ML20154J634
| ML20154J634 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/23/1978 |
| From: | Madgett J DAIRYLAND POWER COOPERATIVE |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20154E750 | List: |
| References | |
| LAC-5185, NUDOCS 8805270082 | |
| Download: ML20154J634 (84) | |
Text
{{#Wiki_filter:DA1RYLAND POWER COOPERATIVE Ba Gusse, 01'wonsin t 54601 February 23, 1978 In reply please refer to LAC-5185 DOCKET No. 50-409 Director of Nuclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch #4 * ' Division of Reactor Licensing 'Z U.S. Nuclear Regulatory Commission ..a 4 m Washington, D. C. 20555 -;< j s
}j
SUBJECT:
Dairyland Power Cooperative . . '. / La Crosse Boiling Water Reacter (LACBWR) . J Provisional Operating License No. DPR-45 RE: Letter from Reid to Madgett, dated December 16, 1977.
Dear Mr. Reid:
En.:losed please find the response to your request for additional information in the subject letter. The enclosed information demonstrates that LACBWR, with utilization of its present radwaste treatment systems, meets the requirements of 10CFR50, Appendix I. Very truly yours, DAIR}LANDPOWERCOOPERATIVE
~Td Jo P. Ma neral Manager JPM/cw Enclosure cc: J. Keppler, Reg. Dir.,
NRC-DRO III 8805D70082 800516 PDR ADOCK 05000409 P PDR d[(g/7
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Responses to Request for Mditional Infomation - La Crosse Boiling Water Reactor dated December 16, 1977
Responses to Request for , Additional Information - La Crosse Boiling ! Water Reactor dated December. 16, 1977 l I l 1. If there is a prior knowledge that the current 50 mile popu- \ \ lation age distribution may be significantly different fron l the U.S. population distributions then furnish the current , age distribution of the 50 mile population (e.g.o 0-12o 12- l lo o >18). l Response: The current age distribution of the 50-mile popu- l lation is assumed to be the same as the U.S. population age ! distribution, as suggested in Regulatory Guide 1.109. l
- 2. Provide in tabular fora, the distances from the nuclear plant stack to the following for each of the 22-1/2 degree radial ;
sectors centered on the 16 cardinal compass directionst a) Mearest site boundary, b) -Nearest residence (to a distance of 5 miles). Indicate if a milk cow o milk gosto meat animal, or vegetable garden also exist at these locations. c) Nearest milk cow (to a distance of 5 miles). Indicate if a milk gosto meat animalo or vegetable garden also exists at these locations. l d) Nearest alik goat (to a distance of 5 miles),, Indicate l if a milk cow o meat animalo or vegetable garden also
- exists at these locations.
e) Nearest meat antasi (to a distance of 5 miles). Indicate if a milk cow o milk goat, or vegetable garden also exists at these locations. f) Mearest vegetable garden greater than 500 ft2 (to a dis-tance of 5 miles). Indicate if a milk cow, alik gos t o or meat animal also exists at these locations. Response: The information requested on milk cows, milk goats and meat animals is contained in the following Table I out to a distance of 5 miles in Sectors 1 - 10 and to a distance of 3 miles in Sectors 11 - 16. Information on residence loca-tions is available to 5 miles in all directions. No informa-tion on the location or size of vegetable gardens is avail-able, however, since LACBWR is located in'a rural area, we have assumed that all residences within 5 miles of the plant have a vegetable garden larger than 500 ft 2. g) Location of all alik cows o milk goatso meat an!
- ti -
dences o and vegetable gardens o out to a distan t ailes for each radial sector. AW w r* ww-=e *+w-- w m wrer - m-v wwwverm ,w=w--w-w -,-wvwww---eww.'w-.
Response: This information was furnished in our letter dated November 16, 1976. The information is repeated here in Tables II, III and IV.
- 3. Provide the dilution and transit time from plant radwaste discharge to nearest location where an individual can obtain aquatic foodo drinking water and utilize the shoreline. Pro-vide the discharge transit time from radwaste input to dis-charge stream to point where it enters the unrestricted area r and the stream discharge in Cubic feet per second. If there are locations where reconcentration may occuro describe them and provide the pertinent information as above.
Response: Two receptor locations were considered for doses to individuals from liquid releases. The nearest location where an individual could obtain aquatic food (fishing) was taken to be at the south end of Thief Slough, approximately 1.0 mile south of the plant radwaste discharge. The loca-tion of an individual engaged in other river-related activ-ities (drinking water, swimming, boating) was taken to be the center of Pool No. 9 of the Mississippi River, approximately 15 miles south of the discharge. The requested parameters for these two locations are: Fishing (south end of Thief Slough) Stream discharge for dilution - 8360 cfs Discharge transit time - O hours other river-related activities (Center of Pool No. 9) Stream discharge for dilution - 28,000 cfs Discharge transit time - 3 hours No reconcentration of discharged isotopes was considered possible.
- 4. Provide data on population for mid-life of planto annual meat (kg/yr), milk (li t er s/ gr) , and vegetable production (kg/gr),
and distribution within a 50 mile radius from the plant. Pro-vide the data by sectors in the same manner indicated in Sec-tions 2.1.2.1 and 2.1.2.2 of Regulatory Guide 4.2, Revision 1. [ Response: The requested data is furnished on 1970 population figures and 1971 production of meat, milk and vegetables in i Tables V, VI, VII and VIII. This information is based on the j 1970 U.S. Census of Population and the 1971 U.S. Census of Agriculture. Projections of these figures to mid-life of LACBWR are not available. Since the area has a stable agri-cultural base, the 1970, 1971 data could be assumed for mid-7 life of plant.
- 5. Provide information on the grazing season (give dates), and fraction of daily intake of cows derived from pasture of fresh green chop during the grazing season. Provide the same informa tion for meat animals and milk goats.
Responses A six month (April 15 - October 15) grazing season was assumed for both cows and meat animals. It was assumed that all daily intake of cows and meat animals is from fresh green chop during the grazing season. Doses via milk goat pathways were not calculated, however, assumption of the same intake parameters would be fair.
- 6. Provide the fraction of the year that leafy vsgetables are grown.
It was assumed that leafy vegetables are grown six months during the year and that 76 percent of an individual's intake of leafy vegetables comes from his private garden.
- 7. Provide the average absolute humidity in grams per cubic meter during the growing season.
Response The average absolute humidity during the growing season was assumed to be 8 grams per cubic meter.
- 8. Provide the present and projected commercial fish and inverte~
brate catch (in kg/yr) from waters within 50 miles downstream of the plant radwaste discharge. Provide the data by major catch locations o the distance from the plant radwaste dis ~ charge r the transit time and dilution from plant radwaste dis ~ charge to major catch location and the basis for the dilutior and transit time. :ndicate the amounts consumed within che 50 mile radius of the plant. i Provide the same information for sport fish and invertebrate catch. . Response: Commercial and sport catches of aquatic life which were considered in dose calculations were those which have been recorded in Pool No. 9, which extends approximately 30 miles downstream of the plant's radwaste discharge. For purposes of transit time and dilution factors, it was assumed that all fish were caught in the center of Pool No. 9. ! Commercial Fish catch 6.63x105 kg/ year Commercial Invertebrate Catch no significant catch Sport Fish Catch 1.65x105 kg/ year
- Sport Invertebrate Catch no significant catch 4
River Dilution Flow 28,000 cfs Transit Time 3 hours
t . r Sport fish catch is based on a 1967 creel census of Pool No. 9 conducted by the Iowa Conservation Commission and an , . assumed average fish flesh weight of 0.5 kg per fish. Com- ! l mercial fish catch is based on 1970 data supplied by the Wisconsin Department of Natural Resources. It was assumed i that all fish caught were consumed within the 50-mile radius of LACBWR. b Provide similar information for other aquatic ilfe such as ; seaweed, any fish forms or other aquatic activity within 50 ailes of the plant which may reasonably be affected by the plant radwaste discharge. Response No other aquatic life dose pathways are believed - i to exist in the vicinity of LACBWR. j 9. Provide present and projected drinking water intake locations , within 50 miles downstream of the plant radwaste discharge. e Provide the distance from the plant radwaste discharge r the l 1 transit time and dilution from the plant radwaste discharge to each major location and the basis for the transit time l , and dilution, and either the population served at each water intake location or the gallons per day supplied by each loca-i tion. L Response The information requested for present drinking water l intake locations is furnished below: McGregor, Iowa 1 ' l 1970 Population 1,000 River Dilution Flow 32,310 cfs , Distance Downstream 44 miles Transit Time 8 hours Davenport, Iowa j ,, fn l , g, r 1970 Popula ion 98,500 45',310 cfs
/7 4
))/7 3
4 , r Diluti n Flow (R4DAs ance'Downytrean, \q /200 m,iles i Tra g/T ime (/ U 40 hou'rsj No other major drinking water intakes are known to exist or ! expected in the future. }
- 10. For any irrigated land using water from within 50 miles down-stream of the plant radwaste discharge, provide the irrigation i rate (liters / square meter / month), yield of the crop (kg/m 2 ), ;
annual production (kg/yt), and growing period (days)s specify 7 f (
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the crop type and its use (i.e. for L in me apt.. , for milk or meat animals), the dilution ans .t time from plant radwaste discharge to each major use: location and basis for the dilution and transit time s and the total pro-duction in the 50 mile area (Kg). Indicate the amounts con-sumed within the 50 mile radius of the plant. Responset There are no known uses of river water for irri-gation within 50 miles downstream of LACBWR.
- 11. Identify any additional exposure pathways specific to the region around the site which could contribute 10% or more to either individual or population doses.
Response: There are none.
- 12. Annual Population Doses - Calculate r using the information provided in response to questions 1 - 11 above and any other necessary supporting data r the annual total-body man-tem and man-thyroid-rem doses to the population expected to reside in the 50 mile region at the midpoint of plant operation as well as the annual total body man-ren and the annual man-thyroid-tem received by the U.S. population at the same time from all liquid and gaseous exposure pathways. Provide as an appendix to your responss a description of the models and assumptions used in these calculations.
Responset The calculated population doses are: 50-mile Radius Total j of LACBWR United States t Pathway Total Body Thyroid Total Body Thyroid man-ram man-ram man-ram man-ram { l Liquid i Releases 1.95 0.512 1.95 0.512
- Airborne Releases 2.81 3.29 13.0 19.3 Tctal 4.76 3.80 14.9 19.8 1
) i A description of the methodology used to calculate these
- doses is contained in Appendix A.
\ 13. Maximum Individual Doses - Calculate r using the information provided in response to questions 1 - 11 above and any other l supporting data, the maximum annual individual doses as j described in Appendix I to 10 CTR Parc 50. Provide as an appendix to your response a description of the models and i assumptions used in these calculations. l l
Response: The calculated maximum annual individual doses from operation of LACBWR as compared to the design objectives of Appendix I to 10 CFR 50 are: Type of Dose Appendix I Point of calmlated Dose Design Objective Evaluaticm Dose Iocation Liquid Effluents Dose to total 3 mram/ year Highest Dose 0.728 center of Pool body frca offsite* mran/ year No. 9 all patbays Dose to any 10 mre:v' year Same as 0.996 See as above onJan frem above mravyear all patb ays 4 Gaseous Effluents Gamma air 10 mrad / year Righest Dose 7.4 Famhouse dose offsite** mead / year 1300m INE - Beta air dose 20 mrad / year Same as 7.4 Same as above
; above mrad / year
'Ibtal body 5 mre Wyear Highest Dose 4.8 Same as above dose .offsite* mruWyear Skin dose 15 mre vyear Same as 10.6 Same as above above mreWyear PhiMLnes and Particulates Released to the At:nosphere Dose to any 15 mram/ year Highest dose 12.6 Same as aheve organ frcm offsite*** mreWyear all patNays A description of the methodology used to calculate these doses is contained in Appendix A.
i 14. For the modifications to the gaseous waste storage tanks, j Provide the holdup time (hours) for the series configuration and continuous flow mode of operation. Describe the tests and resv:ts which provide the basis for this holdup time.
- Evaluated at a location that is anticipated to be occupied during plant lifetime.
4
** Evaluated at a location that could be occupied during the
! term of plant operation.
*** Evaluated at a location where an exposure pathway actually exists at time of licensing.
_____.._m _ _ . , _ y___,_ _ _ _ __
Response: The holdup time was determined to be approximately 10.5 hours for continuous flow series operation. This was determined by measuring the concentrations of the noble gases Kr, Kr and Kr*sm at the inlet and outlet of the system and correcting the activities for radioactive decay. The holdup times determined were 7.4, 11.0 and 13.2 hours respectively for these isotopes. This results in an average holdup time of 10.5 hours.
