Text

Technical Instruction 47, Offsite Dose Calculation Manual
	ML20081J171
Person / Time
Site:	Browns Ferry
Issue date:	01/04/1983
From:	; TENNESSEE VALLEY AUTHORITY
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ML20081J143	List: ML20081J141; ML20081J154; ML20081J171;
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	BF-TI-47, NUDOCS 8311080332
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{{#Wiki_filter:- _ ~ ENCLOSURE 5 Q TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT i / x ', ^ / + ~ TECHNICAL INSTRUCTION NO. 47 ~ OFFSITE DOSE CALCULATION MANUAL (ODCM) O.

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t JAN 41983 {~~ Table of Contents u 1.0 Gaseous Effluents... 1 1.1 Alarm / Trip Setpoints 1 1.1.1 ' '.' Release' Rate? Limit M.ethodology pCi/s I f s y .r. f _- ... ~ A. 4 Noble gases-ass $cptions and equations 2 n 4 ._7' 1,.. n p e.. Radioiodines and particulates--assumptions and 3 5 ',c. - i [, equations U.,,....... } .g

$ 1. 'L Mont'nly. Dose Calculations.

13 { h* _ M,s s L

2.1 Noble Gases.

....../-.............. 14 (. 1.2.2 Iodines and Particulates 18 1 . ~ $] 1.3 Quarterly and Annual Dose Calculations. 20 1.4 . Gaseous Radwaste Treatment System Operation. 21 f' ("] t 1.4.1

System Description

21 ,. s.,i s 1.4.2 Dose Calculations. 21 ......i....... y.: 2.0 , Liquid EfG n hts'.,. 48 3 r. s,***

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7~,' 'Concent'T.stion}. y 2.1 48 A ,l t o REIP Re,q6irls.eht a 2.1.1 48 .,s. i >1r. c 2.1.2 Prerele!se' Analysis. 48 k 2.1.3 MPC-Sum'o,f,the Ratios. 48 i 2.2 Instrument Setpoints 49 / 2.2.1 .Setpoint Determination 49 2.2.2 Post-Release Analysis. 50 2.3 Dose 50 ,x.;, ~ 2.3.1 RETS' Requirement 50 d I 2.3.2 Monthly Ana/-lysi.s 51 1 n s Wate,r.Inge,stion....................... p 2.3.2.1 51 ^ s / 2.3~.2.2 Fis,h Inpstion 52 _g w ,, c w., - O f f. ).y-ci { l' [ _,,d~_. 4- - + < ~ ~ = ' + - '-' -'" ~ "

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2.4.11

> Release Limit. 55 p-x 3.0 Radiological Environmental Monitoring. 63 i -' 3.' 1 - Monitoring Program 63 ~ n. 3.2' ' Detection Capabilities 63 s hi s '. 3.3. s.N, Nonroutine' Reports 63 f ,i. y s -e

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~ Page i BF TI 47 JAN 41983 V ~ Gaseous Effluents 1.0- ~ .l.1 Alarm / Trip Setpoints Technical Specification 3.8.B.1 requires that the dose rate in unrestricted areas (see figure 1.1) due to gaseous effluents from the BFN site shall be limited at all times to the following values. ~~ 1. 500 mrem /yr to the total body and 3,000 mrem /yr to the skin from noble gases. 2. 1,500 mrem /yr to any organ from radioiodines and particulates. Technical Specification 3.2.K.1 requires gaseous effluent monitors to have alarm / trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to del' ermine these setpoints. r- . png. f t The methodology for determining alarm / trip setpoints is divided into Q) two major parts. The first consists of backcalculating from a dose rate to a release rate limit relation for each nuclide type and release point. The second consists of using the release rate limit relations to determine the physical' settings on the monitors. The methodology for the latter is contained in Technical Instruction 15. 1.1.1 Release Rate Limit Methodology - pCi/s Step'1 . The first step involves calculating.a dose rate based on the design objective source term mix used in the licensing of the plant. His- 'torical meteorological data used are in this calculation. Doses are determined for (1) noble gases and (2) iodines and particulates. Depending on the pathway involved, either air con-l (,). centrations or ground concentrations are calculated. Figures 1.2 \\. W j

A Page 2 BF TI 47 JAN 41983 n},,( - and 1.3 show the Offgas System, Standby Gas Treatment System, and - normal building ventilation with effluent monitors located. A. Equations and assumptions for calculating doses from

noble gases are as follows:

Assumptions Doses to be calculated.are total body and skin. 1. 2. Exposure pathway is submersion within a cloud of noble gases. u 3. Noble gas radionuclide mix is based on the expected source term given.in table 1.1. ~ 4. Basic radionuclide data are given in uable 1.2. 5. Releases are treated as ground level, split level, or elevated. ' 6. Meteorological-data are expressed as joint frequency distribu-tions (JFDs) of wind speed, wind direction, and atmospheric em IL,-} - stability for the period January 1974 to December 1975 (table 1.3). Releases from the turbine building are treated as 100 percent ground level, whereas stack releases are considered 100 percent elevated. Releases from the. reactor building and radwaste build-ing are treated as split level, i.e., partly elevated and partly ground level. 7. Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 10 m and temperature measurements of 10 m and 45 m. The ground-level portion of the split-level JFD was based on wind speeds and directions ~~ measured at the 10-m level and temperature measurements at 10 m and 45 m. The elevated portion of the split-level JFD was based on wind speeds and directions measured at 46 m and tempera-7% ture measurements at 45 m and 90 m. Windspeeds and directions N _) t pm

Page 3 BF TI 47 JAN-41983 for elevated releases were measured at'93mm. Stability class D hi .\\m,j was assumed to persist during the entire period for elevated releases. 8. Dose is to be evaluated at the nearest land site boundary point .in each sector and at other locations expected to be maximum exposure points. .g. =9. . A. semi-infinite cloud model is used. - The use of a finite cloud model~would result in calculated doses of less than 3 percent '~ ' higher than those calculated using the semi-infinite cloud 4 model for BEN. 10. No credit is taken for shielding by residence. 11. . Plume depletion (figure 1.4) and radioactive decay are con-sidered consistent with Regulatory Guide 1.111 methodology. 12. Building wake effects on effluent dispersion are considered. ~ ~ ( )' 13. A sector-average dispersion equation is used. 1 <14. The wind speed classes that are used are as follows: Number Range (m/s) Midpoint (m/s) 1 <0.3 0.13 ~~ 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.80 6 3.4-5.5 4.45 7 5.6-8.2 6.91 9 >10.9 13.00 15. The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond . f-')s. ^(_ to A=1, B=2,..., G=7. a.

Page 4 BT TI 47 .JAN 4198 / i ) 16. Terrain elevations are considered. Ecuations To calculate'the dose from radioactive effluents discharged from a given release point for any one of the 16 potential maximum-exposure ~~ points, the following equations are used. For determining the air concentration of any radionuclide: 9-7 / 1 'j k O P E i "j) exp (-he /2U ~1'} i exp ( _g X_, i in, -I u (2nx/n) ~ g (1.1) where ~ = air concentration of radionuclide i, pCi/m, a xi f.k. = joint relative frequency of occurrence of winds in j .m wind speed class j, stability class k, blowing toward ) this exposure point, expressed as a fraction. Q = average release rate of radionuclide i, pCi/s. g p = fraction of radionuclide remaining in plume, figure 1.4, consistent with Regulatory Guide 1.111 methodology. I = vertical disperson coefficient for stabliity class k which zk includes a building wake adjustment, Izk * ("zk + 0.5A/n)*, where a is the vertical dispersion coefficient for stabilit: k class k (m), and A is the minimum building cross-sectional 2 area (2,350 m ),, u. = midpoint value of wind speed class interval j, m/s. J x = downwind distance, m. n = number of sectors,16. b) A = radioactive decay coefficient of radionuclide i, s 1 \\e g 2nx/n A sector width at point of interest, m.

