both programs will be similar with the exception that the below described topical studies will be part of the operational monitoring program.
Visual intake screen inspections will be conducted by divers at least monthly from March through November, when they can be safely conducted, for the first year of operation for the purpose of monitoring for fish impingement and to determine the frequency at which screen cleaning will be reauired.
- 6. 2-2
W1P-2 ER During the first year of operation a study of the intake system will be conducted to evaluate the number of juvenile fish entrained.
It is expected that this study can be com-pleted prior to actual operation of the plant.
Fish entering through the intake will be trapped in screened cages inside the intake pump well.
The impact of the intake on downstream migrating salmonoid fry will be emphasized in the study.
The operational radiological monitoring program will be the same as the preoperational program described in the AEC Final Environmental Statement (December 1972)* for the first year of operation.
The scope of monitoring in subsequent years will be determined based upon the results of the two-year preopera-tional program and the first year's operational program.
6.2.5 Meteorolo ical The operational monitoring program will include wind speed, direction and temperature measurements made at the 245 and 30 foot levels, and dewpoint measurements at the 30 foot level.
Rainfall amounts and intensities will also be measured.
Real-time wind speed, direction and stability data will be available in the control room.
6.2.6 Land The first year operational program will continue the preopera-tional programs described in 6.1.4 unless preoperational results indicate changes are necessary.
- The AEC FES statement that ground water samples will be taken from "private" wells is incorrect.
The wells identified for sampling are all on the federally-owned Hanford Reservation.
- 6. 2-3
WNP-2 ER A enc Pro ram U.S.
Army Corps of Engineers, Grant County
- PUD, Chelan County PUD National Marine Fisheries Service Studies of upstream adult migrant fish passing Columbia River dams.
These fish counts are generally made from 'April to October each year.
Research on the enhancement of downstream passage of juvenile salmonids at Priest. Rapids Dam and other PUD dams on the Columbia River.
6.3.3.
Ecolo ical Parameters Terrestrial Studies in Pro ress A enc Pro ram Washington Public Power Supply System Studies by Battelle-Northwest including characterization of small mammal populations in burned and unburned shrub-steppe plant communities, avi-fauna of shrub-steppe plant communities, ecological charac-terization of burned and unburned shrub-steppe plant communities, primary production of cheatgrass, and aerial photography of shrub-steppe plant communities.
U.S. Energy Research and Development Administration, Division of Biomedical and Environmental Research U.S. Energy Research and Development Administration, Division of Biomedical and Environmental Research A small mammal trapping study by Battelle-Northwest is on the WYE burial ground located immediately west of the WNP-2 site.
This study has been in progress for 2 years and yields information on abundance, age, weight, and sex ratios of great basin pocket mice.(>4)
Extensive ecological studies by Battelle-Northwest concerning plant and animal communities have been conducted on the Arid Lands Ecology (ALE) Reserve since 1968.
The ALE Reserve is located about 10 miles west of the WNP-2 site.(
6.3-5
WNP-2 ER A enc Pro ram U.S. Energy Research and Development Administration, Division of Biomedical and Environmental Research Mule deer fawns have been tagged by Battelle-Northwest along the Columbia River for a number of years to determine mule deer movements beyond the Hanford Reservation.
A nesting survey of the Columbia River Canada goose population has been conducted for nearly 30 ye>>s.(14>
U.S.
Energy Research and Development Administration, Division of Biomedical and Environmental Research Radiotracking of coyotes and breeding ecology of raptors and long-billed curlews are currently being studied by Battelle-Northwest og tQe Hanford Reservation.<
6.3.4 Meteorolo ical Monitorin Pro rams in Pro ress A enc Pro ram Washington Public Power Supply System Meteorological data collection at the WNP-2 site by Battelle-Northwest from March 1972 to September 1974 with temporary system and from September 1974 to June 1976 with permanent system.
Temporary system measurements included wind speed on 23-ft mast, air tempera-ture and relative humidity.
Permanent system measurements included wind speed and air temperature at top of 7-ft mast and at 33-ft level and top of-245-ft tower, dewpoint, tempera-ture at the 33-ft level, and precipitation at ground level.
U.S.
Energy Research and Development Administration, Richland Operations Office The Hanford Meteorological
- Station, 14 miles west-north-west of the WNP-2 site, is operated for ERDA by Battelle-Northwest.
This station is manned by an observer-forecaster 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
Complete surface weather observations are made hourly.
Wind and tempera-ture profiles from the surface 6.3-6
COLUMBIARIVER 4
ELlENS BURG HANFORD BOUNDARY OTHEI.LO WAHLUKE 1
~g ~o BERG RANCH VERNITA r BRIDGE WAHLU A
YAKIMA~
YAKIMAR I VER
~ CONNELL KE
~ COOKE BROS PA BENTON RICHLAND CITY x BACKGROUND AIR SAMPLING LOCATION
~ PERIMETER AIR SAMPLING LOCATION WASHINGTON BARRICADE RATTlESNAK~E SPRINGS BAXTER SUBSTATION SUNNYS I DE ERC "i BYERS LANDING "pc SCO WASHTUCNA
" WALLAWALlA 0
10 20 MILES McNARY DAM>
OREGON WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 Environmental Report HANFORD ENVIRONMENTAL AIR SAMPLING LOCATIONS DURING 1975 PIG ~ 6.3-1
HANFORD BOUNDARY STATE HlGHWAY24 1~
100D VERNITA BRIDGE COLOMBIA RIVER IIXN ue ~*
OLD HANFORD o
I TOWNSITE I
-1 WYEr BARRICADE VlPPSS
/
IDOBQ'00C YAKIMA
/ BARRICADE PROSSER BARRICADE 0
F FTF SUNNYSIDE
+o R I CHIAND
~
BARRICADE 300 0
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WNP-2 ER 6.4 PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING DATA The subject monitoring program is scheduled to begin two years prior to fuel load.
Fuel load is currently estimated to be December 1979. 'onitoring data will be amended to this section as available.
- 6. 4-1
WNP-2 HR 2.
the water seal can be overpressurized, 3.
the water can leak through a faulty drain.
I Although the failure of the water seal is unlikely, it is nevertheless placed in the upset category (Section 7.1.11).
7.1.4 Class 4
Fission Products to Primar S stem Events which lead to the release of activity into the primary system are a result of transitory stress which exceeds the mechanical properties of the cladding material.
7.1.4.1 Fuel Claddin Defects Random cladding defects are allowed for in design and are in-cluded and evaluated in Section 5.2.4.2 under normal operation.
7.1.4.2 Off-desi n Transients that Induce Fue'1 Fa'ilures Above Those Ex ected The plant design criteria includes the requirement that any anticipated transient event concomitant with a single equip-ment malfunction or single operator error must not result in a minimum critical heat flux ratio (MCHFR) less than 1.0 for any normal plant operating mode.
Since the design basis cor-relation(3) used in determination of the CHF is conservatively selected with a large margin between predicted and observed CHF, fuel which experiences a MCHFR of 1.0 is not likely to have cladding failure. It is, therefore, concluded that there are no off-design transients other than the control rod drop accident identified in section 7.1.8.3, which induce fuel failure above that. normally expected.
7.1.5 Class 5
Fission Products to Secon'dar S stem In the direct cycle BWR, "secondary system" is interpreted to mean the secondary side of heat exchangers whose primary side contains primary system coolant.
The BWR system has several heat exchangers in this category:
1.
main turbine condenser, 2.
RHR heat exchangers, 3.
drywell cooler heat exchanger, 4.
spent fuel storage heat exchanger.
All of these heat exchangers are operated in a mode or employ an intermediate heat exchanger which precludes the release of activity to the environment.
The main condenser is protected 7 ~ 1 3
WNP-2 ER during plant operation by the normal vacuum.
The drywell, and spent fuel heat exchangers are protected by being cooled with a closed cooling loop, the RHR heat exchangers are pro-tected by being cooled by the cooling towers or spray pond.
In addition during shutdown cooling the cooling water side is maintained at a higher pressure to prevent any out leakages to the Cooling System.
7.1.6 Class 6
Refuelin Accidents (FUHA)
The fuel bundle is the heaviest object which could be dropped onto the core during normal refueling operations.
The fuel bundle drop is postulated to occur as a result of equipment failure during the refueling process and occurs within the reactor cavity above the core.
7.1.6.1 Estimated Release The following parameters are used to determine the amount of activity released to the environment.
l.
The accident occurs four days after shutdown.
2.
8 fuel rods are damaged.
3.
A water partition factor of 10 is used for iodine.
3 4.
SGTS filter efficiency is 99.9% for all forms of iodine and 0% for noble gases.
5.
The volumetric leak rate from the reactor building is 100%/day.
7.1.6.1.-2 Estimated Dose The dose calculated for this accident is shown in Table 7.1-2.
7.1.6.1.3 Probabilit Considerations See subsection 7.1.7.1.3.
7.1.7 Class 7
S ent Fuel Handlin Accident Spent fuel handling accidents are of dropping a fuel bundle onto the fuel and dropping a spent fuel cask.
The is a design basis accident; the cask peated to result in fuel damage.
two essential types:
in the fuel storage
- area, fuel bundle drop accident drop accident is not ex-7.1.7.1 Fuel Assembl Dro in Fuel Stora e Pool (FUHA)
This accident is postulated to occur while a fuel bundle is
- 7. 1-4
WNP-2 ER the assumed 10 rods is insufficient to cause a radiation level high enough to trip the main steam line isolation valves.
How-ever, it is high enough to cause isolation of the offgas system For the purpose of evaluating the consequences of this ac-cident, it is assumed that 100% of the noble gases and 1% of the iodine activity released from the failed fuel rods is transferred to the condenser.
Since the offgas system and ultimately the reactor vessel are isolated, it is assumed that the condenser activity achieves an equilibrium condition be-tween the condensate and the free volume and is released un-filtered to the environment at a rate of 0.25% of the con-denser free volume per day.
7.1.8.3.2 Estimated Dose The dose calculated for this accident is shown in Table 7.1-2.
7.1.8.3.3 Probabilit Consideration For a rod drop accident to occur the control rod must first become detached from the drive, remain lodged in position while the drive is fully withdrawn from the core, and then, become disloged and fall freely.
