ML19225A224

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Draft Offsite Dose Calculation Manual
ML19225A224
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 01/26/1979
From:
ALABAMA POWER CO.
To:
Shared Package
ML19225A223 List:
References
NUDOCS 7907180582
Download: ML19225A224 (47)
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{{#Wiki_filter:, Ju. 2 6,i ? 'Tf '" AFT 0FFSITE COSE CALCULATION MANUAL JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 i ALASAMA POWER COMPANY 346 146 7 90718o53>

TABLE OF CONTENTS Radiological Effluent Technical Dose Calculation Soecification Section Manual Pace 4.11.1.2.1 Liquid Effluents 3.11.2.1 Gaseous Effluents 3.11.2.2 Noble Gases 3.11.2.3 Radiciodines and Radioactive Materials in Particulate Form 3.11.2.5 Dose Assessment for Environmental Radiation Standards 34b ik7

Dose Calculation Due to Liauid Effluents 4.11.1.9 1 Licuid Effluents-Dose Calculations m The dose contributions for the total time period I at shall be determined y f =1 by the following calculation and a cumulative summation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides measured in liquid effluents released to unrestricted areas using the following expression: m D = @jT at C Fjg] T y $g where: the cumulative dose or dose commitment to the total body or an D. = organ : from the liquid effluents for the total time period m I atq, in mrem. f =1 th the 'c'igth of the J time period over which C and Fy at = j are averaged for all liquid releases, in hours $ g C;f the average concentration of radionuclide i in undiluted liquid = effluent during time period aty from any liquid release, in uCi/ml. the site related ingestion dose and dose commitment factor to A, = j' the total body or any organ T for each identified principal gamma and beta emitter, in mrem-mi per hr-uCi. A =kUB DF jT g f pj j where: unit conversion factor,1.14 x 105 (year /hr). k = U (ml/1).(pCi/uCi) adult fish consumption, 21 kg/yr. U = f B - the bioaccumulation factor 1. 'ish fo-each measured radionuclide F1 i, in pCi/kg per pCi/ liter (Table 1). the dose conversion factor for nuclide i for adults, in mrem /pCi D = Fi (Table 2). during any liquid Fj the near field average dilution factor for Cg = effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5. (5 is the site specific applicable factor for the mixing effect of the discharge structure. ) 346 148

For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summ' tion may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. I 346 149

m, .( i i \\_ U cm, O PE F OE o L_ _5D nV, 7 9 0 7 / g C5 7dfo NO. OF PAGES A E ILLEGIBLE: x 0 HARD COPY FILED AT: PDR OTHER C BETTER COPY REQUESTED ON / / O PAGE TOO LARGE TO FILM: O HARD COPY FILED AT: PDR CF OTHER O FILMED ON APERTURE CARD NO. 346 150

Dose Calculation Due to Gaseous Effluents 3.11.2.1 Gaseous Effluents-Dose Calculations The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following expressions: (a) Release rate limit for noble gases: 0 f'$ K [(x/Q)yQjy] < 500 mrem /yr, and 10 4 ,1 v 6 4 y]J 10 (L5 + 1.1 M ) [(x/Q)yQ < 3000 mrem /yr j 1 v where the terms are defined belcw: (b) Release rate limit for all radiciodines and radioactive materials in particulate form, with half lives greater than 8 days: 2 6 f,C fP C 5 Ip/Q)mv iv] < 1500 mrem /yr 238 x 10 0 where: the factor to convert inhalation dose to grass-cow-milk 238 = pathway dose. the total body dose factor due to gamma emissions for each K. = I identified radionuclide, in mrem /yr per pCi/m3 (Tabel 3). the skin dose factor due to beta emissions for each identified L. = I radionuclide, in mrem /yr per pCi/m3 (Table 3). the air dose factor due to gamma emissions for each identified M. = I radionuclide, in mrad /yr per pCi/m3 (Table 3). the product of the largest inhalation dose factor for any P = j organ of an infant for each identified radionuclide and the infant inhalation rate of 1900 m3/yr, in mrem /yr per pCi/m3 The infant age group and pathways are the most restrictive, thus the infant dose factors in Table 4 usually apply. However, for the kidney and for some radionuclides, the adult inhalation dose factors in Table 5 are applicable. (x/i{} y = the highest value of the annual average atmospheric dis-persion factor at the site boundary, for all sectors, in sec/m3 The value of 7.5 x 10-7 sec/m3 will be used for the plant vent and 1.2 x 10-5 sec/m3 for the turbine building steam jet air ejector.

e TABLE 2* (Continued) xt ::.m aan mn m n no:t m:0 n:m u:::: c:-u.: 53I 133 1.43E-06 2.:!E-06 7.57E-07 a.77E-04 4.33E-n6 0.0 2.15E-06 531 134

1. 0 bE -0 7 2.35E-07 1.03E-37 3.7aE-05 6.59E-07 0.0 2.51E-10 53!

135 c.43E-07 1.17C-16 J.Jor-37 1.53E-os t.asr.3% 6.0 1.3tE-06 15;5 taw" 2.1A ve 4.4,0-06 2. 3 a 5 -3 0.J d.-wE-14 3.431-09 1.5si-Ci 55CS 138 6.22E-05 1.L9E as 1.2t!-04 0.0 4.'0E-05 1.59E-05 2.5'E-06 SSCS 135 t.95E-05 1.10E-69 2,ME-as 6.c o.9pr-36 ?.05E-36 c.2t'-fl 55;5 133 s.514-93 d.5/E-05 1.a5E-OS 0.0 1.a3E-05 1.7ac-06 2.925-06 55CS 137 7.75E-05 1.0aE-04 7.15E-Oi 0.0 3.71E-05 1.23E-05 2.10E-06 55CS 119 5.52E-09 1.1*E-67

c. ate-o*

0.0 9.02E-a? ?.02E-00 J.355-13 55Cs 121 5.wii-48

5. Ni-co 1..*5E

,5 0.; w.eli-04 5.70i-09 0.. 56BA 139 4.71E-08 b.o2E-11 2.54E-09 0.0 6.47E-11 3.92E-11 1.72E-07 SGSA tc0 2.1'E-05 ?.95E '* '.3:E-19 0.0 9.65E-S8 1.2eE-09 a,tSE-Os SoBA 181 0.0 3.5o -11 1.59(-09 0.0 3.51i-11 2.02E-11 2.42t-1/ SbSA 122 2.13E-05 2.19E-11 1.3 E-09 0.0 1.55E-11 1.24E-11 0.0 57LA tuo 2.50E-09 1.26'-98 3.3 E-10 f.1 0.9 6.o o.2SE-os 57LA tal 3.195-10 4.31i-11 1.osi.: 0.0 0.0 0.0 1.1E-v5 57LA tc2

1. 2 8 E - 10 5.52E-11 1.45E-11 0.0 0.0 0.0 4.25E-07.

