ML20236L148
| ML20236L148 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/30/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20236L018 | List: |
| References | |
| AP.310, TAC-64736, NUDOCS 8711100165 | |
| Download: ML20236L148 (105) | |
Text
_ _ _ .
I SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 0FFSITE DOSE CALCULATION MANUAL PAGE _1 0F 105 AGM, Tech & Adim Serv /Date Mgr, Quality /Date AGM, Nuc Pwr Prod /Date Quality Review Required [X] Yes [] No PRC Review Required [X] Yes [] No MSRC Review Required [X] Yes [] No Revision Sumary:
Complete Rewrite I
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B711100165 871030 PDR ADOCK 05000312 PDR P
t
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 0FFSITE DOSE CALCULATION MANUAL PAGE _2 0F 105 1.0 PURPOSE The Offsite Dose Calculation' Manual-(00CM) describes the methodologies used to calculate doses from ionizing radiation to the general-public due.to operations at the Rancho Seco. Nuclear Generating Station (RSNGS). In addition, methodologies are described for using the results of the calculations to demonstrate compliance with 10 CFR 20, 10 CFR 50 and the Rancho.Seco Technical Specifications as they apply to liquid and gaseous effluents.
2.0 SCOPE The 00CM describes the methodologies used to calculate doses to the general public, effluent'moaitor setpoints,
- pre-release and post-release parameters and diffusion coefficients .for both gaseous and liquid effluents. The -
00CM also contains a Data Base of important parameters i used in the calculations (Attachment 7.1). Detailed instructions for performing th'e calculations described in '
the ODCM are contained in separate implementing procedures for the 00CM.
3.0 REFERENCES
3.1 Code of Federal Regulations, Title 10, Chapter 1, Parts 20, 50.34a and Part 50 Appendix I.
3.2 Rancho Seco Unit 1 Technical Specifications, Sections, Sections 3.15 through 3.26, 6.15 and 6.16.
4.0 DEFINITIONS 4.1 Average Individual The Average . Individual is defined as that person whose.
characteristics for offsite dose calculation purposes are at the 50th percentile for the data.being used. These characteristics include such factors as usage factors, occupation times, etc. Data associated with the Average Individual is used only for Calculations to demonstrate compliance with 40 CFR 190.
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I SMUD-NUCLEAR ORGANIZATION NUMBER: .AP.310 q REVISION : 4. ;
0FFSITE DOSE CALCULATION MANUAL- PAGE _3 0F 105 1
4.2 Real Individual The'Real Individual is defined as any person.who participates in~ activities that result in that person being in the actual pathways for offsite dose. A Real Individual who is expected, based on land census, to receive the maximum offsite dose to real individuals may . !
be used to calculate doses to demonstrate compliance with 40CFR190. ;
l' 4.3 Batch Release 4.3.1 The discharge of liquid radioactive wastes.of discrete volume. Batch releases are norma 111y from one of the Retention Basins to the Waste Water discharge canal. ."C" RHUT is a non-radioactive source of water and can'be used _
as a' source of dilution water when it is being discharged. d i
4.3.2 The discharge of gaseous wastes of discrete volume. Batch. -
1 releases for the gaseous pathway include but are not .
j limited to Reactor Building Purges and Waste Gas' Decay' l Tank releases. j 4 4 4.4 Continuous Release 4 4.4.1 Continbous liquid releases are not planned to be made from RSNGS. j i 4.4.2 A continuous gaseous release is the discharge of-gaseous '
wastes of a nondiscrete volume from a system that may have an input flow during the release.
4.5 Default Radionuclides Mix A mixture of radionuclides that can be used to determine monitor set points when no detectable activity is available. (Tables A-1, Liquid Source Terms and Table A-13,GaseousSourceTerms).
4.6 Dilution Flow l
The volume or volume rate of fluid' (liquid or gas) which.-
is added to a radiological release stream for ths purpose of decreasing the instantaneous concentration of the -
stream. )
(0 J
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 0FFSITE DOSE CALCULATION MANUAL PAGE _4 0F 105 4.7 Maximum Hypothetical -Individual The Maximum Hypothetical Individual is a hypothetical receptor of radiological. exposure resulting from the.
discharge of radioactive effluent. The maximum ..
. hypothetical individual is characterized as;" maximum" .with regard to food consumption, occupancy, other usage factors 1 or exposure pathway parameters'in the vicinity of Rancho l Seco that would represent an individual with. habits {
greater than usually expected for.the average of the - 1 population in general. No single individual would be ]
expected to be. exposed to all the potential effluent exposure pathways at the " maximum" value. For dose ,
calculation purposes, the " maximum hypothetical- !
individual" concept is used only in calculation for compliance with Technical Specifications 3.17.1, 3.17.2, 3.18.1, 3.18.2 and 3.18.3. .The numerical value of.each consumption or usage factor is equal to the value at the -
85th percentile-of the distribution which has been >
established for the actual population in the vicinity of '
Rancho Seco. In the event site-specific data is not available, the recommended values from USNRC Regulatory 1
Guida 1.109 are used.-
4.8 RSNGS Rancho Seco Nuclear Generating Station j
l 4.9 Unrestricted Area 1 Any area at or beyond the site boundary access to which is ,
not controlled by the licensee for purposes of protection '
of individuals from exposure to radiation and radioactive materials, and any area within the site boundary used for-residential quarters or industrial, commerical, institutional and recreational facilities. For i environmental protection / effluent control purposes, the l Rancho Seco Unrestricted Area is the area outside the I Exclusion Area and Liquid Effluent Discharge boundaries, i as shown'in Figures.4.8-1 and 4.8-2.
-4.10 Windspeed Interval The differential increments that result from the partitioning'of the magnitude of the wind velocity range. ,
The velocity-data is gathered from= the. wind speed channels of the meteorological tower for RSNGS. Table A-8'of the ODCM Data Base contains the wind speed intervals and their
- average velocities used in this ODCM.
SMUD-MUCLEAR ORGANIZATION NUMBER: AP.319 REVISION': 4 OFFSITE DOSE. CALCULATION MANUAL PAGE -5 OF 195 m,t
, f 5.9- "FWM:EDURE ,
a -
r b.
5.1 Calculations Involving Liquid Effluents - General f Considerations ]
5.1.1 The liquid effluent discharge of RSMOS fcrues the headwaters of Clay Creek. The. dilution factse of a typical nuclear power plant is not applicable.
5.1.2 Dilution of the liquid effluent occurs offsite:
- 1. At the confluence of Clay and Hadselville Creek and of Hadselville and Laguna Creek.
\
- 2. At the confluence of Laguna Creek and the Casuunnes_' t ~ {
River. )
- $ j tA )
5.1.3 For calculation of offsite doses'to determine complimace {
with 49 CFR 199 (Technical Specification 3.25) dilution j which occurs outside the' protected area may be used. When 'j dilution outside of the protected area is used, the l following general equation applies:
F Cd=C a p l l
d l Where: I C is e m uentration downstream from a d
confluence.
.. ,r,. , , . ,
- w, j ff ,. "h
{CTD fa&, U ,
-t.e.
is the concentration upstream from a
, f *,? . j,., confluence.
',}Q Q @D+
8 "' 'h<
C[ is the average yearly upstream flow rate.
Ff F is the aver age yearly downstream flow rate.
d 5.1.4 When calculations are done to demonstrate compliance with Appendia I, 19 CFR 59 (Technical Specifications 3.17.2),
no dilution which. occurs outside . the liquid effluent release point is used.
i l
l SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319
-e REVISION : 4 l OFFSITE DOBE CALCULATION MANUAL PAGE --
6 OF 195 4
- g , m '
1 5.2 ' Calculations for Compliance With 19 CFR 29 (Technical l Spoolfications 3.17.1 and 3.15).
5.2.1 Pre-Release Calculations 5.2.1.1 Radioactive 11guld effluent discharges normally originate in one of the RHUT tanks (A or B) and are then discharged to one of the Retention Bacins (North or South). Samples ,
are collected and analyzed from each RRUT prior to I discharge to ensure that compliance with Technical Specifications 3.17.1 and 3.17.2 can'be achieved when '
discharging from the Retention Basins. The Retention Basin discharge is the actual liquid affluent release 4 point. , . ,
9 : !
5.2.1.2 The following equation is used to determine.if a UlA s A " ,_
radioactive liquid ef fluent discharge will' meet the!,$. '
)
conditions of Technical Specification 3.17.'1 :
- C' F#
MPCF, = 2 MPC.
1 FC+Fr Where: i MPCF, is the calculated MPC fraction of the radioactive liquid effl%ent to be discharged.
Cg is the total concentration of radionuclides
. , "1" in the batch, prior to dilution, of
,3
,j_.yj.y % ,q liquid effluent in pCi/ml.
, v k?9 f t . ; L : 4'
- M3 ,' ,
e'a i j q? 4 y ;
e n r.
i
- - un W C g .,,/ % is the MPC of radionuclides "i" from Appendia B, Table II, Column 2 of le CFR 29 in pCi/ml. l F is the flow rate of the radioactive liquid r
batch release from the retention basin to the Masta Water Discharge' Canal (GPM). .l I
I l
F is the total available flow rate of the C
dilution water at the time of discharge of- -1 the 11guld effluent-in GPM.
1 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319
, Q* ,
REVISION : 4 OFFSITE. DOSE PAGE 7 OF 195
- y (CALCULATION MANUAL 2, is a built in saftey factor which will allow for the reaction time of equipment I and/or Operations personnel as MPCF, is used to determine the 11guld effluent monitor set .
I point.
Compliance with Technical Specification 3.17.1 has been demonstrated when MPCF, is less than or equal to 1.9.
I 5.2.1.3 When it is desired to determine the dilution flow or i maximara discharge flow so as to meet Technical ..
Specification 3.17.1 the following equations are used:
MOTE: 2E C g /MPC g 11 will require a determination of 't eitherminimumdilutionflow(F,)ormaximumdischargep flow (F7 ). I y . - 3 5.2.1.3.1 Minimum Dilution Flow (F ) j C'
F cain
= F r ( 2 -1) l WC i
Where F is set at a f1med value.
r ;
5.2.1.3.2 Masimma Discharge Flow (F rma )
4 .
.p t Mmfy % .hf{ ,g 4:gp
" ,',)?, D ?.;ili
. It: G .. -
F J :
M,st ,o,".
- 4 C
?*"" ' M - V C
( 2 1 - 1}
MPC g Where F ** * * '"" '" ""*
C l
5.2.2 Monitor Setpoint Calculation i i
l MOTE: When no batch release is occurring or the liquid effluent. I streams which make up the batch have no detectable. )
activity,.then the mixture.in Table A-1 of the ODCH Data -l Base anny be used to make the liquid effluent monitor l
_m __e m _ __ m _ _ _ m _ m m _ m _m_ m .c,_ n n - n n _- ;
I SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 OFFSITE DOSEfCALCULATION MANUAL PAGE 8 OF 105 4
5.2.2.1 The' following' equations are given for the general situations:
5.2.2.1.1 When the monitor is measuring the radioactivity of a process liquid prior to that liquid being diluted by either dilution flow or volumetric dilution:
Cg F FC+ r undiluted " i '( MFC i
} ( F r
+ 0 i
l 5.2.2.1.2 When the monitor is measuring the radioactivity of the liquid effluent as it is discharged or no further dilution will occur prior to discharge offsite, the f ollowing .
formula is used - '
4
@s.
^
ft Cg ZCg /( +
LSP,gg =h MFC 1 l l
l 5.2.2.1.3 Where LSP is the monitor setpoint level in pCi/ml.
for either the diluted or undiluted case.
Bkg is the background re$ ding of the monitor 7 z .. g in pCi/ml.
4
.9- , gn. .m jy['Ag.'V
'F
.~
^
- '., g
.u is the flow rate of the Waste Water Canal (jp* 4 []* 6- (total avaialahe dilution flow) prior to the addition of process liquids from the Retention Basins and/or RHUT's in GPM.
F is the flow rate of the Retention Basin or C REUT in GPM. l 5.2.2.2 LSP is the highest value which shall be used as the alarm setpoint for the liquid effluent monitor. A. lower value may be used for the liquid effluent monitor. alarm setpoint.
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SMUD-NUCisan ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSITE' DOSE CALCULATION MANUAL PAGE _9 OF 195 R
5.3 'Caioulations For Compliance With 19 CFR 59, Appendix I (Technical Specification 3.17.2) !
l 1
5.3.1 Prior to the intitiation of a batch release, a calculation j of the projected dose from the liquid pathmey is made. l This projected dose is added to any cumulative dose for i the calendar year and quarter.
5.3.1.1 Pre-Release Calculations are performed to estimate if-the limits of Technical Specification 3.17.2 will be maintained for the total amount of radioactive material expected to be released in the liquid effluent. The following equations are designed so that the dose from the release will allow f uture releases that will be within the applicable limits. A 19 */. reduction in the limits of.
Technical Specification 3.17.2 is used. This allows for, errors in estimation, analysis, equipment, etc. The'l[
f ollowing equations are used: 4 q,j' 5 "
+
5.3.1.2 The expected dose from the release is found by the following equation:
1 D,J = A gJ (C gg AT F, )
t Where:
D, is the highest total calculated dose to a I Maximum Hypothetical Individual's organ (or K total body), j in erem for the release.
M*@)T@ k j@%Q E X,1 1' is the Rancho Seco site related ingestion
, as s.kD cv yp Yf p .( U' dose factor to the total body or any organ for each identified principal gamme and beta emitter 1isted in Table A-7. The units of Ag are urem-ul/hr-pC1. C gg is the activity of the Radionuo11de 1" in the liquid effluent to be released in pCi/ml.
o -- 1 { -- l l. SMUD-NUCI.Ran ORGANIZATION NUMBER: RP.319
. REVISION : 4 OFFSITE DOGE CALCULATION MANUAL PAGE _10 OF 195- l
, 1 F, is the near field average dilution factor for C g during any. liquid effluent release. j defined as the. ratio of the ma ximum )'
undiluted liquid waste flow during release - to the average flow f rom the site discharge structure to unrestricted receiving waters. AT is the expected time period of the release ; in hours . l 5.3.1.3 The Rancho Seco site related ingestion dose factor, A j ,
]
is found by .the following equation.
.y A =
gj 1.14 ES (21.BFg)(DFgJ) J 41 E Where BF g and DF g have the meanings assigned to themfin , USMRC Regulatory Guide 1.139
*D <
g' ' l 5.3.1.4 Determination of the releases impact on Technical Specification 3.17.2 limits is determined by the following dose tracking equations [ Dst + Dfta l bI* hqt l
~
1 month n month [D so +Dfon] [4.5 - Dbqo] 1 month n month
'htgl b* h st l
~
M.. s .
'd%. %
jr' q.3 1(q ter a quarter ce sg 4 K .3iD* so - +D foq] [9.9 -'Dhao] i quarter a quarter i Where D is the empeated whole' body dose from the release in _ area. D is the espected whole body dose from fta future-planned' liquid releases within the current calendar: month in mrem. , i
,0, 7
c ,
,9g -
SMUD-MUCISAR ORGANIZATION < NUMBER: AP.319 , REVISION : 4 ) OFFSITE DOSE. CALCULATION MANUAL 'PAGE _11 OF 195 j 3 ;
~1.35 is the limit from Technical Specification f
, 3.17.2 for quartely, total body dose minus le
% in aren.
(1.5 - (.1 X 1.5) $[1.35) 7 D is the dose to the total body within the current-calendar, quarter from liquid releases in area. D so is the highest-espected organ doseffiom the release in uren. E"'" l 4 D is the empected whole body; dose from: fan f", furture liquid releases pisaned fois the*,g. current calendar quarteer ifs l mrem. A m 8[ ;ph, '
- 4.5 is the qdarterly organ dose' limit from Technical Specification 3,17.2 minus le %.
(5 - (.1X5) = 4.5) ' n .,
,U D is the highest.ortgan dose.within the' current calendar goarter from liquid releases in " wen.
D o tbm espected total body dose'from ftq 1 planned liquid..rplease for rest of the calendar quarter.
' 3 y 2< ' a. _,
f
's qd
- a '. s.,)tg3+n;;.
.g.. M..Q LRG;4c .- y, 4 K. ,yft;#
is the Ilseit from Technical Specification
.'p pgQ%;r mpz j 3.17.2 for annual total body dosn minus ten u,--
- y. An! area.- c(3. 0 - (9.1H3) = 2.7) ,
i D is the highest total body dose from liquid releases for the current calendar year in uren. ' I
.i l
D, _ sun is the highesi organ oose from planned liquid releases during the rest of the calendar quarter. l
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. SMUD-NUCIEen ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSI'IE DOSE CALCULATION (AANUAL PAGE -
12 OF 195 g 9.9 ,
) is the limit from Technical Specification 3.17.2 for organ dose for one year in urem "I' minus le */.. (19 - (8.1X19) = 9.9)
Dg, ;- is the highest organ dose from liquid releases during the current calendar year in y are a. - I n is the number of months left in the current calendar quarter, including the current month. e is - the number of q'uariters left in the ; current calender year, including the 4 7.] 1
\ current quarter.' W -~,>-
y, ~
-l b,,4pY 5.3.1.5 The determination of dose from f uture planned relsaites.ti.,'.
, .I 1
calculated,by using an average of the offsite dose'f h, ' previous l'ir,uid releases.This average is determined k al unren/ day basis. The following formulas are used to ' "- , compute future doses. l 4
% 3.1.5.1 Historical Dose Rate Average
' ?.
D =D /365 t Where 6 is the historical dose rate average in t a.r . #.3 ., aren/ day to the total body.. pm, ., .; ., 7.
-Mf;;ff,c r h ;;
g 3di$, \ h,i.: ; ." SE. 9,-+ p. is the average of all previous year's total
.+
~
_i A";y O c& M fo; f: t p> body doses in serem/yr. f
. 365 is the number of days in one year. I And the organ dose rate average, 6,, ist i D = D /365 o on Where: l
.,.- i
'e .r
,7_ ,e _
.(-
y a i
.4 l q> '
'5 f ;
i SMUD-MUCLEAR ORGANIZATION T ", MUMBER: AP.319 6 REVISION : 4 OFFSITE DOGE CALCUIJI' ION MANUAL 3 PAGE _13 OF 185 s k & o . Ns is the' historical dose rate average i} i e i arekday to the organ having the highest p\- dosdl rate. . ( ,,,y i s 4
',n
- s. c.4 D
na is t,he av rage of the previous year,-chdoses
, j for the organ (s) having the highest dose.
8 1 5.3.1.5.2 The values for planned future doses are f ourt by: ,
,& 1 f, d
> - 4 i ]
D fta i (Dt I) Y .
.c 2
'\'/j t ..
l : l
., xj $ aQt. 1 and v /; (I y, r.lip g ' )y, j ,
~ , ;- ~S , l D
fam
=
(6a I) ,
i t' ,!
'< , t I
Where E is the n'auber of days lett in the calendar month. i,'.
/
D " ftq t t
-f.. .'
i A , and g
)
(
, 4 D =
' (6 oM) / y fog ,
p i / Y j Where M J s the utwjoer of days lett in!the calendar ' Ic Y quarter.i j 3 / // N y ;py r; + o 3 m. s' 1
.h. ykdrM vp%;d M ,
( i 5.3.1'.6 .. h t:the results of the calcula ions .ip' Sections 5.3/.t.1 Cilksgi 5i3165 show ' that the releat s' day tal in eacoss of the ~
~ 3
.. ' 11alis ts jgsf 3 Speci f ica t ion ,3.,17. 2, asesures 'shall'he taken to dI
~
i 4.rgdenettheignanthty o'f' radioactive natarial to Jy , I discharged such thatfSpecification 3.17.2 timits will be 1 met. Guidelices for the reduction of radio. active material in liquid efflidents are contained in# the OLCM implementing procedures. t e
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[ ,/ 3 ,i
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'){- /
s
,s
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l F( , I
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i
.,e
, wt-.
; 4, ,i
- i I, 'y , a h_ i.
'<' 3 ;
M+C s t h ; 1 9
?d> .
+
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 i REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE 14 OF 105 l
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5.3.2 The calculations perf ormed for determination of Of f site l Doses for the liquid pathway follow the mathematical j models in USNBC Regulatory Guide 1.199. These models are j used to compute the dose to an~individur.1's total body or j one of six organs for a given type and age group'of the individual. Determination of quarterly and annual dose is taken from the cumulative amount of radioactive m4terial discharged via the liquid release pathway. In all cases, $ data which reflect the Maximum Hypothetical Individual are 'l used to' demonstrate compliance with Technical j Specification 3.17.2. l i 5.3.3 The liquid release pathway consists of ten separate subpathways. The sum of the doses f rom each ' subpathway yields the total dose to an individual in one of four: age classes. line age classes are ' defined in USKRC Regulatory Guide 1.199. The ten subpathways are - Freshwater Fish, Freshwater Invertebrates, Drinking Water, Shoreline Deposits, Swimming, Boating, the Fruits, Vegetables','and 3 Grains subpathway, Meat,-Milk'and Leary Vegetables. [t ,1 5.3.3.1 The equation \to determine dose from the Freshwater Fish and ! Freshwater Invertebrate subpathways is: , w I' U M I ( Q.1 DampJ
. .exp(-A.tp} }
R . = 1100 ap p B. apJ Ap 1 F 5.3.3.2 The dose f rom the Drinking Water suta.ithways is: l s U M l R apJ
. = 1100 ap p I ( Q.1 D arpJ
. .exp(-A_t2.p} } l l
F l e f 5.3.3.3 The dose from the Shoreline Deposits subpathway is. l l 0 U M d R apJ
. = 110,000 ap p W I'{ Q.1 T.
1 D alpJ[exp(-A.tp)] 1 I F [1-exp(-A jtb l}' s [d- l
1 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 i
~
REVISION : 4 d OFFSITE DOSE CALCULATION MANUAL PAGE 15 OF 105 5.3.3.4 The dose from the Swimming' and Boating subpathways is. ;j found hy the following equation: . R 1190 ap p I (.Q;
- 1D.exp(-A.t1 p))
. =
apJ 1 F i Where D. is the dose conversion factor found in Table 1 A-37. The units of D g are urem-liter /hr-pC1. 5.3.3.5 The.four irrigated foods subpathways are the Fruits,. ] Vegetables and Grains subpathway, the Mbat.subpathway, the '] Milk subpathway and the Leafy Vegetable subpathway. The' ) equation to determine the-dose f rom any one ' of these : j subpathways is. 1 U M R apJ
. = 1199 ap p I E {Q.-oxp(-A.tp}}
1 1 , F
\
{Dalpj r (1-exp(-Ae it-) e u Ei f B I
+ 1 iu [1-exp(-A tg b)3 PA g )
1 l 5.3.3.6 Doses of ionizing radiation from Tritium can, occur in the Freshwater Fish, Freshwater Invertebrate,' Drinking Water and Irrigated Foods subpathways. Tritium enters into- 1 equilibrium with products in the Irrigated Foods subpathways. Therefore, the. concentration of Tritium in food products.cannot exceed the concentration of Tritium in the water which entersLinto the Irrigated Foods' - subpathway. Because of_this,.the following equations 2 i apply when calculating doses from Tritium'in the Irrigated Foods'subpathways.. 1 U M R = 1190 ap p'I Z-'{ Q g D aTpj eMP(-A T t )) F Where the subscript lT refers to the values for Tritium. :
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f SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE 16 OF 105 1 5.3.4 The'fs11owing symbols and values used in the equations in section 5.3.2 have tbo meanings and units.as listed in USMRC Regulatory Guide 1.189, " Calculation'of Annual Doses - to Man From Bountine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with le CFR Part 59, ! Appendia I": ! l B gy, B gp,D,gpj, F,'F j IA' I' I' N' P P, Qgg, Q,Q'# g F 8 R ,T, g t h, t,, t h, t p, U,p, W, Y,, A g, A Ei, 1 , and lie,ces. 5.3.4.1 The table below gives the location in USERC Regulatory; . s, Guide 1.189 where values of the referenced variables.oan be found. , . A Variable USNBC Regulatory Guide 1.199 Tdble ;. Ic,. v a( S ? . '.1. B, g E-1 - B ' A-1 D,g p E-11.thru E-14 F E-1 iA P E-15 t b E-15 5.3.4.2 The table below gives the location in the ODCH Data Base (Attachsment 7.1) where values of.the referenced variables can be found.
