ML20246L822
| ML20246L822 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/31/1989 |
| From: | Randolph G UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20246J712 | List: |
| References | |
| PROC-890531, NUDOCS 8909070049 | |
| Download: ML20246L822 (116) | |
Text
- - _ -
EMac 15 CALLAWNY PLANT l
OFFSITE DOSE CALCULATION MANUAL May,1989 JM- :ibe
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SON R ov. 6 Etscraic 53 CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL i
May,1989 INFORMATION ONLY/
UNCONTROLLED COPY
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Approved:
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$s Chadimak, Onslie Revfew Committee ORC meeting number i
R evie w e d:
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.Sup MnidncintTHeaith enysics l
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Prepared by:
M A';A -
Supervisor, HP Technical Support g\\tp1 Cg ISSUED l
MAY 191939 l
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2 This document contains the'following:
Pages-1-
through 99-Tables 1
through.
12 y
Figures 4.1, 5.1A, 5.1B,'5.2A, S.23, 5.3 W
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CALLAWAY PLANT,
.OFFSITE DOSE CALCULATION MANUAL Rev..
6 Table of Contents.
Page 1-. 0 L
. PURPOSE:AND SCOEE 1
2.0 LIQUID EFFLUENTS 2'
p,
2.1 TECHNICAL SPECIFICATION
.3.3.3.10 2
2.2
~ LIQUID EFFLUENT MONITORS-2' 2.3 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS 5
2.4
. LIQUID EFFLUENT' CONCENTRATION
. MEASUREMENTS 10
- 2.4.1 Technical Specification 3.11.1.1 10
- 2.4.2 Liquid Effluent Concentration Measurements 11 LtO 2.5 DOSE DUE TO LIQUID l
D EFFLUENTS 11
?
2.5.1 Technical Specification 3.11.1.2 11 2 5.2
~
The Maximum Exposed Individual 12 s
2.5,3 Calculation of Dese from y
Liquid Effluents 12.
1 p
2.5.4 Summary, Calculation of Dose Due to Liquid Effluents 15 J
2.6 LIQUID RADWASTE TREATMENT SYSTEM 19 2. 6 ~.1 Technical-Specification 3.11.1.3 19 2.6.2 Operability of the Liquid Radwaste-Treatment System 19 3.0 GASEOUS EFFLUENTS 20 3.1 TECHNICAL SPECIFICATION 3.3.3.10 20 N_
W W
u_2.__:_u_.__=-_._-_--_---_--
CALLAWAT PLANT-OFFSITE DOSE CALCULATION' MANUAL Rev. 6'
.,.p -
Table of Contents (continued)
= <,
,Page-3.2 TECHNICAL SPECIFICATION 3.11.2.1 20
- 3.3 GASEOUS EFFLUENT MONITORS
'20
'3'4 CALCULATION' F' GASEOUS EFFLUENT _ MONITOR SETPOINTS 23 3.4.1 Total Body Dose Rate Setpoint Calculations
- 2-4 3.4.2-Skin Dose Rate Setpoint
. Calculations
- 26 3.4.3 Gaseous Effluent Monitors Setpoint Determination 27 3.4.4
'Sumrsry,' Gaseous Effluent Monitors Set;; int Determination 29 3.5 CALCULATION OF DOSE FROM GASEOUS EFFLUENTS 29
/~
3.5.1 Calculation of Dose Rate 29
(
3.5.1.1
' Noble Gases 29 3.5.1.2 Ra *2onuelides other 7han Neble Laces 31 3.5.2 Inddvidual Dese Dne,to Noble Gases 36 L
3.5.2.1 Technical Specification 3.11 2.2 36 3.5.2.1 1 Noble Gases 36 3.5.2.2 Technical Specifiention 3.11.2.3 3B 1
3.5.2.2.1 Radionuclides Other Than Noble-Gases 38
~
3.6 GASEOUS RADWASTE TREATMENT SYSTEM 60 3.6.1 Technical Specification 3.11.2.4 60
- 3.6.2 Description of the Gaseous Radwaste Treatment System 60 C.
- mm_m
___.._.-_______._____m_____________.m._
g
. CALLAWAY PLANT?
OFFSITE DOSE CALCULATION MANUAL Rev.'6-
-Table of Contentt-(continued)
Pace
'3.6.3' operability of the' Gaseous Radwaste Treatment Syjtem 61:
4.0 DOSE AND' DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 62 4.1 TECHNICAL SPECIFICATION 3.11.4 62 4.2 CALCULATION OF DOSE AND'
' DOSE' COMMITMENT FROM. URANIUM FUEL CYCLE. SOURCES 62 4.2 1
-Identification of the MEMBER 63 OF.THE PUBLIC
- 4.2.2-Total Dose to the Nearest Resident 63 4.2.3 Total Dose to the Critical Receptor 64 Within the SITE BOUNDARY 5.O.
RADIOLOGICAL ENVIRONMENTAL MONITORING 68
..3 l
Q.-
5.1 TECHNICAL SPECIFICATION 3.12.1 68
5.2 DESCRIPTION
OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 68 5.3 PERFORMANCE TEST 7.NG OF EIT/IRONMENTAL 69 THERMOLUl!INESCENCE DOSIMETERS 6.0 DETERMINATION OF ANNUAL AVERACE
(_
AND SHORT TERM ATMOSPHERIC
' DISPERSION PARAMETERS 82 i..
6.1 ATMOSPHERIC DISPERSION PARAMETL"RS 82 g<
6.1.1 Long-Term Dispersion Estimates 82 6.1.2~
Determination of Long-Term Dispersion Catimates for Special Receptor Locations 83 6.1 :. 3 Short-Term Dispersion Estimates 83 7.0 S_EMI-ANNUAL RADIOACTIVE EFFLUENT 90 RELEASE REPORT iii hmm____.____.__._.______a___-_.____.-_____u m
O d
CALLAWAY PLANT OFFSITE DOSE. CALCULATION MANUAL Rev. 6 Table'of Contents (continued)
Pacre 8.O IMPLEMENTATION OF ODCM METHODOLOGY.
92 9.O REFERENCES 93 r
t
'm
.iv.
CALLAWAY PLAht 0FFS!TE DOSE CALCULATION
' MANUAL Rev. 6 l
List of Ficures Figure 4.1
. Site' Area Closed to Public Use l..
Figure 5.1A Airborne & TLD Sanpling Network
\\
l.;
Figura 5.1B Airborne & TLD Sampling Network Figttre 5.2A Location of Acuatic Sampling Stations Figure 5.2B Location.of Aquatic Sampling Stations Figure 5.3
-Food Products Sampling-Locations P.
1:
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l[
I
-V-L2:___--____-_._____-________--
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 List of Tables Page Table 1 Ingestion Dose Commitment Factor (Agy) for Adult Age Group 16 Table 2 Bioaccumulation Factor (BF ) Used g
in the Absence of Site-Specific Data 18
. Table 3 Dose Factors for Exposure to A Semi-Infinite Cloud of Noble Gases 28 Table 4 Dose Parameter (Pg) for Radio-nuclides other Than Noble Gases 33 Table 5 Pathway Dose Factors (R ) for g
Radionuclides Other Than Noble Gases 42 Table 6 Radiological Environmental Monitoring Program 70
. Table 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 78 Table 8 Maximum Values for the Lower Limits of Detection 79 Table 9 Highect Annual A terage Atmospheric Dispersion Parataeters - Radwasce Building Vent 36 Tr.ble 10 Highest Annual Average Atmospheric Dispersion Parameters ~ Unit 'sent 87 Table it Short Term Dispersion Parsmeters 52 Iable 12 Application of Atmospheric Lispersion Parameters 89 l
-vi-
CALLAWAT PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 Record of Revisions Revision Reason Number-Date for Revision Rev. O March 1983 Rev. 1 November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments Rev. 2 March 1984 Revised to incorporate NRC Staff comments Rev. 3 June 1985 Revised to incorporate errata iden-tified by ULNRC-803 and changes to the Environmental Monitoring
/
Program.
Incorporate I-sults of 1984 Land use Census.
Rev. 4 February 1987 Minor clarifications, incorporated 31-day projected dose _ methodology.
Change in the utilization of areas within the Site Boundary.
Rev. 5 January 1980 Minor clarifications, revised deurriptions of liquid and gaseous rad monitors, revised liquid set-point methodology to incorporate monitor background, revised dose calculations f or 40CFRLEO require-i ments, Fevised Table 6 and Figures 5.1A and 5.13 to refine descrip-ticLs of environmental TLD sta-tions, incorporated description of environmental TLD testing required by Reg. Guide 4.13, ravised Tables 1, 2, 4,
and 5 to add addi-tional nuclides, deleted redundant material from Chapter 6.
l
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CALLAWAY PLANT OFFSITE DOSE CALCULAT10N MANUAL Rev. 6 1 Rev. 6 May 1989 Revised methodology for calculating l
maximum permissible liquid effluent-1 discharge rates and liquid effluent l
monitor setpoints, provided metho-l dology for calculating liquid ef-l fluent monitors response correction l
factors, provided an. enhanced I
description of controls on liquid l
monitor background limits, provided I
additional liquid & gaseous dose l
conversion factors and bioaccumula-l tion factors (Tables 1, 2, 4 & 5),
'l provided description of the use of l
the setpoint required by Specifica-l tion 4.9.4.2 during Core Altera-l tions, added discussion of gasecus l
& liquid monitor setpoint selection
.l in the event that the sample' con-l tains no detectable activity, added I
minimum holdup requirements for l
Waste Gas Decay Tanks, revised l
dispersion parameters & accompa-l nying description per FSAR Change
,_ l Notice 88-42.
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l
-viii-
CALLAWAY PLANT OFFSITE DOSE CALCULAT!ON MANUAL Rev. 6 y
l.0 - PURPOSE AND SCOPE f
The.Offsite Dose Calculation Manual'(ODCM) describes the methodology and parameters used 'in the calettlation
- of offsite doses and dose rates due to radioactive 3
liquid anc gaseous' effluents and:in the calculation of-
' liquid:and gaseous effluent monitoring ~ instrumentation alarm / trip.setpoints.. The ODCM.also contains a list and description of the specific sample' locations for-
~
the radiological environmental monitoring program.
- Changes in,the calculational _ methodologies or paramet--
ers;will'be incorporated into the ODCM rnd documented-in the. Semi Annual Radioactive Effluent' Release: Report.
The ODCM.does not replace any station tmpiementing
- procedures.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 2.0 LIQUID EFFLUENTS 2.1 Technical Specification 3.3.3.9 e
The radioactive liquid effluent monitoring instruments-tion channels shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Technical Specification 3.11.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be ad-justed to the values determined in accordance with the methodology and parameters in the ODCM.
2.2 Liquid Effluent Monitors Gross radioactivity monitors which provide for au-tomatic termination of liquid effluent releases are present on the liquid effluent lines.
Flow rate meas-urement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown).
Setpoints, precautions, and limitations applicable to the operation of the Callaway Plant liquid effluent monitors are provided in the appropriate Plant
('
l Procedures.
Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding
,~'
the Maximum Permissible Concentration (MFC) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA.
The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measur-ing devices must satisfy the following equation:
l cf
~
~
C F+f (2.1)
Where:
C=
the liquic; effluent concentration limit (MPC) implementing Technical Specification 3.11.1.1 for the sits in (uCIAr.l'....
m_A__.mm._
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 c=
The setpoint, in (uCi/ml), of the radioactiv-ity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, l
which is inversely related to the volumetric l
flow of the effluent line and.directly related to the volumetric flow of the dilution stream plus.the effluent stream, represents a value, which, if exceeded, would result in concentra-tions exceeding the limits of 10 CFR Part 20 in the UNRESTRICTED AREA.
f=
The flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.
F=
The dilution water flow setpoint as measured prior to the release point, in volume per unit time.
{If (F) is large compared to (f), then F + E = Z).
(Ref. 9.8.1)
If no dilution is provided, then c < C.
The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River.
Normally, the dilution flow is obtained from the cooling tower blowdown, but should this become unavailable, the plant water treatment facility sup-plies the necessary dilution flow via a bypass line.
The batch release limiting concentration (c) which cor-responds to the liquid radwaste effluent line monitor setpoint is to be calculated using methodology from the expression above.
i 6
, 1 L_ __
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 Thus, the expression for determining the setpoint on the liquid radwaste effluent line monitor becomes:
e5 C(F + f)
(vCi/ml) f (2.2)
The alarm / trip setpoint calculations are based on the minimum dilution flow rate (cooling tower blowdown, 5000 gpm), the maximum effluent stream flow rate, and the actual isotopic analysis.
Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway.
The determination and usage l of the allocation factor is discussed in Section 2.3.
l In the event the alarm / trip setpoint is reached, an j evaluation will be performed using actual dilution and l effluent flow values and actual isotopic analysis to l ensure that Technical Specification 3.11.1.1 limits were not exceeded.
2.2.1 Continuous Liquid Effluent Monitors The radiation detection monitors associated with conti-nuous liquid effluent releases are (Ref.
9.6.1, 9.6.2):
Monitor I.D.
Description EM-RE-52 Steam Generator Blowdown Discharge Monitor LE-RE-59 Turbine Building Drain Monitor l
1 !
l 1
l
j i
CALLAWAY PLANT-OFFSITE DOSE CALCULATION MANUAL ^
Rev. 6 1
v nes o et ity has be ee ed by he associated effluent radiation-monitor or by laboratory analysis.
The sampling frequency, minimum analysis frequency, and type of analysis performed are as per.
l Technical Specification Table 4.11-1.
Since the Tur-l.bine Building Drain is not a designated liquid radioac-l tive effluent discharge point, its setpoint is esta-l-blished as a function of background.
I 2.2.2 Radioactive Licuid Batch Release Effluent Monitors The two radiation monitors which are associated with the liquid effluent batch release systems are (Ref.
9.6.4, 9.6.5):
MONITOR I.D.
Description HB-RE-18 Liquid Radwaste Discharge Monitor 7
HF-RE-45 Secondary Liquid Waste System Monitor l These effluent streams are normally considered to be I radioactive.
The sampling frequency, minimum analysis I frequene and the type of analysis performed are as l per Techi. sal Specification Table 4.11-1.
l 2.3 Calculation of Licuid Effluent Monitor Setooints The dependence of the setpoint (c), on the radionuclides distribution, yields, calibration, and monitor paramet-ers, requires that several variables be considered in setpoint calculations.
(Ref. 9.8.1)...
_m__ _ _. __ _
CALLAWAT PLANT OFFSITE; DOSE' CALCULATION MANUAL'.
-Rev. 6 F
~ l.2.3.'1l Calculation of-the MPC Sum The isotopic concentration of the release (s) being con-sidered must be determined.
This is obtained.from:the
- l analyses required per Technical Specifications l Table 4.11-1, and is used.to calculate an MPC sum:
l MPCSUM =
l (I(C )f (MPC )g)+(C,/MPC,)+(C,/MPC,)+(C /MPC )+(C /MPCg) (2.3)
/
g g
t f
l 1
l Where:
I l (C )g =
the concentration (Cg) of each measured gamma g
. I emitting nuclide, i observed by gamma-ray y'
spectroscopy of the waste sample.
'~
C,*
=
the measured concentration (C,) of alpha emit-ting nuclides observed by gross alpha analysis.
C,*
=
the measured concentrations of Sr-89 and Sr-90 l
as determined by analysis of the quarterly composite sample.
C*=
the measured concentration of E-3 in t
l liquid effluents.
C*=
the measured concentration of Fe-55 in liquid f
waste as determined by analysis of the quar-terly composite sample.
I
- Values for these concentrations will be based on previous composite sample analyses as required by Tech-l nical Specifications Table 4.11-1.
4 O
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I CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6
,P w
= are the limiting g
f concentrations of the appropriate radionuclides from 10CFR 20, Appendix B, Table II, Column 2.
For dis-solved or entrained noble gases, the concentration
~
shall be limited to 2x10 ' vC1/ml total activity.
l SF =
the safety factor; an administrative factor used j
to compensate for statistical fluctuations and l
errors of measurements.
This factor also l
provides a margin of safety in th= calculation i
of the maximum liquid effluent discharge flow-I rate (f 33).
The value of SF should be $1.
l For the case MPCSUM $ 1, the monitor tank effluent l concentration meets the limits of Technical Specifica-tion 3.11.1.1 without dilution and the effluent may be l released at any desired flow rate.
If MPCSUM > 1 then dilution is required to ensure compliance with Techni-cal Specification 3.11.1.1 concentration limits.
If simultaneous releases are occuring or are anticipated, l an allocation fraction, N, must be applied so that available dilution flow may be apportioned among
] simultaneous discharge pathways.
The value of N may be l any value between 0 and 1 for a particular discharge l point, provided that the sum total allocation fractions l for all discharge points must be 5 1.
l 7-1 1
CALLAWAY PLANT-OFFSITE DOSE CALCULATION MANUAL Rev.
6'
~
. ]I2.3.2 Calculation of the Maximum Permissible Liquid l
Effluent Discharce Flowrate l' The maximum. permissible. liquid effluent discharge'_. flow-l~ rate is calculated by:
l f,,x 1 (F t f ) (SF) (N) + (MPCSUM)
(2.4) p
. ] Where:
. If Maximum permissible liquid effluent discharge
.=-
max 1.
flowrate, in (gallons / minute);
l f
=
the expected undiluted liquid effluent flow-p l
rate, in gpm.
l.N'=
'the allocation fraction which apportions dilu-l-
tion flow among simultaneous discharge path-l
-ways (see discussion above),
- l F, SF, & MPCSUM, are as previously defined.
.(
. l The minimum value of F is 5000 gpm, wLi:h is used.as a l default value.
The dilution water supply is furnished l with a flow monitor.which isolates the liquid effluent V
l discharge if the dilution flow rate falls below the l 5000 gpm-minimum value.
l.In the event that f,,3 is less than f, then the value p
1 of-f is substituted into the equation for f and a max p
l new value of f,,x is ca'lculated.
This substitution is l performed for three iterations in order to calculate I the correct value of f,,x.
'V.
8_
lJ a_-________-___-__-
-CALLAWAT PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 l 2.3.'3 Calculation'of Liquid Effluent Monitor Set.
j point l~The liquid effluent monitors are NaI(TI) based systems l-and respond primarily to' gamma radiation.
Accordingly, litheir setpoint is based,on the total concentration of
.l' gamma emitting nuclides.in the effluent:
l, c = EKG.+.(I(Cg)g + SF) vC1/ml (2.5)
-g' g
'l Where:
jc=
the monitor setpoint as previously defined, in l
(pCi/ml);
- l EKG =
the monitor background. prior to discharge, in
.l (vCi/ml);
lC and.SF are as previously defined.
g c.
j' l The monitor's background is controlled at an appropri-
'q-
[' ate limit to ensure adequate sensitivity.
Utilizing l the methodology of ANSI N13.10-1974 (Ref. 9.23), the l background must be maintained at a value of less than l.or equal to 2.23E-6 pCi/ml (relative to Cs-137) in or-
.l der to detect a change of 1E-7 vCi/ml of I-134 (the
~
l most restrictive nuclide in Table 1 of reference 9.23).
l In the event-that there is no detectable gamma activity l in the effluent or if the'value of (I(Cg)g+SF) is less l than the background of the monitor, then the monitor l setpoint will be set at twice the current background of l tie monitor.
e
l}
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 l AsLpreviously1 stated, the monitor's response is depen-j dent on the gamma emitting radionuclides distribution of l the. effluent.
Accordingly, a new database conversion l factor is calculated for each; release based upon'the l results of the gamma spectrometric analysis of the ef-lLfluent sample and the measured response of the' monitor
- l to NBSLtraceable' calibration sources:
l DECF
, (2. 6).
e l Where:
-l DECF
=
the monitor data base conversion factor which c
l-converts count rate into concentration l
(pCi/ml);
l CMR =:
the. calculated response of the radiation moni-l
. tor to the liquid effluent; l-ECF =
the conversion factor for Cs-137, which' con-jb l
verts count rate into concentration (pCi/ml).