- 15. a) Describe the meteorciogical measurements available at and near the LACBWR site, including instrumentation specifica-tions and data recovery. The meteorological parameters of con *ern are measurements of wind speed and direction repre-sentative of conditions at the height of release from the plant stack, and an indicator of atmospheric stability (vert-ical temperature gradient is preferred, sigma-theta is acceptable).
Response A complete description of the LACBWR meteorolog-ical program was submitted in our letter of November 16, 1976. To recapitulate, the program was updated beginning in 1974 Three new meteorological stations have been installed at various locations in the site vicinity to give a more accurate representation of atmospheric activity in the hilly terrain around the site. A Meteorology Research, Inc. (MRI) Model 1074-22 anemometer and wind vane are mounted on a boom at the top (250-foot level) of the LACBWR stack. This instrument is equipped with a MRI sigma meter, providing a separate con-tinuous output of the standard deviation of the fluctuation in horizontal wind direction which gives a measure of atmos-pheric stability. Boem length has been increased to 2-1/2 stack diameters to minimize stack aerodynamic interference. A second MRI anemcmeter/ wind vane / sigma meter has been in-stalled on a 10-meter pole on the LACBWR site in order to assess surface winds. A Rosemount Model 442A dry bulb temper-ature system has been installed to measure ambient temperature and differential temperature between the stack-top and 10-meter pole locations. A third MRI anemometer / wind vane / sigma meter has been placed at the top of a 100-foot radio tower located 2.0 miles east-southeast of LACBWR on the bluffs. Grade elevation at the tower is 1200 feet MSL. LACBWR site grade is 639 feet MSL. The accuracy of this instrumentation surpasses the specifica-tions of Regulatory Guide 1.23: Anemometer starting threshold - 0.75 mph accuracy - :0,25 mph Wind Vane starting threshold - 0.75 mph accuracy - :3.6' J
Temperature (dry bulb) , accuracy - t 0.18'F (! 0.10'C) Differential Temperature accuracy -t0.025'F (2 0.014*C) l Instrumentation was placed in service according to the follow-ing schedule: ( Radio Tower anemometer / wind vane / sigma - July 1974 LACBWR Site ambient temperature - January 1976 ' surface anemometer / wind vane / sigma - June 1976 differential temperature - July 1976 stack anemometer / wind vane / sigma - August 1976
- 15. b) Provide joint requency distribu tions of wind speed and direc-tion by atmospheric stability for meass:rements made on the plant stack and at the bluff tower for a concurrent annual cycle. Data recovery for each data set should approach 90 percent. If data recovery-is less than 90 percento periods of extended instrument outage (i . e . o 24 hours or more) should be Jdentified.
Joint frequency distributions are provided from the bluff tower (Mound Ridge NE) and the plant stack (LACBWR stack) wind instruments for the following periods: Mound Ridge NE: 1/1/77 - 7/7/77 LACBWR stack 1/1/77 - 7/1/77 1/1/77 - 12/31/77 Periods of extended instrument outage during 1977 were Mound Ridge NE: 1/1/77 - 2/18/77 7/6/77 - 12/31/77 LACBWR stack 3/1/77 - 5/11/77 7/17/77 - 9/28/77 10/22/77 - 10/24/77 These outages were due to lightning strikes and other failures in the instrument electronics.
1 i 9 i 16. provide topographic cross-sections of terrain height versus i distance for each of sixteen 22-1/2 degree sectcts centered i on true north, north-northeasto northeasto etc. Zdentify i plant grade and the elevation of the stack. ' l The requested topographic cross-sections are contained in s
- Table IX. Plant grade elevation is 639 feet MSL. Height
4 of the radwaste stack is 107 meters (350 feet), with gas i 1 exit elevation of 989 feet MSL. l l I 4 b 4 [ 1 f a l ] l } i l l
TABLE V POPULATION IN THE LACBNR VICINITY 1970 CENSUS Direction Prom Distance - Miles LACBWR 1 2 3 4 5 10 20 30 40 50 WismuuuumP+;h N 4 12 24 12 32 1010 50,357 13,230 4,830 5,600 NNE 50 270 20 25 24 240 4,059 7,270 7,410 4,390 NE 12 12 8 44 416 1,944 1,920 4,740 6,090 ENE 4 8 4 32 32 242 1,226 2,360 4,470 5,740 E 8 12 12 72 246 5,074 1,900 4,110 5,280 ESE 12 16 16 12 24 359 1,079 3,170 4,014 5,160 SE 16 16 12 20 16 238 665 2,810 3,670 7,550 SSE 58 8 36 40 24 260 583 1,490 3,670 7,550
$ S 8 12 20 332 2,182 7.740 3,480 4,650 SSW 215 635 1,634 11,800 3,350 5,570 5*4 8 20 492 518 2,840 4,330 6,030 WSW 12 12 12 132 827 1,190 4,330 5,130 W 8 12 16 142 790 4,210 3,660 4,700 WNW 4 24 12 145 3,697 910 3,490 4,880 NW 60 24 196 962 3,320 4,110 5,280 NNW 12 194 5,829 2,900 22,180 4,490 Total Population in 50-mile Radius - 331,252 Source: 1 - 20 Miles - LALnWR Environmental Analysis 30 - 50 Miles - 1970 U.S. Census of Population, County Basis l
TABLE VI MEAT PRODUCTION IN THE LACBWR VICINITY 1971 CENSUS * (103 kilograms / sector) Direction From Distance - Miles LACBWR 1 2 3 4 5 10 20 30 40 50 N 58 133 80 234 438 NNE 0.2 0.8 1 1 11 69 133 158 113 NE 0.2 0.4 0.8 1 1 11 52 79 92 118 ENE 0.2 0.4 0.8 1 1 11 45 's 98 121 E 0.2 0.4 0.8 1 1 11 45 80 128 165 ESE 0.2 0.4 0.0 1 1 11 129 566 238 560 i
! SE 0.2 0.4 0.8 1 1 11 380 776 971 3939 i
SSE 0.1 0.4 0.8 1 1 32 186 863 1480 3939 m S 40 1110 2120 4727 5574 SSW 318 1585 2650 4236 6062 ] SW 8 34 397 1585 944 4728 6003 WSW 6. 26 34 316 1515 3312 4728 5668 W 13 26 34 281 1121 2181 3383 4218 WNW 26 9 34 281 1121 1999 2965 3194 NW 2 18 34 281 1121 1561 '1352 ' 1494 . NNW 3 17 281 1121 854 6al' 554 Source: 1971 U.S. Census of Agriculture
TABLE VII MILK PRODUCTION IN THE LACBWR VICINITY 1971 CENSUS (103 liters / sector) Direction From Distance - Miles } LACBWR 1 2 3 4 5 10 20 30 40 50 N 803 3,622 10,120 23,110 25,680 NNE 50 166 232 298 2491 10,050 16,870 22,190 17,070 NE 34 100 166 232 298 2491 9,979 14,250 18,940 24,390 ENE 34 100 166 232 298 ^2491 9,950 16,020 21,100 25,480 E 34 100 - 166 232 298 2491 9,950 '16,539 21,970 26,230 s , x - ( ..- 7 ESE 34 100 166' 232 298 2491 9,316 f2,920 20,610 ?? 410 SE 34 100 166 232 298 2491 7,414 11,330 13,920 29,670 SSE 17 100 100 100 100 2330 2,712 8,329 17,280 29,670 U S 153 4,273 8,162 17,850 21,680 SSW 1223 6,105 10,200 15,100 18,890 SW 43 182 1529 6,105 10,940 16,a20 19,460 WSW 30 142 182 1525 6,155 11,860 16,820 18,980 W 71 142 182 1523 6,081 9,782 13,450 16,400 WNW 51 142 182 1523 6,081 9,708 13,500 19,650 NW 10 99 182 1523 6,081 11,750 20,680 27,720 , NNW 14 91 1523 6,081 13,380 21,280 25,720 Source: 1971 U.S. Census of Agriculture
TABLE VIII VEGETATION PRODUCTION IN THE LACBWR VICINITY 1971 CEPSUS (103 kilograms / sector) Direction From Distance - Miles LACBWR 1 2 3 4 5 10 20 30 40 50 N 48 3'1 1026 2138 1732 NNE 3 10 13 17 144 889 1710 2211 1449 NE 2 6 10 13 17 144 665 1017 1178 1514 ENE 2 6 10 13 17 144 575 938 1260 1556 E 2 6 10 13 17 144 575 1034 2113
,1645 ESE 2 6 10 13 17 144 623 1239 1852 2502 SE 2 6 10 13 17 144 765 1358 1607 3664 SSE 1 6 10 13 17 156 325 1024 2087 3664 S 21 584 1114 6118 7666 SSW 167 834 1393 5338 17295 SW 3 12 209 834 1661 2881 12500 WSW 2 9 12 131 765 1996 2881 6823 W 4 9 12 97 389 3991 8453 11900 WNW 3 9 12 97 389 3210 9231 10280 NW 1 6 12 97 389 1248 4307 4743 .
NNW 1 6 97 389 2180 2209 1719 Source: 1971 U.S. Census of Agriculture
E 0O0O0O0O0O0O05080602 S 0 0 0 0 0 3 09021405 S 1 2 3 4 5 8 0 2181 31 1 1 1 7 E 0O0O0O0O070700040009 S 0 0 0 0 030331 333405 1 2 3 4 5 8 91 1 141 1 1 1 1 2 E 0O0O0809070900000901 S 0 0 0104065701 346557 E 1 2 3 4 5 5 81 9131 51 1 1 2 3 0O0O0404000800050501 E 0 0 020601 5204060607 1 2 3 4 51 5161 6101 51 1 2 3 3 E 0O0O0801 000400080501 N 0 0 01 0601 0304547607 E 1 2 3 4 516181 8121 31 1 5 9 E 0O0O0O08090300000005 N 0 0 0 71 540771 543486 1 2 3 3 4 5 51 8181 21 2 5 E . . . . . . . . . . . . . . . . . . . . T E 0O0O0O0O050804060209 I N 0 0 0 0 055253540505 S N 1 2 3 4 5 7111 2141 01 1 3 7 8 E H . . . . . . . . , . . . . . . . . . . . T 0O0O0O0O0O0O09000001 M N 0 0 0 0 0 5 04010407 O 1 2 3 4 5 4 7 0151 51 R 2 2 3 6 8 F N . . . . . . . . . . . . . . . . . . . . O I W N 0O0O0O0O0O0O0O0O0402 0 0 0 0 0 0 0 0 0385 X T N 1 2 3 4 5 0 0 9 21 71 I C 1 2 5 6 7 E E R I . . . . . . . . . . . . . . . . . . . . L D W 0O0O0O0O0O0O0O040603 B N 0 0 0 0 0 0 0 435354
- A F 1 2 3 4 5 0 4 8141 81 T O 1 4 4 7 8 S
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i APPENDIX A l l i l l t
EVALUATION 'JF LACBWR OFF-SITE DOSES DCE TO RADIONUCLIDE RELEASES IN GASECUS EFFLUENTS Prepared for DAIRYLAND POWER COOPERATIVE By NUCLEAR ENERGY SERVICES, INC. Danbury, Connecticut 06810 1 , - , , , , . . . ..,,-,.,--,n-- , . --w~~nw.n-- v--,---~~, - - - - , - - - - - , - - - - - - - - - - - - - - - -
TABLE OF CONTENTS PAGE
- 1. INTRODUCTION . . . . . . . . . . . . . . . . . 1
- 2. CONCLUSIONS . . . . . . . . . . . . . . . . . 2
- 3. GASEOUS EFFLUENT DOSE CALCULATIONS . . . . . . 3 3.1 Human Activities .. . . . . . . . . . . . 3 3.2 Meteorology . . . . . . . . . . . . . . . 9 3.3 Atmospheric Dispersion Calculations . . . 9 3.4 Gaseous Source Term . . . . . . . . . . . 19 3.5 Dose Calculations . . . . . . . . . . . . 19 3.5.1 Annual Air Doses . . . . . . . . . 19 3.5.2 Maximum Individual Annual Dose to Tissue from Noble Gas Effluents. . 22 3.5.3 Maximum Individual Annual Doses from Radiciodines, Radioactive Particulates and Tritium . . . . . 23 3.5.4 Population Doses . . . . . . . . . 26
- 4. REFERENCES . . . . . . . . . . . . . . . . . . 30 i
1 LIST OF TABLES TABLE TITLE PAGE 3.1-1 Population in the LACBWR Vicinity 1971 Census . . . . . . . . . . . . . . . . 4 3.1-2 Milk Production in the LACBWR Vicinity 1971 Census . . . . . . . . . . . . . . . . 5 3.1-3 Meat Production in the LACBWR Vicinity 1971 Census . . . . . . . . . . . . . . . . 6 3.1-4 Vegetation Production in the LACBWR vicinity - 1971 Census . . . . . . . . . . 7 3.1-5 Site Specific Data . . . . . . . . . . . . . 8 3.2-1 Annual Joint Frequency Wind Distributions. . 10 3.2-2 Grazing Season Joint Frequency Wind Distributions . . . . . . . . . . . . . . 11 3.3-1 Topographical Data in the Vicinity of LACBWR . . . ... . . . . . . . . . . . . . 13 3.3-2 Annual Average Radionuclide Concentration. . 14 3.3-3 Decayed Radionuclide Concentration . . . . . 15 3.3-4 Decayed and Depleted Radionuclide Concentration . . . . . . . . . . . . . . . 16 3.3-5 Annual Average Radionuclide Deposition . . . 17 3.3-6 Special Locations . . . . . . . . . . . . . 18 3.4-1 Source Term - Individual Doses . . . . . . . 20 3.5-1 Gamma Air and Beta Air Dose Rates. . . . . . 24 3.5-2 Total Body and Skin Dose Rates.. . . . . . . 25 3.5-3 Dose Rates Due to Deposition of Radioiodine, Radioactive Particulates, Tritium . . . . . 27 3.5-4 Population Doses . . . . . . . . . . . . . . 28 3.5-5 Source Term - Population Doses . . . . . . . 29 11
. 1. INTRODUCTION At the request of Dairyland Power Cooperative (DPC), Individual i and Population doses due to radioactive material in gaseous effluents have been calculated to demonstrate LACBWR's compliance with the requirements of 10 CFR 50, Appendix I. Calculations were performed using the equations and assumptions of Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating compliance with 10 CFR 50, Appendix I" and Regulatory Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors" using various source terms supplied by DPC. This report presents the results of these calculations. h 1
, 2. CONCLUSIONS Based on the conservative models used, the calculations performed here indicate that LACBWR meets the requirements of 10 CFR 50, Appendix I. Assuming the worst plant releases, population doses are extremely low. It therefore appears, that there are no cost beneficial modifications which can be made to the plant gaseous waste treatment system. I l l l i l 2
- 3. GASEOUS EFFLUENT DOSE CALCULATIONS 3.1 Human Activities Evaluation of doses to individuals and the population due to the release of radioactive material in gaseous effluents requires considerable information which describes the pathways at and near the site by which the radioactivity released may make its way back to individuals. Described following are the parameters used in making dose calculations to individuals and populations.