)
Variable ODCN Data Base Table
-2 Mp$y;I,gf.ip; A-2 Q f.. 19*4y p
,M h34.4 cs. A-3 l A-4
. ; 'y -h.g t
h A-4 t g_4 p Y, A-5 l Ag A-36'
I ! e nuu-n uu .n.w w unuunatustun nunoent ur.J1W 1 f' REVISION : 4 ! OFFSITE DOSELCALCULATION MANUAL PAGE 17 OF 105 i 5.3.4.3 The following values have been assigned: Variable Value W 9.2 r 0.25 Where W is a shore-width factor that describes the geometry of the esposure. r fraction of deposited activity retained on orops, leafy vegetables, or pasture grass. h 5.3.5 The total dose from all subpathways to an organ (or' total body), j, of an individual, a, in uren is: 14
~'
h?. DL,j = R (Fish) + R (Invertebrate) ~j { u, '-
.tz
+ R,,j(Water) +'R,, (Shoreline)
+ R,,j(Swimming) + B,, (Boating)
+ R,pj(Fruits, Vegetables & Grain)
+ R,,j(Leafy Vegetables)
+ R, (Milk) + R,,j(Heat) i 1
Where DL, is the dose to the organ, J, of an individuni:cla age class, a, in wem for a period of one
, i ysMar'.mf arcis[-:b liquid ef fluent pathway.
*: 1, g g */ Q 5.3.6 Freum(taie Iysis of composite samples and other sample j G
'aasiyeinfoIJ11guld effluents, a calculation of the offsite '
-dese fNee 1>iquid releases is performed after each calendar month to determine the cumulative quarterly dose and annual dose.
5.3.7 Compliance with Technical Specification 3.17.2 is demonstrated when: i
f f SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310
, REVISION : 4 t OFFSITE DOBE' CALCULATION MANUAL PAGE 18 OF 105 5.3.7.1 The dose to the total body is less than or equal to 1.5 mrom and less than or equal to 5.6 mrem to any organ in a calendar quarter from radioactive materini discharged as liquid effluents.
l 5.3.7.2 The dose to the total body is less than or equal to 3.9 mrem and less than or equal to 19.9 mrem to any organ in a calendar year from radioactive material discharged as liquid effluents. i 5.4 Gaseous Effluent Release Points and Boundaries 5.4.1 The Gaseous Effluent release points at RSMGS are <,f summarized in Table 5.4-1. g,} ( Table 5.4-1 fd;[h Gaseous Effluent Release Points _ p , i t 3 , Release Point Data Reactor Building Systems Reactor Building Stacks Ventilation i Flow rates 74,999 CFM l Height of Top of Stacks: 146 feet above grade Location MBW face of the Reactor Building 3
's k? + v.C neight of
,7Ik.I,' Top of Nearest
'%L AW Structure: 162 feet above grade
#'lffyf6, . g. (Reactor Building)
. y 4, +
, .vl1 Jn ,
i l I
. f
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE OF 105
. <, i s
Table 5.4-1 Gaseous Effluent Release Points i Continued
]
Auxiliary System: Auxiliary Building Building Stacks Ventilation Maaius:n Flow rate: 42,399 CFM (with one Fan motor) l Height of l Top of Stacks: 146 feet above grade Locatlon: WSW face of the~ Reactor Building
>. f Height of f Top of Nearest '1 4 Structure 162 feet above grade. ;
(Reactor Building) Auxiliary Systems Ausiliary Building Building Grade Ventilation Level Vent Maximum Flow rate: 19,598 CFM Height of Top of Stacks: 66 feet above grade Location: ME Corner of the , Auxiliary Building
,kbift dj E,at-Gi,f Height of
" 44 13YS2 y' 7 ,3
^
Top of Nearest f-[.p3-!] ' ' V f :- Structures 162 feet above grade-S, F p-M% ,jgk, Jy;p (Reactor Building) j ,q - Miscellaneous System Miscellaneous Waste Waste Water Unter Evaporator Evaporator Vent Maaiaus Flow rates Variable, dependent upon evaporator pressure
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310
- .g REVISION : 4 l OFFSITE DOSE l CALCULATION MANUAL PAGE __20 __ OF.105 j i
Table 5.4-1 Gaseous Effluent Release Points Continued Miscellaneous Beight of Haste Water Top of Veni: 146 feet aoove grade Euaparator Uent (continued) Locations MBM Face of the Reactor Building Ebight of Top of Mearest Structures 162 feet above grade (Reactor Building) { d' i
, , 1
.c -
5.4.2 The two boundaries for. compliance with gaseous efflamat-} Technical Specifications are the Esclusion Area Bpundary and the Gaseous Effluent Discharge Boundary. The y ,%" T Esclusion Area Boundary,is for calculations involving Technical Specification 3.18.1. The Gaseous Effluent Discharge Boundary is used for calculations involving Technical Specifications 3.18.2 and 3.18.3. In general the Esclusion Area-Boundary is used for calculations to demonstrate compliance with le CPR 29, - while the Gaseous Effluent Discharge Boundary is used for calculations to demonstrate compliance with le CFR 59, Appendim I. 5.5 Diffusion Methodology for Gaseous Effluents 5.5.1 The calculation of diffusion of gaseous effluents at RSNOS uses the " Chi over Q" method as outlined in USERC Regulatory.0nide 1.111 and USNRC NUREG/CR-2919. Because y jef;the chairectoristics of the Rancho Seco Nuclear !
< Generating Station's Site, all gaseous releases from RSMGS
(%faretaamsidered to be ground level releases. Diffusion y insiemaat'. ions for continuous releases use cantinuous - f asteurologloal data for the period of time under ocasideration. Diffusion calculations for batch releases compile the joint frequency. distributions ,(from the actual time releases were occurring) in order to determine the batch diffusion coefficients (z/Q or 6g(r,0) 5.5.2 Windspeed, horisontal wind direction, and ambient temperature are measured at le meters and 68 meters above grade at a single tower on District property'3000 feet ! east f rom the Roactor Building. - Wind Spaed Intervals, Radial Sector Boundaries and Atmospheric Stabilities are contained in Table A-8.
j1 I
)
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE 21 OF 195 1 1 5.5.3 Amamal' average values of.z/Q and 6g(r.0) (the deposition ' rate) are meintained in Tables A-9, A-19, A-11 and A-12. These tables are updated annually in accordance with the iglementing procedures for this ODCH. 5.6 Calculations for cogliance with 19 CFR 29 (Technical Specifications 3.16 and 3.19.1). l 5.6.1 Pre Release Calculations - Batch Gaseous Releases l 5.6.1.1 After appropriate radiological analysis, the following ! formulas are used to determine cogliance with 19 CFR 29 at the Exclusion Area Boundary: R = 1 tb .
. 1 (z/Q ZQ ~Ig) + D t h* '
3.: , - I i 3988 L' ~ E,
=
g/Q Z Q (Lg + 1.1Mg ) + D, I A R, =
+
"a # 91p 1 D, i
i 5.6.1.2 When all of the ratios E th' I s" o equal to 1.9 then compliance with Technical Specification I 3.18.1 has been demonstrated. 5.6.1.3*',.'ThE(foiabagsymbolsandnumbersusedintheequations in
;;.V ,. on#5.e.1.1 have the meanings assigned to them 1 w ?.Am . NUREG-9133:
c,
~}{
' Lg%;?p{.
i(Eg l.17 W,, Pg The values for P g are found'in Tables A-39 through A-43. t 5.6.1.4 The variable g/Q refers to the highest average annual value in the sixteen meteorological sectors in Table 4-9 at the Enclusion Area Boundary . 5.6.1.5 The variables are defined as follows:
SMUD-NUCLEAR ORGANIZATION NUMBER: RP.310 REVISION 4 OFFSITE DOSE CALCULATION MANIJAL PAGE 22 OF 105
) #y y Table 5.6-1 Symbols and Numbers Used in Section 5.6.1.J VARIABLE DESCRIPTION I
R " #"*' " I '" #" " tb limit (5GG .wom/yr) to the actual total body dose rate (aren/ year) at the Exclusion Area Boundary for the radioactive noble gases in the release under consideration. D is the total body dose from the radioactive t noble gases in any other ongoing releases.. I which are planned to occur at the time of'. s the batch release. ?. I' M
... . ff '
m D}ft .i
- ' - q .
l R, is the ratio of the skin dose rate limit I (3999 mrea/yr) to the actual skin dose rate (arem/ year) at the Exclusion Area Boundary for the radioactive noble gases in the release under consideration. D, is the highest skin dose from the radioactive noble gasss in any other ongoing releases which are planned to occur at the time of the release. y O:.:a;' fjfh; f y;i' f5 is the highest organ dose rate (aren/ year)
. i ,, '
?
.+ - w a ,) 7' - from the release due to Iodine-131, go;q;g"" .i % 4# Iodine-133, Tritium and particulate with
~
half livos greater than eight days in any
~ CQ other ongoing releases which are planned to occur at the time of the release.
l l l l SMUD-NUCLEAN ORGANIZATION NUMBER: AP.310 l
. .j REVISION : 4 i OFFSITE DOSE CALCULATION MANUAL PAGE 23 OF 105 i Table 5.6-1 Symbols and Numbers Used in Geotion 5.6.1.1 VARIABLE DESCRIPTION )
R, is the ratio of the organ dose rate limit (1598 arem/yr) to the actual organ dose rate (mren/yr) for the critical organ at the Esclusion Area Boundary plus any ongoing releases espected during the batch release.
' l I
is. .s ! Q3 is the espected release rate of gy ;pf radionuclides "i" from release point Yhd: '
)
during the espected time of the baMob '$ releans., 5.6.1.6 The following variables have these values assigned VARIABLE ASSIGNED UALUE l r S.2 for particulate
.1.9 for radienuo11 des 4 l
t 24 hours or 8.64E4 seconds, g t 3.15E7 seconds or one year
?Alib s1 N1 l 5.6.2 t'or Ses ints - Gaseous Batch Releases
' Qa,,)th c u [y " %
.ap ~1e .
5.6.2.1 The#espected ' dose ratios for the total body and skin dose rates are determined for the' gaseous effluent batch te be released using the equations in Section 5.6.1.1. These espected dose ratios are used to determine radiation monitor alarm set points for total body or skin dose limits, whichever is most limiting.. C i tb
- 5 R, to l l
a C, ts " 2 ~ R s e I
.\
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319
~
i REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE 24 . OF 105
' 'IMhere C g is the concentration of noble gas radionuclides "1" in the gaseous' effluent to be released.
5.6.2.2 The smaller of the two values found in 5.6.2.1 is used as 3 the monitor setpoint in Ci/cm .- This is the highest value which may be used as a monitor setpoint. Lower values for the monitor setpoint may be useG. 5.6.2.3 The symbolt and values in Section 5.6.2.1 have the following meanings a M or is t e a are se Point'for the gaseousI tb e a ge . N effluent monitor ubich cause'an alare/ trip ts m qm such that plant equipment'and/or Operati,ons personnel can react so as to bringrthoff, F release under control and maintain theh'- limits of Technical Specification 3.18.1. l I 2.9 is a factor whloh alloes'for the reaction-time of plant equipment, Operations personnel and errors in analysis, equipment ] accuracy, etc. ; Qg is the concentration of noble gas radionuclides "1" in the gaseanus effluent to be released. cl . . y' ,% ' > j . '}-"Jfk 5.6.3 'Gmemous Effluents - Continuous Releases
} }fg l 5.6.3.1 ' Dataloa[the types and quantitles of radioactive material dreteesed asi, gaseous offluents are determined from the samples and analysis taken according to Part E of Table 4.22-1 of tho'BSNGS Technical Specifications. Other.
samples of gaseous affluent streams may also be used to perform analysis of radioactive material released as gaseous effluents.' These data are used in.tuu umys. First, the data ara used as historical data'to estimate future release levels for the purposes of determining monitor setpoints. Second, the data are used in calculations to determine dose rates at the'Esclusion Area Boundary from' continuous releases of gaseous effluents released at RSNOS. The Historical Mia for: determining the gaseous effluent monitor setpoint during continuous , releases ls amintained in Table A-12.
-1 )
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 : REVISION : 4 l OFFSITE DOSE CALCULATION MANUAL PAGE 25 OF 105 l 5.6.3.2 The calculation of gaseous effluent monitor setpoints for continuous releases is determined by using the Historical Mix in Table A-12. i 1 l 5.6.3.3 The percentage values of each of the j noble gas radionuclides in-Table A-13 is used to determine j the fraction of radionuclides "i" in the historical mix. I l P. k F.
= l 3 00 */. !
l Where: i F. 2 is the fraction of radionuclides "i" in the J 1 historical. mix. 1 Pg is the percentage of radionuclides "i" in , each of the release points in Table A-13. i ( 5.6.3.4 The total nob {e gas concentration which yields a dose rate of 500 mre dyr (total body) and 3090 mrem /yr (skin) is determined. See nt (1 E6)(z/Qg ) IP g E g IF A 3090
"*~
(1 E6)(z/Q ) IF IP g (L g + 1.1Mg ) Where: Fp is the highest flow rate in-cubic meters per second for gaseous release point, "p". Each of_the release points.used in Table A-13 are used in the summation term of F. P 1 l4 vf
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE 26 OF 105 5.6.3.5 The highest value of A,4 or A ns is hosen. .This value is-used to compute the, gaseous monitor setpoint for continuous releases. MSP = A or A no nt ns And MSP g is the highest gaseous effluent monitor alarm /setpoint for continuous releases which will cause plant equipment / Operations personnel to take actions to bring the release under control such that compliance with Technical Specification 3.18.1 is maintained. 5.7 Calculations for Determining Compliance With 10 CFR 50, Appendix I, Section II, B.1 (Technical Specification-3.18.2) 5.7.1 The gamma and beta air doses are computed at the Site Boundary for Gaseous Effluents from the release of radioactive noble gases. The following formulas are used to compute the gamma air dose and beta air dose from the discharge o't radioactive noble gases as Gaseous Effluents i
'I 5.7.1.1 Gamma Air Dose -
D (r,0) = 3.17E-8 I M y [K/ Q (r,0) Q 1 ] + (K/Qb (r,0) Qib) 5.7.1.2 Deta Air Dose D (r,0) = 3.17E-8 I N g [z/Qg (r,0) Q g ] + [z/Qb k#' }9 1b 3 ls i 5.7.1.3 Values for M. and N. are provided in Table A-38 1 1 5.7.2 Compliance with Technical Specification 3.18.2 is - demonstrated when the f ollowing conditions are not: ] 5.7.2.1 For the air doses computed for 1 calendar. quarter, the highest dose of the sixteen radial sectors is less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation. l
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 REVISION : 4 i OFFSITE DOSE' CALCULATION I1ANUAL PAGE _27 OF 195 m I, I e 1 5.7.2.2 For the air doses computed for 1 calendar year, the { highest dose of the sixteen radial sectors is less than or equal to le erad for gamma radiation and less than or equal to 29 mrad for beta radiation. ] l l 1 5.8 Calculations for Determining Compliance With le CFR 50, i Appendix I, Section II, C (Technical Specification 3.18.3) ) l l 5.8.1 Doses that result from the release of Iodine-131, Iodine-133, Tritium and particulate with half lives ! greater than eight days released as airborn effluents from j RSMGS are determinate using the mathematical models in !
'USNRC Regulatory Guide 1.199. These models compute the dose to an individual's total body or one of s i x o'r'gans l for a given type and age group of the individual.; The; result of the calculation is for a period of one year.f(
Determination of quarterly and annual dose is~taken,frDe' - the cumulative amount of radioactive material discharging'ff JJ ) via the gaseous release pathway. In all cases, data 4mbich reflect the Maximum Hypothetical Individual are used t'a determine compliance with Technical Specification 3.18.2. 5.0.2 The gaseous release pathway consists of 3 general separate subpathways. The sum of the doses from each subpathway yields the total dose to an individual's organ or total body. The 3 general subpathways are: , 1 5.0.2.1 External irradiation f rom standing on contaminated ground. i l 5.8.2.2 Organ (total body) dose from the inhalation of radioactive unterial. 5.8.2.3. fGrgha
/dk .y . e t.-
total body) dose from the ingestion of radioactive ljgsteri I W
, A%u cy W.n u ..
ytp
.s . ,
5.0.3 jTheiformulaT, ror computing the dose from standing on loadeta'mineted ground is: D ,(r,O) = I [8769 SF 1E12 Sg(r,O,t) Qti DFG gJ] (1-exp(-Ag.tb))
)
h 1 i I J
l SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 i REVISION : 4
)
OFFSITE DOSE CALCULATION MANUAL PAGE 28 OF 105 ; i 5.6.4 The f ormula f or computing the dose f rom inhalation of radioactive material is: D (r,0) = I 3.17E4 g/Q(r,0,t) R Q it DFA, j 3 5.8.5 All of the symbols used in sections 5.8.3 and 5.8.4 have the meanings assigned to'them in USNRC Regulatory Guide 1.109 except for "t". The subscript t is used to denote a gaseous release (batch or continuous) which occurred during the time period of interest. l l 5.8.6 The dose to an organ "j"-(or total body) of an individual l
- of age class "a" at distance "r" in radial sector "O" from q
l the ingestion of radioactive material from gaseous releases is found from the ingestion of four classes of material. These four classes of. material are: 1) I vegetation, 2) milk, 3 seat and 4) leafy vegetation.
- 5.8.7 The total dose from releases of Iodine-131, Iodine-133, .
l Tritium and radioactive materials in particulate form with ; half lives greater than eight days to organ "j" (or total - body) of the Maximum Hypothet ical Individual of age class j "a" may also be calculated using the f ollowing expressi,on: DPR, = 3.17E-8 I R 1 ka [Iu cki Noi)
- INbki 9 hi ll l
5.8.8 The total dose from releases of Iodine-131, Iodine-133, Tritium and radioactive materials in particulate form with j half lives greater eight days to organ "j" (total body) of j the Maximum Hypothetical Individual of age class "a"'at j l distance "r" in radial sector "O" is: l l D G A D D.Ja(r,0) = D.(r,0) J + D.Ja(r,0) + D.Ja(r,0) i i L L
q l i i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 I
. REVISION : 4 l OFFSITE DOSEIi:ALCULATION MANUAL PAGE _,29 OF 195 1
% 1 5.8.8.1 Mberes I I
l l k is tue sunscript union uenotes tne patamay that the variable is associated with. The i f ollowing pathways are denoted by k s l 1 l Ground Plane l Vegetables - ingestion ' Meat - ingestion Cow milk - ingestion Goat milk - ingestion Inhalation
.1 i
DPR is total dose from releases of ... Iodine-131, Iodine-133, Tritium and .e l l radioactive materials in particulate forni' i I with half lives greater eight days [to okgan. ,
"j" (total body) of the Maximum Hypothetical Individual of age,clasr "a". l i
l 3.17E-8 is the inverse of the number 1 secured s in a year. I i R is the dose factor for each identified ijka radionuclides "1" for pathway "k", orgau "j" (or total body), and age group "a" in arem-sec/yr-Ci or urem-m3/yr pC1. Appropriate values for Egjg, are found in Tables A-15 thru S-33.
,:f
'yt e.
- 'nf i t t,
IU { , Ip# '} is the highest calculated annual
*[$k [ [
2, -[ ' 1 atmospheric dispersion factor releases for radionuclides "1" "k" from Table A-19. For the for continuous for pathway inhalation and ingestion pathways, values of 8 day decayed K / Q in sec/m are used. For Tritium, the zero decay g/Q values are used. For the ground plane pathway, values of 5 g(r,0) in m are used. l
1 I 1 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE _30 OF 185 Q,3 is the total amount of radionuclides "1" l released as a continuous gaseous effluent ; release during the time period of interest j in pCi. 1 Wggg is the highest calculated annual atmospheric dispersion factor for batch releases for radionuclides "1" for patheny "k" from Table A-12. For the inhalation and , ingestion pathways, values of 8 day decayed z/Q in sec/m are used. For Tritium, the zero decay z/Q values are used. For the ground plane pathemy, values of Sg(r,9) in
~
m are used. s 1
-- [ h - #
Q. bi is the total awount of radionuotide'"i"Ji, x - released >as part of batch. releases of gaseous effluents during the time period.of interest in gC1. 5.8.8.2 The values of E gJg, ase determined annually. Details of how these' calculations are perf ormed are given in the implementing procedure for the review and maintenance of l the ODCM. 5.8.8.3 Doses calculated from the formula in Section 5.8.11. may be used to determine the projected dose from a planned r,elease of, The resultant dette,[DPE{ yaseous r j,2 e - is addedradioactive to the pastmaterial. doses to the total body 1, ~ tor #ergan; fi t om Gaseous Ef fluents. This sum must less than d l l _i'tndr'limiltsdin Technical deepstratelocepliance withSpecification 3.18.3 in order Technical Specification to 3.18.3. q ,;f; g 5.8.9 Compliance with Technical Specification 3.18.3 is demonstrated when the following conditions are met: i 5.8.9.1 For the dose to the Maximum Hypothetical Individual of any age class to any organ or the total body computed.for 1 calendar quarter, the highest dose in any the sixteen. radial sectors is less than or equal to 7.5 mrem to'any organ and 2.5 mrem to the total body.
~ ~
\' ]
1 i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310
,, , < REVISION : 4 0FFSITE DOSE? CALCULATION MANUAL PAGE 31 OF 195 l
5.8.9.2 For the dose to the Maximum Hypothetical Individual of any age class to any organ or the total body computed for 1 calendar year, the highest dose in any of the sisteen radial sectors is less than or equal to 15 mrem to any organ and 5 mrem to the total body. 5.9 The formulas used in Sections 5.7 and 5.8 shall be used as appropriate to evaluate the potential dose from release l gaseous effluents for the purposes of cosylying with Technical Specification'3.18.4. A ' 5.19 Calculations for Determining Ccapliance With Technica3g ' .j Specification 3.25. z , 4(
'l-5.19.1 The Action statement of Technical Specification 3.25e; j-requires that a Special Report be' prepared in the event /
that calculated doses are twics the limits of Techoloal 1 Specifications 3.17.2.a. 3.17.2.b, 3.18.2.a, 3.18.2.b, l 3.18.3.a. or 3.18.3.b. The details of how the Special Report is prepared for oompliance with the Action statement of Technical Specification 3.25 are contained in the implementing procedure. The Special Report contains the following elements: , 5.19.1.1 Estimmtes of the radiation esposure (dose)_to a member of the public from uranium fuel cycle elements from all effluent pathways and direct radiation for the current calendar year. u . .+- 5.18.1.2 Deece19tlameVef the levels of radiation and concentrations eflead&oact'ive material involved. [c @/DN Ngh 5.19.1.3 Desuripklon'cfthecause(s)of the esposure(s).
?h! kNN Yhb ?=
5.19.1.4 Corrective ~actlon(s) ta be taken ta reduce subsequent releases to prevent reoccurrence of esoeeding the limits of the Technical Specifications listed in Section 5.19.1 5.19.2 If the limits of Technical Specification 3.25-have been exceeded and-if the condition (s) which caused _the limits to be exceeded have not'been corrected, a request-for variance is submitted with the Special Report.
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE _32 OF 195 5.19.3 The methodologies outlined in this ODCM shall be used in performing dose calculations required by Technical Specification 3.25. 5.19.4 Where available values associated with an identified individual shall be used in the calculation of doses q required by Technical Specification 3.25. 5.18.5 When inf ormation f rom the ODCM data base manual is used, data which matches the Seth percentile should be used. 5.10.6 In general, calculations should be performed for the . a, 3 Average Hypothetical Individual as defined Section 4.9. , j mt , I 7M, *~ d[ . " . . 5.19.7 Whole body counts, environmental samples, bioassays,Gh;U" , J environmental LLD results, Environmental Samplin6 Program 3 results and other such field data should he used ,to vehify3', l calculations required by Technical Specification 3.25. 5.10.8 The information gathered from the sources indicated in Section 5.11.7 may be used for the values of the terms in the mathematical models described in the appropriate sections of this ODCH. 5.10.9 Inf ormation on how to conduct calculations for the purposes of compliance with Technical Specification 3.25 are contained in the ODCM Iglementing Procedures. 5.11 Administration of Offsite Dose Calculations 4Af y,1 . .r>&
& . g 5.11.1" (1 ementing procedures which provide detailed
'dasdructions for'the calculation of Offsite Doses ,
'stetpointsk; Atmospheric Dispersion Coefficients and other
% walues?for which formulas are provided for in the ODCM shall be written and used.
5.11.2 A procedure for the review and maintenance of the ODCM shall be written and approved. Elements of this procedure shall include 5.11.2.1 Detailed instructions for the review and (if necessary) revision of the ODCM. The ODCM shall be reviewed annually.