Page 5 BF TI 47 ~ JAN 41982 []' h,- = effective release-height, m. V .For effluents exhausted from release points that-are higher than twice the height of adjacent structures (elevated releases) the effective release height is determined by the following equation, consistent with Regulatory Guide 1.111 h =h+h -h -c (1.la) ~= c s pr t where = correction for low relative exit velocity, c = 3(1.5-W /u) d, c where W, = vertical plume exit velocity (m/s), u = mean wind ~ speed (m/s), and d = inside diameter of the release point, m. h l = P ume rise above release point as determined by the Briggs pr equations given'in Sagendorf (ERL ARL-42), m. h', = physical height of release point, m. h. = maximum terrain height between release point and receptor g location, m. For effluents released from points less than the height of adjacent structures, a ground level release is assumed (h, = 0). ~For effluents released from points at the level of or above adjacent structuras, but lower than elevated release points, releases are treated as follows: Case 1 - elevated if W /u > 5 Case 2 ground level (h, = 0) if W /u < 1. , Case 3 - split level if 1 < W /u < 5. Under Case 3 a split-level dispersion approach is implemented using a model that requires for each release point two JFDs, one for elevated releases and one for ground-level releases. The summation of the elevated . f. .q \\j and. ground-level JFDs account for the total period of record. Releases

Page 6 BF TI 47 e :- JAN 41983 yby ' are considered to be elevated 700 '(1-E ) percent of the time and ground level 100 E percent of the time where the entrainment coefficient, E, t "~ is defined by E = 2.58 - 1.58 (W /u) for'l < W /u $ 1.5 (1.lb) t ~ .E 0.3 - 0.06 (W /u) for 1.5 < W /u 5 5 (1.lc) t ~ For determining the total body dose rate -D = X DFB (1.2) TB i g i-where D = total body dose rate, mrem /yr. TB a X. -= air concentration of radionuclide i, pCi/m, 1 g s 'A) DFB. = total body' dose factor due to gamma radiation, mrem /yr per 1 pCi/m3 (table.l.5). ~ For determining the skin dose rate X. [DFS. + 1.11 DFT.] (1.3) ' D = S 1 1 1 i where D = skin dose rate, mrem /yr. s 3 ~ X = air concentration of radionuclide i, pCi/m. i 3 j. DFS. = skin dose factor due to beta radiation, mrem /yr per pCi/m 1 (table 1.5). [. DFT = gamma-to-air dose factor for radionuclide i, mrem /yr per g pCi/m3 (table 1.5). l.11 = the average ratio of tissue to air energy absorption coefficient. [. s. e .. _. _,.. -. _ -, _. ~.. _ - _ _,... _., - _... _ _, _. _ -.. _ _... ~. _, _. _.. -. _. _ _ _ _ _ _ _.. _.........,.... -.

Page 7 BF TI 47 7, JAN 41982 m- 't i i,,j The above dose calculations.are repeated for each release point (vent .or stack)fand then summed to obtain maximum total' body and skin dose 7 rates. The maximum-total body and skin dose -rates will 'then be used in step 2. -B. Equations and assumptions for-calculating doses from radioiodines and particulates are as follows: Assumptions, same as 1.1.1.A, except: l. Dose is'to be calculated for the critical organ, thyroid, and the critical age group, infant. 2. Exposure pathways from iodines and particulates are milk inges-tion, ground contamination, and inhalation. 3. The radioiodine and particulate mix is based on the expected source term given in table 1.1.

-~ (A

) 4.- Real cow and garden locations are not considered. 2:( 5. . Deposition is calculated based on the curves given in figure-1.5. Regulatory Guide 1.111 [ ~ Equations To calculate the-dose from radioactive effluents discharged from a given release point for any one of the potential maximum-exposure points, the.following equations are used. 1. Inhalation I Equation for calculating air concentration, x, is the same as in the Noble Gas Section, 1.1.1.A. For determining the thyroid dose rate: D = 1 x 10 8 X. DFI. (1.4) THI i 1 t /N l tx_ / -1 i w neup _ _ _ _, _ _ - ~ _.

Page 8 BF TI 47 ' ~ JAN 41982 n(a/ where D_.. = thyroid dose rate due to inhalation, mrem /yr. 181 3 Xg = air: concentration of radionuclide i, pCi/m. 3 DFI = infant inhalation dose factor,-mrem /yr per pCi/cm, g ~ based on Regulatory Guide 1.109 dose commitment factors 3 (mrem /pci).and an assumed 1400 m /yr infant breathing 4 rate. ~ 1x10 6- = m /cm3 conversion-factor. 3 2. Ground Contamination ~ - For determining the ground concentration of any nuclide: 7 7 I 9 E ~Si 'b)] (1.5) k 1 [1-exp 3.15x10 G 8. i (2nx/n) A.1 k=1 -(Aw} where 2 ~ -G = ground concentration of radionuclide i, pCi/m, g k = stability class. f = j int relative frequency of occurrence of winds in k stability class k blowing toward this exposure point, expressed as a fraction. i ~ Q. = average release rate of radionuclide i, pCi/s. 1 DR = relative deposition rate, m 1 (figure 1.5). The choice of figure is governed by the effective release height I - ' calculated by equation 1.la. A linear interpolation is used for effective release heights that fall in between e- ~~ the given curves. x = downwind distance, m. n = number of sectors, 16. ) v k. ~ 3 + _. _.. ~, --.2

Page 9 BF TI 47 JAN 41983 n i .. y) ~

2nx/n: = sector width et point of. interest, m.

-A = radioactive deca 3 coefficient of radionuclide i, yr 1 g = time'for buildup of radionuclides on the ground, 35 yr. tb 3.15x107 =-s/yr conversion factor. For determining the thyroid dose rate from ground contamination: 8 D = (8,760) (1x10 ) G. DFG. (1.6) THG 1 1 i ~ where D = thyroid dose rate due to ground contamination, mrem /yr. THG 2 G = ground concentration of radionuclide i, pCi/m, g DFG = dose factor for standing on contaminated ground, mrem /h g per pCi/m2 (table 1.7). 8,760 '= occupation time, h/yr. b) q, lx108 = pCi/pCi conversion factor. 3. Hilk Ingestion For determining-the concentration of any nuclide (except H-3) ~~ f in and on vegetation: 9 DR f e)] CV = 3,600 k i rJ1-exp ~ Ei + (1.7) f ~' (2nx/n) [ Y A y Ei Bgy [1-exp (-Ag t )]I ~ 3 l P A. i-I where l CV = concentration of radionuclide i in and on vegetation, g [ pCi/kg. k = stability class. ~ f = frequency of this stability class and wind direction C k e i. \\_ combination, expressed as a fraction. L 5 I em