. g j;C is as previously defined.
g
'l The new value of the DBCF s ca culated and. entered c
l into the. monitor data base prior to each discharge.
A l more corplete discussion of the derivation and calcula-l tion of the CMR is given in reference 9.16.8.
2.4 Liquid Effluent Concentration Measurements 2.4.1 Technical Specification 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20,
- Appendix B,. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or ent ained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml total accivity.
4
_m
_.___.u.-...-
CALLAWAY PLANT OFFSITE DOSE CALCULATION MMUAL Rev. 6 2 4.2 Liquid Effluent Concentration Measurements Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at time of release.
To assure re-preventative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection.
The methods for-mixing, sampling, and analyzing each batch are outlined in applicable plant procedures.
The allowable release rate limit is calculated for each batch based.upon the pre-release analysis, dilution flow-rate, cad other procedural conditions, prior to authorization for release.
The radwaste liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the-pre-selected alarm / trip setpoint is exceeded.
Concentra-tions are determined primarily from the gamma isotopic, H-3, & gross alpha analyses of the liquid batch sample.
For Sr-89, Sr-90, & Fe-55, the measured concentration from the previous composite analysis is used.
Compo-site samples are collected for each batch. release and quarterly analyses are perfor.ned in accordance with r~
Technical Specification Table 4.11-1.
Doses from liquids discharged as continuous releases are calculated by utilizing the last measured values of samples required in accordance with Technical Specifi-cations Table 4.11-1.
2.5 Dose Due to Liquid Effluents 2.5.1 Technical Specification 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, to UNRESTRICTED AREAS shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the whole body and less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.,.
O L____..__
_ _ - _ = _ - _.
f.
-CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL' Rev. 6
'j,ess',
3.5.2 The Maximum Exposed Individual' L
The cumulative dose determination considers the' dose ~
contributions from the maximum. exposed' individual's consumption.of fish and potable-water,.as-appropriate.
Normally,.the adult'is considered to be the maximum ex-posed individual.
(Ref. 9.8.3, 9.8.4).
n L.
The Callaway Plant's liquid = effluents ~are~ discharged-to p
the Missouri River.
As there:are no potable water'in--
takes within 50 miles of the discharge pointf(Ref.
9.7 1, 9.6.6), ithis pathway does not require routine'.
evaluation.
Therefore,1the dose contribution.from fish consumption.is' expected to account for more than 95% of<
the1 total man-rem dose from discharges to the. Missouri River.. Dose from recreational activities'is. expected
.to. contribute the additional 5%, which is. considered to-be. negligible.
(Ref.- - 9. 6. 7 )
- 2. 5. 3 - Calculation of Dose From Liquid Effluents l
2.5.3.l Calculation of Dose Contributions The dose contributions for the total time period g
m
"~
Iat g t=1
- are calculated at least once each 31 days and a cumula-tive summation of the total body and individual organ doses is maintained for each calendar quarter..These dose contributions are calculated for all radionuclides identified in-liquid effluents released to UNRESTRICTED tr.2AS using the following expression (Ref. 9.8.3)
+
1
.__A_._-.---___.__l.__--__.,_.--,_.-_.1--..
. _ _. - - - _. _ - _.. - -.. ~ - _ _ _... _ _ _ _ _. _ _. -. _. - - - _. - - _ _ _. - - _ _ _. _. _ _ _. -. _ _ _ _ _. - - - _ _ _ _ - _ - -_ _. _ _. _ - - - _ - _
CALLAWAY PLANT:
JOFFSITE DOSE CALCULATION MANUAL' Rev.' 6
. jp
.a R4 i
r m
-D
=-I [Ait.I Atg gg C
F]
(2;12)1 g
'i t=l Where:
Dt =
the. cumulative dose commitment to'the total
. body 'or any organ, t,
from the liquid.ef-
'fluents for the total period m
IAtg-t=1 in mrem; f:
..At ;=
'the length of the Ith time period over which
~.gi -
g
~
-Cgg.and F are averaged-for all111guid' g
l
' releases,-in hours.
At corresponds to the g
l actual duration of the release (s).
Cgg =
.the average measured.' concentration of radionuclides, i, in undiluted' liquid effluent.
during ' tinse period At from'any liquid g
release, in (nCi/ml).
the site related 1.ngestion doae commitment
~A
=
3 factor so the total body or any organ-t for each identified principal gamma and beta emit-ter listed in Technical Specifications,
'i T.Ll. 4.11-1, (in mrem /hr).per (gCi/ml).
The calculation of the.A, values-is detailed in l
y l:
F.ef. 9.16.6 and are given in Table 1.
I 1
.a.
1 13 -
l u -
-=-
-b
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6
- ke F1 =
the near field average dilution factor for C gg during any liquid effluent release.
f t=
max (F + f,,x) 89.77 Where:
f,33 maximum undiluted effluent flow rate during
=
the release F=
average dilution flow 89.77 =
site specific applicable factor for.the mixing effect of the discharge structure. (Ref 9.5.1)
The term C is the undiluted concentration of radioac-it tive material in liquid wasti at the common release point determined in accordare:e with Technical Specifi-cation 3.11.1.1., Table 4.11-1, " Radioactive Liquid Waste Sampling and Analysis Program".
All dilution factors beyond the sample point (s) are included in the F term.
g I
The nearest municipal potable water intake downstream from the liquid effluent discharge point into the Mis-souri River is located near the city of St. Louis, Mo.,
approximately 78 miles downstream.
As there are cur-rently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally er; posed individual, or in dose estimates to the population.
Should future water intakes be constructed within 10 river miles downstream of the dir, charge point, then this manual will be revised to include this pathway in j dose estimates.
(Ref. 9.6.0).
I l.
__.__.i____.__-
1
CALLAWAT PLANT OFFSITE DOSE CALCIEAT!OM MANUAL-Rev. 6
/
2.5'.4~
Summarv, Calculation of Dese-Due to Licuid Effluents The dose contribution for the total time period m
Iat g E=1
~is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ
~ doses is maintained for each calendar quarter.
The-projected dose contribution from liquid effluents for which. radionuclides concentrations are determined by periodic composite and grab ample analysis,'may be ap-
. Dose con-proximated by'using the last measured value.
tributions are determined for all radionuclides identi-fied in liquid ~ effluents released to UNRESTRICTED AREAS.
Nuclides-which are not detected in the analyses are reported.as "less than" the.nuclide's Minimum.
Detectable Activity (MDA) and are'not reported as being-present at the LLD level for that nuclide.
The "less than" values are not'used in.the required dose
.c calculations.
4 f _
__=_-
CALLATAY PLANT OTTSITE DOSE f4LOULATION MAN"AL R:v. 6 TABLE 1 INGESTION DOSE COMMITMENT TACTOR (Ap ) TOR ADULT ACE GROUP (trem/hr) per (uct/ml) l l
l l Total l l
l l
l lNuclide! Bone 1 Liver f Bodv i Thyroid t Kidnev ! Lunt I GT-IL1 1
'l H-3 lNo Data 12.26E-01 12.26E-0112.26E-01 12.:6E-01l2.26E-0112.26E-01l l Be-7 l1.30E-0212.9EE-02 l1.45E-02lNo Data l3.15E-02 lNo Data 15.16E+001 1 C-14 13.13E+04l6.26E+03 16. 6E+03l6.26E+03 16.26E+03l6.26E+0316.26E+03l l Na *4 14.07E+02l4.07E+02 ja.07E+02l4.07I+02 14.07E+02l4.07E+0214.07E+02l l P-32 14.62E+07l2.87E+06 11.76T+06lNo Data lNo Data lNo Data l5.19E+06l l Cr-51 lNo Data lNo Data 11.27E+00l7.62E-01 12.81-01 l1.69E+0013.20E+02l l Mn-54 lNo Data l4.3EE+03 j8.35E+02lNo Data 11.30E+03]No Data 11.34E+041 l Mn-56 lNo Data ll.10E+02 l1.95E+01lNo Data 11.40E+0:lNe Data 13.5:E+03l 1 Te-55 16.57E+0214.5=E+0: 11.06E+02lNo Data INo Data l1.$3E+02l2.61E+02l
[ Te-59 l1.04E+03l2.44E+03 19.3'.E+02lNo Data INo Data l6.61E+0218.13E+03l l Co-57 lNo Data 12.09E+01 13.4SI+01lNo Data lNo Data lNo Data 15.31E+021 l Co-58 lNo Data l8.94E+01 12.00E+02lNo Data INo Data lNo Data l1.61E+031 l Co-60 lNo Data 12.5'E+02 l5.66E+0:lNo Data (No Data jNo Data 14.8 E+031 l Ni-63 13.11E+D4j2.15E+03 11.04E+03lNo Data lNo Dats !No Data l4.49E+02)
{ Ni-65 l1.26E+0:11.64E+01 l7.4EE+00lNo Data jNo Data INo Data 14.16E+021 l Cu-64 lNO Data 11.00E+01 14.69E+00lNo Data 12.52E+01lNo Data 16.52E+021 l En-65 12.32E+04l7.3EE+04 13.33E+04lNo Data l4.93E+04lNo Data l4.65E+04l l 2n-69 14.93E+01l9.44E+01 16.56E*00lNo Data 16.13E+01lNo Data l1.4 E+01l 7
/
l Br-82 lNo Data lNo Data l2.27E+03lNo Data INo Data [No Data 12.60E+03) l Br-83 !No Data INo Data 14.04E+011No Data INo Data lNo Data l5.61E 01l l Br-64 lNo Data lNo Data 15.26E+011No Data lNo Data lNo Data 14.13E-041 1 B -55 lNo Data JNo Data l2.15E+00lNo Data lNo Data lNo Data 1 0
l 1 kb-66 (No Data 11.01E+05 l4.71E+04lNo Data (No Data INo Data 11.99E+04l l Rb-88 lNo Data 12.90E+0: 11.54E+02lNo Data INo Data INo Data l4.00E-09l l Rb-89 lNo Data 11.9:E+02 11.35E+0:lNo Data lNo Data lNo Data 11.12E-11]
l Sr-89 12.21E+04lNo Data l6.35E+0:lNo Data INo Data.!No Data 13.55E+03l i St-90 15.K E+0$lWo Data 11.34E+051No Data INo Data INo Data 11.57E+041 l Sr-91 l4.07T+02lNo Data 11.64E+011ho Data INo Data INu Data 11.94E+03l l $r-02 !1.54E+02lNo Data 16.66E+00tNa Datn lNo Data lNo Date 13.06E+03l i F 90 15.'5boUSo Data 11.5!.E-u2'tlo Dat a 17.0 Data itio Data 16.10i+031 l-l F 91M i!.44E-0!!M Data s.DE-DilFo Dat.a A Lata !Nc Dasa D.60DC2l l b91 18.43bODINe Dass M:.h!-U'41No Data 30 Vare jNo T'sta H.64E*03l 4
lPh 13.0SI-N'No Date 11.'EE-031!% Data iNo Dat4 INo Daar jB.ESE+02) i, i F93 M 40D 01lNo Ec.a (4.4E-03lNo Itta lHo Data ;Eo ?sta 15.0BE+C3l l
l Zr-95 12.4 7.-h l7.70D 02 (5.21E-02tNo Lets il.21E-01)No Data f2.44E+0:1 1
1:47 11.33E-0212.6Eb 03 11.1:b O3lNo Esta 14..D4bMINo Data it.30E+021
! Nb-95 14.47E+0212.4EE+02 il.34E+02lNo Ista 10.4JE+0?JNo Dr.t4 13.51E+0ef i Mo+#1 lNo Data 11.03E+02 11ME+01[No Data 12.~3 E+02lNe Datz 12.39E*0:1 l h 49MI6.27E-0312.51b f2 13.19b O11No D'ta 13.61E-01tl.DE-0211.6EE+D11 i Tc-101lP.11bO31!.Dit 0 ' il.29E-NlNo Gata lh.36E-01;6.70E 03l 0
l l Ru-10314.4:E+00lNe' Data 11.9CI+00lNo Data 11.69E*01lNo Data l5.17E+C:!
) Ru-105l3.6Eb 01tEc Data 11.45E-011No Data 14.76E+00lNo Data ]2.25E+C21 1 Ru-10616.57E+01iNo Data lB.3:E+00lNo Data 11.27bC2lNo Data l4.25E*031 l Cd-109]No Data 15.54E*02 11.94E+011No Data (5.31E+C:lNo Data 15.59E+03l l Sn-11315.66E4 l1.61E3 13.26L3 19.1BE2 lNo Data INo Data 11.69E5 l j Sb-124l6.69E-00ll.06E-01 12.65E+00ll.62E-02 lNo Data 15.01E+00ll.9CE+0:1 - - _. _ -
t 4
+
z CALLAYAY P1 ANT C
. OTTSITE DOSE CALCULATION r
{1 MANUAL.
Rsv. 6-Q b
L-TABLE 1 (Continued; INGESTION DOSE COMMITMENT FACTOR (Ag ) EOR ADULT AGE GROUP its (crem/hr) eer (vei/m))
l -
ic l
l Total l
_l
-l l
l
-jNuclidet Bene 'l Liver l Bodv l Thyroid i Kidnev l Lunt i GT-LLI f'
?lSb-125l4.28E+00l4.78E-02l1.02E+0014.35E-03'lNoDatal3.30E+00l4.71E+01l~
. lTe-125Ml2.57E+03l9.30E+02 13.44E+02l7.72E+02 11.D4E+04lNo Data l1.02E+04l lTe-127Ml6.47E+03l2.32E+03.l7.90E+02l1.66E+03.l2.63E+04lNo Data l2.17E+04l
.lT".-127 11.0$E+0213.78E+01-l2.28E+01l7.80E+01 l4.29E+02lNo Data 18.30E+03l lTe-129Ml1.10E+04l4.11E+03 11.74E+03l3.78E+03 l4.60E+04lNo Data l5.54E+04l.
(Te-129 13.01E+01l1.13E+01 17.33E+00l2.31E+01 l1.26E+02lNo Dats l2.27E+01)
'lTe-131Ml1.66E+03l8.09E+02 l6.75E+02l1.08E+03 l8.21E+03lNo Data l8.03E+04l lTe-131 l1.89E+01l7.86E+00 j$.96E+00l1.53E+01 [8.25E+01lNo Data 12.67E+00l lTe-132'l2.41E+03l1.56E+03 l1.47E+03l1.72E+03 l1.50E+04lNo Data 17.38E+04l lI-130 12.71E+0118.01E+01 l3.16E+0116.79E+03.ll.25E+02lNo Data l6.89E+01]
' lI-131-l1.49E+02l2.14E+02 11.22E+02l 7.00E+04 l3.66E+02lNo. Data 15.64E+01]
lI-132 l7.29E+00l1.95E+01 l6.82E+00l6.82E+02 l3.11E+01lNo Data 13.66E+00l 11-133 l$.10E+01l8.87E+01 12.70E+0112.30E+04 l1.55E+02lNo Data l7.97E+01l
' lI-134 l3.81E+00l1.03E+01 13.70E+00ll.79E+02 l1.64E+01lNo Data 19.01E-03) ll-135 l1.59E+01l4.16E+01 Il.54E+01l2.75E+03 l6.68E+01lNo Data l4.70E+01l lCs-134 l2.98E+05 l7.09E+05. l5.80E+05 lNo Data 12.29E+0517.62E+0411.24E+04l lCs-136 l3.12E+0411.23E+05 l8.86E+04lNo Data l6.85E+04l9.39E+03l1.4DE+04) lCs-137 l3.82E+0515.22E+05 13.42E+03lNo Data 11.77E+0515.89E+04l1.01E+04]
s -.
lCa-138 12.64E+0215.22E+02 12.59E+02lNo Data.l3.B4E+02l3.79E+01l2.23E-03l
,]
18a-139.l9.29E-01l6.62E-04 l2.72E-02lNo Data l6.19E-0413.76E-04l1.65E+00l lBa-140 l1.94E+02l2.44E-01 11.27E+01lNo Data 18.31E-0211.40E 01l4.00E+02l lBa-141 14 50E-01l3.40E-04 l1.52E-02lNo Data 13.16E-0411.93E-04l2.12E-101 lBa-142 12.04E-01l2.09E-04 11.28E 02lNo Data l1.77E-04l1.19E-04l 0
l lLa-140 11.50E-0117.53E-02 11.99E-02lNo Data INo-Data lNo Data (5.53E+031 lLa-142 l7.65E-0313.48E-03-l8.66E-04lNo Data -lNo Data lNo Data (2.54E+01)
- lCe-141 12.24I-02l1.51E-02 11.72E-03lNo Data l7.03E-03lNo Data (5.781+01l lCe-143 13.94E-0312.92E+00 13.23E-04tNo Data 11.2EE-03fNo Data 11.09E+021 lCe-144 l1.17E+00l4.88E-01 l6.2fE-02lNo Date l2.89E-01lNo Data i3.94E+02l lPr-143 15.50E-0112.21E-01 12.73E-02lNo Data ll.27E-01lNo Data 'l2.41E+031 lNd-147 (3.76E-01)l.35E 01 l2.60E *?lNo Data' !2.54E-011Ne Data l2.09E+03l lEu-154 (3.67El 14.54E0 l3.21EJ JNo Data l2.16El lNo Data l3.27E3 l
[Hf-181 l3.99E-02l1.94E-01 11.80E-02lNo Data l4.17E-02lNo Data 12.21E+021
- lW-187 12.96E+02l2.47E+02 l8.64F.+01lNo Data INo Data (No Data l8.09E+04l lNp-239 l2.84E-02l2.80E-03 11.54E-03lNc Data 18.72E-03 No Data 15.74E+02]
t 4
%. j
gn; l %
)k CALLAWAY PLANT w
~
OFFSITE DOSE CALCULATION MANUAL
< w Rev. 6 f.
j..
'. nM-I cA l
TABLE 2
- BIOACCUMULATION FACTOR.(BF ) USED IN THE ABSENCE g
-OF SITE-SIECIFIC' DATA" (pCi/ka) per (pCi/ liter).
- BF.
l
~
1 Element.
Fish 1(Freshwater)
H 9.0 E - Ol' y
Se, 2.0 E + 00-l' C
4.6'E + 03 i.
Na 1.0 E + O2 L
P
.1.0 E-+
05~
Cr 2.0 E + O2 Mn 4.0 E + O2 Fe 1.0 E +-02 Co 5.0 E + 01
- Ni'.
1.O E + O2 Cu-5.0 E + 01 Zn 2.0 E + 03' Br 4.2 E + O2 Rb 2.0 E +oO3 Sr 3.0 E + 01
/
Y 2.5 E + 01.
'Zr 3.3 E + 00 l
Nb 3.0 E + 04 Mo' 1.0 E + 01
- Tc
.1.5 E + 01 Ru 1.0 E + 01 Rh
.1.0 E + 01 Cd 2.0 E + O2 Sn 3.0 E + C.3 Sb 1.0 E + CO Te 4.0 E + O2-I 1.5 E + C1 Cs.
2 O E-+ 03 Ba 4.0 E + 00 La '
- 2. 5 E : + 01 Ce 1.0 E + 00 Pr 2.5 E + 01 Nd 2.5 E + 01 i
Iw 2.5 E + 01 Hf 3.3 E + 00 W
1.2 E + 03 Np 1.0 E + 01 (a)
Values from Regulatory Guide 1.109, Rev 1, l
Table A-1 and References 9.16.5 and 9.16.9.
c -
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 2.6 LIQUID RADWASTE TREATMENT SYSTEM 2.6.1 Technical _ Specification 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM Shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0.06 mrem to the total Dody or O.2 mrem to any organ in a 31 day period.