population Based upon a 1970 census provided by the LACBWR Environmental Analysis Report and the County Basis Census, there are 331,252 people living within a 50 mile radius of the LACBWR facility. Table 3.1-1 summarizes the population data by dividing the area within the 50 mile radius concentrically into rings and, by compass direction, into 16 sectors of 22'30' each, centered upon the compass points indicated. Land Use Milk production is the primary activity in the LACBWR vicinity. Table 3.1-2 tabulates the 1971 milk production figures provided by the U.S. Census of Agriculture. Again the 50 mile radius from the LACBWR has been considered; divided into annular sectors and centered upon 16 compass points. Tables 3.1-3 and 3.1-4 present data, tabulated in a similar manner, for meat and vegetation production. Parameters for Maximum Individual Dose Assessment In the calculation of maximum doses to the individuals exposed to gaseous discharges from LACBWR, usage factora given in l Regulatory Guide 1.109 have been assumed in lieu of site specific data. Doses were calculated at the offsite residence for which the highest values of radionuclide concentrations in air were generated. ( Site specific data required to perform dose calculations on dose , rates to individuals were assigned the default values referenced l in Regulatory Guide 1.109. All site-specific parameters input into the code may be found in Table 3.1-5. l l L- 3
)
TABLE 3.1-5 SITE-SPECIFIC DATA Fraction of Leafy Vegetables Grown in Garden of Interest 1.0 Fraction of Year Cows on Pasture 0.5 Fraction of Year Beef Cattle on Pasture 0.5 Fraction of Feed Derived from Pasture During Grazing Season 1.0 Fraction of Produce from Garden 0.76 Hamidity During Growing Season 8.0 gr/m3 4 9 8 8
Parameters for Population Dose Assessment Calculations of population doses, required the input of popu-lation, milk, meat and vegetation production, (Tables 3.1-1 through 3.1-4) and the atmospheric relative radionuclide con-centrations and deposition valves. Atmospheric dispersion was calculated by the X00DOQ computer code, described in the following section. 3.2 Meteorology Meteorological data for the five-year period January,1967 through December, 1971 provided by the U.S. Department of Commerce were used as input to the atmospheric dispersion calculations. The data were collected at the Lacrosse, Wisconsin weather station, located approximately 18 miles north of the LACBWR site. Annual and quarterly joint frequency distribution of wind speed and wind direction are provided in Table 3.2-1. In the joint frequency summaries, speed below 1 mph were classified as calms. Wind data for the spring and summer seasons were used in the calculation of intake of radionuclides through milk, meat, and vegetable pathways. Since the valley at the La Crosse location has a north by north-westerly orientation as compared to the site's northerly orienta-tion, the meteorological data for La Crosse was rotated one sector to be more representative of site topography. Thus, North becomes North-Northeast, etc. 3.3 Atmospheric Dispersion Calculations In assessing compliance with 10 CFR 50 Appendix I, atmospheric dispersion was calculated using the methods and procedures outlined in Regulatory Guide 1.111. Calculations were performed using the XOQDOQ computer codell) i The code incorporates the "straight line" airflow model, outlined ! in Section C of Regulatory Guide 1.111. The equation used by the code is:
- (X) = 2. 0 5 2
- RF ( x ) g DECi (x)
- DEPLiik (x)
- flik Qx, k x, ij ,
utazj
-1. he2 ,
- exp 2 2 (3.1) c23 (x) l r where, (h)x,k = average effluent concentration normalized by the source strength at distance c and direction k (sec/m 3);
l ut. = mid-point value of the ith wind speed class, corrected l for wind speeds measured at a height different than l the release point (m/sec); , 9
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3CC C C CC CC CCC - C C CC - h CC CCC C -* CC C b CCVCC C Cw-ce =C=C C < r h e' C c C N r. 4 c c C C C c C C C h ~ 4 C C o c < C eC. Oe C. C. OCNChCCC C CCCCC C CC C F-CCCC C h y e . . . 2 . . e . . . . . . . . - eVe -e C Ce C e .Cehe C e 4. h C e e e . e e e e e . e . l CC CC CC CC CC C C CC - CCC CCC CCC C J C C N C C C C C C' ->CCCCC G V-TCCCCC-O-CC<?CCCCCC C CCC V l g 3CC CCC CCCCENCCCC C. - < - C C C C P C N N C C C C 4 C C C C C F C C C C 7 e V . . e e . e e e e . e e e e e . e e e e . e . . e e o e . . e e e o e e e o e e e e l 3CC CC CC CCoCC C oo ,- OC CoCCC CCCC V t ' e t i CCFCCCCOCPPCOCCCPCFC-CCr>->CCC-4CCCN-<CCCC W 3CC CCCCCCCNCCCCC CC-CCC C C-MFCCCCC-COChC4CCCC r y e e e e e e e e o e e o e e e e . e e e o e e e e e . e e e e e o e e e e o e e e e e y V CC C CCCCC COCC C- C CC C CC , C C, C CC CC h O, _* CCCCCCCV-4-CC C?-> C C ? > Q g *; T O 3 ss 3 C O C3 O o - - O C 8 ==** C
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- e w_
< k - k r J V 4 6 - N m 4 V 4 6 - N m c Ve < N - h r 4 V < > - N n 4 V R h - N F J V 4 h Cc M b a La l'
U " O $1 ll U U U li Il Il ll H H ll U II. U U U ll U C 2 e= H 11 ll it H le if, II H ll H l1 h Il ll ll ll c It. i .- q.f r, o rza er rm s e.- - .II .e.--*= = = e= == > N _
cz j(x) = vertical (z) spread of the effluent at a distance x for the jth stability class (m) ; fijk = joint probability of the ith wind speed class, jth stability class, and kth wind direction (dimensionless) ; x = downwind distance from the release point (m); he = effeceive plume height (m); DECi(x) = reduction factor due to radioactive decay at a distance x for the ith wind speed class (dimensionless) ; DEPLijk (x) = reduction factor due to plume depletion at distance x for the ith wind speed class, jth stability class, and kth wind direction (dimensionless); and
= correction factor for air recirculation and stagnation RFk (x) at a distance x and kth wind direction (dimensionless).
The above equation assumes a continuous release whose effluent is evenly distributed across a 22030' sector. Values of X/Q are cal-culated for routine plant releases, at standard radial distances and segments for downwind sectors and at specified individual locations. The following options which were used in the calculation of disper-sion values for the LACBint facility:
- 1. The release point of the plume is assumed to be elevated 100%
of the time.
- 2. The plume for elevated releases undergoes plume rise due to its momentum only.
- 3. The varying topography of the 50-mile radius surrounding LACBWR was used as input into the computations.
- 4. The values of (X/0) etc., were amended to reflect the effects of local air recirculation.
Topographical data may be found in Table 3.3-1. Again, these data are divided concentrically into rings, and by compass direction, into 16 sectors of 22030' each. l Tables 3.3-2 through 3.3-5 present annual average relative radio-l nuclide concentration (X/0), decayed relative concentration (X/0dec)< (X/Od and depleted relativeand decayed relative deposition (D/0) concentrationvalueswhichwerecalcu$afekeEo)r, sectors out to 50 miles. Table 3.3-6 contains (X/0), (X/0d ec), (X/Odec, dep) and (D/0) values for the following receptor locations: l me
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gg - - 'J C' ' i
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m to . * . . . . . . '. . . . . . . . . . . . . . y ta. 2 CC C C C C C C T d C C C*. C C C C C C C If g
- l .
Z C C . N *= U < C t' N - V < t' < C< . E
& - 6. . t**
- l' < Lf tf-C-0-he t ?
l 5 A V. l - m x- -
= . C ru . . . . . . . . . . . . . . . . . . . . ; .
(* c. Z .3 .o c o o C o o o 'J. C' T 1 ? 3 .C <\ c .? l . ts. 2 C O O .C C & V N V.t* if 4 C '.f' C f e (As en N t* < T > =e e - N - . - c: - l O 7
- g
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> C- 2 . . . . . . . . . . . . . . . . . . . . !
Ed H CC CC C c C C c C C e C e e C c. e c - ! ; H Z u C- c3 o o a tf. a<C-.' -en e < H H k N t' '< v. e & C-J-U - C O, ** e 6, 4 i U w i ! M H :- g . . . . . . . . . . . . . . . . . . . .
* > Z C C C. C C C C C C C < C ** OCe
- C f( .
M
- A %C C C C C C C" C
- CF C Lf '
M 3 C - N *** < V C "-- :* .~.-N -
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- C3 A 2 hf . . . . . . . . . . . . . . . . . . . . 3
,C Z gC C c CCC F E< H . c CC cCC g C C. C C
, c CC q g. < C. ., 4 p .C.
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= .?
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.- V C C CCCCCCC C CCCCCC,CCCC .
q t/ t' C C .C C C e C C Lf 4 , I C - t\ t* < tf C C C C C - f C e 6 F F F
- k *- -
H U= . . . . . . e e e . e . . . . e . . . . e C C CC CCCCC C C c. C o, C t\ C 0 cc I [' C C. C C C C. C (f - C - t* t\ C < ( 2 e (\ t' < U C t' C 4 - tf - i .
<f H ,= - N t\c &
- f V7 "I 2 7 7 7 2 Z 7 2 2 ;
W C k. C W tat c ta.' C W C W C Lu C W C W o e .' U - U .- U .C- Otoi-C. U - U - U - U e-. U - U - U -
- 2. H I P- 2 >- 2 H' 2 P- 2 >= E >- 2 >- % > 2 H E H
. t
< U .2 < <r < < <r <r < .c < er < < < < < < < < < a .
