ML20207T624
| ML20207T624 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1986 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20207T594 | List: |
| References | |
| PROC-861231, NUDOCS 8703240188 | |
| Download: ML20207T624 (42) | |
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- '~ 9 NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT
-s RADIOLOGICAL-AND ENVIRONMENTAL SERVICES DEPARTMENT PROCEDURE NO.: N/A TITLE: OFFSITE DOSE CALCULATION MANUAL (ODCM)*
PORC Review No./Date Meeting No. (6 -o3T Date /4/Jgstf Approved By: --
/ I^ .
v
/
Nu) ~ ResidentManag,er! ' Approved By: 1 Na & Radiological h d Envi dnmental Services Superintendent Page No.: 11 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Rev. No.: 22 2 2 2 2 2 4 2 4 2 4 4 4 2 4 Page No.: 16 17abe 18 19 20 21 22 23 24 25 26 27 28 29 30 Rev. No.: 2 3333 4 2 4 4 4 4 4 4 2 4 4 4 4 Page No.: 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 key. No.: 4 2 4 2 2 4 4 4 2 4 4 2 4 4 2 Page No.: 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 Rev. No.: 2 2 4 2 2 2 2 2 2 2 2 2 2 2 2 Page.No.: 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 76 77 78 79 80 31 82 83 84 85 86 87 88 89 90 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 Rev. No.: 2 2 2 2 2 2' 2 2 2 2 2 2 2 2 2 Page No.: 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 Rev. No.: 2 2 2 4 2 2 2 2 2 4 4 4 2 2 2 Page No.: 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 181 182 183 184 185 186 187 188 189 190 191 192 193 194 195 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 196 197 198 199 200 201 202 203 204 205 206 207 208 209 210 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 n Page No.: 211 212 213 214 215 216 217 218 219 220 221 222 223 224 225
. Qg Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240
;g o a Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 g Page No.: 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: 256 267 258 259 260 261 262 263 264 265 266 267 268 269 270 jl*k
- Rev. No.: 2 4 2 2 2 2 2 2 2 2 2 4 2 2 2 St Page No.: 271 272 273 274 275 276 277 278 279 280 281 282 283 284 285 4 4 4 Rev. No.: 2 2 2 2 2 2 2 4 4 4 4 4 ng Page No.: 286 287 288 289 290 291 292 293 294
. Sam Rev. No.: 2 2 2 2 2 2 2 2 2 Rev No. 4 Date 12/86 .
Oc ~g 34 potential release point for radioactive liquid efflu-ents. To assure the combined releases do not exceed
'10 CFR.20 limits, the alarm set point, as determined in-section 3.3 is normally multiplied by 0.5.
The basic equation which determines the fraction F3 of the 10 CFR 20 MPC limits is: f 1 n C C FILTER i 7 , FILTRAT[ + Eq.3-1
/ i=1 (M C) SOL 1 MSOL t_
Where: F = The fraction' of 10 CFR 20 MPC limits resulting from the '~ 3 release source being discharged, dimensionless. f l
- The undiluted release rate of the release s o'irc e as l measured at the liquid effluent monitor location, in gpm.
f - The discharge structure exit flow in gpm. .( Summation of 2 circulating water pump and service water pump discharge flou .minus the percentage redirected for tempering.) C [. FILTRATEg= The undiluted. concentration of nuclide (i) in pCi/ml from filtrate sample assay. When a radionuclide concentration is below the LLD for the analysis, it is not reported as being present in the sample. (MPC) SOL = t Soluble Maximum Permissible Concentration of nuclide (i) from Appendix A, in pCi/ml. C FILTER t = The undiluted concentration of nuclide (i) in pCi/ml from filter sample assay. When a radio- nuclide concentra-tion is below the LLD for the analysis, it is not reported as being present in the sample. (M C)INSOL t = Insoluble Maximum Permissible Concentration of nuclide (i) from Appendix A, in pCi/ml. Using the general approach, the fraction of the 10 CFR 20 MPC limit may be determined by a nuclide-by-nuclide evaluation. Rev. No. 4 Date 12/86 Page 7 of ODCM l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _J
g.- , Y 3.3 Determination'of Set Points for Radioactive Liquid-Effluent Monitors
- 3. 3.1 ' ' Requirements Technical Specifications Appendix B Section 2.1.'a requires that-the-radioactive liquid effluent monitor.be operable
-and set to initiate an alarm and/or. trip in the event that '
the. limits of Technical Specifications Appendix B Section 2.2 are approached. The alarm and/or trip set points shall be determined .and- adjusted by the methodology which fol-lows. The set point values should be applied above normal background levels. The alarm set point for the liquid effluent radiation mon-itor is derived from the concentration limit provided in 10 CFR 20 Appendix B Table II Column 2 applied at the un-restricted area boundary where the discharge tunnel flows into Lake Ontario. 3 . 3 .' 2 Methodology The alarm set point does not consider dilution, disper-sion, or decay of. radioactive material beyond the unre-stricted. area boundary 1.e., the alarm setpoint is based on a concentration limit at the end of~the discharge-tun-y nel. A sample of each batch of liquid radwaste is analyzed for I-131 and other principal gamma emitters prior to re-lease. The fraction F of 10 CFR 20 MPC limits and the minimum required diludion factor to achieve F, =1 is ! determined in accordance with the preceding section for ! the activity to be released. A conservative alarm and/or trip setpoint (uCi/ml) is de-termined in accordance with the following equation. Eq.3-3 i S = 0.5 x hL Where: S = ' The alarm and/or trip set point above background corresponding to the limiting concentration of undiluted liquid effluent (uCi/ml). 0.5 - Conservatism factor to account for releases from multiple points. C = Total gamma isotopic or gross activity concentra-tion (uci/ml) of sample as determined in the labo-ratory. Rev. No. 4 Date 12/86 Page 9 of ODCM
,. .. ._ ,.. . . ~. . . . .
$ 1 9 b f ,
x,
' =:(2~.65E-4),x 1,000 0.265-
^
1 g. The ' liquid. effluent monitor set point , S ' in uCi/ml, from equation 3-3 is: V. S = 0~.5 .x hL -l 4
= 0.5 -x-((3E-5)/(0.265)] l
- . . i
= 5.66E-5 uCi/ml !
E
- h. Appropriate calibration factors are applied to - this limiting concentration determined in step 3.3.3.g to determine an effluent monitor alarm potentiometer set l- point.
p 3.4: Dose Determination for Radioactive Liquid Effluents 3.4.1 Annual Dose Assessment-Radioactive Effluent Release Report Submittal
'a.; Requirements Technical Specifications Appendix B Section 7.3 r e --
quires .a semi-annual Radioactive Effluent. Release Report to be submitted that includes an assessment of-the radiation doses to the public due . to the radio-active liquid and gaseous effluents. released from the unit during. the previous calendar year. The dose assessment required by.this report is due annually 90 days after January'first of each' year.
- b. Methodology This section p~rovides the methodology to calculate the doses to all. age groups and organs from all radionu-clides identified in the liquid effluents.- The method is based on the methodology suggested by NUREG-0133 -
October 1978' Sections 4.3 and24.3.1. The site-related dose factors for all viable pathways are listed in Appendix A Tables L-2 and L-3. Tabid-L-3 dose factors are compiled by age. groups, for all organs and radio-nuclides common to a BWR environment. The following equation provides for a dose calculation to the total body or any organ for a given age group based on actual release conditions during a specific time interval for radioactive liquid releases: D = At , Aty Qy t Eq.3-4 it (DF)y
- Rev. No. 4 Date 12/86 Page 11 of ODCM
s+ a i
..' \
Where: D
= Dose commitment in mrem received by organ it .t of age group (to be specified) resulting from releases during tima interval at y.
A - The site-related dose commitment factor to i' the total body or. any organ for each identified radionuclide (1). 'h e' A- val-ues listed in Appendix A, Tm ~.e s bl2 and L-3 are site specific, in mrem /hr per pCi/ml. Dose commitment factors are com-piled by age groups, for all organs and radionuclides common to a BWR environment. The derivation of A i' values is described in Appendix A. at y = The number of hours of liquid . effluent release during the calendar year. Q1
= The total quantity of nuclide (i) released during the. time period aty, in pCi.
(DF)y = The total volume of dilution that occurred during the calendar year period at summation of circulating water pbp(i . eand ., service. water pump discharge flow, minus the percentage redirected for tempering). By entering the appropriate annual parameter values onto a form similar to that shown in Table 3.4.2, to-tal body or organ doses may be calculated as outlined in step 3.4.2.c. In addition, more realistic assumptions may be made concerning the dilution and ingestion of fish and potable water by individuals who live and fish in the area. 3.4.2 Monthly Dose Assessment - Verification of Compliance with 10 CFR 50 Appendix I Limits
- a. Requirements Technical Specification Appendix B Section 2.3 re-quires an assessment to be performed at least once every month in any quarter in which radioactive efflu-i ent is discharged, to verify that radioactive liquid effluents do not result in a cumulative dose in excess of 1.5 mrem to the total body and 5 mrem to any organ in a calendar quarter,
- b. Methodology This section presents the calculating method to be used for the 10 CFR 50 Appendix I compliance verifica-Rev. No. 4 Date 12/86 Page 12 of ODCM
w.