2.6.2 OPERABILITY Of The LIQUID RADWASTE TREATMEN1 SYSTEM The LIQUID RADWASTE TREATMENT. SYSTEM is capable of varying treatment, depending on waste type and product dasired.
It is capable of concentrating, gas strip-ping, and distillation of liquid wastes through the use of the evaporator system.
The demineralization system is capable of removing radioactive ions from solutions to be reused as makeup water.
Filtration is performed on certain'11guid wastes and it may, in some cases, be the only required treatment prior to release.
The sys-tem has the ability to absorb halides through the use
'T of charcoal filters prior to their release.
The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases of radioactive materials in liquid effluents will be kept "As Low As Reasonably Achievable" (ALARA).
The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for use when liquids require treatment prior to their release to the environment.
OPERABILITY is demonstrated through com-pliance with Technical Specifications 3.11.1.1 and 3.11.1.2.
Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each 31 days by dividing the cum-mulative annual total by the number of elapsed months.
[
19 -
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL.
Rev. 6 c.
3.0-GASEOUS ~ EFFLUENTS 3.1 Technical Specification 3.3.3.10 The radioactive gaseous effluent monitoring instrumen-tation channels shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifica-tion 3.11.2.1. are not exceeded.
The Alarm / Trip Set-points of these channels shall be adjusted to the values; determined.$n accordance.with the methodology and parameters in the ODCM.
3.2 Tochnical Specification 3.11.2.1 The dose rate due toiradioactive materials released in gaseous'efflucnts from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less'than or equal.to 3000 mrem /yr to the skin, and b.
For Iodine - 131 and 133, for tritium, and for all radionuclides in particulate form with half lives
/_
greater than 8 days:
Less than or equal to 1500 mrem /yr. to any organ, from the inhalation pathway only.
3.3 Gaseous Effluent Monitors Noble gas activity monitors are.present on the contain-ment building ventilation system, plant unit ventila-tion system, and radwaste building ventilation system.
The alarm / trip (alarm & trip) setpoint for any gaseous effluent radiation monitor is determined based on the instantaneous noble gas total body and skin dose rate limits of Technical Specification 3.11.2.1, at the SITE BOUNDARY location with the highest annual average X/Q value. (Figure 5.13)
Each monitor channel is provided with a two level sys-tera which provides sequential alarms on increasing radioactivity levels.
These setpoints are designated as alert setpoints and alarm / trip setpoints.
(Ref.
9.6.3)
( _
__._w
CALLAWAY PLANT OFFSITE DOSE CALCULAT20N MANUAL Rev 6
The radiation monitor alarm / trip setpoints for each release point are~ based on the radioactive ncble gases in gaseous effluents.
It is not considered practicable to. apply instantaneous alarm / trip setpoints to inte-grating radiation monitors sensitive to radiciodines, radioactive materials in particulate form and radionu-clides other than noble gases.
Conservative assump-tions may be necessary in establishing setpoints to ac-count for system variables, such as the measurement system efficiency and detection capabilities during normal, anticipated, and unusual operating conditions,
- the variability in release flow and principal radionu-clides, and the time lag between alarm / trip action and the final isolation of the radioactive effluent.
(Ref.
9.8.6.) Technical Specifications Table 4.3-13 provides the instrument surveillance requirements,. such as cali-bration, pource checking, functional testing, and chan-
=nel checking.
3.3.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with conti-nuous gaseous effluent releases are (Ref.
9.6.8, 9.6.9):
Monitor I.D.
Description GT-RE-21 Unit Vent GH-RE-10 Radwaste Building Vent L
Each of the above continuously monitors gaseous radi-eactivity concentrations downstream of the last point of potential influent, and therefore measures effluents and not inplant concentrations.
The Unit Vent monitor continuously monitors the ef-fluent from the unit vent for gaseous radioactivity.
l The Unit Vent, via ventilation exhaust systems, conti-nuously purges various tanks and sumps normally con-taining low-level radioactive aerated liquids that can potentially generate airborne activity.
1 1 _
l
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rov. 6 The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the ac-cess control area, the containment purge, and the con-denser air discharge.
The Unit he at monitor provides alarm functions only, and does ne-terminate releases from the Unit Vent.
The Radwaste Building Ventilation effluent monitor con-tinuously monitors for gaseous radioactivity in the ef-fluent duct downstream of the exhaust filter and fans.
The flow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path for the waste gas decay tank release line.. These components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.
This monitor will isolate the waste gas decay tank dis-charge line upon a high gaseous radioactivity alarm.
The continuous gaseous effluent monitor setpoints are
('
established using the methodology described in Section l
3.4.
Since there are two continuous gaseous effluent release points, a fraction of the total dose rate limit (DRL) will be allocated to each release point.
Ne-glecting the batch releases, the plant Unit Vent moni-tor has been allocated 0.7 DRL and the Radwaste Build-ing Vent monitor has been allocated 0.3 DRL.
These al-location factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e. 1.0).
Therefore, a particular moni-ter reaching the setpoint would not necessarily mean the dose rate limit at the SITE BOUNDARY is being ex-ceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems. i.
m
_ _ ~ _ - _ _ _ _ _. _ _. - _ - - - _ - - - _. -. - -
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rov. 6 3.3.2 Batch Release Gaseous Monitors i
The' radiation monitors asrociated with batch release gaseous effluents are (Ref.
9.6.9, 9.6.10, 9.6.11):
Monitor I.D.
Description GT-RE-22 Containment Purge System GT-RE-33 GH-RE-10 Radwaste Building Vent l
The Containment Purge System monitors continuously monitor the containment purge exhaust duct during purge operations for gaseous radioactivity.
The primary pur-pose of these monitors is to isolate the containment purge system en high gaseous activity via the ESFAS.
The sample points are located outside the containment between the containment isolation dampera and the con-tainment purge filter adsorber unit.
The Radwaste Building Vent monitor was previously described in Section 3.3.1.
Setpoints for the batch gaseous effluent monitors are calculated using the methodology described in Section 3.4.
A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides, The alarm / trip setpoint(s) is adjusted accordingly to ensure that the limits of Technical Specification 3.J',2.1 are not exceeded.
3.4 Determination of Gaseous Effluent Monitor Setooints The alarm / trip setpoint for gaseous effluent monitors is determined based on the lesser of the total body dvec tale and eklu dw.= late, as calculated for the SITE BOUNDARY.
23 -
h u.___._____._.-__m_.__
LCALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rov. 6 l During core alterations, the setpoint for the Contain-l ment Purge Monitors, GT-RE-22 and GT-RE-33 is set at a l value of less than or equal to SE-3 pCi/cc, as required j by Specification 4.9.4.2.
The actual setpoint value l Vill be reduced according to the Instrument Loop Uncer-l.tainty Istimate (ILUE).
This value vill also be util-l 1:ed in the event that there is no detectable noble gas i activity in the containment atmosphere sample analyzed l in accordance with Specification 3.11.2.1.
The full l derivation of this value is discussed in reference l 9.16.7.
3.4.1 Total Body Dose Rate Setpoint Calculations To ensure that the limits of Technical Specification 3.11.2.1 are met, the alarm / trip setpoint based on the total body dose rate is calculated according to:
S 5D R
F tb tb,F, (3.1) tb Where:
Stb =
the alarm / trip setpoint based on the total body dose rate (uCi/cc).
D b=
Technical Specification 3.11.2.1 limit of 500 mrem /yr, conservatively interpreted as a continuous release over a one year period.
F, =
the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement.
(For example, F, = 0.5 corresponds to a 100% variation.)
Default value is F, = 1.0.
l
. l l
l-
st; CALLAWAY PLANT o
OFFSITE DOSE CALCULATION MANI.7AL-Rov.
6-L F
=
the allocation factor which will modify the a-reqaired dilution factor such that simultaneous gaseous releases may be made t
- without_ exceeding the limits of Radiological Effluent-Technical Specification 3.11.2-.1.
The def ault value is.1/n, where - n is. tie num-
.ber of pathways planned for release.
Rtb =
factor used'to convert dose rate to the effluent concentration as measured by the ef-firent monitor, in (vCi/cc) per (mrem /yr) to the total body, determined according to:
Rtb = C + [(X/Q) IKQ)
(3.2) gg 1
LWhere:
~
C=
monitor reading of a noble gas monitor cor-responding to the sample radionuclides concen-trations:for the batch to be released.
Concentrations are determined in accordance with Technical Specifications Table 4.11-2.
The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to_a calibration factor to determine monitor response.
The monitor response is based on concentrations, not release rate, and is in units of (vCi/cc).
+,
X/Q =
the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY in (sec/m'). Refer to Tables 9, 10, and 12.
Om Lutal 'sdy dea 6 factsr due ts gamma K
u g-emissions for each identified noble gas radionuclides, in (mrem /yr) per (vCi/m*).
(Table 3)
~
I
~ -
CALLAWAY' PLANT OFFSITE DOSE' CALCULATION-
~
MANUAL Rav. ; 6 B
g
.i'l
- Qg =-
rate of release'of noble gas radionuclides, i,'in:(pCi/sec).-
'I Qg is calculated'as the product'of the'ven-
'tilation path design flow rate-and the' meas-ured activity of the effluent: stream-as deter-mined by grab sampling.. Flow rates for the.
ventilation pathways can-be found in ref-erence's 9.6.21, 9.6.22, 9.6.23,. and 9.6.24.
L-3.4.2 Skin D'ose Rate Setpoint-Calculation To ensure that'the limits'of Technical' Specification
. 3.11.'2.1-are met, the alarm / trip.setpoint based on the skin dose. rate is calculated according to:
S, < D,R,F,F, (3.3)
/~
Where:
F, and F, are as previously defined in'.Section 3.4.1.1.
5, =
the alarm / trip setpoint-based on'the' skin dose rate.
- D, =
Technical Specification 3.11.2.1 limit of 3000 mrem /yr, conservatively interpreted as a continuous release over a one year period.
d 4
i
/
W. _..____.,._-__a__m__.
.____._:..mm.____
'I
CALLAWAY PLANT'
.OFFSITE. DOSE CALCULATION' MAINAL.
- Rov. 6 s
Rs=
. factor used to convert dose' rate to the effluent" concentration as measured by the ef-fluent monitor, in (vCi/cc) per (mrem /yr).to
.the sking determined according to:
9 R
=C+
[(X/Q) I (L. + 1.1M ) Q4)
(3.4) s 1
.a 1
Where:
- L
=.
the skin dose factor due to beta emissions for g
each identified noble gas radionuclides, in 3
(mrem /yr) per (pCi/m ).
(Table 3) 1.1 = conversion factor:
1 mrad air dose =
1.1 mrem skin dose.
p Mg=
the air dose factor due.to gamma emissions for each identified noble gas radionuclides, in 3
(mrad /yr) per (vCi/m ).
(Table 3)
C, (X/Q) and Q are as previously defined.
g 3.4.3 Gaseous Effluent u nitors Setpoint Determination The results of Equation (3.1) and Equation (3.3) are compared.
The setpoint is then selected as the lesser I
'of the two values.
T l.
,A.
>=
4,.
~a CO @ ';
I cl.
wQ>
E C
<WC.
J 60 m
- m g..
E g
<W:
O 2nd
'A
- ~<
w ogc
'L-iwE-bC 6
NmmemsmmmmNmemm (w<
. = * * ' C t
CCCCCCCCCCCCCCC
QCE
. C. m. C. EO. *.. C. M. M. N. N. N.
go a N O
O-t N w - *= N
- N s= *== P= N
- X M C.
m W
6 -
W E
a C
w C
k E
m a
e 6
m C
1 w
e C
=
C O
C
.J C
O C
b b
mpmeccNNNmmmmm W
=b
>=
<C - C CCCCCCCCCCCCCCC G
+++++++++++++++
WWWWWWWWWWWWWWW 6
- E
@UEa CD Ee 6
mmNNNmm@NmcNeo-o
=
M 6
E6 h
S. N. P* w e. P* C. A. N. e. m. m. e. N. m.
-C E
- m N
W QC. t
- = *= ** @ w *= *= ** m m m * = m m
.3
=
..g...-
.J a
m e e
3"1 C^
Em em
-E D E m
w w
.+
g g
g C
.=.
00 m
N C
6 E
a
>=
0 w
W U
-U C
g 4 &
C es.
w Mr.mmeMNNNNmcmm C
O C C C C C C C. C C C C.C C C Q
C C
L
++++++
++++e++
b e
C WWWWW6wWWWWWWW X
C-4 8
m W
C o.i c c M N w m @ r c== @ N M cs C
8 : m. N. M. C. N. N. m. c. **. to. N. e c.
=
C C
6 C
h a== *= m N e= P= M m m P= = ** N E
=
w x
N-M E
g m
C w
E 6
C E
t w
C O
4
.w
=
=>
i b
C W
E D
M c
=N O
O 6
bib N M.= m e r r - N N m m =* m m w
- D C CCDCCCCCCCCCCCC C aa b
e++++++++++++++
6 CO C
WWWWWWWWWWWWWWW C
e L
-w -
@ P= w N P= c c e== c N w N m e 0
1 Xa 1
.il
- e. w. @. b. r. c. A. *=. e. m. *=. IC. c. to. C.
R aC 6
6 Ce h m e-== e s= w - D N N m a- ** 4010
>= 0 N
O C E e
C C
6 i
V E
1 w
T C
!t C
l t
EE E EE e m m e c e-C 1.
4, O
m e e ** C B C m m m m m m m==
C C
C C EO C C C m m = w ~ *= w w e
.lll:
C e e s e e e a e e e e e e e a w
C b 6 6 6 6. 6 6 CCCCCCC6 i
l-
=
XXXXXXXXXXXXXX<
'O em i
e a
C w
_n 1
CALLAWAY PLANT-OFFSITE DOSE CALCULATION.
,y MANUAL-
'Rev. 6 1
g_
3.4.4-Summarv, Gaseous Effluent Monitors Setpoint Determination 1The' gaseous effluentimonitors setpoints:are calculated-
.according.to equations (3.1)'and (3.3), as described in.
- SectionT3.4.
However, it should-be:noted that a batch
~
release will alter the-flow rate characteristics at the
=
Unit Vent and therefore the concentration;as sensed by.-
-+
the monitor.
.For. example, in.the case.of a mini-purge, the'r.etpoint for the Unit Vent monitor must be re-calculated to-include both'the continuous and batch sour es.
3.5 ' Calculation of Dose From Caseous Effluents Dose rate calculations are performed.for gaseous ef-
-fluents'to ensure compliance.with Technical Specifica-tion 3.11.2.1.
3.5.1 ' Calculation of Dese Rate The.following. methodology is applicable to the location (SITE BOUNDARYJor beyond)' characterized by the values of the parameter (X/Q).which results in the maximum ft" total' body or' skin dose rate.-
In the event that the I
T7 analysis indicates a different location forethe total
-body and skin dose' limitations, the-location selected
.for consideration:is that'which minimizes the allowable l=
rn.1. ease values.
-(Ref. 9.8.7)
The factors K,
L, and M relate'the radionuclides air-g g
g borne concentrations to.various. dose rates, assuming a
. semi-infinite cloud model, and are tabulated in Table 3.
3.5.1.1.
Noble Gases The release rate limit for noble gases is determined according to the following general relationships (Ref.
- 9. 8. 7 ) -:
L D b = I (Kf( {X/Q)Q )) < 500 mrem /yr (3.5).
i s
[
L L-
b'
..CALLAWAY PLANT OFFSITE DOSE CALCULATION:
MANUAL.
Rev.= 6 g,
s,
~
' D;
= I - [(L1 + 1.1 M )((X/Q)Q )) <_ 3000 mrem /yr (3.6) g 1
i o
Wherei Dg=.
Total body dose rate,. conservatively averaged over a period of:ene year.
Kg =
Total body-dose factor due to! gamma emissions for each identified noble gas radionuclides, in-3-
-(mrem /yr) per-(vCi/m ),
(Table 3)
(X/Q) = :The highest calculated: annual average relative
,Jr(.
concentration for any area at or beyond'the SITE BOUNDARY.. ' Refer to Tables?9,~10,:and.12.
Qp=
The release' rate of noble gas' radionuclides, i, in gaseous effluents, from all vent releases in (vci/sec).
Qg-is calculated as.the product of the ven-tilation path design flow rate and the meas-ured activity of the' effluent stream as deter-mined by grab sampling.
Flow rates for the ventilation? pathways can be found in ref-erences 9.6.21, 9.6.22, 9.6.23, and 9.6.24.
D,=-
Skin dose rate, conservatively averaged over 1
. yetivd vf - cI4e year.
L
=
Skin dose factor due to beta emissions for each identified noble gas radionuclides, in (mrem /yr) per (uCi/m') (Table 3).
1.1 =-
Units conversion factor; 1 mrad air dose = 1.1 mrem skin dose.
(-
J
- 3o -
l
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rsv. 6 Mg=
Air dose factor due to gamma emissions for each identified noble gas radionuclides, in 8
(mrad /yr) per (pCi/m ) (Table 3).
3.5.1.2 Radionuclides Other Than Noble Cases The release rate limit for Iodine-131.and-133, for tri-tium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 9.8.8):
D, = I P [(X/Q)Qg] $ 1500 mrem /yr (3.7) g i
Where:
D
=
Dose rate to any critical organ, in (mrem /yr).
g Pg=
Dose parameter for radionuclides other than f
L noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem /yr) per (pCi/m').
(Table 4)
Q=
The release rate of radionuclides, i, in g
gaseous effluents, from all vent releases, in (pCi/sec).
Q is calculated as the product of g
the ventilation path design flow rate and the measured activity of the effluent stream as determined by grab sampling.
Flow rates for the ventilation pathways can be found in ref-erences 9.6.21, 9.6,22, 9.6.23, and 9.6.24.
(X/Q) is as previously defined.
The dcss paramster (r ) includes the internal dosimetry g
of radionuclides, i, and the receptor's breathing rate, which are functions of the receptor's age.
Therefore the child age group has been selected as the limiting age group.
5)
.CALLAWAY PLANT.
1 OFFSITE DOSE CALCULATION.
ci MANUAL Rev. 6:
- For.'the child exposure, separatevaluesofPgaretabu-lated'in Table 4 for the inhalation pathway.
These:
. values were. calculated according'to (Ref. 9.8.9):
u Pg = C (BR) MAg (3.8),
Where:
K' =
Units conversion factor: luCi.= lE06 pC1.
BR=.
The. breathing rate of the maximum exposed child age group, 3700 m /yr.
(Regulatory 8
Guide'1.109,' Table E-5).
- DFAg=
The maximum organ inhalation dose factor'for the child age group for the ith radionuclides, in (mrem /pC1).
The total body is considered as an organ in the selection of DFA.-
(Ref.
g 9.11.5 and 9.16.5) r Note:
All radiciodines are assumed to be released in elemental form.
(Ref.9.8.8) 4 4
4> i
p~ -
0FFSITE DOSE CALCULATION A
~
CALLA'; LAY PLANT :
MANUAL Rsv. 6 2
TABLE 4 DOSE PARAMETER'(P ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Inhalation Pathway-8 (mrem /yr) per'(UCi/m )
I I
l i Total l
l.
I 1
l lNuclidel Bone -l-Liver l Body 1 Thyroid l Kidney I Lung' l GI-LLI 1 l H-3 l ND l 1'.12E3
.l1.12E3 l1.12E3
,l1.12E3 l1.12E3 l1.12E3 l
l Be-7 l6.47E2 l1.44E3 19.25E2 l.ND
.l.