This complex series of events is offset by the many annunciators and procedures that are meant to avoid such an event, for example:
rods are test-ed weekly, thus providing many opportunities for a uncoupled rod to be detected.
Actual experience has been good.
However, conservative judge-ment indicates that this event should be assigned as an emer-gency condition (See Section 7.1.11).
7.1.8.4 Li uid Radwaste Tank Accident (LRTA)
The postulated accident is assumed to occur as a result of a catastrophic failure of the waste storage tanks.
The design of the radwaste building precludes the release of liquid rad-waste to the cooling pond;
- however, some evaporation may occurs
~N 7.1.8.4.1 Est'imat'e'd Releases The liquid radwaste tanks are not pressurized nor are they kept at a high temperature.
Nevertheless, because of evaporation, it. is assumed that 0.5% of the iodines become airborne and are released to the environment.
7.1.8.4.2 Estimated Dose The resultant doses for this accident are shown in Table 7.1-2.
7.1-9
WNP-2 ER 7.1.8.4.3 Probabilit Considerations Although the below grade liquid radwaste tanks are unpres-surized accumulators, they are designed in accordance with the appropriate ASME codes.
There are no other parts other than piping attached to the tanks.
Therefore, the probability of a radwaste tank failure is so low as to place it in the fault category (See Section 7.1.11).
7.1.8.5 OffGas S stem Accident (OGSA)
The postulated accident for this category. is the failure of a charcoal tank in the offgas system.
The tank with the largest noble gas inventory is assumed to fail and spill the contents of the tank.
7.1.8.5.1 Estimated Release The activity inventories of the offgas system are based on an offgas release rate of 60,000 microcuries per second for noble gas and on a reactor water coolant concentration of.005 microcuries per gram for I-131, with 2% steam cherry over, and a condenser decontamination factor of 7.2 x 10
. It is also assumed that 5% of the noble gas inventory and 0.5% of the dine inventor are released.
10 Y
These release fractions are based on evaluation of the retention characteristics of charcoal for spillage of the entire contents of the tank.
7.1.8.5.2 Estimated Dose The. dose calculated for this accident is shown in Table 7.1-2.
7.1.8.5.3 Probabilit Consideration The offgas system is designed and constructed in accordance with appropriate ASME codes.
In the unlikely event that the tank fails only a small fraction of the contents would be released to the environment.
The probability of such an oc-currence is so low as to classify a release to the environment in the fault category (See Section 7.1.11).
7.1.9 Trans ortation Accidents Accidents in this category have no significant impact on the environment,
- however, they are discussed for the purpose of completeness of this report.
7.1.9.1 Shi ment of S ent Fuel An evaluation by the AEC of the frequency of accidents in-volving the shipment of high level radioactive wastes shows
- 7. 1-10
WNP-2 ER
- that, on the average, approximately 0.05 accidents may occur in transportation during the lifetime of a light water re-actor(9).
In addition to the very low occurrence rate of ac-
- cidents, the consequences of an accident involving radioactive material are mitigated by the procedures which carriers are required to follow(10).
These procedures include:
separation of persons from packages or materials and immediate notification of the shipper and DOT in case of an accident, fire, or leaking package.
Therefore, in the unlikely event an accident occurs, the radiological exposures will be limited to a relatively small number of persons and does not present any concern to the general population.
7.1.9.2 Low Level Radwaste Shi ments The only time a radiological exposure could be received in rad-waste shipment is for the case of an accident involving the solid waste drums.
These drums usually contain a very "stiff" or viscous slurry or are actually mixed with polymer and cata-lyst to form a solid.
Such exposures would be minor and would be limited to those workers involved in any necessary cleanup following the accident.
The effect to the -population is judged to be insignificant.
7.1.9.3 New Fuel Shi ment New fuel is normally shipped by rail in containers designed to protect them from physical damage due to the normal handling and vibration of transportation.
.Because new fuel contains practically no fission products or radioactive
- gases, the re-sults for an accident, even if the fuel should be damaged, would be limited to an economic loss.
- 7. 1. 10 Summar of Radiolo ical Effects of Accidents The radiological effects of each of the accidents evaluated in Chapter 7 are shown in Table 7.1-2.
Also shown for the purpose of comparison, is the average normal background and man made radiation exposures.
When compared to background and manmade exposure it is clear that the exposure received by the popula-tion as a result of postulated accident is extremely small.
7.1.11 Probabilit Assessment In Reference 11, the Commission requires that "in the consid-eration of the environmental risks due to postulated accidents, the probabilities of their occurrence must
. be taken into account."
Consideration of the yearly probabilities of abnormal conditions is necessary to an assessment of environmental risk for the obvious reason that such conditions are not expected to occur 7.1-11
WNP-2 ER as often as once a year or even once in a plant lifetime.
Com-parison of accident exposures with the man-rems per year fully expected from natural sources and normal operation of the plant operation of the plant requires that the former be weighted by their annual frequencies in order to predict an average an-nual effect. It will be noted, however, that the forgoing analyses have concentrated principally on prediction of expo-sures iven the occurrence of the accident and have factored in the probability of the event in the overall dose affect.
The reason for this treatment is two-fold.
- 1. It emphasizes the fact that radiological exposures due to the accidents are in fact exceedingly low in themselves, without additionally complicating the issue with probabilities; 2.
The "classes" of accidents tend to be less homogeneous in their probabilities than in their releases;
- thus, to propose a two-significant figure probability as "typical" of a class would be not only inaccurate but misleading as well.
7.1.11.1 Probabilit Cate pries To alleviate the problem of inhomogeneity mentioned
- above, the probability of occurrence of each "class" of accidents and in-cidents has been placed in a broad probability category about two decades wide.
The system chosen for this categorization is derived from Section III of the ASME Boiler and Pressure Vessel Code.
These classes are used by the General Electric Company in design safety analyses and have appeared in safety analysis reports for several stations.
A brief semi-quantita-tive description of each class is given below.
7.1.11.1.1 Normal Condition (P = 1)
A normal condition is any planned and scheduled event that is the result of deliberate plant operation according to pre-scribed procedures.
7.1.11.1.2 U set Condition (1
P >2.5x10
)
An upset condition is a deviation from normal conditions that has a moderate probability of occurring during a 40 year plant lifetime.
These conditions typically do not preclude subsequent plant operation.
7.1.11.1.3 Emer enc Condition (2.5x10 P
> 2.5x10
)
An emergency condition is a deviation from normal plant operation that has a low probability of occurring during a 40-year plant lifetime.
Emergency condition events are typified by transients 7.1-12
WNP-2 ER CHAPTER 8
ECONOMIC AND SOCIAL EFFECTS OF PLANT CONSTRUCTION AND OPERATION 8.1 BENEFITS 8.1.1 Primar Benefits The primary benefits of WNP-2 are those inherent in the value of the generated electricity which will be delivered by Bonneville Power Administration (BPA) to 27 municipalities, 22 public utility districts, and 45 electric cooperatives, collectively called the Participants, located principally in Washington,
- Montana, and California and each of whom is a statutory preference customer of BPA.
The Participants'hares of the WNP-2 output range from approxi-mately 15 percent to 0.005 percent.
An aggregate of approx-imately 22.5 percent of the output is shared by 64 of the Participants each of whom has a share of less than 1 percent.
8.1.1.1 Electric Ener In its first full year of commercial operation (1980-81),*
the project is scheduled to supply 798 MW (average) of energy (7.0 billion kW-hr).
The following year, and each year thereafter, it is scheduled to supply 825 MW (average)
(7.2 billion kW-hrs.), according to the projections in the West Group Forecast.
As part of Phase I of the Hydro Ther-mal Power Program, the plant is expected to supply base load energy to the Pacific Northwest while peaking requirements will be met increasingly by hydro facilities.
The demand for electric energy from the Project is expected to be similar to that experienced in the West Group Area in 1970.
The estimated contribution of each class of consumer to the West Group Area coincidental electric power peak and the share of electric energy consumed by each, based on available data for 1970, is as follows:<1)
Residential Commercial Industrial Other TOTAL Peak 50.0%
21.3%
28.0%
0.7%
100.0%
1970 Enerqe
- 31. 4%
13.4%
50.2%
5.0%
100.0%
- The West Group Forecast uses a water year calendar which runs from July 1 to the following June 30.
- 8. 1-1
WNP-2 ER For 1990 the contribution of each class of consumer to the West Group Area coincidental peak and the percentage of energy consumed are estimated as follows:~~~
Residential Commercial Industrial Other TOTAL Peak 50.0%
24.0%
25.0%
- l. 0%
100.0%
1990 Enerqe 30.9%
15.3%
48.1%
5.7%
100.0%
Actual and estimated electric power requirements in the West Group Area are shown on Table 8.1-1.
A lower annual average growth rate is expected for the period from 1973 to 1990 than was experienced in the period from 1950 to 1973.
This change is the result of consumer and producer efforts to conserve
- energy, higher nonpromotional electric rates, more efficient electrical appliances, electrical appliance satur-
- ation, and a leveling off of population.
8.1.1.2 Benefits of Avertin Electrical Shorta es The probability of electrical shortage with and without the Project on schedule is discussed in Section 1.1.3.2 in regards to effects on capacity reserves and the magnitude of a deficit to meet firm energy requirements.
In the West Group Forecast of Power Loads and Resources, July 1976 June
- 1987, dated March 1, 1976, the expected date of commer-cial operation for WNP-2 is July 1979.
Based on that date, the forecast states the probability of meeting total energy load in all periods of July 1979 June 1980 with the Project on schedule is 82.2 percent and of meeting firm energy load is 89.8 percent.
With all projects, including WNP-2, on schedule the probability of meeting total energy load in all periods of 1976 to 1987 decreases steadily from 97.0 percent in 1976 to 21.1 percent in 1987.
With all projects, includ-ing WNP-2, on schedule the probability of meeting total firm energy load in all periods of 1976 to 1987 decreases from 100.0 percent to 1976 to 44.8 percent in 1987.
Since the West Group Forecast, schedule slippages have occurred which will reduce the probabilities of meeting these load require-ments.