> 's e- > >- > >- > H > H > >- > >- > F- > k- > >- > '
- V O t/ ta.,_V-tu V. '.
a ts-V rLa.- VaLL- VaLA.-_. - -tr. LA Va-a k V L. V tu . Slit
TABLE 3.3-2 ANNUAL AVERACE RELATIVE RADIONUCLIDE CONCENTRATION (x/OI org,r1%rs ran*,geensso, _ M I'EC4Y. te*F P, r yro , , _ , , gl rnoorttrii Form nores Troo. s.; eecc g amesse a v ine. _ a wp u t. Avro ne.r c t fn g a:r, f- e rro ct. r:.) . . n e s t ".cr J os .g tr . .,, , _,,_ _ _ _ , . , . _ _ . . . . . . . _ . . _ trr700 ,7ea ,cai ,7ea t.e-- t,e*1 7.n a p cnn 1.aco 1.cea 4,noo 4.*n9 s 2,s==r.-o 1,4. mc.c-; s 3, s .1r- 3.s 2,3;.-e.** 3 ,s .t; . 7 g ,
- g ir. . , 3,t w -gy.y.nn,eE. y 5,9?7E ** 4,s.>7r no 3,74cr-o1
%SM got ne- M o.a v .c.c.g 3,M),r.eJ 3, r 4 3 r.r 1 3,*,te.r- g ,*7 r.se 3 , n 4 9 r. p .g g,'0*F-91 S.osEr Ca s,77?f-90 4.*^9'-19 Sw 1,4 t >c ao * . 4 )*r
- 9 5,981 -as I . , 3 ir .. . e,.ea,- s, g ,73,.7 9,ganr.co 7,cosE-in 1,cale .ie 7,nspr.ae 7,11tr-em
__ _ mest? 7 -e A,Aeit as A.,gr.ce x , i o . ,, % saar-3g .o. >0
, ...?74r an t.,?t.er .
- 9E-0 9 .4. 0 28.E-C 7
- e. ,.....r .. ..r.,1 s......-s ....<.,,..,,,, .e ,...,,.,7 . . . o,-n ? 3. 024E-2
. . ,. s 77 7,.1*4r-3
.s, -o, 7. ,t .93E F-n 7-
.,t,,. ,
9.e+ o.ocar .,- e,*tx e 7,A 1 -r* 7,i'ar.*n s.,s.ae.s.r- e,saar -e ',c )4r-as 1,40'E 17 ?.e73g.37 p. g .3 7 r-n 7 1. 7 7;.*m0 7
, , , . _, ., Mw , t 324r.*: v >aar-;e :,elsr -* . . . or . . s *
,se. .i. e..ig is : ,4 3 - , ..e 2, v ,.r s - ?,ng.r.;7 3,st75 97 1,75cr.ov Nms 1. poor se 4.eeer 7 2, s.- se-a 7 3 ,. v wr. .;v 3 ,53>r .7 4,4s t r.a s v,1 *sr-n e c =9 Ar-.-* s . vu t t.g a 2.gasr-37 1,761r-n7 N A,737r-no 1,OA7r-re C,7 3Ar-ne s,)sar.ae 1,ca>r 9b 3 gsir.iv o,%4Ar-pe 6, nos r..i s 5,14t[-no ,,1epr-c4 1,77dr-na
._ ,_ ?Ptr ,, m,=47c ac tot 34r -e,5,4str.g7 2,iorr-37 g,ei,s.); s,37pr an 1,egpr.og .,7,ss3r.gs g, cert-3e t,gger-ge 3,754r_on, p.r 3,osar.-= 2.,73r .5 3 , n i e r ,,, 4,s,...y 3, ,r 3
.f... 57c.c. t ,,is7c.nn 4 ,sogg- o 1.21ag-ns y,sgir-no p nonr_qq r.;r : ,1ase.g r e,o s pe- m s , v. > -a, 3, s .. ir ,.$ v,-r.,.<-ry .:.pe_.7 2,s y nc-c 7 g,74 t ,.,3,137c-nv 3 nspr c7 q,ptar gm r c . 74. ir e 7 e,iAsc -A 2.s i re - s.:. 3,,..Ar.. s,, .--rr s.,isc.-7 t,cepr.or i,1 sir.cv .*,-7pr .1: e 7c7c *in s,c7ar-Ga rsr 7,7cre r ? i,sser.54 2,oss.r_sa 2, ~.c in 4,,e..-y 4,apAr.a7 1,nryr ny 7.3 par.37 3,s7pg.n7 1,72nc-07 o.a037-09 sr 1,21sr.no 7.e.7 7r . .7 a:,4 cec-na e,cmir :.s 4 ave y s,sa9r-n? 1,7sAr-07 2,7arr.n? g,te,.c.av g,t:1r n7 t,noor-or t..,. yr_ ,,, __ 7,segr ao 3,ocar-3e,c,1ne. -7s p,c>vr.. s,a,.c.-, e . ,1 F- 2 7 .3.2500-0 7_2.249E-3 7 1. 566E- 3 7 1.20SE-0 7. 1,04 3rr n 7.
awrtsat, avroar.r cur fo stref r er s . ,rsrea ,, , , t .
- e t t -s
- t e, r q PE spINr. %,91e 7,4a3 g a , n == g e ,1s.s 3. , - a r, .. , n e, r 3g,gp0 19.000 60,80G As.nne cq,1on
. . . , 4 1.tn'r a* 1.* t *:r .,e t'9 , sir. = 4, .. ar- ye n . e,.u . r. . 1.litr.So 7,441r.09.1.995E-01 1.476E-e1 I.aier.ng,1.754r-no ss'* 4,tner.-o 7,c,4r -9 s,siir. 9 i , .. *r . 1 s , ..... 3, aue.;o 1,7%6r.04 3.nigr_p a,se rg-3 , 7,6vor-i n A,sa4r-t o sw 3,osar ae 3, as 7c.. e s,os er-w s , .v g r.co 3, . g a., . * , ., p a r _ -o e, spir.no 3.129r-ca 3.in..r-33 o,s,or.gc a, spar-in ws, 3,Asur i7 w,cser. a 5,s. s w... i,3,sr.ag i, , v.e . ... ,,-syr... y ,3, e.r-c e 3,asar-Se a. sine e 7,ssir-co 6,A64 -09 w t,7cor-s= g, vor-se s,ossr a. 1, s i w e.. ,,1ur - i,4 g psy. ae 3,17se-09 I,tPar-9e 9, sear.ni notanr.no 7,97ne-09 w*e .* 1,4 ace a7 7,srAr-e.e g,9r.rir.no 7. x4r tm 1,oser ae 3..%er *:e 1.14tr-09 9,170r ^o 7.*77E-n* 5.'7tir-go s,esir-o9 Pcf 3.asar.97 c.147r ,,e 1,4gst.cn p,nair am 3,.e.or.ct 3,3ngr gq y,9790-09_6.413E-31 5.1^9E- U 4.solr.09 3,993r-09.
__ , **=w t ,471r
- 7 7,7 ele-ce 5.967c-ga p,.a1%r e.e 3.. nee-o I,.anr.ee 3 gn0r.on 9,A47F-co e,3por,.32 4,osor n9 4,nygr.no N 1,1iFr-na 1.samr-44 t 75?r.e. 7.3,.7r.io s,11-e.a9 1, gor. o y,p=9r-oq p.11 or-So I ,o7Ar ao I,r.str-no 1,472r.nq g%r 3.caae.co s,cete-ro 1,=asc.n1 p,.ptr-So e,17tr.nv 3..i g re. ;1 7,eg%r.39 a,yogr.19 i.'27E-la 4.cier en 3,933r-go mer 3,724r-ge o,*cor-r o s,o vsr.ao 3,se ar. no 3,,ctr-nv I . Faar ao 3.14Ar.04 1.11 1 E-f.o 7,astr-gn 6,000r-10 FNr 4,707r no 1.scre.re 2,zaoc.e4 3 i er r.a e, st gr 99 A. sor.so s 34gr-09 4 s.apr.g, ".3.<gsr-30 291E-le 1.enor-no ? A20r-n9 -
l r 4,3%2c.no 7,tspr -g g,1 swr-no 7,.ssr-io s, seas.m4 1,*1 Ar-n o 1.0% AE-O s_ P.4 a*E-n1 2.?*aE-;1 I.TT9E-n9 1.s4;r-09. __ _ rsr , go i n Sr.e.. 4.setr.-m 2 ssgr as 3,miar.** t,-v.r-nk 7,,str.eq c,oatr nw 4,*41E-97 *,nA7E-41 1,47ar-90 3,n23r.n9
$r 9,eair.re A,Caor-%p p,o7Ar.aJ ),794r.Me g,gmar.gg 4,%21r.99 4.7%cr.no s.4oqr.io e,AQi(-Go 1,017r.4o 1,62%r-10
, $$r 4,%1Ar.ae * ,4&sr me 7,ongr.q4 g,4.esr.44 g,ggnfora e air.,90 p,vfyr-Q4 C, suer.c o 4, s, g ir- g.a 1,oAir.no 1,4c 7r-p9 1 '.
i 14
I TABLE 3.3-3 DECAYED RELATIVE RADIkNUCLIDE CONCENTRATION (x/0e ,c) ertretr ro.T* LSco-o. 2.260 nay orrev. .egerstrerg .. , , __cooprCtro rno noen vroce sn orcipress avle s _ l3 i a.mtml Avroar.r rutfa terrr eerr. ew.rns nerf W r t e : Sit.re _ . - - - - - - . -
%FC700 7ct ,c9 ,vsr 3,ne a e,e r f , r r.
- 7,sq0
. . . _ . . - _1.n00 1.s00 4,0no 4.sno 5 S.l'ir *' 1.4'*r -e 3;tstr ae p, ss g r . m e,vsvt.-7 3,ta9r av g.17&r-07 7.79er.ae s.viiE-O' 4.ssor.n o 1,a24r-ce sss 3,gsnr.ao a case -o e,eisa.13 g,e.pr.se e,.7 . <-ig 1.75ar .-' t,07wr-On q,137r.90 6.77ag.co e,An7r.co 4,visr.c9 sw 1,4ter.ao e.sovr -9 3,es/r-na 3, e s pr. e 3,essr.r. 3,ealr.ea e,o17r.co 7,411E..to 3,s77E-03 7.757E.ge 7.735r-08 wsw 7.17 tr r:s %,7s cr ca s ,s ur . a 4, 3 7.c e, e s , ,4 : s . a u 4,ys tr.aa o,c73C-0
- 3.91*E-0 7 2.451E-3 7 2.3350-07 1,972r-07.-
w a,4*ar ac 1,.ner ee 4,ma . -s s,essr.-e s,,q-r.3. .. star aa 1,45Ar-n7 4,40*E-n? 1.277r-o* 7,essr.n7 7 c=7r.n7 www o, cope ca e .* s vr-r * ?, ae.. . 1 r.,-Fr. a a , s. 3 -c.a - s, icr.r - a g,s>9r-na 1.715r-97 7.75,r-nv p.gstr-n7 1,77sr.g7 Nw 3,37se ee 7.sege.-= o, s s t e *. e,onar ee 7,iser -p m 7tcr.7a 4,u99r-ce 7,aapr.37 3 savg-17 3.s>4r-17 1,726e-17 New 1,2aie.am 4, irr -* 7,misr -7 3,eaar.4r 3,>vse-57 o, cer.ae 1,74nr-04 s vpar-a= 4,*6cr-n* 7.gnar-n7 1,7 tor-ny N a,73r en i.oscr-,e s,7.scr c i s ,nsar- y 1 ,cear.o. t . iwr .-7 o,423r-04 6.77'E-p* 5.'**E-'8 '.?'or-po 1,45sr-Ga unr a,gior ao totair-rA s,9.,ar a7 7,.iar.37 g,.1.r ,y 4..siir_-1 3.74%r-04 2.Al?E-ci 3.oS'E-0* g.*)7r.o t,733r-CA - . wr 7,o*7r aa ?, a?r.ea e,qar ag s,vaar- 7 f . ' 8"8 a 7 4..<7e-T* *.oror-no 4.337r-ae 1.g6sE no 7,6*7r-aa 2,aost-09 rnr c,S.s ar - , e , m acc. .. g,g, r -S 7,ao pr . . e,g..-37 4 .q7e -7 s,csic.n7 1.7Ctr.a7 3.991E.07 4.**70 e= A.006r.ra r s,743r_rv r,igoc.,4 7,4 7,r- ,4 g,,-1r ;g 4,,7.. -r 7.s99r a7 t,capr.07 1.aFaE-e7 7.726E -= 6.l>4r-re 4,9csr.n= rsr 7,7cor ev 1,437r-34 7,ostr.