ND l6.48E4 l2.55E3 'l
.l C-14 {3.59E4 -l6.73E3
.l6.73E3 16.73E3 l6.73E3 l6.73E3 l6.73E3 l
l Na-24 l1.61E4 l1.61E4 l1.61E4 l1.61E4 11.61E4 l1.61E4 11.61E4 l'
l P l2.60E6 l1.14E5 19.88E4 -l ND l ND l ND l4.22E4 l-l Cr-51 j. ND l ND l1.54E2 l8.55El l2.43E1 l1.70E4 l1.08E3 l
l Mn-54 l ND l4.29E4 l9.51E3 l ND l1.00E4 l1.58E6. l2.29E4 l
.l.Mn-56 l. ND l1.66E0 l3.12E-1 l ND l1.67E0 l1.31E4 l1.23E5 l
!l Fe-55 l4.74E4 l2.52E4 l7.72E3 l ND l ND
'll.11E5 l2.87E3 l
l Fe-59.'l2.07E4 l3.34E4 l1.67E4 l ND l ND l1.27E6 l7.07E4 l
f1 l'Co-57.l ND.
19.03E2 l1.07E3 l ND l ND 15.07ES. l1.32E4 l-
-l Co-58 l ND l1.77E3 l3.16E3 l ND l @
l1.11E6 l3.44E4 -l l.Co-60 l ND l1.31E4 l2.26E4 l ND l ND l7,0756 19.26E4 l
l Ni-63 l8.21E5 l4.63E4 l2.80E4 l. ND l ND l2.75E5 l6.33E3 l
] Ni-65-l2.99E0 l2.96E-1 l1.64E-1 l ND l ND l8.18E3 18.40E4 l
-l Cu-64 l-;ND l1.99E0 l1.07E0 l ND l6.03E0 l9.58E3 l3.67E4 l
l'Zn-65-l4.26E4 l1.13E5 l7.03E4 l ND l7.14E4 19.95ES l1.63E4 l
{ Zn-69 l6.70E-2 l9.66E-2 l8.92E-3 l. ND l5.85E-2 l1.42E3 l1.02E4 l
-l Br-82 l ND l @
l2.09E4 l ND l ND l ND l @
l
.] Br-83 l ND l ND l4.74E2 l ND l ND l ND l-0 l
- l Br-84 l ND l ND l5.48E2 l ND l ND l ND l
0 l
l Br-85 l ND l ND l2.53E1 l @
l ND l ND l
0 l
l Rb-86 l 'ND l1.98E5 l1.14E5 l ND l ND l ND l7.99E3 l
l Rb-88 l ND l5.62E2 l3.66E2 l ND l ND l ND l1.72E1 l
1 Rb-89 1 ND 13.45E2 12.90E2 1 ND l ND 1 ND l1.89E0 l
' l Sr-69 l5.99E5 l ND l1.72E4 l @
l ND l2.16E6 l1.67E5 l
l Sr-90 l1.01E8 l ND
]6.44E6 l ND l.ND l1.48E7 l3.43E5 l
l Sr-91 l1.21E2 j ND 14.59E0 l ND l ND l5.33E4 l1.74E5 l
.l Sr-92 l1.31El l ND l5.25E-1 l ND l ND l2.40E4 l2.42E5 l
l Y-90 l4.11E3
-l ND l1.11E2 l ND l ND l2.62E5 l2.68E5 l
m _
___.___.___.__m___
CALLA':!AY PLANT OFFSITE DOSE CALCULATION MANUAL Rtv. 6 TABLI 4 (Cont'd.)
l DOSE PARAMETER (P ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa f
Inhalation Pathway (mrem /yr) per (pC1/m')
l l
l l Total l
l l
l l
lNuclidel Bone i Liver i
Body i Thyroid l Kidney I Lung i GI-LLI_[
l Y-91m l5.07E-1 l ND l1.84E-2 l ND l ND l2.81E3 11.72E3
[.
l Y-91 l9.14E5 l ND l2.44E4 l ND l ND l2.63E6 l1.84E5 l
l l Y-92 l2.04E1 l -ND l5.81E-1 l ND l ND l2.39E4 12.39ES l
l Y-93 l1.86E2 l ND l5.11E0 l ND l
ND.
l7.44E4 13.89E5 l
l Zr-95 11.90E5 l4.18E4 13.70E4 l ND l5.96E4 l2.23E6 l6.11E4 l
l Zr-97 l1.88E2 l2.72E1 l1.60E1 l ND l3.89El l1.13E5 13.51E5 l
l N'o-95 l2.33E4 l9.18E3 l6.55E3 l ND l8.62E3 l6.14E5 l3.70E4 l
l Mo-99 l ND l 1'. 72E2 14.26El l ND l3.92E2 l1.35E5 11.27E5 l
l Tc-99 mil.78E-3 l3.48E-3 l5.77E-2 l ND l5.07E-2 19.51E2 l4.81E3 l
(-
l Tc-101l8.10E-5 l8.51E-5 l1.08E-3 l ND l1.45E-3 l5.85E2 l1.63E1 l
s~'
l Ru-103l2.79E3 l ND l1.07E3 l ND l7.03E3 l6.62E5 l4.48E4 l
l Ru-105l1.53E0 l ND l5.55E-1 l ND l1.34E0 l1.59E4 19.95E4 l
l Ru-106l1.36ES l ND l1.69E4 l
ND l1.84E5 l1.43E7 l4.29E5 l
lAg-110ml1.69E4 l1.14E4 l9.14E3 l ND l2.12E4 l5.48E6 11.00E5 l
l Cd-109l ND l5.48E5 l2.59E4 l ND l4.96ES l1,05E6 l2.78E4 l
l Sn-11311.13E5 l3.12E3 l8.62E3 12.33E3 l ND l1.46E6 12.26E5 l
l Sb-12415.74E4 l7.40E2 l2.00E4 l1.26E2 l ND l3.24E6 l1.64E5 l
l Sb-125l9.84E4 l7.59E2 l2.07E4 19.10E1 l ND l2.32E6 l4.03E4 l
lTe-125ml6.73E3 l2.33E3 19.14E2 l1.92E3 l
ND l4.77ES l3.38E4 l
lTe-127ml2.49E4 18.55E3 l3.02E3 l6.07E3 l6.36E4 l1.48E6 l7.14E4 l
lTe-127 l2.77E0 l9.51E-l' l6.11E-1 l1.96E0 17.07E0 11.00E4 l5.62E4 l
lTe-129ml1.92E4 l6.85E3 l3.04E3 l6.33E3 l5.03E4 11.76E6 11.82E5 l
lTe-129 l9.77E-2 l3.50E-2 12.38E-2 17.14E-2 l2.57E-1 l2.93E3 l2.55E4 l
lTe-131ml1.34E2 l5.92E1 15.07El l9.77El 14.00E2 l2.06ES l3.08E5 l
ITe-131 12.17E-2 18.44E-3 16.59E-3 11.70E-2 15.88E-2 12.05E3 ll.33E3 l
lTe-132 l4.81E2 l2.72E2 l2.63E2 13.17E2 l1.77E3 l3.77E5 ll.38E5 l
m.> - __ _ _-_
CALLAWAY PLANTS 0FFSITE DOSE CALCULATION' MANUAL R3v. 6' M-TABLE 4 (Cont'd.)
DOSE PARAMETER (P ) FOR RADIONUCLIDES OTHER THAN NOBLE GASE5" g
Inhalation Pathway 8
(mrem /yr) per (vC1/m )
l l
-1 l Total l
l l.
l
.l lNuclidel Bone l Liver' 1 Body i Thyroid l Kidnev l ' Lung l GI-LLI l-lI-130 l8.18E3-l1.64E4 l8.44E3 l1.85E6 l2.45E4-l ND.
l5'.11E3 l
11-131l4.81E4 ~ l 4'. 81E4 l2.73E4 l1.62E7 17.88E4 l ND 12.84E3 l
lI-132. 12.12E3 l4.07E3
-l1.88E3 l1.94E5 l6.25E3 l ND 13.20E3-j
-lI-133 "l1.66E4; 'l2.03E4-l7.70E3 l3.85E6 l3.3BE4 l
ND l5.48E3 l
lI-134. l1.17E3 - l 2.16E3 '
l9.95E2 j5.07E4 l3.30E3 l ND l9.55E2 ')
~
lI-135' l4.92E3 :l8.73E3 14.'14E3 l7.92E5 l1.34E4 l ND 14.44E3 l
lCs-134'l6.51ES' l1.01E6-l2.25E5 l
ND
-l3.03E5 l1.21ES. l3.85E3' l lCs-136.l6.51E4 l1.71ES l1.16ES l
ND l9.55E4 11.45E4 l4.18E3
-l lCs-137 19.07ES l8.25L5.
11.2BE5 l
ND l2.72E5 l1.04E5 l3.62E3 l
lCs-138'j6.33E2 -l8.40E2 l5.55E2 'l ND l6.22E2 l6.81El 12.70E2-l
]['E~
.lBa-139-l1.84E0 l9.84E-4 'l5.37E-2 l ND 18.62E-4 l5.77E3 l5.77E4 -l lBa-140 17.40E4 l6.48E1
'l4.33E3 l' ND l2.11El l1.74E6' l1.02E5 l
lBa-141'l2.19E-1 l1.09E-4 'l6.36E-3 l ND l9.47E-5 l2.92E3 l2.75E2 l.
lBa-142 l5.00E-2 l3.60E-5 l2.79E-3;l. ND.
l2.91E-5 l1.64ES. l2.74E0 l
lLa-140 16.44E2 12.25E2 l7.55El-l ND l ND l1.83E5 12.26ES l
lLa-142 l1.30E0 l4.11E-1 l1.29E-1 l ND l ND l8.70E3-l7.59E4 l
lCe-141 l3'.92E4 l1.95E4 l2.90E3 l ND l8.55E3 15.44E5 l5.66E4 l
lCe-143 l3.66E2 l1.99E2' l2.87El' l ND l8.36El l1.15ES l1.27E5 l
lCe-144 l6.77E6 l2.12E6 13.61E5 l ND l1.17E6 l1 20E7 -l3.89E5 l
lPr-143 l1.85E4 l5.55E3 l9.14E2
- 1. ND l3.00E3 l4.33E5 l9.73E4 l
s lPr 244 l5.96E-2 l1.85E-2 13.00E-3 l ND l9.77E-3 l1.57E3 l1.97E2 l
lNd-147 l1.08E4 l8.73E3 16.81E2 l ND l4.81E3 l3.28E5 l8.21E4 l
lEu-154.l1.01E7 l9.21E5 l8.40E5 l
ND l4.03E6 l6.14E6 11.10E5 l
lHf-181 l2.78E4 l1.01E5 ll.25E4 l ND l2.05E4 l1.06E6 l6.62E4 l.
lW-187 l1.63E1 19.66E0 l4.33E0 ! ND l ND l4.11E4 19.10E4 l
lNp-239 l4.66E2 l3.34E1 l2.35El l AT l9.73E1 l5.81E4 l6.40E4 l
1, l (a) The child age group; refer to reference 9.16.6.
1 4
J :'
CALLAWAY PLANT OFFSITE DOSE CALCULATION' MANUAL
- Rav. 6' 3.5.2 Dose Due To Gaseous Effluents 3.5.2.1 Technical Specification 3.11.2.2 The air dose due.to noble gases released in gaseous'ef-fluents, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for. gamma radiation and less'than or egaal to 10 mrad for beta radiation and,
. b.
-During any calendar year:
Less than or equal to '10 mrad for gamma radiation and less than or equal-to 20 mrad for beta radiation.
3.5.2.1 1 Noble Gases
> The. air dose at the SITE BOUNDARY due to noble gases released from the site is calculated according to the following methodology (Ref. 9.8.10):
During any calendar quarter, for gamma radiation:
'l' D = 3.17 E-08 I [Mg {(X/Q) Qg + (X/q) qf)) 55 mrad (3.9) g i
During any calendar quarter, for beta radiation:
Db = 3 17 E-08 I [Ng {(X/Q) Qg+ (X/q) q1)) $ 10 mrad (3.10) i During any calendar year, for gamma radiation:
D
= 3.17 E-08 I TM. {(X/0) 0, + (X/q) q,11 < 10 mrad (3.11) y a
s s
1 L
During any calendar year, for beta radiation:
Db = 3.17 E-08 I [Ng {(X/Q) Q1+ (X/q) q )) 5 20 mrad (3.12) 1 i
u__-.-_.--_.__----------
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rov. 6 Where:
D
=
Air dose from gamma radiation due to noble g
gases released in gaseous effluent.
Db=
Air dose from beta radiation due to noble gases released in gaseous effluents.
(X/q) =
The relative concentration for areas at or beyond the SITE BOUNDARY for short-term releases (equal to or less than 500 hrs / year).
Refer to Tables 9, 10, 11, and 12.
qf =
The average release of noble gas radionu-clides, i, in g&seous effluents from all vent releases for short-term releases (equal to or less than 500 hrs / year), in (uC1).
Releases are cumulative over the calendar quarter or year, as appropriate.
Ng=
The air dose factor due to beta emissions for each identified noble gas radionuclides, i, in (mrad /yr) per (uCi/m'). (Table 3)
Qg=
The average release of noble gas radionu-j clides, i, in gaseous effluents from all vent releases for long-term releases (greater than 500 hrs / year), in (vCi).
Releases are cumula-tive over the calendar quarter or year, as appropriate.
(X/Q) =
The highest calculated annual average relative concentration for areas at or beyond the SITE BOUNDARY for long-term releases (greater than 500 hrs /yr).
Refer to Tables 9,
10, and 12.
3.17E-08 = The inverse of the number of seconds per year.
M is as previously defined. (Refer to Section 3.4.1.2)
)
g w.-.
.mm_..
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 3.5.2.2 Technical Specification 3.11.2.3
.c The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-fluents released, to areas at and beyond the SITE BOUN-DARY shall be limited to the following (Ref. 9.8.10):
a, During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
3.5.2.2.1 Radionuclides Other Than Noble Cases The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-fluents released, to areas at and beyond the SITE SOUN-DARY, is calculated according to the following expressions:
During any calendar quarter:
Dg = 3.17E-08 I R3
[W Qi + w g ) 5 7.5 mrem (3.13) g i
During any calendar year:
33 = 3.17E-08 I Rg
[W Qg + w g ) 5 15 mrem (3.14) g i
Where:
D.
=
Dose to a MEMBER OF THE PUBLIC from 1
radionuclides other than noble gases.
- l A-Mhm_____m--m_
.CALLAWAY PLANT--
g' OFFSITE1 DOSE CALCULATION' MANUALL Rev. 6 p
-7 Qg =
The releases of radio 1odines,. radioactive materials <in particulate' form, and radionu-clides other than noble gases, i, in-gaseous effluents, for all; vent releases for.long-term releases'(greater than:500 hrs /yr), in'(uci).
Releases are cumulative over the calendar quarter or year as. appropriate.
~
gg=
The releases of radiciodines,- radioactive-materials in particulate. form; and.radionu-
'clides other than noble gases, 1, in gaseous effluents for all vent releases for short-term releases (equaluto or less than 500 hrs /yr),
in-(uC1).
Releases are cumulative over the calendar quarter or year as appropriate.
' Rg=
~The dose factor for each identified radionuclides, i, in m*(mrem /yr)' per-(vCi/sec) 8 or (mrem /yr) per (vCi/m ). (Table 5)
W=
The dispersion parameter for estimating the dose to an individual at the controlling loca-
-tion for long-term releases (greater than 500
,? "
hrs /yr):
W= (X/Q) for the inhalation and tritium pathways, in(sec/m').
W =:(b/Q) for the. food and ground plane pathways, in(meters"8).
Refer ~to Tables 9, 10, and 12.
f h-1 ___J_--_--_
c, -.-
CALLAWAY PLANT-
- OFFSITE DOSE. CALCULATION-MANUAL Rsv. 6 l-l' i
L w.=-'
.The dispersion parameter for estimating the l
~
dose to an individual at the controlling,loca-
. tion for short-term releases (equal to or less:
than 500 hrs /yr):
1 w = (X/q) for the inhalation pathway, 8
in(sec/m )
w = (D/q) for;the food and' ground plane pathway, in (meters ~2).
_ Refer to Tables 9, 10, 11, and 12.
l l
3.17 E-08
= The inverse of the number of seconds per year.
(D/Q) =- the average relative deposition of the ef-fluent at'or beyond the SITE BOUNDARY, consid-ering depletion.of.the. plume during transport, for long term releases'(greater than 500 hrs /yr), in (meters"8).
~.
S 9
40
____.-._.__________________.____.____.l______.____._i_____.__________._________._....
CALLAWAY PLANT-OFFSITE DOSE CALCULATION.
- MANUAL,
-Rsv. 6
.,. =
. (D/q) =,thefrelative deposition of'the effluent at or beyond the SITE BOUNDARY, considering deple-tion of'the-plume during transport,'for1short
-term releases (less than or equal to 500 hrs /yr), in (meters"8)'.
Note:
For.the direction sectors:with existing pathways:
within 5 miles fromLthe site,; the appropriate R values g
are used.
If no-real pathway exists within 5 miles from the. center of the building complex, the' cow-milk R value is used, and it is assumed that this pathway g
exists at the 4.5 to 5.0 mile distance in the limiting-case sector.
If the R for an existing, pathway within-g 5 miles is less than a cow-milk Rg.at 4.5 to 5.0 miles, then the value of the cow-milk R.at 4.5 to 5.0 miles-3 P
is used. (Rev. 9.8.10.)
Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q).
ar,e generally considered to be at the approximate receptor location in lieu of the SITE BOUNDARY for L
these calculations, it is acceptable to consider the i
ingestion, inhalation, and ground plane pathways to l
coexist at.the location oflthe nearest residence with the highest value.of (X/Q).
(Ref. 9.8.10)
The Total Body; dose from ground plane deposition is added to the dose for each individual organ.