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~ 2 Page 10 BF TI 47 n JAN 4198 i i /- Qg = average release rate of radionuclide i, pCi/s. DR L= relative deposition rate, m 1 (figure 1.5). The choice of figure is governed by the effective release height calc'ulated by. equation 1.la. A linear interpolation is used for effective release heights that fall in between the given curves. 1 x = downwind distance, m. n- = number of sectors,'16. 2nx/n ~= sector width at point of interest, m. = fraction of deposited activity retained on vegetation, 0.47, r consistent with NUREG/CR-1004. I A = effective removal rate constant, AEi

i+

w, where Ag Ei is the radioactive decay coefficient, h 1, and A is a , - ~. y measure of physical loss by weathering (A = 0.0023 h 1 w for particulates and 0.0017 for iodines). t, = period over which deposition occurs, 720 h. J 2 Y = agricultural. yield, 1.18 kg/m. y 1- .B = transfer. factor from soil to vegetation of radionuclide i gy (table 1.6). ~~ A. = radioactive decay coefficient of radionuclide i, h l. 1 5 tb. = time for buildup of radionuclides on the ground, 3.07x10 h (35 yr). _ = P = effective surface density of soil, 240 kg/m. 2 3,600 = s/h conversion factor. For determining the concentration of H-3 in vegetation: -?_ CV = lx103 T XT (0.75)(0.5/H) (1.8) .,,/ where = chncentration of H-3 in vegetation, pCi/kg. CVT ' J-

Page 11 BF TI 47 i JAN 41983 3 X = air concentration of-H-3, pCi/m. 7 v a0.75 = fraction of; total plant mass th t is water. 0.5 = ratio of tritium concentration in plant water to tritium concentration in atmospheric water. ~~ 3 j - H = absolute humidity of the atmosphere, 9 g/m. 1x103 = g/kg conversion factor. .6 For determining the concentration of any nuclide in cow's milk: FM Q exp (~ i' f) CMg = CVf g g where CM. = concentration of radionuclide i (including H-3) in 1 a . cow's milk pCi/1. CV. = concentration of radionuclide i in and on vegetation, 1 pCi/kg. ' /'~ . ()h'_ EM. = transfer factor from feed to milk for radionuclide i, ~~ table 1.6,-d/1. Q = amount of feed consumed by the cow per day, kg/d. g A = radioactive decay coefficient of radionuclide i, d 1 g t = transport time of activity from milking to ingestion, g 1 day. For determining the thyroid dose rate from ingestion of cow's milk: 6 DTHM = lx10 CM. DFING. UM (1.10) i 1 i where D = thyroid dose rate due to milk ingestion, mrem /yr. THM Cil = concentration of radionuclide i in cow's milk, pCi/1. g l ) DFING. = infant ingestion dose factor from Reg. Guide 1.109 (/ 1 L(Rev. 1), mrem /pci. J ~~

Page 12 BF TI 47 js JAN 4198. ~i ) if UM. = infant ingestion rate for milk, 330 1/yr. lx108 = pCi/pCi conversion factor. 4. Total Thyroid Dose Rate For determining the total thyroid dose rate from iodines and i particulates: (1*III DTH = DTH1 + DTHG + DTHM where D = total thyroid dose rate, mrem /yr. TH. -D = thyroid dose rate due to inhalation,. mrem /yr. THI D = thyroid dose rate due to ground contamination, mrem /yr. THG D = thyroid dose rate due to milk ingestion, mrem /yr. THM The above dose calculations are repeated for each release point. [ Dose rates from building vents are summed. The calculated thyroid uM:- dose rates from the vents and stack will then be used in step 2. -Step 2 The dose rate limits of interest (10 CFR 20) are 500 mrem /yr. , Total Body = Skin = 3,000 mrem /yr. Maximum Organ = 1,500 mrem /yr. Dividing the above limits by the appropriate dose rates calculated in step 1 yields the.following ratios: Dose Rate Limit Dose Rate Limit = Vent Dose Rate step 1 Stack Dose Rate (Step 1) These ratios, R, represent how far above or below the guidelines the g ~ step 1 calculation was. Multiplying the original source terms Q g by the appropriate ratio R will give release rates, r, that will i 1 g result in the dose rate limits given above. Instantaneous, release rates (q1) for each nuclide type and release . point are now limited by the following equations: em .-..__.,,.-.,,..-._--.,.,--.._...,_.-_m._-_,..

k e Page 13 EF TI 47 a JAN 41981 .,--s ( ).: For noble gas releases: k, .92 <1 ~ 91 r r + 3 3 where .q3 = instantaneous release rate from building exhaust vents (Ci/s). I .q2 = instantane us release rate from main stack in Ci/s. a ~~ For iodines and particulates, half-lives > 8 days. 43 94<1 3 "4 where q3 = instantaneous release rate from building exhaust vents (pCi/s). t q4 = instantaneous release rate-from main stack (pCi/s). To simplify the dynamic operation of the plant, the dose rate limits were transformed into. conservative release rate limits based on histor-I~ ~ The values listed below were used as j Ng _ical source terms and meteorology. s '<I administrative guidelines for operation and development of alarm / trip setpoints (see Technical Instruction 15) to ensure that the instanteous dose rate limits are not exceeded. ,) Airborne Noble Gas Ha' logen and Particulate Elevated 0.68 Ci/s 1.96 pCi/s i i f Ground Level 0.13 Ci/s 1.61 pCi/s 1.2 Monthly Dose Calculations Dose calculations v'11 be performed monthly to determine compliance with specifications 3.8.P.3 and 3.8.B.S. These specifications require that the dose rate in unrestricted areas due to gaseous effluents from each j. reactor at the site shall be limited to the following values: l. For noble gases, t 1. During any calendar quarter, 5 mrad to air for gamma radiation and g-~g ) l - -[_ 10 mrad to air for beta radiation. ~~ j --

Page 14 BF TI-47 ~ . (< m. JAN 4198: ) 2. -During any calendar year,10 mrad to air' for gamma radiation and 20

y.

mrad to air for beta. radiation. For iodines and particulates, T1. During any calendar quarter, 7.5 mrem to any organ. ' ~ ~ ' 2. During any calendar year, 15 mrem to any organ. This sectionJof the ODCM describes the methodology that will be used to perform these monthly calculations. Doses will first be calculated by a simplified conservative approach -~ (step 1). If these exceed the specification limits, a more realistic calculation will be performed (step 2). 1.2.1 Noble Gases Step 1 Doses will be calculated using the methodology described in this step. (3J' If any limits are exceeded, step 2 will be performed. f Equations and assumptions for calculating doses from releases of noble gases are as follows: . Assumptions-1. Doses to be calculated are gamma and beta air doses. 2. The highest annual-average X/Q based on licensing meteorology for any offsite location'(not necessarily a site boundary location) = - - will be used. Elevated meteorology is assumed for stack releases. All other vent releases assume ground-level meteorology. 3. No credit is taken for radioactive decay. '4. For gamma doses, releases of Ar-41, Xe-138, Kr-87, and Kr-88 are consider ~ed. l-5. For beta doses, releases of Xe-133, Xe-138, Kr-85, Kr-87, and Kr-88 s _. s-) are considered. i_ L i 3