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.319 REVISION : 4 OFFSITE DOSE CALCULATION MANUAL PAGE _33 OF 195 5.11.2.2 . Detailed instructions for the maintenance, review and revision of the ODCM Data Base (Appendix A to the ODCM). Provisions for the appropriate incorporation of Land Use Census Data, results of Environmental Monitoring Samples, changes to USKRC regulatory guides, etc into the ODCM shall be included. 5.11.2.3 Detailed instructions for the incorporation of new and/or improved mathematical models into the ODCM. These instructions will include details on validation and verification methods. 5.11.3 A procedure shall be written for the acquisition, maintenance and use of computer codes for.the computation of formulas given in the ODCH. Each computer code-shall 3 have it's own written procedure which provides detailed , j instructions on how to use tPat computer code. ,,
, j
$ @ {p( 4.
4 6.9 RECORDS ' i None 7.O AT1ACHMENTS 7.1 ODCM Data Base 4
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i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 0FFSITE DOSE CALCULATION MANUAL PAGE ,_36 0F 105 ODCM DATA BASE TABLE OF CONTENTS Table A-1 Liquid Source Terms Table A-2 Rancho Seco Site Liquid Effluent Pathway
- Usage Parameters l Table A-3 Rancho Seco Site liquid Effluent Pathway )
- Dilution' Factors i l
Table A-4 Rancho Seco Site Liquid Effluent Pathway l
- Time Parameters I Table A-5 Rancho Seco Site Liquid Effluent Pathway
- Irrigated Foods Parameters l l
Rancho Seco Site Liquid Effluent Pathway Table A-6
- Animal Consumption' Rates Table A-7 Radiological Impact On Man - Liquid Pathway i I'
Table A-8 Meteorological Constants Table A-9 1986 Annual Average X/Q and D/Q, Exclusion Area Boundary - Continuous Table A-10 1986 Annual Average X/Q and D/Q, Special Locations 4
- Continuous 1 I
Table A-11 1986 Batch Average X/Q and D/Q, Exclusion Area Boundary Table A-12 1986 Batch Average X/Q and D/Q, Special Locations Table A-13 Gaseous Source Terms Table A-14 Distances for Gaseous Effluent Pathway Evaluation Table A-15 R Values for the Rancho Seco Nuclear Generating Station
- Ground Pathway, Age Group - All ATTACHMENT 1 PAGE 1 0F 70
_.---__.-.____.5--.-_. _-------__M
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 l REVISION : 4 J 0FFSITE DOSE CALCULATION MANUAL PAGE _ 37 0F 105
]
I Table of Contents i Continued i Table A-16 R Values for the Rancho Seco Nuclear Generating Station
- Pathway -Vegetables, Age Group - Adult Table A-17 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Vegetables, Age Group - Teen Table A-18 R Values for the Rancho Seco Nuclear Generating I Station - Pathway - Vegetables, Age Group - Child j Table A-19 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Meat, Age Group - Adult j Table A-20 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Meat, Age Group - Teen ]
Table A-21 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Meat, Age Group - Child I Table A-22 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Cow Milk, Age Group - Adult i Table A-23 R Values for the Rancho Seco Nuclear Generating 1 Station - Pathway - Cow Milk, Age Group - Teen
]
Table A-24 R Values for the Rancho Seco Nuclear Generating j Station - Pathway - Cow Milk, Age Group - Child Table A-25 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Cow Milk, Age Group - Infant Table A-26 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Goat Milk, Age Group - Adult Table A-27 R Values for the Rancho Seco Nuclear tenerating Station - Pathway - Goat Milk, Age Group - Teen i Table A-28 R Values for the Rancho Seco Nuclear Generating - ! Station - Pathway - Goat Milk, Age Group - Child Table A-29 R Values for the Rancho Seco Nuclear Generating ; Station - Pathway - Goat Milk, Age Group - Infant i Table A-30 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Inhalation,- Age Group - Adult Table A-31 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Inhalation, Age Group - Teen ATTACHMENT 1 PAGE 2 0F 70 ___.__-mmm_.___.-___.m---____.__m
i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION : 4 0FFSITE DOSE CALCULATION MANUAL PAGE __38 0F 105 Table of Contents Continued Table A-32 R Values for the Rancho Seco Nuclear Generating Station - Pathway - Inhalation, Age Group - Child Table A-33 R Values for the Rancho Seco Nuclear Generating ; Station - Pathway - Inhalation, Age Group - Infant Table A-34 Distances for Gaseous Effluent Pathway Evaluation , Table A-35 Gaseous Effluent Pathway - Usage Parameters ] Table A-36 Radioactive Decay Constant i Table A-37 Imersion Dose Factors for Swiming Table A-38 Dose Factors for Noble Gases and Daughters - Table A-39 Inhalation Dose Factors for Infant (Pi) l Table A-40 Ingestion Dose Factors for Infant (Pi) -l Table A-41 Ingestion Dose Factors for' Child (Pi) Table A-42 Ingestion Dose Factors for Teen (Pi) Table A-43 Ingestion Dose Factors for Adult (Pi) ATTACHMENT 1 PAGE.3 0F 70 j 4
.i
l 1 J J j Y \ l![ > SMUD-NUCLEAR ORGANIZATION NUMBER: AP.3Ili ~ ~"'I I REVISION: 4 PAGE 39 0F 105 0FFSITE DOSE CALCULATION MANUAL j q TABLEA-lyIQUIDSOURCETERMS , A ) n, t ; i H Radioactivity (c) l Radionuclides MPCj (pCi/ml)(a) _-( Aj )(C1/yr) Ho-99 4.00E-5 (Insol)- 2.65E-3 I-131 3.00E-7 (Soluble) , 1.88E-3' I-132. 8.00E-6 (Soluble) 1.90E l, I-133' 1.00E-6 (Soluble)- 1.86E-3 Cs-134' 9.00E-6 (Soluble) 3.30E I-135 4.00E-6 (Soluble) .5.40E-4 Cs-137 , 2.00E-5 (Soluble). 92.50E-4 H-3 3.00E-3 (Both) 'i3.00E+1 .! Cr-51 2.00E-3 (Both) 1.00E Mn-54 1.00E-4 (Both) --- Fe-59 5.00E-5 (Insol)- 1.00E-5 , l Co-58 9.00E-5 (Insol) 1.20E-4 i j Co-60 3.00E-5 (Insol) . 1.00E-5
- 3 Total ---
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> ,t , i Notes j (a) Based on 10 CFR 20, Appendix B. Table II Column 2.
(b) Based on Anoendix I Evaluation Pecort _o Rancho Seco Nuclear Generattqg Station. Table 3.4-1. 1 3 (c) Liquid source terms are representative of the " radionuclides mix" of the liquid effluents. .A t i . i r. i Sy( i t ( [,, ATTACHMENT 1 E PAGE 4 0F 70- , b 1 ,;?
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f SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310
. REVISION: 4
' h. 0FFSITE DOSE CALCULATION MANUAL PAGE 40 0F 105 TABLE A-2 RANCHO SECO SITE i LIQUID EFFLUENT PATHNAY Usage Parameters Vap i Maximum Exposed Individual Pathway Units. Infant Child Teenager Adult Freshwater Fish Kg/yr 0 6.9 16 21 Freshwater Invertebrate Kg/yr 0 0.34 0.76 1 Drinking Hater R/yr 0 0 0 0 l Shoreline Deposits br/yr 0 14 100 200 Swimming hr/yr 0 100 100 100 Boating hr/yr 0 0 0 0 l , Irrigated Foods Fruits, Vegetables, Grain Kg/yr 0 520 630 520 Leafy Vegetables Kg/yr 0 0 0 0 i Milk . 2/yr 0 330 400 310 ! Heat, Poultry Kg/yr 0 41 65 110 Average Exposed Individual General Public Freshwater Fish Kg/yr 0 2.2 5.2 6.9 Freshwater Invertebrate Kg/yr 0 0.33 0.75 1.0 Drinking Hater 1/yr 0 260 260 370 l Shoreline Deposits hr/yr 0 9.5 47 8.3 Swimming hr/yr 0 '9.5 47 8.3 Boating hr/yr 0 9.5 47 8.3. Irrigated Foods Fruits, Vegetables, Grain Kg/yr
~
0 200 240 190 Leafy Vegetables Kg/yr 0 10 20 30 Milk 1/yr 0 170 200 110 Heat, Poultry Kg/yr 0 37 59 95
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.'t. REVISION: T ,
0FFSITE DOSE CALCULATION MANUAL 4 e /
- PAGE 41 DV "1$J,l p i*k TABLE A-3 j RANCHO SECO-SATE LIQUID EFFLUENT PATHNAY,
'l . Dilution Factors (reciprocal of Mp) .,
\
l' Maximum Exposed Individual'
'f Maximum Exposed Individual Quarter 1 Quarter 2 Quarter 3 QuarteN4 Freshwater Fish 1 1 1 1 5
Freshwater Invertebrate 1 1 1 1 Drinking We.ter ,' Shoreline Deposits 1 1 1 1- .e Swimming 1, ' jl. 1 1 Boating Irrigated Foods 1 '" i Fruits, Vegetables, Grain 1 1 1 1 l Leafy Vegetables I
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) Heat, Poultry
~
1 1 <1 1 4 s ,, l Averago Exposed 1 Individual ' i General Publicc s , t i
/, Freshwater F1sh'. 1000 100- .j100 1000
,.,. l Freshwater Invertebrate ~ 1000 4 100 1000
; Drinking Hater 1000 I 100 Shoreline Deposits 1000 100 k100 1000j 100 v 100 1000 i t Swimming 1000 y 100 100 INjo Boating 1000 (, 100 l'ICG(
Irrigated Foods ~",1000 j Fruitsi Vegetables, Grain 1000 100 100 100d' Leafy Vegetables .1000 100 100 1000 - Milk 1000 100 100 1000 . Heat, Poultry <. 3. 1000 100 .jQ, 100 , a1000 [' 4 3 ....
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SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 42 0F 105 TABLE A-4 RANCHO SECO SITE LIQUID EFFLUENT PATHNAY Time Parameters (hours) Maximum Average. 3 3 Exposed' Exposed General l Pathway Individual Individual Public ; Freshwater Fish 24 '24 168 Freshwater Invertebrate 24 24 240 Drinking Hater - 12 24 Shoreline Deposits 0 0 0 ' Swimming 0 0 0; Boating - . 0 Oa i Irrigated Foods 'i Fruits, Vegetables, Grains 336 1440 .1440* i Leafy Vegetables - 48 '48- 1 o Milk , 48 ~96 95 Meat, Poultry 480 480 480 Release Holdup and 72 96 96-Transit Time f
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, ATTACHMENT 1
( PAGE 7 0F 70-
SMUO-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 43 0F 105 i TABLE A-5 ! RANCHO LECO SITE , LIQUID EFFLUENT PATHNAY ! Irrigated Foods Parameters Non- Non-Irrigation Crop Growing Irrigated Irrigated ; Rate Yield Period Feed Hater ! (1/m2/month) (Kg/m2) (days) Fraction Fraction I Fruits, Vegetables, Grain 263 2.0 60 Leafy Vegetables 263 2.0 90 Milk 263 1.4 30 0- 1.0 Heat, Poultry 263 1.4 30 0 0 i TABLE A-6 RANCHO SECO SITE LIQUID EFFLUENT PATHWAY Animal Consumption Rates l i Feed or Forage Hater QF (Xg/ day) QAH (1/ day) Milk Cow 50 60 Beef Cattle 50 50
)
ATTACHMENT 1 PAGE 8 0F 70
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 44 0F 105 TABLE A-7 ! RADIOLOGICAL IMPACT ON MAN LIQUID PATHNAY MAXIMUM ADULT Ajj VALUES ORGAN NUCLIDE Bone Liver T. Body Thyroid Kidney Luna GI-LLI-H-3 0 2.3E-1 2.3E-1 2.3E-1 0 2.3E-1 2.3E-1 Na-24 4.1E-2 4.1E2 4.1E2 4.1E2 0 '4.1E2' 4.1E2 Cr-51 0 0 1.3E-1 7.6E-2 0 1.7E-1 3.2E1 Mn-54 0 4.4E2 8.4E1 0 0 0 1.3E3 Fe-59 1.0E2 2.4E2 9.4E1 0 0 6.8E1. 8.1E2 Co-58 0 8.9El 2.0E2 0 0 0 1 1.8E3 Co-60 0 2.6E2 5.7E2 0 0 0 4.8E3 Zn-65 2.3E4 7.4E4 3.3t4 0 0 0 4.6E4 Sr-89 2.2E4 0 6.4E2 0 0 0 - 3.6t3 - Sr-90 5.4E5 0 1.3E5 0 0 0 1.6E4 [ Nb-95 4.5E2 2.5E2 1.3E2 0- 0 0 1.5E2 Zr-95 2.2E-1 7.0E-2 4.7E-2 0 0 0 2.2E2 Ho-99 0 1.0E2 2.0E1 0 0 0 2.4E2 Ag-110m 7.7E-1 7.1E-1 4.2E-1 0 0 0 2.9E2 I-131 1.5E2 2.1E2 1.2E2 7.0E4 0 0 5.6El I-133 5.1El 8.9El 2.7El 1.3E4 0 0 8.0El' Cs-134 3.0E5 7.1E5 5.8E5 0 0 7.6E4 1.2E4 Cs-137 3.8E5 5.2E5 3.4E5 0 0 5.9E4 1.0E4 Ba-140. 1.9E2 2.4E1 1.3E1 0- 0 1.4E-1 4.0E2 '
~
Ce-141- 2.3E-2 1.5E-2 0 0 0 0 5.8E1 Ce-144 1.2E0 4.9E-1 6.3E-2 0 0 0 4.0E2 ATTACHMENT 1 o l PAGE 9 0F 70
],
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310-REVISION: ~4 0FFSITE-DOSE CALCULATION MANUAL PAGE 45 0F 105 TABLE A-8 METEOROLOGICAL CONSTANTS HIND SPEED INTERVALS'(mph) Interval Mean Value (MPH) (MPH)
<1 0.5 j 1 1 2.5 0.75 '4
> 2.5 1 4 3.25 i
> 4 1 5.5 4.75
> 5.5 1 7 6.25
>718 7.5
>819 8.5
> 9 1 10 9.5
> 10 1 11 10.5
> 11 1 12.5 11.75
> 12.5 1 14 13.25
> 141 18 16 :
> 18 1 24 21
> 24 ,
27 RADIAL SECTOR BOUNDARIES Sector Deareas Centerline . N 348.75-11.25' 0 .j NNH 326.25 - 348.75 337.5 ; NH 303.75 - 326.25 .315.0 l HNH 281.25 - 303.75 292.5 I H 258.75 - 281.25 270.0 i HSH 236.25 - 258.75 247.5 SH 213.75 - 236.25 225.0 SSH 191.25 - 213.75 202.5 S 168.75 --191.25 180.0 SSE 146.25 - 168.75 157.5 SE 123.75 - 146.25 135.0 ESE 101.25 - 123.75 112.5 E 78.75 - 101.25 90.0
~ENE 56.25 - 78.75 67.5.
NE ' 33.75 - 56 25 45.0 NME 11.25 - 33.75 P2.5 ATMOSPHERIC STABILITY - Stability Pasquill A*C A*F Classification Categories 100 meters- 50 meters -(degress). Extremely Unstable A <-1.9 <-1.71 . >22.5 Moderately U. stable -1.9 to -1.7 -1.71 to.-l.53 :17.5:- 22.5
-8 Slightly Unstable- .C -1.7 to'-1.5 -1.53.to -1.35 12.5 -'17.5-Neutral D -1.5 to -0.5- -1.35 to:-0.45, .7.5 -'12.5 Slightly Stable E -0.5 to 1.5 -0.45 to 1'.35' 3.75~- 7.5 Moderately Stable F 1.5 to 4.0 1.35 to 3.60. 2.05 - 3;75-Extremely Stable G >4.0 >3.60- <2.05
-ATTACHMENT'l
SMUD-NUCLEAR ORGANIZATION NUMBER: AP 310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 46 0F 105 l TABLEA-9 1986 ANNUAL AVERAGE X/Q AND D/Q SITE BOUNDARY (TECHNICAL SPECIFICATIONS 5.1) X/Q (seconds / meter 3) Iodine-131 6 and (1/mhter2) Tritium Noble Gases Particulate Ground Deposition no 2.26 Day 8.0 Day Decay Decay Decay no no Depletion Depletion Depleted Exclusion 1.658E-05 1.654E-05 1.534E-05 7.061E-08: Area e Boundary (640 meters)
- s i
i ATTACHMENT 1 PAGE 11 0F 70
i
.l SMUD-NUCLEAR ORGANIZATION- NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 47 0F 105 TABLE A-10 1986 ANNUAL AVERAGE X/Q AND D/Q SPECIAL LOCATIONS X/Q (SECONDS / METER3 ) 6;(r,0)
LOCATION DISTANCE NO 2.26 DAY 8.00 DAY (1/ i (METERS) DECAY DECAY .. DECAY METER2 ) UNDEPLETED UNDEPLETED DEPLETED TRITIUM NOBLE IODI'NE & GAS PARTICULATE NEAREST HOUSE NE 1432.00 '4.157E-06 4.144E-06~ 3.663E-06 2.348E-08 NEAREST HOUSE ENE 1128.00 9.092E-06 9.071E-06 8.127E-06 6.559E-08 , NEAREST HOUSE SE 2560.00 9.085E-07 9.032E-07. 7.665E-07 3.868E-09 1 NEAREST HOUSE SSE 7803.00 8.593E-08 8.424E-08 6.397E-08 1.786E-10 1 NEAREST HOUSE S 6492.00 1.580E-07 1.553E-07 1.206E-07 ~ 2.245E-10 l NEAREST HOUSE SSH 3718.00 5.269E-07 5.213E-06 4.290E-07 7.598E-10 l NEAREST HOUSE SH 1219.00 7.613E-06' 7.587E-06 6.774E-06 .1.477E-08 i NEAREST HOUSE HSH 2103.00 1:455E-06 1.447E-06 1.248E-06 2.905E-09 NEAREST HOUSE H 3414.00 5.814E-07 5.763E-07 4.775E-07' 1.060E-09 NEAREST HOUSE HNH 4389.00 3.737E-07 3.702E-07 2.991E 8.669E-10 NEAREST HOUSE NH 5334.00 3.250E-07 3.215E-07 12.545E-07 8.826E-10' NEAREST HOUSE NNH 7254.00 1.852E-07 1.822E-07 1.394E-07 5.441E-10 SITE BOUNDARY N 658.00 1.607E-05 1.604E-05 1.484E-05 7.225E-08 SITE BOUNDARY NNE 670.00- 1.125E-05' 1.124E ~1.038E-05 5.795E-08' SITE BOUNDARY NE 792.00 1.191E-05 1.189E-05 1.088E-05: 7.292E-08 SITE BOUNDARY ENE 1185.00 8.428E-06 8.408E-06 7.513E-06 6.036E-08 SITE BOUNDARY E 3605.00 4.555E-07 4.513E-07 3.721E-07. 1.938E-09 SITE BOUNDARY ESE 1697.00 1.981E 1.973E-06 1.726E-06 8.876E-09 SITE BOUNDARY SE 1152.00 5.465E-06 5.451E 4.880E-06 2.832E-08 SITE BOUNDARY SSE 1170.00 4.344E-06 '4.321E-06 3.865E-06 1.689E-08 SITE BOUNDARY S 1759.00 2.106E-06 2.096E-06 -1.830E-06 5.084E-09 SITE BOUNDARY SSN 1103.00 6.921E-06 6.899E-06 6.193E-06' 1.472E-08 SITE SOUNDARY SH 1146.00 8.408E-06 8.381E-06 7.508E-06 1.642E-08 SITE SERNIDARY HSH 987.00 7.461E-06 7.441E-06' 6.720E-06 1.683E-08' SITE B0UNDARY H 969.00 8.059E-06 8.039E-06 7.268E-06 2.072E-08 SITE 8(MIDARY HNN' 987.00 8.072E-06 8.055E-06 7.271E-06 2.970E-08 SITE BOUNDARY NH 795.00 1.474E-05' 1.472E-05 1.346E-05 6.743E-08 SITE BOUNDARY NNH 670.00 1.986E 1.983E-05 1.833E-05 l'087E-07 MILK CON- ENE 1128.00 9.092E-06 9.071E-06 8.127E-06 6.559E-08 MILK C0H SH 3187.00 9.254E-07 9.170E-07 7.651E-07 :1.305E-09 MILK C0H HSH 3621.00 4.936E-07 4.889E-07 4.030E 7.714E-10 - MILK C0H H 7741.00 1.3 9E-07 1.303E-07 9.903E-08 1.634E-10 -l MEAT ANIMAL N 433.00 3.132E-05 3.129E-05 : 2.954E-05 .1.384E-07 l MEAT ANIMAL NNE 430.00 2.283E 2.281E-05 -2.154E-05~ 1.155E-07. HEAT ANIMAL NE 430.00 3.124E-05 3.121E-05. 2.947E-05' l'.900E-07 HEAT ANIMAL ENE 448.00- 4.033E-05 4.030E-05 '3.798E-05 2.863E-07' MEAT ANIMAL E 472.00 2.480E-05 2.477E-05 2.330E 1.355E-07. ATTACHMENT 1-
.PAGE 12 CF~70'
SMUO-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 48 0F 105 TABLE A-10 (Continued) 1986 ANNUAL AVERAGE X/Q AND D/Q SPECIAL LOCATIONS X/Q (SECONDS / METER3 ) 6;(r,0) LOCATION DISTANCE NO 2.26 DAY 8.00 DAY (1/ (METERS) DECAY DECAY DECAY METER2 ) UNDEPLETED 'UNDEPLETED DEPLETED TRITIUM NOBLE IODINE & GAS PARTICULATE HEAT ANIMAL ESE 667.00 1.129E-05 1.127E-05 1.041E-05 5.631E-08 MEAT ANIMAL SE 235.00 7.680E-05 7.676E-05 7.407E-05 3.319E-07 MEAT ANIMAL SSE 198.00 8.515E-05 8.511E-05 8.251E-05 2.587E-07 MEAT ANIMAL S 195.00 1.170E-04 1.169E-04 1.134E-04' 2.2.15E-07 MEAT ANIMAL SSH 198.00 1.379E-04 1,379E-04 1.337E-04 2.043E-07 MEAT ANIMAL SH 286.00 9.569E-05 9.561E-05 9.172E-O'i 1.437E-07 . HEAT ANIMAL HSH 405.00 3.469E-05 3.465E-05 3.281E-05 6.880E-08 l MEAT ANIMAL H 509.00 2.410E-05 2.407E-05 2.256E-05 5.794E-08 I MEAT ANIMAL HNH 442.00 3,096E-05 '3.094E-05 2.918E-05 1.064E-07 ] MEAT ANIMAL NH 500.00 3.092E-05 3.089E-05 2.897E-05 .1.403E-07 I MEAT ANIMAL NNH 448.00 3.750E-05 3.747E-05 3.532E-05 .2.036E-07 .i MILK GOAT SH 5633.00 3.247E-07 3.196E-07 2.522E-07. 3.456E-10 NEAREST GARDEN ENE 1128.00 9.092E-06 9.071E-06 8.127E-06 . 6. 559E -08 1 NEAREST GARDEN SE 6550.00 1.405E-07 1.384E-07 1.072E-07 4.289E-10 NEAREST GARDEN SSH 5327.00 2.705E-07 2.664E-07~ 2.115E-07 3.299E-10 ; NEAREST GARDEN SH 5633.00 3.247E-07 3.196E-07 2.522E-07 3.456E-10 .' NEAREST GARDEN HSH 2816.00 8.046E-07 7.986E-07 6.730E-07 1.412E-09 NEAREST GARDEN H 7714.00 1.337E-07 1.311E-07 9.965E-08 1.647E-10 i NEAREST GARDEN NH 7242.00 1.866E-07 1.838E-07 1.405E-07 4.455E-10 , VISITOR CENTER E 225.00 9.004E 8.999E-05 8.695E-05 '4.045E-07 ! PARK KIOSK E 525.00 2.076E-05 2.073E-05 1.940E-05 1.150E-07 HAREHOUSE ENE 225.00 1.350E-05 1.349E-05 .1.304E-05 7.892E-07 DESIGN CITY ENE 250.00 1.118E-05 1.117E 1.076E-05 6.791E-07 EXCLUSION AREA N 640.00 1.676E-04 1.673E-04 1.550E-04 7.549E-07 EXCLUSION AREA NNE 640.00 1.206E-04 1.204E-04 1.115E-04 6.232E-07 EXCLUSION' AREA NE 640.00 1.648E-05 1.646E-05 1.525E-05 1.025E-08 EXCLUSION' AREA ENE 640.00 2.246E-05 2.243E-05 2.078E-05 1.644E-08 EXCLUSION AREA E 640.00 1.508E-05 1.505E-05 1.395E-05' 8.428E-07 EXCLUSION AREA ESE 640.00 1.204E-05 1.202E-05 1.114E-05 6.012E-07 EXCLUSION AREA SE 640.00 1.384E-05 '1.382E-05 1.280E-05 7.357E EXCLUSION AREA SSE 640.00 1.125E-05 1.123E-05 1.040E-05 4.502E-08 EXCLUSION AREA S 640.00 1.460E-05 1.457E 1.350E-05. 3.775E-08 EXCLUSION AREA SSH 640.00 1.741E-05 1.738E-05 1.610E-05. .3.555E-08 EXCLUSION AREA SH 640.00- 2.298E-05 2.294E-05 2.126E-05 4.228E-08 EXCLUSION AREA HSH 640.00' 1.558E-05 1.556E-05 <1.441E 3.390E-08 EXCLUSION AREA H 640.00 1.629E-05 1.626E-05 1.506E-05 4.049E-08 EXCLUSION AREA HNH 640.00 1.652E-05 1.649E-05 1.528E-05 5.985E-08' EXCLUSION AREA- NH 640.00 2.074E-05: 2.072E-05 1.919E-05 9.540E-08 EXCLUSION AREA NNH 640.00 2.127E-05' 2.124E-05 1.967E-05~ 1.169E-07. i ATTACHMENT 1 PAGE 13 0F 70. , . ! 1 _______-_______U