(Ref. 9.11.3) o
,,... 1 a=
t CALLAWAY PLAST OFFSITE DOSE CALCULATION MANUAL Rov. 6 TABLE 5 a
PATHWAY DOSE FACTORS (R ) FOR RADI0hTCLIDES OTHER THAN NOBLE GASES g
Inhalation Pathway y
(mrem /yr) per (vCi/m')
l l
l l Total l' l
l l
l lNuclidel Bone i
Liver i
Body l Thyroid i Kidney l Lung l GI-LLI l l H-3 l ND l1.12E3 l1.12E3 11.12E3 l1.12E3 l1.12E3 11.12E3 l
l Be-7 l8.47E2 l1.44E3 l9.25E2 l ND l ND 16.48E4 l2.55E3 l
l C-14 13.59E4 16.73E3 16.73E3 16.73E3
]6.73E3 l6.73E3 l6.73E3 l
l Na-24 l1.61E4 l1.61E4 l1.61E4 11.61E4 l1.61E4 l1.61E4 l1.61E4 l
l P-32 12.60E6 l1.14E5 l9.88E4 l
ND l
ND l
ND l4.22E4.l l Cr-51 l ND l
ND ll.54E2
]8.55El l2.43E1 l1.70E4 l1.08E3 l
l Mn-54 l ND l4.29E4 l9.51E3 l
ND l1.00E4 l1.58E6 12.29E4 l
l Mn-56 l ND l1.66EO l3.12E-1 l ND l1.67E0 l1.31E4 l1.23E5 l
l Fe-55 l4.74E4 l2.52E4 l7.72E3 l ND l ND l1.11E5 l2.87E3 l
l Fe-59 l2.07E4 l3.34E4 l1.67E4 l
ND l
ND l1.27E6 j7.07E4 l
i' l Co-57 l ND
!9.03E2 l1.07E3 l
ND l
ND l5.07ES l1.32E4 l
l Co-58 l ND l1.77E3 l3.16E3 l
ND l ND l1.11E6.l3.44E4 l
l Co-60 l ND l1.31E4 l2.26E4 l
ND l
ND 17.07E6 19.26E4 l
l Ni-63 l8.21E5 l4.63E4 l2.80E4 l
ND l
ND l2.75ES 16.33E3 l
l Ni-65 l2.99E0 l2.96E-1 l1.64E-1 l ND l ND 18.18E3 18.40E4 l
l Cu-64 l ND l1.99E0 l1.07E0 l ND l6.03E0 l9.58E3 l3.67E4 l-l Zn-65 l4.26E4 l1.13E5 l7.03E4 l
ND l7.14E4 19.95E5 l1.63E4 l
l Zn-69 l6.70E-2 l9.66E-2 l8.92E-3 l ND l5.85E-2 11.42E3 l1.02E4 l
l Br-82 l ND l ND l2.09E4 l ND l ND l ND l
ND l
l Br-83 l ND l
ND l4.74E2 l ND l
ND l
ND l
0 l
l Br-84 l ND l
ND 15.48E2 l
ND l ND l ND l
0 l
l Br-85 l ND l
ND l2.53E1 l
ND l
ND l
ND l
0 l
l Rb-86 l ND l1.98E5 l1.14E5 l ND l
ND l
ND l7.99E3 l
l Rb-88 l ND 15.62E2 13.66E2 l
ND l ND l
ND l1.72E1 l
l Rb-89 i ND 13.45E2 12.90E2 l
ND l ND l
ND l1.89E0 l
l Sr-89 l5.99ES l
ND l1.72E4 l
ND l
ND l2.16E6 l1.67E5 l
l Sr-90 l1.01E8 l
ND l6.44E6 l
ND l
ND l1.48E7 13.43E5 l
l Sr-91 l1.21E2 l
ND l4.59E0 l
ND l
ND 15.33E4 l1.74E5 l
l Sr-92 l1.31El l
ND l5.25E-1 l ND l
ND l2.40E4 l2.42E5 l
l Y-90 l4.11E3 l
ND l1.11E2 l
ND l ND l2.62E5 l2.68E5 l
CALLAk'AY PLANT OFFSITE DOSE CALCULATION hANUAL Eav. 6 TABLE 5 (Cont'd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" f
Inhalation Pathway 8
(meem/yr) per (pCi/m )
l l
{
l Total l
l l
l l
lNuclidel Bone
! Liver l
Body l-Thyroid l Kidney l Lunt 1 GI-LLI 1 l Y-91m l5.07E-1 l ND l1.84E-2 l ND l
ND l2.81E3 l1.72E3 l
l Y-91 l9.14E5 l ND l2.44E4 l ND l ND l2.63E6 l1.84E5 l
.l Y-92 l2.04El' l ND 15.81E-1 l ND l ND l2.39E4 l2.39E5 l
l l Y-93 l1.86E2 l
ND' l5.11E0 l
ND l
ND l7.44E4 13.89E5 l
)
l Zr-95 l1.90E5 l4.18E4 l3.70E4 l ND l5.96E4 12.23E6 l6.11E4 l
l Zr-97 l1.88E2 l2.72E1 l1.60E1 l
ND l3.89El l1.13E5 l3.51E5 l
l Nb-95 l2.33E4 19.18E3 l6.55E3 l ND l8.62E3 l6.14E5 l3.70E4 l
l Mo-99 l ND l1.72E2 l4.26El l ND l3.92E2.ll.35E5 l1.27E5 l
l Tc-99ml1.78E-3 l3.48E-3 l5.77E-2 l ND l5.07E-2 l9.51E2 l4.81E3 l
l Tc'-101l8.10E-5 l8.51E-5 l1.0BE-3 l ND ll.45E-3 l5.85E2 l1.63EI l
l Ru-103l2.79E3 l ND l1.07E3 l ND l7.03E3 l6.62E5 l4.48E4 j
l Ru-105l1.53E0 l ND l5.55E-1 l ND l1.34E0 l1.59E4 l9.95E4 l
l Ru-106l1.36E5 l ND l1.69E4 l ND l1.84E5 11.43E7 14.29E5 l
lAg-110ml1.69E4 l1.14E4 19.14E3 l ND l2.12E4 l5.48E6 l1.00E5 l
l Cd-109l ND l5.48E5 12.59E4 l ND l4.96E5 11.03E6 l2.7BE4 l
sml Sn-113l1.13E5 l3.12E3 l8.62E3 l2.33E3 l ND l1.46E6 l2.26E5-l l Sb-124l5.74I4 l7.40E2 l2.00E4 l1.26E2 l ND l3.24E6 l1.64E5 l
l Sb-125l9.84E4 l7.59E2 12.07E4 19.10E1 l ND l2.32E6 l4.03E4 l
lTe-125ml6.73E3 l2.33E3 19.14E2 l1.92E3 l ND l4.77ES l3.38E4 l
lTe-127ml2.49E4 18.55E3 l3.02E3 l6.07E3 l6.36E4 l1.4BE6
]7.14E4 l
lTe-127 l2.77E0 19.51E-1 l6.11E-1 l1.96E0 l7.07E0 l1.00E4 l5.62E4 l
lTe-129m[l.92E4 l6.85E3 l3.04E3 l6.33E3 l5.03E4 ll.76E6 11.82E5 l
lTe-129 l9.77E-2 l3.50E-2 l2.38E-2 l7.14E-2 l2.57E-1 l2.93E3 l2.55E4 l
lTe-131 mil.34E2 l5.92E1 l5.07El 19.77El l4.00E2 l2.06E5 l3.08E5 l
ITe-131 12.17E-2 18.44E-3 16.59E-3 11.70E-2 15.88E-2 12.05E3 11.33E3 l
lTe-132 l4.81E2 l2.72E2 l2.63E2 13.17E2 l1.77E3 l3.77E5 l1.38E5 l
lI-130 l8.18E3 l1.64E4 l8.44E3 l1.85E6 l2.45E4 l
ND l5.11E3 l
l
.lI-131 l4.81E4 l4.81E4 l2.73E4 l1.62E7 l7.88E4 l
ND l2.84E3 l
lI-132 l2.12E3 l4.07E3 l1.88E3 l1.94E5 l6.25E3 l ND l3.20E3 l
lI-133 l1.66E4 12.03E4 l7.70E3 l3.85E6 13.38E4 l
ND
[5.48E3 l
lI-134 l1.17E3 l2.16E3 19.95E2 l5.07E4 l3.30E3 l
ND 19.55E2 l
l CALIE3AY PLANT OFFSITE DOSE CALCULATION MANUAL Rav. 6 TABLE 5 (Cont'd.~)
PAThTAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Inhalation Pathway-(mrem /yr) per (VCi/m')
~
l j
l l Total l
l l
l l
lNuclidel Bone
! Liver i Bodv i Thyroid ! Kidney l Lung i GI-LLI 1 lI-135 l4.92E3 l8.73E3 l4.1*E3 l7.90E5 l1.34E4 l ND l4.44E3 l lCs-134 l6.51ES l1.01E6 12.25E5 l ND l3.03E5 l1.21E5 l3.85E3 l
lCs-136 16.51E4 l1.71ES l1.16E5 l hD l9.55E4 l1.45E4 l4.18E3 l
lCs-137 l9.07E5 18.25E5 l1.28E5 l ND l0.72E5 l1,04E5 l3.62E3 l
lCs-138 l6.33E2 l8.40E2 l5.55E2 l
ND l6.22E2 l6.81El l2.70E2 l
lBa-139 l1.84E0 l9.84E-4 l5.37E-2 l ND 18.62E-4 l5.77E3 l5.77E4 l
lBa-140 [7.40E4 l6.48E1 l4.33E3 l ND 12.11El l1.74E6 l1.02E5 l
lBa-141 l2.19E-1 l1.09E-4 l6.36E-3 l ND l9.47E-5 l2.92E3 l2.75E2 l
lBa-142 15.00E-2 l3.60E-5 l2.79E-3 l ND l2.91E-5 l1.64E3 -l2.74E0 l
lLa-140 l6.44E2 l2.25E2 l7.55El l ND l ND l1.83E5 l2.26ES l
lLa-142 11.30E0 l4.11E-1 l1.29E-1 l ND l ND l8.70E3 l7.59E4 l
-lCe-141 l3.92E4 l1.95E4 l2.90E3 l
ND l8.55E3 l5.44E5 l5.66E4 l
lCe-143 l3.66E2 ll.99E2 l2.87El l ND l8.36El l1.15E5 l1.27E5 l
lCe-144 l6.77E6 l2.32E6 l3.61E5 l ND l1.17E6 l1.20E7 l3.89E5 l
lPr-143 l1.85I4 l5.55E3 l9.14E2 l ND l3.00E3 l4.33E5 l9.73E4 l
lPr-144 l5.96E-2 l1.85E-2 13.00E-3 l ND l9.77E-3 l1.57E3 l1.97E2 l
lNd-147 11.08E4 l8.73E3 l6.81E2 l NL l4.81E3 l3.28E5 18.21E4 l
lEu-154 l1.01E7 l9.21E5 l8.40E5 l ND l4.03E6 l6.14E6 l1.10E5 l
lHf-181 l2.78E4 l1.01ES 11.25E4 l ND l2.05E4 l1.06E6 l6.62E4 l
l lW-187 l1.63E1 l9.66E0 l4.33E0 l ND l ND l4.11E4 l9.10E4 l
lNp-239 l4.66E2 l3.34E1 l2.35El l ND 19.73EI l5.81E4 l6.40E4 l
l (a) The child age group; refer to reference 9.16.6.
e
CALLAWAY PLANTJ OFFSITE DOSE CALCULATION;
^
MANUAL Rev.,6'
. );
) TABLE 5'(Cont'd.)
PATHWAY DOSE FACTORS (R ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Ground' Plane Pathway 8
I (m mrem /yr)'per-(uCi/sec)?
Ncelide Total Body Skin j
- Be-7 2.24E7:
-3.21E7
.)
Na-24L 1.19E7 1.39E7 l
Cr 4.65E6 5.51E6 Mn-54c 1.39E9
'1.63E9 Mn-56 9.03ES-1.07E6
~
.Te-59 2.72E8 3.20E8
- Co-57' 2.9BEB 4.37E8 Co-58 3.79EB 4.44E8 1
Co-60 2.15E10 2.53E10 Ni-65 2.97ES 3.45E5 j
LI:
~
Cu-64 6.07E5 6.88E5
- fr-Zn-65 7.47E8 8.59E8
-- B r-82.
3.14E7 4.49E7 Br-83 4.87E3 7.08E3 Br-84 2.03E5 2.36ES Rb-86 8.99E6 1.03E7 Rb-88 3.31E4 3.78E4 I
Rb-89 1.23E5
-1.48ES 5r-89
.2.16E4
'2.51E4-Sr-91 2.15E6 2.51E6 l
- l Sr-92 7.77ES 8'.63E5
'l Y-90 4.49E3 5.31E3 I
Y-915 3.00E5 1.16E5 Y-91 1.07E6 1.21E6 Y-92 1.80E5 2.14E5
'Y-93 1.83E5 2.51E5 Zr-95 2.45EB 2.84E8 Zr-97 2.96E6 3.44E6 Nb-95 1.37E8 1.61E8 Mo-99 3.98E6 4.62E6 L;
M
'A.y.
O
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 L
l
.m I
TABLE 5 (Cont'd.)
b PATWAY DOSE FACTORS (R ) FOR REIOWCLIDES OMR E NOBE GASES" g
Ground Plane Pathway 2
(m mrem /yr) per (pCi/sec)
Nuclide Total Body Skin Tc-99m 1.84E5 2.11E5 Tc-101 2.04E4 2.26E4 Ru-103 1.08E8 1.26E8 Ru-105 6.36E5 7.21E5 Ru-106 4.22E8 5.07E8 Ag-110m 3.4tE9 4.01E9
- Cd-209 3.76E7 1.54E8
- Sn-113 1.43E7 4.09E7
- Sb-124 8.74E8 1.23E9
- Sb-125 3.57E9 5.19E9 Te-125m 1.55E6 2.13E6 Te-127m 9.16E4 1.0SES
\\
Te-127 2.9EE3 3.28E3 Te-129m 1.98E7 2.31E7 Te-129 2.62E4 3.10E4 Te-131m 8.03E6 9.46E6 Te-131 2.92E4 3.45E4 Te-132 4.23E6 4.98E6 I-130 5.51E6 6.69E6 1-131 1.72E7 2.09E7 I-132 1.23E6 1.45E6 I-133 2.45E6 2.98E6 I-134 4.47E5 5.30E5 I-135 2.51E6 2.93E6 Cs-134 6.86E9 8.00E9 Cs-136 1.53E8 1.74E8 Cs-137 1.03E10 1.20E10 Cs-138 3.59ES 4.10E5 Ba-139 1.06E5 1.19E5 Ba-140 2.05E7 2.35E7 _
0
.CALLAVAY PLANT OFFSITE DOSE CALCULATION MANUAL Rav.'6 1
en
'. " d TABLE 5'(Cont'd.)
jf PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" j
Ground Plane Pathway.
2 (m mrem /yr)'per (pC1/sec)
-Nuclide Total Body
~ Skin Ba-141 4.15E4 4.73E4' Ba-142 4.44E4 5.06E4.'
La-140 1.92E7
-2.18E7 La-142 7.40E5 f.89ES
-Ce-141 1.37E7 1.54E7 Ce-143 2.31E6 2.63E6 Ce-144 6.96E7 8.04E7 Pr-144; 1.84E3 2.11E3 Nd-147 8.41E6 1.01E7'
- Eu-154 2.21E10 3.lfE10
. - Ef-181 1.37E8 2.82E8
-.. ~
lW-187 2.36E6 2.74E6
' \\ _: -
Np-239 1.71E6.
1.98E6
' l-(a) Refer to reference:9.16;6 for calculational details.
z n
M 3
-ws- :
__z___:;n.._-_.__-
_._-_m
_ - _. ~
CALLA':!AY PLANT OFFSITE DOSE CALCULATION MANUAL Rsv. 6 TABLE 5 (Cont 'd. )
a PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Meat Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone i Liver Bodv i Thyroid i Kidnev i Lung l GI-LLI l l H-3 l ND l2.34E2 12.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l
l Be-7 l7.37E3 l1.26E4 l8.06E3 l
ND l1.23E4 l ND 17.00E5 l
l C-14 l3.83E8 l7.67E7 l7.67E7 17.67E7 17.67E7 l7.67E7 17.67E7 l
l Na-24 l1.78E-3 l1.78E-3 l1.78E-3 l1.78E-3 l1.78E-3 11.78E-3 l1.78E-3 l l P-32 l7.41E9 l3.47E8 l2.86E8 l
ND l ND l
ND l2.05E8 l
l Cr-51 l ND l ND 18.79E3 14.88E3 l1.33E3 l8.91E3 l4.66E5 l
l Mn-54 l ND l8.01E6 l2.13E6 l
ND l2.25E6 l ND l6.72E6 l
l Mn-56 l ND l
0 l
0 l ND l
0 l ND l
0 l
l Fe-55 l4.57E8 l2.42E8 l7.51E7 l ND l ND l1.37E8 14.49E7 l
l Fe-59 l3.76E8 l6.09EB l3.03E8 l ND l ND l1.76E8 l6.34E8 l
l Co-57 l ND l5.92E6 l1.20E7 l
ND l ND l
ND l4.85E7 l
l Co-58 l ND l1.64E7 15.02E7 l
ND l
ND l ND
[9.58E7 l
l Co-60 l ND l6.93E7 l2.04E8 l ND l ND l ND l3.84E8 l
l Ni-63 l2.91E10 l1.56E9 l9.91E8 l ND l ND j ND l1.05E8 1
l Ni-65 l 0
1 0
l 0
l ND l
ND l ND l
0 l
l Cu-64 l ND l2.97E-7 11.79E-7 l ND l7.17E-7 l ND l1.39E-5 l l 2n-65 l3.75E8 l1.00E9 l6.22E8
[ ND l6.30E8 l ND l1.76E8 l
l 2n-69 l 0
1 0
l 0
[ ND l
0 l ND l
0 l
l Br-82 l ND l ND l1.52E3 l ND l ND l ND l ND l
l Br-83 l ND l ND l ND l ND l ND l ND l ND l
l Br-84 l ND l ND l
ND l
ND l ND l ND l ND l
l Br-85 l ND l
ND l ND l ND l
ND l ND l ND l
l Rb-86 l ND.
l5.82E8 l3.58E8 l ND l ND l ND l3.74E7 l
l Rb-88 l ND l
0 l
0 l ND l
ND l ND l
0 l
l Rb-89 l ND l
0 1
0 l ND l ND l ND l
0 l
l Sr-89 l4.82E8 l ND J1.38E7 l
ND l
ND l ND l1.86E7 l
[ Sr-90-l1.04E10 l ND l2.64E9 i
ND l
ND l ND l1.40E8 l
l Sr-91 12.40E-10l ND l
0 l ND l
ND l ND l5.29E-10l l Sr-92 1 0
l ND l
0 l ND l
ND l
ND l
0 l
l Y-90 l1.71E2 l ND 14.59E0 l ND l ND l ND l4.88E5 l
t
__...___.____________.____._________________m.__
L CALLAYAY PLANT l
OFFSITE DOSE CALCULATION, b
MANUAL Rev. 6 TABLE 5 (Cont'd.)