Page 15 BF.TI 47 ,J/LN 41983 - s-s (} .6. ' Dose factors.are calculated using data from TVA's nuclide library. 7. The calculations extrapolate doses ~ assuming that only 90 percent of' total dose was contributed. 8. A semi-infinite cloud model.is used. ~~' 9. Building' wake effects on effluent dispersion are considered. Equations ~ For determining the gamma dose to air: 6 _ (X/Q) 10 - Q. DFT. (1:12) U - 0.9 3.15x10' 1 T i .where D = gamma dose to air from continuous releases, mrad. T -X/Q = highest annual-average relative concentration, 2.26x10 6 4 3 s/m -(ground level), 1.8x10_s s/m3 (elevated). f-+ ( j 0.9 =[fractionoftotalgammadoseexpectedtobecontributed by these nuclides. Q = monthly release of radionuclide i, Ci. g DFT = gamma-to-air dose factor-for radionuclide i, mrad /yr per g 3 .pCi/m (table 1.5). Equation 1.12 reducts to: D = 7.97x10 8 Q. DFT. (ground level) (1.13) T 1 1 i D = 6.34x10 10 Q DFT (stack) (1.14) T. g g 1 -For determining the beta dose to air: i (x/Qf 106 Q*. DF. (1.15) D 8 0.9 3.15x10' i jg. 4 go ki l 5 MW t

t Page 16 Jh F h gg: ~ ~ - .,r'y it 1 where _1f D ^ .E_ =. beta dose to air, mrad.

x/Q '= highest annual-average relative concentration, 2.26x10 6 s/m3 (ground level), 1.8x10 8.s/m (elevated).

3 0.9 = fraction of total beta dose expected lto be contributed by these nuclides. ~ Q = monthly. release of radionuclide i, Ci. 1 DFp. = beta-to-air dose factor for radionuclide i, mrad /yr per 1 3 pCi/m (table 1.5). . u.. . Equation 1.15 then reduces to: D = 7.97x10 8 Q. DF. (ground level) (1.16) 1 1 i p = 6.34x10 10' Q DFp (stack) (1.17) D g g i i Step 2 This methodology is to be used if the calculations in Step 1 yield doses that. exceed applicable limits. Equations and assumptions for calculating doses'to air from releases of noble gases are as follows: Assumptions 1. Doses to be calculated are gamma and beta air doses. 2. Dose is to be evaluated at the nearest land site boundary point in each sector and at' other locations expected to be maximum exposure points. 3. Historical onsite meteorological data for the appropriate months from the period 1974-1975 will be used. Ov V asm J

Page 17 BF TI 47 JAN 4198.T I/ 4. All measured radionuclide releases are considered. N.)) 5. A semi-infinite cloud model is used. 6. Radioactive-decay is considered. 7. Building wake effects on effluent dispersion are considered. 8. Dose factors are calculated using data from TVA's radionuclide. library. Equations Equation for calculating air. concentration, X, is the same as in * - section 1.1.1, step 1, part A. Air concentrations are calculated fo'r the site boundary in each' sector. For determining the gamms dose to air 4 D =t X. DFT. (1.18) Tn m nr 1 i i~ ( ~ where A ~ D = gamma dose to air for sector n, mrad. Tn X. = air concentration of radionuclide i in sector n, nl 3 pCi/m. i DFT = gamma-to-air dose factor for radionuclide i, mrad /yr per g i pCi/m (table 1.5). 3 ~ t = time period considered, yr. For determining the beta dose to air: l D =t X. DFS. (1.19) 1 n m al 1 l 1 1. where Dg = beta dose to air for sector n, mrad. l 3 X. = air concentration of radionuclide i in sector n, pCi/m. l x., W f I -J ~ L.

t Page 18 BF TI 47 L~~, JAN 41983 2 "s DF. = beta to-air dose factor for radionuclide i, mrad /yr per 1 3 pCi/m (table 1.5). l t, =' time period considered, yr.

. The sector'having the highest total dose is then used to check com-spliance with specification 3.8.B.3.

1.2.2 Iodines and Particulates Step 1 c., - Doses will be calculated using the methodology described in this step. If any limits are ' exceeded, step 2 will be performed. Equations and assumptions for calculating doses frem releases of iodines and particulates are as follows: Assumptions ?, .l. Doses are to be calculated for the infant thyroid from milk ingestion \\' and for the child bone from vegetable ingestion. 2. - Real cow locations -are considered for the milk pathway and nearest resident locations with home-use gardens are considered for the - u.. ' vegetable pathway. ~~ 3. The highest annual-average D/Qs for any location (not necessarily a site boundary location) are used based on licensing meteorology. Elevated meteorology is assumed for stack releases. All other vent releases assume ground-level meteorology. 4. No credit is taken for radioactive' decay. ~- 5. I-131 releases are considered for the milk pathway. Sr-90 releases are considered for;the vegetable pathway. 6. The calculations extrapolate doses assuming that only 90 percent 1 of the total dose was contributed. '[ s}; 1s / 7. The cow is assumed to graze on pasture grass for the whole year. L emum ( J "~

1 Page 19 BF TI 47 JAN 41983 pj ' Equations

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For determining the thyroid dose from milk ingestion of I-131 9 /9 131 131 x 10 (1.20) om 131 7 (0.9) (3.15x10 ) where , bm. - DTH = thyroid dose from I-131, mrem. 131 Q = m nthly release of I-131, Ci. 131 11 DF = I-131 milk ingestion dose factor to infant, 7.24 x,10 131 2 ~ mrem /yr per pCi/m -s based on Regulatory Guide 1.109 and NUREG/CR-1004 dose methodologies. D/Q =. relative deposition rate, 7.26x10 10 2 (ground level); m 1.27x10 9 2 (stack). m 0.9 = fraction of total dose expected to be contributed by I-131. 7 ~ 3.15x10 = s/yr. ~ h3 j -(j 108 = pCi/Ci conversion factor Equation 1.20 reduces to DTII = 18.5 Q131 (ground level) (1.21) w 131 DH = 32.4 Q131 (stack) (1.22) 131 For determining the bone dose from vegetable ingestion: 108 Q DF D/Q = s s (1.23) l DBC l 3.15x107 (0.9) where DEC, = bone dose to child from Sr-90, mrem. ~ Q, = monthly release of Sr-90, Ci. DF, = Sr-90 vegetable ingestion dose factor to child, 1.36x1013 2 mrem /yr per pCi/m -s based on Regulatory Guide 1.109 amd NUREG/CR-1004 dose methodologies. C \\. M-mm6wos e o 6

m_. Page 20 F TI 47 JAN 4198: D/Q = relative deposition rate, 4.69x10 9 2 (ground level); 1/*w) ~ - m ' ' ~ ~ ' l.27x10 9 2 (stack) m 3.15x107 = s/yr conversion factor. 108 = pCi/Ci conversion-factor. 10.9 =. fraction of total bone dose expected to be contributed by Sr-90. ' ~ ~ Equation 1.23 reduces to DBC' = 2250 Q, (ground level) (1*. 24) s ~ DBC i = 609 Q, (stack) (1.25) s i Step 2 This methodology is to be used if the calculations in step 1 yield doses ~ ~ ' that exceed applicable limits. Doses for releases of iodines and particulates shall be calculated using /%c the methodology in section 1.1.1, step 1, part B, with the following t w./ exceptions: 1. All measured radionuclide releases will be used. 2. Doses will be evaluated at real cow and home-use garden locations l and will consider actual grazing information. The receptor having the highest total dose is then used to chech compliance with specification 3.8.B.5. l l l, 1.3 Quarterly and Annual Dose Calculations I I A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and -reported as required in specificatien 6.7.5. Methodology for this analysis is the same as that described in section 1.1.1, except that real pathways and receptor locations (table-l.4A) are' considered. In addition, meteorological 6 \\. em I