. ;h tion. The. method is bas ~ed on the models suggested by l NUREG-0133 October 1978-Sections 4.3 and 4.3.1.
(1) General' Approach
., The general- ap7 roach used is almost identical to that - describec in step 3.4.1 for use in cal- 1 3 culations for the annual-Dose Assesment. Report.
The only difference is'that the liquid effluent dose pathways conside' red are limited to the ingestion of fish and potable water. As
. discussed in Appendix D, these_ dose pathways are the only ones that need be considered for verifying compliance with the requirements
-specified in step 3.4.2.a above.
The site-specific dose factors for the fresh water fish and potable water pathways are pro-vided in Appendix A Table L-2. For JAFNPP, the adult is the most. limiting age group, but the dose for child, and teenager, may also be calculated by this method using the-appropriate dose factors from Appendix A, Table L-3. The following equctien is used to determine a dose to'the total body or any organ for a given age group based on actual release conditions during a specified time interval for radioac-tive liquid. releases.- The equation is: D A fT at y Qy t Eq.3-5 it (DF)7 Where: D = Dose commitment in mrem received by organ T t* of age group (to be specified) from release time interval at t. A l'
= The composite dose factor for the fresh water fish aathway and potable water pathway for nuclic.e (i) for organ i of age group (to be specified). The A f values listed in Ap-pendix A Table L-2 fn this manual have the units mrem-ml/uci-hr.
aty - The number of hours over which the release
- ' occurs.
r-Qt y - The total quantity of nuclide (1) released during the time period atl in uCi. (DF)y The total volume of dilution that occurred t, (i.e., the during the release time period circulating water flow multiplied by the time). Rev. No. 4 Date 12/86 Page 13 of ODCM
._= . .
a _-' :.
-e (2) Obtain . (DF) .f the time period at for the I
release soudce(or s) of interest. DF is the total volume of dilution, (i.e. -the cirbulating water
' flow multiplied by the time.)
(3) Obtain Q4y (uC1) for nuclide (i) for the time period at'y. (4) Obtain A from the appropriate Liquid Dose-Factor Tdtile: Appendix A Table L-2 for the fish and potable water pathways: Appendix A Table L-3 for all other pathways. (5) Solve for Dose (1) D " A ir, aty.Qy t it (DF)y (6) Repeat steps 3.4.2.c.(3) through 3.4.2.c.(5) for each nuclide reported and each organ re-quired. If the limited analysis method is used, limit the radionuclides to Co-60, Mn-54, Zn-65, Cs-134-and Cs-137 and determine the adult total
' body dose and the edult liver dose.
(7) Sum the D values to obtain the total dose to organ frod'the fish and potable water pathways.
.If the limited analysis method is being used, divide the cumulative dose by a conservatism factor of 0.9 to account for any unexpected variability in radionuclide distribution.
Rev. No. 4 Date 12/86 Page 15 of ODCM
p, r m p.; } .P 4.0 GASEOUS EFFLUENT METHODOLOGY -
- 4. l' Gaseous Waste Streams James A. FitzPatrick Nuclear Power Plant- discharge's gaseous effluents through a stack, and discharges . ventilation air from the reactor building, turbine building,_radwaste build-ing, and refuel floor through separately. monitored vent re-lease points. . Normal--gaseous effluent streams, and effluent
. discharge points are tabulated in Appendix F Table F-1.
For the purpose of . estimating offsite radionuclide concen-trations and radiation doses, radionuclide concentrations are first measured in gaseous effluents and ventilation air exhausted '.from the plant. Technical Specifications Appen-dix B Table 3.2-1 identifies the specific radionuclides in gaseous discharges for which sampling and analysis is done. When a radionuclide concentration is below the LLD for the analysis, it is not reported a's.being present in the sample, 4.2 Data Requirements for Gaseous Effluent Calculations Dose calculations to demonstrate compliance with Technical-Specifications Appendix B Sections 3.2.a, 3. 3.a - and 3.4'.a are normally performed.using historical meteorological data and receptor location (s) which yield calculated doses no lower than those received by real receptor (s) . Historical meteorological data for use in performing dose calculations are provided in A ? pendix C. Dose calculations to show con-formance with Technical Specifications Appendix B dose lim-its may be performed using real meteorological data, real. receptor locations, and sector wind frequency distribution if desired. Historical meteorological data factors are calculated and used in dose calculations for the semi-annual Radioactive Effluent Release Report. This report is due-90 days after January first of each year. Historical information and conservative receptor assumptions, are also used for ease of Technical Specifica- tions Appendix B Limiting Conditions for. Operation (LCO) dose limit calculations. JAFNPP uses an
. elevated release model for stack discharges and ground level release model for reactor, turbine, radwaste and refuel floor vents. Those radionuclides that appear in the gaseous-effluent dose factor tables are , representative .of BWR isotopes that may be considered in any dose calculations.
Rev. No. 4 Date 12/86 Page 18 of ODCM
o- :. Where: DR TB
. Total . body dose rate from -noble gases in airborne releases, in mrem /sec.
DR SKIN
= Skin dose rate from noble gases' in airborne releases in mrem /sec.
K 1
= The . total body dose factor due to gamma emissions. for each- noble gas nuclide (i) -reported in the release source, in mrem-m3/uCi-sec.
Li = The skin dose factor- ~due to. beta emissions for each: noble gas nuclide (i) reported in _the assay of the re-lease source in mrem-m3/uCi-sec. M t'
- The air ~ dose factorz due to - gamma-emissions for each noble gas nuclide (i) reported in the - assay of the release source. The constant 1.1 con-verts ' mrad' to ' mrem' since the units of Mt are in: -(mrad-m3/uCi-sec)
(XTQ) = For ground level or elevated releases, the highest annual average, X/Q, calculated using long term . historic meteorological data, for any land sector, at or beyond' the site boundary, in sec/m3 (See Appendix C, Table M-1). Qt = The release rate of noble gas nuclide (i)- from the -release source of inter-est, in pCi/sec. L 4 Rev. No.- 4 Date 12/86 Page 20 of ODCM
e,. . .L (1) ' Limited Analys'is App' roach-- Instantaneous Noble G_as Release Rate. The.above~ methodology can be simplified to pro-vide - ~ for. ' a rapid determination of cumulative - noble gas release limits based ~ on the require-ments specified in: step 4.3.1.a. .Beginning with equation 4-1, the simplification proceeds - as follows. , From an~ evaluation of'past releases, an effec-tive total body dose ' factor can. be derived. This dose ~ factor is ,. (K,,f) fit. effect , a weighted average total. body dose factor '(i.e. , weighted by the radionuclide distribution typi-cal of past operation).. See Appendix E . for . a detailed ex and evaluation; of K The value o[lanationhasbeenderivedfromthe*fk. K dioactive nobl8ff gas effluents for' the. years 1980, 1981, and 1982 for the plant. The value is: K,ff = 7.68E-5 (mrem-m3/uCi-sec) (Ground Level Releases)- K
*ff = 1.41E-4 (mrem-m3/uci-sec)
(Elevated Releases) Either of these values, as appropriate, may be used in conjunction with the. total noble gas release rate - (rQ,) to verify that the instanta-neous dose rate is within the allowable limits. To compensate for any-unexpected variability in the radionuclide distribution a conservatism factor of 0.8 is introduced -into the calcula-tion. The simplified equation is: Eq.4-3 L n .. DRTB = K,gg x (XTQ) Qt
0.8 Where
DR = Total body dose rate from noble gases in TB airborne releases, in mrem /sec. (YTQ) = For ground level or elevated releases, the. highest annual average X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond. the site boundary, in sec/m3 . (See Appendix C, Table M-1) Q = The total release rate of all noble gas nuclides from the release source of interest, in pCi/sec. Rev. No. 4 Date 12/86 Page 21 of ODCM
-~
m " ~ by" J'{q}:%m
' rp' <9+3 '
~ c d
+-
'+
yf , a [g - ~t
~ . -
.d p;j , ._
z s. .
~
g , i c
- k. (&or ! gross) noble A ' s' ingle (- cumulativet
.I gas re- -
Am lease rate , limit ~ for elevated release a id
? ground: level' -releases - mayi be. derived ~ byf repri rangingVquationt4-3 as ' follows . k/'
~
it [g" i g, .
,' g , -6 Eq.4-4 M
~
-[j[ % ,'3[Q1 .
1 DRTB -x:(O.8); Q
. g. u= N
" 4
,f-(
3 K,gg x (W ) ~#X N
-%S> .,
;/!, . .