Recalculated probabilities are expected to be presented in the Spring 1977 West Group Forecast.
Long term shortages of electricity would result in severe social and economic impacts since two-thirds of all electric energy is used in commerce and industry in the Pacific Northwest.
An inadequate energy supply for industry means reduced capital investment, fewer jobs, decreased
- payrolls, 8.1-2
WNP-2 ER less production, and lower living standards.
Unemployment would increase demands on governments for welfare and unem-ployment assistance at the same time that the tax bases financing governments would be declining, and tend to increase social and sociopolitical stresses.
I The Northwest Power Pool has drafted an emergency plan for curtailing loads in the event of long term power shortages.
This plan is discussed in Section 1.3.1.
The voluntary level one curtailment portion of the plan was utilized in the winters of 1972 1973 and 1973 1974 when low flow and adverse hydro conditions were experienced; firm power require-ments were met but some interruptible power utilized by industrial customers was curtailed.
The costs of these cutbacks are not known but are clearly substantial.
As the probability for meeting total and firm energy loads in all periods of 1976 to 1987 decreases, the need for proj-
- ects, such as WNP-2, being available as scheduled becomes greater with the hope that, if a deficit occurs, only the voluntary portions of the emergency plan will need to be utilized.
8.1.1.3 Beneficial Uses of B -Product Heat The U.
S.
Energy Research and Development Administration (ERDA) and the Supply System are cooperating with an agri-cultural research team to utilize hot water from WNP-2 in a program of crop environmental studies, agricultural engin-eering studies, and possibly aquaculture studies.
The Board of Directors of the Hanford Warm Water Utilization Labora-tory, which will conduct the program expected to begin in 1976 and last ten years, consists of members from the Washington State University, the University of Idaho, the Oregon State University, the State of Washington, the State of Idaho, the State of Oregon, ERDA and the Supply System.
WNP-2 will be the hot water source for the experimental program.
During the operation of WNP-2, 4,000 GPM of water taken from the hot water leg between the plant and the cooling towers will be available to the warm water agricul-tural project.
Cold water will be utilized when warm water is not available.
ERDA has leased approximately 900 acres of land adjacent to WNP-2 to the Warm Water Utilization Laboratory of which at least 400 acres will be used in the study.
Benefits of the studies will be experimentation and research in using warm water to irrigate crops and trees and the cost-effective demonstration of use of warm water for increased
- 8. 1-3
WNP-2 ER production.
No monetary benefits to any of the parties are anticipated.
8.1.2 Other Social and Economic Benefits 8.1.2.1 Pa rolls and Em lo ment Construction began in mid-1973 and is expected to extend through 1979, with a total construction payroll outlay of about.
$ 105 million, an average of approximately
$1.6 million per month over the entire period.
In 1977, the anticipated year of peak employment of approximately 1650 construction
- workers, the average payroll outlay will be about
$ 3.3 million per month.
These payroll outpays represent an addition to the regional income as the labor force is pri-marily 'drawn from the Pacific Northwest and resides in the Tri-City area.
During the 40 year operation period beginning in 1980, 102 permanent operation staff will be employed plus an addi-tional WPPSS support staff of approximately 25 workers.
The annual payroll outlay for these employees is estimated to be
$ 3.1 million, based on an annualized 1979 manworth of
$24,150.
8.1.2.2 Tax Revenues During the construction of the Project a total of
$ 21 million in sales taxes will be paid to state and local government.
Since the Project is entirely owned by WPPSS, a joint oper-ating agency and public utility, no real estate taxes will be levied.
During the operation period, the Supply System is required by law to pay a "privilege tax" as imposed by RCW 54.28.020 which consists of "five percent of the first four mills per kilowatt of revenue obtained from the sale of self-generated energy for sale."
The privilege tax revenues, amounting to approximately
$ 1.4 million annually for a 75 percent plant factor, will accrue to Benton County.
Legislation has been introduced in the Washington State legislature which would allocate the privilege tax to municipalities as well as to Benton and Franklin Counties.
In addition to this privilege tax, the Supply System is making payments during the construction period to local school districts experiencing increased enrollment as a
result of the Project.
These payments are prescribed by RCW 54.36 and will amount to approximately
$ 300 per Project pupil per year.
- 8. 1-4
WNP-2 ER 8.1.2.3 Public Facilities A visitor center which will be opened prior to commercial operation of WNP-2 is planned by the Supply System.
The visitor center, which will serve WNP-1 and WNP-4 as well as WNP-2, will either be located in North Richland adjacent to the WPPSS administrative office or in the City of Richland.
Because of a continuing effort on the part of nuclear firms in the Tri-City area, including WPPSS and ERDA, to establish a joint visitor center, the location and design for the public facility has not been finalized at this time.
8.1-5
WNP-2 ER TABLE 8.1-1 ELECTRIC POWER REQUIREMENTS BY MAJOR CONSUMER CATEGORIES IN THE PACIFIC NORTHWEST (West Group Area) 1950 Actual 1960 1970 Estimated 1973 1975 1980
.1990 1995 Population (000) 1 No. Domestic Consumers (000)
No. Commercial Consumers (000) kWh Per Consumer 4, 675 1,073 140 5,490 6,435 1,407 1,986 177 242 6,657 2,195 261 6,878 7,201 8,476 2g205 2g451 3g089 271 314 402 8,940 3, 555 455 Domestic Commercial Energy Sales (billions kWh) 5,112 9;841 13,831 14,809 14,970 18,800 22,600 24,600 16g799 29g143 50g035 56g825 57g100 70~700 88J300 97g100 Domestic Commercial Industrial Irrigation Other Total Losses 5.5 2.4 ll.1
.1
.6
- 19. 7 3.1 13.8 5.2 22.3 1.0
.8
- 43. 1 4.7 27.5 12.1 44.1 2.6 1.4 87.7 9.6 32.5 14.8 45.7 3.3 2.5 98.8 9.9 33.0 15.5 47.7 3.8 2.6 102. 6 10.1 46.2 22.2 67.7 6.1 2.7 144. 9 14.3 69.9 35.5 102.0 9.1 4.9 221.4 21.9 87.4
- 44. 2 129.6 9.8 6.0 277. 0
- 27. 4 Total Requirements Ten Year Annual Growth Rates
- 22. 8 47.8
- 7. 75
- 7. 5%
- 5. 0%
4.3%
97.3 108.7 112.7 159.2 243.3 304.4 States of Washington,
1976
WNP-2 ER 8.2 COSTS The costs associated with the construction and operation of an electric generating facility can be either internal or external.
Internal costs are those capital costs associated with the construction, operation, and maintenance of the project.
External costs are those environmental and social and economic impacts that occur as a consequence of construc-tion and operation of the project.
8.2.1 Internal Costs 8.2.1.1 Primar Internal Costs The following are the primary internal costs associated with the construction and operation of WNP-2:
(a)
The capital cost of leasing the Project site from ERDA is
$ 36,000.
The capital cost of site improvements including temporary roads, railroads, well water sys-tem, fire protection system, and sanitary sewer and disposal system is
$ 2,139,000.
(b)
The total capital costs of WNP-2 construction is
$ 794 million.(1)
(c)
The cost to WPPSS for transmission and distribution facilities is budgeted to be
$ 7,272,200 as the total station equipment cost including escalation.
The BPA and WPPSS are expected to enter into a trust agreement whereby the BPA will budget
$ 5,526,000 for WNP-2 inte-gration into the BPA grid (cost for the 18 miles of 500 kv line between Ashe Substation and existing Hanford transmission line) and
$ 95,300 for a 230 kv terminal in the Ashe Substation.
(d)
The levelized 15 year cost for fuel, including costs of spent fuel disposition, is 4.5 mills/kWh for WNP-2 with a
75 percent plant factor.(
(e)
The annual costs for the Project, excluding fuel costs and debt. service, is expected to be
$ 10,041,000.
This includes licensing fees and taxes.
(f)
The costs for decommissioning of a nuclear plant such as WNP-2 in 1979 dollars are estimated to be approxi-mately
$ 34.5 million for dismantling or
$ 7.6 million for concrete entombment.
(g)
Since WPPSS is precluded from research and development activities by its charter as a public agency, no re-search'nd development costs are anticipated with WNP-2.
8.2-1
~
~
WNP-2 ER The direct and indirect cost components of WNP-2 construc-tion are presented in Table 8.2-1 and additional information requested by the NRC on such items as interest during con-struction, site labor force size and pay rate, and escala-tion rates are presented in Table 8.2-2.
8.2.1.2 Estimated Cost of Generatin Electricit The estimated net annual cost per kilowatt hour of electri-city generated from the Project (at a
75 percent, capacity factor) is 14.8 mills.
Table 8.2-3 shows the estimated cost of generating electricity from WNP-2.
For estimates of the cost of generating electricity from coal fired plants, consult the Construction Permit Environmental Report for WNP-2.
t 8.2.2 External Costs 8.2.2.1 Tem orar External Costs The temporary external costs associated with WNP-2 are a
consequence of site preparation and project construction activities scheduled to occur between May 1973 and December 1979.
This topic is usually considered more appropriate for the ER at the CP stage, but since more data have been developed since the previous ER was submitted, the new data will be summarized here.
A significant increase in local population is expected to occur during the construction of the Project and is pro-jected to stabilize at a lower rate of increase in the 1980's.
This population increase is associated with a variety of economic activities of which WNP-2 is a part, which are developing in the Tri-City area.
An effort is made below to describe the total population increase ex-pected and the portion which can be associated with WNP-2.
Table 8.2-4 shows historical and estimated population data for the Tri-City area including Benton and Franklin Counties for the period from 1940 to 1974.
Table 8.2-5 shows the pro-jected short-term total population growth anticipated in the Tri-City area from 1974 to 1982; the projection was made by Woodward-Clyde Consultants in a study prepared for WPPSS entitled:
Socioeconomic Stud WPPSS Nuclear Pro ects Nos.
1 and 4 and dated Aprz.l 1975.
The Woodward-Clyde projection is based on a consideration of projects scheduled for the remainder of this decade, including the Fast Flux Test Facility (FFTF), WNP-2, WNP-1/4, and growth in the industrial and agricultural sectors of the local economy.