PATE'AY DOSE TACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" Meat Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone 1 Liver l Body l Thyroid i Kidnev l Lung i GI-LLI l l Y-91m ]
O l ND l
0 l ND l ND l ND l
'O l
l Y l1.80E6 l ND l4.82E4 l ND l ND l ND l2.40E8 l l Y-92 l 0
l ND l
0 l ND l ND l ND l
0
]
l Y-93 l
0 l ND J
0 l ND l ND l ' ND l1.55E-7 l l Zr-95 l2.66E6 -l5.85ES l5.21ES l ND l8.38E5 l ND l6.11E8 l
l Zr-97 l3.20E-5 14.63E-6 l2.73E-6 ] ND l6.65E-6 l ND l7.02E-1 l l Nb-95 l3.09E6 l1.20E6 l8.61ES l ND l1.13E6 l ND l2.23E9 l
l Mo-99 l ND l1.15E5 l2.84E4 l ND l2.46E5 l ND l 9.51E4 l
l Tc-99ml 0-l 0
l 0
l ND l
0 1
0 l
0 l
l Tc-101l 0
l 0
j 0
l ND l
0 l
0 l
0 l
/- -
l Ru-103l1.55E8 l ND l5.96E7 l ND l3.90EB l ND l4.01E9 l
(
l Ru-105]
O l ND l
0 i ND l
0 l ND l
0 l
l Ru-106l4.44E9 l ND l5.54E8 l ND l5.99E9 l ND l6.90E10 l lAg-110ml8.40E6 15.67E6 l4.53E6 l ND l1.06E7 l ND l6.75ES l lCd-109 l ND l1.90E6 l8.83E4 l ND l1.70E6 l
KD l6.18E6 l
_ l5n-113 l2.18E9 l4.48E7 l1.24E8 l3.31E9 l ND l ND l1.54E9 l
lSb-124 l2.93E7 l3.79ES l1.02E7 l6.45E4 l ND l1.62E7 ll.83E8 l
lSb-125 l2.85E7 12.20E5 l5.97E6 l2.64E4 l ND l1.59E7 16.80E7 l
lTe-125ml5.69ES l1.54E8 l7.59E7 l1.60E8 l ND l
KD l5.49E8 l
lTe-127ml1.77E9 la.78E8 l2.11E8 l4.24E8 15.06E9 l ND l1.44E9 l
lTe-127 l4.11E-10 l1.11E-10 l 0
l2.85E-10 l1.17E-9 l ND l1.61E-8 l lTe-129ml1.79E9 l4.99ES l2.77E8 l5.76E8 l5.25E9 l ND l2.18E9 l
lTe-129 l 0
l 0
1 0
l 0
l 0
l ND l
0 l
lTe-131ml7.00E2 12.42E2 l2.58E2 l4.98E2 l2.34E3 l ND l9.82E3 l
lTe-131 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
iTe-132 12.09E6 19.26E5 11.12E6 1: 35E6 18.60E6 l ND 19.33E6 l
lI-130 l3.04E-6 l6.13E-6 l3.16E-6 16.76E-4 19.17E-6 l ND l2.87E-6 l lI-131 l1.66E7 l1,66E7 19.46E6 15.50E9 l2.73E7 l ND l1.48E6 l
lI-132 l
0
]
O l
0 l
0 l
0 l ND l
0 l
lI-133 l6.16E-1 l7.61E-1 l2.88E-1 l1.41E2 11.27E0 l ND
[3.07E-1 l lI-134 l
0 l
0 l
0 l
0 l
0 l ND l
0 l
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL R:v 6 TABLE 5 (Cont 'd. )
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Meat Pathway 2
(m mrem /yr) per (UCi/sec) l l
l l Total l
l
[
t l
lNuclidel Bone Liver i Body l Thyroid ! Kidney I Lung l GI-LLI l lI-135 l
0 1
0 l
0 1
0 l
0 l
ND l
0 l
lCs-134 l9.22EB l1.51E9 l3.1958 l
ND l4.69E8 l1.68E8 18.16E6 l
'lCs-136 l1.61E7 l4.43E7 l2.86E7 i ND l2.36E7 13.51E6 11.56E6 l lCs-137 l1.33,E9 l1.28E9 l1.88E8 l ND l4.16E8 l1.50E8 l7.99E6 l
lCs-138 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-139 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-140 l4.38E7 l3.84E4 l2.56E6 l ND l1.25E4 12.29E4 l2.22E7 l lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142.l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 15.69E-2 l1.99E-2 l6.70E-3 l ND l ND l
ND 15.54E2 l
lLa-142 l 0
l 0
l 0
l ND l
ND l
ND l
0 l
\\
lCe-141 l2.22E4 l1.11E4 jl.64E3 l ND l4.85E3 l
ND l1.38E7 l
lCe-143 l3.17E-2 l1.72E1 l2.49E-3 l ND l7.21E-3 l ND l2.52E2 l
lCe-144 l2.32E6 l7.26ES l1.24E5 l ND 14.02E5 l ND l1.89EB j lPr-143 l3.35E4 l1.00E4 l1.66E3 l ND l5.44E3 l
ND l3.61E7 l
.lPr-144 1 0
l 0
l 0
l ND l
0 l
ND l
0 l
lNd-147 l1.17E4 l9.50E3 l7.35E2 l ND l5.21E3 l
ND l1.50E7 l
lEu-154 l1.12E7 11.01E6 l9.20E5 l ND l4.42E6 l ND l2.34E8 l
lHf-181 l4.76E6 l1.73E7 l2.15E6 l ND l3.52E6 l
ND l6.40E9 l
lW-187 l3.35E-2 l1.98E-2 l8.91E-3 l ND l ND l ND J2.79E0 l
lNp-239 l4.20E-1 l3.02E-2 l2.12E-2 l FD l8.72E-2 l ND l2.23E3 l
l (a) The child age group; refer to reference 9.16.6.
h'.
m_._
CALLAWAY PLANT OFFSITF. DOSE CALCULATION MANUAL Rsv. 6
.f TABLE 5 (Cont'd.J PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Grass-Cow-Milk Pathway 2
(m mrem /yr) per (uCi/sec) l I
I l Total I
i l
l l
lNuclidel Bone 1 Liver l Bodv l Thyroid l Kidney l Lung i GI-LLI l l H-3 l ND l1.57E3 11.57E3 l1.57E3 l1.57E3 l1.57E3 l1.57E3 l
l Be-7 l7.49E3 11.28E4 l8.19E3 l ND l1.25E4 l ND l7.11ES l
l C-14 l1.19E9 l2.39E8 12.39F8 l2.39E8 l2.39ES l2.39E8 l2.39E8 l
l Na-24 18.89E6 18.89E6 l8.89E6 l8.89E6 18.89E6 l8.89E6 l0.89E6 l.
l P-32 l7.77E10 l3.64E9 l3.00E9 l
ND l ND l ND l2.15E9 l
l Cr-51 l ND l ND l1.03E5 l5.65E4 l1.56E4 l1.04E5 l5.40E6 l
l Mn-54 l ND l2.10E7 l5.59E6 l
ND l5.68E6 l ND l1.76E7 l
l Mn-56 l ND l1.29E-2 l2.90E-3 l ND l1.56E-2 l ND l1.86E0 l
l Fe-55 l1.12E8 l5.93E7 l1.84E7 l ND l ND l3.35E7 l1.10E7 l
J Fe-59 l1.20E8 l1.94E8 l9.69E7 l
ND l
ND l5.64E7 l2.02E8 l
/.
l Co-57 1 E l3.84E6 l7.76E6 l ND l ND l ND l3.15E7 l
l Co-58 l ND ll.21E7 l3.71E7 l ND l ND l ND l7.07E7 l
l Co-60 l ND l4.32El l1.27E8 l ND l ND l ND l2.39E8 l
l Ni-63 l2.96E10 l1.59E9 l1.01E9 l
ND l ND l ND l1.07E8 l
l Ni-65 l1.66E0 l1.56E-1 l9.01E-2 l ND l ND l ND l1.91El l
l Cu-64 l @
!7.46E4 l4.51E4 l
ND l1.80E5 l ND l3.50E6 l Zn-65 14.13E9 l1.10E10 l6.85E9 l
ND l6.94E9 l ND l1.93E9 l Zn-69 l 0
l 0
l 0
l ND l
0 l ND l1.12E-9 l l Br-82 l ND l ND ll.15ES l
ND l ND l ND l ND l
l Br-83 l ND l ND l ND l ND l ND l ND l ND l
l Br-84 l ND l ND l ND l ND l
ND l ND l ND l
l Br-85 l ND l ND l ND l ND l ND l ND l ND l
l l Rb-86 l ND l8.80E9 l5.41E9 l ND l ND l ND l5.66E8 l
l l Rb-88 l ND l
0 l
0 l ND l
ND l ND l
0 l
l l Rb-89 l ND l
0 l
0 l ND l ND l ND l
0 l
l l Sr-89 l6.62E9 l ND l1.89E8 l ND l ND l ND l2.56E8 l
l Sr-90 l1.12E11 l ND
'l2.83E10 l ND l ND l ND l1.51E9 l
l Sr-91 11.30E5 l ND l4.92E3 i
ND l ND l ND l2.88E5 l
l Sr-92 l2.18E0 l ND l8.75E-2 l ND l ND l ND l4.13E1 l
j.
l Y-90 l3.22E2 l ND l8.62E0 l ND l ND l ND l9.17E5 l
s.
r*
- ese E_
CALLA'.!AY PLANT OFFSITE DOSE CALCULATION MANUAL Rsv. 6
-~
TABLE 5 (Cont 'd. )
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Grass-Cow-Milk Pathway 8
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclide!
Bone l
Liver i
Body l Thyroid'l Kidney l Lung l GI-LLI l l Y-91m l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-91 l3.90E4 l
ND l1.04E3 l ND l ND l
ND l5.20E6 l
l Y-92 l2.53E-4 l ND l7.24E-6 l ND l ND l ND 17.31E0 l
j Y-93--l1.05E0 l ND l2.90E-2 l ND l
ND l
ND l1.57E4 j
.l Zr-95 l3.83ES l8.42E2 l7.50E2 l ND ll.21E3 l
ND l8.79E5 l
1 Zr-97 l1.92E0 l2.77E-1 ll.64E-1 l ND l3.98E-1 l ND l4.20E4 l
l Nb-95 l3.18E5 l1.24E5 l8.84E4 l ND l1.16ES l ND l2.29E8 l
l Mo-99 l ND l8.14E7 l2.01E7 l ND l1.74E8 l ND l6.73E7 l
l Tc-99ml1.32E1 l2.59El l4.29E2 l
ND l3.76E2 l1.32E1 l1.47E4 l
l Tc-101l 0-l 0
l 0
l ND l
0 l
0 l
0 l
l Ru-103l4.28E3 l
ND l1.65E3 l ND l1.08E4 l
ND l1.11E5 l
l Ru-105l3.82E-3 l ND ll.39E-3 l ND l3.362-2 l ND l2.49E0 l l Ru-106l9.24E4 l
ND l1.15E4 l ND l1.25E5 l
ND l1.44E6 l
lAg-110ml2.09E8 l1.41E8 l1.13E8 l
ND l2.63E8 l ND l1.68E10 l lCd-109 l ND l3.86E6 l1 79E5 l ND l3.45E6 l
ND l1.25E7 l
- lSn-113 l6.10E8 l1.25E7 l3.48E7 l9.27E8 l
ND l ND l4.31E8 l
lSb-124 l1.08E8 l1.41E6 13.81E7 l2.40E5 l ND l6.03E7 l6.79EB l
lSb-125 18.70E7 l6.71ES l1.83E7 l8.06E4 l ND l4.85E7 l2.08E8 l
lTe-125ml7.38E7 12.00E7 l9.84E6 l2.07E7 l ND l
ND l7.12E7 l
lTe-127mi2.08E8 l5.60E7 l2.47E7 14.97E7 l5.93E8 l ND l1.68E8 l
lTe-127 l3.05E3 18.22E2 16.54E2 l2.11E3 l8.67E3 l ND l1.19E5 l
lTe-129ml2.71E8 l7.57E7 l4.21E7 18.74E7 17.96E8 l ND 13.31ES l
lTe-129 i O
l 0
l 0
l 0
l2.90E-9 l ND l6.17E-8 l JTe-131ml1.60E6 l5.53E5 15.89E5 l1.14E6 l5.35E6 i
ND l2.24E7 l
lTe-131 1 0
l 0
l 0
l 0
1 0
l ND l
0 l
iTe-132 11.02E7 14.52E6 15.46E6 16.58E6 14.20E7 l
ND 14.55E7 l
lI-130 l1.73E6 l3.49E6 l1.80E6 l3.84EB l5.22E6 l
ND l1.63E6 l
lI-131 l1.30E9 l1.31E9 l7.45E8 l4.33E11 l2.15E9 l
ND l1.17E8 l
lI-132 16.02E-1 l1.11E0 l5.08E-1 l5.13E1 l1.69E0 l ND l1.30E0 l
lI-133 11.74E7 l2.15E7 l8.13E6 l3.99E9 l3.58E7 l
ND 18.66E6 l
lI-134 l
0 l
0 l
0 l
0 l
0 l ND j
0 l
CALLA'.!AY PLANT OFFSITE DOSE CALCULATION MANUAL Rav. 6 f*
TABLE 5 (Cont 'd. )
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Grass-Cow-Milk Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
- lNuclidel Bone I
Liver I Body 1 Thyro!.d l Kidney i Lung l GI-LLI l lI-135 l5.40E4 19.72E4 l4.60E4 18.61E6 l1.49ES
-l ND l7.40E4-l-
7 lCs-134 l2.26E10 l3.72E10 l7.84E9 l ND l1.15E10 l4.13E9 12.00E8-l lCs-136 l1.01E9 l2.77E9 l1.79E9 l
ND l1.48E9 l2.20E8 l9.74E7 l
lCs-137 13.22E10 l3.09E10 14.56E9 l ND l1.01E10 l3.62E9 l1.93E8 l
lCs-138 l 0
l 0
{
0 l ND l
0 l
0 l
O' l
lBa-139 l1.89E-7 l 0
l5.48E-9 l~ ND l
0 1
0 l1.09E-5 l lBa-140 l1.17E8 l1.03E5 i6.84E6 l ND l3.34E4 l6.12E4 l5.93E7 l
lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 l1.95El l6.80E0 12.29E0 l ND l ND
~ l ND l1.90E5 l
lLa-142 l 0
l 0
l.
0 l ND l ND l ND l2.90E-6 l
\\
lCa-141 l2.19E4 l1.09E4 l1.62E3 J ND 14.76E3 l ND ll.36E7 l
lCe-143 l1.87E2 l1.02E5 l1.47El l ND l4.26El l ND l1.49E6-l lCe-144 l1.62E6 l5.09E5 18 66E4 l ND l2.82E5 l ND l1.33E8 l
lPr-143 17.19E2 l2.16E2 l3.57El l
ND l1.17E2 l ND l7.75E5 l
lPr-144 l 0-l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 14.45E2 13.61E2 12.79El l ND l1.98E2 l ND
.l5.71E5 l
lEu-154 l 9.41E4 l8.47E3 l7.73E3 l ND l3.72E4 l
ND l1.97E6 l
lHf-181 l6.43E2 l2.35E3 l2.90E2 l ND l4.75E2 l ND 18.65E5 l
lW-187 l2.91E4 l1.73E4 l7.73E3 l
ND 1 ND l ND l2.42E6 l
lNp-239 11.72E1 l1.23E0 18.68E-1 l ND 13.57E0 l ND l9.14E4 l
j (a) The child age group; refer to reference 9.16.6.
.___a.
~ -.-- -. -. - - - -
2
-CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL.
Rsv. 6 1i TABLE 5 (Contd. ) -
I' a
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES j
1 Grass-Goat-Milk Pathway (m* mrem /yr) per (VCi/sec) l
.-l-l.
l Total l
l l
1.-
.l~
lNuclidel Bone l ' Liver l-Body l Thyroid l Kidney l Lung l GI-LLI l l H 1. ND l3.20E3.
l3.20E3 l3.20E3 13.20E3 l3.20E3 l3.20E3 l
-l Be-7 l8.98E2 l1.53E3' 19.82E2 l
ND-l1.50E3 l ND l8.53E4 l
l l C 11.19E9..l2.39E8 l2.39E8 l2.39E8 l2.39ES,-l2.39E8 l2.39E8 l
i l Na-24'll.07E6 l1.0?E6 l1.07E6 -l1.07E6 l1.07E6-l1.07E6
[1.07E6 l'
l
'l P-32 l9.33E10 l4.37E9. -l3.60E9 l
ND l. ND
~l ND-l2.58E9 l
l l.' Cr-51. l ND l ND
'll.23E4 16.78E3 l1.87E3 l1.25E4 l 6 ~.48E5 l
.j l Mn-54 l ND l2.52E6 l6.70E5 l ND l7 06E5 l ND l2.11E6' l l Mn-56 l ND 11.54E-3' l3.49E-4 l ND l1.87E-3 l ND.
l2.24E-1 l l Fe-55 l1.45E6 l7.71ES l2.39E5' l ND
.l ND
]4.36E5 l1.43E5 -l
- J
-l Fe-59 l1.56E6 l2.53E6 l1.26E6 l ND l ND l7.33E5 l2.63E6 l.
j.
- l Co-57 l. ND.
l4.60E5 l9.31ES l ND l ND l ND
-l3.77E6 -l l Co-58 l ND l1.45E6-l4.45E6 l ND l ND l ND l8.49E6 l-l Co-60 l.
ND l5.18E6 l1.53E7 l ND l ND
[ ND l2.87E7
.l-l Ni-63 13.56E9 l1.90E8 l1.21E8 l ND l ND l ND -
l1.28E7 l
l'Ni-65 l1.99E-1 jl.87E-2 l1.09E-2 l ND l ND l ND l2.29EO. ]
l.Cu-64 l ND 18.31E3-l5.02E3 l
ND l2.01E4 l ND
[3.90E5 l.
l Zn-65 l4.96E8 l1.32E9 l8.22E8 l ND l8.33E8 l ND l2.32E8 l
l Zn-69 l 0
l 0
l 0
l ND l
0 l ND l1.35E-101
-l Br-82 l ND l ND l1.38E7 l ND l ND l ND l ND l.
l Br-83 l ND l ND l ND l ND l ND l ND l ND l.
l Br-84 l ND l ND l ND l ND l
ND.
l - ND -
l ND
[
1.Br-85 l ND l ND l ND l ND l ND l ND l
ND l
l:Rb-66 l ND jl.06E9 l6.50E8 l @
l ND l ND
.l6.80E7 l.
J Rb-88.] ND l
0 l
0 l ND l ND
.l ND l
0 l
l'Rb 89 l ND l
0 l
0 l ND l ND l ND l
0 l
l Sr-89 11.'i9E10 i ND 13.97E8 i ND l ND l ND 15.38E8 l
l Sr-90 l2.35E11~l ND l5.95E10 l ND l ND l ND l3.16E9 l
l Sr-91 l2.74E5 l ND l1.03E4 l ND l ND l ND l6.04E5 l
a l
.l
7 CALLAWAY PLANT-OFFSITI DOSE CALCULATION s
MANUAL Rsv. 6
- (
TABLE 5 (Contd. )
a' PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBII. GASES g
Grass-Goat-Milk Pathway 2
(m mrem /yr):per (pCi/sec) l
. l.
l
- l. Total _ l
-l
_ l l
l lNuclidel-Bone l
Liver l' Body l Thyroid l'Kidnev i Lung i GI-LLI l l'Sr-92 l4.58E0 l ND l1.84E-1 l ND l ND l ND l8.68E1 l
l Y l3.87El l-ND l1,03E0
.l.
ND l' ND l-ND ll.10E5' l' l_Y-91m'l' O
l ND l
0 J ND l ND l ND l
0.
l 1 Y l4.68E3 j ND l1.25E2. l ND l ND
~l ND l6.24E-5_l l Y-92 [3.04E-5 l ND:
l8.69E-7 l ND l
ND.
l ND 18.77E-1 l.
-l:Y-93 l1.27E-1.] 1G) l3.48E-3 l ND l ND l
ND l1.89E3' l l Zr-95 l4.60E2 -l1.01E2 l9.00E1 l ND l1.45E2 l ND
'll.05ES l
l-Zr-97-l2.30E-1 l3.33E-2--11.96E-2 l ND l4.78E-2 i ND l5.04E3 l
l Nb-95 l3.81E4-l1.48E4 l1.06E4 l ND l1.39E4 -l ND l2.75E7 l
l Mo-99 l. ND l9.76E6-l2.42E6' l ND l2.09E7 l
ND-18.08E6 l
f' l Tc-99ml1.59E0 l3.11E0 l5.15El l ND l4.52E1 l1.58E0 l1.77E3 l
f i
l Tc-101l 0
l 0
l 0
l ND l
0 l
0 1
0 l-l~Ru-103l5.14E2 l ND l1.98E2 l ND l1.29E3 l ND l1.33E4 l
l Ru-105l4.58E-4 l ND l1.66E-4 l ND l4.03E-3 l ND l2.99E-1 j l Ru-106l1.11E4 j ND l1.38E3 l ND l1.50E4 l ND jl.72E5 l
l Ag-110ml2' 51E7 l1.69E7 l1.35E7 l ND l3.15E7-l ND l2.01E9. l
- lCd-109 l' ND l4.63E5 l2.15E4 l ND l4.13E5 l ND l1.50E6 l
~ lSn-113 17.32E7 l1.50E6 l4.17E6 l1.11E8
.l ND l ND l5.17E7 l
- lSb-124 l1.30E7 l1.69E5_
l4.56E6 l2.87E4 l ND l7.22E6 l8.14E7 l
~ lSb-125 l1.04E7 l8.04E4 l2.19E6 19.66E3 l ND l5.81E6 l2.49E7 l
lTe-125ml8.85E6 l2 40E6-jl.18E6 12.48E6 l ND l ND l8.54E6 l
lTe-127ml2.50E7 l6.72E6 l2.96E6 15.97E6 l7.12E7 l ND l2.02E7 l
~lTe-127 l3.66E2 -l9.86El 17.85El l2.53E2 l1.04E3 l ND l1.43E4 l lTe-129ml3.25E7 l9.09E6 l5.03E6 l1.05E7 l9.55E7 l ND l3.97E7 l
lTe-129 l 0
l 0
l 0
l
.0 l
0 l ND l7.40E-9 l lTe-131 mil.92E5 16.64E4 17.07E4 l1.37E5 l6.43E5 l ND l2.69E6 l lTe-131 l 0
l 0
l 0
[
0 l
0 l ND l
0 l
lTe-132 l1.23E6 l5.42E5 l6.55E5 l7.90E5 l5.04E6 l ND l5.46E6 l
_lI-130 l2.07E6 l4.19E6 l2.16E6 14.61ES l6.26E6 1 ND ll.96E6 l
. _. - L=
CALLAWAY PLANT OFFSITI DOSE CALCULATION.