J These (11oits may be determined by taking . the-4,@p ~ highest \ ca'Lculated1 annual average, X/Q,- 'for i at any of ~ 1,;a4I elevated. and - ground 1~cvel. releases ,)d ( e the _ land b@ed 'st:ctors , at C or be' Tab e on M-1 the site these- ~
< X [u.i t 1values boundary. are: / From Appendix
.. -% s
-/ }.A (c#2 y $ w fg' tack Relkases) s 4 g N
y;
~
\h3 Mf g.
(yJq) n p3.8E-8 . y J . Q . tL ?it( f 5 , s C i
, /(T/th) y = 1.8E-7 (Ve t Relha)es
' 585E-59 ky X6 Al's o, thebdose limit of-500. mrem /yr =
r mqm/sec may be substituccd, for DRTB n equa g 3- y,
~
f .
-{ ,
ti 9 4-4. .s A g,, In 6ddition, from; a revie'w of gaseous eff3.uent ^ti t rel(eases as reported in the - JAFjPP semiannual Effluent Release Reports ifor /che years ~1980,! L' ( c A 1981 and(1982, it .. was determined that,.on the'
- . L , u. average, approximatelys 90 percentrof the annual k.
total. body dose from noble gases is..due to ele- %' i ; vated; releases. The'se data are presented in
- k. Appendix E , In acc/rdance withN this , the re-lease limi[<is,splix as follows.
n, t
'+
y -90% - Elevated Stack Release Q
- .. 10,%,- y,Ground Level Ve.ntGElease- '. g 7%
yf l4 , '3 Making tiiese substitutiotis in equaticn 4-4. ' s . yields ;'thebfollowing cumulative '4 (or gross) no - 3 - p' ble gas release rate limits'1 %)q
,n t f-
~
Elevated Release' Rate Limit \ c 1
=42.1E+6uCibb (
b Ground Levels Release Rate (Limit = 9.2E+4 :uci/see ' I A \ l As long as the noble, gas , release . rates do not , exceed these values 0 1 i N* , , releases, and 9 . 2 E + 4 % C i / s;e c(2.1E+6 g.Ci/seF for eleva for ground level s releases) t to additional Yose rate calculatior6 i j g8 %, are neede4 f eo s veri'fy, compliance with i t instantaneous release rate. limits' of Technical
\ Specifications Appendix B SAtion 3.2.a.1.
c ,g i 3 s iy' ,
\
.Rev. No. 4 ( Date 12/86 Page 1 , of ODCM j 1 L. . , . . . _ _ _ . _ . _ . . . _ . _ . _ _ _ _ . _ .____./
q a.
-(2) General' Approach - Total Body and Skin Nuclide-Specific Instantaneous Release Rate Calcula-tions The methods described herein need only be1used if the actual releases exceed the' values of:
Elevated Release --2.1E+6 uCi/sec Ground Level Release.= 9.2E+4 uCi/sec-Total Body Dose Rate Eq.4-5 n n . DR DR TB = I i=1 E TBi "i=1 i x (X/Q) x Qg Where: DR = Dose rate to the total body due TB to gamma emissions from noble gas nuclide (1), mrem /sec. 4
~, . DR = Dose rate to the total body due TBi.
to gamma emissions from nuclide (1), mrem /sec. K = The total body dose factor due to i gamma emissions from noble gas radionuclide (1), in mrem-m3/ pCi-sec (see Appendix B Table G-2). (X/Q) = For ground level or elevated re-leases, the highest annual-aver-age X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m3 (See Appendix C, Table M-1). Stack XTQ = 3.8 E-8 sec/m3 Vent XTQ = 1.8 E-7 sec/m3 k = Release rate of the i th nuclide. in uCi/sec. Total Skin Dose Rate Eq.4-6 n n . DR DR " I SKIN = i=1 SKIN i E i=1 i+ 1*I 1(RTQ}I
- 01 Rev. No. 4 Date 12/86 Page 23 of ODCM
$ - ;4 sg
- Where:
Dose rate to skin due to beta and gamma
~
DR SKIN. = radiation from noble gas nuclide (i) (nrem/sec). Lt = -The- skin dose factor ~due to . beta emissions from noble gas . nuclide '(1) , in mrem-m3/uCi-sec -(see Appendix B
~ Table G-2).
M = The air dose factor 'due to gamma t emissions - from ' noble gas nuclide (i), in mrad-m3/uCi-sec (see Appendix B Table G-3),
- 1. l~ = Conversion factor for M t from mrad to mrem.
u -
- X/Q = -For ground level or elevated releases, the highest . annual average X/Q, calculated .using_long term historic meteorology data,- for any. land sector, at or beyond the site boundary, in sec/m3 (See Appendix C, Table M-1).
th Qt = Release rate of the i nuclide in
.uCi/sec.
The dose rate contribution of this release source shall be added to all other simultaneous gaseous release sources, if any, to determine overall total
- dose rate to the total body and skin from noble gas effluents.
- c. Calculating Process The following outline provides a step-by-step explana-tion of how the total body and skin dose rates are ,
calculated on a nuclide-by-nuclide basis to evaluate compliance with Technical Specifications Appendix B Section 3.2.a.1. This method is only used if the ac-tual releases exceed the value specified in ODCM Sec-tion 4.3.1.b.(1). Rev. No. __4 Date 12/86 Page 24 of ODCM
e,4 : ... 4 (1) ' The X/Q value = sec/m3 and is the most limiting land. sector at.or beyond-the site boundary. (2) Enter the release rate in f t3/ min of the' re-lease source and convert it to cc/ secs -
"( )ft3
- 2.8317E+4 cc
- min min ft3 60 sec
=~
cc/sec volume release rate (3) Determine Q4 for nuclide .(1) by obtaining the. pCi/cc assay value of the release source and multiplying it by the release rate computed -in the previous steps. Qt , (- )pCi x ( )cc CC' seC i Q, t uCi/sec for nuclide (i) I (4) To evaluate the total' body dose rate, obtain the K value for nuclide (i) from Appendix B Tableb-2.
'(5) Solve for DR TBi DR TBi =
N ix I ) x i =
"#**~*'
x sec x pCi uCi-sec m3 see DR TBi
= Total body dose from nuclide (i) for the specified release source in mrem / {
sec (6) To evaluate the skin dose rate obtain the L and M, values. from Appendix B Table G-2 fob nuclid'e (1) . (7) Solve for DR SKIN i DR SKIN i " i + 1*1 "il( ) , DR = Skin dose from nuclide (i) for the SKIN i specified release source, in mrem / sec (8) Repeat steps 4.3.1.c.(1) through 4.2.1.c.(7) for each noble gas nuclide (i) reported in the assay of the release source. l Rev. No. 4 Date 12/86 Page 25 of ODCM
.p. 7.
- b. Methodology This-section describes the methodology for determining alarm / trip set. points for the stack and vent gaseous release pathways. To allow for multiple sources of releases from different or common release points, the allowable operating set points will be administrative-ly controlled to allocate a percentage of the total allowable release to each of the release sources. The cumulative noble gas release rate limit for a stack (elevated) release (2.1E+6 pCi/sec) is based on allo-cating 90 percent of the total body dose limit to the stack release point. The individual release rate' lim-its for the four other gaseous release points (assumed to be ground level releases), are based upon an allo-cated -percentage of the cumulative ground level - re-lease rate' limit (9.4E+4 uCi/sec).
The method that follows establishes a procedure for determining set points. (1) Determine the maximum volume release rate po-tential for the release source under considera-tion. (2) Based upon that release rate (ft3/ min or other units of vol/ time) determine the equivalent activity concentration in (uCi/cc) that would produce a release of: 2.4E+6 uCi/sec - Elevated Release 9.2E+4 pCi/sec - Ground Level Release (3) Referring to the calibration curve (uCi/cc vs. CPM or CPS) for the release source's gaseous effluent monitor, determine the CPM or CPS value (C) corresponding to the value of activity concentration determined in step 4.3.2.b.(2). (4) For an elevated release, the set point is equal to the CPS value (or corresponding potentiometer setting) as follows. - SP = (C) CPS Eq.4-7 (5) For a ground level release, (C) corresponds to 100 percent of the ground level release rate limit assuming no other ground level release sources at the time. To obtain an operational set point value SP, take (C) in (CPM) and mul-tiply it by the allocated fraction for the individual ground release point. Rev No. 4 Date 12/86 Page 27 of ODCM
m ,;c . 7 -
~
. fraction-allocated for- Eq-4.8' SP_=-(C)' CPM x. -a:particular
. ground release:
, A; typical allocation mayJ be sur follows (example only)'.-
Turbine _ Vent - 0.60 Reactor Vent 0.15 Refuel Floor.' -0.15 Radwaste Vent -.0.10 4 The _: total; body: dosesis~ moreflimiting than the calcu-lated skin dose (see Appendix E for a detailed evalua-tion).. Therefore, the skin dose rate calculations are not required if.the simplified dose rate . calculation
; is ' used (i.e. , using K,ff to determine release rate' f limits).