58CE tut o.37E-40 4.3:E-63 7,teg-10 n.n 2.scE-oo 9.1 2.c2C-05 SaCE tus t.o3E-09 1.2 2 c -O s 1.15d-t: 0.0 5.382-10 0.0 u.5cE-65 SSCE tua a.daE-07 2.0aE-07 2.62E-08 0.0 1.21E-07 0.0 1.e5E-04 5174 123 '.2tE-00 3.73r-io a.5?:-ia 1.a 2.t3r ac nn s,13r-03 5974 td* 3.0et-tt 1.255-11 1.53t-12 3.J 7.06i-t2 0.0 4.31E-L'S 60ND 137 6.30E-09 7.2EE-39 a.35E-10 0.0 4.25E-09 0.0 3.ucE-05 6tPM t27 7.5:E-08 7 t0E-oo ?.*- -50 0.0 1.34E-19 0.0

  • o!!-OS 6t#M [W69 3.0/d-ud 1.isi-J4 6.1?i-09 0.0 1.21E.08 0.0 0 iwt-05 6tPh 143 7.tsE-09 1.19E-09 6.00E-to 0.0 2.25E-09 0.0 9.34F-05 6tPM 149 1.52E-09 2.15E-13
  • 72E-11,i. 0 a.07E-10 0.c J.03E-05 6tPM 151 e.4ii-10 1.tii-10 5.;2i-11

.0 2 aSi-10 0.0 3.22i=05 625M 151 6.91E-08 1.11E-03 2.36E-09 0.0 1.33E-05 0.0 5.2SE-06 6239 153 8.5?F-to

7. tee-to c.23E-11 3.0 2.3?e-to a.0 2.55E-05 bliu 132 1.936-01
4. at-03 3.915-03 0.0 2.75E 07 0.J 2.5si-G5 63EU 154 6.16E-07 7.57E-0$

5.39E-0$ 0.0 3.62E-07 0.0 5.JaE-05 63EU 155

  • .6LE-09 i.22!-ni 7.**E-oo A.o 5.jur-na 6.0 9,60E-0%

b3EU 15s 1.37E-Co 1.056-0$ t.Iti-49 0.0 7.;aE-09 0.0 1.236-G5 6579 160 a.70E-08 0.0 5.5st-09 0.0 1.9aE w; ..Q 4.33E-05 67wC t$h9 2.70E-07

3. ace-69
6. 41 r.19 0.0 1.26E-07 S.-

0.0 Jua til 9.9dE-09 ).2=c-]+ 5.-et-iJ 0.v 0.J 3.0 a.s06-07 74a 155 a.C6E-07 1.355-07 1.u2E-at 0.0 0.0 0.0 1.5sE-05 7ad 157 1.01E-07 3.62r-64 1.1:r-34 a.1 9.S 4 6 ?.92'-c5 82F3 210 1.53 -02 35 -03 5.-4E-G4 0.0 1.23E-42 0.0 5.d2E-05 8331 210 d.62E-07 3.!*E-03 3.47E-0$ 0.0 3.54E-05 0.0 e.75E-05 54P0 210 3.57E-04 7.57E-04 S.6cE-05 0.0 2.52E-03 0.0 6.36E-05

  • 0btained from Regulatory Guide 1 109 (March 1976)

-~ -c

(x/Q)"V the highest value of the annual average atmospher.'c = dispersion factor at the distance of 5 miles, for nll sectors, in sec/m3 The value of 7.6 x 10-8 sec/m; will be used for the plant vent and 5.1 x 10 7 sec/n3 for the turbire building s'eam jet air ejector. Q" - the average release rate of nuclide i in caseous efflue..t from each vent release point v at the site, in pCi/sec. Noble gases may be averaged over a period of I hour, and any other nuclides may be averaged over a period of 1 week. 103

TABLE 3"*** DnsE FAcTons con NoriL gases A Nn DAt'G11TFits Fi* Ki** Ni** s v-Bodv**(Oc?,) Nucifde s,-: e (CF;) f-Skin **(CFS g) v-Air (0F3{} 1.93E-05 7. 5 6'E - 0 3 tr-E2m 2.SSE-04 Kr-85c 1.97E-03 1.46E-03 1.23-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05

1. 61 E- 05 Ir-87 1.0:~-02

.9.73E-03 6.17C-03 5.92E-03 Kr-88 7.93E-03 2.37E-03 1.52E-02 1.47E-02 Ir-89

1. 0 S E- 0 2 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Ie-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 Ie-122c 1.4SE-03 9.94E-04 3.27E-04 2.51E-04 Ie-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Ie-135c 7.39E-04 7.11 E- 04 3.36E-03 3.12E-03 Ie-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Ie-137 1.27E-02 1.22E-02
1. 51 E-03 1.42E-03 Ie-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.23E-03 1.69E-03
9. 3 0 E-03 8.84E-03 nrad-e.3 PC1-yr mren-n-pC1-yr 2.88E-04 2.38 x 10'#
        • 0btained from Regulatory Guide 1.109 (March,1976) 6 h

O b ll[. , 3 /) e // I

Dh H i-l V vu u PAGE PJ _ _E D AkO. eomosu 4 NO. OF PAGES d REASON: MPAGE ILLEGIBLE: C HARD COPY FILED AT: PDR ) OTHER C BETTER COPY REQUESTED ON / / O PAGE TOO LARGE TO FILM: C HARD COPY FILED AT: PDR CF OTHER C FILMED ON APERTURE CARD NO. 3th 155

Dose Calculations Due to Noble Gases 3.11.2.2 Noble Gases - Dose Calculations I. Method A: Real Time Meteorological Inout (Normal Mode) The air dose in unrestricted areas due to noble gases released in gaseous effluents from each reactor at the site shall be determined by using the following expressions: (a) During any calendar quarter, for gamma radiation: D = 110 IMiJ=1 tg [fx/Q))gyQjjy],and g During any calendar quarter, for beta radiation: n 0 = 110 I Nj y Ag h/OjgyQ )y], and 4 3S J_1 (b) During any calendar year, for gamma radiation: n D = 110 { Mj?_I atg [(x/Q)3gyQj3y],and g J-During any calendar year, for beta radiation: n = 110 f N Q )y] j q atj [(x/Q)3gy D 4 gg ] =1 where: the total beta air dose in sector 3 from gaseous effluents D = gg n for the total time period atj, in mrad. Z J=1 the total gamma air dose in sector 0 from gaseous effluents D = 6y n for the 'Atal time period atj, in mrad. Z j=1 h the length of the j time period over which (x/Q) and Q. at. = are averaged for all gaseous releases, in hours. 3 a 5J 3 For batch releases, no time period At shall be more than I hour; j for continuous releases, no time period At shall be more than a week. j r I

the air dose factor due to beta emissions for each N. = identified radionuclide, in mrad /yr per pCi/m3 (Table 3). I (x/Q)3gy the average atmospheric dispersion factor for the time = period Atj in sector 9, from all vent release points at the site, in sec/m3 When atj is greater than I hour, the average shal~l be based on observations of wind speed and atmospheric stability taken at least every hour during atj. The turbine building steam jet air ejector is considered a ground-level release at all times. The plant vent is a mixed-mode release (elevated at times, ground level at times, and mixed at times). However, for ease of implementation, the licensee may consider the plant vent to be a ground level release and calculate (x/Q)3gy values using the following equation. (x/Q)jev = k LO 6v L = 2.03/r : gy g7 (of+0.5h /r) 2 = 7 subject to the condition

Z -<[a Z The values of L are provided in Table 6 for the site boundary and food pathways.