-l I
MANUAL Rev. 6 p+.
TABLE 5 (Contd.)
a i
. PATHWAY DOSE FACTORS (R ) FOL
- RADIONUCLIDES OTHER THAN NOBLE GASES f
Grass-Goat-Milk Pathway 2
(m mrem /yr) per (vCi/sec) l l
l l Total l
l l
l l-lNuclidel Bone Liver l
Body l Thyroid i Kidney l Lung i GI-LLI I lI-131 l1.56E9 l1.57E9 l8.94E8 l5.20E11 l2.5BE9 l
ND l1.40E8 l
lI-132 17.22E-1 l1.33E0 l6.10E-1 l6.15El l2.03E0 l
ND l1.56E0 l lI-133 l2.09E7 l2.58E7 l9.76E6 l4.79E9 l4.30E7 l ND l1.04E7 l
lI-134 l
0 1
0 l
0 l
0 l
0 l ND l
0 l
lI-135 l6.48E4 l1.17E5 l5.52E4 l1.03E7 l1.79ES l
ND 18.88E4 l
lCs-134'l6.79E10 l1.11E11 l2.35E10 l ND l3.45E10 l1.24E10 l6.01E8 l
lCs-136 l3.03E9 l8.32E9 l5.38E9 l
ND l4.43E9 l6.61E8 l2.92E8 l
lCs-137 l9.67E10 (9.26E10 l1.37E10 l ND l3.02E10 l1.09E10 l5.80E8 l
lCs-138 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-139 l2.27E-8 l 0
l 0
l ND l
0 l
0 l1.31E-6 l lBa-140 l1.41E7 l1.23E4 l8.20E5 l
ND l4.01E3 l7.34E3 l7.12E6 l
\\
lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 l2.34E0 l8.17E-1 l2.75E-1 l ND l
ND l
ND 12.28E4 l
lLa-142 l 0
l 0
l 0
l ND l
ND l
ND l3.49E-7 l lCe-141 l2.62E3 l1.31E3 l1.94E2 l-ND l5.74E2 l
ND l1.63E6 l
lCe-143 l2.25El l1.22E4 l1.77E0 l
ND l5.12E0 l
ND l1.79ES l
lCe-144 l1.95E5 l6.11E4 l1.04E4 l ND l3.38E4 l ND l1.59E7 l
lPr-143 18.62E1 l2.59El l4.28E0 l ND l1.40E1 l
ND l9.30E4 l
lPr-144 l 0
l 0
l 0
l ND l
0 l
ND l
0 l
lNd-147 15.34E1 14.33E1 l3.35E0 l
ND l2.37El l
ND l6.85E4 l
-lEu-154 l1.13E4 l1.02E3
!9.27E2 l ND l4.46E3 l
ND l2.36E5 l
-lHf-181 17.71El l2.81E2 l3.4BE1 l
ND l5.70E1 l ND l1.04E5 l
lW-187 l3.49E3 12.07E3 19.27E2 l ND l
ND l
ND l2.90E5 l
lNp-239 l2.06E0 l1.48E-1 l1.04E-1 l ND l4.28E-1 l N7 l1.10E4 l
l (a) The child age group; refer to reference 9.16.6.
r v.,.
T CALLAVAY PLANT OFFSITE DOSE CALCULATION MANUAL
.Rav. 6
~
d TABLE 5 (Contd.)
a PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 8
(m mrem /yr) per (pCi/sec) l l
1 1 Total l
l l
l l
lNuclidel Bone 1 Liver i Body l Thyroid i Kidney l Lung l GI-LLI l l H-3 l
ND.
l4.01E3 l4.01E3 l4.01E3 l4.01E3 l4.01E3 l4.01E3 l
l Be-7 ~l3.3BE5 l5.76E5 l3.70E5 l ND l5.64E5 l ND l3.21E7 l
l C-14 l8.89ES l1.78E8 l1.78E8 l1.78E8 l1.78E8 l1.78E8 l1.78E8 l
l Na-24 13.75E5 l3.75E5 13.75ES l3.75E5 13.75E5 13.75E5 13.75E5 l
l P-32 l3.37E9 l1.57E8 l1.30E8
] ND l ND l ND l9.30E7 l
l Cr-51 l ND l
ND l1.17E5 l6.50E4 l1.78E4 l1.19ES l6.21E6 l
l Mn-54 l ND l6.65ES 11.77E8 l ND l1.86E8 l ND 15.58E8 l
l Mn-56 l ND l1.88E1 l4.24E0 l ND l2.27El l
ND l2.72E3 l
l Fe-55 l8.01EB l4.25E8 l1.32E8 l
ND l ND l Fe-59 l3.97ES l6.43E8 l3.20E8 l ND l ND
^l2.40E8 l7.87E7 l
l1.85E8 l6.69E8 l
l Co-57 l ND l2.98E7 l6.04E7 l
ND l ND l
ND l2.45E8 l
\\
l Co-58 l ND l6.44E7 l1.97ES l ND l ND l ND l3.76E8 l
l Co-60 l ND l3.78E8 11.12E9 l ND l ND l ND l2.10E9 l
l Ni-63 13.95E10 l2.11E9 l1.34E9 l
ND l ND l ND l1.42E8 l
l Ni-65 l1.05E2 l9.89E0 l5.77E0 l ND l ND l ND l1.21E3 l
l Cu-64 l ND l1.10E4 l6.64E3 l
ND l2.66E4 l
ND l5.16E5 l
l 2n-65 l8.12E8 l2.16E9 l1.35E9 l ND ll.36E9 l ND l3.80E8 l
l 2n-69 l1.09E-5 l1.57E-5 l1.45E-6 l ND l9.52E-6 l ND 19.11E-4 l l Br-82 l ND l
ND l2.04E6 l
ND l ND l ND l
ND l
l Br-83 l ND l ND
[5.37E0 l ND l ND l ND l
0 l
l Br-84 l ND l
ND l
0 l ND l ND l ND l
0 l
.l Br-85 l ND l
ND l
0 l ND l ND l ND l
0 l
l Rb-86 l ND 14.58E8 l2.82E8 l
ND l
ND l ND 12.94E7 l
l Rb-88 l ND l
0 l
0 l ND l ND l ND l
0 l
l Rb-89 l ND l
0 l
0 l ND l ND l ND l
0 l
l Sr-89 13.59E10 1 ND 11.03E9 i ND 1 ND l
ND ll.39E9 l
l Sr-90 l1.24E12 l ND l3.15E11 l ND l ND l ND l1.67E10 l l Sr-91 l5.24E5 l ND l1.98E4 l ND l ND l ND l1.16E6 l
l Sr-92 l7.28E2 l ND l2.92E1 l ND l
ND l
ND l1.38E4 l
l Y-90 l2.31E4 l
ND l6.18E2 l
ND l
ND l
ND l6.57E7 l
t
l-CALLA'.iAY PLANT
-0FFSITE DOSE CALCULATION MANUAL Rev. 6 TABLE 5 (Contd.)
a PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclidei Bone i Liver i Body l Thyroid'l Kidnev i Lung i GI-LLI l l Y-91m l8.87E-9 l ND 13.23E-10l ND l ND l ND l1.74E-5 l l Y-91 _l1.86E7 l ND l4.99E5 l ND l ND l ND l2.48E9 l
l Y-92 l1.58E0 l ND l4.53E-2 l ND l ND l ND l4.58E4 l
l Y-93 13.01E2 l ND 18.25E0 l ND l ND l ND l4.48E6 l.
l Zr-95 l3.86E6 l8.45E5 l7.55E5 l ND l1.21E6 l ND l8.84EB l
l Zr-97 l5.70E2 18.24E1 l4.86El l ND l1.18E2 l ND (1.25E7 l
l Nb-95 14.10E5 l1.59E5 l1.14E5 l ND l1.50E5 l ND l2.95E8
[
l Mo-99 l ND l7.71E6 l1.91E6 l ND l1.65E7 l ND j6.38E6 l
l Tc-99ml4.71E0 l9.24E0 ll.53E2 l ND l1.34E2 l4.6SE0 l5.26E3 l
l Tc-101l 0
l 0
l 0
l ND l
0 l
0 l
0 l
l Ru-103l1.54E7 l ND l5.90E6 l ND l3.87E7 l ND l3.97EB l
l Ru-10519.16El l ND l3.32E1 l ND l8.05E2 l ND 15.98E4 l
l Ru-106l7.45E8 l ND l9.30E7 l ND l1.01E9 l ND l1.16E10 l lAg-110ml3.22E7 l2.17E7 l1.74E7 l ND l4.05E7 l ND l2.58E9 l
l
.lCd-109 l ND l2.45E8 l1.13E7 l ND l2.18E8
[ ND
[7.94E8 l
ISn-113 l1.58E9 l3.25E7 l9.00E7 l2.40E9 l ND l ND l1.12E9 l
)
lSb-124 l3.52E8 14.56E6 l1.23E8 l7.76E5 l ND l1.95E8 l2.20E9 l
l lSb-125 l4.99ES l3.85E6 l1.05E8 14.62E5 l hT l2.78E8 l1.19E9 l
lTe-125ml3.51ES 19.50E7 l4.67E7 l9.84E7 l ND l ND l3.38E8 l
lTe-127ml1.32E9 l3.56ES l1.57E8 l3.16E8 l3.77E9 l ND l1.07E9 l
1 lTe-127 l1.00E4 l2.69E3 l2.14E3 l6.91E3 l2.84E4 l ND l3.90E5 l
l lTe-129ml8.38E8 12.34E8 l1.30EB l2.70E8 l2.46E9 l ND l1.02E9 l
lTe-129 l1.16E-3 l3.23E-4 l2.75E-4 l8.26E-4 l3.39E-3 l ND l7.20E-2 l
.)
lTe-131 mil.54E6 l5.33E5 l5.68E5 l1.10E6 l5.16E6 l ND l2.16E7 l
lTe-131 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lTe-132 l6.98E6 l3.09E6 13.73E6 14.50E6 l2.87E7 l ND l3.11E7 l
lI-130 l6.16ES l1.24E6 l6.38E5 l1.37E8 l1.86E6 l ND l5.79E5 l
lI-131 l1.43E8 l1.44E8 l8.17E7 l4.75E10 l2.36ES l hT l1.28E7 l
lI-132 l8.58E1 l1.58E2 l7.25El 17.31E3 l2.41E2 j hT 11.86E2 l
lI-133 l3.56E6, l4.40E6 l1.67E6 l8.18E8
[7.34E6 l ND ll.77E6 l
lI-134 l1.55E-4 l2.88E-4 l1.32E-4 l6.62E-3 l4.40E-4 l ND l1.91E-4 l q
lI-135 l6.62E4 11.13E5 l5.33E4 19.97E6 l1.70E5 l ND 18.58E4 l
l
/
i l I
l i
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rsv. 6 TABLE 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR. RADIONUCLIDES OTHER THAN NOBLE GASES" g
Vegetation Pathway 8
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone l Liver l
Body i Thyroid i Kidney I Lung l GI-LLI l lCs-134 l1.60E10 12.63E10 l5.55E9 l
ND l8.15E9 l2.93E9 l1.42E8 l
lCs-136 l8.17E7 l2.25EB l1.45E8 l ND l1.20E8 l1.78E7 l7.90E6 l
lCs-137 l2.39E10 l2.29E10 l3.38E9 l ND l7.46E9 l2.68E9
[1.43E8 l
lCs-138 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-139 l4.80E-2 l2.56E-5 l1.39E-3 l ND l2.24E-5 l1.51E-5 l2.77E0 l
lBa-140 l2.77E8 -l2.42E5 l1.62E7 l
ND l7.89E4 l1.45E5 l1.40E8 l
lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
l 0
l ND l
0 1
0 l
0 l
lLa-140 l3.25E3 l1.14E3 l3.83E2 l ND l ND l ND l3.17E7 l
lLa-142 l2.50E-4 l7.98E-5 l2.50E-3 l ND l
ND l
ND.
l1.58E1 l
I lCe-141 l6.56E5 l3.27E5 l4 86E4 l ND l1.43E5 l ND l4.08E8 l
,(
lCe-143 l1.72E3 l9.31E5 l1.35E2 l ND l3.91E2 l ND l1.36E7 l
lCe-144 l1.27ES l3.98E7 l6.78E6
[ ND l2.21E7 l ND l1.04E10 l lPr-143 l1.46E5 l4.38E4 17.25E3 l ND l2.37E4 l ND l1.58E8 l lPr-144 l 0
l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 l7.17E4 l5.81E4 l4.50E3 l
-lEu-154 l1.66E8 ll.50E7 l1.37E7 l ND l6.57E7 l ND l3.48E9 l
lHf-181-l4.90E5 l1.79E6 12.21E5 l ND l3.62E5 l
ND-l6.59E8 l
lW-187 l6.47E4 l3.83E4 l1.72E4 l ND l ND l ND l5.38E6 l
lNp-239 12.55E3 l1.83E2 11.29E2 l
ND l5.30E2 i ND l1.36E7 l
l-(a) The child age group; refer to reference 9.16.6.
i 4
r CALLAWAY PLA.NT OFFSITE DOSE CALCULATION MANUAL Rtv. 6 The cumulative critical organ doses for a monthly, quarterly or annual evaluation are based on the calcu-lated dose contribution from each specified time period occurring during the reporting period.
3.6 Gaseous Radwaste Treatment Svstem 3.6.1 Technical Specification 3.11.2.4 1
The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY would exceed:
l a.
O.2 mrad to air from gamma radiation, or b.
0.4 mrad to air from beta. radiation, or c.
O.3 mrem to any organ of an Individual 3.6.2 Description of the Gaseous Radwaste Treatment System
'~
The gaseous radwaste treatment system and the ventila-l i
tion exhaust system tre available for use whenever gaseous effluents require treatment prior to being l
released to the environment.
The gaseous radwaste 1
treatment system is designed to allow for the retention l
of all gaseous fission products to be discharged from 1
The retention system con-sists of eight (8) waste gas decay tanks, six (6) for use during normal operations and two (2) for use during I shutdown conditions.
Normally, waste gases will be l retained for at least 60 days prior to discharge.
These systems will provide reasonable assurance that the releases of radioactive materials in gaseous ef-fluents will be kept ALARA.
f~
j; 1
)
I i
___.._u____.___
J
t L
-CALLAWAY PLANT L
-0FFSITE DOSE CALCULATION h
MANUAL Rev. 6 Y
j ~
3.6.3,. OPERABILITY of the Gaseous Radwaste Treatment.
System.
e.
4
- The. OPERABILITY of.~the gaseous.radwaste treatment'sys-tem ensures this system will be available for use when gases require treatment prior to their release tojthe:
environment.. OPERABILITY is demonstrated:through com-
'pliance.with. Technical' specifications-3.11.2.1,.
~3~11 2 2, and 3.11.2.3.
Projected doses.(gamma air, beta air,.and organ dose) due to gaseous effluents at or beyond the SITE, BOUNDARY are' determined each 31 days by dividing the cumulative
- annual total by the number of elapsed months.-
.. O 9.
JY t
- r..
[
L
_m____
.m
__m-
-n--m..-
' gg -
iCALLAWAY PLANT [
i OFFSITELDOSE CALCULATION
-MAEUAL:
Rev.'6' x
4.0 DOSE AND-DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 4.1 Technidal'S' specification 3.11.4 The annual;(calendar' year)' dose.or dose commitment toi any MEMBER OF THE PUBLIC due~to releases of radioactiv-it'y:and.to: radiation from uranium fuel. cycle 1 sources shallibe limited to-less than.or equalito 25 mrem to Ethe total' body or any organ, exceptLthe thyroid,=which
-shall be limited to less than or equal'to 75: mrem.
4.2L Calculation of Dose and Dese' Commitment from Urs-nium-Fuel > Cycle Sources LThe annual-dose or dose commitment to a MEMBER OF.THE PUBLIC for Uranium Fuel Cycle Sources;is determined as:
a)'
Dose'toDthe tot'al body and internal organs due to gamma ray exposure from submersion in a
. cloud'of radioactive noble gases,Lground plane exposure, and-direct radiation from the Unit
-and'outside storage tanks; g
(n b):
Dose to thefskin due to beta radiation from submersion in a cloud of radioactive noble gases, and ground plane expor.ure;.
c)
Thyroid dose due to inhalation and ingestion of radiciodines; and d)
. Organ dose due to inhalation and ingestion of
. radioactive material.
~It is assumed-that total body dose from. sources of gamma: radiation irradiates internal body organs at the same' numerical rate. (Ref. 9.12.5)
The dose from gaseous effluents is considered to be the summation of the dose at the individual's. residence and' the dose to-the individual from activities within the OITC OOUNOARY.
f; l
I
-[,
[
\\_
L lt
-f
.y' L_
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 j
Since the doses via liquid releases are very conserva-tively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways.
Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190.
(Ref. 9.12.3)
]
It should be noted that there are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant.
4.2.1 Identification of the MEMBER OF THE PUBLIC i
The MEMBER OF THE PUBLIC is considered to be a real in-dividual, including all persons not occupationally as-sociated with the Callaway. Plant, but who may use por-tions of the-plant site for recreational or other pur-poses not associated with the plant.
(Ref. 9.4 and 9.8.11.)
Accordingly, it is necessary to characterize this $ndividual with respect to his utilization of areas both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CFR 190 through the use of more realistic assumptions.
(Ref. 9.12.3 and 9.12.4) f.
The evaluation of Total Dose from the Uranium Fuel Cy-cle should concider the dose to two Critical Receptors:
a) The Nearest Resident, and b) The Critical Receptor within the SITE BOUNDARY.
4.2.2 Total Dose to the Nearest Resident The dose to the Nearest Resident is due to plume expo-sure from noble gases, ground plane exposure, and in-halation and ingestion pathways.
It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.
I l
l L
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 1
r It'is assumed that direct radiation dose from operation of the Unit and outside storage tanks, and dose from gaseous effluents due to activities within the SITE BOUNDARY, is negligible.for the Nearest Resident.
The total Dose from the Uranium Fuel Cycle to the Nearest r
Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q.
13ue. location of the Nearest Resident in each meteorlog-
'ical sector is determined from the Annual Land Use Cen-sus conducted in accordance with the Requirements of Technical Specification 3.12.2.
4.2.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Con-servation for management of the residual lands sur-rounding the Callaway Plant, including some areas within the SITE B.OUNDARY.
Under the terms of this agreement, certain areas have been opened to the public
<~-
for low intensity recreational uses (hunting, hiking, i,
sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant. site (Refer to Figure 4.1).
Much of the residual lands within the SITE BOUNDARY are' leased to area farmers by the Depart-ment of Conservation to provide income to support management and development costs.
Activities conducted under these leases are primarily comprised of farming (animal feed), grazing, and forestry.
(Ref 9.7.2, 9.7.4, 9 14, 9.14.1).
Based on the utilization of areas within the SITE BOUN-DARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the SITE BOUNDARY is due to exposure incurred while conducting his farming activities.
The current tenant has estimated that he spends approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in this area (Ref 9.5.6).
Occupancy of areas within the SITE BOUNDARY is assumed to be averaged over a period of one year.
,I -
CALLAWAY PLANT OFFSITE DOSE CALCULATION p
MANUAL Rev. 6 p.