- 7,aier s6 .s .n s s, .a 7 s srce av 3, alar-07 7.noiE-1' 3.c61E-87 3.go4r-ov 4 c67r-no sr 3,31sr.a= 3 ,c ,se ,7 s ,12 e.sa 7,c ir r- .,4 . , ,i ar. i c.,3,>r.av '.*l3F-07 7.73cr-}7 3.4.cr-ov 3,797r.07 t.637r-p?
_ ssr 1,51re co i.e.,or-ge ,s,17 .r en 7 s s t r 49 o, v ise.n 7 c. 31=r a 7 3, g osr-0 7 2. 20 70-0 7 1.423E-17 1.7^2r-n7.1.nt3r-n?.._ l Am1:43. avrone.r c tfa a cer f*-r ero c.s sa s t **e e norr ey -.st re
- pr an t sr. s,sgs v cae gr,1-o t c.q .e e ,119 7*. . a a s 'a.$on 15,090 4a.*00 4%.ana cS. Con I
$ 2,oo m se e,c>or sn o;7,ar-se e,4*tr_no 1. cars .is 7,%7ar co 1,c sr-Oo.l.51oE-ao 1.?*FE-fa I.11?r.q1 n a79r-13 ...
sse 4 ssAr-se 9,sc$r o e,saar..a 7,,..;r_99 t , = .-r -n . 3 . t i t r .* S 3.ater-no n,gter-to A.s79r.ia e.. ,r ,in 4.cSar-13 Sw g,emor ce e,ersr -o a,( s*r.* s 1,- e ar_ , a 7, s.;nt .n.e 3.67sr a1 3,7sar-co o.nger.l.s 7,eyar-39 %,satr. $ c 19tr-11 wsw 3.ccer av e.sser ae s, t ile.! S.aanr .;a e,*svr..c. 3.insr.s* 1.*1tr-04 9.amar ao 6.974r ,11 s.131r-no s,cgsr.74 W 3.sopr c y p.Aise-
- 5,sisr-1* 1 **.o. -1m 7, r acr .t.-. 3,s71a.ag 1.g'lf-04 9,aAcr-99 7.707E-3' 4.2 $r se 5.sssr -4 wnw 1.47s a7 7.?ssr.en 4,agsc-14 7,ansr-34 3,71:s.9 t .spr.-i o,.7%r-09 7.c09r-60 S.12?E-02 5..taar ao 4.11sr *q NW 3.ngir.e7 s.ss*r-an 1,Pe r.;* I,*14r-pa 3,sa<r-o- a,n7gg-;o 8.s4SF-09 5.214E.Go 4.74tE-15 1.5'5E-39 2.96tF *9_.
__ unw t,csse sv 7.137c an a,aoir -e 7 n><r re 1. 7 u r e.4 t,2spr.-* o,671r.09 7,47cr-co 5 131E-qc 4.ovsr ,o 4,397r.ra
-e 3,312r se A,isor .go 4,3 7 pr-1 s 7.471r-13 .'.tmer-04 1.701r-ca 3.16sr-Oc g.l!7r ao 0,113r-is N 1,7ns -Se 3.*c7c wpr f.e14r.a* *.?ote-a9 1;1aar-;i g,e-Ag.14 3,st 7F-3; e, Tace.t a, 4,5=7r-10 5.g**E-19 6.70*E-11 3.4*er-ta 2.a*Sr-11 Mr f.A'7r-in
- asor. a c,se r. 3 1,gn4r-po ?,a1*F-19 3.as'r-93 3.nsor-Og 9.410r.te n.97cr-to E.741r si 4,asar-33
- Eyr A,4acr-94 1,icer-en p gsar-34 3, sear-1g y,n73r.q, s,n71r ec 4.776r-09 3.1erE-34 2 75'E-94 7.7sar. 9 3 ,9 3 3 r.3 9 F ,- 4.94-1 ** *.81sr-rm,3,popg..e 7,gsar-go 4 ao7t-0* .1. gear-02 7.550E-09.2.027E-09 1.'44E a9 I.16'E-t* 1.154r-ce .
Esr 7,emcc as ,1,o-or ee 7,st.r.-e 3, sage an o,,ase.... 6.sopr st C.33%r-04 1.057F -2 '.?llF-i* 7.**7F.mo 7,756r-;a Mr e,ss<r a= 4,1 car-se 2;741r.aa 3.ccir.ae 1,- 2 3 3 -
- 7,segr a= c cssr-co 4,1rng.co 1.941E 'e 7.317r ra 2.s76r.c3
, , _,. $sr e,tr.or_am a,*ser-se 7,7ser a 1,-igr.14 t,1s,r... r,gg ir -o e,s agr.00 4,11 E. , 3,e21c $s 7,ossr.as ?.4tHr-94 1 I
t TABLE 3.3-4 DECAYED Al8D DEPLETED RELATIVE EADIONUCLIDE CONCENTRATION (X/Od ee, depI - ortyssrs ron t,arsde.>. I a.nOO naY girr w . grosevrp __ , , ,
._conurrgrn rno oprw Tro;eg g.. ore g oes's,4 3 3*eas I
AN*fust, avrs'arr cieg fas s cref re rro eve'r*,3 9,t r e cr g. s g g,r<. . . _ , ,_ _.. _,, Krr700 ,>ca .ce t. 7cq 3.ar t s ,ci a /,nss 7.r.a n 1 n00 1.*00 4.nno a. Man
% 7. t ys. .a.3 1.sscr a p. g s tr.a. 2,13 q.., e 3 , ,.e g . .t y 3,74se r7 3 , g e w.0 7 7.4C'E-3* 4.As7E.2e 4.7aer.aq 3,15 =r.o .i
<%d 8.3 mar.ao o. rate -1 g,c1ir.as 3,c g sr . n 3,e yg. aa 3,3*gsc -a o,eopr-Oo 7.eScr-40 6 175E--10 C.? gor-no 4.so6r-ag 5d 3.4 t te-to a .417e-t o 3,ralr
- e 3,seve , e 3,este-en 3.61gr.a1 a.%94r-09 7.n7AC-10 1.643E-09 7.511r-ng ?,375r-nq ,l
,_, , . tesia 7. 3 71r ao 4.srsr-e n 4.4 tor.c at n sarr.u c spr-pe 4.13 er.0* o.173r-O't .3.92iE-O F 2.006E-9, 2.2csr-n7 1.P98r-07, is n.seir- u 3,si,ar..-= 4,7o7r ce g, a s pr. ..e 4. '706 1.* 4.soer an 1.4nAr.07 4.177E.o7 1.pl>E-97 7.c77r nv I.o70r.07 ww; o cose -o e, var -a 7,c t ir.ag 7, s e ,r . , a.svar-1a s.3asr a= o.gler-o= 1.vlar-c7 2.71sr 97 7.a36r.97 1.ne0r.nr
, _ we 3 i>4r ce 7.3 2 r -e 4,siir e g,vser.e5 7,esr4 c.*?or .= a,44'r.0m 2,4ctr nv 3 .os ar-.s v 3.astr-07 3.392r-n7
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TABLE 3.3-6 SPECIAL LOCATIONS (X/0) (X/Odec) (X/Odec , _dep) (D/o' Receptor Location (sec/mJ) (sec/mJ1 (sec/ma) (1/m4[ Malin House - 1300m. ENE 3.635E-06 3.620E-06 3.439E-06 2.671E-08 Malin Farm - 1060m. ENE* 1.995E-06 1.994E-06 1.905E-06 3.379E-08 Bluff - 600m. ENE 1.514E-05 1.511E-05 1.496E-05 1.010E-07 Roadside - 150m. ENE 6.157E-15 6.156E-15 6.157E-15 1.298E-15
- Joint frequency wind distribution data for spring and summer months used to generate (x/Q) values.
i 1 l l 18
- 1. The Malin farm - located 1300 m. ENE of the facility, and the associated pasture 1000 m. ENE.
- 2. The bluff 600 m. ENE of the facility. (This location is actually on the face of a cliff and would not be expected to be occupied during the term of plant operation.)
- 3. The roadside 150 m. ENE of the facility.
These three locations represent a) the highest offsite X/0 for a resi-dence in an unrestricted area which could be occupied, b) the highest offsite X/Q, and, c) the public highway which provides access to the plant. 3.4 Gaseous Source Terms - j During early 1977 the facility was operating with a fuel cladding condition which can be assumed to represent the highest off gas release rates which can be expected from future LACBWR operation. Additionally, during this period detailed measurements of actual releases of gaseous activity were made. 'For purposes of this calculation, it was assumed that these releases wo ontinua *hrqughout he year with the plant operating at a 50 percent capacity factor w h characterizes the plant factor cu tNE facility began commercial operation. The resulting source term based on this assumption is shown in Figure 3.4.1. 3.5 Dose Calculations Calc 21ation of doses was performed by use of the GASPAR(2) computer
- code developed by the Nuclear Regulatory Commission, and designed to evaluate doses to individuals and populations from atmospheric releases. In addition, gamma air dose rates close to the plant were evaluated using a finite plume model to check for sky shine.