Page 21 BF TI 47 JAN 41983 ~~'T-data representative of each corresponding calendar quarter will be used. ~ (j. \\ This analysis will replace the estimates in section 1.2. At the end of each year an annual dose analysis will be performed by calculating the sum of the quarterly doses to the critical receptors. ~ ~ ' 1.4 Gaseous Radwaste Treatment System Operation The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep doses ALARA. 1.4.1

System Description

A flow diagram for the GRTS is given in figure 1.3. The system includes the subsystems that process and dispose of the gases from the main con-denser air ejectors, the startup vacuum pumps, and the gland seal con-densers. One gaseous radwaste treatment system is provided for each unit. The processed gases from each unit are routed to the plant stack for dilution and elevated release to the atmosphere. The air ejector off gas \\_ line of each unit and the stack are continuously monitored by radiation monitors. 1.4.2 Dose Calculations Doses will be calculated monthly using the methodology described in section 1.2. These doses will be used to ensure that the GRTS is Operating as designed. esas W emse W O w WW

Page 22 BF TI 47

~ JAN 4198: [l Table 1.1 \\_ / Expected Annual Routine Atmospheric Releases From One Unit at BFN Nuclear Plant -(Ci/Yr/ Unit) Stack Reactor Radwaste Turbine Gland Complex Building Building Seal and Isotope Vent Vent Vent Offgas MVP Kr-85m 6 <1 2 1.66 E4 0 Kr-85 630 Kr-87 6 <1 95 747 0 Kr-88 9' <1 102 1.35 E4 0 ~ Kr-89 1 34 503 4095 0 Xe-131m 309 Xe-133m - 0 60 0 851 0 Xe-133 103 294 581 9.47 E4 300 Xe-135m 111 667 464 917 0 Xe-135 173 328 672 599 200 Xe-137-78 113 386 5040 0 XE-138 12 2 1179 3150 0 I-131 I 0.0594 0.0050 0.0156 0.0041 0.0085 I-132 I 0.594 0.050 0.1786 0.0469 0.0973 I-133 I 0.297 0.025 0.1231 0.0323 0.0671 I-134 I 1.485 0.125 0.0267 0.0070 0.0145 ("'T I-135 I 0.594 0.050 0.1231 0.0323 0.0671 \\._ ' I-131 0 0.0316 0.029 0.0065 0.0332 0.2741 I-132 0 0.316 0.290 0.0744 0.3801 3.1384 ~~ I-133 0 0.158 0.145 0.0513 0.2619 2.1626 I-134 0 0.790 0.725 0.0111 0.0568 0.4687 I-135 0 0.316 0.290 0.0513 0.2619 2.1626 Cr-51 3 E-3 9 E-4 1 E-3 1 E-4 0 Mn-54 3 E-3 5 E-3 2 E-3 4 E-5 0 Co-58 2 E-3 4 E-4 9 E-5 2 E-5 0 Fe-59 1 E-4 8 E-4 4 E-4 2 E-4 0 Co-60 3 E-2 6 E-3 3 E-3 1 E-5 0 Zn-65 3 E-3 2 E-4 4 E-4 9 E-5 0 Sr-89 1 E-2 3 E-1 ~ 0 Sr-90 2 E-3 4 E-3 0 Nb-95 3 E-4 2 E-4 9 E-6 8 E-5 0 -Sr-95 1 E-4 1 E-4 8 E-6 8 E-5 0 Ru-103 3 E-5 1 E-4' 2 E-4 1 E-4 0 Ag-llom 7 E-6 0 Sb-124 3 E-5 3 E-4 6 E-5 8 E-5 0 Cs-134 5 E-3 3 E-4 5 E-4 2 E-5 0 Cs-136 2 E-3 5 E-5 1 E-4 9 E-8 0 Cs-137 7 E-3 4 E-4 2 E-3 7 E-4 0 Ba-140' 4 E-3 5 E-4 2 E-2 8 E-3 0 Ce-141 4 E-4 2 E-4 2 E-3 2 E-5 0 .Ce-144 5 E-6 4 E-6 0 Ar-41

5 0

0 0 0 2 (N C-14 0 0 0 9.5 0 A._, H-3 0 9.5 0 0 0

Not available.

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e r-
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i c i 1., i i JAN 4 883 i i i m v;,.i 1 i i y i i s - =.e. .., ~ ~. O ...,-c.O.. O. .g .o i -== ** O O U C== O O O O O O O O Ch Ca. 1 l l t i l l 'l I e. ^ l l .s t O I .i i i ] 4 O O. c c O. O O. O O O. C O O O O V .n e o e o e e e

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==
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....m t. Page 33 BF TI 47 'JAN 41983 Table 1.4A l Real Receptor Locations Nearest Home-Use Milch i - Sector' Resident (m) Garden (m)* Animal (m) N 1740 1740 7500 a NNE 2960 2960 NE - 3140 3140 10000 ENE 1920 1920 9688 E 4390 4390 ESE 4570 4570 a SE 8050 8050 1 SSE 7130 7130 l l ' ~ S 4330 4330 SSW 4050 4050 8001 p SW. 4880 4880 WSW 4050 4050 J W 2440 ,2440 WNW-4180 4180 NW 3124 3581 NNW 1620 1620 11250 . i
~~Home-use gardens are assumed to exist at nearest resident locations.~~
~ I .w J 4 _m - M 4 M .t
Page 34 TI 47 JN' N 4198.7 2 .,. k Table 1.5 Do::e Factors for Submersion in Noble Cases b b DFB" DFT DFS' DFE 1 -Kr-85m. 1.17(+3)C' 1.21(+3) 1.46(+3) 3.86(+3) .Kr-8'5 ' 1.61(+1) 1.69(+1) 1.34(+3) 3.83(+3) Kr-87 5.92(+3) 6.05(+3) 9.73(+3) 2.01(+4) Kr.l.47(+4) 1.50(+4) 2.37(+3) 5.72(+3) Kr-89 1.66(+4) 1.59(+4) 1.01(+4) 1.88(+4) Xe-131m 9.15(+1) 1.53(+2) 4.76(+2) 2.18(+3) { Xe-133m 2.51(+2) 3.17(+2) 9.94(+2) 2.90(+3) Xe-133 2.94(+2) 3.46(+2) 3.06(+2) 2.06(+3) j .Xe-135m 3.12(+3) 3.30(+3) 7.11(+2) 1.45(+3) Xe-135 l.81(+3) 1.88(+3) 1.86(+3) 4.84(+3) Xe-137 1.42(+3) 1.48(+3) 1.22(+4) 2.50(+4) Xe-138-8.83(+3) 9.00(+3)- 4.14(+3) 9.25(+3) Ar-41 8.84(+3) 9.76(+3) 2.69(+3) 5.54(+3) i-3 mrem /yr per pCi/m. 3 mrad /yr per pCi/m. 3 l 1.17(+3) = 1.17x10. i a 4 .w i , u ~ t ..m,.
Pa',"3 U Table 1.6 BF TI 47 JAN 4198t Radionuclide Transr.er Data s B m h i 'Is.m 3En estr.u rr- _ qE7En710, (veg/ soil) (d/1) i ,,7 a t ?'!w - 111 6.62E.01 6.7er.91 4.eaE.on 1.3st.o2 E.16 696 2.cor.qA 4.Fr.E.nl s,seE.ni 1.20F.62
.1 1 7a*
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Page 48 ~ BF TIl47 JAN 41993 j%,, 1 2.0-Liquid Effluents /l 2.1 Concentration 2.1.1 RETS Requirement Specification.3.8.A.1 of the Radiological Effluent Technical Specifi-cations (RETS) requires that the concentration of radioactive material released at any time from the ~ site to unrestricted areas (see figure 2.1) ~~ ~ 'shall be limited to the Maximum Permissible Concentration specified in 10 CFR 20, Appendix B, Table II, Column 2, for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x10 4 pCi/ml total activity. To ensure compliance, the following approach will be used ~~ for each release. 2.1.2 Prerelease Analysis Prior to release a grab sample will be analyzed for the concentration ,-ss '(h.s)' of each radionuclide. n C= )[ C (2.1) f i=1 4 -~- where C = total concentration in the liquid effluent, pCi/ml' C =-concentration of radionuclide i, pCi/ml. g 2.1.3-MPC-Sum of the Ratios . The sum of the ratios (R ) for the release will be calculated by 3 the following relationship. C C C C A +1 B i n (2.2) R= +, .s,. MPC MPC MPC,,,, MPC A B g -O E bW . j .t -e.- r,.. -,,,,.m .-,,v-- ..-,-n
Page 49 -t . r. JF TI 47 ~~ cAN 41981 ( ), .where u-Cg = undiluted effluent concentration of radionuclide i, as determined for section 2.1.2, pCi/ml. MPC = the MPC of radionuclide i,.pCi/ml (10 CFR 20 - Appendix B, g ~ Table II, Col. 2) -{ R = the sum of the concentration ratios for the release. For prerelease and post-release analysis the radionuclides present in the sample are first assumed to be unknown and the MPC after dilution at the site boundary is then lx10 7 pCi/ml gross radioactivity. If the ~ R calculated is too' large for equation 2.3, then the appropriate MPC; will be used with each C. to determine the actual MPC fraction and com-1 pare.to the 10 CFR 20 limit of 1. There is one liquid release point into the discharge canal by one of three possible modes. ^ / ..____.open - 3 pumps @ 200,000 gpm/ pump------- .%/. adwaste - ------helper - 3 pumps @ 150,000 gpm/ pump------ Discharge