Total population is projected to increase rapidly during the 8.2-2
period 1974 to 1978 from 108,000 to 130,500.
A small de-crease is projected around 1980 with total population pass-ing the 130,000 mark again around 1982.
Consequently the short-term population growth is expected to be permanent.
The occurrence of the rapid increase in population projected by Woodward-Clyde Consultants is substantiated by the num-bers of new residential telephone hookups experienced by General Telephone in 1974,
- 1975, and 1976 and the expansion of the residential housing market. in the Tri-City area.
The residential population increase is scattered among the Tri-Cities and outlying communities.
The association of WNP-2 to the total residential population increase can be estimated from the results of a survey of WNP-2 workers in February 1975 performed as part of the socioeconomic study by Woodward-Clyde Consultants.
It was found that.
65 percent of the workers surveyed (about 70 percent of 550 workers) lived in the Tri-City area before construction on WNP-2 began and that about p0 percent of the workers surveyed lived in the Tri-Cities.'
At the time of the survey in February 1975, approximately 1200 construction workers were employed on the FFTF. Project.
In making projections of total population growth in the Tri-City area, Woodward-Clyde Consultants assumed that 40 percent of the peak construction work force on WNP-2 in 1977 or 660 workers would be new residents.
It is significant that the demand for workers on WNP-1 and WNP-4 will be increasing from 1975 to 1978 at about 3300 workers as the WNP-2 and FFTF Projects are completed.
Since the mix and magnitude of building trades workers is similar on these, projects, the new resident workers on FFTF and WNP-2 are expected to remain in the Tri-City area to work on WNP-1 and 4.
As construction activities on WNP-1/4 peak and are completed between 1978 and 1982, population growth in the Tri-City area is expected to decline;
- however, the expansion occuring in other local industries and irrigation agriculture is expected by 1982 to take up the slack in population growth caused by a decline in construction indus-try employment.
It is likely that other construction proj-ects related to energy research and development will occur in the Tri-City area during the 1980 1989 decade.
The increase in population from 1974 to 1978 is anticipated to have certain adverse effects related to the increased burden of new residents on community services and facilities.
Although conceived as adverse effects in the short-term, the act of increasing community services and facility capacities during the late 1970's will be a benefit in the 1980's as
- 8. 2-3
WNP-2 ER the area population stabilizes at a higher permanent level.
The anticipated effects of short-term population growth on community services and facilities 'is summarized in Table 8.2-6.
The housing requirement noted in Table 8.2-6 is being met by the number of new homes and apartments which have been and are being constructed.
The local residential housing market sector seems capable of responding to the short-term need wlpch is anticipated.
The effects of population growth on school enrollments is a major problem in the Tri-City area which is being met by considering split-shifts and year round school programs as well as the construction of new facilities.
The Supply System has negotiated an agreement with school districts affected by WNP-1 and 4 to make financial assist-ance payments for construction of new facilities.
Also included in the agreement is a procedure for compensating for enrollment increases caused by WNP-2 and WNP-1/4.
The conditions of the agreement are consistent with WPPSS authority as a public agency and are detailed to ensure a
fair and equitable distribution of funds when and where need exists.
Local hospitals are not expected to be impacted by the anti-cipated short-term population increase.
- However, need for increased fire and police protection is anticipated.
Table 8.2-6 shows that the City of Richland is expected to have a water capacity problem related to peak use in the short-term.
The Cities of Richland and Kennewick are ex-
.pected to overload their sewage treatment capacities dur'ng peak use period by 1978.
Measures to restrict peak use of these facilities, such as restricting lawn irrigation, could diminish the impact on capacities;
- however, the expected permanent population increase expected in the early 1980's makes the addition of new permanent facilities now an economically safe and socially desirable measure.
Traffic congestion associated with workers traveling to the Hanford Reservation through the City of Richland is a problem on George Washington Way and the By-Pass Highway during peak periods during the morning and afternoon.
Woodward-Clyde estimated that the combined average daily traffic of George Washington Way and the By-Pass Highway was 22,000 vehicle trips in April 1975 and that approximately 2360 vehicle trips were attributable to combined construc-tion employment on FFTF and WNP-2.
Total average daily 8.2-4
WNP-2 ER traffic is projected to 24,400 in December of 1976 and 23,890 in July of 1978 as construction schedules fluctuate and construction employment declines.
The City of Richland is considering cost-effective methods to improve the move-ment of through traffic.
A 1974 study by Stevens,
- Thompson, and Runyon, Inc., Traffic 0 erations Pro ram to Increase Ca acit and Safet (TOPICS), Cit of Richland, Washin ton, recommended among other options the installation of a signal system interconnect and a master control to synchronize signals on George Washington Way at a cost of
$ 450,000.
L Since the WNP-2 site is located on the ERDA Hanford Reser-vation twelve miles north of the City of Richland and two miles west of the Columbia River, noise and temporary aesthetic disturbances on residential populations is ex-pected to be negligible.
In addition, the acquisition of land for WNP-2 did not cause any affect on local residents because the land is leased from ERDA and has not had resi-dents since 1943 when it was acquired by the Manhatten Project of the Army Corps of Engineers.
8.2.2.2 Lon -Term External Costs Long-term external costs are those associated with the oper-ation of WNP-2 beginning in 1980 for approximately 40 years.
The operation of the Project will not impair recreational values; deteriorate aesthetic values; or degrade or restrict access to areas of scenic, historical, or cultural interest.
The Project j.s located 12 miles north of the City of Richland on the ERDA Hanford Reservation
- and, as such, is not antici-pated to create locally adverse meteorological conditions or noise.
The increased costs to local governments for services required by the permanently employed plant workers and their families are expected to be compensated for by local taxes paid by individual workers who become permanent residents and by the generation tax paid by the Project.
There is no known economic incentive for heavy industry to be attracted to the WNP-2 site area.
There are no electric rate incentives or deterents to influence the growth of residential or commercial customers in the WNP-2 site area.
Therefore, no long-term external costs are anticipated with respect to further industrial development in the area.
8.2-5
WNP-2 ER TABLE 8.2-1 COST COMPONENTS OF WNP-2 Direct Costs a
~b.
c ~
d.
e.f.
go h ~
lo Land and land rights Structures and site facilities Reactor (boiler) plant equipment Turbine plant equipment Heat rejection system (cooling towers)
Electric plant equipment Miscellaneous plant equipment Spare parts allowance Contingency allowance Subtotal 36,000 90,290,000 99,178,400 100
~ 821 g 700 7,306,000 30,301,100 32,712,900 2,500,000 28,661,000
$ 391,807,200 Indirect Costs b.
cd.
Construction facilities, equipment and service Engineering and construction manage-ment services Other costs Interest during construction (9 7.05%/year*)
Escalation during construction (9 9.5%/year*)
Total Plant Cost, at start of commercial operation 4,410,100 70,963,200 141 g 351 g 400 1 18 / 802 g 1 00 66,666,000
$ 794,000,000
- Average
WNP-2 ER TABLE 8.2-2 INFORMATION REQUESTED BY NRC WNP-2 1 ~
2.
3.
Interest during construction Length of constructin work week Estimated site labor requirement Total manhours of construction effort 7.05%/year (average) 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 7.73 manhours/KWe 8.5 million manhours 4.
5.
6.
Average site labor pay rate (including fringe benefits) effective at month and year of NSSS order Composite escalation rates for 1975 Composite escalation rates for 1976 Composite escalation rates for 1977 Composite escalation rates for 1978 Total plant cost at start of commercial operation
$12.00/hour*
12%/year 10%/year 8%/year 8%/year
$ 794,000,000
- NSSS was ordered in April 1971 before site construction began.
The
$ 12.00/hour represents average site labor pay rate for March 1976, the delivery date for NSSS.
WNP-2 ER TABLE 8.2-3 ESTIMATED COST OF ELECTRICITY FROM WNP-2 Fixed Costs Annual Cost mills/kilowatt hour Estimated Debt Service Insurance Property Liability Operation and Maintenance (fixed)
Administration and General Subtotal Less:
Surplus of Prior Year' Payment to Reserve and Contingency Fund Total Fixed Cost Variable Costs (2)
Nuclear Fuel Cycle (3) 64,363,000 1,300,000 295,000 8,169,000 2,678,000 76,805,000 4,167,000 S 72,638,000 8.939
. 181
. 041 1.134
.-373 10.668
.579 10.089 Cost of 0 0 (yellow cake)
Cost of ski ping Cost of conversion and enrichment Cost of conversion and fabrication Cost of reprocessing Carrying charge on fuel inventory Cost of waste disposal Credit for plutonium, U-233 or U-235 Total cost for fuel Taxes Spare Parts Usage and Replacement 32,191,000 1,446,000 320,000
.800
.219 1.336
.644 1.000
.076
.909
.513 4.471
.201
.044 Total Variable Cost Net Annual Cost 33,957,000
$ 106,595,000
- 4. 716 14.805 (1) Includes cost of money, interest, and amortization.
All variable costs are calculated at 75 percent plant (2) factor.
Mills/kWh derived from data developed for the 1976 Fuel levelxzed over a 15 year period and is escalated.
WNP-2 ER TABLE 8.2-4 POPULATION DATA FOR THE TRI-CITY AREA 1940 1950 1960 1970 1971*
1972*
1973*
1974*
Benton County 12,053 51,370 62,070 67,540 67,700 67,800 68,200 69,800 Franklin County 6,307 13,563 23,342'5,816 26,000 26;000 26,000 26,200 Totals 18,360 64,933 85,412 93,356 93,700 93,800 94,200 96,000 Kennewick Pasco Richland West Richland 1 g 918 10 106 14 244 15 212 15 400 15 ~ 580 16 ~200 16,800 3 g 913 10 '28 14 g 522 13 ~920 13 g 920 14 g 000 14 g 050 14 g 100 247 21 J 809 23 g 548 26
~ 290 26 g 300 26 f 350 26 f 600 28 F000 1,347 1,107 1,143 1,159 1,225 1,247 Tri-City Totals 6,078 42,143 53,661 56,529 56,763 57,089 58,075 60,147
- Estimates from Tri-City Chamber of Commerce and the Washington State Office of Program Planning and Fiscal Management.