3.5.1 Annual Air Doses Semi-Infinite Plume Model GASPAR calculates air gamma and air beta dose rates using a semi-infinite plume model. The model assumes receptor submersion in a plume of uniform concentration, which is semi-infinite in size, having as its only boundary, the ground plane. This medel proceeds 19
TABLE 3.4-1 SOURCE TERM for Individual Doses Nuclide Curies Released Gaseous Effluents KR-85M 1170. i KR-85 103. KR-87 782. KR-88 1852. KR-89 84. XE-131M 161. XE-133M 255. XE-133 12,340. XE-135M 42. XE-135 14,440. XE-107 585. XE-138 152. Radioiodines and Particulates I-131 0.0477 I-133 0.0413 SR-89 0.0170 SR-90 0.0012 , CS-134 0.0012 CS-137 0.0012 BA-140 0.0023 H-3 12.577 C-14 2.28 L 20 i
by calculating first, the relative radionuclide concentrations from atmospheric dispersion values as outlined by Regulatory Guide 1.111, and Equation (3.1) . The annual gamma air and beta air doses are then calculated using the calculational model found in Regulatory Guide 1.109 for the semi-infinite plume model: y D (r ,0) or 3D(r,0) = 3.17 x 104{Qi (x/Q)1 [DFGi or DFBi / (3.3) where, yD (r ,0) or gD(r,0) = gamma and beta air doses at the distance r, direction 0 (mrad /yr); Qi = release rate of radionuclide 1 (Ci/yr) ; DFGi or DFBi = gamma and beta air dose f actors as found in Table B-1 of Regulatory Guide 1.109 (mrad-m3/ pCi-yr); (X/Q) = the relative airborne concentration of' radio- ' nuclide i, corrected for radioactive decay in I transit to the receptor location (r,0) (sec/m3); and 3.17 x 104 = is the number of pCi per Ci divided by the number of seconds per year. Finite Plume Model The finite plume model calculates the dose rate due to direct ex-posure to gamma-emitting radionuclides from a non-infinite, non-uniform plume, assuming decay in transit, dispersion of the plume, l and attenuation of gamma energies due to absorption in air. The ! finite plume model calculates the direct gamma dose from the plume I using Equation (3.2) below, based upon the work of Gamertsfelder (1960). (See Reference 3). Note: No correction for recirculation has been included. l .- YD(R 1 0) = 0.2865 9 ,0fy LY1 + kI27 (3.2) , l i URO l where, i in a direction 0 yD(R,6) = the gamma) (mra /yr. ; dose rate at a distance R, 1 Va = the energy-absorption coefficient for gamma rays in air (1/m); Q = the source release rate (ci/yr); Ey = average gamma energy released at each disintegration (Mev/ dis); 1 21
u = mean value of the wind speed, corrected for wind speeds measured at a height different than the release point (m/sec); R = distance from the release point to the receptor location Un) ; O = direction of interest (radians) ; integrals which describe plume dispersion--depen- [Yi+ kIg7 = dont upon joint frequency distribution, the effec-tive stack height, the total gamma absorption coefficient, and the receptor coordinates. ' Table 3.5-l~ tabulates gamma and beta air dose rates calculated for the special locations mentioned in Section 3.3. The finite model was used to calculate the gamma air dose rate only at the roadside location, since at the other locations,. meteorological conditions submerge the receptor in the plume. 3.5.2 Maximum Individual Annual Dose to Tissue.from Noble' Gas Effluents The total body dose rate from external radiation assuming the atten-uation of 5 gr/cm2 of tissue, was calculated by GASPAR utilizing
~
thrfo~IT6wihg RegHiliitory Guide 1.109 model:
~
Dt(r,0) = Sy[(X/Q)i Qi DFBt (3.4) i I where, l Dt(r,0) = annual total body dose due to immersion in a semi- . infinite cloud, at the receptor location (r,0) Onrem/yr) ; includes DFB i=totalbodydosefactorforgetaradiationwhicg/pci-yr); the attentuation of 5 gr/cm of tissue (mram-m i (X/Q)1 = annual average ground-level concegtration of radionuclide i at the receptor location (sec/m )i and Sy = the dueattenuation to shie141ng factor that accounts provided for the by residential dose reduction structures (dimen-sionless). The skin dose rate from external radiation was calculated using GASPAR at a claculation depth of_1_mg/cm2_using the following Reg-ulatory Guide 1.109 model: Ds (r,0) = 1.11 Sp { (X/Q)1 Qi DFGi + { (X/Q) t Qi DPS i (3.5) where, Ds (r,0) = annual skin dose due to immersion in a semi-infinite cloud at the receptor location (mrem /yr); t qp
l.11 = average ratio of tissue to air energy absorption coefficients; and DFS i = beta skin dose factor, which includes the attenuation factor (mrem-m3/pci-yr) Table 3.5-2 shows total body and shin doses for an individual at the Malin farm house 1300m. ENE fro:a the plant. 3.5.3 Maximum Individual Annual Doses from Radiciodines, Radioactive Particulates, and Tritium Organ doses do to the release of radiciodines, radioactive particu-lates, and tritium were calculated for five pathways: ground con-tamination, vegetation, meat, cow milk, and inhalation using the GASPAR code. GASPAR incorporates the following models presented in Regulatory Guide 1.109 to calculate doses in eight organs: total body, gastro-intentinal tract, bone, liver, kidney, thyroid, lung, and skin. The annual dose rate to an organ resulting from direct exposure to contaminated ground plane is calculated using the open field. ground plane dose conversion factors for the skin and total body found in Regulatory Guide 1.109. The annual dose rate to all other organs is taken to be equivalent to tbs total body dose. The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model presented in Regula-tory Guide 1.109 estimates the transfer of radionuclides from the atmosphere for all radiciodines and particulate radionuclides, except tritium and carbon-14. The concentration of tritium in vegetation is calculated from its concentration in air surround-ing the vegetation. The concentration of carbon-14 in vegetation is calculated by assuming the carbon-14 is in its oxide form (CO t or CO 2
) and that its ratio to the natural carbon in the vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation. ,
l For radiciodines, deposition is computed only for that fraction of the effluent that is estimated to be elemental iodine. Measure-ments at operating facilities indicate that about half of the radiciodine emissions may be considered to be elemental. l Radionuclide concentration in milk is dependent upon the amount and contamination Irvel of feed consumed by the animal. Calculation ' of radionuclile concentrations in meat assumes similar parameters. The annual dose resulting from inholation of radionuclider is de-i pendent upon the concentration, in air, of each radionuclide. l l l l l l
. . _ . __ ._ 23 _ _ _
1 TABLE 3.5-1 GAMMA AIR AND BETA AIR DOSE RATES Receptor Location Calculational Model Dose Rate (mrad /yrj, Roadside - 150m. DE Finite Dy = 1.36 Roadside - 150m. DE Semi-infinite Dy = 1.37E-08 DS = 1.43E-08 Bluff - 600m. DE Semi-infinite D 32.1 Df w=32.4 ,.
/
Malin IMuse - 1300m. DE Semi-infinite D 7.4 , l
-l .-
Df == 7.4 t, ; ,'. * -
-c l
v l t l 4 24
TABLE 3.5-2 TOTAL BODY AND SKIN DOSE RATES Receptor Location Dose Rate (mram/yr) Malin House - 1300m. ENE Dt= 4.8 Ds = 10.6 ; 4 i t l 25
1 J a Table 3.5-3 presents dose rates to a receptor at the Malin farm f. , the organs and pathways described above, for each of the four age groups: adult, teenager, child and infant. Note that seasonal pathways (i.e., vegetables, cow milk, goat milk and meat) use (X/Q) values for the growing season only, from the field located 1000m.
, ENE from the LACBWR.
/
3.5.4 Population Doses Population dose ratas as computed by GASPAR are contained in Table 3.5-4. Site-specific data for population doses incorporates dif-forent usage factors for food consumption, etc., than those found in a GASPAR individual run. These values may be found in Regula-tory Guide 1.109.
, The source term used in calculation of population doses was actual 7 undscayed airborne releases from LACBWR during 1976. This gives a very conservative estimation of source strength and population dose y '). commitment. Future releases are expected to be substantially below this level due to the modifications to the gaseous waste
', storage tanks and the installation of an additional particulate The source term used for the population and charcoal filter.
dose is shown in Table 3.5-5. i l i L l i 26 - . _ _ _ _ - _ - . . . - _ _ _ - - - - - - - - _
TABLE 3.5-3 DOSE RATES DUE TO DEPOSITION OF RADIOIODINE, RADIOACTIVE PARTICULATES, TRITIUM Source Term: 1976 Releases from LACBWR Receptor Location: Malin Farm All Values in arem/yr* Age Ground Vegetable Cow Milk Meat Inhalation Total Adolt .0179 .246 .0352 .0138 .00293 .316
.0179 .533 1.65 .0689 .0754 2.35
$ Teen .0179 .320 .0496 .0106 .00302 401
.475 2.51 .0511 .0935 3;16
.0179 Child .0179 .567 .0h93 .0181 .00273 .695
.0179 .770 5'.17 .0801 .106 6.14 Infant .0179 --- .153 ---
.00144 .172
.0179 --- 12.5 --- .0966 12.6
- First line is total body, second line is thyroid e
TABLE 3.5-4 POPULATION DOSES Source Term: Actual 1976 releases from LACBWR 0-50 Mile Radius of LACBWR Total Body 2.81 man-rem /yr Thyroid 3.29 man-rem /yr Total United States Total Body 13.0 man-rem /yr Thyroid 19.3 man-rem /yr 9 0 4 28 :
TABLE 3.5-5 . SOURCE TERM for
//8'
/~
Population Doses Nuclide Curies Released Gaseous Effluents KR-85M 1928 KR-85 233 KR-87 11,597 KR-88 3427 KR-89 4149 XE-131M 933 XE-133M 215 XE-133 5075 XE-135M 19,166 XE-135 8365 XE-137 13,490 XE-138 55,025
/
Radioiodines and Particulates I-131 0.0477 I-133 0.0413 SR-89 0.0170 SR-90 0.0012 CS-134 0.0012 CS-137 0.0012 BA-140 0.0023 H-3 12.577 C-14 2.28
- 4. REFERENCES
- 1. "XOQDOQ Program For the Meteorological Evaluation of Routine Effluent Releases At Nuclear Power Plants,"
(XOQDOQ Code).
- 2. "Evaluation of Atmospheric Releases," (GASPAR Code).
- 3. Meteorology and Atomic Energy, 1968. U. S. Atomic Energy Commission, July 1968, page 350-5.
i l l l l l t 30
a , e EVALUATION OF LACBWR OFF-SITE DOSES DUE TO RADIONUCLlDE RELEASES IN LIQUID EFFLUENTS i Prepared for ; DAIRYLAND POWER COOPERATIVE By NUCLEAR ENERGY SERVICES, INC. Danbury, Connecticut 06810 I F i i I
TABLE OF CONTENTS Page
- 1. INTRODUCTION . . . . . . . . ..... .. . ... . . 1-1
- 2. CONCLUSIONS . . . . . . . . .... . .. . .. . . . 2-1
- 3. LIQUID EFFLUENT DOSE CALCULATIONS . . .. .... .. 3-1 3.1 Human Activities . . . ... .. . ... .. . 3-1 3.2 Liquid Source Term . . . .. .. . ... . . 3-1 3.3 Dose Calculations . . .. . . . .. ..... . 3-4 Maximum Indivtcual Dose . .. .... .. 3-4 3.3.1 3.3.2 Population Doses . ... . .. ... . .. 3-7 LIST OF TABLES SITE DATA . . . . . . . . .. .. .. .. ..... 3-2 3.1-1 SOURCE TERM . . . . . . . .. .. . . . ... ... 3-5 3.2-1 INDIVIDUAL DOSES . . . . .. .. .. . . ... .. 3-8 3.3-1 COST-BENEFIT ANALYSIS . . . ...... .. . . . .
3-9 3.3-2 AA
- 1. INTRODUCTION At the request of Dairyland Power Cooperative (DPC), Individual and Population doses due to radioactive material in liquid effluents have been calculated to demonstrate LACBWR's compliance with the requirements of 10 CFR 50, Appendix I. Calculations were performed using the equations and assumptions of Regulatory Guide 1.109 "Cal-culation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I" using data compiled in LACBWR's Radioactive Effluent
. Report and Environmental Monitoring Report for the cal end ar year 1976. This report presents the results of these calculations.
- l l
l l l l l l l l l 1-1
- 2. CONCLUSIONS Based upon the models used, the calculations performed here indicate that, for the operational year 1976, LACBWR has operated within the limits for design objectives of 10 CFR 50, Appendix I, Section II, A and D. Resulting population doses are extremely low, indicating that there are no cost beneficial modifications which can be made to the plant liquid waste treatment system. Using the 1976 releases as a source term for these calculations, the maximum individual doses were found to be:
, Location Dose Southern End of Thief Slough DT otal Body (Adult) = .728 mrem /yr.
DLiver (Adult) = .993 mrem /yr. These doses are well below the limits established by Appendix I to 10 CFR Part 50. l l e
- 3. LIQUID EFFLUENT DOSE CALCULATION 3.1 Human Activities Evaluation of doses to individuals and the population due to the release of radioactive material in liquid effluents requires con-siderable information which describes the pathways at and near the site by which the radioactivity released may make its way back to individuals. Described following are the parameters used in making dose calculations to individuals and populations.
Water Use Virtually all municipal water supplies for cities and towns along the river downstream from the site for a distance of at least 40 miles are obtained from ground water. The nearest major city using the Missicsippi as a source of water for municipal supply is Daven-port, Iowa, about 195 miles downstream from the reactor site. Accord-ing to a canvas made in June, 1962 by Dairyland, the only industrial use made of river water between the reactor site and Prairie du Chien, 40 miles downstream, is at the power plant below Lansing, Iowa. At this plant, river water is used for boiler feed and cooling purposes, but ground water is used for such purposes an showering and drinking. Parameters for Maximum Individual Dese Assessment In the calculation of doses to the maximum individuals exposed to liquid discharges from LACBWR, ~ usage factors given in Regulatory Guide 1.109 have been assumed in lieu of site-specific data. Doses I were calculated at the nearest location downstream from the plant for which the maximum individual might confine his aquatic activities. Site-specific data required to perform dose calculations on dose rates to individuals were assigned default values reference in Reg. Guide 1.109. All site-specific parameters input into the code may be found in Table 3.1-1. Parameters for Population Dose Assessment Calculations of population doses required the input of the site-specific data. These data represent the nearest centers of human settlements by which pathways are assumed to exist from LACBWR liquid radioactive r# Teases. Site-specific parameters for popula-tion dose assessments may be found in Table 3.1-1. 3.2 Liquid Source Term i The calculation of doses to individuals and populations required the input of a source term which accurately describes the radioactive In considering the dose effluents released into the environment. calculations for LACBWR, one source term was used.
.__m _ - . . .