ev the vertical standard deviation of the plume for the = o applicable atmospheric stability class (Pasquill Category) Z determined at least hourly, for the distance r during the time g period Atj. the distance from the midpoint between the vent stacks to r = 2 the receptor for each sector 9, in meters, provided in Table 6. the average wind speed determined at least hourly, curing time Ii = period atj in sector a, at a height of 10 meters for vent releases, in m/sec. the recirculation factor accounting for spatial and temporal k = g variations in air flow. For noncontinuous releases, its value is unity. For continuous releases, see figure 1 for correction fac tor. the height of the tallest adjacent structure, which is the h = y containment building (=40 m). 346 153

Since the plant vent is actually a mixed-mode reiease, when these effects are taken into consideration, (x/Q).- is calculated using methods described in Regulatory Positions C.l.c, C.295! C.2.b, and.C.2.c of Regulatory Guide 1.111 (March 1976). As an alternative meth-.6, the dispersion factor may be calculate using values from joint frequency tables sur:rarizing hourly metaorological observations during release period. 346 138 4 F

O to Z Z @ @ W @ T tf $ W W tf. @ W oCCCoCoCCCC CCooo I 1 5 1 1 t I I I I i 1 'l i I I bl Ll L4J L.! LJ LJ L1 tJ L4J L.J d LJ LJ LJ LJ tsJ & O a) C & Cb C. n n n. ?&CT 4 a sf tf tf - D Us &... D.1 J.-. e O t r C' N 4C<N57765 j "~ Ch N N N.C. i i "e i e Z V ti' @ # wa T'f.Ot/.T W W $ @ W t4 l' ,CCCC C CC CCCC COCCO I*I I I I i 1 1 8 8 t i I I I I f tJ ts. La te w t2 k k' LC k* L: LL' %) w' LJ hJ l tw L:,,o C.C "- N C & C C C T. t'- N C. C CCC *L ~ .x. C. C. C. C. C C. -- - - 1\\ t1. ........... e. l < lD D D D < T. D A D ts. D 4 < D D I 6 l l tr 'v tr v v tr V tr e c t: V tr it tr T CC CC C CC C OCC CC CCC 1 5 1 1 I I t 1 3 1 1 I I.I i I k',10 LJ L.J L4J tJ La ta uJ L a tc k L.B uJ t4.348 a = .% N O C. f*= .C

4. 4N N O O

.% 6 - ?. ?.. J.e p f. e -. O. 7.

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g Q - e -. 44 4'< < 4 4 4 4 t*' t'. t'. < 4 4 l'4 I l l I V W Lf t[ Y tf t? $ (? $ W- $ W $ $ W. CC CCC CC CCC C CC CCC 9 8 6 1'I i i 1 1 l 1 1 1 1 1 I N 't k tu h " lA s L., b a tu L L b e L' W LA td L h.J I.3 4 m R t'. 4 C t*' D C @t. R D 4 n n y g a N - - e. rm r~ - c.O D - n r~.

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1. ts.' tf. f. C s D.r '%.

'\\. N. ?. tf C6 C. T. if 1 U m 3 U o = ~ ~ us O D u ) ) l l c w z o p a m o ,o e o ao o o o c,e o o e,c c 4 -A O C# OOOOC OO CCC OOooCC 1 l l 8 'I i I h ( l*I I i i i i 1 1 L l' td tJ LJ L. L LAf LJ L1 LJ t.* Las tJ kJ la m w s A H E-* t.o 4 Lf f t!' 4 4 'P 4 4 ~3 J tn 4 'C U" tf -;o O o.- - o c c. 4 O C - - C. C H 3 H ei.... M [ (0 4 *O 4'C C) 014 4 4 :C 4 C C:. CC l 1 1 e i & D <.OlQ D v 4 4 4 D,0 Q Q c : CC OOOC C C o o o o c> c G a I 3 I 8 8 8 8 'I l ' l I 8 8 I 8 U tal LJ 1AJ LJ LJ Q L.; '.J ta.J bJ LJ tAs ta.1 kl 6 t.8 p-Z N ce o o N P-o( 4 O o o t=- a-OC tf.6. 4 4. D. f. 4. ;1% (%' N < 4 t!' D 4 4 4 y 4 a l ~ i !...l....!... + OCCOOOO O ")O'C)CDC'O O Q C1 IP lJ1 W O C"10 m e' - d LA O C'1 O t/1 w U e NJ 4 4 N N :- 4 4 O c 4 (V N 4 4

o

- - e le e e. f s r.o O s u C3 O ~% 5 k& B i z ta n. (n u.e mia v-12 2 E ~ e

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= 2 w un u s tmm a m e 3 3.[ JL 2-p i-z y U 1 CJ 8 y w J s.s { f l M ~ ~ 20

TABLE 6 (CONTINUED) i M MER[ FARLEY NUCLEAR PLANT VALUES OF L gy LIMITING FOOD PATHWAY DISTANCE FOOD PATHWAY L 0v VENT PASQUILL CATEGORY DIPECTION OISTANCE (M) A B C D E F G N 4020. S.0SE-07 5.0SE-07 2 38r-06 6.2SE-06 8.80E-06 1.43E-05 P.02r-OS NNE 3860. S.26E-07 S.P6F-07 P.SSF-06 6.67E-06 9.32F-06 1.slE-05 2.13r-05 r> E 3700. S.49F-07 S.49F-07 p.75F-06 7 13E-06 9.91E-06 1 99E-05 2.P4r-05 Er:E 3860 S.26E-07 5.P6F-07 L.SSr-06 6.6/E-06 9.3PF-06 1.clE-05 2.13c-05 F 4340. 4 60E-07 4.68F-07 P.08F-06 S.53E-06 7.HHF-06 1.29E-05 1.94r-05 ESE 4830. 4.20F-07 4.POE-07 1 73F-06 4.6SE-06 6.7SF-06 1 12E-05 1.61F-05 SE S470. 3.71E-07 3.71F-07 1 39F-06 3.81E-06 S.64F-06 9.46E-06

1. 3 /r- 0 5 SSE 7240.

2 80F-07 2.90E-07 8.50F-07 P.43E-06 3.76F-06 6.4RE-06 9'.s9c-06 j w 3 S 5670. 3.61E-07

3. ale-07 1.32F-06 3.64E-06 S.41F-06 9 10E-06 1.32r-05 SSW
2090, 9.71E-07 2.30E-06 7 74r-06 1.77E-05 2.37F-09 3.94E-05 4.ASF-05 54 1970.

1 0SE-06 2.93E-06 R.97F-06 P.0lf-05 2.69E-05 3.46E-05 S.14c-05 g'. wsw 1490. 1.40E-06 6.0SF-06 1 52r-05 3.13E-05 4.17F-0E S.98E-05 7.sPr-05 1440. 1 40E-06 6.0SF-06 1 52F-05 3.13E-05 4.17F-05 S.P8E-05 7. s si r - 0 5 w WNw 33a0. 6.01E-07 6.60E-07 3.P2F-06 8.24E-06 1.13E-05 1.90E-05 2.41F-05 tu 4500. 4.SIE-07 4.SIE-07 1 95r-06 S.21E-06 7.4HE-06 1.PTE-05 1.76r-05 cm 3220. 6.30E-07 7.66E-07 3 50E-06 8.90E-06 1.21E-05 1.91E-05 P.66F-05 Note: This table may be updated based on annual land census resu,ts as required in STS Section 3.12.2. Note: hv = 40m 4