~~closed - 5 0,000 gpm --------------------~~

conduit The following relationship will ensure concentrations are within allowable limits. f(R-1) i N (2.3) m where f = the radwaste flow rate (gallons / minute) before dilution. R = the sum of the ratios of the release as determined by + equation 2.2. N = minimum dilution flow rate for prerelease analysis. 2.2 Instrument Setpoints L2.2.1 Setpoint Determination ~(n) The=setpoint for each liquid effluent monitor will be established V s. using plant instructions. Concentration, flow rate, dilution, J~
Page 50 PE TI 47 JAN 41983 - [ ') ~. principal gamma emitter, geometry, and detector efficiency are com-tv bined to give an equivalent setpoint in counts per minute (cpm). -The locations ar.d identification numbers for each liquid effluent radiation detector are shown in figure 2.2 and figure 2.0. The respective alarm / trip setpoints at each release point will be -s conservatively set such that equation 2.2 is satisfied. The methodology describing the setpoint determination is contained in Technical Instruction 45. 2.2.2 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in section 2.1.1 were not exceeded.
~~A composite list of concentrations (C ), by isotope, will be used with 1~~
the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) / during the release. The data will be substituted into equation 2.3 to (h ,/ demonstrate compliance with the limits in section 2.1.1. This data and setpoints will be recorded in auditable records by plant personnel. ~ " " 2.3 Dose-2.3.1-RETS Requirement Specification 3.8.A.2 of the Radiological Effluent Technical Specifi-cation (RETS) requires that the dose or dose commitment,to an individual from radioactive materials in liquid effluents released to unrestricted areas from each reactor (see figure 2.1) shall be limited: .a. During any calendar quarter to i 1.5 mrem to the total body and 0~ to-5 5 mrem to any organ, and b. During.any calendar year to 1 3 mrem to the total body and to $ 10 mrem to any organ. -["'} To ensure compliance, cumulative dose calculations will be performed at V least once per month according to the following methodology.
Page 51 BF TI 47 JAN 41982 t c. (v }- L 2. 3'. 2 Monthly Analysis ~ Principal radionuclides will be used to conservatively estimate the ^ monthly contribution to the cumulative dose. If the projected dose exceeds.section 2.3.1 limits, the methodology in section 2.3.3 will be implemented. The following radionuclides based on operational source terms contribute more than 95 percent of the total estimated dose to the total body and maximum organ for both water and fish ingestion. The maximum organ for i the ingestion pathway is the thyroid and for the fish pathway both the liver and gastrointestinal (GI) tract are considered. ~ H-3 - Sr-90 Cs-134 Na-24 Nb-95 Cs-136 Co-60 I-131 Cs-137 -s 7 ~.d 2n-65 I-133 A. conservative calculation of the monthly dose will be done according ..~~ to the following procedure. First, the monthly operating report con-taining the' release data will be obtained and the activities released of each of the above 11 radionuclides will be noted. This information will then be used in the following calculations. 2.3.2.1 Water Ingestion ~ The dose to'an individual from ingestion of water is described by the following equation. 11 _ D= 3 i 0 95 i=1 4 'aw I f
~~--r.y~~
~~+,---g, ,yme, .w.v -,-----,n-., ,..,w-==-w &w~~
~~--w~~
'- er v-wwt w w -e--+ve- '--e
Page 52 i- .i g n ,( where th D. = dose for the j organ from 11 radionuclides, rem. J j = the organ of interest (bone, thyroid, liver, GI tract, or total body). '~ 0.95 '= conservative correction factor, considering only 11 radio-nuclides. th DCF ) = adult ingestion dose commitment factor for the j organ g from the i'h radionuclide rem /pCi, see attached table 2.1. th I = monthly activity ingested of the i radionuclide, pCi. f ' ~ I is described.by t 365 A V ~ g g (2.5) i 12 u 6 where j 365 = days per year th A = activity released of i radionuclide during the month, g pCi. V ~= average rate of water consumption (2000 ml/d, R.G. 1.109) 12 '= months.per year u = total dilution water flow during releases, ml. j-6 = minimum diffuser pipe dilution (5) The dose equation then becomes 11 1.3x107 Dj= (DCF)f) x A mrem (2.6) g i=1 t' 2.3.2.2 Fish Ingestion The dose to an individual from the consumption of fish may be described a ' by equation 2.4 where I is described by t A B M g f pCi (2.7) i i u6 x .nsme ......_._.__..._..m..,_. , _, _.. _.. _. -..,. _, - _ _ _. ~.. _ _.,,, _ _
Page 53 EF TI 47 JAN 41983^ .,.x, -() where th A = activity released of i radionuclide during the month, g ~~ pCi. th B = fish concentration factor of i radionuclide pCi/g f pCi/ml (see attached table 2.1). 3 H = amount of fish eaten monthly (1.9x10 g). u = total dilution water flow during releases, ml. 6 = minimum diffuser pipe dilution (5). The dose equation 2.4 then becomes 4x105 1I A xB x DCF mrem (2.8) D f f g j= u i= If these calculated monthly doses exceed limits specified in section 2.3.1, then a more accurate and complete calculation will be done as described ' I in section 2.3.3. An annual check will be made to ensure that the monthly dose. estimates account for at least 95 percent of the dose calculated by ~ the method described in section 2.3.3. If less than 95 percent of the dose has been estimated, a new list of principal isotopes will be prepared or a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose ~is predicted. To simplify the dynamic operation of the plant, the dose rate limits ~ were transformed into conservative release rate limits based on histor-ical source terms. The values per unit listed below are used as admin-istrative guidelines for operations to ensure that the dose rate limits are not exceeded. Liquid (Administrative Limits) ,m 13 Ci/ quarter / Reactor Unit 26 Ci/ year / Reactor Unit r l
>I ,j. ,a: 1 1 Page 54 EF TI 47 j/ ,s // "JAN 41983 h,,.
~~2. 3.~ 3 Quarterly and A'nnual Analysis!~~