The calculating processes of step 4.3;1.c are.to be used if the actual releases of noble gases' exceed the predetermined limits of 2.1E+6 uCi/sec for - elevated' releases or 9.2E+4 pCi/see for. ground. level releases. Under these conditions, a nuclide-by-nuclide evalua - tion is required to evaluate compliance with the dose-rate -limits of Technical Specifications Appendix B - Section 3.2.a.1. 4.3.3 Determining the Radiciodine and Eight Day Particulate In-stantaneous Release Rates v
- a. Requirements Technical Specifications Appendix B Section 3.2.a.2 limits the instantaneous dose rate from inhaled radio-iodines and particulates with half-lives greater than- -
eight,djays to 1,500 mrem /yr to any organ. The criti-cal age group is the child, and the critical organ is the thyroid, per Technical Specifications Appendix B Section 3.2 Bases.
- b. Methodology The following calculating method is provided for de-termining the dose rate from radioiodines and particu-lates. It is based ca NUREG-0133 October 1978 Sections 5.2.1, and 5.2.1.1 through 5.2.1.3.
Actual concentrations of Iodine-131, Iodine-133, and 3 radionuclides in particulate form with half-life greater than 8 days released from the plant in gaseous effluents shall be determined using gamma isotopic analysis. Sampling and analysis shall be performed in accordance with frequency specified in Table 3.2-1 of the RETS. 1-Rev. No.. 4 Date 12/86 Page 28 of ODCM
=: a r'
' Based'on'an analysis of doses to all' organs and age groups - for _ the inhalation pathway (Impell Corporation-RG109 Computer Analysis, Impell Version 2,.Rev. 0 )', -
the . child was verified as being . the ' controlling age -l group and the thyroid as -being ~ the critical organ. This pathway is.the only.one that-need be considered
.for instantaneous releases. -The long term (X/Q)
M' ' depleted values are based on~ historical meteorological data. Dose factors for nuclides listed ~in Appendix B
-Table G-4 will be used.
Inhalation Pathway Eq.4-9_ l n . DR I&BDP P f,x (M)D *
= I 91 r- i=1 Where: ~
r =- The organ of interest for the age group of
, interest.(thyroid, child).
.Q t
=- Release rate of nuclide (i), (uCi/sec).
DR = Dose rate to the child thyroid from I&8DPr iodines and eight day particulates via the. inhalation pathway (mrem /yr). (XTQ)D
= The long term depleted and eight day de-cayed X/Q value based on historical meteo-rological data !(see Appendix C Table' M-1) in (sec/m3).
P i = The dose factor for the inhalation pathway in (mrem /yr: per uCi/m3) (see Appendix B Table G-4) . The derivation of P values is given in Appendix B Table G-7. g The limiting iodine release rate is thus determined by the following relationships: Eq.4-10 Q1 Thyroid x 0.8 (XTQ)D 1(Thyroid) Where: DRThyroid = Dose rate to the child's thyroid from the inhalation patbway set equal to the Technical Specifications Appen-dix B Section 3.2.a.2 limit of 1,500 mrem / year. Rev. No. 4 Date 12/86 Page 29 of ODCM L. --
- 4- # .
7,_
~P1 (Thyroid)
-=
The instantaneous dose . f actor for nu-clide: i for the child's thyroid for the inhalation pathway.
.(XTQ)D.
The long term depleted . and eight day decayed. X/Q value for any land sector value based on historical mateorolog . ical ~ data -(see Appendix C Table M-1) in (sec/m3). Qr
= Limiting io_ dine release rate.,- in uCi/sec.
0.8 = A conservatism factor of 0.8 for a typical - radioisotope _ distribution and
-dose contribution.
l: 4.4 Dose Determination for Radioactive Gaseous Effluents 4.4'.1 Annual Dose Assessment-Radioactive Effluent Release Report Submittal
- a. Requirements-Technical Specifications Appendix B Section 7.3 re-quires a s_emi-annual- Radioactive Effluent Release Report to be submitted that includes an ' assessment of the radiation doses to the public - due 'to the radio-active liquid.and gaseous effluents released from the unit during the previous calendar year. This report is due annually 90 days after January first of each year.
- b. Methodology -
The section provides the methodology to calculate the doses to all age groups and organs from radionuclides identified in the gasaous effluents. The method is based on the methodology suggested by NUREG-0133 October 1978 Sections 5. 3 and 5. 3.1. The site related dose factors for all viable pathways are listed in Appendix B. Dose factors are compiled by age groups, for all organs and radionuclides common to a BWR environment. Normally calculated annual long term historical atmospheric dispersion factors are esed to perform the annual dose assessment. Actual meteorological data and sector wind frequency distri-butions for the year of interest may be used in lieu of the annual long term historical factors. 40 CFR 190 dose assesments, when required, will be made using actual meteorological data and frequency distribution data for the year covered by the evaluation. The following equations provide for a dose calculation to the total body or any organ for a given age group Rev.~No. 4 Date 12/86 Page 30 of ODCM
a- . based on actual release rates during a specific time interval for radioactive gaseous release sources:
- 1) Annual Dose Due to Noble Gases n Eq.4-11 D "
E )
- 91 Gamma-Air ( y "i *I Where:
DGamma-Air = The gamma air dose from radioactive noble gases, in mrad. My = The gamma air dose factor for radioactive noble gas nuclide 'i', in mrad-m3/uCi-sec (see Appendix B Table G-3). (R7Q) = The long term historical atmospheric disper-sion factor for ground level or elevated releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/m 3. Qt = The number of uCi of nuclide 'i' released during the year of interest. n Eq.4-12 D " Beta-Air E i*I } *9 1 i=1 Where: Beta-Air - mrad. Beta air dose from radioactive noble gases in D N i
= The beta air dose factor for radioactive noble gas nuclide (i) in mrad-m 3 /uCi-sec (see Appendix B Table G-3).
(X7Q) = The long term atmospheric dispersion factor for ground level or elevated releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to deter-mine annual X/Q for the year of interest in sec/m3 Qt = The number of uCi of nuclide 'i' released during the year cf interest. Rev. No. 4 Date 12/86 Page 31 of ODCM
- g. v Where:
r - The organ of interest for the age group of interest. z' = All the applicable pathways. D I&8DP i = Annual dose to the organ r for the ' age group of interest from iodines and eight day particulates via the pathway of inter-est in (mrem). D
= Total annual dose to-organ r from all ap-plicable pathways for the age group of in-terest in1(mrem).
Qt = The number of pCi of nuclide 'i' released during the year of interest. R, = The dose factor for nuclide (i) for organ-1 t for the pathway specified (units vary with pathway) (see Appendix B Table G-8). The derivation of-R values is given in NUREG-0133OctoberIN8Section5.3. (D7Q) = A long term historical annual average relative deposition value for elevated and ground level releases. A factor with units of m 2 which describes the deposition of particulate matter from a plume at a point downrange from the source. Actual meteor-
-ological data and sector wind frequency-distribution may be used to determine annual average D/Q for the year of interest.
(27Q)D
= A long term historical annual average depleted and eight day decayed relative
.oncentration value for elevated and ground level release. It describes the physical dispersion characteristics of a semi-infinite cloud travels downrange.
Since iodines and particulates settle out (fallout of the cloud) on the ground, the (X/Q) represents what physically remains of thS cloud at a given location downrange from the release point. Actual meteoro-logical data and sector wind frequency distributions may be used ':o determine annual average (X/Q)D f r the year of in- l terest. Total body and organ doses will be calculated for pathway and age group on an annual basis. t t-Rev..No. 4 Date 12/86 Page 33 of ODCM
f[6 [ (X/Q) - The highest long. term annual average - atmospheric' dispersion;-factor for ground level or elevated releases I for any land. sector,'in sec/m3-(see Appendix C Table M-1.) Q-1
=
The number of uCi of ' nuclide 'i' released (or projected)' during the - dose - calculation- _ exposure period-
-(e.g. , month, quarter, or year) .
-(a) Limited Analysis Approach The following limited < analysis approach may !
be used to establish monthly release objec-tives (uCi/ month) that will ensure compliance l with 10 CFR 50 Appendix I gamma dose limits. ! From an evaluation of past releases,. a-single effective gamma air dose factor (M has been derived, which is representativl bff )- the'radionuclide abundances and corresponding dose contributions typical of past operation (see Appendix C for a detailed explanation and evaluation of M . The value of M l has been derived fr$k[)the radioactive no8fk gas effluents for the years 1980, 1981, and 1982. The value is: Meff = 8.17E-5 mrad-m3/uCi-sec (Ground Release) M,ff = 1.37E-4 mrad-m3/uci-sec (Elevated Release) The effective gamma air dose factor may be used in conjunction with the total noble gas release (IQ ) to simplify the dose evaluation and to verdfy that the cumulative gamma air dose is within the equivalence of the limits of Technical Specification 3.3.a.2. To compensate for any unexpected variability in the radionuclides distribution, a conser-vatism factor of 0.8 is introduced into the calculation. The simplified equation is: Rev. No. _ 4 Date 12/86 Page 35 of ODCM
.e .