0 0 1 g-1 j i q_ b _ __ _ _ ) 6 7 9 R 1 0 O T j. 1 J l__ C h A c F r N l M a ) S t 0 l ( l 1 E T 1 1 T C 1 E E N l F i M E R R 1 O R O 1 U C L t G e i i d I t l ( A u E R G C R E N y T r A T t to t E S P a \\ I O l D u ge 0 R 1 l

I J

m 1 o r I f d q_ _ __ e n i a t b 0* 1 0 4 0 1 0 1

  • O 5,iigemog 5l C

unc e x p

3.11.2.2 Noble Gases - Dose Calculations / Cont'd) II. Method B: This method is to be used when the real time meteorological inputs are not acolicable. The dose contribution due to noble gases in gaseous effluents shall be calculated using the following expressions: (a) During any calendar quarter, for gamma radiation: 3.17 x 10-2 Mj (x/Q)yQ, and 0 = 5 During any calendar quarter, for beta radiation: 3.17 x 10-2 Ng (x/Q)yQ, and D = j g (b) During any calendar year, for ga:ma radiation: 3.17 x 10-2 M5 (x/Q) Qj, and D = During any calendar quarter, for beta radiation: 3.17 x 10-2 Nj E)yQ D = 4 g where: D.( = the total gamma air dose from gaseous effluents, in mrad. the total beta air dose from gaseous effluents, in mrad. D = g (x/Q)v the highest value of the annual average atmospheric dispersion = factor at the site boundary, for all sectors, in sec/m3 The value of 7.5 x 10-7 sec/m3 will be used for the plant vent and 1.2 x 10-5 sec/m3 for the turbine building steam jet air ejector. Q. = the release of noble gas radionuclides, i, in gaseous effluents I in uCi. Releases shall be cumulative over the calendar month or quarter as appropriate. Other terms are defined in Specifications 3.11.2.1. 346 162

3.11.2.3 Radioicdines and Radioactive Materials in Particulate Form - Dose Calculations I. f'ethod A: Real Time Meteorological Inout (Normal Mode) The dose to an individual from radiciodines and radioactive materials in p'ar-ticulate form, with half lives greater than 8 Jays, in gaseous effluents released from each reactor at the site to unrestricted areas (see Figure 5.1-1) shall be the following expressions: (a) During any calendar quarter: n t.,tj [W Qjjy] D = 110 5;) R g gj 4 J=l (b) During any calendar year: n 110 fR atj [W Qjjy] O = $) gj j er where: the cumulative dose from gaseous effluents to the total body D = 3' or an orcan T of an individual in sector 9 for the total n time period I at, in mrem. j j =1 R. the dose factor for each identified radionuclide into = O' sector 6, in mrem /yr per pCi/m3 for tritium and in mrem /yr per pCi/m2-sec for other isotopes, from Table 7. For sectors with real pathways within 5 miles from the point at the midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, the values of R,hs with no real pathways have been determined based on these real pathways. For secto within 5 miles from the point at the midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, R has been determined assuming that all pathways exist at the ajmile g distance. dispersion parameter for calculation of food pathway dose, W = 4 j (x/Q)3gy for tritium (H-3) W = j = (D/Q)3gy for other isotopes. W factor which eauls 1 if wind in hour t is into sector e and is f, = equal to 0 otherwise. 346 163

(D/Q))gy sector 9, in meters-{ areal) for the time period Jt, in relative deposition = When atj is greater than one hour, relative deposition shall be based on observation of at:nospheric stability taken at least every hour during atj. (0/0)jev " 0.3 2 [ (I-E) 6 eve + E6gyg ] rg width (arc length) of 22.5 degree sector at distance r, 0.3927r = g g in meter. 6* relative deposition rate (linear) at distance r; in = sector e for stability class of interest and release height h in meter-l.(Figures 3, 4, 5) g relative deposition rate (linear) at distance ro for S = ay9 stability class of interest and for ground level release, in me ter-l. (Figure 2) fraction of effluent entrained in building wake. E = E=1 if (W /u ) s 1 rh sb g e s y E = 2.58-1.58 (W /u ) if I* I (W /"e) s 1.5 g e o E = 0.3-0.06 (W /u ) if 1.5 5 (W /IT ) < 5.0 g e g e E=0 if (W /u ) > 5.0 g e 346 164

)fiY TA _7 Dose Factor R 0i mrem /yr per pCi/m'3 for H-3 mrem /yr per pCi/m -sec for all other isotopes FARLEY NUCLEAR PLANT I l N NNE NE ENE E FSE SE SSE SECTOR 7 2 t+ 0. 4830. 9470. CISTANCE' 4020. 386d. 3700. 3860. 4340. r, (m) i . _4 r Radionuclide F-3 4 29E-03 4 29E-03 4 29E-03 4.?9E-03 4.29E-03 4 29E-03 4.24E-03 4.29E-03 CR-cl 2 10E+01 2 10E+01 2.10E+01 2 10E+01 p.10E+nl 2 10E+01 2.InE+01 2.iOE+01 MN-94 2 7dF+07 2.70E+03 2.70E+03 2 70E+03 p.70E+03 2.70E+03 2.70E+03 2.70F + 03 FE-54. 1 54F+03 3.54E+03 3.59F+03 3 59E+03 7.59E+03 3.59E+07 3.54E+01 1.59E+03 CO-59 1.SIE+03 1.slE+03 1.SIE+03 1 51E+03 1 51E+03 1.SlF+01 1.SIE+03 1.Slf+03 CO-60 2 95E+04 2.95E+04 2 95E+04 2.95E+04 p.95E+04 2 95F+04 2.9%E+04 2 9SF + 04 7h-65 5.11F+03 5.llE+03 S.llE+07 5.llE+03 s.llF.03 5.llF+03

5. lie +07 5.llF+93 sR-99 4.24E+04 4.P4E+04 4 24F+04 4 24E+04 4.24E+04 4 24E+04 4.24L+04 4 24F+34

, [ SR-40 1 60F+06 1 60E+06 1 60F+06 1 60E+06 1 60E+06 1 60E+06 1.6nf+06 1 60E+06 79-45 3 62E+07 3 62E+03 3 62E*03 3 62E+03 3 62F n3 3 62F+03 3.6PE+03 3 6/E+03 1-lll 2.53E+04 2.53E+04 2.53E+04 2.53E+04 P.53E+04 2.53F+04 2.57E+04 2.5 3E + 04 I-133 3.89E+0? 3.A9E+02 3.89F+02 7.89E+02 7.89F+02 3.89E+02 '1.H4E+02 3.39r.02 CS-134 3.44E+04 3.94E+04 3.94E+04 7 94E'e4 7.44F+04 3.94E+04 7.94E+04 3.94E+04 f CS-116 4.87E+02 4 87F+02 4.87E+02 4 87E~ ' 4.87E+02 4.87F+02

4. ATE +02 4.H7E+02 CS-137 4 19F+04 4 19E+04 4 19E+04 4 19Evo4 4 19E+04 4 19F+04 4.14E*04 4 19E+04

' O PA-140 4.lHF+02 4 18E+02 4 18F+02 4 18E*02 4 18E+02 4 18E+02 4.InE+02 4.lHE+02 CE-141 6 86E+02 6.86E+02 6.86E+02 6 86E+02 6.86E+02 6.86E+02 6.86E+02 6.h6E+02 i Note: 1) This table may be updated based on annual land census results as required in STS Sect.on 3.12.2.