l SMUD-NUCLEAR ORGANIZATION NUMBER: AP 310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 49 0F 105 TABLE A-ll 1986 BATCH X/Q AND D/Q-(2552 HOURS) SITE BOUNDARY (TECHNICAL SPECIFICATIONS 5.1)' X/0 (seconds /ineter3)- Iodine-131 6 and (1/mhter2)- j Tritium Noble Gases Particulate Ground Deposition j no 2.26 Day 8.0 Day Decay Decay Decay no no Depletion Depletion Depleted Exclusion 1.307E-05 8.509E-06 7.761E-06 3.794E-08 i Area Boundary (640 meters) - ATTACHMENT 1. PAGE 14 0F 70 tl
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION:- 4 0FFSITE DOSE CALCULATION MANUAL PAGE 50 0F 105 TABLE A 1986 ANNUAL AVERAGE X/Q (BATCH) i X/Q .(SECONDS / METER 3) 6 y LOCATION DISTANCE NO 2.26 DAY 8.00 DAY ;(r,0) (1/ (METERS) DECAY DECAY DECAY METER2 ) 1 UNDEPLETED UNDEPLETED DEPLETED l TRITIUM N08LE IODINE & GAS PARTICULATE NEAREST HOUSE NE 1432.00 4.073E-06 4.060E-06 3.589E-06 '2.277E-08 NEAREST HOUSE ENE 1128.00 8.668E-06. 8.648E-06 7.749E-06 6.259E-08 i NEAREST HOUSE SE 2560.00 9.349E-07 9.293E-07 7.887E-07 '3.849E-09 . NEAREST HOUSE SSE 7803.00 8.498E-08 8.328E-08 6.325E-08, 1.759E-10' NEAREST HOUSE S 6492.00 1.490E-07 1.464E-07 1.137E-07' 2.185E-10 NEAREST HOUSE SSH 3718.00 5.369E-07 5.311E-07 4.371E-07 7.676E-10 NEAREST HOUSE SH 1219.00 7.767E-06 7.740E-06 6.911E-06 1.492E NEAREST HOUSE HSH 2103.00 1.471E-06 1.463E-06 1.261E-06 -2.948E-09 . NEAREST HOUSE H 3414.00 5.002E-07 5.949E-07 4.930E-07 1.096E-09. I NEAREST HOUSE HNH 4389.00 3.781E-07 3.746E-07 -3.027E-07. 8.724E-10 i NEAREST HOUSE NH 5334.00 3.206E-07 3.171E-07^ 2.510E-07 8.652E-10 1 NEAREST HOUSE NNH 7254.00 2.054E-07 2.020E-07 1.545E-07 6.112E-10 I SITE BOUNDARY N 658.00 1.605E-05 1.603E-05 1.482E-05 7.508E j SITE BOUNDARY NNE 670.00 1.059E-05 1.057E-05 9.770E-06 '5.523E-08 i SITE BOUNDARY' NE' 792.00 l'.165E-05 1.162E-05 1.064E-05 7.073E-08 j SITE BOUNDARY ENE 1185.00 8.031E-06 8.012E-06 7.160E-06 5.760E-08 J SITE BOUNDARY E 3605.00 4.357E-07 4.317E-07 .3.560E-07; 1.903E-09 1 SITE B0UNDARY ESE 1697.00 1.896E-06 ~1.889E-06' '1.652E-06 8.667E-09 3 SITE BOUNDARY SE 1152.00 5.612E-06 5.597E-06 5.011E-06 2.818E-08 i SITE BOUNDARY SSE- 1170.00 4.272E-06 4.259E-06 3.810E-06 1.663E-08 j SITE BOUNDARY S 1759.00 1.991E-06 1.982E-06 1.730E 4.949E-09 l SITE BOUNDARY SSN 1103.00 7.076E-06 7.054E-06 6.332E-06 1.488E-08 SITE BOUNDARY SH 1146.00 8.582E-06 8.554E-06 7.663E-06' 1.658E-08 SITE BOUNDARY HSH 987.00 7.543E-06 7.523E-06 6.793E-06 1.707E-08 ) SITE BOUNDARY H 969.00 8.315E-06 8.294E-06 7.498E-06 2.142E-08 l SITE BOUNDARY HNH 987.00 8.210E-06 8.193E-06 7.395E-05 '2.989E-08 i SITE BOUNDARY NH 795.00 1.455E-05 '1.452E-06 1.320E-05 6.610E-08' SITE BOUNDARY NNH 670.00 2.196E-05 2.193E-05 2.02bE-05 1.222E-07 MILK CON ENE 1128.00 8.668E-06 8.648E-06 7.749E-06: 6.259E-08 I MILK C0H SH' 3187.00 9.449E-07 9.363E-07 7.811E-07 1.317E-09 l MILK C0H HSH 3621.00' 4.993E-07 4.946E-07 4.077E-07 7.826E-10 MILK C0H H 7741.00 1.372E 1.345E-07 l'.022E-07 1.689E-10 i HEAT ANIMAL N 433.00- 3.122E-05 3.119E-05 2.945E-05 '1.439E-07 i MEAT ANIMAL NNE 430.00 2.143E-05 2.141E-05 2.022E-05: 1.101E-07. MEAT ANIMAL NE '430.00 3.063E-05 3.033E 2.864E-05 1.843E-07 MEAT ANIMAL ENE 448.00- 3.859E-05 3.856E-05 3.634E 2.732E-07 ) 1 MEAT ANIMAL E '472.00 2.381E-05 2.378E-05 2.237E-05 1.330E-07: ATTACHMENT'1 PAGE 15 0F 70 5 I
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 51 0F 105 TABLE A-12 (Continued)- 1986 8ATCH X/Q AND D/0 (2552 HOURS) SPECIAL LOCATIONS X/Q (SECONDS / METER3 ) xt(r,0) ' LOCATION DISTANCE- NO 2.26 DAY 8.00 DAT (1/ (METERS) DECAY DECAY DECAY METER2 ) UNDEPLETED UNDEPLETED CEPLETED i HEAT ANIMAL ESE 667.00 1.077E-05 1.076E-05 .1.537E-05 5.498E-08 MEAT ANIMAL SE 235.00 7.954E-05 7.949E-05 1.158E-04 3.303E-07 d HEAT ANIMAL SSE 198.00 8.427E-05 8.422E 2.197E-04 2.548E-07 MEAT ANIMAL - S 195.00 1.102E-04 '1.102E-04 1.717E-04 2.157E-07' MEAT ANIMAL SSN 198.00 1.410E l'.409E-04 1.423E-04 2.063E-07 MEAT ANIMAL SH 286.00 9.822E-05 9.814E-05 9.887E-05. 1.451E-07 MEAT ANIMAL HSH 405.00 3.514E-05 3.510E-05 -7.056E-05 6.980E-08 NEAT ANIMAL H 509.00 2.490E-05 2.486E-05 2.866E-05 5.989E-08 4 i MEAT ANIMAL HNH 442.00 3.129E-05 3.126E-05 5.141E-05 1.070E-07 MEAT ANIMAL NH 500.00 3.054E-05 3.051E-05 4.936E-05 '1.376E HEAT ANIMAL NNH 448.00 4.135E-05 2.486E-05 5.874E-05 2.287E-07 MILK GOAT SH 5633.00 3.324E-07. 3.271E-07 3.376E-07 3.490E-10 - NEAREST GARDEN ENE 1128.00 8.668E-06' 8.648E-06 .7.251 E 6.259E-08 NEAREST GARDEN SE 6550.00 1.457E-07 1.434E-07 1.775E 4.268E 1 NEAREST GARDEN SSN 5327.00 .2.757E-07 2.715E-07 2.717E-07 3.333E-10 , NEAREST GARDEN SH 5633.00 3.324E-07 3.271E-07 3.376E-07 3.490E-10 l NEAREST GARDEN HSH 2816.00 8.136E-07 '8.076E-07' '1.601E-06' 1.432E-09 ! NEAREST GARDEN H 7714.00 1.380E 1.353E-07 1.881E-07 1.702E-10 i NEAREST GARDEN NH 7242.00 1.841E-07 1.814E-07 '2.892E-07. 4.367E-10 .i VISITOR CENTER E 225.00 8.622E-05 8.617E-05 2.268E-05 3.971E-07 a PARK KIOSK- E 525.00 1.994E-05 1.992E-05 1.213E-05 1.129E-07 NAREHOUSE ENE 225.00 1.292E-05 1.291E-05 1.304E-05 7.531E-07 DESIGN CITY ENE 250.00- 1.070E-04. 1.069E-05 1.076E-05 6.480E-07 EXCLUSION AREA N 640.00 1.674E-05 1.671E-04 1.550E-04' .7.846E-08 EXCLUSION AREA NME 640.00 1.134E-05 1.133E-04' 1.115E-04 5.940E-08 EXCLUSION AREA NE 640.00 1.607E 1.605E-05 1.525E-05 9.946E-08 EXCLUSION AREA' ENE 640.00 2.149E-05 2.146E-05 2.078E-05 1.569E-07 EXCLUSION AREA E 640.00 1.449E-05 1.447E-05 1.395E-05 8.274E-08 EXCLUSION AREA ESE. 640.00 1.150E-05 1.148E-05 1.114E-05 5.871E-08 . EXCLUSION AREA SE 640.00 1.427E-05 1.424E-05 1.280E-05 7.321E-08 EXCLUSION AREA SSE 640.00 1.111E-05 1.109E-05 -1.040E-05 4.434E-08 EXCLUSION AREA S 640.00 1.377E-05 1.374E-05 1.350E-05 .3.674E-08 EXCLUSION AREA SSH 640.00 1.780E-05 1.777E-05 1.610E-05 3.591E-08 EXCLUSION AREA SH 640.00 ~2.355E-05: 2.350E-05 2.126E-05 4.268E-08 EXCLUSION AREA HSH 640.00 1.577E-05 1.575E-05 1.441E-05 3.439E EXCLUSION AREA H 640.00 1.682E-05 1.679E-05 1.506E-05 4.185E EXCLUSION AREA HNH 640.00 1.673E-05L 1.671E-05 1.528E-05 6.023E-08 EXCLUSION AREA ' NH 640.00 2.048E-05 2.045E-05 1.919E-05 9.352E-08 EXCLUSION AREA ~ NNH 640.00 2.350E-05 2.346E-05' 1.967E-05 1.314E-07
' ATTACHMENT 1 PAGE 16 0F 70
.___i._______
t I l 3 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 1 REVISION: 4 I 0FFSITE DOSE CALCULATION HANUAL PAGE 52 0F 105' j l TABLE A-13 ,i
,\l GASEOUS SOURCE TERMS l Aux Bldg Percent Reactor Percent Decay Tank Percent j (a,b) Vent of Mix ' Bldg (a) Vent of Mix Release (a) of Mix I Nuclide (At )(Ci/Yr) (A1 )(Ci/Yr) (Aj)(Cl/yr) !
Kr-85m 4.05 0.2% 0.498 0.05% 0.00 0.00% ) Kr-85 0.00 0% 6.43 0.7%- 7.66 7.0%: i Kr-87 5.99 0.3% 0.165 0.02% 0.00 0.00% I Kr-88 1.58 0.07% 0.492 0.05% 0.00 - 0.00% j Xe-131m 0.26 0.011 0.759 0.081- 2.33 2.0% l Xe-133m 1.73 0.08% 8.637 0.9% 0.00 0.00% j Xe-133 1867.40 92% 913.81 96% 100.08 91.0% l Xe-135 140.30 22.06 1.25
~71 2.0% 1.0%
Xe-135m 1.38 0.07% 0.008 0.008% 0.00. . Xe-138 .82 0.04% { Ar-41 E 0.04% 0.282 0.37. 0.00 i 1 Total 2024.33 953.14 111.32 Notes ! i (a) Based on operational hi_ story of Rancho Seco. l
.\
(b) This source term is also applicable for the Auxiliary Bldg. Grade Level Vent
; )
l .l I f1 l ATTACHMENT 1 PAGE 17 0F 70 l
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 q REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 53 0F 105 TABLE A-14 Distances for Gaseous Effluent Pathway Evaluation (Meters) i Receptor Site Nearest Nearest Nearest Nearest Nearest Direction Boundary Reijfaara Garden Heat Animal Milk Cow Milk Goat 3 J N 658 (1) - 440 - - i NNE 670 - - 430 - - NE 792 1430 4830 430 - - I
'1140 ENE 1185 1140 1140 450 -
)
E 3605 - - 470 - - ESE 1697 - - 670 - - SE 1152 2560 2560 240 - - SSE 1170 7800 - 200 - - S 1759 6490 . - 200 - - j SSH 1103 2900 5330 200 - - SH 1146 1220 3190 290 3190 5630 HSH 987 1830 2380 400 3620 - H 969 3230 3230 510 7740 3230 HNH 987 4390 .4390 440 - - l NH 795 5330 6750 500 - - NNH 670 7250 - 440 - - (1) Locations, if they exist, are greater than 8,047 meters (5 miles) from ; the Rancho Seco site. ! Additional Locations: Visitor Center E 225 meters 17.9% occupancy factor Park Kiosk E 525 meters 41.7% occupancy factor Harehouse ENE 225 meters 23.8% occupancy factor Design City ENE 250 meters 23.8% occupancy factor ; (2) Exclusion Area Boundary - 640 meters (2100 feet) (3) Gaseous Effluent Boundary - 762 meters (2500 feet) ATTACHMENT 1 PAGE'18 0F 70 _.__-.--__-.-_a- -.-_-_--__.__-__A
j i SMJ0-NUCLEAR ORC s.!?>h - NUMBER: AP.310 d REVISION: 4 0FFSITE DOSE CALCULA, % MANUAL PAGE 54 0F 105 ) i TABLE A-15 .
]
i R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION j l PATWAY = GROUND j AGE GROUP = ALL l 1 NUCLIDE T.800Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN I i PN 54 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.57E 09 I FE 59 2.75E G8 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 3.23E 08 ] l CO 58 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 4.44E 08 # l CO 60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.52E 10
)
ZN 65 7.49E OS 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 8.61E 08 l R8 86 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 1.03E 07 l l 1 SR 89 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.58E 04 Y 91 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.22E 06 j 1 l ZR 95 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.89E 08 l l N8 95 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.60E 08 j l RU103 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 .1.09E 08 1.09E 08 1.27E 08 RU106 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 5.03E 08 1 AG110M 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.06E 09 ATTACHMENT 1 PAGE 19 0F 70
1
]
NUMBER: AP.310 I SMJD-NUCLEAR ORGANIZATION REVISION: 4 QfFSITE DOSE CALCULATION MANUAL PAGE 55 0F 105 TABLE A-15 (Cont.) ; R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION j l PATHWAY = GROUND AGE GROUP - ALL I NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY- THYROID LUNG SKIN. i TE127M 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 1.08E 05 i l TE129H 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.34E 07 I I 131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 ,
)
i I 133 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.47E 06 3.00E 06 l CS134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.96E 09 CS136 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 06 1.49E 08 1.49E 08 1.69E 08 ; I CS137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 BA140 2.')SE 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.34E 07 i CE141 1.345 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.36E 07 1.53E 07 CE144 6.95f 37 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 8.03E 07 UNITS OF R VALUIS: HREM/YR PER MICR0 CURIE /CU METER FOR ALL NUCLIDES IN INHALATION PATHWAY AND FOR H-3 IN r.LL PATHWAYS, MREM /YR PER MICR0 CURIE /SEC FOR THE REMAINING NUCLIDES AND PATHWAYS ATTACHMENT 1 PAGE 20 0F 70
SNUD-NUCLEAR ORGANIZATION. NUMBER: A9.310 REVISION: '4 0FFS11E DOM CALCULATION NAM]AL PAGE 55 0F.)05.' [
]
TABLE A-16 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STAY 10N I) PATHWAY = VEGETABLES ,] AGE GROUP = ADULT ] NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
)
q H 3 2.28E 03 2.28E 03 Data Not 2.28E 03 2.28E 03 2.28E 03 2.28E 03,.2.28E 03 f Available
.I P 32 5.91E 07' 1.72E 08 1.53E 09 9.51E 07. Data Not Data Not Data Not Data Not {
Available Availdle Available Available j I PW 54 5.83E 07 9.36E 08 Data Not 3.05E 08 9.09E 07 Data Not Data Not Data Not i Available Available Available Available . FE 59 1.12E 08 9.75E 08 1.24E 08. 2.93E 08 Data Not Data Not 8.17E 07 Data Not Available Available Available CO 58 6.71E 07 6.07E 08 Data Not 2.99E 07 Data Not Data Not Data Not Data Not Ava11g>1e Available Availdle Available Available C0 60 3.67E 08 3.12E 09 Data Not 1.66E 08 Data Not Data 30t Data Not Data Not Available Available Available Available Available ( l ZN 65 5.77E 08 8.04E 08 4.01E 08 1.28E 09 -8.54E 08 Data Not Data Not Data Not Available 'Available Available RB 86 1.03E 08 4.36E 07 Data Not 2.21E 08 Data Not Data Not Data Not. Data Not Available Available Available Available Available SR 89 2.87E 08 1.60E 09 1.00E 10 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available SR 90 1.64E 11 1.93E 10 6.70E 11 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available Y 91 1.34E 05 2.76E 09 5.01E 06 Data Not Data Not Da'ta Net Data Not Data Not' f Available Available Available Available Available ZR 95 2.51E 05 .1.17E 09 1.16E 06 3.71E 05; 5.82E 05 Data Not Data Not Data Not j Available Available Available i NB 95 4.19E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 Data Not Data Not Data Not Available Available Available j I ATTACHMENT 1 PAGE 21 OF 70 q a I _ _____1___-e.
I I l l l SMJD-NUCLEAR ORGANIZATION NUMBER: AP.310 j REVISION: 4
. M Ug_q0 H CAltutATION MANUAL PAGE 57 0F 105 TABLE A-16 (Cont.)
R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION i l PATHWAY = VEGETABLE AGE GROUP = ADULT NUCLIDE T.80DY GI-TRACT 00NE LIVER KIDNEY THYROID. LUNG SKIN RU103 2.04E 06 5.53E 08 4.74E 06 Data Not 1.31E 07 Data Not Data Not Data Not , i Avail abl e Available Ava(M1AAva41able j l RU106 2.46E 07 1.26E 10 1.94E 08 Data Not 3.75E 08 Data Not Data Not Data Not^ j Avail able Available Available Aval_lable j i' AG110H 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.06E 07 Data Not Data Not Data Mot Aval_lable Availab*ie AvaQ3hlt [ TE127M 6.12E C7 1.68E 09 5.02E 08 1.80E 08 2.04E 09 1.28E 08 Data Not Data Not Available Available TE129M 4.71E 07 1.50E 09 2.98E 08 1.11E 08 1.24E 09 1.02E 08 Data Not Data Not ] Availatle Available j I 131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 Data Not Data Not Available Available l I 133 1.12E 06 3.30E 06 2.11E 06 3.67E 06 6.40E 06 5.39E 08 Data Not Data Not Available Available J f CS134 8.83E 09 1.89E 08 4.54E 09 1.08E 10 3.49E 09 Data Not 1.16E 09. Data Not j Available Avail able l i CS136 1.19E 08 1.88E 07 4.19E 07 1.66E 08 9.21E 07 Data Not 1.26E 07 Data Not i Ava(1able Available -l 1 CS137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 Data Not 1.02E 09 Data Not Avail able Available a
... 1 BA140 8.40E 06 '2.64E 08 1.28E 08 1.61E 05 5.47E 04 Data Not 9.22E 04 Data Not Available Available CE141 1.48E 04 4.99E 08 1.93E 05 1.31E 05 6.07E 05 Datt. Not Data Not Data Not j Available Available Available CE144 1.69E 06 1.06E 10 3.15E 07 1.32E 07 ~ 7.80E 06 Data Not Data Not ' Data Not Available Available Available i
ATTACHMENT 1 PAGE 22 0F 70
)
SMJD-NUCLEAR ORGANIZATION NllMBER: AP.310 REVISION: 4-0FFSITE D01E CALCULATION MANUAL PAGE 58 0F 105 TABLE A-17 R VALUIS FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = VEGETABLES AGE GROUP = TEEN NUCLIDE T.80DY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.61E 03 2.61E 03 Data Not 2.61E 03 2.61E 03 2.61E 03 2.61E 03 2.61E 03 ' Avail able P 32 6.80E 07 1.47E 08 '1.75E 09 1.09E 08 Data Not Data Not Date Not Data Not Available Available Available Available MN 54 8.79E 07 9.09E 08 Data Not 4.43E 08 1.32E 08 Data Not- Data Not Data Not Available Available Available Ava113hlg <
- i FE 59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 Data hot Data Not 1.30E 08 bata Not t j Available Available Available .