', [ '5 v< .'A com l tp e e analysis utilizing t$d tetal estir.ated liquid releapes for f ? each calendar quarter will be perfprmed -and reported as ' required. This analysis'will replace previous estimates calculated in'section 2.3.2 and' consists of the following approach. - The dose to the j'7' orga'n from m - radionuclides, D., is described by ^ J m ' { .- IJ, rem t( (2* 9) D = D.~. - j i=1 r m i {1 f(DCF)lj.. x I., rem j (2.10) = 1 i= / where t h * '- th-D.. = dose.to theijf forgan 'Irom the i radionuclide, rem. IJ ,,,.-=.s.i s j ;- ~ the organ of i' terest (bone, GI tract'/ thyroid, liver, and .j = u . ;,m 3,a to'tal bodf). l ,c .) adult,Lingestion doge commitment fact.cr for the ~j,th (DCF)ij.. = organ from the i,h radionuclide, rem /pCi (see attached table 2.1l). t - th I. = activity ingested of the i radionuclide, pCi. 1 I.,for water ingestion is described by 1 A. V n __t- ,i pCi -(2.11) F. d t andforfishingEstionI.isdescribedby ~ 1 A. B. n '/ + 1 1 , pC1-- (2.12) F d t where th 1 A. = activity released of i radionuclide during the release i .,s- -period, pCi., >\\ .Vl / t k
~~J-s~~
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f. ^#' 7 ^; Page 55 f -.-j + 444-7f .jj BF TI 47-J R,n.. /p.,9[) 4 JAN 41983 a Yf x ~ V'=averageratg)of/daterconsumption: ) ny 16 /; 6 } ,y 1 vy-v .y 'L2000 ml/d,fmhx. individual (RG 1.109) 2;g n , ;, v. 730bl/d', avg.-individual (ICRP23) Q,- ?- sln v, k, )' r _ ht. 1, ' n '= number of' days during the release period (d). .m ' E I " N;g i. ? F = total river flow at location of interest for period (ml). "1 : a th I/[f'i 'B. = fish concentration factor of the i radionuclide, pCi/g r pCi/ml 3 y' c h: r1 -M -= amount of fish eaten during period (fraction of. year x,50 lb/yr. y !'t x 453.6g). + ,3 - g 0 d = fraction of river flow available for-dilution (1/5 above
~~y, -.-~~
g 3 Wheeler Dam, l'bclow the dam). s;, v 2.4 Operability of Liquid Radwa'ste Equipment U ~ . Specification 3.8.A.5Iof,theRadiologicalEffluentTechnicalSpecifi-LU cations requires that the' liquid radwaste system shall be used to.: educe , {_). y/ the radioactive' materialstir. liquid wastes prior to their discharge when s 'the projected dose per unit due to liquid effluent releases to unrestricted 7 Q areas (see figure 2.1)'when averaged over 31 days would exceed 0.06 mrem m y to the= total body or 0.21 mrem to any organ. The following methodology ic \\g will be implemented to ensure compliance. Vj. f f/F .i 2.4.1 - ' Release Limit Without Treatment The liquid radwaste operability.12mit is an activity release limit based -{,. ig upon 4 years 4f operational releases excluding tritium. The curie limit ,l 't is> dependent u,pon the future operational mix being similar to past y (j
~~L.,~~
. operational mix. The most restrictive pathway is to the total body by C-ingestion (offish. b. The individual dose from the.16 Ci operational ,u-source terms (excluding tritium) was calculated to be 0.02 mtem/mo. s 7 x., b.-- '1 This dose is a factor of 3 below the operability limit of 0.06 mrem /mo. r i f) V %a* 8 ene b {- O 1 1 r 2' m.
r... g + q. L l Page 56 p; _. :. BF TI 47-JAN 41983~ c per reactor' unit to the. total body. The' allowable release without f-exceeding 0.06 mrem /mo. per reactor unit is 3 ('.06' divided by.02)' j.'-- ntimes 0.16 curie, or 0.5 curie /mo. per reactor unit-(excluding tritium). I 'A.. = 0.5 Ci/mo, per reactor unit (excluding tritium) 11mit' 4 .. ~ ,The value.of 0.5 Ci/mo. per: reactor unit will correspond to the-limits specified-in section 2.4 if the' mixture of-isotopes is similar to.the f . operational' mixture. 2 i l j' - e 1-1- t
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Page 63 BF T1 47 JAN 41983 3.0 Radiclogical Environmental tionitoring ,- x 3.1 ?!onitoring Program An environmental radiological monitoring program, as described in tables 3.1-1, 3.1-2, and 3.1-3 and in figures _ 3.1-1, 3.1-2, 3.1-3, and 3.1-4'shall be conducted. Results of this program shall be y reported in accordance with Technical Specification 3.13. ~ '~ The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates m; shall be collected. The terrestrial monitoring program shall consist of the collection of vegetation, milk, soil, drinking water, and food crops. In addition, direct gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant. L The reservoir. sampling program shall consist of the collection of samples /m'l '[ of surface water, sediment, and' fish. Deviations are permitted from the required sampling schedule if specimens Lare unobtainable due to hazardous conditions, sample unavailability, or malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling i_ period. 3.2 Detection capabilities Analytical techniques shall be such that the detection capabilities listed in Technical Specification table 3.13-2 are achieved. 3.3 Nonroutine Reports [ Nonroutine reports shall be submitted pursuant to Technical Specification 3.13. a 1u /" h ( ) AJg L f i .j
w- _'~ l' if .ll g- '[f y s g. g- -' {- -(- - [- [ [ lr j (_ (. " ~{~ l" ~ [ N' N,). - Table 3.1-1 ~ l ENVIRONMENTAL RADIOLOGICAL MONITORING Exposure Pathway' Number of Samples' Sampling and Type and Frequency and/or Sample and Locations Collection Frequency of Analysis ' . AIRBORNE 4 Particulates -5 samples from locations Continuous sampler Particulate sampler. (in different sectors) at operation with sample Analyze for gross beta F or near the. site boundary collection at least radioactivity-J 24 hours 4 once per 7 days, following filter change. Perform gamma isotopic 2 samples from control analysis on each sample locations greater than when gross beta activity 10 miles from the plant is J 10 times the average of control samples. Per-form gamma isotopic analysis 3 on composite (by location) sample at least once per 92 days. 1 3 samples from locations Gross beta following filter in communities approxi- . change. Gamma scan at least mately 10 miles from the once per year. plant i Radioiodinc 3 samples from locations Continuous sampler 131I every 7 days, '(in different sectors) at operation with charcoal i or near the site boundary canister collection 2 samples from control at least once per 7 days. locations. SOIL Samples from same loca-Once each 3 years Gamma scan, 89Sr, 90Sr tions as air particulates once each 3 years. g;, t: - 3Dm l. ~ DIRECT 2 or more dosimeters At least once per Gamma dose once per 92 days 3E! ;! ' placed at locations 92 days. (in different sectors) A" at or near the site gg; boundary in each of the Co 16 sectors CA)