2) Sector is wind into. distance in metehs.

s

TABLE 7 , iJtlTlfiUED) Dose F.ctor R 0i mrem /yr per pCi/m for H-3 2 mrem /yr per pCi/m -sec for all other isotopes FARLEY NUCLEAR PLANT SECTOR S SSW SW WSW W WNW rdy ,;tgg CISTANCE 5630. 2090. 1930. 1450. 1450. 33RO. 4500. 3220. n(m) r l Radi0nuclide l P-3 4.29E-01 4.29E-03 4.29E-03 4.29E-03 4.24E O' 4.29E-03 4.29E-01 4.29E-03 CR-s1 2 10E+01 2 10E+01 2 10E+01 2 10E+01 P.10E+01 2 10F+01' P.InE+01 P.10E+01 PN-54 2 70F+07 2.70E+03 P.70E+03 2 70E+03 7.70E.03 2.70F+03 P.7nE+03 2.70E+03 FE-59 1 59F+03 3.59E+03 3 59F+03 1 59E+03 7.59E+03 3.s9E+03 3.59E+03 3.99E+07 CO-98 1 51F*03 1.51E+03 1 51E+03 1 51E+03 1 51E+03 1 51E+03 1.51E+03 1.SIF+03 to-60 2 95F+04 2.95E+04 2.95E+04 2 95E*04 P.95E+04 P.95E+04 P.9sE+04 2 95F+04 Y 7N-65 5.)lE+03 5.llE+03 5.llF+03 5 11E+03 s.llE+03 5.llE+03 6.llE+03 5.llF*03 SR-39 4.24F+04 4 24E+04 4.24E+04 4 24E+04 4.24"+04 4 24E+04 4.24E+04 '*4E+04 S9-90 1 60F+06 1.60E+06 1 60F+06 1 60E+06 16. +06 1 60E+06 1.6nE+06 1.60E+06 79-9G 3 62F+03 3.62E+03 3.62F+03 3 62E+03 7.62E+03 3.62F+03 3.6PE+01 3 62F+03 1-131 2 53E*04 2.53E+04 P,53E+04 2 53E+04 P.53E+04 P.53F+04 2.51L+04 2.53E+04 t-133 3.89F+02 3.89E+02 3.89E+0? 3 89E+02 7.89E+02 3 89E+0? 3.89E+02 3.H9E+02 O CS-134 3.94E+04 3.94E+04 3.94F+04 3 94E+04 7.94E+04 3 94E+04 3.94E+04 3.94F+04 CS-136 4.87F+0? 4.87E+02 4.87E+0? 4 87E+02 4.H7F+02 4.87E+0? 4.87E+02 4.87E+02 CS-137 4.19F+04 4.19E+04 4.19E+04 4.19E+04 4.19E+04 4.19E+04 4.19E+04 4.19E.04 PA-140 4.18F+02 4.18E+02 4.18E+0? 4.18E+02 4.18E+02 4.18E+02 4.lHE+02 4.18E+02 CE-141 6 86E+02 6.86E+02 6.86E+02 6,86E+02 6.86E+02 6.86E+02 6.86E+02 6.86E+02 tio te: 1) This table may be updated based on annual land census results as required in ST5 Section 3.12.2. 2\\ Secter is wind into. distance in meters. 6

10-3 i i, i, 4 i ei, i i ii i i i is i i i i i la t _ l l l l l 1 l I I Ii! i l It'l l Ill l l l l llll i 104 l\\ ! Qlll l i i l lll c 6 ,,si, s iI iX l i l i y \\ I I e .l \\ E \\ G Ni 3 \\ l $ 10-5 ,( i ,, l ' ?x i x, 8 i i N i i,i c. I l 6 X l I i i 16 I i ll \\l Il 11 l '\\l l E '\\ m we 10-6 \\ ,i r i6 i ) il l I f I tl l 4 l l 'l l l l l l l 1 3 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) l-Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes) } z{ 6 }b7 FIGURE 2*

  • 0btained from Regulatory Guide 1.111 (March,1976)

~

10-3 ,,,i'i l ll,l l 'l' ', i,iiii i i ' iii' i 6 i i.ei i I 1lil I I I I III l l t !l l i l ll l lll l } l l I' ll I l l 1 l ll 1 I UNSTABLE ( A,B,Cl I 104 %I 'IIII i / i K ii. I i r A.t i .iii i i i<i iii i g f I 8 i f i i t i i w l l Ni j l l l Ili i i e i Wh 1 l l I f j[ l l\\N NEUTRAL Nh 5 / l / N s r l ill Nh 1 i IN EUTR AL (D) N l l ll'il li%

SlsBLE, 2

9 30-5 T N f.", % 'Y I I l[ \\ I \\' I I I I l / o if i i 'f f 1 W i I i i i i /i \\\\ i\\lI6 6 'j m /t i i 11 11 I iII/ I KW\\ '. 6 I 2 / I ~ i l lL - '/ N I ID-I! i / HP / R h t i N N

i

= ' 'l l 1 -l 10-6 x i i . i ii,,, x i i iiii i i ,is i !l 6 I I i 6 1 1 I t I si

I f

I ti /I ll i I I I I J ll l I I I I I l lll [ Ili I J / I ~ l. I 10-7 10.0 100.0 200.0 0.1 1.0 PLUME TRAVEL DISTANCE (KILOMETERS) Relative Deposition for 30in Releases (Letters denote Pasquilt Stacility Class) i 3 f,6 j ()8 1 FIGURE 3*

  • 0btained frcm Regulatory Guide 1.111 (March,1976)

104 i i l ll l l,.llll i i i i i i i i6 I l l lll l l l l l ll W 4 UNSTABLE ( A,8,C) I l I i li [ \\ I I / N \\ / If I l t 10-5 / NEUTRAL (D) \\ a ,/ ,,f, A i ,,i.,,x h / ,,/ i6 Al I i i H / / I i \\N II I y / l \\ N UNSTABLE /[' E ~.__, S:. N \\ w / NEUTRAL N N m k [ \\ \\ 10-6 P l l,, ,l<' i 's i i ,ii .,v. ) o i i i i ii 6 i 6 i/ 2 g i i i l 1 l l/ a l/ l ii i l I/ s !/ I / I 5 l / aw C" 10-7 STABLE (E,F,G) i l

l';l i

i o i l I I t i I i I J ll Ii i U i i I li i I I ~ d I l I / ll i I t i m f II) 10-8 I \\ i 0.1 1.0 s.0' 100.0 200.0 ~ PLUME TRAVEL L.5TANCE f CLOMETERS) k 3'3 Ralative Deposition for 60m Releases (Letters denote Pasquill jy Stability Class) FIGURE 4* bkN "Obtained from Regulatory Guide 1.lll(March,1976)

0-4 r I l I I I 1 II I i l l !I UNSTABLE (A,B,C) l [ N N N 10-5 As / ,, Tw ,/ ; ,,i f, ,w i NEUTRAL (D) 'll x(l ll f l

i i f

'y / I / i i N iM / / \\ N c / / N N \\ \\ $c i $ 10-6 i li ', 'll l l l'

  • l l

l E i r / \\ i t i i i / I l / I I' I I I I g / / I I 5 / a STAB LE (E,F,G) y NO DEPLETION I 10-7 ',i .i i, t 1, I I / ii t i I I I / I I I f / l i l / 4 l p 10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) i.;lative Deposition for 100m Releases (Letters denote Pasquill f Stability Class) (. FIGURE 5*