Source:
Socioeconomic Stud WPPSS Nuclear Projects Nos.
1 and 4, by Wocdward-Clyde Consultants, Aprz.l 1975, Tables 4.3-1 and 4.3-2.
WNP-2 ER TABLE 8.2-5 PROJECTED SHORT-TERM POPULATION GROWTH IN TRI-CITY AREA 1974 1975 1976 1977 1978 1979 1980
'981 1982 Yearly Change
+ 5000
+ 6500
+ 4500
+ 6500 1000 1500
+
500
+ 1500 Population 108,000 113,000 119,500 124,000 130,500 129,500 128,000 128,500 130,000 1974 base population estimated from total population of Benton and Franklin Counties and population of Burbank, Sunnyside, Grandview, and Mabton (State of Washington, 1974.
Official Population of Cities,
- Towns, and Counties of the State of Washington as of April 1, 1974, Olympia:
Office of Program Planning and Fiscal Management).
After 1978 changes will depend upon new major construction.
Source:
Socioeconomic Study:
WPPSS Nuclear Pro'ects Nos.
1 and 4, April 1975.
TABLE 8.2-6 IMPACT OF
SUMMARY
ESTIMATE:
EFFECTS'F TOTAL REGIONAL GROWTH Richland Kennewick Pasco Population Increases Housing Required School Enrollment Increases Present to 1978 1978 Present to 1978 1978 Present to 1978 1978 3,500 3,500 l., 000 7/885 3J000 10g885 7g950 3g250 llg200 4/828 900 5g700 28 F 000 7g 900 35'00 18 F000 7 g900 25 ~900 16 F800 2g 250 19'50 Water Requirements (MGD)
Plant Capacity Average Use Peak Use.
36 16
- 4. 5 20.5 35.5 10 45.5
- 13. 5 6
19.5 6
2 6
8.6, 13 5.7 18.7 20 5
15
.7 2
20 5.7 17 Sewage Disposal (MGD)
Plant Capacity Average Use Peak Use 6
3.4 1
5 1.4 4.4 6.4 8
4.5 2
6.5 6.5 3
9.5 81.2
.2 6
.8 1.4 6.8 Policemen Firemen Hospital Beds Available Needed 32 10 37 10 42 47 (Kadlec Hospital) 135 0
135 28 13 41 26 12 38 (Kennewick General) 60 0
60 29 5
34 26 4
30 (Our Lady of Lourdes) 81 0
81 Source:
Adapted from table in Summar of Socioeconomic Impacts of WPPSS Nuclear Pro'ects Nos.
1 and 4 on the Trz.-Catty Region, Woodward-Clyde Consultants, May 1975.
pKp-2 ER CHAPTER ll
SUMMARY
BENEFIT COST ANALYSIS ll.1 INTRODUCTION In the Environmental Report at the construction
- permit, stage, and in earlier sections of this Environmental Report, data have been presented on the need for the facility, environmental and monetary costs and benefits of the faci-lity, and on various project and facility alternatives.
The purpose of this section is to summarize and weigh the over-all benefits and costs of operating the completed plant.
This final balancing must of necessity be qualitative, since it is not possible to quantify all of the costs and benefits in uniform units of measure.
WNP-2 ER ll.2 NEED FOR POWER The need for the electrical energy to be furnished by WNP-2 has been described in Chapter 1.
The project is an essen-tial component of the hydrothermal program in the Pacific Northwest and will be depended upon to help fulfillthe future power requirements projected in the West Group Fore-cast of Power Loads and Resources.
Based upon the West Group Forecast, which assumed a July 1979 commercial opera-tion date, the probability of meeting firm energy loads in 1980-1981* is 0.884.
Conversely, the probability of not meeting these loads is 0.116, and is considered a high socioeconomic risk that would be considered unacceptable to the majority of citizens.
Since the West Group Forecast (March 1976) the WNP-2 commercial operation date has been rescheduled for June
- 1980, and project progress has continued at a reduced rate due to an extended labor strike.
These delays are further increasing the probability of not meeting future firm energy loads.
- July 1, 1980 to June 30, 1981 11.2-1
WNP-2 ER 11.3 Alternatives Numerous alternatives were considered in the Environmental Report for a construction permit.
During plant construction, certain plant alternatives were incorporated into the plant design in an attempt to continuously optimize the benefit-cost balance of the project.
Among these later changes were the selection of the cooling tower configuration and make-up water intake system design.
At this stage of the project, any further major changes can not be expected to show a desirable benefit-cost ratio.
Since enviromental factors, have been considered since early design stages and have continued to receive consideration during the construction
- phase, the Supply System is confi-dent that the project can be operated as presently designed and constructed with no significant or lasting harm to the environment.
11.3-1
WNP-2 ER 11.4 BENEF1T-COST BALANCE 11.4.1 Benefits The major benefits of operating WNP-2 are listed in Table 11.4-1.
These various benefits have all been discussed in detail in the text of earlier chapters and are only summa-rized here.
11.4.2 Costs The capital construction cost of WNP-2 is expected to be
~ $ 794 million.
Annual operating costs are estimated to be about
$ 74.4 million or 14.9 mills/kwhr at 65 percent plant factor.
The environmental costs of operating WNP-2 are summarized in Table 11.4-2.
11.4.3 Summar Benefit-Cost Anal sis After considering the various monetary, social, and environ-mental costs of operating WNP-2 and the corresponding benefits to be derived from its operation, the Supply System concludes that operation of WNP-2 represents a positive value to the immediate area where it is located and to the Pacific Northwest.
Every effort has been made during design and construction of the facility to minimize environmental,
- social, and monetary costs of the project so that the plant is currently optimized from a benefit-cost standpoint.
I 11.4-1
WNP-2 ER TABLE ll.4-1
SUMMARY
BENEFITS OF OPERATING WNP-2*
2.
Item Expected Average Generation Proportional Distribution of Electrical Energy (1990)
Benefit 7.2 billion kwhr/yr 30.9% Residential 15.3% Commercial 48.1% Industrial 5.7% Other 100.0% Total 3.
Direct Taxes 4.
Use of By-Product Heat 5.
Direct Employment 6.
Public Facilities
$1.4 million/year to Benton County 4,000 GPM warm irri-'ation water for agricultural research 102 operation staff 25 support staff 127 total employment A permanent visitor center will be sponsored.
- Refer to Section 8.1.1 for details
WNP-2.
ER TABLE 11.4-2
SUMMARY
ENVIRONMENTAL COSTS OF OPERATING WNP-2 (Sheet 1 of 4)
Effect Reference Section Si nificance Land Approximately 30 acres of shrub-steppe land diverted to industrial use at the plant site.
2.1 Negligible represents a very small percentage of the available acreage of similar type (see Fig. 2.2-1).
Approximately 648 acres of right-of-way will be required for transmission.
3.9 Negligible represents a very small percentage of the available acreage of similar type (see Fig. 10.9-4).
Surface Water Consumptive use of water will be about 13,000 gpm.
Thermal load from blowdown of WNP-2 plus WNP-1/4 is 75, 000 Btu/sec.
5.1.2 5.1.4 5.1.2 Negligible represents only.05% of average steam flow.
A Negligible raises bulk river tem-perature only 0.033 F.
0 Thermal increases within a limited mixing zone.
5.1.2 Slight thermal increases will vary according to a sliding scale permit-"
ting increases at the mixing zone boundary of a few degrees at cooler river temperatures and a maximum of 0.5 F contributing to a rjver tem-perature not exceeding 68 F.
WNP-2 ER REFERENCES FOR CHAPTER 1 Section 1.1 1.
Pacific Northwest Utilities Conference Committee Sub-committee on Loads and Resources,'est Grou
- Forecast, March 1, 1976 (prepared annually).
2.
Pacific Northwest Utilities Conference Committee Sub-committee on Loads and Resources, Lon Ran e Pro'ection of Power Loads and Resources for T ermal,P annwfn 1995-96, to be pubis.shed.
prepared annually 3.
Bonneville Power Administration, Load Estimatin
- Manual, July 1965.
4 ~
Speech by Mr.'ernard Goldhammer at the Bonneville Power Administration Preference Customer Meeting held in Seattle, Washington, December 14, 1972.
5.
6.
Bonneville Power Administration, Final Environmental Statement Wholesale Power Rate Increase, August 15, 1974.
Western Systems Coordinating Council, Reliabilit Criteria, Part' Reliabilit Criteria for S stem Des',
July 16, 1971.
7.
Western Systems Coordinating Council, Reliabilit Criteria, Part II Minimum 0 eratin Reliabilit Criteria, June 19, 1970.
WNP-2 ER REFERENCES FOR CHAPTER 2
Section 2.1 Atom'ic Energy Commission, Richland Operations Office, Letter, Appendix 2.P to Managing Director of the Washington Public Power Supply System,
- Richland, WA, November '25, 1970.
Bonneville Power Administration, Po ulation, Em lo ent=
and Housin Units Pro'ected to 19
, Fe ruary 9
Pacific Northwest Bell, Po ulation and Household Trends in Washin ton, Ore on and Northern Idaho, 1970 to 1985, January 97 Population Studies Division, Office of Program Planning and Fiscal Management, State of Washin ton, Po ulation
- Trends, 1975, Olympia, Washington, 1975.
Po ulation Estimates:
Ore on Counties and Incor orated Cities, Center or Popu ation Research an
- Census, Portland State University, Portland, OR, July 1, 1975.
- Clement, M., et al., Stud and Forecast of Tri-Cit Economical Activit an its Re ate Im act on Gasp ine Needs and Housin
, Battelle, Pacific Northwest Labora-tories to Tri-City Nuclear Industrial Council, Richland, WA, May'974.
Columbia-North Pacific Re ion Com rehensive Framework Stud of Water and Related
- Lands, A
endix VI, Economic Base an Pro ections, Paci ic Nort west River Basins Commission, Vancouver, WA, January 1971.
Woodward-Clyde Consultants, Socioeconomic Stud WPPSS Nuclear Pro'ects 1 and 4, Prepare or Was ington Pu ic Power Supply System, Richland, Washington, April 1975.