Eq.4-21 D = ("*ff}* ( } 9-1 Gamma-Air 0.8- i=1 For purposes of calculations - the appropri-ate meteorological dispersion (X/Q) should be-used. Solving quation 4-21 for Qt yields the following Eq.4-22
" D q , Gamma-Air x (0.8) i=1 (geff) * (IIN)
Technical Specifications Appendix. B Sec-tion 3.3.a- states that the doses must be l evaluated once per month. The yearly dose limit is 10 mrads, which corresponds to a monthly allotment of 0.83 mrads. If the O.83 mrads is substituted for D in equation 4-22, a cumulative nMW"~kkI monthly release . objective can be calcu-lated for elevated and ground level re-leases. As described in section 4.3, 90 percent of the dose will be allocated to elevated releases and 10 percent to ground level releases in accordance with release source terms for the year 1980, 1981, and 1982 (Appendix E). Thus (X/Q) values of 1.8E-7sec/m3 fo. ground level releases and 3.8E-7 sec/m3 for elevated releases can be used, along with the corresponding M, values, to calculate the followfhg, cumulative noble gas monthly release ob-jectives. Q (ground level release) = 4.5E+9 uCi/ month Q (elevated release) = 1.lE+11pCi/ month As long as these values are not exceeded in any month, compliance with the quarterly noble gas release limits of Technical l Specifications Appendix B Section 3.3.a.1 is , determined. When the limited approach method l is used, calculations must be performed , monthly as a minimum. Rev. No. 4 Date 12/86 Page 36 of ODCM
- b. D_etermining the Beta Air Dose for Radioactive Noble Gas Release Sources The beta air dose calculations of step 4.4.2.b is required to be performed when the radionuclide specific dose analysis is performed. The radionuclide specific dose analysis is performed at least monthly t for calculations in the semi-annual Radiological ,
Effluent Release Report (Annual Dose Assesment). i (1) Requirement Technical Specifications Appendix B Section 3.3.a.2 limits the yearly dose due to noble gases in the gaseous effluents to less than 20 mrads to the skin from beta. When the nuclide specific dose calculation is used to evaluate compliance with the gamma air dose limits (step 4.4.2.a), the beta air dose shall be evaluated on a nuclide specific basis using the methodology presented below. (2) Methodology The following calculating method is provided for determining the beta air dose and is based on NUREG-0133 October 1978 Section 5.3.1. The dose calculation is independent of any age group. The equation may be used for dose cal-culations for semi-annual Radiological Effluent Release Reports, or for projecting dose, pro-vided that the appropriate value of (X/Q) is used. Actual concentrations of Iodine-131, Iodine-133 and radionuclides in particulate form with half-life greater than 8 days released from
.the plant in gaseous effluents shall be determined using gamma isotopic analysis.
Sampling and analysis shall be performed in accordance with the frequency specified in Table 3.2-1 of the RETS. Rev. No. 4 Date 12/86 Page 37 of ODCM
=
The equation for beta air' dose is: n Eq.4-23 D I N 1 x (X M) xQ 1 Beta-Air = i=1 Where: D = Beta air dose from radioactive noble Beta-Air gases in (mrad). . N:i
.= The beta air dose factor - for ra-dioactive noble gas nuclide 'i' in-mrad-m3/uCi-sec (see Appendix _ B Table G-3).
(XM) = For ground level or elevated -re-leases, the highest annual average, X/Q, calculated using long ~ term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m3 (see Appendix C, Table M-1). Qg
=
The number of uCi of nuclide 'i' released (or projected) during the dose calculation exposure period.
- c. Determining the Radioiodine and Eight Day Particulate Dose to any Organ from Cumulative Releases (1) Requirement Technical Specifications Appendix B 3.4.a.1 limits the dose to the total body or any organ resulting ~ from the release of radioiodines and particulates with half-lives-greater than eight days to less than 7.5 mrem / quarter and less than 15 mrem /yr to any organ.
(2) Methodology The following calculating method is provided for determining the critical organ dose due to releases of radioiodines(I-131, I-133) and particulates. It is based on NUREG-0133 October 1978 Section 5.3.1. The equation can be used for any age group provided that the appropriate dose factors are used and the total dose re-flects only those pathways that are applicable to the age group. The symbol (X/Q)D represents a depleted (X/Q) in that takes into account the loss of iodines, eight (X/Q)D day particu-lates and tritium from the plume as the semi-infinite cloud travels over a given distance. Rev. No. 4 _, Date 12/86 Page 38 of ODCM
; . .. s 4 j:x -
- g y 4, ,
4i w. - R= = Thef dose factor for .nuclide'. (i) - for - ; pathway z. to. organ ~ :r Lof -the
, 1specified . age group.- The units mrem-m3/yr-uCi ~
are 'either- for e pathways using' , or mrem-m*-sec/yr-aci for_(X/Q)'htways pat . using ,
-(D/Q) (see Appendix B Tables G-5 and?
G-6).
:(XM)D
= The depleted _X/Q) ( value for a specific location-where the receptor:
is located. The units are - (sec/m3)' (see Appendix C' Table'M-2.or M-3).
=
(F/Q) The deposition value for.a specific location where the. receptor. .is located. The units are (m 2) .(see . Appendix C Table M-2 or M-3). Qt = ~The number of micro-curies- of nuclide (1) released (or projected) during the dose calculation exposure period. (a) Limited Analysis Approach .. Based on an analysis 'of doses to all or-gans from all' atmospheric release pathways-and age groups (Impell Cor'poratian RG109 Computer Analysis, Impell Version'2, Rev. 0), the contaminated forage / cow / goat /mila pathway has been identified as the most limiting pathway' with the infant's ~t hyroid being the most critical organ and age group. This pathway contributes, on: average, over-85 per cent of the total dose . received by infant's thyroid and the _ radiciodines contribute essentially all of this dose. Therefore, it is possible to demonstrate compliance with the dose limit of Technical Specifications Appendix B Section 3.4.a.1 for radiciodines and particulates by only evaluating the infant's thyroid dose due to the release of radioiodines via the contaminated forage / cow / goat / milk pathway. " Date 12/86 Page 40 of ODCM
.Rev No.. 4
+= ,.
tg.c ;> 4 ({
.The calculating - method to be used includes c 'a conservatism factori of 0.8 which assures
[ that - the calculated - dose' is always greater
~
F' than 'or equal = to - the : actual . dose despite
-possible atypical distributions of- radio-nuclides in .the gaseous- effluent. The simplified dose equation reduces'to:
h Eq.4-28 D r = [3.17E-8 (D7Q)iod nes ir* Si ] / 0.8 (b). Approach Selection Criteria l The limited analysis may be used in all cases to demonstrate compliance with the dose limit of , Technical. Specifications F Appendix B Section 3.4.2.1 (7.5 mrem /qtr) for radioiodines and particulates. However, for the dose assessment included in the s emi- annual Radioactive- Effluent Release Report, doses will.be evaluated for all designated; age groups and organs via all designated pathways from- radioiodines and particulates measured in the gaseous ef-fluents according to sampling and analyses required by Technical Specification. 4.5 Dose-Projection-Determination of Need to Operate Offgas Rad-waste 4.5.1 Requirement-Technical Specifications Appendix B Section 3.6.a requires that the.offgas radwaste treatment system be used to re-duce radioactive material in waste prior to discharge with the offgas treatment system not in use, doses due to gase-ous releases from the site will be projected monthly in accordance with the following methodology. 4.5.2 Methodology The following calculation method is provided for determin-ing the projected doses. PD = 31 x D Eq.4-29 Y p Y PD g = gxD g Eq.4-30 A Rev. No. _4 Date 12/86 Page 41 of ODCM
g- o 5.0 40 CFR 190 DOSE EVALUATION Technical Specifications Appendix B Section 5.1.a requires that the annual (calendar year) dose or dose commitment to any member of the public from uranium fuel cycle sources be limited to <25 mrem to the total body or any organ (except the thyroid which is limited to <75 mrem). The following approach should be used to demonstrate compliance with these dose limits. 5.1 Evaluation Bases Dose evaluation to demonstrate compliance with the 40 CFR 190 dose limits need only be performed if the quar- l terly and annual doses calculated in steps 3.4.1, 3.4.2, 4.4.1, and 4.4.2 exceed twice the dose limits of Technical Specifications Appendix B Sections 2.3.a, 3.3.a and 3.4.a respectively. Quarterly doses exceeding 3 mrem to the total body- (liquid releases), 10 mrem to any organ (liquid releases), 10 mrads equivalent gamma air dose, 20 mrads equivalent beta air dose, or 15 mrem to the thyroid or any organ from radioiodines and particulates (atmospheric releases) and annual doses exceeding 6 mrem to the total body (liquid releases), 20 mrem to any organ (liquid releases), 20 mrads equivalent gamma air dose, 40 mrads equivalent beta air dose, or 30 mrem to the thyroid or any organ from radioiodines and particulates (atmospheric ; releases) would require 40 CFR 190 evaluation. The dose , evaluation includes dose contributions to a maximally i exposed real individual from the calendar quarter in which the quarterly or annual limits were exceeded in addition to plant offsite dose contributions during the balance of the current calendar year. For purposes of the evaluation, if required, it may be as-sumed that the dose commitment to the maximally exposed real individual from other uranium fuel cycle sources is neglig-ible. However, dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. 5.2 Doses From Liquid Releases For the evaluation of doses to real individuals from liquid releases, the same calculating method as employed in section 3.4 will be used. However, more realistic assumptions and any current field data or updated estimates may be used, if available, concerning the dilution and ingestion of fish and potable water by individuals who live and fish in the area. Also, the results of the Radiological Environmental Monitor-ing Program will be included in determining more refined estimates of doses to real individuals by providing data on actual measured levels of plant-related radionuclides in the environment. Rev. No. 4 Date 12/86 Page 43 of ODCM m _ _
p- .,
~
5.3 Doses From Atmospheric Releases For the evaluation of doses to real individuals from the atmospheric releases , the same calculating methods as em-ployed in section 4.4 will be used. In section 4.4, the total-body dose factor (K,) should be substituted for _ the -
) To determine the total body dose..