j CO 58 9.79E 07 5.85E 08 Data Not 4.25E 07 Data Not Data Not Data Not Data Not' Available Available Available Available Available
~
CO 60 5.57E 08 3.22E 09 Osta Not 2.47E 08 Data Not Data Not Data Not Data Not ! Avail able Available Available Available Available l i ZN 65 8.68E OS 7.88E 08 5.36E 08 1.86E 09 1.19E 09 Data Not Data Not_' Data Not l Available Available Available RB 86 1.30E 08 4.09E 07 Data Not 2.76E 08 Data Not Data Not Data Not Data Not Available Available Available Available Available SR 89 4.36E 08 1.81E 09 1.52E 10 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available 4 SR 90 2.06E 11 2.33E 10 8.32E 11 Data Not ' Data Not -Data Not Data Not Data Not Available Available Available Availghla 1.vailable Y 91 2.06E 06 3.15E 09 7.68E 06 DataNot.DataNot[DataNot Data Not Data Not Available Available Available Available Available ZR 95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 05 Data Not Data Not Data Not
. Available Available Available NB 95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 1.02E 05 Data Not' Data'Not Data Not Avail'able Available Available ATTACHMENT 1 PAGE 23 0F 70
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 59 0F 105 l TABLE A-17 (Cont.) I R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION i PATHWAY = VEGETABLE ] AGE GROUP = TEEN 'l NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN' 1 RU103 2.90E 06 5.66E 08 6.78E 06 Data Hot 2.39E 07 Data Not Data Not Data Not Available Available Available Available j RU106 3.93E 07 1.50E 10 3.12E 08 Data Not 6.02E 08 Data Not Data Not - Data Not Available Available Available Available , 1 AG110H 9.39E 06 4.34E 09 1.63E 07 1.54E 07 2.95E 07 Data Not Data Not' Data Not Available Available Available - l l TE127N 9.44E 07 1.90E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 Data Not Data Not Available Available TE129H 6.79E 07 1.61E 09 4.29E 08 1.59E 08 1.79E 09 1.38E 08 Data Not Data Not
.. ' Av_ailable Availab'le j I 131 5.77E 07 2.13E 07 7.68E 07 1.07E 08 1.85E 08 3.14E 10. Data Not'Deta Not' Available Availabio ,
I 133 1.01E 06 2.51E 06 1.%E 06 3.32E 06 5.83E 06 4.64E 08 Data Not Data Not Available Available CS134 7.54E 09 2.02E 08 6.90E 09 1.62E 10 5.16E 09 Data Not 1.97E 09 Data Not Available Available CS136 1.13E 08 1.35E 07 4.28E 07 1.68E 08 9.16E 07 Data Not 1.44E 07 Data Not Available Available CS137 4.90E 09 2.00E 08 1.06E 10 1.41E 10 4.78E 09 Data Not 1.88E 09 Data Not Available Available BA140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 Data Not 1.14E 05 Data Not Avail able Available CE141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 Data Not Data Not Data Not Available Available Available CE144 2.71E 06 1.27E 10 5.04E 07 2.09E 07 1'.25E 07 Data Not Data Not Data Not Available Available Available ATTACHMENT 1 PAGE 24 0F 70
i SMUD-HUCLEAR ORGANIZATION NUMBER: AP.310 ! REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 60 0F 105 TABLE A-18 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION 1 l PATHWAY = VEGETABLES AGE GROUP = CHILD ) NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 4.04E 03 4.04E 03 Data Not 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 Available j P 32 1.42E 08 1.01E 08 3.67E 09 1.72E 08 Data Not Data Not Data Not Data Not j Available Available Available Available j MN 54 1.73E 08 5.44E 08 Data Not 6.49E 08 1.82E 08 Data Not Lata Not Gata h t Avail able Available Available Available l FE 59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 Data Not Data Not 1.84E 08 Data Not . . l Available Available Available i CO 58 1.92E'08 3.66E 08 Data Not 6.27E 07 Data Not Data Not Data Not Data Not- l Avail able Available Available Available Ava11abia . 4 CO 60 1.11E 09 2.08E 09 Data Not 3.76E 08 Data Not Data Not Data Not Data Not Avail able Available Available Available Available - , ZN 65 1.70E 09 4.81E 08 1.03E 09 2.74E 09 1.73E 09 Data Not Data Not Data Not I Available Available Available RB 86 2.81E 08 2.94E 07 Data Not 4.56E 08 Data Not Data Not Data Not Data Not Available Available Available Available Available SR 89 1.03E 09 1.40E 09 3.62E 10 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Availablg SR 90 3.49E.11 1.86E 10 1.38E 12 Data Not Data Not Data Not Data Not Data Not Available Available Available Ava11 3 hle Available Y 91 4.89E 05 2.44E 09 1.83E 07 Data Not~ Data Not Data Not Data Not Data Not Available Available Available Available Available ZR 95 7.44E 05 8.71E 08 -3.80E 06 8.35E 05- 1.20E 06 Data Not Data Not Data Not Available Available Available l NB 95 1.12E 05 2.91E 08 4.04E 05 1.57E 05 '1.48E 05. Data Not Data'Not Data Not Available Available Availabit l ATTACHMENT 1 PAGE 25 0F 70 i
l SM)D-NUCLEAR ORGANIZATION NUMBER: AP.310 ] REVISION: 4 ; 0FFSITE DOM CALCULATION MANUAL PAGE 610F 105 I TABLE A-18 (Cont.) R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION 1 l PATHWAY = VEGETABLE AGE GROUP = CHILD NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN I i RU103 5.86E 06 3.94E 08 1.52E 07 Data Not 3.84E 07 Data Not' Data Not Data Not Available Available Available Available I RU106 9.38E 07 1.17E 10 7.52E 08 Data Not 1.02E 09 Data Not Data Not Data Not ) Avail able Available Available Available l AG110M 1.87E 07 2.78E 09 3.46E 07 2.34E 07 4.35E 07 Data Not Data Not Data Not Available Available Available ! TE127H 2.26C 08 1.54E 09 1.90E 09 5.12E 08 5.42E 09 4.55E 08 Data Not Data Not Available Available , TE129M 1.55E 08 1.22E 09 9.98E 08 2.791 08 2.93E 09 3.22E 08 Data Not Data Not I Available Available I 131 8.16E 07 1.28E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 Data Not Data Not Available Available I 133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.36E 06 8.21E 08 Data Not Data Not Available Available ' CS134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 Data Not 2.84E 09 Data Not 1 Available Available j CS136 1.43E 08 7.77E 06 8.04E 07 2.21E 08 1.18E 08 Data Not 1.76E 07 Data Not Available Available CS137 3.52E 09 1.50E 08 2.49E 10 2.39E 10 7.78E 09 Data Not 2.80E 09 Data Not j Available Available BA140 1.61E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 Data Not 1.44E 05 Data Not Available Available CE141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05 Data Not Data Not Data Not Available Available Available CE144 6.49E 06 9.94E 09 1.22E 08 3.81E 07 2.11E 07 Data Not Data Not' Data Not Available Available Available ATTACHMENT I PAGE 26 0F 70
a l X l SPtJD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 I 0FFSITE DOSE PAlfilLATION MANUAL PAGE 62 0F 105 l TABLE A-19 ] l R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION 1 PATHWAY = MEAT AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN l l H 3 3.27E 02 3.27E 02 Data Not 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 ) Available ] l P 32 1.76E 08 5.13E 08 4.56E 09 2.83E 08 Data Not Data Not Data Not Data Not Available Available Available Available MN 54 1.39E 06 2.23E 07 Data Not 7.29E 06 2.17E 06 Data Not Data Not Data Not Available Available Available Available FE 59 2.06E 08 1.79E 09 2.28E 08 5.37E 08 Data Not Data Not 1.50E 08 Data'Not Available Available Available CO 58 3.40E 07 3.07E 08 Data Not 1.52E 07 Data Not Data Not Data Not Data Not Avail able Availkble Available Available Available CO 60 1.31E 08 1.12E 09 Data Not 5.95E 07 Data Not Data Not Data Not Data Not Availabl e Available Available Available Available ZN 65 4.60E 08 6.41E 08 3.20E 08 1.02E 09 6.81E 08 Data Not Data Not' Data Not Available Available Available l RB 86 2.11E 08 8.94E 07 Data Not 4.53E 08 Data Not Data Not Data Not Data Hot Avail able Available Available Available Available SR 89 7.45E 06 4.16E 07 2.59E 08 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available SR 90 2.53E 09 2.98E 08 1.03E 10 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available Y 91 2.55E 04 5.25E 08 9.54E 05 Data Not' Data Not Data Not . Data Not Data Not Available Available Available Available Available ZR 95 3.42E 05 1.60E 09 1.57E 06 5.05E 05 7.92E 05 Data Not Data Not Data Not l Available Available Available l NB 95 6.00E 05 6.78E 09 2.01E 06 1.12E 06 1.10E 06 . Data Not Data Not Data Not Available Available Available
-l ATTACHMENT 1 PAGE 27 0F 70 l'
l l I SM)D-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DDSE CALCULATION MANUAL PAGE 63 0F 105 TABLE A-19 (Cont.) l I R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION l PATHWAY = MEAT AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 3.94E 07 1.07E 10 9.15E 07 Data Not 3.49E 08 Data Not Data Not Data Not Availabl e Available Available Availab13 RU106 2.85E 08 1.46E 11 2.25E 09 Data Not 4.35E 09 Data Not Data Not Data Not Available Available Available Available AG110H 3.06E 06 2.10E 09 5.56E 06 5.15E 06 1.01E 07 Data Not Data Not Data Not Available Available Available TE127M 1.33E 08 3.66E 09 1.09E 09 3.90E 08 4.43E 09 2.79E 08 Data Not Data Not Available Available TE129H 1.70E 08 5.42E 09 1.08E 09 4.01E 08 4.49E 09 3.69E 08 Data Not Data Not Available Available l I 131 8.66E 06 3.99E 06 1.06E 07 1.61E 07 2.59E'07 4.95E 09 Data Not Data Not' l Available Available H I 133 2.27E 01 6.68E-01 4.28E-01 7.44E-01 1.30E 00 1.09E 02 Data Not Data Not Available Availablt I i CS134 1.01E 09 2.15E 07 5.17E 08 1.23E 09 3.98E 08 Data Not 1.32E 08 Data Not f Avail able Available l CS136 3.20E 07 5.06E 06 1.13E 07 4.45E 07 2.48E 07 Data Not 3.39E 06 Data Not j Avail able Available CS137 6.30E 08 1.86E 07 7.03E 08 9.61E 08 3.26E 08 Data Not 1.08E 08 Data Not Avail able Available l BA140 1.80E 06 5.65E 07 2.74E 07 3.45E 04 1.17E 04 Data Not 1.97E 04 Data Not' Available Available CE141 9.44E 02 3.18E 07 1.23E 04 8.33E 03 8.87E 03 Data Not Data Not Data Not Available Available Available CE144 6.17E 04 3.89E 08 1.15E 06 4.81E 05 2.85E 05 Data Not Data Not Data Not Available Available Available ATTACHMENT 1 PAGE 28 0F 70 ,
-- --_ -_.----.--____._s_
1 SMD-NUCLEAR ORGANIZATION NUMBER: AP.310 l REVISION: 4 j OFFSITE 001E CALCULATION MANUAL PAGE 64 0F 105 ' TABLE A-20 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATP)G STATION PATHWAY = NEAT AGE GROUP = TEEN NUCLIDE T.80DY GI-TRACT BONE LIVER K10NEY THYROID LUNG SKIN H 3 1.95E 02 1.95E 02 Data Not 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 Available j P 32 1.49E 08 3.24E 08 3.85E 09 2.39E 08 Data Not Data Not' Data Not Data Not Available Available Available Available - MN 54 1.10E 06 1.14E 07 Data Not 5.56E 06 1.66E 06 Data Not Data Not Data Not Available Available Available Available 4 FE 59 1.65E 08 1.01E 09 1.83E 08 4.26E 08 Data Not Data Not 1.34E 08 Data Not
- Available Available Available CO 58 2.69E 07 1.61E 08 Data Not 1.17E 07 Data Not ' Data Not Data Not Data Not Available Available Available Available Available j CO 60 1.04E 08 6.01E 08 Data Not 4.61E 07 Data Not Data Not Data Not Data Not Available Available Available Available Available l ZN 65 3.64E 08 3.31E 08 2.25E 08 7.81E 08 5.00E 08 Data Not' Data Not Data Not i Available Available Available I RB 86 1.78E 08 5.60E 07 Data Not 3.78E 08 Data Not Data Not Data'Not Dat'a Not Avail able Available Available Available Available $R 89 6.27E 06 2.61E 07 2.19E 08 Data Not Data Not Data Not Data Not Data Not Available Available Available' Ava11able Available SR 90 1.46E 09 1.87E 08 6.67E 09 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available Y 91 2.15E 04 3.29E 08 8.04E 05 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available ZR 95 2.73E 05 9.17E 08 1.26E 06 3.98E 05 5.84E 05 Data Not Data Not ' Data Not Available Available Available' NB 95 4.78E 05 3.72E 09 1.57E 06 8.69E 05 8.43E 05 Data Not Data Not Osta Not Available Available' Available RU103 3.19E 07 6.23E 09 .7.45E 07 Data Not 2.63E 08 Data Not_ Data Not Data Not Avail able Available Avaliable Available ATTACHMENT 1 PAGE 29 0F'70
$ MUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 QEESITE DOSE CALCULATION MANUAL PAGE 65 0F 105 ; TABLE A-20 (Cont.) R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = MEAT
-3 AGE GROUP = TEEN
~
NUCLIDE T.80DY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU106 2.39E 08 9.09E 10 1.90E 09 Data Not 3.66E 09 Data Not Data Not Data Not Available Available ' Available Available l AG110M 2.43E 06 1.12E 09 4.21E 06 3.99E 06 7.60E 06 Data Not Data Not Data Not Available Available Available - ] d TE127M 1.09E 08 2.29E 09 9.21E OS 3.27E 08 3.73E 09 2.19E 08 Data Not 4 Data Not- ! Available Available l TE129M 1.43E 08 3.38E 00 9.01E 08 3.34E 08 3.77E 09 2.91E 08 Data Not IData Not'
, Available Available I 131 6.60E 06 ' 2.43E 06 8.78E 06 1.23E 07 2.12E 07 3.59E 09 Data Not . Data Not Available Available I 133 1.85E-01 4.59E-01 3.58E-01 6.07E-01 1.06E 00 8.47E 01 Data Not Data Not ,
Available Aviilable CS134 4.49E 08 1.20E 07 4.11E 08 9.68E 08 3.07E 08 Data Hot 1.17E 08 Data Not Available Available CS136 2.32E 07 2.78E 06 8.79E 06 3.46E 07 1.88E 07 Data Not 2.97E 06 Data Not 1 Available 'Available C$137 2.70E 08 1.10E 07 5.84E 08 7.76E 08 2.64E 08 - Data Not 1.03E 08 Data Not Available Available ! BA140 1.46E 06 3.50E 07 2,27E 07 2.78E 04 9.42E 03 Data Not- 1.87C 04 Data Not Available Avail able . j CE141 7.93E 02 1.97E 07 1.03E 04 6.90E 03 3.25E 03 Data Not Data Not Data Not l Available Available Available l
. l CE144 5.21E 04 2.44E 08 . 9.69E 05 '4.01E 05 '2.40E 05 Data Not Data Not .' Data Not. 'I Available Available Available j d
-.I ATTACHMENT 1 PAGE 30 0F 70 '
l __ ____-_-____-_L
1 SMUD-HUCLEAR ORGANIZATION NUMBER: AP.310 j REVISION: .4 ; 0FFSITE DOSE CALCULATION MANUAL PAGE 66 0F 105 l l TABLE A-21 I R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION l l PATHWAY = MEAT f I AGE GROUP = CHILD i NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.36E 02 2.36E 02 Data Not 2.36E 02 2.36E 02 2.36E 02 2.36E 02 2.36E 02 Available
]
P 32 2.80E 08 2.01E 08 7.26E 09 3.40E 08 Data Not Data Not Data Not Data Not Available Available Available Availasle MN 54 1.70E 06 5.34E 06 Cata Not 6.36E 06 1.78E 06 Data Not Data Not ' Data Not Available Avail able Avail able Available FE 59 2.61E 08 5.46E 08 3.24E 08 5.24E 08 Data Not Data Not 1.52E 08 Data Not '! Available Available Available I CO 58 4.18E 07 7.96E 07 Data Not 1.36E 07 Data Not Data Not Data Not Data Not ! Available Avail able Available Ava11 able Available ' CO 60 1.62E 08 3.04E 08 Datt. Not 5.48E 07 Data Not Data Not Data Not Data Not Available Available Available Available Avail able ZN 65 5.59E 08 1.58E 08 3.37E 08 8.99E 08 5.66E 08 Data Not Data Not Data Not , Avail able Avail able Available f RB 86 3.30E 08 3.45E 07 Data Not 5.37E 08 Data Not Data Not Data Not Data Not , Available Avail able Available Available Avail able l l
$R 89 1.18E 07 1.60E 07 4.14E 08 Data Not Data Not Data Not Data Not Data Not Available Available Available Avail able Available SR 90 2.18E 09 1.16E 08 8.62E 09 Data Hot Data Not Data Not Data Not Data Not Available Avail able Available Available Available Y 91 4.06E 04 2.02E 08 1.52E 06 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Available Available .
ZR 95 4.38E 05 5.13E 08 2.24E 06 4.92E 05 7.04E 05 Data Not Data Not Data Not Available Available Available NB 95 7.53E 05 1.95E 09 2.71E 06 1.05E 06 9.90E 05 Data Not Data Not Data Not Available Available Available ATTACHMENT 1 PAGE 310F 70 I I
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SMJD-NUCLEAR ORGANIZATION : NU;EDt: AP.310 -
/ REVISION: 4-0FFSITE DOSE CALCULATION MANUAL PAGE 67 0F 105 TABLE A-21 (Cont.)
R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = MEAT A0E GROUP = CHILD NUCLIDE T.90DY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN j
~
l RU103 5.18E 07 3.48E 09 1.35E 08 Data Not 3.39E 08 Data Not Data Not Data Not i Available Available Av411 abl e Avail able RU106 4.45E 08 5.55E 10 3.57E 09 Data Not 4.82E 09 Data Not Data Not' Data Not - j Avail able Available Available Avail able ] i AG110M 3.77E 06 5.61E 08 6.99E 06 4.72E 06 8.79E 06 Data Not Data Not y Data Not l
,, tt yallable Available Available ( j TE127M 2.06E 08 1.41E 09 1.74E 09 4.67E 08 4.95E 09 '4,15E 08 Data Not ~
Data Not Available ' Available TE129M 2.64E 08 2.07E 09 1.70E 09 4.74E 08 4.98E 09 5.47E 08 Data Not Data Not Ava11ahle juRg6dg' I 131 9.30E 06 1.46E 06 1.63E 07 1.64E 07 2.69E 07 5.41E 09 Data Not Data'Not' AvailaW . Availablg I 133 3.11E-01 3.31E-01 6.64E-01 8.21E-01 1.37E 00 1.53E 02 Data Not ~D,7ta Hot Available Available i CS134 2.51E 08 6.41E 06 7.25E 08 1.19E 09 3.69E 08 Data Not 1.32E 08 Data Not Available Avail able' CS136 2.70E 07 1.46E 06 1.52E 07 4.17E 07 2.22E 07 'D4.ta Not 3.31E 06 - 1 Data Not Available Available CS137 1.52E 08' 6.44E 06 1.07E 09 1.03E 09 3.35E 08 Data Not 1.21E 08 Date,Not-Avail able Ava t fa'Of BA140 2.44E 06 2.12E 07 4.19E 07 3.67E 04 1.19E 04 Data Not 2.19E 04 -Data Not Available Available - CE141 1.44E 03 1.21E 07 1.95E 04 9.71E 03 4.26E 03 Data hot Data'Not Data Not Available Available Avail abl e . CE144 9.75E 04 1.49E 08 1.83E 06 5.73E 05 3.17E 05 Data Not Data Not Data Not Available Available Avail able :
^
ATTACHMENT 1 PAGE' 32 0F 70
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( i i SMUO-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: .4 0FFSITE DOSE CALCULATION MANLIAL- _fAGE 68 0F 105 TABLE A-22 4 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION h; g.- i .<> PATHWAY = COW MILK AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT s BONE LIVER KIDNEY THYROID LUNG SKIN H 3 (7 91 02 7.69E 02 , Data Not 7.69E 02 7.69E 02 7.69E 02 7.69E'02 7.69E 02
' Available P 32 6.46E 08 1.88E 09 1.67E 10 1.04E 09 Data Not Data Not - Data Not Data Not Avail able Available Available ' Available i
m 54 1.281 06 It.05E 07 Data Not 6,69E 06 1.99E 06 Data'Not Data Not Data Not' j i i Available Available ' Available - Awa61able j i ! .. FE 59 2.30E 07 2.00E 08 2 55E 07 5.99E 07 Data Not Data Not 1.67E 07 Data Not. l Available Availabla Available
.]
3 CO 58 8.78E 06 7.94E 07 Data Not 3.92E 06 Data Not Data Not Data Not Data Not Available Available Available Avail able Available ' i CO 60 ' 2.86E 07 2.44E 08 Data Not 1.30E 07. Data Not Data Not' Data Not Data Not ~ i Avail able Available Avail able - Available Available IN 65 1.77E 09 2.47E C'9~ 1.23E 09 3.92E 09-- 2.62E 09 ' Data Not Data Not Data Not Available - Available Available R8 66 1.12E 09 4.75E 08 Data Not 2.41E'09 Data Not'- . Data Not' Data Not' ' Data Not . Available Available Available Avail able' Availabla
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,. SR 89 3.56E 07 1.99E 08 1.24E 09 Data Not -Data Not Data Not' Data Not Data Not ]
Avail able ' Avail able ' Available Available Available
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SR 90 9.52E 09. 1.12E 09 3.88E 10 Data Not. Data Not Data Not Data Net' Data Not Available Available Available Available Available - Y 91 1.93E 02 3.97E 06 '7,22E 03' Data Not Data Not Doth Not Data Not' . Data Not: Available Available' Available Available Available > 2R 95 1.71E'02 8.03Ed5'~7.hY)E02-2.$3E 02 3.97E 02 Data Not1 Data Not- Data Not 1,, Available Available Available NB 95 2.16E'04 2.44E 08 7.21E 04 4.01E 04 3.97E 04 Data Not Data Not . Data Not ' Available Available Available ' < ATTACHMENT-1 PAGE 33 0F 70-4 .2 hi<
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T.800Y 'C:-7AACT LIVER ' THYROIO V;4NEY- 3 SKIN NUCLIDE ' BONE ' LUNG r- , t .4 RU103 .3.81E 02 1.03E 05 8.84E 02 Data Not .3.37YO'J- Dat'ahot Data Not' Da W Not Available Availa!.le ' Available Avail ab,J,g RU106 2.08E 03 1.06E 06 '1.64C 04 Data Not 17E 04 i' Data Not . Data Not Data Not L 4 jyalltble - ' Ay.gilghle- Available Availab'.a/[f ,' AG110M 2.66E 07 1.83E 10 4.85E 07 4.48E 07' . # 6.81E 07 Data V/d Data No(f Data Not' Availdle [Availabie Available ~
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i I i f V SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 70 0F 105 TABLE A-23 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY - COW MILK AGE GROUP = TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.00E 03 1.00E 03 Data Not 1.00E 03 1.00E 03 1.00E 03 1.00E 03 1.00E 03 Available P 32 1.20E 09 2.59E 09 3.09E 10 1.91E 09 Data Not Data Not Data Not Data Not Available Available ' Avail able Available MN 54 2.21E 06 2.29E 07 Data Not 1.12E 07 3.33E 06 Data Not Data Not jDataNot Avail able Available Available Available FE 59 4.01E 07 2.46E 08 4.45E 07 1.04E 08 Data Not Data Not 3.27E 07 Data Not Avail able Avail able Available CO 58 1.52E 07 9.09E 07 Data Not 6.59E 06 Data Not Data Not Data Not Data Not Available Available Available Available Available CO 60 4.95E 07 2.86E 08 Data Not 2.20E 07 Data Not Data Not Data Not Data Not Avail able Availabl e Avail able Available Avail able 2N 65 3.07E 09 2.78E 09 1.89E 09 6.57E 09 4.21E 09 Data Not Data Not Data Not Available Avail able Avail able
,AB 86 2.06E 09 6.50E 08 Data Not 4.39E 09 Data Not Data Not Data Not Data Not Available Available Avail able Avail able Available SR 89 6.54E 07 2.72E 08 2.28E 09 Data Not Data Not Data Not Data Hot Data Not Available Avail able Avail able Available Available v ;
'j SR 90 1.35E 10 1.54E 09 5.48E 10 Data Not Data Not Data Not Data Not Data Not {
j _ Avail able Available Avail able Available Available j Y 11 3.56E 02 5.45E 06 1.33E 04 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Available Available ZR 95 3.00E 02 1.01E 06 1.38E 03 4.36E 02 6.40E 02 Data Not Data Not Data Not __ Available Available Avail able NB 95 3.76E 04 2.92E 08 1.23E 05 6.82E 04 6.61E 04 Data Vot Data Not Data Not Avail able Available Available
~I ATTACHMENT 1 1j PAGE 35 0F 70
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I SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 71 0F 105 TABLE A-23 (Cont.) R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = COW MILK AGE GROUP = TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 6.72E 02 1.31E 05 1.57E 03 Data Not' 5.54E 03 Data Not Data Not Data Not ! Avail able Avail able Available Available RU106 3.80E 03 1.45E 06 3.02E 04 Data Not 5.82E 04 Data Not- Data Not Data Not Available Available Available Available AG110M 4.61E 07 2.13E 10 8.01E 07 7.58E 07 1.45E 08 Data Not Data hot . Data Not Available 'Available Available TE127H 9.81E 06 2.06E 08 8.25E 07 2.93E 07 3.34E 08 1.M E 07 Data Not Data Not Available Available
. 1 TE129M 1.65E 07 3.90E 08 1.04E 08 3.86E 07 4.35E 08 3.35E 08 Data Not Data Not .)