- Cone, B. W., The Economic Im act of the Second Bacon S3. hon and Tunne on t e East Hi Area, t e State of Washin ton and the Nation, Columbia Basin Development
- League, P.O.
Box 9 0, Ephrata, Washington, 1970.
Xan'don, K. E., Assum tions for Po ulation Estimates and Pro'ections b
S ecific Com ass Sectors and Radii Distances rom WNP-Site, Battelle, Paci ic Northwest Laboratories to Burns and Roe for the Washington Public Power Supply System,
- Richland, WA, in preparation.
Tri-City Herald, "The New Frontier", Kennewick, WA, p.
6, March 7, 1976.
WNP-2 ER
'EFERENCES'OR CHAPTER 2
Continued Section 2.2 21.
- Mains, E.
M. and J.
M. Smith, "The Distribution, Size Time and Current Preferences of Seaward Migrating Chinook Salmon in the Columbia and Snake Rivers,"
'i'sh'erie's'e'se'a'r'ch'a
'e'rs, vol. 2, no.
3, pp. 5-42, 1964.
22.
- Becker, C.
D. and C.
C. Coutant, Tem erature, Tim'in
'an'd'eaward Mi'ation'f Juvenile Ch'inookSalmo'n'r'om
then'tra Co'1'umbi'a'iver, BNWL-1472, Battelle, Pacific Northwest Laboratories,
- Richland, WA,, 1970.
1 23.
Washington Public Power Supply System, The Pro 'osed
'a'n'ford'umber Two'uclear Power Plant, Fina Environ-men'tal'ta'tement, Docket No. 50-397, December 1972.
24.
Environmental Protection Agency/AEC/ and National Marine Fisheries Service, Columbia'iver Thermal'ffe'cts
'tu'd
, vol. I Biolo ical Effect's Stu'dies, January 1971.
'anford'uInb'er Two Nuclear Power Plant, Fin'a'1'nviron-menta'1't:a'tern'ent, Docket No. 50-397, Subsection 2.3.6.1, p
8, 1972.
26.
- Watson, D. G., "Fall Chinook Salmon Population Census,"
Pa'cific'orthwest L'aborator Annual Re ort foi 19'72
't'o'he USAEC Divisi'on of Biomedica'1 an'd Env'i'ronmen'tal Resea'rch, vol. 1, part 2, p. 6.16-6.17, 1973.
27.
- Watson, D. G., Fall Chinook Salmon S awnin in'he Columbia River near Hanford 194'7-1969, Battelle, Pacific Nort west. La oratories, BNWL-1515, 1970.
28.
- Watson, D. G., Estimate of Steelhead Trout' awnin'n
" the Hanford Rea'ch of the Columbi'a River, Contract No.
DACW67-72-C-0100, Battelle, Paci ic Northwest Laboratories, 1973.
WNP-2 ER
'EFERENCES'OR'HA'PTER 2
Sects.on 2.3 1.
- Stone, W. A., et al.,'l'ima't'o ra h
'o'f::the Hanfo'r'd'ica, BNWL-1605, Battelle, Pacifxc Northwest Laboratories,
- Richland, WA, June 1972.
2.
- Jenne, D. E.,'reen'c Ah'a'1 s'iso'f Some'l'im'at'o'1'o i'cal
'xtr'emesa't'a'nford, HW-75445, General Electric, Hanford Atomic Pro ucts Operation,
- Richland, WA, April 1963.
WNP-2 ER REFERENCES FOR CHAPTER 4
Sects.on 4.1 Architect Engineers Estimate, April 15, 1976.
Phone call to D. Roe of BPA, May 1, 1976.
Woodward-Clyde Consultants. Socioeconomic Stud WPPSS Nuclear Pro'ects 1 and 4, April 1975.
Letter:
Robert J. Kuhta, Engineer Planner of Benton County to S. K. Billingsley of WPPSS, January 5,
1971.
Architect Engineers
- Estimate, August 31, 1976
WNP-2 ER l.
REFERENCES'OR CHAPTER 4
Section 4.2 Bonneville Power Administration 1975 Fiscal Year Pro os'ed Pro ram,'nvironme'ntal Stateme'n't,'acu' Evaluati:on A
e'ndix.
2.
Bonneville Power Administration, Environmental Statement:
Genera'1 Co'nst'ru'ct'ion'n'd Mai'n'tenan'ce Pro'am, August 97
WNP-2 ER REFERENCES FOR CHAPTER 5
(Continued Section 5.1 12.
Patrick, R.,
"Some Effects of Temperature on Freshwater Algae,." Biolo ical As ects of Thermal'oilu't'ion, P.
A. Kren e an F. A. Par er eds.),
Vander ilt Univ.
- Press, pp. 199-213, 1969.
13.
Applicant's Environmental Report, as
- amended, Section 2.3.6.1.
14.
- Becker, C. D., Food and Feedin of Juvenile Chinook Salmon 'in theentra'1plumb'ia River 'in'el'a't'ion'o Therma'1'i'sch'ars'n'd'ther Envi'ronmenta'1'eatures, BNWL-1528, Pacific Northwest Laboratories, Richlandg Washington, 1971.
15.
Curry, L. L., "A Survey of Environmental Requirements for the Midge (Diptera:
Tendipedidae),"
Biolo ical Problems in Water Pollution, C.
M. Tarzwell {ed.), P.
H. S. Publ.
No. 999-WP-25, 1965.
16.
- Nebeker, A. W. and A. E. Lemke, "Preliminary Studies on the Tolerance of Aquatic Insects to Heated Waters,"
J.
Kansas Ent. Soc., vol. 41, p.
- 413, 1968.
17.
- Becker, C. D.,
Re's onse oolumbi'a River Xn'vertebrates to Therma'1 Stress, BNWL-1550, Pacific Northwest, Labora-tories, Richland, Washington, vol. 1, no. 2, p. 2.17, 1971.
18.'outant, C. C., The Effects of Tem erature on the Develo-men't of Bot'tom Or 'anisms, BNWL-714, Pacific Northwest Laboratories,
- Richland, Washington, 1968.
19.
"Columbia River Thermal Effects Study," Vol. I:
Bio-lo ical Effects Studies, Environmental Protection Agency, pp. 102, January 1971.
20.
22.
- Pearson, W. D. and P.
R. Franklin, "Some Factors Affecting Drift Rates of Bactis and Simuliidae in a Large River,"
EcolocC, vol. 49, p.
75, 1968.
Testimony of D. R. Eldred, Dept. of Game, in hearing on Application TPPSEC 71-1 before State of Washington Thermal Power Plant Site Evaluation Council, Exhibit 62.
WNP-2 ER REFERENCES'OR CHAPTER 5
Continue Section 5.1 23.
- Salo, E.
O. and R. E. Nakatani, in hearings on Application TPPSEC 71-1 before State of Washington Thermal Power Plant Site Evaluation Council, Exhibit 26.
24.
- Olson, P. A.,'Effects 'o'f Therma'1 Increment's
'on'
's and Youn of Columba.a'ay'er
'Fa'1'1 Chin'oo, BNWL-538, Pacxfa.c Nort west La
- ratorxes, Rxc an
, Washington, 1971.
25.
Brett, J. R.,
"Temperature Tolerance of Young Pacific
- Salmon, Genus'n'corh nchus," J. Fi'sh.'es.'d'.'a'n'a'da, vol. 9, p. 265, 26.
- Nakatani, R. E., in hearings on Application TPPSEC 71-1 before State of Washington Thermal Power Plant Site Evaluation Council, Figure 13, Exhibit. 49.
27.
- Snyder, G.
R.
and T. H. Blahm, "Effects of Increased Temperature on Cold-, Water Organisms,"
'J.
Wa't'er Po'llut'i'on Control'ed., vol. 43, p.
- 890, 1971.
28.
- Bush, R. M., E.
B. Welch and B.
W. Mar, "Potential Effects of Thermal Discharges on Aquatic Systems,"'nyironme'n'tal
'Scien'ce an'd'echn'olo' vol. 8, p. 561, 1974.
29.
Schneider, M. J., Vulnerabilit of Juvenile Salmonids to Predation Following Thermal Schock,'BNWL-l150, Pacific Northwest Laboratories, Richland, Washington, vol. 1, part 2, 2.19, 1971.
30.
Templeton, W. L. "and C.
C. Coutant, "Studies on'he Biological Ef ects of Thermal Discharges from the Nuclear Reactors to the Columbia River at Hanford," IAEA-SM-146/33, Environmenta'1s
'ect's o'f Nucl'ear Power'tations, pp.
591-612, 1971.
31.
Effects of Circul'ar'eehan'ica'1 Dra'ftCo'ol'i'n'owersat Wash'zn t'on'ub'lac'ower Su 1
'S s't'em Nu'cl'ear'oWer Pl'ant Number Two, Battelle, Pacific Northwest Laboratories.
to Burns and Roe',.,for the Washington Public Power Supply
- System, Richland, WA, in preparation.
WNP-2 ER REFERENCES FOR CHAPTER 6
Section 6.1
- Becker, C. D. and W.
W. Waddel, A Summar of Environ-men'tal'ffec't's'tudies on the Columbia'iver, Battelle, Pac~
z.c Nort west La orators.es, Rzc
- and, WA, November 1972.
2.
U.S. Geological Survey, Water Resources Data for
'a'sh'int'on','P'art',
Surface Water Records, 1973.
3.
Hilty, E. L., Water Resources S stems Section, Battelle, Pacific Northwest Laboratories,
- Richland, WA, unpublished
- data, 1975.
4.
- Bramson, P.
E. and J.
P. Corley, Environmental Surveillance
'aanfordf'o'r CY-1972, BNWL-1727, Battelle, Pacxfzc Northwest Laboratories,
- Richland, WA, April 1973.
5.
Vertical Mixin Characteristics of the Columbia River
'a'tRiVe'r'i'1'e'51'.75',
WNP No. 2, Battelle-Pacific Nort west La oratories, Rxc
- and, WA, March 16, 1972.
6.-
- Page, T. L., E.
