ML20153H389
| ML20153H389 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/30/1988 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20153G840 | List: |
| References | |
| PROC-880330, NUDOCS 8809090164 | |
| Download: ML20153H389 (22) | |
Text
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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL DATES OF REVISIONS Original ODCM 02/29/80*
Revision 1 04/15/80**
Revision 2 10/07/80**
Revision 3 11/03/80, 02/10/C1 04/08/81, 06/04/81**
Revision 4 11/22/82 (10/22/81, _
11/28/81, 04/29/828*)
Revision 5 10/21/82**
Revision 6 01/20/83**
Revision 7 03/23/03**
Revision 8 12/16/83**
Revision 9 03/07/84**
Revision 10 04/24/84**
Revision 11 08/21/84**
Revision 12 02/19/85**
\ Revision 13 12/02/85 Revisien 14 04/14/86 Revision 15 . 11/05/86***
Revision 16 01/16/87**
Revision 17 10/28/87**
Revision 18 01/05/88**
Revision 19 03/30/88**
A/ ,
Approvedbf 3/
_ _ Date RARC Chai . '
-o Approved by N d f Date T//3/7
~ Mansfer,RADCg
- Low Power license for Sequoyah unit 1
- RARC Meeting date -
- Date aporoved by RARC Chairman
""i' t*a 2' 225'e jsPigsggggggg PDh,
a SE0UOYAH NUCLEAR PLANT
}'
OFFSITE DOSE CALCULATION MANUAL ,
LIST OF TABLES REVISION 19 Page 1.1 EXPECTED ANNUAL ROUTINE GASEOUS RELEASES FROM ONE UNIT AT SEQUOYAH NUCLEAR PLANT 38 1.2 BASIC RADIONUCLIDE DATA 39 1.3 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 41 1.4 SQN - 0FFSITE RECEPTOR LOCATION DATA - 49 1.5 DOSE FACTORS FOR SUBMERSION IN ROBLE GASES 50 1.6 NUCLIDE SPECIFIC TRANSFER DATA 51 1.7 INTERNAL DOSE FACTORS - INFANT THYROID 53 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 54 g
2.1 INGESTION DOSE FACTORS 56 2.2 FISH CONCENTRATION FACTORS' 60 2.3 RECREATION DOSE FACTORS 62 2.4 PUBLIC WATER SUPPLY INFORMATION 66 2.5 FISH HARVEST DATA 67 2.6 RECREATION USAGE DATA 68 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORNG PROGRAM 69 3.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING 73 3.3 SEQUOYAH NUCLEAR PLANT THERM 0 LUMINESCENT DOSIMETER 75 LOCATIONS 3.4 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 77 p TOC - 3 1157c
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I SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES REVISION 19 Page 1.1 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 79 1.2 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 80 1.3 CASE 0VS RADWASTE TREATMENT SYSTEM 81 3.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN 82 1 MILE OF PLANT 3.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN 83 1 TO 5 MILES OF PLANT 3.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - 84 GREATER THAN 5 MILES OF PLANT i
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- SQN ODCM Page 35 of 85 Revision 19
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3.0 Radiolotical Environmental Monitorint 3.1 Monitorins Pronram An environmental radiological monitoring program shall be conducted in accordance with Technical' Specification 3.12.1. The monitoring program described in Tables 3.1, 3.2, and 3.3, and in Figures 3.1, 3.2 and 3.3 shall be conducted. Results of this program shall be l reported in accordance with Technical Specifications 6.9.1.6 and 6.9.1.7.
The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which sanples of air particulates and atmospheric radioiodine shall be collected. ,
The terrestrial monitoring program shall consist of the collection of vegetation, milk, soil, ground water, drinking water, and food l erops. In addition, direct gamma raciation levels will be measured in the vicinity of the plant.
The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.
Deviatione are permitted from the raquired sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prict to the end of the next sampling period.
3.2 Detection Carabilities Analytical techniques shall be such that the detection capabilities listed in Table 3.4 are achieved.
3.3 Interlaboratory Comparison Program Analyses shall be performed on' radioactive materials supplied an part of an Interlaboratory comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annval Radiological Environmental Operating Report (or the EPA program code designation may be provided).
If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Opprating Report.