gamma airthe Otherwise dose factor
. same (M,lating sequence applies.
calcQ However, any-current field data or updated estimates may be used, if available, concerning the actual location of real individu-als, the meteorological conditions, and. the consumption of food'(e.g., milk, meat and vegetation). Data obtained from the latest land use census (Technical Specifications Appen-dix B Section 6.2) should be used to determine locations for evaluating doses. Also, the results of the Radiological Environnental Monitoring Program will be included in deter-mining more refined dose estimates to real individuals by providing data on actual measured levels of radioactivity and radiation at locations of interest. 5.4. Doses From Direct Radiation Because 40 CFR 190 requirements include consideration of the offsite dose contribution from direct radiation, an estimate must be provided in the evaluation. Direct radiation dose contribution from turbine shine and from outdoor facilities containing radioactive material, if applicable, may be esti-mated by shielding calculations or from the results of the environmental monitoring program for direct radiation.
6.0 REFERENCES
6.1 Background References 6.1.1 Regulatory Guide 1.109, Rev. 1, October 1977. 6.1.2 NUREG-0133, October 1978. 6.1.3 Impell Corporation RG109 Computer Analysis, Impell Version 2, Rev. O. 6.1.4 Technical Specifications Appendix B. 6.2 Essential References / Controlled Documents None Rev. No. 4 Date 12/86 Page 44 of ODCM
.n. - 3 ,
TABLE L-l' MAXDOi PERMISSIBLE CONCEN1 RATIONS IN WAFJL IN UNRESIRICTED AREAS b .Nuclide- MPC (uCi/ml) Nuclide MPC (uCi/ml) ! (Insol.) -(Sol.) (Insol.). (Sol.) H-3 3 E 3 E-3 Ru-103 8 E-5 8 E-5
.Na-24 ~3 E-5 2 E-4 Ru-105. .1 E-4 :1 E-4 y . P-32 2 E .2 E-5 Ru-1% 1 E-5 'l E-5.
Cr-51 2 E-3 2 E-3 Ag-110m 3 E-5 3 E-5 h -54 1 E-4' L1 E-4 Sn-113 8 E 9 E-5 Mi-56 1 E-4 1 E-4 In-113m 1 E-3 1 E-3 Fe-55 '2 E-3 8 E-4 Sb-122 3 E-5 ^ '3 E-5 Fe-59~ 5 E-5 6 E-5 Sb-124- 2 E-5 2 E-5 Co-57 4 E-4 5 E-4 Sb-125' 1 E-4 1 E-4 i Co-38 9 E-5 1 E-4 Te-125M ~1 E-4 2 E-4 Co-60 3 E-5 .5 E-5 Te-127M '5 E-5 6 E-5 Ni-65 l'E-4 1 E-4 Te-127 2 E-4 3 E-4 Cu-64 -2 E-4 3 E-4 Te-129m 2 E-5 3 E-5' Zn-69: 2 E-4 1 E-4 Te-129 8 E-4 8 E-4
-Zn-69 2 E-3 2 E-3 Te-131m 4 E-5 6 E-5
.Br-82 4 E-5 3 E-4 Te-131 None None Br-83. .3 E 3 E Te-132 2.E-5 3 E-5 Br-84 None None I-130 3 E-6 3 E-6 Br-8f None None I-131 6 E-5 3 E-7 l Rb-86 2 E-5 7 E-5 I-132. 2 E-4 8 E-6 i Rb-88 None None I-133 4 E-5 1 E-6 Rb-89 None None I-134- 6 E-4 2 E-5
-Sr-89 3 E-5 3 E-6 I-135 7 E-5 4'E-6
- Sr-90 4 E-5. 3 E-7 Cs-134 4 E-5 9 E-6 Sr-91 5 E-5 7 E-5 Cs-136 6 E-5 9 E-5
- - Sr-92 6 E-5 7 E-5 Cs-137 4 E-5 2 E-5 Y-90 2 E-5 2 E-5 'Cs-138- None None-Y-91m 3 E-3 3 E Ba-139' None None 3 E-5 2 E-5 3 E-5 Y-91 3 E-5 Bs-140 Y-92 6 E-5 6 E-5 Ba-141 None None Y-93 '3 E-5 3 E-5 Ba-142 None None. l Zr-95 6 E 6 E-5 La-140 2 E-5 2 E-5 ,.
L- Zr-97 2 E-5 2.E-5 La-142 None None
- - Nb-95 1 E-4 .1 E-4 Ce-141 9 E-5-- 9 E-5 Nb-97 9 E-4 9 E-4 Ce-143 =4 E-5 4 E-5
'Mo-99 4 E-5 2 E-4 Ce-144 1 E-5 1 E-5 L Tc-99m 3 E-3 6 E-3 Pr-144 None None .
I- Tc-101 None None W-187 6 E-5 7 E-5 Np-239 1 E-4 1 E-4 (1) If a nuclide-is not listed, refer to 10 CFR 20, Appendix B, and , use the most conservative insoluble / soluble MPC where they are given in Table II, Colten 2. All MPC values are taken from 10 CFR .20, Revised as of January 1,1984, 1 (2) None - (As per 10 CFR 20, Apendix B) No MPC limit for any single radionuclide not listec. above with decay mode other than alpha anission or spontaneous fission and with radioactive half-life less than 2 hours. } Rev. No. 4 Date 12/86 Page 48 of ODCM
gh Blank Page Rev. No. 4 Date 12/86 Page 139 of ODCM
. . 1 TABLE G-4
- ENVIR0lEENTAL PADMAY - DOSE CONVERSION FACIORS HR GASECUS DISCIMRGES (Pi)
- c PA'I1NAY - INIMIATION AGE GROUP - CHILDRm o
NUCLIDE ORGAN DOSE FACIOR - G E.4/YR PER pCi/M3) 2: BONE LIVER HIYROID KIDNEY IENG GI-Ill SKIN 'IUTAL BODY o H- -3 0. 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 0. 1.12E+03 N---13 2.78E+01 2.78E+01 2.78E+01 2.78E+01 2.78E+01 2.78E+01 0. 2.78E+01 C---14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73EM3 0. 6.73E+03 l P---32 2.60E+06 1.14 EMS 0. O. O. 4.22E+04 0. 9.87E+04 "mm "mm mm" ""mA AmmA m"m "mm " " " *
- AR--41 CR--51 0. O. 8.54E+01 2.43E+01 1.70EM4 1.08E+03 0. 1.54E+02 MN--54 0. 4.29E+04 0. 1.00E+04 1.58E+06 2.29EM4 0. 9.51E+03 FE--59 2.07E+04 3.34E+04 0. O. 1.27E+06 7.07E+04 0. 1.67E+04 00--57 0. 9.03E+02 0. O. 5.07E+05 1.32E+04 0. 1.07E+03 00--58 0. 1.77E+03 0. O. 1.11E+06 3.44E+04 0. 3.16E+03 l 00--60 0. 1.31EM4 0. O. 7.07E+06 9.62E+04 0. 2.26E+04 NI--63 8.21E+05 4.62E+04 0. O. 2.75E+05 6.33E+03 0. 2.80E+04 l c ZN--65 4.25EM4 1.13E+05 0. 7.14E+04 9.95E+05 1.63E+04 0. 7.03E+04 "mm m ** m m ""m mm" mm"
' O KR--85 mm"
""R "mm ww"
"* "mm W" *A m m "mm KR-83M wmaa "Rm um " *mmA " " m m m aa KR-85M KR--87 WR" " =" " AA " " "mm "
w "AA"" AA""AA ^^^A"** "A""A
- A A A"" AA"AAA* """" ^^^^^"A KR--88 m KR--86 0. 1.98E+05 0. O. O. 7.99E+03 0. 1.14E+03 KR--89 Amma "m "W ******** "m "m m" "m RB--89 0. 2.05E+02 0. O. O. 1.13E+00 0. 1.72E+02 RB--87 0. 1.17E+05 0. O. O. 1.10E+03 0, 5.07E+04 RB--88 0. 5.53E+02 0. O. O. 1.70EMI 0. 3.60E+02 SR--89 5.99E+05 0. O. O. 2.16E+06 1.67E+05 0. 1.72E+04 i m SR--90 6.77EM7 0. O. O. 1.48E+07 3.43E+05 0. 4.51E+06
$O Y---90 4.11E+03 0. O. O. 2.62E+05 2.68E+05 0. 1.11E+02 Y---91 9.14 EMS 0. O. O. 2.63E+06 1.84E+05 0. 2.44E+04 ZR--95 1.90E+05 4.18E+04 0. 5.96E+04 2.23E+06 6.10E+04 0. 3.70E+04 " 6.14E+05 3.70E+04 0. 6.55E+03 NB--95 2.35EM4 9.18E+03 0. 8.62E+03 "mm u mm" m"m m"m =m" = " " * "mm mm" NB-95M o RU-103 2.79E+03 0. O. 7.03E+03 6.62E+05 4.48E+04 0. 1.07E+03
- 1.84E+05 1.43E+07 4.29E+05 0. 1.69E+04 RU-106 1.36E+05 0. O.