1
'A' l: O. 1 -. i f. a-. ~ 1-1 1-I. .I. [ n l..- I I.... I I l'. ' I._ (- (... _, I.- I..- - w/ .w Table 3.1-l'(Continued) e 1 ENVIRONMENTAL RADIOLOGICAL HONITORING i Exposure Pathway Number of Samples Sampling and Type and Frequency. and/or Sample and Locations Collection Frequency ' of Analysis 2 or more dosimeters At least once per 9'2 Ganna dose once per 92 days' ~ placed at stations days. located N5 miles from the. plant in each of F the 16 sectors { 2 or more dosimeters in at least 8 additional i locations of special interest I WATERBORNE i Surface 1 sample upstream Collected by automatic Gamma scan on 4-week composite. i 1 sample immediately sequential-type sampler Composite for' tritium at least downstream of discharge with composite sample once per 92 days taken at least once per j 31 days # ~ Drinking 1 sample at the first Collected by automatic Gross beta and gamma scan on potable surface water sequential-type sampler 4-week composite. Composite supply downstream from with composite sample for tritium at least once per the plant taken at least once per 92 days I sample at control 31 days" b i location t AQUATIC Sediment 1 sample upstream from At least once per 184 Gamma scan, 89Sr. and 90Sr C-. m I discharge point days. analyses. D "' e. 2" sn> H t Composite samples shall be collected by collecting an aliquot at intervals *not exceeding 2 hours.
(,
The surface water control sample shall be considered a control for the drinking water sample. c. This assumes that the nearest drinking water intake is >3.0 mile downstream of the plant discharge. tr) If a drinking water intake is constructed within 3.0 miles downstream of the plant discharge, sampling l}} j and analysis shall be every 2 weeks.
[h -[_ (; 11 . (f 1-l' ~ 1l" [ (T Li ~i~ f l! l ill I ,I" Table 3.1-1 (Continued) 'l
~~.ENVIRONNENTAL RADIOLOGICAL HONITORING~~
-Exposure Pathway . Niunber of: Samples Sampling-and' Type' and Frequency : and/or Sample and Locations - Collection Frequency of-Analysis l' sample in immediate At least once per 184 Gamma scan,. 89Sr, and' 90Sr j downstream area of dis-days-analyses -t ) . charge point i INGESTION 4 j Milk At least 3 samples from - At least once per 15 days 131I on each sample. Gamma l dairy. farms in the _ immedi-when animals 'are-on past-scan, 89Sr and 90Sr at Icast'- i ate vicinity of the plant ure; at least once per 31 once per 31 days l days at other. times. I At least 1: sample from 4 control'1ocations.(usually from 3 locations) i j Fish 3' samples representing At le'ast once per 184 Gamma scan at least once per a commercial and game days- ~ 4 da,s on edible portions, 18 species in Guntersville 89,90Sr on 2 whole fish samples - Reservior above the plant { 3 samples representing commercial and game species'in Wheeler l Reservoir near the j plant r i j Fruits & Vegetables Samples of food crops At least once per year 1311, gamma scan on edible portion such as corn, green at time of harvest f beans, tomatoes, and C f. potatoes grown at pri-28' E. } vate gardens and/or DE i .i farms in the immediate' .35 j vicinity of the plant i g 4 CO i W t i i I --n h
.. _. ~.. .[ g. -- p. g-. g_. 3-p- - j p.- - fg..- g 0 i L ' Table 3.1-l'(Continued), l a ENVIRONMENTAL RADIOLOGICAL HONITORING i i Exposure Pathway -Number of Samples ' Sampling and Type and Frequency; and/or Sample and Locations Collection Frequency of - Analysis ~ 1 sample of each of the 4 { same foods grown at . greater. than 10 miles } distance from the plant r Vegetation (pasturage. Samples from the nearby .Once per 31 days 1311, gamma scan once per'31-and grass) . dairy farms and from days. 89Sr and 90Sr once per i the atmospheric monitoring 92 days. l j stations ANNUAL REVIEW f Critical Pathway At least 24 samples At.least once per year Dependent on pathway. Verification-Typically gamma' scan, 1311 special studies as needed to verify j critical pathways, j such as the air-2 vegetation-milk pathway or the water-fish pathway, or to track radio-activity in the environment, i i I C j 3hnElL j at si! s Ak LC) cn-Ca.) p e
Pane s8 BF TI 47 JAN 41983 /N - Table 3.1-2 '\\ I 'ATHOSPEERIC AND TERRESTRIAL MONITORING STATION LOCATIONS Browns Ferry Nuclear Plant i si Location and Approximate Distance and Direction from Plant . i: L i' .U1-1 BF-1.0 mile N L_ LM-2 BF. 0.9 mile NNE b_- LM-3 BF 1.0 mile NE LM-4 BF~ '1.7 miles NNW 3 LM-6'BF 3 miles SSW PM-1-BF.(Rogersville, AL) 13.8 miles NW PM-2 BF (Athens, AL) 10.9 miles NE -~ i'~' PM-3 BF (Decatur/ Trinity, AL) 8.2 miles SSE RM-1 BF'(Muscle Shoals,.AL) 32.0 miles W LRM-6 BF'(Madison, AL, area). N25 miles E 1 Farm B 7.0 miles NNW Farm S 4.8 miles N Farm L 5.8 miles ENE 1 Farm Ca (control) 32 miles W ' Farm X-1 (control) to be determined 4 Farm X-2 (control) to be determined T esimm .use f g g s d 4
Page'69 i - BF TI 47 JAN 41983 {'~' - c Table 3.1-3 LISTING OF TENNESSEE RIVER SURFACE k'ATER SUPPLIES TO BE SAMPLED IN ENVIRONMENTAL MONITORING PROGRAM Distance from plant Supply Source (miles) 'Courtland'(Champion Paper Co.)* . Tennessee River 11.6 (mile 282.6) b - Control Tennessee River 11.0 (mile 305.0) l o 1 e 3 I First potable water supply downstream of the plant. Sample collected b* automatically and analyzed monthly. The sample collected at Champion Paper Company is a raw water sample taken at 'the intake, area; therefore, the upstream surface water sample will be considered the control sample for drinking water. E J _.. ~,. _ _ _...
Page 70 -EF TI 4i y [_,_ JAN 419E -Figure 3.1-1 ^ "N-o - U: o ins Ferr i ::uclear Pisa: 3 , ;:.s 1 ATMOS?HERIC - AMD TZERESTRIAL' MONITCRiNG NETWORK ~ / / s q LK.*iREf;CEEUP.G D ~' F AYETTEVILLE f_f .\\. ~ \\ N, \\. \\
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