  • 0btained from Regulatory Guide 1.111 (March, 1976) a46 1?0

3.11.2.3 Radiciodines and Radioactive Materials in Particulate Form - Dose Calculations (Cont'd) II. Method B: This method is to be used when the real time meteorolooical inouts are not available. The dose contribution due to radiciodines, radioactive materials in par-ticulate form, with half lives greater than 8 days, in gaseous effluents shall be calculated using the following expressions: (a) During any calendar quarter: -8 ? 0 = 3.17 x 10 }R$ W Q, and 7 (b) During any calendar year: -8 D = 3.17 x 10 R WQ 7 4 where: 07 = the cumulative dose from radiciodines and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents in mrem. 2 R. = the dose factor for each identified radionuclide, i., in m I (mrem /yr) per pCi/sec or mrem /yr per uCi/m3 from Table 8. the annual average dispersion parameter for estimating the dose W = to an individual at the critical location: W = (x/Q) for the inhalation pathway, in sec/m3 from Table 9a. -2 W = (D/Q) for the food and ground plane pathways, in meters from Table 9b. Q.= the release of radiciodines, radioactive raterials in particulate, I with half lives greater than 8 days in gaseous effluents. Releases shall be cumulative over the calendar month or quarter as appropriate. 3 k() )

TABLE 8 FARLEY

  • NUCLEAR PLANT PATIIWAY DOSE FACTORS DUE TO RADIONUCLIDES OTliER TIIAN NOBLE GASES Ma r un ane Cow-Milk-Infant Leafy Vegetables Inhalation

. Pathway Pathway Pathway Pathway Fathway IQ Ri Ig RA RA (mrem /yr (m *orem/yr (m

  • mrem /yr (m
  • mrem /yr (m
  • mrem /yr Radionuclide per pCi/m )

per pCi/sec) per p Ci/sec) per p Ci/sec) per u Ci/sec) e-3 1.12F+03 P.13E*02 0. 2.laE*03 ?.47E*07 C0-41 1.70E*04 4.9HF+0S 5 31F+06 s.75E+06 1 6TE+06 PN-44 1.57F+06 7.60F+06 1 56F+09 3.73F+07 S.3eE+07 FE-c9 1.27F+06 A.44F+08 3 09E+09 4.01E*06 1 14E+09 cO-sa 1.10F 06 4.49F+07 4 27E+08 7.Olf+07 4.ScE+07 co-a,0 7.06F+06 3 61E+08 2 44E+10 P.25E+0a 1.Scf+06 7 ta - 6 5 9.94F+0S 1 0SF+09 8.28E+08 1 99E+10 ?.2cE*06 (R-49 ?.lSF+06 4.99F+08 2 42E+04 1.28E+10 S.3sE*09 5p-90 1.Olf+0A

1. ole +10 0.

l.19E+11 4.8%E+10 7R-9s 2.23F+06

6. t: 9 F + 0 8 -

2.73E+0d A.76E+0S 1.13F+04 1-111 1.6?f+07 P.60F+09 1 01E+07 4.9SE+11 2.0aE.10 1-171 3.84F+06 6.4SE+01 1 43E*06 4.62E+09 3.HPE 64 CS-134 1.01F+06 1.4PE+09 7.70E+09 6.37F*10 1.9AE+09 CS-136 .l.71F+0S E.06E+07 1 64E+08 A.61E+09 1.6nE*06 CS-137 9.0SF+0S 1.27F+09 1.lSE+10 s.7SE+10

1. HOE +09 PA-140 1.74F+0n 5.00E+07 2.E5E+07

?.75E+08 2.03E+08 CE-141 S.43E+0S 1.4SE+07 1 48E+07-1 43E+07 8.99E+07 61 43.. Ch mm. fM

FARLEY NUCLEAR PLANT TABLE 9a DISPERSION PARAMETER D7i)T r Distance to the control location, in miles Sector 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.2E-06 6.9E-07 4.8E-07 3.lE-07 2.lE-07 1,.6E-07 1.2E-07 1.OE-07 9.lE-08 7.6E-08 NNE 2.4E-06 7.4E-07 4.8E-07 3.0E-07 2.0E-07 1.5E-07 .l.lE-07 9.2E-08 8.3E-08 6.8E-08 NE 2.2E-06 7.lE-07 4.8E-07 3.lE-07 2.0E-07 1.6E-07 1.2E-07 9.6E-08 8.6E-08 7.lE-08 ENE 1.lE-06 4.0E-07 3.2E-07 2.2E-07 1.5E-07 1.2E-07 9.3E-07 7.6E-08 6.9E-08 5.7E-08 E 1.2E-06 4.0E-07 3.0F-07 2.0E-07 1.4E-07 1.lE-07 8.5E-08 7.lE-08 6.4E-08 5.4E-08 ESE 1.5E-06 4.5E-07 3.0E-07 2.0E-07 1.3E-07 1.lE-07 8.lE-08 6.7E-08 6.lE-08 5.lE-08 SE 2.5E-06 6.6E-07 4.4E-07 2.8E 1.9E-07 1.5E-07 1.lE-07 9.5E-08 8.6E-08 7.3E-08 SSE 2.8E-06 7.6E-07 5.3E-07 3.5E-07 2.4E-07 2.0E-07 1.5E-07 1.3E-07 1.lE-07 9.8E-08 S 2.5E-06 6.6E-07 4.9E-07 3.4E-07 2.4E-07 2.0E-07 1.5E-07 1.3E-07 1.2E-07 1.0E-07 SSW 2.0E-06 6.7E-07 5.lE-07 3.3E-07 2.3E-07 1.8E-07 1.4E-07 1.2E-07 1.2E-07' l.0E-07 SW 2.0E-06 8.lE-07 6.4E-07 4.0E-07 2.7E-07 2.lE-07 1.6E-07 1.3E-07 1.3E-07 1.lE-07 WSW l.9E-06 7.4E-07 5.9E-07 3.7E-07 2.SE-07 1.9E-07 1.6E-07 1,3E-07 1.lE-07 9.3E-08 W l.7E-06 6.lE-07 5.0E-07 3.2E-07 2.lE-07 1.7E-07 1.7E-07 1.3E-07 1.2E-07 9.7E-08 WNW l.4E-06 4.5E-07 3.4E-07 2.8E-07 1.9E-07 1.7E-07 1.7E-07 1.4E-07 1.2E-07 9.8E-08 NW l.3E-06 4.3E-07 3.2E-07 2.2E-07 1.5E-07 1.4E-07

1. 2E- 07 1.2E-07 1.lE-07 8.7E-08 NNW l.7E-06 5.5E-07 4.0E-07 2.6E-07 1.8E-07 1.4E-07 1.lE-07 1.0E-07 9.4E-08 7.8E-08 Note: Values are based on the joint frequency data between 1971 and 1975.

u A L -!