Available Avail able I 131 3.97E 08 1.46E 08 5.28E 08 7.39E 08 1.27E 09 2.16E 11 Data Not Data Not f Available Available ) 1 I 133 3.74E 06 9.28E 06 7.23E 06 1.23E 07 2.15E 07 1.71E 09 Data Not Data Not Available Available - CS134 8.43E 09 2.26E 08 7.72E 09 1.82E 10- 5.77E 09 Data Not 2.20E 09 Data Not I Available Available CS136 1.12E 09 1.34E 08 4.24E 08 1.67E 09 9.08E 08 Data Not 1.43E 08 Data Not Available Available CS137 5.00E 09 2.04E 08 1.08E 10 1.44E 10 4.88E 09 Data Not 1.90E 09 Data Not Avail able Available BA140 2.98E 06 7.14E 07 4.63E 07 5.67E 04 - 1.92E 04 Data Not 3.82E 04 Data Not-Avail able Available CE141 5.98E 02 1.49E 07 7.80E 03 5.21E 03 2.45E 03 Data Not Data Not Data Not Available Available Available CE144 2.79E 04 1.31E 08 5.19E 05 2.15E 05 '1.28E 05 Data Not. Data Not Data Not Available Avail able Available ATTACHMENT 1 , PAGE 36 0F 70 6
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 l OFFSITE DOSE CALCULATION MANUAL PAGE 72 0F 105 TABLE A-24 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY - COW MILK AGE GROUP = CHILD i NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN ; H 3 1.58E 03 1.58E 03 Data Not 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 Available P 32 2.93E 09 2.10E 09 7.61E 10 3.56E 09 Data Not Data Not Daca Not Data Not l Avail abl e Available Available Available I MN 54 4.44E 06 1.40E 07 Data Not 1.67E 07 4.68E 06 Data Not Data Not - Data Not Available Available Available - Available FE 59 8.31E 07 1.74E 08 1.03E 07 1.67E 08 Data Not Data Not 4.84E 07 Data Not Available Avail able Available CO 58 3.08E 07 5.88E 07 Data Not 1.01E 07 Data Not Data Not Data Not Data Not-Avail able Available Available Avail able Avail able CO 60 1.01E 08 1.89E 08 Data Not 3.41E 07 Data Not Data Not Data Not Data Not Available Avail able Available Available Available ZN 65 6.16E 09 1.74E 09 3. JE 09 9.90E 09 6.24E 09 Data Not Data Not Data Not Avail able Available Available RB 86 5.01E 09 5.24E 08 Data Not 8.15E 09 Data Not Data Not Data Not Data Not i Avail able s. vail abl e Avail able Available Available SR 89 1.61E 08. 2.19E 08 5.65E 09 Data Not Data Not Data Not Data Not Data Not Available Available Available Avail able Available SR 90 2.35E 10 '1.25E 09 9.26E 10 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Available Available Y 91 8.78E 02 4.37E 06 3.28E 04 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Available Avail able ZR 95 6.28E 02 7.35E 05 3.21E 03 7.05E 02 1.01E 03 Data Not Data Not Data Not Avail able Avail able Avail able NB 95 7.73E 04 2.00E 08 2.78E 05 1.08E 05 1.02E 05 Data Not Data Not Data Not Available Avail abl e Available ATTACHMENT 1 PAGE 37 0F 70
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 CffSITE DOSE CALC'JLATIOf' MANUAL PAGE 73 0F 105 J TABLE A-24 (Cont.) R VALUES FOR THE RANCHO SECO NUCLFA0 GENERATING STATION PATHWAY = COW MILK AGE GROUP - CHILD NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
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I RU103 1.43E 03 9.62E 04 3.72E 03 Data Not 9.36E 03 Data Not Data Not Data Not Available Available Available Available i RU106 9.27E 03 1.16E 06 7.43E 04 Data Not 1.00E 05 Data Not Data Not Data Not ) Avail able Available Available ' Available - j q AG110M 9.38E 07 1.40E 10 1.74E 08 1.17E 08 2.19E 08 Data Not . Data Not . Data Not ) Available Available Available j TE127M 2.41E 07 1.65E 08 2.03E 08 5.48E 07 5.80E 08 4.86E 07 Data Not. Data Not Available Available TE129M 3.98E 07 3.13E 08 2.56E 08 7.16E 07 7.52E 08 8.26E 07 Data Not Data Not Availabl e Available I 131 7.31E 08 1.15E 08 1.28E 09 1.29E 09 2.11E 09 4.26E 11 Data Not Data Not Available Available I 133 8.22E 06 8.75E 06 1.76E 07 2.17E 07 3.62E 07 4.03E 09 Data Not Data Not Available Available I' CS134 6.16E 09 1.57E 08 1.78E 10 2.92E 10 9.05E 09 Data Not 3.25E 09 Data Not Avail able Avail able CS136 1.70E 09 9.24E 07 9.57E 08 2.63E 09 1.40E 08 Data Not 2.09E 08 Data Not Available Avail able CS137 3.67E 09 1.56E 08 2.60E 10 2.49E 10 8.11E 09 Data Not 2.92E 09 Data Not Available Avail able BA140 6.52E 06 5.66E 07 1.12E 08 9.79E 04 3.19E 04 Data Not 5.84E 04 Data Not Available Available CE141 1.42E 03 1.20E 07 1.92E 04 9.58E 03 4.20E 03 Data Not Data Not' Data Not Available Available Available CE144 6.83E 04 1.05E 08 1.28E 06 4.01E 05 2.22E 05 Data Not Data Not Data Not Available Avail able Available ATTACHMENT 1 PAGE 38 0F 70
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I SPtJD-NUCLEAR ORGANIZATION NUMBER: AP.310 j REVISION: 4 0FFSITE DOSE taldiLATION MANUAL PAGE 74 0F 105 ! TABLE A-25 l R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = COW NILK AGE GROUP = INFANT NUCLIDE T. BODY 'GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
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H 3 2.40E 03 2.40E 03 Data Not 2.40E 03 2,40E 03 '2.40E 03 2.40E 03 - 2.40E 03 Available P 32 6.08E 09 2.12E 09 1.57E 11 9.22E 09 Data Not Data Not Data Not- Data Not ] Available Available Availabl e Available -! Pti 54 7.03E 06 1.14E 07 Data Not 3.10E 07 6.88E 06 Data Not Data Not Data Not Avail able Available Available Available ' i l FE 59 1.33E 08 1.61E 08 1.93E 08 3.36E 08 Data Not Data Not : 9.94E 07 2 Data Not Available Available "Available CO 58 5.03E 07 5.02E 07' Data Not 2.01E 07 Data Not Data Not Data Not Data Not j Available Avail able Available Available Available ! CO 60 1.65E 08 1.66E 08 Data Not 6.97E 07 Data Not Data Not Data Not ' Data Not i Avail able Available Available Available Available j ZN 65 7.89E 09 1.45E 10 4.99E.09 1.71E 10 8.30E 09 Data Not- Data Not Data Not Available Available Available RB 86 1.02E 10 5.29E 08 Data Not 2.07E 10 Data Not Data Not Data Not Data Not , Available Available Av111 able ' Available Available - 'l l
$R 89 3.08E 08 2.21E 08 1.07E 10 Data Not Data Not Data Not Data Not Data Not J Available Available Available Available Available SR 90 2.57E 10' 1.26E 09 1.01E 11 Data Not Data Not Data Not Data Not Data Not.'
Available ' Available Available Available Available ! Y 91 1.64E 03 4.42E 06 6.16E 04 Data Not Data Not. Data Not- Data Not DataNotL i Available Available Available ' Available Available ZR 95 9.34E 02 6.91E 05 5.70E 03 1.39E 03 1.50E 03 Data Not' Data Not" Data Not :, Available Available Available 5 N8 95 1.23E 05- 1.80E 08 5.18E 05 2.14E 05 1.53E 05 Data Not ' Data Not' Data Not i Available Available Available ATTACHMENT 1 PAGE 39 0F 70 r _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ w
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SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 75 0F 105
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l TA8LE A-25 (Cont.) R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = C0W MILK AGE GROUP - INFANT ) l NUCLIDE GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN T. BODY ( RU103 2.52E 03 9.16E 04 7.53E 03 Data Not 1.57E 04 Data Not Data Not Data Not , Available Available Available Available i RU106 1.91E 04 1.16E 06 1.53E 05 Data Not 1.81E 05 Data Not Data Not Data Not l Available Available Available Avail able ] AG110M 1.55E 08 1.22E 10 3.21E 08 2.34E 08 3.35E 08 Data Not Data Not Data Not Avail able Available Available TE127M 4.98E 07 1.66E 08 4.12E 08 1.37E 08 1.01E 09 1.19E 08 Data Not ~ Data Not Avail able Available TE129H 8.10E 07 3.14E 08 5.26E 08 1.80E 08 1.32E 09 2.02E 08 Data Not Data Not Available Available I 131 1.38E 09 1.125 08 2.67E 09 3.15E 09 3.68E 09 1.03E 12 Data Not Data Not Avail able Avail able I 133 1.58E 07 9.14E 06 3.71E 07 5.40E 07 6.35E 07 9.82E 09 Data Not Data Not i Available Available CS134 5.40E 09 1.45E 08 2.87E 10 5.35E 10 1.38E 10 Data Not 5.64E 09 Data Not i _ Available Avail able 1 l CS136 2.05E 09 8.35E 07 1.87E 09 5.50E 09 2.19E 09 Data Not 4.48E 08 Data Not Avail able Available CS137 3.44E 09 1.52E 08 4.15E 10 4,86E 10 1.30E 09 Data Not 5.28E 09 Data Not Available Available BA140 1.19E 07 5.65E 07 2.30E 08 2.30E 05 5.46E 04 Data Not 1.41E 05 . Data Not Availa51e Available CE141 2.73E 03 1.20E 07 3.81E 04 2.32E 04 7.16E 03 Data Not Data Not Data Not Available ' Avail able Available CE144 1.03E 05 1.05E 08 1.83E 06 7.51E 05 3.03E 05 Data Not Data Not Data Not Available Available Available ATTACHMENT 1 PAGE 40 0F 70
1 i SHUD-NUCLEAR ORGANIZATION NUNBER: AP 310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 76 0F 105 TABLE A-26 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = GOAT NILK AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.57E 03 1.57E 03 Data Not 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 Available P 32 7.76E 08 2.26E 09 2.01E 10 1.25E 09 Data Not Data Not. Data Not . Data Not Avail able Avail able Available Available MN 54 1.53E 05 2.46E 06 Data Not 8.03E 05 2.39E 05 Data Not Data Not Data Not' Available Available Avail able - Available FE 59 2.98E 05 2.60E 06 3.31E 05 7.79E
- 05 Data Not Data Not 2.18E 05 Data Not Available Available Available CO 58 1.05E 06 9.53E 06 Data Not 4.70E 05 Data Not Data Not Data Not Data Not ;
Available Available Avail able Available Available ! CO 60 3.43E 06 2.93E 07 Data Not 1.56E 06 Data Not Data Not Data Not Data Not Available Available Available Available Avail able ZN 65 2.13E 08 2.97E 08 1.48E 08 4.71E 08 3.15E 08 Data Not Data Not Data Not Available Available Available j RB 86 1.35E 08 5.71E 07 Data Not 2.89E 08 Data Not Data Not. Data Not . Data Not Available Available Avail able Available Available SR 89 7.47E Oi 4.17E 08 2.60E 09 Data Not Data Not Data Not Data Not Data Not .. Available Available Available Available Available SR 90 2.00E 10 2.35E 09 8.14E 10 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Avail abl e - Available Y 91 2.32E 01 4.77E 05 8.67E 02 Data Not Data Not Data Not Data Not Data Not Available Available Available Avail able Availabig ZR 95 2.06E 01 9.63E 04 9.47E 01 3.04E 01 4.77E 01 Data Not Data Not Data Not Available Avail able ' Available NB 95 2.59E 03 2.92E 07 8.66E 03 4.81E 03 '4.76E 03 Data Not Data Not . Data Not Available Available " Available ATTACHMENT 1 PAGE 410F 70
l l I SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 77 0F 105 TABLE A-26 (Cont.) R VALUES FOR THE RANCHO SECO dVCLEAR GENERATING STATION e PATHWAY = GOAT MILK j AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 4.57E 01 1.24E 04 1.06E 02 Data Not 4.05E 02 Data Not Data Not Data Not Avail able Available Avail able Available RU106 2.49E 02 1.27E 05 1.97E 03 Data Not 3.80E 03 Data Not Data Not Data Not Available Available Available AG110M 3.19E 06 2.20E 09 5.82E 06 5.3CE 06 1.06E 07 Data Not Data Not : Data Not Available Available Available TE127M 6.55E 05 1.80E 07 5.37E 06 1.92E 06 2.18E 07 1.37E 06 Data Not " Data Not Available Available TE129M 1.08E 06 3.43E 07 6.82E 06 2.54E 06 2.85E 07 2.34E 06 Data Not Data Not Available Available I 131 2.86E 08 1.32E 08 3.49E 08 4.99E 08 8.56E 08 1.64E 11 Data Not Data Not Available Available I 133 2.52E 06 7.42E 06 4.75E 06 8.26E 06 1.44E 07 1.21E 09 Data Not Data Not Available Available CS134 2.59E 10 5.55E 08 1.33E 10 3.17E 10 1.03E 10 Data Not 3.41E 09 Data Not Available Available CS136 2.12E 09 3.35E 08 7.47E 08 2.95E 09 1.64E 09 Data Not 2.25E 08 Data Not Available Avail able ' CS137 1.60E 10, 4.73E 08 1.78E 10 2.44E 10 8.29E 09 Data Not 2.75E 09 Data Not Available Avail able BA140 2.02E 05 6.34E 06 3.03E 06 3.87E 03 1.31E 03 Data Not 2.21E 03 Data Not l Available Available ! CE141 3.92E 01 1.32E 06 5.11E 02 3.45E 02 1.60E 02 Data Not Data Not Data Not Available Available Available CE144 1.82E 03 1.15E 07 3.39E 04 1.42E 04 8.40E 03 Data Not- Data Not Data Not Available Avail able Available ATTACMMENT 1 l PAGE 42 0F 70 1 - _ _ _ _ _ _ - - _ _ - _ - - _ _ _ _ _ _ _ - - _ . _ _ _ . _1
7 l SPtJ0-NUCLEAR ORGANIZATION NUNBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 78 0F 105 TABLE A-27 R VALUES FOR THE RANCHO SECC NUCLEAR GENERATING STATION PATHWAY = GOAT MILK AGE GROUP = TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.04E 03 2.04E 03 Data Not 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 Ava'Obie P 32 1.44E 09 3.11E 09 3.wE 10 2.29E 09 Data Not Data Not Data Not' Data Not. Available Available Avail able Availabl.g j PN 54 2.65E 05 2.74E 06 Data Not 1.34E 06 3.99E 05 - Data Not Data Not
- Data Not Available Avail able Available Available FE 59 5.21E 05 3.19E 06 5.78E 05 1.35E 06 Data Not Data Not 4.26E 05 Data Not Avail able Available Available CO 58 1.82E 06 1.09E 07 Data Hot 7.91E 05 Data Not Data Not Data Not Data Not Available Avail able Available Available Available CO 60 5.94E 06 3.44E 07 Data Not 2.64E 06 Data Not Data Not Data Not Data Not Available Available Available Available Available ZN 65 3.68E 08 3.34E 08 2.27E 08 7.89E 08 5.05E 08 Data Not Data Not Data Not Available Available Available RB 86 2.48E 08 7.80E 07 Data Not 5.27E 08 Data Not Oatt. Not ~ Data Not Data Not ,
Available Available Available ' Available Available l SR 89 1.37E 08 5.71E 08 4.80E 09 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Avail able SR 90 2.84E 10 3.23E 09 1.15E 11 Data Not- Data Not Data Not- Data Not Data Not Available Available Available Avail able Available Y 91 4.27E 01 6.54E 05 1.59E 03 Data Not Data Not Data Not = Data Not- Data Not Availabl e Avail able Avail able Available Available ZR 95 3.60E 01 1.21E 05 1.66E 02 5.23E 01 7.68E 01 Data Not ' Data Not Data Not Available Available Available NB 95 4.51E 03 3.50E 07 1.48E 04 8.19E 03 7.94E 03 Data Not Data Not Data Not Available Avail able Available ATTACHMENT 1 PAGE 43 0F 70
i k SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 79 0F 105 TABLE A-27 (Cont.) l R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION . PATHWAY = GOAT MILK AGE GROUP = TEEN i NUCLIDE T.800Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 8.07E 01 1.58E 04 1.89E 02 Data Not 6.65E 02 Data Not Data Not Data Not Available Available Available Available RU106 4.56E 02 1.74E 05 3.62E 03 Data Not 6.98E 03 Data Not Data Not Data Not Available Available Available Available j AG110M 5.53E 06 2.56E 09 9.61E 06 9.10E 06 1.74E 07 Data Not Data Not Data Not Avail able Availabl e Available TE127M 1.18E 05 2.47E 07 9.90E 06 3.51E 06 4.01E 07 2.35E 06 Data Not Data Not Availabl e Available TE129M 1.97E 06 4.68E 07 1.25E 07 4.63E 06 5.22E 07 4.03E 06 Data Not Data Not 1 Avail able Available l I 131 4.76E 08 1.75E 08 6.33E 08 8.86E 08 1.53E 09 2.59E 11 Data Not Data Not Available Available l
' 133 4.49E 06 1.11E 07 8.67E 06 1.47E 07 2.58E 07 2.05E 09 Data Not Data Not a Avail able Available CS134 2.53E 10 6.78E 08 2.32E 10 5.45E 10 1.73E 10 Data Not 6.61E 09 Data Not Avail able Available 1
CS136 3.36E 09 4.03E 08 1.27E 09 5.00E 09 2.72E 09 Data Not 4.29E 08 Data Not Available Available ! l CS137 1.50E 10 6.13E 08 3.24E 10 4.31E 10 1.47E 10 Data Not 5.69E 09 Data Not Available Available li BA140 3.58E 05 8.57E 06 5.56E 06 6.81E 03 2.31E 03 Data Not 4.58E 03 Data Not Available Available l CE141 7.18E 01 1.79E 06 9.36E 02 6.25E 02 2.94E 02 Data Not Data Not Data Not .] Available Available Available { CE144 3.35E 03 1.57E 07 6.23E 04 2.58E 04 1.54E 04 Data Not Data Not Data Not Avail abl e Available Avail able 1 l ATTACHMENT 1 ! PAGE 44 0F 70 ) i 1 1 1 ) I o
I t SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE talNilATION MANUAL ~ PAGE 80 0F 105 TABLE A-28 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = GOAT MILK AGE GROUP = CHILD l NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG . SKIN H 3 3.23E 03 3.23E 03 Data Not 3.23E 03 3.23E 03 3.23E 03 3.23E 03- 3.23E 03 Avail able P 32 3.52E 09 2.52E 09 9.13E 10 4.27E 09 Data Not Data Not Data Not' Data Not Available Avail able Available Available MN 54 5.33E 05 1.68E 06 Data Not 2.00E 06 5.61E 05 Data Not Data Not . Data Not ; Available Available Avail able - Available ! FE 59 1.08E 06 2.26E 06 1.34E 06 2.17E 06 Data'Not Data Not 6.29E 05 IDataNot Available Avail able ' Available ' CO 58 3.70E 06 7.05E 06 Data Not 1.21E 06 Data Not. Data Not Data Not Data Not Avail able Available Available Available Available CO 60 1.21E 07 2.27E 07 Data Not 4.10E 06 Data Not Data Est Data Not Data Not Available Avail able Avail able Avail able - Avail able ZN 65 7.39E 08 2.09E 08 4.46E 08 1.19E 09 7.48E 08 Data Not Data Not Data Not Avail able Available Available RB 86 6.02E 08 6.29E 07 Data Not 9.78E 08 Octa Not Data Not Data Not Data Not Available Available Avail able Available Avail able SR 89 3.39E 08 4.60E 08 1.19E 10 Data Not ' Data Not Data Not Data Not Data Not l Available Available Available Avail able Available SR 90 4.93E 10 2.625 09 1.94E 11 Data Not Data Not- Data Not Data Not Data Not Available - Avail able Avail able Available Ava11Ahlg Y 91 1.05E 02 5.25E 05 3.94E 03 Data Not Data Not Data Not' Data Not Data Not l Available Available Avail able Available Available ZR 95 7.53E 01 8.83E 04 '3.85E 02 8.46E 01 1.21E 02 Data Not' Data Not Data Not Available Available Available NB 95 9.27E 03 2.40E 07 3.33E 04 1.30E 04~ 1.22E 04 Data Not Data Not Data Not l Available Available Available ATTACHMENT.1
. PAGE 45 0F 70 2
l l l SMUD-4AJCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE 00$E CALCULATION MANUAL PAGE 810F 105 TABLE A-28 (Cont.) i R VALUES FOR THE RANCHO SECO NUCLEAR G2NERATING STATION PATHWAY = GOAT MILK AGE GROUP = CHILD NUCLIOE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 1.72E 02 1.15E 04 4.46E 02 Data Not 1.12E 03 Data Not Data Not Data Not Available Avail able Available Available l l RU106 1.11E 03 1.39E 05 8.92E 03 Data Not 1.20E 04 Data Not Data Not Data Not Available Available Avail able Available l AG110M 1.13E 07 1.68E 09 2.03E 07 1.41E 07 2.62E 07 Data Not Data Not Data Not Availabl e Available Available 1 3 l TE127M 2.90E 06 1.98E 07 2.44E 07 6.57E 06 6.96E 07 5.H E 06 Data Not Da'ta Not l _ Available Available l TE129M 4.77E 06 3.75E 07 3.08E 07 8.59E 06 9.03E 07 9.91E 06 Data Not Data Not l Available Available I 131 8.78E 08 1.38E 08 1.54E 09 1.54E 09 2.54E 09 5.11E 11 Data Not Data Not Avail able As allable I 133 9.86E 06 1.05E 07 2.11E 07 2.61E 07 4.34E 07 4.84E 09 Data Not Data Not Available Available CS134 1.85E 10 4.72E 08 5.34E 10 8.76E 10 2.72E 10 Data N t 9.74E 09 Data Not Availabl e Available CS136 5.11E 09 2.77E 08 2.87E 09 7.89E 09 4.20E 09 Data Not 6.27E 08 Data Not Avail able Available CS137 1.10E 10 4.67E 08 7.80E 10 7.46E 10 2.43E 10 Data Not 8.75E 09 Data Not ! Available Available BA140 7.83E 05 6.80E 06 1.34E 07 1.18E 04 3.83E 03 Data Not 7.01E 03 Data Not Avail able Available CE141 1.71E 02 1.43E 06 2.31E 03 1.15E 03 5.04E 02 Data Not Data Not Data Not Available Avail able Available CE144 8.20E 03 1.26E 07 1.54E 05 4.82E 04 2.67E 04 Data Not Data Not Data Not Available Available Available ATTACHMENT 1 PAGE 46 0F 70 t
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1 i l i 1 _ 1 SMUD-NUCLF.AR ORGANIZATION NUNBER: AP.310 ) REVISION: 4 I 0FFSITE DOSE CALCULATION MANUAL PAGE 82 0F 105 I TABLE A-29 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = GOAT NILK AGE GROUP = INFANT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 4.90E 03 4.90E 03 Data Not 4.90E 03 4.90E 03 4.90E 03 4.90E 03 4.90E 03 Available l P 32 7.29E 09 2.55E 09 '1.88E 11 1.11E 10 Data Not Data Not Data Not Data Not l Availahle Avail able Available Availabl e ) 1 1 i tW 54 8.44E 05 1.37E 06 Data Not 3.72E 06 0.25E 05 Data Not Data Not Data Not ! Available Available Available Avail able
'I FE 59 1.72E 06 2.09E 06 2.50E 06 4.37E 06 Data Not Data Not 1.29E 06 l Data Not l Available Available Available l I
CO 58 6.03E 06 6.02E 06 Data Not 2.42E 06 Data Not Data Not Data Not Data Not l Available Available Avail able Available Available CO 60 1.98E 07 1.99E 07 Data Not 8.37E 06 Data Not Data Not Data Not Data Not i Available Avail able Available Available Available ZN 65 9.47E 08 1.73E 09 5.99E 08 2.05E 09 9.96E 08 Data Not Data Not Data Not Available Available Available RB 86 1.23E 09 6.35E 07 Data Hot 2.48E 09 Data Not Data Not Data Not Data Not Avail able Available Available Avail able Available SR 89 6.48E 08 4.64E 08 2.26E 10 Data Not Data Not Data Not -Data Not Data Not j l Available Avail able Available Available Avail able ) l 1 SR 90 5.39E 10 2.64E 09 2.12E 11 Data Not Data Not Data Not Data Not Data Not Available Available Avail able Available Avail able l Y 91 1.97E 02 5.30E 06 7.39E 03 Data Not Data Not Data Not Data Not Data Not Available Available Available Available Available j i ZR 95 1.18E 02 8.29E 04 6.83E 02 1.67E 02 1 79E 02 Data Not Data Not' Data Not Available Available - Available NB 95 1.48E 04 2.16E 07 6.22E 04 2.56E 04 1.84E 04 Data Not Data Not Data Not Avail able Available Available ATTACHMENT 1 PAGE 47 0F 70 i ____._._._.__________-__.--_.__mw
~m SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 83 0F 105 TABLE A-29 (Cont.)