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s' Page 49 of 85 Revision 19 Table 1.4 SQN - 0FFSITE RECEPTOR LOCATION DATA DIST ELEV x/Q D/Q POINT SECTOR (m) (m) (s/m s)
(1/m8 L 1 Land Site Boundary N 950 -6. 5.12E-06 1.29E-08 2 Land Site Boundary NNE 2260 -6 1.93E-06 5.28E-09 3 Land Site Boundary NE 1910 -6. 2.32E-06 6.33E-09 4 Land Site Boundary ENE 1680 -6. 1.12E-06 2.64E-09 i 5 Land Site Boundary E 1570 -6. 7.10E-07 1.46E-09 6 Land Site Boundary ESE 1460 -6. 7.91E-07 1.58E-09 7 Land Site Boundary SE 1460 -6. 9.14E-07 2.41E-09 8 Land Site Boundary SSE 1550 -6. 1.34E-06 3.23E-09 9 Land Site Boundary S 1570 -6. 2.37E-06 4.18E-09 10 Land Site Boundary
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SSW 1840 -6. 4.51E-06 9.26E-09 11 Land Site Boundary SW 2470 -6. 1.38E-06 2.63E-09 12 Land Site Boundary WSW 910 -6. 2.93E-06 3.86E-09 13 Land Site Boundary W 670 -6 3.63E-06 3.74E-09 14 Land Site Boundary WNW 660 -6. 2.49E-06 2.44E-09 15 Land Site Boundary NW 660 -6. 2.25E-06 3.67E-09 16 Land Site Boundary NNW 730 -6. 3.95E-06 17 Resident N 1370 0.
0.
2.93E-06 1.49E-06 6.59E-09l 7.10E-09 3.88E-09 18 Resident NNE 2710 g
19 Resident, Garden NE 2140 15. 1.98E-06 5.21E-09l 20 Resident ENE 2290 0. 7.13E-07 1.57E-09 21 Resident E 1790 8. $.85E-07 1.18E-09 22 Resident ESE 1790 46. 5.86E-07 1.14E-09 23 Resident SE 1680 0. 7.42E-07 1.92E-09 24 Resident, Garden SSE 2210 46. 7.99E-07 1.79E-09 25 Resident S 2020 0. 1.65E-06 2.75E-09 26 Resident, Garden SSW 2290 0. 3.31E-06 6.38E-09 27 Resident SW 3010 0. 1.04E-06 1.88E-09 28 Resident WSW 1140 8. 2.09E-06 2.67E-09 29 Resident W 1750 47. 8.53E-07 7.82E-10 30 Resident, Garden WNW 1750 12. 5.71E-07 4.98E-10 31 Resident NW 1140 11. 1.25E-06 1.50E-09 32 Resident, Garden NNW ,
800 0. 3.42E-06 5.67E-09 33 Garden N 1680 0, 2.20E-06 5.10E-09 34 Garden NNE 3010 0. 1.28E-06 3.24E-09 35 Garden E 2630 9. 3.38E-07 6.14E-10 36 Garden ESE 1980 29. 5.08E-07 9.57E-10 37 Garden SE 3010 47. 3.19E-07 7.16E-10 38 Garden S 2290 0. 1.38E-06 2.22E-09 39 Garden SW 3660 24. 7.96E-07 1.34E-09 40 Carden WSW 1680 0. 1.16E-06 1.43E-09 41 Garden W 1830 . O. 8.02E-07 7.26E-10 42 Garden .* NW 1180 11 1.19E-06 1.42E-09 43 Milk Cow Adult N 4120 0; 6.18E-07 1.10E-09 44 Milk Cow Adult NE 6750 47, 3,94E-07 7.03E-10 45 Milk Cow Adult WNW 1750 12. 5.71E-07 4.98E-10 46 Milk Cow Adult NW 1980 5. 5.61E-07 6.09E-10
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TABLE 3.1 (Sheet 1 of 4)
RADIOLOGICAL ENVIRONMENTAL PONITORING P90GR$
Exposure Pathway Sangling and Type and frequency and/or Sample Sample tocations* Collection Frequency of Ar.alysis
- 1. AIRBORNE
- a. Particulates 4 samples fran locations Continuous sarnpler Analyze for gross beta (in different sector *) at operation with sapple radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or near the site boundary collection once per following filter change.
(LM 2, 3, 4, and 5) 7 days (more frequently Perform gasuna Isotopic if required by dust analysis on each sample loading) if gross beta > 10 times yearly mean of control sample.