3-1
TABLE 3.1-1 SITE DATA Population Distribution Adult .66 Teenager .14 Child .20 Reconcentration No reconcentration of cooling water. Worst Individual Locatien ? col No. 9; center of pc:1 for swimming a..i boating, end of Thief Slough for fishing. L* sage Fa::crs Regulatory Guide 1.109 - Values. Shorewidth Factor .2 River Dilution Flc.- 28,000 cfs (swimming & boating) 8,360 cfs (fishing) i Discharge Transit Time 0 hours Time to Drinking Water Intake 3 hours l I Population Don _e Sportfish liarvest 1.65 x 105 kg/yr (Pool No. 9 dilution and transit time assumed) 1 A
Commercial Harvest 6.63 x 105 kg/yr (Pool No. 9 dilution and transit time assumed) Sport Invertebrate Harvest No significant harvest Commercial Invertebrate No significant harvest Harvest Population Drinking Water McGregor, Iowa Population 1000 River Dilution Flow 32,310 cfs Transit Time 8 hours , D'avenport, Iowa ff5'&rdclAs Populngion 98,500 River Dilution-Ffow* 45,320'efs Tiansit Tim ( ~40 hourd Population Shoreline and No significant recreation Swinning Population Boating Location Pool No. 9 area River Dilucion Flow S,120 cfs i Transit Time 1 hour l 3-3
4 The source term used represents the actual 1976 releases from LACBWR, and may be found in Table 3.2-1. LACBWR had an approximate 50% plant capacity f actor during 1976. a 3.3 Dose Calculations Calculation-of doses was performed by use of the LADTAP (1) computer' code developed by the Nuclear Regulatory Commission, and designed to evaluate doses to individuals and populations from liquid releases. 3.3.1 Maximum Individual Dose Individual doses are calculated due to drinking potable water, eat-4
. ing aquatic foods, and shoreline recreation. The models used are described below.
Potable Water j organ doses resulting from the ingestion of water are calculated in ! LADTAP using the model found in Regulatory Guide 1.109: Rapj = 1100 MpUap[Qi Daipj exp(-li tp) (3.1) F where, Rap'a = the annual dose to organ j of an individual of age group a via pathway p (mrem /yr. ); at Mp = the chepoint mixing ratio (reciprocal of the dilution factor) of withdrawal of drinking water (dimensionless); Uap =rate a usage for an factor that specifies individual the exposure of age group time or a associated withintake path-way p, in hr/yr, 1/yr, or kg/yr; 3 F = the flow rate of the liquid effluent (ft /sec.); Qi = the release rate of nuclide 1 (Ci/yr.); l D,gp3 =nuclide the dose factor, specific i, pathway to a given p, the organ agecan j, which group be a,usedradio-to j 4 calculate the radiation dose from an intake of radionuclide, in mrem /pci, or from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem /hr) and the areal radionuclide concen-tration (in pCi/m2), 1 1 = the radionuclide decay constant of nuclide 1 (in hr~1); { l , tp = the average transit time.?or required for doses, internal nuclides t o to is reach the the point of exposure. total time elasped between release of the nuclides and ingestion of food or water (hrs.); and, t i i 3-4
a
~.
TABLE 3.2-1 SOURCE TERM Nuclide Curies / Year . , 56BA 140 012 , 38SR 89 .013 - 53I 131 .285 55CS 137 .857 55CS 134 .551 27CO 60 .381 27CO 53 3.070
. 0 '. 3 24CR 51
( .044 25MN 54 i 30"N 65 .047 33SR 90 .012 ' 1H 3 41.000 I . l l ( - w
1100 = the factor to convert from (Ci/yr)/(ft 3/sec.) to pCi/ liter. Aguatic Foods The concentrations of radionuclides in aquatic foods are assumed to be directly 'related to the concentrations of nuclides in water. The inclusion of the bioaccumulation factor, B io, in Equation ( 3.1) yields Equation (3.2), which is suitable for calculating the internal dose from consumption of aquatic foods. R apj=1100UaMo{Qi B ip D aipj exp(-Aipt ) (3.2) where, B the equilibrium bioaccumulation factor for nuclide i in ip = pathway p, expressed as the ratio of the concentration in biota (pci/kg) to the radionuclide concentration in water (in pCi/ liter) , (liters /kg) . All other parameters have been previously defined. Dose from Shereline Decosits The calculation of individual doses from shoreline deposits is com-plex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with suspended and de-cosited materials. An estimate of the radionuclide concentration in shoreline sediments can be obtained from the following expression: C 4, /1 - exp (- A itw L7 Cis " E c Ai (3.3) where, Cis = the concentration of nuclide in sediment (pci/kg); Ciw = the concentration of nuclide i in water adjacent to the sediment (pCi/ liter); ! K = an assumed transfer constant from water to sediment (liters /kg-hr); tb = the length of time the sediment is exposed to the con-taminated water, nominally 15 years (in hours); and li = the decay constant of nuclide i (hours). Ignoring the dose contribution from the radionuclides at depths be-low 2.5 cm, a model for "effective" surface contamination is developed: Si = 100 T iciw W 1 - exp(-A ti b) (3.4) \. %-p
where, . S = the "effective" surface contamination (pCi/m 2), t Ti = the radiological half-life of nuclide 1 (days); W = a shore-width factor that describes the geometry of the exposure; and 100 = equal to Kc 4Tl/kg-hr)
- 40 (kg/m 2)
- 24 (hr/ day)/0. 693,7 Shore-width factors represent the fraction of uhe dose from an infinite plane source that is estimated for these shoreline situations.
The combination of Equations (3.3) and (3.4) leads to Equation (3.5) below for calculation of radiation dose from exposure to shoreline sediments. UapMpW Rapj = 110,000 { Oii t l7 f,T-exp (+ Aib T D,ip) f,exp (- Aip t)7 (3.5) F. All factors in this equation have been previously defined. The maximum individual doses may be found !.n table 3.3-1. 3.3.2 Population Doses Population dose rates as computed by LADTAP are contained in Table 3.3-2. This table contains the cost-benefit analysis data as re-quired by Appendix I. Site-specific data for population doses in-corporates different usage factors for water consumption, etc., than
- those found in LADTAP individual dose assessment. These values may l
be found in Regulatory Guide 1.109. l t l l 3-7
.+
I TAllLl? 3. 3-1 INDIVIDUAI.IXM1S - 1 Skin Bone Liver T. Ikid y, Thyroid Kidney Lung GI - LLI
.0375 .332 .109 .0326 Adult .000318 .592 .993 .728 Teenager .00178 .599 .996 . 4 0!! .0333 .254 .128 .0236 Y
n
.000371 .741 .873 .160 .0504 .110 .100 .G0975 Child 0 .0237 .0228 .00427 .0731 .00137 .00285 .00123 Infant 6
TABLE 3.3-2 COST-BENEFIT ANALYSIS Man-Rara Dose Nuclide Total Body Thyroid 56BA 140 1.69E-05 0. 38SR 89 l .' 7 6E-0 4 0. 531 131 9.98E-04 5.07E-01 55CS 137 9.11E-01 0. 55CS 135 9.93E-01 0. 27CO 60 2.87E-03 0. 2700 55 7.9'I-33 0. 24CR 51 9.56I-:I 5.77E-08 25M:s 54 1.45E-34 0.
. 30ZN 65 5.llI-03 0.
I I 3SSR 90 2.87E-02 0. t lH 3 4.79E-03 4.79E-03 ! TOTAL 1.95E+00 5.12E-01 r l l i l iI . v
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l- 55W * .07 .07 .19 11.40 d * .__ _ . _ _ . _ _ _ . . _ . . - - _ _ . _ . _ _ _ _ _ _. 1
.o, .o, .11 9. y a w . .o1
. 35 r.3s !h
- j. l sw . .a7 .or .t9 ~ ' ~ ~ ~ ~ ~ ~ ~ "~
l
.37 66 .82 .2% f .~D 6 li.l C ~'~
p' Nd *
* .54
.19 54 94 1.17 19 .19 1.e4 17.75 [
o NNw 1
!. ; V/.R I A 3L E
- _ _ _ _ _ _ . _ . . _ _ _ . . _ _ _ _ . _ _ _ . _ _ . . . . _. _ ,
~
h,
;. l' j PtRCENT
- I,; i T OT tt
- 1.79 2.12 5.26 R.R3 5.30 3.81 79.64
.-j '~ ~ ' ~ ~
svG spFco . /.41 6.47 l o.42 ' is.04 ~~2 i '. i f ' ~ ~ ll'.W ~ ~~ ~i f . M - ~ , e p... . 4 PFRCENTAGL F R C OtlF t!C V DF cat *85 DI910lROTFD AROVE wtTH E S T A p t t. l T Y =. .__ 11_ _
$ v u t o a c a > l v.s . 770
'I pr.
t,i p .t ,q g dw .
- i. .i 6
ry e 4 9 J
",V S T r M os?f ~ '6 p' OpC E 4v l a OFFriiTIL PON I T OP I NG l f FUNDATF 01/17/79 PF9CENTEGE WINO FREOOFNCY DIST*4 t AOf tt1N ny Patoutti $ T ARit.l TY CL A M ,
- P
- Or.e a M *O 2 OJf GO *
. .~t
. .e..e..e..eee.e.e..ee....e....e....ee...ee....e..ee......eee.e.e..e..e.......ee..ee....e.e....e...e...........e.e...*.e...{*!
PM90tLL CI4S% -r
%ITE NAur. LACBwq STACK PERIOD OF 9ECO2n ol/01/TY (00:01: Tuou 07/01/r7 (00:018 't??t C 4 f tt Y S14pt' a
- SA00PD NO 5116?0004 STARILITY INST R9M"NT AT inn-WINO $1G'44 '
- .....................a.........a;...;..u....a..ua..,2a.aa..u.aa.s...........................................:
J. .,
;d
- winn SPEEO. tap 60._ PCar pat Evre aGL . _ _ _ _ _ _ _ _. ]'"
j* TOTAL SPEfp
.,4-T ntattif0N
- 9-3 3-12 13-19 10-24 > 24
'r;
- t. 5
.92 1.37 94 1.17 4.65 19.79
" N
- 07 .23 _ _ , _ _ _ _ _ , _ ,
-t F ,_ _ _ _ , _ _,__ _ _ _
- ENE *
- C * ! !
.07 .07 .15 72.7c CSS *
.03 .04 .03 .11 73.pa [.
m SF *
.54 4r .19 .19 1.92 17.15 "-~ ~ ~ ~ ~ ~ ~
* .11
~
!i
~ ~ S s t ~~ .07 .07 .23 l '~'.
4 54~~ e S~ . .07 n l' ? q ssa . v H sw . 7
. wsw 4 w .
3.99 dl 01 -~ ~~~ ~- ~
- WNw * ~.0) ~
.o i .11 9.to !j
' ~ ' ' ^w ~ ~~ * .oi
.63 11.22 NNd * .Oi .ts .15 .3s
'y . ,
. V aRl a t9L E
- _, _
- j. ;
p;
~ ~ ' " '
t
- t f, oc4CFMT f.5m TOTAL * .1% .34 1.64 2.16 1.M1 1.64
' ~ ~ ~ ~ ~ ~ ~ ' ~ ' ' '
'IE.52 ~ ( ;
- t v'; Spir n
- i.4R i.91 ~ io. id ' ' ~I V.fi ~ 'Ii. ii ' ~il. so p; q 3
- t a
't ,
STtAILITY = 00 H P"-LC ENT AGE F RL OO F racy OF cal
- S DI S T21. tit (O AROVE WI TH T !
4 ' i e valin 9: A91NGS . 195 .... - - - . . . . . - - . - - ,
. - . . - -- - . --- . --.-.-.. . .. .-... - .. . 1 I
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. ' ,,,_.%- - . . . e- -* .
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P ara cuNDATE 02/1F/79 OPC ENVIRONMENTAL NONITnFINF. SY$ fl 4 '7_'*I
'i
- P90'.R H NO 2 NAoJ DEoCFUTAGE wlND FQf 0ijf MCY DISTO I4Hil0N tiv P ASQOtt l STA9tt.ify CLASS k .
. .. _ - ~ . _ ~ _ . . ~ _ - _ _ _ . . . . ~
....................................................................e......................,......**.......e.....ee....ee. 8 a 4 . 4' -
PERino OF RECeRO 01/01/77 400:01 DHot; 07/01/7 7 (00:01) PMou t ti Ct AM SITF NAMF LACP.WR STACC StP070 Nd 51 %20004 STARILITY INSinOM9NTATl0N-WTNO SICMA TXTor.cty %Tf st a
.f
.t i.
..........a...........;;........;;..e;4..e.;..e.;;....;...s.;;;.;;..e;;.a...e......... 4.e............................... g ;. .' f. _ ,., 1.. !