R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = GOAT HILK AGE GROUP = INFANT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYR 010 LUNG $ KIN RU103 3.02E 02 1.10E 04 9.09E 02 Data Not 1.88E 03 Data Not Data Not Data Not .- Available Avail able Avail able Available , RU106 2.29E 03 1.39E 05 1.84E 04 Data Not 2.17E 04 Data Not Data Not Data Not Available Avallable Availabl e Available AG110M 1.86E 07 1.46E 09 3.85E 07 2.81E 07 4.02E 07 Data Not Data Not Data Not Available Available Available
~
i TE127M 5.98E 06 1.99E 07 4.94E 07 1.64E 07 1.22E 08 1.43E 07 Data Not Data Not Available
- Availablg TE129M 9.72E 06 3.77E 07 6.31E 07 2.17E 07 1.58E 08 2.42E 07 Data Not Data Not l Available Available I 131 1.66E 09 1.35E 08 3.21E 09 3.78E 09 4.41E 09 1.24E 12 Data Not Data Not Available Avaliablg I 133 1.90E 07 1.10E 07 4.45E 07 6.48E 07 7.62E 07 1.18E 10 Data Not Data Not l Avtil abl e Avail able CS134 1.62E 10 4.36E 08 8.60E 10 1.60E 11 4.13E 10 Data Not 1.69E 10 Data Not Available Avail able CS136 6.15E 09 2.50E 08 5.61E 09 1.65E 10 6.57E 09 Data Not 1.34E 09 Data Not
, Avail able Avail able CS137 1.03E 10 4.55E 08 1.24E 11 1.46E 11 3.91E 10 Data Not 1.58E 10 Data Not Available Avail able ;
BA140 1.42E 06 6.78E 06 2.76E 07 2.76E 04 6.55E 03. Data Not 1.69E 04 Data Not Avail able Avail atd3 CE141 3.28E 02 1.44E 06 4.57E 03 2.79E 03 8.59E 02 Data Not Data Not Data Not Avail able Available Avail able
~
\
CE144 1.23E 04 1.26E G7 2.20E 05 9.01E 04 3.64E 04 Data Not Data Not Data Not Available Available Available i ATTACHMENT 1 - PAGE 48 0F 70 - _ _ . ~ _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _ _ - _ _ _ _ . _ _ _ _ _ _ - _ _ _ . _ - - - _ _ _ . . _ _ _ _ _ _ _ _ . _
i i SMJD-NUCLEAR ORGANIZATION NUNBER: : AP.310 REVISION: 4 l OFFSITE DOSE CAlmi ATION NANUAL PACE 84 0F 105 j TABLE A-30 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION , i AGE GROUP = ADULT NUCLIDE T.800Y GI-TRACT BONE LIVER KIDNEY. TWROID LUNG $ KIN I H 3 1.26E 03 1.26E 03 Data Not 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 Available P 32 5.00E 04 8.63E 04 1.32E 06 7.70E 04 : Data Not Data Not- Data Not Data Not Avail able ' Available Available Available NN 54 6.29E 03 7.72E 04 Data Not 3.95E 04' 9.83E 03 Data Not 1.40E 06 LData Not' Available Available Available' FE 59 1.05E 04 1.88E 05 1.17E 04 2.77E 04 Data Not Data Not 1.01E 06 ~ . Data Not' Available Available ' Available CO 58 2.07E 03 1.06E 05 Data Not 1.581 03. Data Not Ihta Not , 9.27E 05 Data Not Available Available Available Available CO 60 1.48E 04 .2.84E 05 Data Not 1.15E 04 Data Not Data Not 5.96E 06 Data Not Available Available Available Available l ZN 65 4.65E 04' 5.3AE 04 3.24E 04 1.03E 05 6.89E 04 Data Not 8.63E 05 Data Not Available Avail able j RB 86 5.89E 04 1.66E 04 Data Not 1.35E 05 Data Hot ' Data Not -Data Not Data Not Available Available Available Available Available- 1 SR 89 8.71E 03 3.49E 05 3.04E 05 Data Not Data Not Data'Not 1.40E 06 Data Not Available Available Available Ava11ab13. . SR 90 6.09E 06 7.21E 05' 9.91E 07 Data Not ' Data Not Data Not 9.59E 06 Data Not j Avail able Available Availabl e Available Y 91 1.24E 04 3.64s 05 4.62E 05 Data NotL Data Not Data Not. 1.70E 06 Data Not Avail able Available Avail abl e' Available ZR 95 2.32E 04 .1.50E 05 1.07E 05 3.44E 04 5.41E 04 Data Not- 1.77C 06 Data Not Available Available N6 95 4.20E 03 1.04E 05 1.41E 04 7.80E 03 '7.72E 03 Data Not- 5.04E 05- Dat'a Not i Avillable Avail able ATTACHNENT 1' PAGE 49 0F 70 ,
.il :
i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 85 0F '05 1 TABLE A-30 (Cont.) j R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION AGE GROUP - ADULT . j NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TNYROID LUNG SKIN < RU103 6.57E 02 1.10E 05 1.53E 03 Data Not 5.82E 03 Data Not 5.04E 05 Data Not ~ Avail abl e Availabl e Available l RU106 8.71E 03 9.11E 05 6.90E 04 Data Not 1.33E 05 Data Not 9.35E 06 Data Not I Available Available Available I l AG110M 5.94 03 3.02E 05 1.08E 04 9.99E 03 1.97E 04 Data Not 4.63E 06 Data Not J Available Available I TE127N 1.57E 03 1.49E 05 1.26E 04 5.76E 03 4.57E 04 3.28E 03 9.59E 05 Data Not
- Available TE129M 1.58E 03 3.83E 05 9.75E 03 4.67E 03 3.65E 04 3.44E 03 1.16E 06 Data Not Available j
I 131 2.05E 04 6.27E 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07 Data Not Data Not Availably Available { I 133 4.51E 03 8.87E 03 8.63E 03 1.48E 04 2.58E 04 2.15E 06 Data Not Data Not ; Available Available CS134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 Data Not 9.75E 04 Data Not Avail able Available 1 CS136 1.10E 05 1.17E 04 3.90E 04 1.462. 05 8.55E 04 Data Not 1.20E 04 Data Not I Available Available .. CS137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 Data Nct 7.51E 04 Data Not Available Avail able ) l BA140 2.56E 03 2.18E 05 3.90E 04 4.90E 01 1.67E 01 Data Not 1.27E 06 ' Data Not Available Available CE141 1.53E 03 1.20E 05 1.99E 04 1.35E 04 6.25E 03 Data Not 3.61E 05 Data Not Availabl e Available CE144 1.84E 05 8.15E 05 3.43E 06 1.43E 06 8.47E 05 Data Not 7.76E 06 Data Not Available Available ATTACHMENT 1 PAGE 50 0F 70
1 SMUD-NUCLEAR ORGANIZATION N9MBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 86 0F 105 TABLE A-31 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION AGE GROUP = TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.27E 03 1.27E 03 Data Not 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 Available P 32 7.15E 04 9.27E 04 1.89E 06 1.09E 05 Data Not Data Not Data Not Data Not Avail ?.bl e Available Avail able Available HN 54 8.39E 03 6.67E 04 Data Not 5.10E 04 1.27E 04 Data Not 1.98E 06 Data Not Available Avail able Availqhlg FE 59 1.43E 04 1.78E 05 1.59E 04 3.69E 04 Data Not Data Not 1.53E 06 . Data Not Available Available Available CO 58 2.77E 03 9.51E 04 Data Not 2.07E 03 Data Not Data Not 1.34E 06 Data Not Available Available Available Available CO 60 1.98E 04 2.59E 05 Data Not 1.51E 04 Data Not Data Not 8.71E 06 Data Not Available ~ Available Available Available ZN 65 6.23E 04 4.66E 04 3.85E 04 1.33E 05 8.63E 04 Data Not 1.24E 06 Data Not Available Available RB 86 8.39E 04 1.77E 04 Data Not 1.90F 05 Data Not Data Not Data Not Data Not Available Available Available Available Available SR 89 1.25E 04 3.71E 05 4.34E 06 Data Not Data Not Data Not 2.41E 06 Data Not
. Available Available Available Available SR 90 6.67E 06 7.64E 05 1.08E 08 Data Not Data Not . Data Not 1.65E 07 Data Not
, Available Available Avail able Avail able Y 91 1.77E 04 4.08E 05 6.60E 05 Oata Not Data Not Data Not 2.93E 06 Data Not Available Available Available Available ZR 95 3.15E 04 1.49E 05 1.45E 05 4.58E 04 6.73E 04 Data Not 2.68E 06 Data Not Available Available NB 95 5.66E 03 9.67E 04 1.85E 04 1.03E 04' 9.99E 03 Data Not 7.50E 05 Data Not Avail abl e - Available ATTACHMENT 1 PAGE 510F 70
i SK'D-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 87 0F 105 TABLE A-31 (Cont.) R VALUES FOR The RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION 1 AGE GROUP = TEEN NUCLICE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN j RU103 8.95E C2 1.09E 05 2.10E 03 Data Not 7.42E 03 : Data Not 7.82E 05 Data Not Available Available Available l RU106 1.24E 04 9.59E 05 9.83E 04 Data Not 1.90E 05 Data Not 1.61E 07 Data Not-Available , Avail able ' Available
~
i AG110M 7.98E 03 2.72E 05 1.38E 04 1.31E 04 2.50E 04 Data Not 6.74E 06- Data Not ; Available Available ! TE127M 2.18E 03 1.59E 05 1.80E 04 8.15E 03 6.53E 04 4.38E 03 1.65E 06 ; Data Not Available ; TE129M 2.24E 03 4.04E 05 1.39E 04 6.57E 03 5.18E 04 4.57E 03 1.97E 06 Data Not Available I 131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 Data Not -Data Not Availablo Available I 133 6.21E 03 1.03E 04 1.21E 04 2.0$E 04 3.59E 04 2.92E 06 Data Not Data Not l Available Available ) 1 CS134 5.48E 05 9.75E 03 5.02E 05 1.13E 06 3.75E 05 Data Not 1.46E 05 Data Not Available Available CS136 1.37E 05 1.09E 04 5.14E 04 1.93E 05 1.10E 05 Data Not 1.77E 04 Data Not Available Available CS137 3.11E 05 8.47E 01 6.69E 05 8.47E 05 3.04E 05 Data Not 1.21E 05 Data Not Available Available - l BA140 3.51E 03 2.28E 05 5.46E 04 6.69E 01 2.28E 01 Data Not' 2.03E 06 Data Not Available Available - CE141 2.16E 03 1.26E 05 2.84E 04 1.89E 04 8.87E 03 Data Not 6.13E 05 Data Not
' Available Available CE144 2.62E 05 8.63E 05 4.88E 06 2.02E 06 -1.21E 06- Data No't 1.33E 07 Data Not Avail able - Available t
ATTACHMENT 1 PAGE 52 0F 70 I
l SMUD-NUCLEAR ORG'.NIZATION NUFEER: AP.310 REVISION: 4 0Ff3ITE DOSE CALCULATION MANUAL PAGE 88 0F 105 TABLE A-32 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION ACI GROUP = CHILD q NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNS SKIN j i H 3 1,12E 03 1.12E 03 Data Not 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 Available 1 P 32 9.86E 04 4.21E 04 2.60E 06 1.14E 05 Data Not Data Not Data Not Data Not ! Available Avail able Avail able Available MN 54 9.50E 03 2.'i9E 04 Data Not 4.29E 04 1.00E 04 Data Not 1.57E 06 Data Not j Avail abl e _ Avail able Available
]
FE 59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 Data Not Data Not 1.27E 06 Data Not Available Avail able Available j CO 58 3.16E 03 3.43E 04 Oata Not 1.77E 03 Data Not Data Not 1.10E 06 Data Not Available Available Available Available j CO 60 2.2fE 0> 9.61E 04 Data Not 1.31E 04 Data Not Data Not 7.06E 06 Data Not Available Avail able Available Available 1 ZN 65 7.02E 04 1.63E 04 4.25E 04 1.13E 05 7.13E 04 Data Not 9.94E 05 Data Not Available Availab13 RB 86 1.14E 05 7.08E 03 Data Not 1.98E 05 Data Not Data Not Data Not Data Not Available Available Avail able Avail able Available SR 89 1.72E 04 1.67E 05 5.99E 05 Data Not Data Not Data Not 2.15E 06 Data Not Available Avail able Available Available SR 90 6.43E 06 3.43E 05 1.01E 08 Data Not Data Not Data Not 1.47E 07 Data Not Avail able Available Avail able Avail able i Y 91 2.43E 04 1.84E 05 9.13E 05 Data Not Data Not Data Not 2.62E 06 Data Not Avail able Available Available Available ZR 95 3.69E 04 6.10E 04 1.90E 05 4.17E 04 5.95E 04 Data Not 2.23E 06 Data Not Avail able Available NB 95 6.54E 03 3.69E 04 2.35E 04 9.16E 03 8.61E 03 Data Not 6.13E 05 Data Not Available Avail able ATTACHMENT 1 PAGE 53 0F 70
i SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE cai mu ATION MANUAL PAGE 89 0F 105 TABLE A-32 (Cont.) R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION AGE GROUP = CHILD NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN RU103 1.07E 03 4.47E 04 2.79E 03 Data Not 7.02E 03 Data Not 6.61E 05 Data Not Available Available Available RU106 1.69E 04 4.29E 05 1.36E 05 Data Not 1.84E 05 Data Not 1.43E 07 Data Not Availabl e Avail able Available AG110H 9.13E 03 1.00E 05 1.68E 04 1.14E 04 2.12E 04 Data Not 5.47E 06 Data Not Avail able Available TE127M 3.01E 03 7.13E 04 2.48E 04 8.53E 03 6.35E 04 6.06E 03 1.48E 06 c Data Not i Available
~
TE129M 3.04E 03 1.81E 05 1.92E 04 6.84E 03- 5.02E 04 6.32E 03 1.76E 06 Data Not Available I 131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 Data Not Data Not Available Available 1 I 133 7.68E 03 5.47E 03 1.66E 04 2.03E 04 3.37E 04 3.84E 06 Data Not Data Not Avail able Available CS134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.30E 05 Data Not 1.21E 05 Data Not i Available Available CS136 1.16E 05 4.17E 03 6.50E 04 1.71E 05 9.53E 04- Data Not 1.45E 04 Data Not Available Avail able CS137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 Data Not 1.04E 05 Data Not Avail able Available BA140 4.32E 03 1.02E 05 7.39E 04 6.47E 01 2.11E 01 Data Not- 1.74E 06 Data Not-Available Avail able 1 l CE141 2.89E 03 5.65E 04 3.92E 04' 1.95E 04 8.53E 03 Data Not 5.43E 05 Data Not Available Availablg CE144 3.61E 05 3.88E 05 6.76E 06 2.11E 06 1.17E 06 Data Not 1.19E 07 Data Not Avail able Available' ATTACHMENT 1
- PAGE 54 0F 70
l l I I l l l SMUD-NUCLEAR ORGANIZATION NUMBER: AP 310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 90 0F 105 l TABLE A-33 R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION AGE GROUP = INFANT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 6.46E 02 6.46E 02 Data Not 6.46E 02 6.46E 02 6.46E 02 6.46E C2 6.46E 02 l Ava8 1able i P 32 7.73E 04 1.61E 04 2.03E 06 1.12E 05 Data Not Data Not Data Not Data Not ) Available Available Available Available l MN 54 4.98E 03 7.05E 03 Data Not 2.53E 04 4.98E 03 Data Not 9.98E 05 Data Not Available Available Avail able FE 59 9.46E 03 2.47E 04 1.35E 04 2.35E 04 Data Not Data Not 1.01E 06 ' Data Not Available Avail able ' ~ Available 1 CO 58 1.82E 03 1.11E 04 Data Not 1.22,E 03 Data Not Data Not 7.76E 05 Data Not Available Available Available Available l C0 60 1.18E 04 3.19E 04 Data Not 8.01E 03 Data Not Data Not - 4.50E 06 Data Not Available Available Available Available , l ZN 65 3.10E 04 5.13E 04 1.93E 04 6.25E 04 3.24E 04 Data Not 6.46E 05 Data Not Avail able Available RB 86 8.81E 04 3.03E 03 Data Not 1.90E 05 Data Not Data Not Data Not Data Not Available Available Available Available Available SR 89 1.14E 04 6.39E 04 3.97E 05 Data Not Data Not Data Not 2.03E 06 Data Not ) Available Avail able Avail abl e Available SR 90 2.59E 06 1.31E 05 4.08E 07 Data Not Data Not Data Not 1.12E 07 !)ata Not Available Available Available Available l l Y 91 1.57E 04 7.02E 04 5.87E 05 Data Not Data Not Data Not 2.45E 06 Data Not I Available Available Avail able Available ZR 95 2.03E 04 2.17E 04 1.15E 05 2.78E 04 3.10E 04 Data Not 1.75E 06 Data Not Available Available NB 95 3.77E 03 1.27E 04 1.57E 04 6.42E 03 4.71E 03 Data Not- 4.78E 05 Data Not Available Avail able ATTACHMENT 1 PAGE 55 0F 70
1 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 910F 105 TABLE A-33 (Cont.) ] R VALUES FOR THE RANCHO SECO NUCLEAR GENERATING STATION PATHWAY = INHALATION AGE GROUP = INFANT 3 NUCLIDE 7. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN l RU103 6.78E 02 1.61E 04 2.01E 03 Data Not 4.24E 03 Data Not 5.51E 05 Data Not Available Avail able Available RU106 1.09E 04 1.64E 05 8.67Z 04 Data Not 1.06E 05 Data Not 1.15E 07 Data Not Available - Available Available AG110M 4.99E 03 3.30E 04 9.97E 03 7.21E 03 1.09E 04 Data Not 3.66E 06 Data Not Avail able Available TE127M 2.07E 03 2.73E 04 1.66E 04 6.89E 03 3.75E 04 4.86E 03 1.31E 06' Data Not Availabig TE129M 2.22E 03 6.89E 04 1.41E 04 6.0BE 03 3.17E 04 5.47E 03 1.68E 06 Data Not Available
]
i I 131 1.96E 04 1.06E 03 3.79E 04 4.43E 04 5.17E 04 1.48E 07 Data Not Data Not Available Avail able I 133 5.59E 03 2.15E 03 1.32E 04 1.92E 04 2.24E 04. 3.55E 06 Data Not Data Not Available Available CS134 7.44E 04 1.33E 03 3.96E 05 7.02E 05 1.90E 05 Data Not 7.95E 04 Data Not Available Avail able CS136 5.28E 04 1.43E 03 4.82E 04 1.34E 05 5.63E 04 Data Not 1.17E 04 Data Not Avail able Available l CS137 4.54E 04 1.33E 03 5.48E 05 6.11E 05 1.72E 05 Data Not 7.12E 04 Data Not !
~'
Avail able Available ' BA140 2.89E 03 3.83E 04 5.59E 04 5.59E 01 1.34E 01 Data Not 1.59E 06 Data Not Available Available CE141 1.99E 03 2.15E 04 2.77E 04 1.66E 04 5.24E 03- Data Not 5.16E 05 Data Not Avail able Available CE144 1.76E 05 1.48E 05 3.19E 06 1.21E 06 5.37E 05 Data Not 9.83E 06' Data Not Avail able Available ATTACHMENT 1 PAGE 56 0F 70
I SHUD-NUCLEAR ORGANIZATION NUMBER: AP.310 l REVISION: 4 l OFFSITE DOSE CALCULATION MANUAL PAGE 92 0F 105 TABLE A-34 DISTANCES FOR GASEOUS EFFLUENT PATHHAY EVALUATION (METERS) l RECEPTOR SITE NEAREST NEAREST NEAREST NEAREST NEAREST DIRECTION BOUNDARY RESIDENCE GARDEN MEAT ANIMAL MILK COW MILK GOAT N 658 (1) (1) 440 (1) (1) NNE 670 (1)- (1) 430 (1) (1) NE 792 1430 4830 430 (1) (1) ENE 1185 1140 1140 450 1140 (1) E 3605 (1) (1) 470 (1) (1) ESE 1697 (1) (1) 670 (1) (1) SE 1152 2560 2560 240 (1) (1) SSE 1170 7800 (1) 200 (1) (1) S 1759 6490 (1) 200 (1) . (1) i SSH 1103 2900 5300 200 (1) ! (1) SH 1146 1220 3190 290 3190 L5630 HSH 987 1830 2380 400 3620 ' (1) H 969 3230 3230 510 7740 3230 j HNH 987 4390 4390 440 (1) (1) { NH 795 5330 6750 500 (1) (1) 1 NNW 670 7250 (1) 440 (1) (1) j l (1) Locations, if they exist, are greater than 8,047 meters (5 miles) ) from the Rancho Seco site. ! Additional Locations: Visitor Center E 225 meters 17.9% occupancy factor i Park, Kiosk E 525 meters 41.7% occupancy factor l Harehouse ENE 225 meters 23.8% occupancy factor Design City ENE 250 meters 23.8% occupancy factor i ATTACHMENT 1 PAGE 57 0F 70
i SHUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL Pf_GE 93 0F 105 TABLE A-35 GASEOUS EFFLUENT PATHNAY l l USAGE PARAMETERS {
)
Maximum 1xoosed Individual 1 i Pathway Units Infant Child Teenaaer Adult Fruits, vegetables, grains kg/hr 520 630 520 HiIk 1/yr 330 330 500 310 J Heat, poultry kg/yr 41 65 110 l Inhalation md/yr 1400 3700 8000 8000 l i 1 Averaae Excosed Individual (General Public)(I) i l Pathway Units Child Teenaaer Adult j Fruits, vegetables, grains kg/khr 200 240 190 Milk 1/yr 170 200 100 Heat, poultry k 37 59 95 Inhalation mg/yr
/yr 3700 8000 8000 l
(1) 50 mile population as of 1986 is 2.08E6. For ! later years up to the year 2010, the 50 mile population, P, is found by: l P - 1.79E4Y + 7.85Y2 - 6.44E7 I { where: P - the population for the year of interest Y - the year of interest (i.e.,1995, 1987, etc.) Distribution: Adult 71% Teenager 11% Child 18% ATTACHMENT 1 PAGE 58 0F 70 u______ _ _ _ _ - _ - _ _ _ _
SHUO-NUCLEAR ORGANIZATION NUMBER: AP.310 j OFFSITE DOSE CALCULATION MANUAL ~ 0F 105 TABLE A-36 RADIOACTIVE DECAY CONSTANT 4 (1/liOUR)
]
NUCLIDE DECAY CONSTANT 1H - 3 6.41E-06 4 4BE- 10 4.93E-11 6C - 14 1.38E-08 ' 7N - 13 4.18E+00 9F - 18 3.78E-01 11NA- 22 3.04E-05 ! 11NA- 24 4.61E-02 i ISP 2.02E-03 R 20CA- 41 5.65E-10 21SC- 46 3.45E-04 24CR- 51 1.04E-03 ) 25MN- 54 9.25E-05 t' 25MN- 56 2.70E-01 26FE- 55 - 2.93E-05 26FE- 59 6.48E-04 27CO- 57 1.07E-04 1 27CO- 58 4.07E-04 27C0- 60 1.50E-05 28NI- 59 1.05E-09 28NI- 63 8.24E-07 i 28NI- 65 2.75E-01 1 29CU- 64 5.47E-02 30ZN- 65 1.18E-04 30ZN- 69M 5.04E-02 30ZN- 69 7.31E-01. 34SE- 79 1.22E-09 358R- 82 1.97E-02 358R- 83 2.90E-01 35BR- 84 '1.31E+00 35BR 1.45E-01 37RB- 86 1.54E-03 37RB- 87 1.68E-15 37RB- 88 2.33E+00 : 37RB- 89. 2.73E+00 38SR- 89 5.72E-04 38SR- 90 2.78E-06 '( 38SR- 91 7.31E-02 38SR- 92 2.56E+01 39Y - 90 .1.08E-02 39Y - 91H 8.39E-01 39Y - 91 4.93E-04, , 39Y - 92 1 95E-01 ATTACHMENT I PAGE 59 0F 70 2
> ,T SMUD-NUCLEAR ORGANIZATION NUMBER: APNE6
., REVISION:.4 0FFSITE DOSE CALCULATION MANUAL ^ PAGE 95 0F 105 TABLE A-36 (Continued). ,
RADI0 ACTIVE DECAY CONSTANT (1/ HOUR) ,L NUCLIDE -
.0ECAY CONSTANT 39Y-- 93'.c 6.88E-02 40ZR- 93 5.18E-11 40ZR- 95
. .4.50E-04' 40ZR- 97 4.10E-02 41NB- 93M 5.83E-06 41N8- 95 8.21E-04 41NB 97 5.76E+01 42MO- 93 2.26E-08 42M0- 99 1.05E 43TC- 99M 1.15E-01 43TC- 99 s 3.71E-10 43TC-101 2.93E+00' 44RU-103 7.34E-04 P 44RU-105 1.56E-01 a i 44RU-106 , 7.85E-05 45RH-105 1.97E ,,
46PD-107 1.22E-)1 j > 46PD-109 '3.15E-02 e1 .. 47AG-110M L )5E-04
- 47AG-111 l5.89E-03 Y.