- Composite at least once per 31 l days (by location for gansna scan) 4 sanples from conmunities approximately 6-10 elles distance from the plant (PM 2, 3, 8, and 9) -
- 4. samples from control locations greater than 10 miles from the plant
( M 1, 2, 3, and 4)
Continuous sampler 181 1 at least once per
- b. Radiolodine 5 spies from same locations as air particulates operation with filter 7 days collection once per 7 days
- c. Soil Sanples from same locations Once per year Gaiuna scan, 8 %r, '%r as air particulates once each year l
- 2. DIRECT RADIAIION 2 or more dosimeters placed Dnce per 92 days Gansas dose at least at 11 of the air particulate once per 92 days sampling stations (LM-3, LM-4, LM-5. PM-2, PM-3, PM-8, PM-9 RM-1, M-2, M-3, and RM-4) 2 or more dosiseters placed at each of at least 30 other .
locations.
(Figures 3.1, 3.2, and 3.3) l 5 UE-
- 5 angle locations are listed in Tables 3.2 and 3.3 and shown or. figures 3.1, 3.2, and 3.3. M Y .,
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TABLE 3.1 (Sheet 2 of 4) 6 RADIOLOGICAL ENVIR0 MENTAL MONITORING PROGRM Exposure Pathway Sampling and Type and Irequency and/or Sample 5mple Locations
- Collection Frequency of Analysis
- 3. IMILIt90RNE
- a. Surface TRM 497.0 Collected b automatic Gansna scan of each TRrt 483.4 sequential- ype sampler" composite sample. l Tart 473.2 with caposite smspies ite for trittism collected over a period ana ysis at least of $ 32 days once per 92 days
- b. Ground Ismpleadjacentto At least once per 92 Gross beta, gauna scan
, plant (location W 6) days and tritlun analysis at least once per 92 days
- I saple fross ground water source upgradient '
- c. Drinking I sasple at the first Collected by autosnatic Gross beta and gauna potable surface water sequential-type s ler" scan of each composite supply downstrean frose with composite sm p e sagele. Composite for the plant (IRrt 4f3.0) collected over a period trillism, * *Sr. *o$r at least of 5 31 days once per 12 days I sample at the next 2 Grab smsple orce per 31 downstrean potable surface days water Iters (greater than 10 les downstremn)
(TRrt 470.5 and 465.3) l 2 sangles at control Samples collected by locattons (TRrt 497.0 autoniatic sequential-and TRet 503.8) type sangler with composite gangle collected over a peruod of 5 31 days
- d. Sedinient inr14%.5 At least once per 184 Gmuna scan of each l TRrl 483.4 days sample Tiut 480.8
- TIWI 412.8 l "Sample locations are Ilsted in Tables 3.2 and 3.3 and shown on figures 3.1, 3.2 and 3.3.
"Sayles shall be collected by collecting an allquot at intervals not exceeding I hours. l E ?E .
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TABLE 3.1 (Sheet 3 of 4) -
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Esposure Pathway Sampling and Type and Frequency and/or Smyle Sample locations
- Collection Frequency of Analysis
- t. Shoreline im 485 At least once per 104 Gansna scan of each Sediment Im 478 days sample TM 411 4,. INGE5 TION
- a. Milk I smple from milk producing At least once per 15 days Ganna isotopic and animals in each of 1-3 areas ml analysts of each '
l indicated by the cow census sample. * *5r, so5r once there doses are calculated per quarter to be highest. If samples are not available from a milk animal location, doses to that area will be estimatedbyprojecting the doses from concentrations detected in milk from other sectors or by sampling vegetation where milk is not available (Table 3.1, 4.d) '
At least I sample from a .
control location.
- b. Fish t saple each for Nickajack, At least once per 184 Gansna scan on edible Jtickamauga, and Watts Bar days. One sample of portion Reservoirs each of the following ,
species:
Channel Catfish Crappie
- l ,,,.
5mallmouth Buffalo ajQ-
- 5 ample locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2, and 3.3. D X o
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TABLE 3.s (Sheet 4 of 4) .,
RADI0toGICAL twin 0NMENTAL MONITORING PROGIM Esposure Pathway Sangling and Type and frequency and/or Sanele Sample tocations* Collection Frequency of Analysis
- c. Invertebrates TM 4%.5 At least once per Gauna scan on edible (Asiatic Cimes) IM 483.4 184 days. portion TM 480.8
- d. food Products I sample each of principal At least once per 365 Gauna scan on edible food products grown at days at time of portion private gardens and/or harvest. The types farias in the lesnediate of foods available vicinity of the plant. for sany11pg will vary.