FARLEY NUCLEAR PLANT TABLE 9b - - DISPERS!0t1 PARAMETER (X/Q)__ ~ g Distance to the control location, in miles Sector 0 - 0. F_ 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 7.3E-05 1.3E-05 5.8E-06 2.9E-06 1.6E-06 1.2E-06 8.2E-07 6.lE-07 5.4E-07 4.2E-07 NNE 6.2C-05 1.lE-05 4.9E-06 2.4E-06 1.4E-06 1.0E-06 6.9E-07 5.lE-07 4.5E-07 3.5E-07 NE 5.JE-05 1.lE-05 4.7E-06 2.3E-06 1.3E-06 9.5E-07 6.5E-07 4.8E-07 4.2E-07 3.3E-07 ENE 5.3E-05 9.6E-06 4.2E-06 2.lE-06 1.2E-06 8.6E-07 .5.9E-07 4.4E-07 3.8E-07 3.0E-07 E 6.3E-05 1.lE-05 4.9E-06 2.4E-06 1.4E-06 1.0E-06 7.lE-07 5.2E-07 4.6E-07 3.6E-07 ESE 6.2E-05 1.lE-05 4.7E-06 2.4E-06 1.4E-06 1.0E-06 7.0E-07 5.2E-07 4.6E-07 3.5E-07 SE 9.5E-05 1.6E-05 7.2E-06 3.8E-06 2.lE-06 1.5E-06 1.lE-06 8.0E-07 7.0E-07 5.5E-07 SSE 1.4E-04 2.5E-05 1.lE-05 5.5E-06 3.2E-06 2.3E-06 1.6E-06 1.2E-06 1.lE-06 8.4E-07 S 1.5E-04 2.6E-05 1.2E-05 5.9E-06 3.4E-06 2.5E-06 1.8E-06 1.3E-06 1.2E-06 9.0E-07 SSW 9.8E-05 1.7E-05 7.5E-06 3.7E-06 2.2E-06 1.6E-06 1 lE-06 8.2E-07 7.2E-07 5.6E-07 SW 7.4E-05 1.3E-05 5.8E-06 2.9E-06 1.6E-06 1.2E-06 8.3E-07 6.lE-07 5.4E-07 4.2E-07 WSW 6.0E-05 1.lE-05 4.8E-06 2.3E-06 1.3E-06 9.6E-07 6.7E-07 4.9E-07 4.3E-07 3.3E-07 W 5.8E-05 1.0E-05 4.5E-06 2.2E-06 1.3E-06 9.2E-07 6.4E-07 4.7E-07 4.lE-07 3.2E-07 WNW 5.6E-05 9.9E-06 4.4E-06 2.2E-06 1.2L-06 8.9E-07 6.2E-07 4.6E-07 4.0E-07 3.lE-07 NW 5.9E-05 1.0E-05 4.5E-06 2.2E-06 1.3E-06 9.3E-07 6.4E-07 4.7E-07 4.2E-07 3.2E-07 NNW 6.6E-05 1.2E-05 5.2E-06 2.6E-06 1.5E-06 1.lE-06 7.5E-07 5.5E-07 4.9E-07 3.8E-07 U tiote: Values are based on the joint frequency data between 1971 and 1975. .h. CN s

( FARLEY NUCLEAR PLANT TABLE 9c I DISPERSION PARAMETER (D/4T r Distance to the control location, in miles Sector 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 3.8E-08 .l.lE-08 5.0E-09 2.3E-09 1.3E-09 8,.7E-10 5.6E-10 3.9E-10 3.4E-10 2.5E-10 Nf1E 4.6E-08 1.3E-08 5.7E-09 .7E-09 1.4E-09 9.9E-10 6.4E-10 4.4E-10 3.8E-10 2.9E-10 NE 4.8E-08 1.3E-08 5.9F.-09 2.8E-09 1.5E-09 1.0E-09 6.6E-10 4.6E-10 4.0E-10 3.0E-10 Et1E 2.7E-08 8.2E-09 3.7E-09 1.7E-09 9.4E-10 6.6E-10 4.2E-10 3.0E-10 2.6E-10 1.9E-10 E 2.9E-08 8.5E-09 3.7E-09 1.8E-09 9.5E-10 6.6E-10 4.2E-10 3.0E-10 2.5E-10 1.9E-10 ESE 3.3E-08 9.2E-09 4.0E-09 .l.8E-09 9.9E-10 6.9E-10 4.4E-10 3.lE-10 2.7E-10 2.0E-10 SE 5.3E-08 1.4E-08 5.9E-09 2.7E-09 1.5E-09 1.0E-09 6.5E-10 4.5E-10 3.9E-10 2.9E-10 SSE 5.lE-08 1.4E-08 6.2E-09 2.9E-09 1.5E-09 1.lE-09 6.8E-10 4.8E-10 4.lE-10 3.lE-10 S 4.9E-08 1.4E-08 5.9E-09 2.7E-09 1.5E-09 1.0E-09 6.5E-10 4.6E-10 3.9E-10 2.9E-10 SSW 4.3E-08 1.3E-08 5.8E-09 2.7E-09 1.5E-09 1.0E-09 6.4E-10 4.5E-10 3.9E-10 2.9E-10 SW 4.7E 08 1.5E-08 6.5E-09 3.0E-09 1.6E-09 1.lE-09 6.9E-10 4.8E-10 4. l E-- 10 3.lE-10 WSW 4 SE-08 1.5E-08 6.lE-09 2.8E-09 1.5E-09 1.0E-09 6.5E-10 4.5E-10 3.9E-10 2.9E-10 W 4.0E-08 1.2E-08 5.3E-09 2.5E-09 1.3E-09 9.0E-10 5.9E-10 4.lE-10 3.5E-10 2.7E-10 WNW 3.2E-08 9.4E-09 4.lE-09 2.0E-09 1.lE-09 7.3E-10 4.9E-10 3.5E-10 3.0E-10 2.4E-10 NW 2.8E-08 8.2E-09 3.6E-09 1.7E-09 9 lE-10 6.4E-10 4.lE-10 1.9E-10 2.5E-10 1.9E-10 NNW 3.2E-08 9.6E-09 4.4E-09 2.0E-09 1.lE-09 7.7'~10 4.9E-10 3.4E-10 3.0E-10 2'.2E-10 Note: Values are based on the joint frequency data between 1971 and 1975. u W i J1

PARLEY NUCLEAR PLANT. TABLE 9d ___ DISPERSI0tl PARAMETER ID/Q) 9 Distance to the control location, in miles Sector 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.5E-07 4.-lE-08 1.5E-08 6.3E-09 3.3E-09 2,.2E-09 1.4E-09 9.8E-10 8.3E-10 6.lE-10 NNE 2.5E-07 4.lE-08 1.4E-08 6.3E-09 3.2E-09 2.2E-09 1.4E-09 9.7E-10 8.2E-10 6.0E-10 NE 2.5E-07 4.lE-08 1.4E-08 6.3E-09 3.2E-09 2.2E-09 1.4E-09 9.7E-10 8.2E-10 6.lE-10 ENE 1.7E-07 2.8E-08 9.8E-09 4.3E-09 2.2E-09 1.5E-09 9.8E-10 6.6E-10 5.6E-10 4.lE-10 E 1.7E-07 2.8E-08 9.8E-09 4.30-09 2.2E-09 1.5E-09 9.8E-10 6.6E-10 5.6E-10 4.lE-10 ESE 1.8E-07 2.9E-08 1.0E-08 4.5E-09 2.3E-09 l.6E-09 1.0E-09 6.9E-10 5.8E-10 4.3E-10 SE 2.8E-07 4.5E-08 1.6E-08 7.5E-09 3.6E-09 2.4E-09 1.6E-09 1.lE-09 9.lE-10 6.7E-10 SSE 3.7E-07 6.0E-08 2.lE-08 9.3E-09 4.8E-09 3.2E-09 2.lE-10 1.4E-09 1.2E-09 8.9E-10 S 3.7E-07 6.0E-08 2.2E-08 9.4E-09 4.8E-09 3.3E-09 2.lE-09 1.4E-09 1.2E-09 9.0E-10 SSW 2.8E-07 4.5E-08 1.6E-08 7.0E-09 3.6E-09 2.4E-09 1.6E-09 1.lE-09