G. Wolf, R.
H. Gray and M. J. Schneider, Ecolo ical Com arison of the Hanford Generatin'l'a'nt
'an t e WNP-'at'es
'on' e'o'm x'a Raver, Batte e,
Pacz.fzc Northwest Laboratories to United Engineers and Constructors for the Washington Public Power Supply
- System, Richland, WA, October 1974.
7.
- Page, T. L., An Evaluation of Sedimentation and Turbidit Effe'cts Resultin'rom Excavation in t e Co umb'za'aver at t e WNP-
- Sate, Au ust to Octo er 7
, Batte e,
Pacific Northwest Laboratories to Burns and Roe for the Washington Public Power Supply System,.Richland, WA, in preparation.
/J 8.
- Trent, D. S., Mathematical Definition of the WNP-1 and
'-4'oo'1'in ToWer 3 oW oWn P ume, Batte e,
Pace.
xc North-west, Laboratories to Un>.ted Engineers and Constructors for the Washington Public Power Supply System,
- Richland, WA, in preparation.
9.
- Jaske, R. T., An Anal sis of the Ph sical Factors Gove~n'i'n'h'e
'Si'z'ean'd'em erature Gradien'ts o'fthe Han or:'E::'uen't P um'es, BNWL-CC-
, Batte e, Pacific Northwest Laboratories,
- Richland, WA, November 1972.
WNP-2 ER REFERENCES FOR CHAPTER 6 Continued Section 6.1 10.
Field Determination of the Tem erature Distribution in the Hanford Number One Cond'enser Coo'lin Wat'e'r Dischar e
- Plume, Bette e, Peer rc Northwest La oratorres,
- Richland, WA, November 1972.
- Jaske, R. T., Personal Communication, 1974.
12.
- Benedict, B. A., J. L. Anderson and E. L. Yandell, Jr.,
Anal tical Modeling of Thermal Dischar es A Review of 'the Stat'e-'o'-the'-Art, ANL ES-18, Argonne National Laboratory, April 1974.
13.
- Trent, D. S.,
and J.
R. Welty, A Summar of Numerical Methods'or Solvin Transient Heat Condu'ction Pro
- ems, Engineering Experiment Station Bulletin No. 49, Oregon State University, Corvallis, OR, October 1974.
14.
15.
- Becker, C. D., A uatic Bioenvironmental Studies in the Columbia'iver't Han'f'ord 1945-1971, A Bibliography with Abstracts, BNWL-
, Batte e, Pacific Northwest Laboratories,
- Richland, WA, 1973.
Final Re ort on A uatic Ecolo ical Studies Conducted at the Han'ford'enera'tin'g'roe'ct,
'97'3-1974, WPPSS Columbia River Ecology Studies Vol. 1, Battelle, Pacific North-west Laboratories to United Engineers and Constructors for the Washington Public Power Supply System,
- Richland, WA, March 1976.
16.
A uatic Ecological Studies Conducted Near WNP-1, -2, and
'-4'e t'ember'"197'4t'o'e
'temb'e'r1975, WPPSS Columbia River Ecology Studies Volume 2, Battelle, Pacific Northwest Laboratories to United Engineers and Constructors for the Washington Public Power Supply System,
- Richland, WA,
'July 1976.
17.
U.S. Atomic Energy Commission, Draft Environmental State-men't','aste'ana em'en't 0 erations, Hanfo'rd Reservation, Ric an WA, Septe er 9 4.
18.
Hanford Wells, BNWL-928, Battelle, Pacific Northwest Laboratories,
- Richland, WA, pp.
8, 126-127, 129P October 1968.
19.
USAEC Regulatory Staff, Standard Format and Content of Safet Anal sis Re orts for Nuclear Power Plants, Revision 1, October 1972.
WNP-2 ER REFERENCES FOR CHAPTER 6
(Continued)
Section 6.1 20.
Office of the Federal Register, Code of Federal Re ula-tions Tit'le 10-Atomic Ener
, part 100, Revised January 1, 1972.
21.
Regulatory Guide 1.4, "Assumptions Used for Evaluating The Potential Radiological Consequences of a Loss, of Coolant Accident for Pressurized Water Reactors,"
USAEC.
22.
- Slade, D. H., ed., Meteorolo ical and Atomic Ener USAEC, TID-24190, July 1968.
23.
- Briggs, G. A., Plume Rise, AEC Critical Review Series, USAEC Report TID-25075, p.
81, November 1969.
24.
Weinstein, A. I., and L. G. Davis, A Parameterized Numerical Model of Cumulus Convection, Report No. 11, NSFGA-777, Pennsylvania.a State University, Department of Meteorology, 43 pp.,
1968.
25.
EG&G, Inc., Potential Environmental Modifications Produced b
Lar e Eva orative Cooling Towers, Final Report on Contract No. 14-12-542, to Federal Water Pollution Administration, Pacific Northwest Water Laboratory.
EG6G, Inc., Environmental Services Opera-tion, Boulder, CO.
26.
Droppo, J. G.,
C. E. Hane, and R. K. Woodruff, Atmospheric Effects of Circular Mechanical Draft Coolin Towers at Washin ton Public Power Su 1
S stem Nuclear Power Plant Number Two, Battelle, Pace.fzc Northwest Laboratories to Burns and Roe for the Washington Public Power Supply
- System, Richland, WA, in preparation.
27.
- Hosier, C. L., J.
- Pena, and R. Pena, Determination of Salt De osition Rates from Drift from Eva orative Coo xn
- Towers, Pennsy vane.a State Unz.versa.ty, Dept. of Meteorology, May 1972.
28.
Roffman, A. and L. D. Van Vleck, "The State-of-the-Art of Measuring and Predicting Cooling Tower Drift and its Deposition," Jour. of Air Pol. Control Assoc., vol. 24, No. 9, pp. 855-859, Septe er 1974.
WNP-2 ER REFERENCES FOR CHAPTER 6
Continued Section 6.1 29.
Woodruff, R. K., D. E. Jenne, C. L. Simpson, and J. J. Fuquay, A Meteorolo ical Evaluation of the Effects of the Pro ose Coo in 'owers o 'an or 'u er Two C
Site on Surroundin Areas, Battelle, Pacific Northwest La oratories to Burns an Roe, Inc., Hempstead, NY, September 1971.
30.
McHenry, J. R., Pro erties of Soils of the Hanford
~pro'ect, HW-53218, Hanford Atomrc Products Operation,
- Richland, WA, 1957.
31.
Hajek, B. F., Soil Surve
.Hanford Pro'ect in Benton Count,,
Washin ton, BNWL-243, Battelle, Pacific North-west Laboratories, Richland)
WA( 1966.
32.
Brown, D. J.,
Geolo Underl in Hanford Reactor Areas, HW-69571,'962.
33.
Brown, R. E.,
and D. J.
Brown, The Rin old Formation and Its Relationshi to Other Formations, HW-SA-2319, Hanfor Atomic Productions Operation,
- Richland, WA, 1961.
34.
Raymond, J.
R. and D. D. Tillson, Evaluation of a Thick Basalt Se uence in South-Central Washin ton, BNWL-776, Batte le, Pacific Northwest Laboratories,
- Richland, WA, 1968 35.
Shannon and Wilson, Inc., Hanford No.
2 Nuclear Power Pl'ant Central Plant Facilities, prepared for Burns and Roe, Inc.,and
- WPPSS, 1971.
36.
37.
Bierschenk, W. H. A uifer Characteristics and Groundwater Movement 'at Hanford, WH-60601, Hanford Atomic Products Operation,
- Richland, WA, 1959.
Brown, D. J.
and P.
P.
- Rowe, 100-N Area A uifer Evaluation, HW-67326, Hanford Atomic Products Operation, Richlan WA, 1960.
38.
Daubenmire, R.,
A Canopy Coverage Method of Vegetational Analysis.
Northwest Sci., vol. 33, pp.
43-64, 1959.
39.
State of Washin ton, Po ulation Trends, 1975, Population Studies Division, Office of Program Planning and Fiscal Management,
- Olympia, WA, 1975.
WNP-2 ER REFERENCES FOR CHAPTER 6
(Continued)
Section 6.1 40.
Population Estimates:
Oregon Counties and Incor orated Cities, Center for Population Research and Census, Portland State University, Portland, OR, July 1, 1975.
41.
Po ulation, Em lo ment and Housin Units Pro'ected to 1970, Bonneville Power Administration, February 1973.
42.
Columbia-North Pacific Re ion Com rehensive Framework Stud of'Water and Re'lated
- Lands, A
endix VI, Economic Base and Pro ecto.ons, Pace.fzc Northwest Raver Basins Commission, Vancouver, WA, January 1971.
43.
Po ulation and Household Trends in Washin ton, Ore on and Northern Idaho, 1970 to 1985, Paczfa.c Northwest Bell, January 1972.
44
- Clement, M., et al., Stud and Forecast of Tri-Cit Economical Activit an z.ts Related Im act on Gasoline Needs and Housing, Battelle, Pacific Northwest Labora-tories to Trz.-Cz.ty Nuclear Industrial Council, Richland, WA, May 1974.
45.
- Cone, B. W., The Economic Im act of the Second Bacon Siphon and Tunnel on the Ea'st Hi h Area, the State of Washin ton and the Nation, Columbia Basin Develop-ment League, P.O.
Box 1980, Ephrata, WA, 1970.
46.
Woodward-Clyde Consultants, Socioeconomic Stud WPPSS Nuclear Pro'ects 1 and 4, Prepared for Washington Public Power Supply System,
- Richland, WA, April 1975.
47.
Yandon, K., Assum tions for Po ulation Estimates and Pro'ections b
Speci'fic Com ass Sectors and Radii Dzstanc'es from WNP-2 Sz.te, Battelle, Pacz.
xc Northwest Laboratories to Burns and Roe for the Washington Public Power Supply System,
- Richland, WA, in preparation.
48.
Terrestrial Ecolo y Studies in the Vicinit of Washin ton Publ'ic Power Su 1
S stem Nuclear Power Stations 1 and 4, Progress Report for the Period July 1974 to June
- 1975, Battelle, Pacific Northwest Laboratories to Burns and Roe for the Washington Public Power Supply System,
- Richland, WA, in preparation.