48CD-113M /5.33E-05 J7 ' 48CD-115M ,
.- ! 6f4SE204- * ' I k.? '"
50SN-123 , , ' 2.24E204 'r 50SN-125 3.00E-03 .<<>
' 50SN-126 ill.7.92E-10 L
f . '.!' s 51S8-124 '
'4 4.79E-04 51SB-125 '2.86E-05 5158-126 2.33E-03!
51SB-127 7.49E-03, M 52TE-125M 4.97E-04 52TE-127M 2.65E-04 52TE-127 '7.42E-02 , ; . 52TE-129M 8.60EJ el T". 52TE-129 5.98E-01 ' M! 52TE-131M 2.31E-02 52TE-131 4
. 1.66E+00 A)[a 52TE-132 8.86E-03 ,
52TE-133M' 7.49E-01 ' (, ,' ~' 52TE-134 ,9. 97E-01. ,, 53I -129- 5.04E-12 w. 53I -130 5.62E-02 ,
, i 29 53I -131 3.59E-03 '"
E- X >" 53I -132 : c 3.01E-01 ,i a ATTACHMENT,1 t,
~PAGE-60 0F 70L i
X 04
r s .s SHMS-NUCLEARORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 96 0F 105 TABLE A IMERSION DOSE FACTORS FOR SHIMMING IN CONTAMINATED HATER (MREM /HR PER PCI/ LITER) NUCLIDE SKIN TOTAL BODY TH'- 3 0.0 0.0 48E- 10 o 0.0 0.0 6C - 14 0.0 0.0 7N - 13 0.0 1.90E-06 , 9F - 18 0.0 1.80E-06 ; 11NA- 22 0.0 4.00E-06 j 0.0 11NA- 24 7.80E-06 15P - 32 0.0 6.40E-09 20CA- 41 0.0 7.28E-07 ! 21SC- 46 0.0 3.70E-06 24CR- 51 s 0.0 5.20E-08 .
,~ 25MN- 54 <0.0 1.50E-06 25MN- 56 0.0 3.20E-06 j 26FE- 55. 0.0 6.40E-11 26FE- 59 0. 0, 27CO- 57 0.0 2.20E-06 f 2.20E-07 {
27CO- 58 0.0 1.80E-06 1 27CO- 60 0.0 4.60E-06 1 28NI- 59 28NI- 63 0.0 0.0 2.30E-09 0.0 j 1 28NI- 65 0.0 1.00E-06 ] 29CU- 64 0.0 3.70E-07 l 30ZN- 65 0.0 1.10E-06 . 33ZN- 69M 0.0 7.50E-07 1 Sb7N- 69 0.0 1.60E-09 I l 34SE- 79 0.0 3.40E-11 35B2- 82 0.0 5.30E-06 l 35BR- 3 0.0 1.70E-08 358R- 84 0.0 3.50E-06
, 35BR 0.0 1.40E-08
. 37RB- 86 0.0 1.70E-07 4;
37RB- 87 0.0 1.20E-10 l 37RB- 88 0.0 1.20E-10 l 37RB- 89 0.0 1.20E-06 38SR- 89 0.0 4.50E-06 38SR- 90 0.0 4.60E-09 1 38SR- 91 0.0 1.90E-06 38SR- 92 0.0 2.60E-06 s 39Y - 90 0.0 1.30E ' 39Y - 91H 0.0 0.0 39Y - 91 0.0 6.70E-09 39Y - 92 0.0 4.60E-07 ' , ATTACHMENT 1
'PAGE 61 0F 70
~s ,
0
. \ ,) -'t }
( L_________ _ _ . . _ _ . _ _ _ _ . _ _ _ . . _ _ __..__'s.& _ _ _
5
,y C e' ,,
H l y, s
,7 ll*I>' s A / , , .l ,
/r j j .
/ ..',
., [ } s SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310-i< REVISION:- 4 i 0FFSITE DOSE CALCULATION MANUAL , PAGE 97 0F 105 _ l
, TABLE A-37 (continued) / -
IMERSION DOSE FACTORS FOR SHIMMING IN CONTAMINMED MATER. (MREM /HR PER PCI/ LITER) { # j 1, i
/, SKIN s ,
NUCLIDE 10TKJ BODY' l 6 lL 39Y - 93 4 i l0.0. ,/J 1.90E-07
' 40ZR- 93 i 4.0 J /' O.0 y 40ZR- 95 0.0 1.50E-06 '
40ZR- 97 0.0 1.50E-06 3' [t ~ 41NB- 93M 0.0 0.0 L i 41NB- 95 0.0 0.0 1
! '41NB- 97 0.0 1.20-06E b ,
-l o 42MO- 93 0.0 1.24E-09 l 42M0- 99 0.0 0.0 s i
43TC- 99M ' 0.0 2.40E-07' 4 43TC- 99 O.0 1.30E-10 43TC-101 O.0 6.80E-07 :- 44RU-103 0.0 0.0 44RU-105 0.0 1.20E-06 44RU-106 , 4 0.0' (+ 0.0 i 45RH-105- { < 0.0 1.70E-07 - 46PO-107 .e 0. 0 N 0.0- J't 46PO-109 O.0 s A 9.30E-09 ft > 47AG-11GM 0.0 ' '4.90E-06 k 47AG-111 " 0.0 .f. 80E-08 48CD-113M .h 0.0 5.90E-10 1
; 48CD-115M "
.- 0.0 0.0 50SN-123 0.0 4 0.0. b 50SN-125
- 0.0 0.0 l'.60E-07 h
'?
50SN-126 1.80E-08
' S 51SB-124 51SB-125 0.0 0.0 ,
3.60E-06 7.80E-07
.h
'I d
0.0
- r'
'"I 51SB-126 51SB-1E7 d 0.0
.< ( 2.40E-06 1.50E-06 7
g'j r l 52TE-125M 0.0 - < 3.69E-09 52TE-127M 0.0 2.60E-10 r 52TE-127. 0.0 A ' '3 2.80E-09 " " "4 (l ' > 52TE-129M 0.0 9- 2.10E-07 ,
< 52TE-129 0.0 1.90E-07 f '
52TE-131M 0.0 2.20E 52TE-131 0.0 :7.40E-07 52TE-132 0.0 4.00E-07 t 52TE-133M S2TE-134 0.0 0.0 4.40E-06 2.50E-07 [f' 53I -129 0.0 1.70E-08 d j{ 53I -130. 0.0 3.90E-06 1
/ 53I~-131 0.0 7.80E-07 ,s 1 I, '
44 '>l 53I -132 0.0- 0.0 i .
// A'y 53I -133 0.0 9.60E-07 Ml /.py ,
j- h r, ATTACHMENT 1
') PAGE 62 0F 70'
q SMUD-NUCLEAR ORGANIZATION -NUMBER: AP.310 REVISION: 4
, OFFSITE DOSE CALCULATION MANUAL PAGE 98 0F 105 -t TABLE A-37 (continued)
> IMERSION DOSE FACTORS FOR SHIMMING IN CONTAMINATED HATER i (MREH/HR PER PCI/ LITER) l NUCLIDE SKIN TOTAL BODY 53I -134 0.0 4.20E-06 53I -135 0.0 0.0 55CS-134M 0.0 1.60E-07 55CS-134 0.0 2.90E-06 55CS-135 0.0 6.60E-11
,! 55CS-136 0.0 4.10E-06 ,
55CS-137 0.0 1.00E-06 I
- 55CS-138 0.0 4.00E-06 l 55CS-139 0.0 1.70E-06 l 56bA-139 0.0 7.70E-08 l 56BA-140 0.0 4.90E-07 ^
56BA-141 0.0 1.10E-06 56BA-142- 0.0 2.20E-06 d 57LA-140 0.0 0.0 57LA-141 0.0 5.10E-08 l
'V 57LA-142- 0.0 '4.50E-06 q i 58CE-141 0.0 '1.30E 58CE-143 0.0 5.70E-07 l
/.
58CE-144 0.0 8.60E-08 59PR-143 0.0 0.0 l 59PR-144. 0.0 .5360E-08; t
, 60ND-147 0.0 ;0.0 61PM-147 0.0 7.50E-11 91PM-148M 0.0 3.72E-06 61PM 148 0.0 1.10E-06 61PM-149 0.0 .1.50E-08 l 61PM-151 0.0 5.00E-07 62SM-151 0.0 2.60E-10 62SM-153 0.0 6.50E-08 63EU-152 0.0 1.80E-06 l 63EU-154 0.0 2.10E-06 l 63EU-155 0.0 9.00E-08 63EU-156 0.0 .2.10E-06 65TB-160 0.0 2.36E-06 67HO-166M 0.0 2.40E-06 1 74H -181 0.0 5.30E-10 74H -185 0.0 3.20E-10
,. r - , , 74H -187 0.0' 8.30E-07 y' 82PB-210 0.0 3.00E-09 0.0 2.70E-09~ J
'82BI-210M C t 0.0 1.50E-11 84PO-210
, $ ^' 88RA-223 , 0.0 4.00E-07 4-[>
- l. ATTACHMENT 1
-PAGE 63 0F 70-l _ - _ _ _ _ - _ _ _
4 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 i REVISION: 4 0FFSITE DOSE CALCULATION MANUAL- PAGE 99 0F 105 TABLE A-37 (continued) IMERSION DOSE FACTORS FOR SHIMMING IN CONTAMINATED HATER (MREM /HR PER PCI/ LITER) NUCLIDE SKIN TOTAL BODY 88RA-224 0.0 2.60E-06 88RA-225 0.0 1.90E-08 88RA-226 0.0 1.80E-06 88RA-228 0.0 3.40E-06 89AC-225 0.0 4.00E-07
-89AC-227 0.0 4.40-07 90TH-227 0.0' 1.30E-07 90TH-228 0.0 2.60E-06 90TH-229 0.0- 5.80E-07 g 90TH-230 0.0 1.80E-06 90TH-232 0.0 3.40E-06 90TH-234 0.0 2.80E-08 t 91PA-231 0.0 5.00E-07 e.
91PA-233 0.0 3.30E-07 i 920 -232 0.0 4.56E-10 92U -233 0.0' 5.90E-07 c 92U -234 0.0 8.50E-10 l 92U -235 0.0 2.70E-07 ! 92U -236 0.0 4.50E-12 j 92U -237 0.0 2.60E-07 l 92U -238 0.0 2.80E-08 93NP-237 0.0 3.60E-07 93NP-238 0.0 '/.70E-07 93NP-239 0.0 2.40E-07 94PU-238 0.0 0.0 94PU-239 0.0 0.0 94PU-240 0.0 0.0 94PU-241 0.0 0.0 94PU-242 0.0 -1.10E-10 94PU-244 0.0 1.256E-07 b 95AM-241 0.0 3.90E-08 95AM-242M 0.0 5.10E-09 0.0 95AM-243 3.10E-07 96CM-242 0.0 3.40E-1G 96CM-243 0.0 2.30E-07 j 96CM-244 0.0- 2.60E-10 j 96CM-245 0.0 9.60E-08 ' 96CM-246 0.0 1.10E-10' 96CM-247 0.0 4.70E-07 96CH-248 0.0 3.09E-07 98CF-252 0.0 1.40E-05 j ATTACHMENT 1 PAGE 64 0F 70
SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 100 0F 105 TABLE A-38 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- Total Body Skin Gamma Air: Beta Air Oose Factor Oose Factor Oose Factor Oose Factor Kj Lj Hj Nj (mrem /yr (mrem /yr (mrad /yr (mrad /yr. ;
Radionuclides per uCi/m3 ) per uCi/m3 ) .per uC1/m3 ) per uCi/m3) .i Kr-83m 7.56E-02 --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03- 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37t+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 ) Xe-131m 9.15E+01 4.76E+02 .1.56E+02 1.11E+03 I 1 Xe-133m 2.51E+02 9.94E+02 3.27E+02- 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02-Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 ! Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 I Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 l Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 1 1 I
*The listed dose factors are for radionuclides that .may be detected in gaseous effluents. ,
1 ATTACHMENT 1 PAGE 65-0F 70
.I
I SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: -4 1 0FFSITE DOSE CALCULATION MANUAL PAGE 101 0F 105 1 TABLE A-39' I INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED) NUCLIOE BONE LIVER TOTAL THYROID KIDNEY LUNG GI-LLI j BODY 531 -131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.0 7.56E-07 l 531 -133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.0 1.54E-06 , 1H - 3 0.0 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 l 6C - 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E 24CR- 51 0.0 0.0 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 1 25MN- 54 0.0 1.81E-05 3.56E-06 0.0 3.56E-06'7.14E-04 5.04E-06 ' l 26FE- 55 1.41E-05 8.39E-06 2.38E-06 0.0 0.0 6.21E-05 7.82E-07 I 26FE- 59 9.69E-06 1.68E-05 6.77E-06 0.0 0,0 7.2SE-04 1.77E-05 l 27CO- 58 0.0 8.71E-07 1.30E-06 0.0 0.0 5.55E-04 7.95E-06 j 27CO- 60 0.0 5.73E-06 8.41E-06 0.0 0.0 3.22E-03 2.28E-05 30ZN- 65 1.38E-05 4.47E-05 2.22E-05 0.0 2.32E-05 4.62E-04 3.67E'05 385R- 89 2.84E-04 0.0 8.15E-06 0.0 0.0 1.45E-03 4.57E-05 :! 385R- 90 1.96E-02 0.0 1.31E-03 0.0 0.0 8.03E-03:9.36E-05 i 40ZR- 95 8.24E-05 1.99E-05.1.45E-05'0.0 2.22E-05 1.25E-03 1.55E-05 5158-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08.0.0 1.89E-03 4.22E-05 55CS-134 2.83E-04 5.02E-04 5.32E-05 0.0 1.36E-04 5.69E-05 9.53E-07 55CS-136 3.45E-05 9.61E-05 3.78E-05 0.0 4.03E-05 8.40E-06 1.02E-06 55CS-137 3.92E-04 4.37E-04 3.25E-05 0.0 1.23E-04 5.09E-05 9.53E-07 56BA-140 4.00E-05 4.00E-08 2.07E-06 0.0 9.59E-09 1.14E-03 2.74E-05 58CE-141 1.98E-05.1.19E-05 1.42E-06 0.0 3.75E-06 3.69E-04 1.54E-05 58CE-144 2.28E-03 8.65E-04 1.26E-04 0.0 .3.84E-04-7.03E-03 1.06E-04 1 I i I
-l
-i 1
l
'l ATTACHMENT 1 PAGE 66 0F 70 a a
1 SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4-0FTSITE DOSE CALCULATION MANUAL PAGE 102 0F 105-TABLE A-40 l l INGESTION DOSE FACTORS FOR INFANT
, (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER TOTAL- THYROIO KIONEY LUNG 1 GI-LLI: BODY I 531 -131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.0 1.51E-06. 531 -133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.0 3.08E-06 IH - 3 0.0 ~3.08E-07 3.08E-07.3.08E-07 3.08E-07 3.08E-07 3.08E-07 6C - 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 24CR- 51 0.0 0.0 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07' 25MN- 54 0.0 1.99E-05 4.51E-06 0.0 4.41E-06 0.0 7.31E-06 26FE- 55 1.39E-05 8.98E-06 2.'40E-06 0.0 0.0 4.39E-06 1.14E-06 26FE- 59 3.08E-05 5.38E-05 2.12E-05 0.0 0.0 1.59E-05 2.57E-05 27CO- 58 0.0 3.60E-06 8.98E-06 0.0 0.0 0.0 8.97E-06t 27CO- 60 0.0 1.08E-05 2.55E-05 0.0- 0.0 0.0 2.57E-05 30ZN- 65 1.84E-05 6.31E-05 2.91E-05 0.0 3.06E-05 0.0 5.33E-05 385R- 89 2.51E-03 0.0 7.20E-05 0.0 0.0 0.0 5.16E-05. 385R- 90 1.25E-02 0.0 3.37E-03 0.0 0.0 0.0 2.31E-04 40ZR- 95 2.06E-07 5.02E-08 3.56E-08 0.0 5.41E-08 0.0 ' 2.50E-05 5158-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.0- -1.34E-05 6.60E-05' 55CS-134 3 77E-04 7.03E-04 7.10E-05 0.0 1.81E-04 7.42E-05 1.91E-06 55CS-136 4.59E-05'1.35E-04 5.04E-05 0.0 5.38E-05 1.10E-05 2.05E-06 55CS-137 1.64E-04 6.64E-05 1.91E-06:
~
5.22E-04 6.11E-04 4.33E-05 0.0' 56BA-140 1.71E-04 1.71E-07 8.81E-06 0.0 4.06E-08 1.05E-07-4.20E-05 58CE-141 ' 7.87E-08 4.80E-08 5.65E-09 0.0 1.48E-08 0.0 2.48E-05 58CE-144 2.98E-06 1.22E-06 1.67E-07 0.0- 4.93E-07 0.0- I'. 71 E-0 4 ' ATTACHMENT 1 PAGE 67 0F 70 1
. _ _ _ = _ - _ _ _ __ _ - - _ .
i
.1, SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 ['
REVISION: 4 - 0FFSITE DOSE CALCULATION MANUAL PAGE 103 0F 105 TABLE A-41 H INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED) NUCLIOE BONE LIVER TOTAL THYROIO KIONEY LUNG GI-LLI BODY 53I -131 1.72E-05 1.73E-05 9.83Ei O6 5.72E-03 2.84E-05 0.0 1.54E-06 531 -133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.0 2.95E-06 IH - 3 0.0 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 6C - 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 24CR- 51 0.0 0.0 8.90E-09.4.94E-09 1.35E-09 9.02E-09 4.72E-07 i 25MN- 54 0.0 1.07E-05 2.85E-06 0.0 3.00E-06 0.0 8.98E-06 26FE- 55 1.15E-05 6.10E-06 1.89E-06 0.0 0.0 3.45E-06 1.13E -i 26FE- 59 1.65E-05 2.67E-05 1.33E-05 0.0 0.0 7.74E-0G 2.78E-05 27CO- 58 0.0. 1.80E-06 5.51E-06 0.0 0.0- 0.0 1.05E-05 27CO- 60 0.0 5.29E-06 1.56E-05 0.0 0.0 0.0. 2.93.E-05 30ZN- 65 1.37E-05 3.65E-05 2.27E-05 0.0- 2.30E-05_0.0 6.41E-06 : 38SR- 89 1.32E-03 0.0 3.77E-05 0.0 0.0 0.0 5.11E-05 385R- 90 1.13E-02 0.0 3.03E-03 0.0 0.0 0.0 2.29E-04 40ZR- 95 1.16E-07 2.55E-08 2.27E-08 0.0 3.65E-08 0.0 :2.66E-05 . 5158-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.0 6.16E-06 6.94E-05 55CS-134 2.34E-04 3.84E-04 8.10E-05 0.0 1.19E-04 4 27E-05 2.07E-06 ' 1 55CS-136 2.35E-05 6.46E-05 4.18E-05~0.0 3.44E-05 5.13E-06 2.27E-06 55CS-137 3.27E-04 3.13E-04 4.62E-05 0.0 1.02E-04 3.67E-05 1.96E-06 l 56BA-140 8.31E-05 7.28E-08 4.85E-06 0.0 2.37E-08 4.34E-08 4,21E-05 d 58CE-141 3.97E-08 1.98E-08 2.94E-09 0.0 8,68E-09 0.0 2.47E-05 ) 58CE-144 2.08E-06 6.52E-07 1.11E-07'O.0 3.61E-07 0.0 1.70E-04 $ i 1 1 i l l
~ATTACHMENT 1 PAGE 68 0F 70
i l SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 i REVISION: 4 i 0FFSITE DOSE CALCULATION MANUAL PAGE 104 0F 105 ! TABLE A-42 INGESTION DOSE FACTORS FOR TEENAGER l (MREM PER PCI INGESTED) l NUCLIDE BONE LIVER TOTAL THYROID KIONEY LUNG GI-LLI BODY 531 -131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.0 1.62E-06 53I -133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.0' 2.58E-06 1H - 3 0.0 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 6C - 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 24CR- 51 0.0 0.0 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 25MN- 54 0.0 5.90E-06 1.17E-06 0.0 1.76E-06 0.0- , 1.21E-05 26FE- 55 3.78E-06 2.68E-06 6.25E-07 0.0 0.0 1.70E-06 1.16E-06 26FE- 59 5.87E-06 1.37E-05 5.29E-06 0.0 0.0 4.32E-06 3.24E-05 27CO- 58 0.3 9.72E-07 2.24E-06 0.0 0.0 0.0 1.34E-05 27CO- 60 0.0 2.81E-06 6.33E-06 0.0 0.0 0.0 3.66E-05 30ZN- 65 5.76E-06 2.00E-05 9.33E-06 0.0 1.28E-05 0.0 8.47E-06 385R- 89 4.40E-04 0.0 1.26E-05 0.0 0.0 0.0 5.24E-05 385R- 90 4.48E-03 0.0 1.20E-03 0.0 0.0 0.0 2.33E-04 40ZR- 95 4.12E-08 1.30E-08 8.94E-09 0.0 1.91E-08 0.0 3.00E-05 5158-124 3.87E-06 7.13E-0E 1.51E-06 8.78E-09 0.0 3.38E-06 7.80E-05 55CS-134 8.37E-05 1.97E-04 9.14E-05.0.0 6.26E-05 2.39E-05 2.45E-06 55CS-136 8.59E-06 3.38E-05 2.27E-05 0.0 1.84E-05 2.90E-06 2.72E 55CS-137 1.12E-04 1.49E-04 5.19E-05 0.0 5.07E-05 1.97F-05'2.12E-06 568A-140 2.84E-05 3.48E-08 1.83E-06 0.0 1.18E-08'2.34E-08 4.38E-05 , 58CE-141 1.33E-08 8.88E-09 1.02E-09 0.0 4.18E-09 0.0 2.54E-05 58CE-144 6.96E-07 2.88E-07 3.74E-08 0.0 1.72E-07 0.0 1,75E-04 ATTACHHENT 1 PAGE 69 0F 70
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'SMUD-NUCLEAR ORGANIZATION NUMBER: AP.310 REVISION: 4 0FFSITE DOSE CALCULATION MANUAL PAGE 105 0F 105 TABLE A-43 INGESTION DOSE FACTORS FOR ADULT (MREM PER PCI INGESTED) i NUCLIDE BONE LIVER TOTAL THYROIO KIONEY LUNG GI-LLI 800Y 53I -131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.0 1.57E-06 531 -133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.0 2.22E-06 1H - 3 0.0 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 6C - 14 2.84E-06 5.68E-07 5,68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 24CR- 51 0.0 0.0 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 25MN- 54 0.0 4.57E-06 8.72E-07 0.0 1,36E-06 0.0 1.40E-05 26FE- 55 2.75E-06 1.90E-06 4.43E-07 0.0 0.0 1.06E-06 1.09E-06 i
26FE- 59 4.34E-06 1.02E-05 3.91E-06 0.0 0.0 2.85E-06 3.40E-05 27CO- 58 0.0 7.45E-07 1.67E-06 0.0 0.0 0.0 1.51E-05 l 27CO- 60 0.0 2.14E-06 4.72E-06 0.0 0.0 0.0 4.02E-05 ; 30ZN- 65 4.84d-06 1.54E-05 6.96E-06 0.0 1.03E-05 0.0 9. 70E-06 ' 385R- 89 3.08E-04 0.0 8.84E-06 0.0 0.0 0.0 4.94E-05 385R- 90 3.84E-03 0.0 1.03E-03 0.0 0.0 0.0 2.19E-04 40ZR- 95 3.04E-08 9.75E-09 6.60E-09 0.0 1.53E-08 0.0 3.09E-05 5158-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.0 2.18E-06 7.95E-05 55CS-134 6.22E-05 1.48E-04 1.21E-04 0.0 4.79E-05 1.59E-05 2.59E-06 55CS-136 6.51E-06 2.57E-05 1.85E-05 0.0 1.43E-05 1.96E-06 2.92E-06 55CS-137 7.97E-05 1.09E-04 7.14E-05 0.0 3.70E-05 1.23E-05 2.11E-06 56BA-140 2.03E-05 2.55E-08 1.33E-06 0.0 8.67E-09 1.46E-08 4.18E-05 58CE-141 9.36E-09 6.33E-09 7.18E-10 0.0 2.94E-09 0.0 2.42E-05 58CE-144 4.88E-07 2.04E-07 2.62E-08 0.0 1.21E-07 0.0 1.65E-04 ATTACHMENT 1 PAGE 70 0F 70 L -- - - - _ __}}