Following is a list of typical foods which may be available:
- Cabbage and/or Lettuce Corn Greeh Seans ' '
Potatoes Tomatoes
- e. Vegetation I sangle from up to three At least once per 31 days Gmina scan at least locations of allk-producing once per 31 days.
animals where a sample of 5r and 'esr allk is not available and analysis and least at each air particulate once per 92 days station
- 5m ple locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2, and 3.3.
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, s SQN ODCM Page .73 of 85 Revision 19 TABLE 3.2 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I)
Location Distance or Samples.
Number _,a Station Sector (Miles) Control (C) Collectedb 2 LM-2 N 0.8 I AP, CF, S. V 3 LM-3 SSW 1.2 I AP, CF, S. V 4 LM-4 NE 1.5 I AP, CF, S. V 5 LM-5 NNE 1.8 I AP, CF, S. V 7 PM-2 SW 3.8 I AP, CF, S. V 8 PM-3 W 5.6 I AP, CF, S. V 9 PM-8 SSW 8.7 I AP, CF, S. V 10 PM-9 WSW 2.6 I AP, CF, S. V 11 RM-1 SW 16.7 C AP, CF, S. V g 12 RM-2 NNE 17.8 C AP, CF, S. V 13 RM-3 ESE 11.3 C AP, CF, S. V 14 RM-4 WNW 18.9 C AP, CF, S. V 15 Fam B NE 43.0 C M, V 16 Farm C NE 16.0 C M, V 17 Farm S NNE 12.0 C M, V 18 Fam J WWW 1.1 I M. V 19 Farm HW NW 1.2 I M, V, WC 20 Fam EM N 2.6 I V 21 Farm Br SSW 2.2 I V 24 Well No. 6 NME 0.15 I W 31 TRMd 473.0 -- 11.5e I PW (C.F. Industries) 32 TRM 470.5 -- 14.0e I pw (E.1. DuPont) -
33 TRM 465.3 -- 19.28 I PW (Chattanooga) 34 TRM 497.0 -- 12.58 Cd SW 35 TRM 503.8 -- 19.38 C PW (Dayton) 36 TRM 496.5 -- 12.08 C CL, SD 37 TRM 485.0 -- 0.58 C SS 38 TRM 483.4 -- 1.le I CL, SD, SW 39 TRM 480.8 -- 3.7e I CL, SD 40 TRM 4 77.0 -- 7.58 I SS 41 TRM 473.2 -- 11.38 I SW 42 TRM 472.8 -- 11.7* I SD 44 TRM 478.8 -- 6.5* I SS
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SQN ODCM Page.74 of 85 Revision 19 TABLE 3.2 (Continued)
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I)
Location Distance or Samples Number a Station Sector (Miles) Control (C) Colle'etedb 45 TRM 425-471 -- --
I F (Nickajack Reservoir) 46 TRM 471-530 -- --
I F (Chickamauga Reservoir) 47 TRM 530-602 -- --
C F (Watts Bar Reservoir) i
- a. See figures 3.1, 3.2, and 3.3
- b. Sample Codes AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish M = Milk PW = Public water R = Rainwater
. S = Soil SD = Sediment '
SS = Shoreline sediment SW = Surface water Y = Vegetation W = Well water
- c. A control for well water,
- e. Distance irom plant
- discharge (TRM 484.5)
- f. Surface water sample also used as a control for public water.
- Added page 11 u.
i SQN ODCN -
Page 75 of 85 Revision 19 Table 3.3 SEQUOYAH NUCLEAR PLANT'
. Thermoluminescent Dosimeter Locations Map Approximate Onsite (On)a Location Distance or Number Station Sect 9e (Miles) Offsite (Off) 3 SSW-1A SSW 1.2 On -
4 NE-1A NE 1.5 On 5 NNE-1 WNE 1.8 On 7 SW-2 SW 3.8 Off 8 W-3 W 5.6 off 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 off 11 SW-3 SW 16.7 off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 off
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14 WNW-3 WNW 18.9 off
. 49 N-1 N 0.6 On 50 N-2 N ' 2.1 off s 51 N-3 N 5.2
- Off '
52 N-4 W 10.0 Off 53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 EVE 0.4 On 58 ENE-2 EVE 5.1 off 59 E-1 E 1.2 On 60 E-2 E 5.2 off 61 ESE-A ESE 0.4 On 62 ESE-1 ESE, 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 SE-B SE 0.4 On 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2. Off 69 SSE-1 SSE 1.6 On 10 SSE-2 SSE 4.6 Off 71 S-1 S 1.5 On 72 S-2 -*
S 4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off
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Table 3.3 (Continued)
SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter Locations Map Approximate Onsite (On)a Location Distance or Number Station Sector (Miles) Offsite (Off)
. 75 SW-1 SW 0.9 On -
76 WSW-1 WSW 0.9 On 7/ WSW-2 WSW 2.5 off 78 WSW-3 WSW 5.7 off 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 off 81 W-1 W 0.8 on 82 W-2 W 4.3 off 83 WWW-1 WW 0.4 On 84 WNW-2 WW 5.3 off g 85 W-1 W 0.4 On 86 W-2 NW 5.2 off 87 NW-1 NW 0.6 On 88 NNW-2 NNW 1.7 On 89 NW-3 NW 5.3 off t
4
- n. TLDs designated onsite are those located two miles or less from the plant.