WNP-2 ER
'REFERENCES'OR
'CHA'PTER 6
Section 6.3 U'.S. Geological Survey, "Water Resources Data for Washington, Part 1,"'urface Water Records, 1973.
Hilty, E. L. and J.
P. Corley, Personal Communication/
Battelle, Pacific Northwest Laboratory, Richland, WA, 1975.
Onishi, Y., Columbia River Quality Radionuclide and Sediment Transport, Battelle, Pacific Northwest Labora-tory, letter to Paul G. Hoisted, U S. Atomic Energy Commission, Richland Operations Office, December ll, 1974.
- Bramson, P.
E. and J.
P. Corley, Environmental Surveil-lance at Hanford for CY-1972, BNWL-17 7, Battelle, Paci ic Nort west La oratory, Richland, WA, April 1973.
- Schultz, M. J.,
Chemical and Biolo ical Pollution Surveil-lance of the Han or Environs, Quarterl Re ort, -Han'ford Environmenta Hea th Foundation,
- Richland, WA, October 1 Dece er Kipp, K. L. Jr., Radiolo ical Status of the Groundwater Beneath the Hanford Pro ect, Jul -December
'1972, BNWL-1752, Batte e, Paci ic Nort west La oratory, Ric
- and, WA, August 1973.
U.S. Atomic Energy Commission, Division of Reactor Research and Development, Evaluation of Nuclear Ener
- Centers, WASH-1288, 2 Volumes, January 1974.
U.S.
Army Corps of Engineers, North Pacific Division, "The Columbia River and its Tributaries," July 1972.
Cunningham,
- Richard, Supervisor, Water Quality Monitor-ing Section, Washington State Department of Ecology, Olympia, Washington, letter to Albin Brandstetter, Battelle, Pacific Northwest Laboratories,
- Richland, WA, May 26, 1976.
U.S. Environmental Protection Agency, Storet Data, 1976.
Final Re ort on A uatic Ecolo ical Studies Conducted at t, e Han or 'eneratin Pro ect,
WPPSS Co um ia River Ecology Studies Vol. 1, Battelle, Pacific Northwest Laboratories to United Engineers and Constructors for the Washington Public Power Supply System,
- Richland, WA, March 1976.
WNP-2 ER REFERENCES'OR CHAPTER 6
Continue Section 6..3
- Page, T. L., E.
G. Wolf, R. H. Gray and M. J. Schneider, Ec'ol'o'c'al'ompar'ison of the Hanford Generat'in Pl'a'nt and 'th'e WNP-2Sate's'n' e'olumbia Reer, Batte le, Pacxfzc Northwest Laboratories to United Engineers and Constructors for the Washington Public Power Supply
- System, Richland, WA, October 1974.
- Watson, D. G., Fall Ch'inook Salmon S 'awnin
'inthe Columbia River Near Hanford, 19-'1969, Report BNWL-1515, Batte le, Pacific Nort west Laboratories,
- Richland, WA, 1970.
Pacific Northwest Laboratories Annua'1'e ortfo'r975to t e U.S'. oner Research'nd Develo ment 'Admz'n'a.'st'ra'tio'n, Dave.'saon'f Bxomedica'1 and Environmental" Rese'ar'ch, Part
'-'co o zca
- Sciences, Report BNWL-
, Part 2, Battelle, Pacific Northwest Laboratories,
- Richland, WA, 1976.
Fickheisen, D. H. and M. J. Schneider (editors),
Proc'eedin
's 'of Gas Bubble Disease Worksho
, Conference 0
Oa Rz. ge, Tennessee, Terrestria'1'colo Studies in the Vicinit o'f Washin ton public'ower 'Su
'1
'S stem Nu'cl'ear power Sta'tions 1 and 4, Progress Report or t e Perxo Ju y 7
to June 7
Battelle, Pacific Northwest Laboratories, to United Engineers and Constructors for Washington Public Power Supply System, Richland.,
WA, in preparation.
- Stone, W. A., Meterolo ical Instrumentation o'f the Hanford
- Area, HW-62455, March 1964.
- Stone, W. A., D. E. Jenne and J.
M. Thorp, Climato ra h of the'anford Area, BNWL-1605, Battelle, Pace xc Northwest Laboratories,
- Richland, WA, 1972.
Thorp, J. M., "1972,Microclimatological Measurements on the Arid Lands Ecology Reserve," in Pacific Northwest Laborator Annual'e ort for 1972 to the USAEC Divis'i'on o'rome
'zca 'h 'nvxronmenta Re's'e'arc,'o
'ume II:
Ph scca'1'c'ience's Part 1',
A'tmos hericci'e'n'ces, BNWL-17
, Part
, Battelle, Pacxfac Northwest Labora-tories, Richland, WA, April 1973.
WNP-2 ER
'EFERENCES'OR CHAPTER 6
Continued Section 6.3 20.
- Baker, D. A.,'i'ffu'sion'l'ima'tolo Stud
'o'f th00-N
'"Are'a','an'for'd'a'sh'in t'on, DUN-7841, Douglas United Nuclear, Inc., Ric lan WA, 1972.
21.
- Blumer, P. J.,
D. A. Myers and J. J. Fix, Ma'ster Schedule
'for 'CY-'1976,'anfor'd Environmenta'1'u'rv'ei'lla'nce'o'ut'ine P~ro ram, BNWL-B-
, Bette e, Pacr rc Nort west Labora-
- tories, Richland, WA, December 1975.
22.
- Speer, D. R., J. J. Fix and P. J. Blumer, Environmen'tal Pacific Northwest Laboratories,
- Richland, WA, April 1976.
23.
- Raymond, J. R., et al., Environmental'onito'rin Re ort
'n'a'di'o'lo i'cal'tatus' the Groundwa'ter Be'ne'ath'he Ha'nfo'rdSit'e','a'nua'r
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24.
- Mooney, R. R., Environmen't'al Ra'diation'urve'i'll'anc'ein
'a'shinon'ta'te,
Annua
Re ortJu 7 '-'June'975, Radiation Control Unit, Division of Social and Health
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- Olympia, WA, 1975.
WNP-2 ER REFERENCES FOR CHAPTER 7
Section 7.1 Horton, N. R. Willians, W. A., Holtzclaw, J. W., "Analytical Methods for Evaluating the Radiological Aspects of the General Electric Boiling Water Reactor,:
APED-5756, March 1969.
B. J. Garrick, W. C. Geklev, L. Goldfisher, B. Shimizu, J.
H. Wilson, The Effect of Human Error and Static Com-ponent Failure on Engineered Safety System Reliability, H N-194, Holmes and Narver, Inc., Los Angeles, California,
- November, 1967.
APED-5286, "Design Basis for Critical Heat Flux in Boiling Water Reactors,"
(Sept.
1966).
Slifer, B. C.,
and J. E. Hench, Loss-of-Coolant Accident and Emer enc Core Co'olin
, Mo'del's for Genera'1'lectric Boa.lang Water Reactors, NED0-10329, General Electra.c Com-
- pany, San Jose, California, April 1971.
Garrick, V. J.,
B. Shimizu, W. C. Gekler, J.
H. Wilson, Col-lection of Reliabilit Data at Nuclear Power Plants HN-199, Holmes and Narver, Los Angeles, California, Dec.
1968.
Garrick, B. J.,
W. C. Gekler, 0. C. Baldonado, E. H. Behrens, B. Shimizu, "Classification and Processing of Reliability Data from Nuclear Power Plants,"
HN-193, Holmes and Narver, Inc., Los Angeles, California, February, 1968.
Failure Data Handbook for Nuclear Power Facilities, Vol. 1, Fax.lure Data and Applications Technology, Vol. II, Failure Category Identification and Glossary, Liquid Metal Engine-ering Center,
- Revised, June, 1970.
S.
R. Vandenberg, "Reactor Primary Coolant System Rupture Study, Quarterly Report No. 22, July-September,
- 1970, GEAP-10207-22, General Electric Company, San Jose, California.
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- USAEC, November 1972.
United States Atomic Energy Commission Rules and Regulations Title 49, Part 171,
- 174, and 177.
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September 1, 1971.
WNP-2 ER 12.
Otway, Harry J., et. al.,
A Risk Anal sis of Ome a West Nea'ctcr, LA-4449,'os Alamos Screntrfrc Laboratory o
the Unrversity of California, March, 1970.
13.
Otway, Harry J.,
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'eact'or Sit'i'nand Des'x, n, LA-4316, Los Alamos Sca.entz. ic Laboratory of the University of California, June, 1969.
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- Green, A. F., "Safety Assessment of Automatic and Manual Protective Systems for Reactors," trans. A.N.S., 12, 172 (1969).
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Garrick, B. J.,
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16.
- Gangloff, W. C.,
An Evaluation of Antici ated 0 erational Transients in Westin hous'e Pres'surized Water Reactors, WACP-7486, West'.nghouse Electric Corporation, Pxttsburgf PA, May, 1971.
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Wall, I. B., and Richard C. Augenstein, "Probabilisitc Assessment of Aircraft Hazard for Nuclear Power Plants,"
ANS 16th Annual Meeting, Los Angeles, California, June 30, 1970.
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Otway, Harry J.,
Robert C. Erdmann, "Reactor Siting and Design from a Risk Viewpoint," Nuclear En ineerin and Dasican, Vol. 13, No. 2, 1970, pp.
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WNP-2 ER REFERENCES FOR CHAPTER 8
Section 8.2 1.
Washington Public Power Supply System, WNP-2 Updated 2.
Washington Public Power Supply System, 1976 Ten-Year Fuel Mana ement Plan, Appendix D,. April 15, 1976.
3.
Woodward-Clyde Consultants, Supplement to Socioeconomic Study:
WPPSS Nuclear Projects Nos.
1 and 4, Aprz.l 1975.
WNP-2 ER REFERENCES FOR CHAPTER 10 Section 10.1 1.
Washington Public Power Supply System, Environmental
- I 2.
U.S. Atomic Energy Commission, Environmental Statement, Hanford Number Two'ucl'e'ar P'ow'er'lant, December 1972.