AG110M 1.69E+04 1.14E+04 0. 2.12E+04 5.48E+06 1.00E+05 0. 9.14EM3 l
@ 0. 2.19E+05 2.17E+06 1.84E+05 0. 1.25E+04 o CD115M 0. 2.92E+05 3: 1 1
NOIES- 1) " m "
- Means that the contribution from this nuclide was not caputed due to insufficient data. l
- 2) Based on 1 pCi/sec release rate of each isotope and a value of I for X/Q, depleted X/Q and relative l deposition.
l
TABLE G-4 , ENVIR0tM27FAL PAT 1MAY - DOSE CONVERSION FACIDRS R)R GASEOUS DISGARGES (Pi)
- o PAT 1MAY - INHALATION AGE GROUP - G ILDREN o
NUCLIDE ORGAN DOSE FACIDR - GREM/YR PER pCi/M3) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TUTAL BODY s-SN-123 4.77E+05 7.92E+03 8.40E+03 0. 3.55E+06 1.50EM5 0. 1.55E+04 SN-126 2.31E+06 3.85E+04 1.05E+04 0. 1.12E+07 6.03E+04 0. 8.73E+04 SB-124 5.73E+04 7.40E+02 1.26E+02 0. 3.24EM6 1.64E+05 0. 2.00E+04 SB-125 9.84E+04 7.58E+02 9.10E+01 0. 2.32E+06 4.03E+04 0. 2.07E+04 TE125M 6.73E+03 2.33E+03 1.92E+03 0. 4.77EM5 3.38E+04 0. 9.14E+02 TE127M 2.49E+04 8.55E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 0. 3.02E+03 TE129M 1.92E+04 6.84E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 0, 3.04EM3 I--130 8.05E+03 1.61E+04 1.82E+06 2.41E+04 0. 5.03E+03 0. 8.31E+03 I--131 4.81E+04 4.81E+04 1.62E+07 7.87EM4 0. 2.84E+03 0. 2.72E+04 a I--132 1.95E+03 3.75EM3 1.78E+05 5.76EM3 0. 2.95U03 0. 1.73E+03 o I--133 1.64E+04 2.01E+04 3.81E+06 3.35E+04 0. 5.43E+03 0. 7.63EM3 8 I--134 9.47E+02 1.74E+03 4.09E+04 2.66E+03 0. 7.71EM 2 0. 8.03EM2 I--135 4.78E+03 8.49E+03 7.70E+05 1.30E+04 0. 4.32E+03 0. 4.03E+03 CS-134 6.51E+05 1.01E+06 0. 3.30E+05 1.21E+05 3.85E+03 0. 2.25E405 C CS-135 2.31E+05 1.53E+05 0. 5.66E+04 1.93E+04 8.03E+02 0. 1.65E+04 3 CS-136 6.51E+04 1.71E+05 0. 9.54E+04 1.45E+04 4.18E+03 0. 1.16E+05 m CS-137 9.06EM5 8.25E+05 0. 2.82E405 1.04E+05 3.62E+03 0. 1.28E+05 CS-133 5.72E+02 7.59E+02 0. 5.62E+02 6.15E+01 2.44E+02 0. 5.01E+02 XE-133 "mm "mm " mm" awam ******** m" "mm XE-135 ** m m "mm "mm am"" mw" ="= m"m "mm XE135M "mm "mm "wm "mm "mm m"m m"m "mm XE131M mm" m"= "mm mm" ="= mm" mm" ="m XE133M *"m" "mm *= m A *mma Am"" m"m mm" "mm XE-138 "mm ="m "mm m " """" mm" "mm m"m , ,o im IA-140 6.44E+02 2.25E+02 0. O. 1.83E+05 2.26E+05 0. 7.55E+01 i$ BA137M mm" """" "" "m " m *"m" ""m "mm a;aa;;La akka;;A' *Aaaaa^k ; a;;Aa' ;;A;A*AA ^^^;;;A; A'a='Aaa aaAAaaAA XE-137 BA136M "mm mm" "mm m"m am A """" "" ******** 5 BA-140 7.40E+04 6.47E+01 0. 2.11E+01 1.74E+06 1.02E+05 0. 4.33E+03 CE-141 3.92E+04 1.95E+04 0. 8.54E+03 5.44E+05 5.66E+04 0. 2.90EM3 CE-144 6.77E+06 2.12E+06 0. 1.17E+06 1.20E+07 3.88E+05 0. 3.61E+05 o PR-143 1.85E+04 5.55E+03 0. 3.00E+03 4.33E+05 9.73E+04 0. 9.13E+02 ND-147 1.08E+04 8.73E+03 0. 4.81E+03 3.28E+05 8.21E+04 0. 6.80E+02 o FE--55 4.74E+04 2.52E+04 0. O. 1.11E+05 2.87E+03 0. 7.7,7E+03 e o
% NUTES: 1) "mm Means that the contribution from this nuclide was not computed due to insufficient data.
- 2) Based on 1 pCi/sec release rate of each isotope and a value of I for X/Q, depleted X/Q and relative deposition.
TARTF G-4 o BVIR0rNENIAL PA11MAY - DOSE CONVERSION FACIORS EDR GASEOUS DISCHARGES (Pi) j W PA11MAY - IMIA1ATION AGE GROUP - CHILDREN l o MXIIDE ORGAN DOSE FACIDR - OREM/YR PER uCi/M3) Z BONE LIVER THYROID KIDNEY Il1NG GI-ILI SKIN TUTAL BODY O FO--99 0. 1.72E+02 0. 3.91E+02 1.35E+05 1.26E+05 0. 4.24E+01 TC-99M 1.77E-03 3.47E-03 0. 5.05E-02 9.47E+02 4.79E+03 0. 5.75E-02 e TC--99 5.60E-08 6.22E-08 0. 7.31E-07 1.41E-04 3.24E-06 0. 2.23E-08 PM-147 1.06E+01 7.61E-01 0. 1.34E+00 6.64E+00 1.72E-01 0. 4.11E-01 SM-147 ******** m"m m m ** " m """" "mm m"= "mm PR144M m" m"" m"m "" m " "m "m" m"m PR-144 2.83E-02 8.77E-03 0. 4.64E-03 7.44E+02 9.35E+01 0. 1.42E-03 ND-144 mm" m"m "mm """" wm" ""m* m"m "mm TE-129 9.27E-03 3.32E-03 6.78E-03 2.44E-02 2.78E+02 2.42E+03 0. 2.26E-03 1--129 2.18E-08 1.33E-08 8.87E-06 2.24E-08 0. 4.46E-10 0. 1.18E-08 TE-127 5.35E-02 1.84E-02 3.78E-02 1.36E-01 1.93E+-2 1.09E+03 0. 1.18E-02 SB-126 4.01E+00 6.11E-02 2.33E-02 0. 6.67E+02 1.32E+02 0. 1.44E+00 g IN115M ="m ******** "m"A m " " A A "W mama n IN-115 ""m* ""m m" m"= m"m m"= m " mm" AG-110 mum m"m mm" m m ** m"m "mm "mm "mm RH-106 m"m "mm m"m mm" "mm "mm wm" mm"
- RH103M ""mA mm" "mm A m " ** mm" W"m m " AmAm w
h TUTAL 8.50E+07 5.55E+06 2.29E+07 2.82E+06 9.78E+07 3.96E+06 0. 6.13E+06 m n co U w V N 1 O l i o l C l O l ;WOIES: 1) "mm Means that the contribution from this nuclide was not mmputed due to insufficient data. l
- 2) Based on 1 pCi/sec release rate of each isotope and a value of 1 for X/Q, depleted X/Q and relative I deposition.