TLDs designated offsite are those located more than two miles from the plant.
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, - . SQN 00Cu Page 77 of 85 Revision 19' Table 3.4 (1 of 2)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a c Airborne Particulate Analysis Water or Cas Fish Milk Food Products sediment (pci/L) (pci/L) (pci/m3) (pC1/kg, wet) (pCi/L) (pC1/kg, wet) (pCi/kg. dry) gross beta 4 1 1 10-2 N.A. N.A. N.A. W.A.
H-3 2000 N.A. N.A. W.A. N.A. N.A.
Mn-54 15 N.A. 130 N.A. N.A. N.A.
Fe-59 30 N.A. 260 N.A. M.A. N.A.
Co-58.60 15 N.A. 130 N.A. M.A. N.A.
2n-65 30 N.A. 260 N.A. W.A. N.A.
g Zr-95 30 N.A. N.A. N.A. N.A. N.A.
Mb-95 15 N.A. N.A. N.A. ,
N.A. N.A.
1-131 lb y g 10-2 N.A. 1 60 W.A.
Cs-134 15 5 I 10-2 130 15 60 150 Cs-137 18 6 1 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 W.A. N.A.
La-140 15 N.A. N.A. 15 N.A. N.A.
r TABtE NOTATION f
- The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% pt-obability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may includn radiochemical separation):
LLD = 4.66 sb E Y 2.22 Y exp(-Kat) l
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SQN ODCM page 78 of 85 Revision 19 Table 3.4 (1 of 2)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a.c ,
TABLE NOTATION (continued)
Where!
LLD is the "a priori" lover llait of detection as defined above (picoeurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting este of a blank sample as appropriate (counts per
- minute).
E is the counting effic!ency (counts per transformation),
V is the sample size (units of mass or volume),
2.22 is the number of transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
\
K is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between sample collection (or end of the sanple collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by ganna-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E V Y, and At shall be used in the es1culations.
b The LLD for analysis of drinking water and surface water samplas shall be performed by gamma spectroscopy at approxLaately 15 pCi/L.
t If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131 drinking water samples will be analyzed at a LLD o,f 1.0 pCi/L for I-131.
e other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
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SQN ODCM Page 80 of 85 Revision 19 Figure 1.2 RELATIVE DEPOSITION FOR GROUND LEYIL RELEASES (All stability Classes) 104 - -
104 .. ,
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y %
10-6 ,_
s v-10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
- Page renumbered 4
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s SQN ODCM Page kl of 85 Revision 19 Figure 1.3 CASEOUS RADWASTE TRE.!TNENT SYSTEM, CWSVCT\
Unit 1 / wa VM CYCS VCT \
Unit 2 /
en a )
WCS RCOT b_
Unit i /
WCS RCOT \
Unit 2 /
Weste Goa Cornpressor Plant
- t Pockege vent
(typical of 2) t, CYC5 EVAPS\
7' Units 1&2 / .
La 7' l La l r' I t
r, R V d k e m r m r m Woote Goa Weste Gas %ste Gee Decoy Tonk Decoy Tonk Decoy Tonk (belas ftes) (wwwM) W)
(Wesi
- 7) w s v w .s r
- Page renumbered 1157c
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SQW ODCM Page 82 of 85 Revision 19 Figu'e 3.1 Environmental Radiological Sampling Locations Within 1 Mile of Plant 348,75 N i i .2 5 NNW
NNE
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326.25 33.75 NW 2 NE 303.75 4 56.25
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281.25
~8 3 ' ~-C I #8~#8 EQUOYAH W-
- NUCLEAR -E
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