9. lE- %

6.7E-10 SW 2.6E-07 4.3E-08 1.5E-08 6~.6E-09 3.4E-09 2.3E-09 1.5E-09 1.0E-09 8.6E-10 6.3E-10 WSW 2.3E-07 3.8E-08 1.3E-08 5.8E-09 3.0E-09 2.0E-09 1.3E-09 9.0E-10 7.6E-10 5.6E-10 W 2.lE-07 3.4E-08 1.2E-08 5.3E-09 2.7E-09 1.9E-09 1.2E-09 8.3E-10 7.0E-10 5.lE-10 WNW l.8E-07 3.0E-08 1.lE-08 4.6E-09 2.4E-09 1.6E-09 1.lE-09 7.2E-10 6.0E-10 4.4E-10 NW l.7E-07 2.8E-08 1.0E-08 4.4E-09 2.3E-09 1.5E-09 1.0E-09 6.8E-10 5.7E-10 4.2E-10 NNW 2.lE-07 3.5E-08 1.2E-08 5.4E-09 2.8E-09 1.9E-09 1.2E-09 8.3E-10 7.0E-10 5.2E-10 flote: Values are based on the joint frequency data between 1971 and 1975. vs b CN

3.11.2.5 Cose Assessment for Environnental Raciation Stancares The Radiciogical Effluent Technical Soecification 3.11.2.5 specifies in the Acti:r. thct nsn the calculated doses associated witn tne efflu-ent releases exceed - tice the limits of any one of the Specifications 3.11.1.2, 3.11.2.2 or 3.11.2.3, it is required to precare and submit a Special Report to the Commission and limit suosequent releases such that the dose or case commitment to the critical individual frcm all uranium fuel cycle sources is limited to 5 25 mrem to the total body or any organ (except the thyroid, which is limited to 5 75 mrem) over 12 consecutive months. ~ The dose assessment which will be described in a Special Report, shall include dose contributions from direct radiation from the plant and its components. A variety of techniques is available for assessing this contri butio n. A simole calculation may be sufficient to demonstrate that the contribution is unimportant, or conditions may dictate more complex analyses. The most appropriate assessment technique will be determined in the course of preparing the Special Report and will be documented in the Special Report. (\\. ~. p I 346 177 ~

s

OfACuAA77DA/ OF GONG 7/NT FOR .DOSEASUAT/DNS /M ODC/id SEGM/VS 7. //. 2.2 ANb 8. //. 2 3 w Dey = //0 f A1; q, Af; OWQ);gyQ,,} g PUMERS MRAD /m fl.; = bo!E FA070A 3 pe;/si i bh = REAEASE 7ws, MouMS p I X,/ =. At//AAff A74/DrN/ Me L /jeV bl6PERS/W /~Ad7aA, SEE/# AVERAGC REdanCE RArn, si&/sse &jt = .i AfAAWPA . HMS. sJe . Idi . ? /bCb6 9 =. Y p6/m3 At3 SJe \\ 7. 'M to U d R //4/.2 AfAnh = T//US, et Det = //hl-2$O f bklhY '8V hyi/ sq cl= l -l g UNITS ceNVEncloAlCCAMM7 346 178

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+ F09 AGE S A MPLIN G A TLD SAMPLING @ TLD, PARTICULATES 8 IOCINE SAMPLING .O W mo KALL A FEL1 FIGURE 3.12-1 IN DIC ATOR S AP!PLING LOC ATIONS FOR AIR 60RNE ENVIRONMENTAL R A 010 AC TI VI T Y AT TH E FA R L E Y NUCL E A R PL ANT. 346 179

R@ I @Wra 3 n, m,9C' 9= 7 I ~ a n ~. a D NA S G E G N I T N AI L G LL r, P NUP n MI CM, L IA A P T m / S MRS L / i EAA s G S PE A h y j" RDDi D n OLL0 FTT1 u .;a x + AbQ 'w ,E E 5S [\\ E L x .s / l g' a \\ / N 2,, / a t x& b,' I A I A Q Y A T I E V R i R T gE d OC N E T F A 7 i N , f& C N 3 O w SI A y - lI m# I R ND L I O A / /' P g ? T R L p ,y A A A T E O N / - q f' L L E N C ,S M ~ ~ G U b N N N a x/ I O K to u .\\ LRl Y c P vE MJ L \\/\\ .N A E'. R q' S A ~ i L5 W EF 5N N r / w LN '1 O RE r "\\ f d S R OH o T BT \\

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LUMBIA \\ 52 52 ANDREWS LOCK a DAM , FARLE 10 MILES / ,/ D @'S p E ARLY COUNTY GEORGI A ASHFORD 's ia GORDON; " 8. g, __

  • e HOUSTON COUNTY k

ALABAMA m, INDIC ATOR STATIONS CONTROL STATIONS E SURFACE AND GROUND WATER SURFACE WATER AND FISH FISH AND SEDIMENT GROUND WATER FIGUR E 3.12-3 INDICATOR AND CONTROL SAMPLING LOC ATIONS FOR WATERBORNE ENV'RONMENTAL RADIOACTIVITY IN THE FARLEY NUCLE AR PLANT AREA. , eg

N O ITAC 8 1 1 1 58 I 1 11 5 F 0 00 1 0 00 1 1 1 I 1 76 2 2 1 76 2 2 T 1 01 0 1 1 01 01 N E D I I I I BB I I I BB P PP PP I I I I I EL PM A S S N O I TACOL ) )

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TABLE 3.12-1 (Contd). EXPOSURE PATHWAY AND/OR SAMPLE SAMPLING LOCATIONS SAMPLE IDENTIFICATION 2. Direct Radiation Indi ca to r S ta tions : Plant Pe rime te r (NE-1.0) RI - 0201 ( E-0.8) RI - 0401 (SSE-1.0) RI - 0 701 (S-1.0) RI - 0801 (SW-0.9) RI - 1001 (WSW-0.9) RI - 1101 (NUW-0.9) RI - 1501 (N-0.8) RI - 1601 Control Sta tions : Blakely, Ga. (NE-15) RR - 0215 Neals Landing, Fla. RB - 0718 (SS E-18) Do than, Ala. (W-18) RB - 1218 3. WATERBORNE a. Surface Indicator S tation: Great Southern Paper WRI Intake Struc ture (River M11e-40) Control S tation: Andrews Lock & Dam Upper Pier (River Mlle-47) WRB L> b. Ground Indicator Station: P-Great Southern Paper C3' Co.Well (SSE-4) WGI - 0 7 Control S ta tion: cry Kings Court T rail er WCB - 12 (;4 Park (WSW-0.9) l I i e

N O ITAC I 11 8 F 00 1 I 0 76 2 T 1 01 1 N 1 E 1 3 D I I I BB I S B GB CB I I B R M FF FF FF F ELPM A S i ) 1 ) ) 4 7

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