+ >
y TABE F-2 EFTILBTT PONIERING SYSIEM IRTA 1 - SM FLING DEIECIOR RANGE CONIM L AIARM REFERENCE 3 PONIER o DESGIPTION IDCATION TYPE MNCITONS SEITOINT CALIBRATI(N 4 USED SOURCE o E 6 1 Main stem Located near 4-gama 0-10 aR/hr Direct scran, Yes Victoreen Cs line monitor the main ste m sensitive contanination, gauna dose rate e lines downstrean ion chanbers isolation source of the outboard (closure of MSIV's, PEIV's in the recire isolation stean tunnel valves, vacutna puup line valve) 6 Yes Gas sanple Off-gas Ibrbine 252' 2-ganma 0-10 mR/hr Initiate closure l radiation west sensitive ion of off-gas system comited on -{ a isolation valves Ge(Li) g monitoring chambers o systen t' Off-gas pipe Stack Scintillation 0-106CPS Indicate and record Yes Gas vent g (Stack) detectors rate of release of marinelli monitor radioactive material counted on to the envirornnent Ge(Li) Process liquid Rad Waste - RW Scintillation 10 I-106 Monitor for leaks of Yes Representative radiation 272' Serdce detectors CPS closed systems. liquid sanple monitors H03 Monitor normal re- counted on 2 ' lease of radio- Ge(Li) y Heater Bay 252' active material to the enviromnent ' w l l O l P% O l 0
. e ,- o
-APPENDIX H ENVIRONMENTAL SAMPLE LOCATIONS TABLE TITLE PAGE H-1 Radiation Environmental 281-
< Monitoring Sampling Locations . FIGURE-H-l! Environmental Sampling 284 [ Location Map H-2 Environmental Sampling Location Map 285 i H-3 ' Liquid Effluent Pathway - 286 Water Intake Points s 9 Rev. No. 4 Date 12/86 Page 278 of ODCM
ENVIRONMENTAL SAMPLING LOCATIONS 1.0 ENVIRONMENTAL MONITORING PROGRAM 1.1 Sampling Stations The current sampling locations are specified in Table H-1 and Figures H-1, H-2. The Radiological Environ-nmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick Nuclear Power Plant, respectively. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. The average dispersion and deposition parameters for the two units have been calculated for a 5 year period, 1978 through 1982. The calculated dispersion or de-position parameters will be compared to the results of the annual land use census. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days. If a new location is added, the old location that yields the lowest cal-culated D/Q may be dropped from th program af ter Oc-tober 31 of that year. 1.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Inter-laboratory Comparison Program, such as the EPA Cross-check Program. Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples are available. The actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Re-port so that the Commission staff may evaluate the results. Specific sample media for which EPA Cross Check Program samples are available include the following: o gross beta in air particulate filters o gamma emitters in air particulate filters Rev. No. 4 Date 12/86 Page 279 of ODCM a
. :,oc..
- o. 1-131 in' milk o gamma emitters in milk o gamma emitters in food product o gamma emitters in water
- o. tritium in water-o I-131 in water 1.3 Thermoluminescent Dosimeters Used for Environmental .
Measurements Thermoluminscent Dosimeters (TLDs) are placed in an inner. ring of stations in the general area of the site boundary (TLDs 7, 18, 23, 75-87), and in an outer ring in the 4 to 5 mile range from the site (TLDs 8, 88-95). There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring. TLDs are also placed in special interest areas such as population centers, nearby residences, schools, and' control lo- I cations (TLDs 14, 15, 18, 49, 56, 58, 96-101). ( Rev. No.. 4 Date 12/86 Page 280_ of ODCM
y e 'cg i
.g TABLE H-1 RADIATION HWIR0tNENTAL MNITORDK; SAMPLING IDCATIONS Type of Map Sample location Collection Site - Iocation Radiciodine and 1 Nine Mile Point Road 1.8 mi @ 88* E Particulates (air) North (R-1)
Radiciodine and 2 Co. Rt. 29 & Iake Road (R-2) 1.1 mi @ 104* ESE Particulates (air) Radioiodine and 3 Co. Rt. 29(R-3) 1.5 mi @ 132* SE Particulates (air) l Radiciodine and 4 Village of Lycoming, NY(R-4) 1.8 mi @ 143 SE Particulates (air) Radiciodine and 5 Montario Point Road (R-5) 16.4 mi @ 42' NE i Particulates (air) Direct Radiation (TLD) 6 North Shoreline Area (75) 0.1 mi @ 5' N Direct Radiation (TLD) 7 North Shoreline Area (76) 0.1 mi @ 25' NNE Direct Radiation (TLD) 8 North Shoreline Area (77) 0.2 mi @ 45' NE Direct Radiation (TLD) 9 North Shoreline Area (23) 0.8 mi @ 70' ENE Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi @ 90* E Direct Radiation (TLD) 11 Rt. 29(79) 1.1 mi @ 115* ESE Direct Radiation (TLD) 12 Rt. 29(80) 1.4 mi @ 133* SE Direct Radiation (TLD) 13 Miner Road (81) 1.6 mi @ 159" SSE Direct Radiation (TLD) 14 Miner Road (82) 1.6 mi @ 181* S Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi @ 200* SSW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi @ 225' SW Direct Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 mi @ 250* WSW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi @ 265* W Rev. No. 4 Date 12/86 Page 281 of ODCM
y 4.. TABLE H-1 (Continued) RADIATION DNIR0tt! ENTAL METIORING SAMPLING IDCATIONS Type of- Map
- Sanple . Incation Collection Site location i Direct Radiation (TLD) 19 North Shoreline Area (85) 0.2 mi @ 294* WNW {
f Direct Radiation (TLD) 20 North Shoreline Area (86) 0.1 mi @ 315' NW ! Direct Radiation (TLD) 21 North Shoreline Area (87) 0.1 mi @ 341 NNW l Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi @ 97* E !
-Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi @ 111* ESE 1:
Direct Radiation (TLD) 24 Rt. 104(90) 4.2 mi @ 135' SE Direct Radiation (TLD) 25 Rt. 51A(91) 4.8 mi @ 156' SSE Direct Radiation (TLD) 26 Maiden Lane Road (92) 4.4 mi @ 183* S Direct Radiation (TLD) 27 Rt. 53(93) 4.4 mi @ 205* SSW Direct Radiation (TLD) 28 Co. Rt. 1(94) 4.7 mi @ 223' SW . l Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi @ 237* WSW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 mi @ 170* S-SSE Direct Radiation (TLD) 31 SW Oswego Control (14) 12.6 mi @ 226' SW , Direct Radiation (TLD) 32 Scriba, NY(96) 3.6 mi @ 199* SSW ! Direct Radiation (TLD) 33 Alcan Alumintrn, Rt.1A(58) 3.1 mi @ 220' SW Direct Radiation (TLD) 34 Lycoming, NY(97) 1.8 mi @ 143' SE Direct Radiation (TLD) 35 New Haven, NY(56) 5.3 mi @ 123' ESE Direct Radiation (TLD) 36 W. Boundary, Bible Canp(15) 0.9 mi @ 237* SW-WSW t Direct Radiation (TLD) 37 Lake Road (98) 1.2 mi @ 101* E-ESE Surface Water 38 OSS Inlet Canal (NA) 7.6 mi 0 235' SW-WSW Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi @ 70* ENE I Rev. No. 4 Date 12/86 Page 282 of ODCM
7_ W&n TABLE H-1 (Continued) I RADIATION DNIR0tt! ENTAL FONI'IORING SAMPLING IDCATIONS Type of Map Sanple location Collection Site location Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi @ 80 E Fish 41 NMP Site Discharge Area (NA) 0.3 mi @ 315 NW and/or
' Fish 42 NMP Site Discharge Area (NA) 0.6 mi @ 55 NE Fish 43 Oswego Harbor Area (NA) 6.2 mi @ 235' WSW
-Milk 44 Milk Location #50(NA) 9.3 mi @ 93* SE
, Milk 45 Milk location #7(NA) 5.5 mi @ 107' ESE Milk 46 Milk Location #16(NA) 5.9 mi @ 190* S ,
Milk 47 Milk location #65(NA) 17.0 mi @ 220' SW Food Product 48 Vegetation location #1(NA) 0.6 mi @ 81.5* E (JAF Site Boundary) Food Product 49 Vegetation location #2(NA) 0.9 mi @ 75.0* ENE (JAF Site Boundary) Food Product 50 Vegetation location #3(NA) 0.9 mi @ 105.5* ESE (JAF Site Boundary) Food Product 54 Vegetation Iocation #4(NA) 15.0 mi @ 223' SW (McMillen) NOTE: 'Ihe numbers in parentheses are environmental program number designations. Rev. No. 4 Date 12/86 Page 283 of ODCM
.-p
' FIGURE H ENVIRONMENTAL SAMPLING LOCATION MAP
. Figure'H-1 is over sized and is located in the folder at the back of this document.
Rev. No. 4 Date 12/86 Page 284 of ODCM
eo* e FIGURE H-2 ENVIRONMENTAL SAMPLING LOCATION MAP Figure H-2 is oversized and is located in the folder at,the back of this document. l i l i Rev. No. 4 Date 12/86 Page 285 of ODCM t .-}}