- WIND SPEF0 tMPH) PFarF4T AVT F A".F
- 9-12 11-1R 19-74 > 24 TCTat SPrrn ,
.b ' D I4 ! C T 10N
- J-1 4-7 ,-
- . l*
. ......................................................................y..........,................... ,
* .03 .11 07 .11 .M 20.R% ,c
..,I Pa
. ___._.. ._ . ,ig f
NNr - . . . _ . . _ _ . . NE
- e ;-
, s. cNg e a
, t..l e . .__ . -_-_-_. 4 - eSe . s., Sr . 17.31
. 0 , 11 .1,1 .03 .11
- l 5 5.E _ _ _ _
- __
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, .) SW .. - _ _ . _ . . _ . _ _ _ _ _ . . . . _
,",) ,
> w *
.! 7 WNW *
; .. .u . p; i ;)
NNw . b 'I ~1 ! ' Y A'* I AU LE
- _ . _ ~ . . _ _ _ _ _ __
__ _ "i I PFRCENT i' ! a T *)T .s t
- 07 .23 .07 .15 .54 l .k ; ,
f.vG SI'F C p
- 10.66 16.4A 71. T3 77.70 19.AO
.. . 1. t
- - . - ~ . - - . _ - .
. ' , i
. J STABILITY . 00
+, P6Rf"NTAGC FC QOt'NCY OF (fL*S DISTD.IMHTEn A5l0VE WITH G ! .t
*' [' i "I Vit In pant NGS = 14 . ,
.J _ - . - _ - - . __ ._.. _.-... [ ,],
i { !" t
~
L. u lw
? -,
- _ _ _ _ _ . . _ _ _ ._ __ . . . _ _ - _ _ _ . . . _ . . . _ . _ . . _ _ ~ . - . g:}i m
r, d 6 Ar,9 ' ethnAf f 02/1 T/ Ta OPC FNVf50NMENTAL woNtToptNr, %YSTru nllal ocuCrttT V.F wtNo rpF')uSNCY DI S T R 10tJ T 11N 84 Y P A 50'1111 STABitITY Clo % l. r a v,n t at NJ 290600 r eeee,*eeeeeee. .e ..eee+eeee+++ ',; e e ertte e e b6 e e s . . . . . . . o . . . . . . . . . .. . . . . . . . . e . e e . . . e s s e s e . . . e . e e . . .e e e e era*oult! e e e eriass ee... 7) e e s!!E N AMr i Ar flW9 STAfK PERIOD or orc 000 01/01/ T7 (00:013 THau 07/01/7T (00:011 STAnttITY I PST ou'*r NT % T ION-w ltm % c,M A =
- sac 7AD N7 %13620 we .
- e. eeeeeee.seee **ene<<
eeeeeeeeeeee. s.
..e eeeeeeeeeeeeee+esee. ..eseeesesseeeeeeeeeeeeeeeeeeeeeeeeeeeereseeeeesesseeeeee wtND spiro quPHI PreCFMT ~~ P VE p ir,r ~ ~ ' '
~~
l 'i-75 ~' >~ 75 ~ 'foTAL SPrvD 0-4 4-7 3-17 11-19 ~ Ot>rCTION *
. ee+**ee**********************
- eeeee seeeeeeeeeeeeee.. eeeeeeeeee+eee*++eeeeeeeee++*eeeeeeeeeee*****
e 1.49 1.49 2.67 17.72 IT.0%
's . 1. 2 '7 1.?" ?.47 1 9 '+ 10.51
.5R .11 0*
NNE
- 41 .27 .39 A.R1
.47 .03 1.64 39 4T .2T Nr .
43 .31 .07 .11 1.25 12.69 ENE * .JT .73 1.29 7.00 45 . 91 .11 .11 I
~
* .39 3s 51 4.61 11.%7 1,,
. w- 94 .67 5 SF * .it 2.47 1.31 1.49 R.44 15.7a L -!
- 62 . 9 '. 1.51 77.71 1 T. 41 4.%1 s c. - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '
i 78 1.97 4.51 S.97 4.12
~~ i 3 . 51'~ ~ ' ~ ~
I sst
- 2.11 2.04 U60 .Sl fd5 s * .39 1.20 0.05 I
62 1.11 62 07 .03 7.60 , 55w * .99 03 1.49 9 64 _ _
.2T
.41 .07 W
- 45 .31 44 .1% .23 7.09 12.In {f, 'lq c,w e 73 .%4 .37 1%.n1 1.49 67 74 4.24 e .47 49 .51 3 .,
! w 2.00 1.17 1.21 T.P5 15.79
.TO .o9 1.57 f l .M 15.Wa I v4w
- 90 '7.3o 3.61 l ~. 94 ~2 . bi ,j j u 4 1.02 2.12 1 17 .R6 ft . 95 11.1o
- 1.41 1.17 7.05i Nw vAot etc.
.....ee......eeeeeeeeee.....eee ****ee.......eeeeee+ eeeeeees. ...eeeaee**eeeeeeeeee+*ee. Q e ~l t
rrorfMT - 21.72 26.66 14.17 15.00 100.00 TotAt
- 9.42 17.40 j
e
- 21. 12 lo.oA 14.12 7.41 6.JT to.Th 15.96 AV3 50". 9
- e -.---- - ---
J v 94 PERCENTAr.E FitOqfNCY OF cat *% DIST2T?toitP A'in Vc wtTH Att s T A st i t_ t T Y i ProCrNT VM 10 - 71.90 j v il 19 M F a n t1% - 7546
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d e *.== 1 e e i j e l l ai 6% 3 e - .
' - ** e j a"* C e t' C e K E h f'*. Psf A *) C =^ E >=grjC F #
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. . e l . .
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. vv4 e,
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e .C s !* > la C-I I _ . -_.___-.-.--y____-
= = * . e e ** s ;-_._?_._ ; . . _,___.___.!__*_ , ; ; l _ _ _ _'_:
_ _ _ _ .f . .t . _ ._ _.____- __* : . ; ;;.- - .4 .' i - - - . - . -.--.-_--
r _ . _ _ _ _ _ }
- v. - ,
"U '
4 S iO 4T : 02/20/Ta ODC FNvir oNM .NTit MaNITO.IN; sv5Ts u DE 4Cr NT AGF wtN0 rpE')9ENCY DYSTDIROTIM' 9Y P 4 5 0'I t t. t (T 4'it t l iv C' A st 2j! i
- M M rt F4 '4 ) 2902:00
_ _ _ . . . _ }; . y
..........................................................................................................................m 4
PE84100 0F PEC0e9 01/01/ F7 (001015 7"ou 01/01/ 7m I66~idil s't.so ui t'. "
. strE N4*E L4Ca p start
* $fX M D N') 513420.)14 ST Mit.tTV INSTA W NTATION-wtNO % I r.'4 A M10 F Airt Y UNST e RI L CtM T E ~ ]C
*l * . . . . . . . . . . .' h i, WIN 9 $pf t n t upiel PfarrNT avn a;- h
' rg
- 9000 y
4-7 o-17 13-18 19-24 > 24 . TOTAL "j n 9t2cCTIJN
- J-)
1.4 ' La
.................................e........... ..........e...... ...................................
4.%1 [q
** 1 * .'O 06 .16
.IJ .06 .07 04 36 7.49
+= NF * .14 _ . _ _ ,
t
** NF * .08 08 '.04 .20 6.47
- ewe *
.02- ,- ' 02 .04: '~24.9) ~ '
l[. > 6.6% n r * .06 .10 * .16 u r5F * .t:4 .t 6 .o9 .04 .0? .74 10.05 1.
. .to .07 .1? .04 0? 10 n. 69 [)
r si
.16 .06 .ns 42 54 10.04 .)
sa s%" * .12 .17 *
* .02 .10 40 .06 4R 4.94
~
46 7.14 ,' ) siw * .10 .no .14 .04 "j
- 06 .07 .06 .02 .16 T.64 ~~ '~
sd ~ j
* .n4 .on .on 02 .02 ./4 R.67 wsw
,- w . .c6 .06 .o9 .o4 .74 R.zt 2> l I
- www . .o4 .o? .04 .06 .16 9.7% ~~ ~
. Nw * .08 .04 .06 .07 alo 6.46 j "' i i
. wtw . .10 .06 .06 a22. 5 12 ,
* #*4 3 4%C * . . . . _ . . . _ _ _ . . ..
fl l l h u PsAcint '. , ,
.- TOTAL
- 1 15 .R4 1.41 .46 .16 .06.[ , 4 10 , .
[, . ~ f 4y
~'
. ~ ~ ~ ~
a vi %pE.iO
- 2.:5 5.99' 10.91 15.31 20.49 2(.5) '1.33
~'
; 7g d
- - - - ~ _ _ - ~
.s "F or ENi v.t m oltNC Y Or cat *S Ol5fttPOff0 A 90VF JITH R ST9Rit.tTV = .12 V' :.;
].
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.. ..---...=-==.--ww.
+.
(- w
,!~ -
f, 4 e 9. .,,
8f 1 L 4. 4 4 DUT)4 TE 0?/ ?9/ 7M DPC (NV I? ON84rW 4 L mr_'N f T C11 Ni $YSTr u DEM ENiaGE ' din 9 FREoiKMCY DIST 4 t aulION Av t'es091L L %T P. alt I T Y Ct. 8 55 rtX l'l} s PW.S M '41 2 b f.OJ ' !.
..........e..e...................e...............e..e.............e...ee.ee.e,..ee.e.e....
e.........e....,e.ee..e....e...7.,, P O 100 Cr pfCne0 J1/al/TF 600:01) Tmq 01/01/TB I41301) P .9 5:31t i t t. (1455 C **.-
*
- SITk N 4 *4" laCRwa % TACK
,*
- S A D J 'l O N 1 > 136!0024 %T ARil. liv Inst ope r4T r T t f1N-WI ND 51".4 4 St icH Tt y (JNstaet: Q
~ . , .
O . e . . e i e . . e' . . e . . e . . . . . e . . . e e . . . . . . . . . . . . . e ; . . . . . . r. . . .; . ; e . . . . . . . . . . ; . . ; . . . . . . . . e . . . . . . . . . . . . . . ; , . . e . e . e . . . , . . . . . . . . . . . . . ., i.
,c ofirrNT Avt D 40:
. wlw sorrn g=oul 10-74 'Sp(CD
" 9fitCTI H . 3-4 4-T a-12 11-ta 4 24 tnt AI
. ] . i'.,
{* e. . . . . e s s e . n e. e .e e e e e .+ .e. e. + e . s.o.e e s e e e e e.e e e e e e e e e e e e e e e e e..e.s e s e.e s.. e..e.e e e e e e e e s e. e e e.e e .e e 3
. 0 2. .42 5.14 d. )-
' ~4 * .!R .?? .10 46 9.14 l..
** T4F
- 06 ,J9 .12 .10 la 7 07. - 4. 2 b ; .. - w , ." ' . . ,
e
- , .24.s 14c' n %.g3 4:r~-
* < .12, .14( ~ -
v mM-p; s .x.N-r ^ NE ")
'C' S
f,,* r gg e ;3e. . o g, 4 __..f._. _. *_ 04- . D ? ._ _ _ . J i . ___ _. 0.2 10 -J.00 _ _ . _ _ _ _ _ , _ . , , , _ _ . , _ _ _ _ , _,
;c,i
.ng .oq .g7 . a ., 35 Ig.at ess .
.50 12.QR [ )
" Si * .10 06 .P9 .16 .04 .06 he
.14 10 .10 .10 .J1 .Q 4 11 .14
" %$: * ,. M b S * .18 .16 .34 .7R .04 1 00 10.16
. 70 - 10.39 P,' )
SSW a 36 .0A .26 .14 .04 .02
" %d * .16 .02 .16 .12 .06 . 92- 10.47 -
8.
" wiw * .op .12 .12 .th .14 .17 74 14.R7 30 44 1.45 19.01 ,," ')
" w * .10 .06 .J9 46
.74 .59 64 7.44 11.97 W4W * . *O .17 .24 '
++
Td ~ * .16 .16 .?9 .34 12 40 1 5T 1 T.70
. .12 .la .02 .04 .02 .50 9.It ., )
NT4 .12
~.
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,_N
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- s )
Yr
- r'2CCNT 17.17 # l
.. T3 fit
- 1.05 1.65 7.44 7.%R 1.(7 1.8$ .
t
- i. -
. 4) . %6 '1
'/f' 4 '.% ~i(58 ' 15.T6 2kd4 7P.40 13.66
.. . 'k Cf 5 3
ST4alLITY . . ? .) ,5..
*
- C N T *. r-E F5t t o JENCY t)F 0 t14 % OI 514 IRtiT 8 0 43 rive dtTH C ,
no
.1 604 I
.e V
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,i
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- 9 ti f t '. C'At* n vf 5, * % AD) iD N3 r ' 'a r,2 0N 4 STAnttITY i t.5 T D 'I P N T *, ' ' Drl-tJ N r s i r *a a t "itit AL
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