Any reevaluation of assumptions.should include a reev-aluation of the occupancy period at the locations of real exposure (e.g. a real~ individual would not simultaneously exist at each point of maximum exposure).
4.2.3.1 Total Dose to the Farmer from Gaseous Ef-fluents
.The Total Dose to the farmer from gaseous effluents is calculated using the methodology discussed in Section-3, utilizing concurrent meteorological data at the, farmer's residence and historical meteorological data from Table,10 for activities within the' SITE BOUNDARY.
These dispersion parameters were calculated-by assuming that the farmer's time is equally distributed over.the l areas farmed within the SITE BOUNDARY, and already have l the' total occupancy of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> / yea'r factored into
~ l' their value (Ref. 9.5.7).
The residence ~of the current tenant is located.at a l distance of 3830 meters in the SE sector.
No meat or milk animals or vegetable gardens were identified by the 1987 Land Use Census for this location, therefore,
/^
the gaseous effluents dose at the farmer's residence is
(
due to plume exposure from Noble Gases.and the ground plane and inhalation pathways.
It is assumed that food ingestion pathways do not exist within the SITE BOUNDARY, therefore the gaseous ef-fluents dose within the SITE BOUNDARY is due to plume exposure from Noble Gases and the ground plane and in-halation pathways.
4.2.3.2 Total Dose from Direct Radiation 4.2.3.2.1 Direct Radiation Dose from Outside Storage Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioac-tive materials, and constitutes the only potentially
.43ut 4mmu. source of direct radiation dose from out-side storage tanks to a MEMBER OF THE PUBLIC. (Ref.
9.6.17, 9.6.18, 9.6.19, and 9.6.20.)
F _
--__.___m__.-..m.m___-
_ _._m.___.
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rrty. 6 Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by signifi-cant plant structures.
This has been determined to be 450 meters from the RWST.
The RWST is a right circular cylinder approximately 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters.
(Ref. 9.6.20.)
The walls are of type 304 stainless steel and have an average thickness of.87 cm.
(Ref. 9.16.1.)
The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and at-tenuation within the volume source.
Appropriate metho-dology for calculating the dose rate from a volume source is given in TID-7004, " Reactor Shielding Design Manual" (Ref. 9.19).
The computer program ISOSHLD (Ref. 9.20, 9.21, 9.22) will normally be utilized to perform this calculation.
h.-._--------
CALLAWAYLPLANT OFFSITE DOSE CALCULATION-MANUAL Rev. 6
- 4.2.3.'2.2-Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit-to a~
- MEMBER OF THE PUBLIC.'has been determined to be 7E-2..
. mrads/ calendar. year, based on a point source:of primary coolant N-16 in the steam generators.
This-source term was then-projected onto-the.inside surface of-the con-tainment dome, taking-credit for shielding provided by the containment dome and-for' distance. attenuation.
No credit was allowed for shielding-by other structures'or components.
The number of gammas per-second.was gener-ated and then converted to a dose rate at.the given distance by use of ANSI /ANS-6.'6.1, " Calculation and Measurement of-Direct and Scattered Gamma Radiation from LWR Nuclear Power Plant 1979"., which considers at-tenuation and buildup in air.
The final value is based on one unit. operating at 100% Power.
The" distance was; determined to be 367 meters, which is approximately-the closest point of.the boundary of the-Owner Controlled.
-Area fence.which is.not obscurred by significant plant
-structures.
(Ref. 9.16.4)
The maximum direct radiation dose from the Unit to a
~
- MEMBER OF THE PUBLIC due to-activities within the SITE BOUNDARY is thus approximately 9E-3 mrads per year, as-Ni <
suming a maximum occupancy of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year.
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CALLAWAY PLANT' f
e 6
a OFFSITE DOSE; CALCULATION
-l MANUAL Rsv.' 6 a
VH 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING l
1 1
5.1 Radiological Effluent Technical Soecifica-
- tion 3.12.1 11 The radiological environmental l monitoring program'shall g
be conducted as specified in Technical Specification' l
Table 3.12-1.
't i
ll
- 5. 2 '
Description of-the Radiological Environmen-tal Monitoring Program j
'l The Radiological Enviormental Monitoring Program is An-tended to_act as a background data base _for preopera-tion.and to supplement the radiological effluent release monitoring program during plant operation.
Radiation exposure.to the public from the'various spe--
s cific-pathways'and. direct radiation can be adequately j
evaluated by this program.
Some-deviations'fromLthe' sampling frequency may be necessary'due-to seasonal unavailability,~ hazardous
-conditions, or other legitimate bases.
Efforts are made to obtain all required samples within time frame f~
outlines.
Any deviation (s) in sampling frequency or 3
location is documented in the Annual Radiological En -
vironmental Operating Report.
N The Environmental samples are collected and analyzed at the' frequency outlined in Table 6.
Reporting levels-and lower limits of detection (LLD) are given in Tables.
7 and 9.
L Airborne, waterbore, and ingestion samples collected
- 1 under the monitoring progra'm are analyzed by an inde-pendent, third-party laboratory.
This laboratory is required to participate in the Environmental-Protection a
Agency's (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program or an equivalent program.
Participation includes all of the 1 determinations (sample. medium - radionuclides combina--
tion) that are' offered by the EPA.and that are also in-uludad - lu the meultering program.
-1
~ 7 w-
CALLA 14AY PLANT OFFSITE DOSE CALCULATION MANUAL Rev.
6-1
- 5 '. 3 Performance Testiner of Environmental' Ther-moluminescence Dosimeters Thermoluminescence Detectors (TLD's)'used in the En-vironmental Monitoring Program are tested for accuracy and precision to demonstrate compliance with Regulatory-Guide 4.13. (Ref.'9.18).
- Energy dependence is tested at several' energies between.
- 30 kev and 3MeV-corresponding to the approximate.ener-gies of the predominant Noble Gases (80, 160, 200-kev),.
Cs-137-(662 kev), Co-60 (1225 kev), and at.'least one energy less than 80 kev.
Other testing is performed relative to either Cs-137 or Co-60.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL R m+.
6-F 9-TABLE B (CONTINUED)
-TABLE NOTATION (a)
The LLD is defined for purposes of/ compliance 4
with the Radiological Effluent Technical Spe-
-cificacions as the smallest concentration of.
radioactive material ~in'a sample that will yield a net count, above system background, that will be-detectedcwith 95% probability with 5% probability of falsely. concluding that a blank observation represents.a "real"'
signal.
-For'a particular measurement system (which may
. include radiochemical separation):
LLD.=
4.66 Sb E* V* 2.22 'Y
- exp -(-lat)
Where:
t LLD =
.The lower limit of detection ac defined above (as picoeurie per unit mass or volume).
b=
The standard deviation of the background S
counting rate or.of the counting. rate of a blank sample as appropriate (as: counts per minute).
E=
The counting efficiency (as counts per disintegration).
V=
The sample sice (in units of mass or volume).
2.22 =
Ehe number of disintegrations per minute Oer cicoeurie.
Y=
The fractional radiochemical yield (when applicable).
^ ~.
_..______..___________________.________.______mO
Y CALLAWAY? PLANT OFFSITE. DOSE CALCULATION MANUAL Rev.~6 r
l'=;
The; radioactive._ decay constant for the par-ticular. radionuclides and, P
- At'=
the elapsed time between' sample collection
. ;(or end.of the'smaple' collection period)'
o and time of counting-(for. environmental-samples, not' plant effluent samples).
l.
Typical values of E, V, Y~and At.shall be used in the c
calculations.
7' It;shouldibe' recognized that the.LLD is defined as-a a-priori-(before theLfact) limit representing the cara-bility of a' measurement system and not as an a posteriori (afterJthe fact) limit;for.a particular-measurement. TAnalyses are-performed-in'such a manner
- that the' stated LLDs are achieved under routine conditions.
Occasionally background' fluctuations,
- unavoidable small sample: sizes,. the presence of inter fering-nuclides,1orLether uncontrollable circumstances may render'these LLDs unachievable. :In such cases,_the
-contributing factors.shallsbe identified and described
'in the Annual Radiological Environmental Operating Report.
.r-Ec (b)
_This' list does not mean that only these nu-clides are to be considered. 'Other peaks that-are identifiable, together'with those of the above nuclides,; shall also-be analyzed and reported in the Annual ~ Radiological Environ-mental Operating Report.
.(c):
' Required detection capabilities for thermolu-minescent dosimeters used for environmental-measurements shall'be in accordance with the recommendations of Regulatory Guide 4.13, Revision'1, July.1977.
(Refer to Section 5.3) ' u..
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CALLAWAY 7/LANT OFFSITE.10SE CALCULATION-MANUAL Rev.-6 6.0 DETERMINATION OF ANNUAL AVERAGE IND-SHORT TERM ATMOSPHERIC DISPERSICN PARAMETERS 15. 1 Atmospheric 1 Dispersion Parameters The values presented in Table 9 and Table 10 were determined through the-analysis of on-site.meterologi-cal data collected during the three year period.of May 4,
1973 to May 5, 1975 and March 16, 1978 to March 16,
- 1979.
6.1.1 Long-Term Dispersion Estimates l The variable trajectory plume segment atmospheric l transport model MESODIF-II.(NUREG/CR-0523)-and the l straight-line Gaussian dispersion model XOQDOQ
-j (NUREG/CR2919) were.used for determination.of the long-term atmospheric dispersion parameters.
A more detailed discussion of the methodology and data util-ized to calculate these parameters can be found l
elsewhere~(Ref. 9.6.12).
1 The Unit Vent and Radwaste Building Vent releases are f
at elevations 66.5 meters and 20 meters above grade, respectively.
Both release points are.within the'bu-ilding wake of the structures on which they are l
located, and the Unit Vent is equipped with a rain cover which effectively eliminates the possibility of-the' exit velocity exceeding five. times the horizontal wind speed.
'All. gaseous releases are thus considered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined..
(Ref. 9.5.2) 1.
l l
1' l^
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rov. 6 6.1.2 Determination of Lona-Term Discersion Esti-mates for Special Receptor Locations Calculations utilizing the PUFF model were performed for 22 standard distances to obtain the desired'disper-sion parameters.
Dispersion parameters at the SITE BOUNDARY and at special receptor locations were esti-mated by logarithmic interpolation according to (Ref.
9.6.14):
l*
X = X)
(d)B (6.1) dy Where:
B=
In (X /X )/ln (d /d ).
2 y
y y
.X,X2 = Atmospheric c ncentrations at distances dy and y
d, respectively, from the source
-(in 2
3 Ci/m ),
'~
The distances d and d were selected such that 7
y 2
dy <d<d '
2 6.1.3 Short Term Dispersion Estimates Airborne releases are classified as short term if they are less than or equal to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during a calendar year and not more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> in any quarter.
Short term dispersion estimates are determined by multiplying the appropriate long term dispersion estimate by a cor-rection factor (Ref. 9.9.1 and 9.17.4):
F = (T /T,)
(6.2) 3 4 l l
I
________.._m
, :b J
CALLAWAY PLANT-2 OFFSITE' DOSE CALCULATION:
MANUAL:
Rev. 6 -
. 2
.[
Where:
H:.
~
~
.T
= '
The. total number of hours of the short term 3
release.
L
.T,
=
The total number of hours in-the~ data collec-
- tion period from which the long term diffusion
' estimate was determined (Refer to Section 6.1).
Values of the slope-factor (S), are. presented in TABLE
.11.
Short-term. dispersion estimates are applicable to short term releases which.are not sufficiently random in both
~timeLof day and. duration (e.g.,
the short term release periods are not dependent solely on atmospheric condi-
~
tions'or time of day) to be represented by the annual' average' dispersion conditions.
(Ref. 9.8.12.)
6.1. 3.1' The Determination of the Slope Factor (S).
The. general-. approach employed'by subroutine PURGE of
. ('~
XOQDOQ (Ref. 9.17.4) was utilized to produce values;of C,
tie slope of the (X/Q), curves (Slope Factor (S))-for-both the:Radwaste. Building Vent and.the' Unit Vent.
However, instead of-using approximation procedures to produce the 15 precentile (X/Q) values, the 15 percen-tile (X/Q) value for each' release and at each location was determined by ranking all the 1-hour (X/Q){ values for that release and at the location in descending order.
The-(X/Q)y value which corresponded to the 15 percentile of all the calculated (X/Q) values within a sector was extracted for-use in the intermittent.
release (X/Q) calculation.
8
.w# _ _
r:
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 The intermittent release (X/Q) curve was constructed
.using the calculated 1-hour 15 percentile (X/Q)y and its corresponding annual average (X/Q),.
A graphic re-presentation, of.how the computational procedure works is illustrated by Figure 4.8 of reference 9.17.4.
The straight line connecting these points represents (X/Q)y values for intermittent releases, ranging in duration from one (1) hour to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />.
The slope (S) of the curve is expressed as:
-log ( (X/0)y/(X/0),1 (6.3)
S=
log (Ta/T )
y or
-(log (X/0)y - log (X/0),1 (6.4)
S=
log Ta - log Ty r
l 6.2 Atmospheric Dispersion Parameters for Farming l
Areas Within The SITE BOUNDARY l The dispersion phrameters for farming areas within the l SITE BOUNDARY are intended for a narrow scope l application: That of calculating the doce to the cur-l rent tennant farmer from gaseous effluents while he l conducts farming activities within the SITE BOUNDARY.
l For the purpose of these calculations, it was assumed l that all of the farmer's time, approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> l per year, is spent on croplands within the SITE SOUN-l DARY, and that his time is divided evenly over all of l the croplands.
Fractional acreage / time - weighted l dispersion parameters were calculated for each plot as l described in reference 9.5.7.
The weighted dispersion I parameters for each plot were then summed (according to l type) in order to produce a composite value of the i dispersion parameters.
The dispersion parameters pre-l sented in Tables 9 & 10 therefore represent the dis-l tributed activities of the farmer within the SITE BOUN-l DARY and his estimated occupancy period.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 TABLE 11 SHORT TERM DISPERSION PARAMETERS (a) (c)
Slope Factor (S)
Location (b)-
Sector Distance Unit Vent Radwaste (meters)
Building Vent Site Boundary S
1300
.328
.320 Nearest Cow NW 5053
.263
.266 Nearest Goat NW 5053
.263
.266 Nearest-Meat NNW 2736
.262
.268 Animal Nearest Vegetable NNW 2865
.264
.268 Garden
,7' '
Nearest Residence NNW 2865
.264
.268 (a)
Reference 9.5.4 (b)
Data from 1987 Land,Use Census (c)
Recirculation Factor = 1.0
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A
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rcv. 6
- 1 7.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation are submitted within 60 days after January 1 and July 1 of each year.
The period of the first report begins with the date of initial criticality.
The Radioactive Effluent Release Reports include a sum-mary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled' Nuclear Power Plants," Revision 1, June 1974, with data summariced on a quarterly basis following the format of Appendix B thereof.
For solid wastes, the format for Table 3 in Appendix B is supplemented with three additional categories:
class of solid waste (as defined by 10 CFR Part 61), type of container (e.g.,
LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g.,
cement, urea formaldehyde).
I The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year includes an annual summary of hourly meteorological data collected over the previous year which may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and pre-cipitation, or in the form of joint frequency distribu-tions of wind speed wind direction, and atmospheric stability.*
This same report includes an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report also includes, the asessment of the radiation doses fr:m radioactive liquid and gaseous effluents to MEM-BERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period.
All assump-tions used in making these assessments, i.e.,
specific activity, expcsure tima and location, is included in these reports.
Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, and the ODCM..
l l
k
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 The Radioactive Effluent Release Report to be submitted 60 days after January 1 ef each year also includes, as required by Technical Specification 3.11.4, an assess-ment of radition doses to the likely most exposed MEM-BER OF THE PUSLIC from Reactor releases and other nearby' uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calender year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation".
The Radioactive Effluent Release Reports include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the ODCM, pursuant to Specifica-tion 6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment System, pursuant to specification 6.15.
It also in-cludes a listing of new locations for dose calculations and or environmental monitoring identified by the Land Use Census pursuant to Specification 3.12.2.
~
The Radioactive Effluent Release Reports also include the following information:
An explanation as to why the inoperability of liquid or gaseous effluent moni-toring instrumentation was not corrected within the time specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and description of the events leading to liquid holdup ranks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.5, respectively.
- In lieu of submission, the Union Electric Company has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
(Ref.9.4)
~
,l
).
CALLAWA'l PLANT OFFSITE DOSE CALCULATION L
MANUAL Rav. 6
.~
8.0 IMPLEMENTATION OF ODCM METHODOLOGY g.
The ODCM provides the mathematical relationships used f
to implement the. Radiological Effluent Technical Specifications..
For routine effluent release and dose assessment, com-puter codes.are utilized-to implement the ODCM methodologies' These codes have been evaluated by a qualified independent reviewer to ensure that they pro-duce results consistent with the methodologies pre-sented in the ODCM.
(Ref. 9.5.5) r m
O i-s _s O
. - ^ = -
--__-m. -. ___.__ _ _._,. _ _ __, _,,
-CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 I
9.0 REFERENCES
9.1 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S.
Government Printing Office, Washington, D.C. 20402, 9.2 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S.
Govern-ment Printing Office, Washington, D.C.
204C2.
9.3 Title 40, " Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S.
Government Printing Office, Washington, D.C.
20402.
9.4 U.S. Nuclear Regulatory Commission, " Technical Specifications Callaway Plant, Unit NO.
1",
NUREG-1058 (Rev. 1), October 1984.
9.5 Communications 9.5.1 Letter NEO-54, D.W.
Capone to S.E. Milten-berger, dated January 5, 1983; Union Electric Company correspondence.
/
9.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values",
J. H. Smith (Bechtel Power Corporation), to D.
W.
Capone (Union Electric Co.), dated February 27, 1984.
9.5.3 (Reference Deleted) 9.5.4 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J H. Smith (Bechtel Power Corporation) to D. W.
Capone (Union Elecetric Co.), dated February 9, 1984.
9.5.5 Letter BLUE 1358, " Comparison of Callaway Plant Offsite Dose Calculations for Routine Effluents", J.H.
Smith (Bechtel Power Corpora-tion) to D.W. Capone (Union Electric Company),
dated March 22, 1984.
9.5.6 Private Communication, H.C. Lindeman & B.F.
Holderness, August 6, 1986 v
~___-m__
/
A CALLAWAY PLANT i
.OFFSITE DOSE CALCULATION a,
MANUAL
- Rov. - 6
}/
t A.
3[
. l19.5.7
- Calculation"ZZ-67, " Annual Average Atmospheric-
- j; Dispersion Parameters",LApril'1989.
- j 9.5.8
-(Reference Deleted)'
' 9. 6 -
Union'-Electric Company Callaway Plant, Unit l',
Final Safety. Analysis Report.
o V'.
9. 6.1' -
Section 11.5'.2.2'.3.1 9.6.2' Section 11.5.2.2.3.4 9.6.3
'Section 11.5.2.1'.2
~
9.6.4 Section' 11.5.2.2.3.2
. e
- 9. 6. 5-
-Section-11.5.2.2.3.3 19.6.6 iSection 11.2.3.3.4
.9.6.7 Section 11.2.3.4.3 9.6.8
'Section'11.5.2.3.3.1 T
/
9.6.9 Section 11.5.2.3.3.2 3
~~
9.6.10 Section 11.5.2.3.2.3 9.6.11
'Section 11.5.2.3.2.2 9.6.12 Section 2.3.5 9.6.13 (Reference Deleted)
.9.6.14 Section 2.3.5.2.1.2 9.6.15 (Reference Deleted) 9.6.16 (Reference Deleted) 9.6.17-Section 9.2.6 9.G.18 Section 9.2.7.2.1-9.6.19 Section 6.3.2.2
/ %.
I-
g%-_ _ - -
i-y i '
CALLAWAY' PLANT
.OFFSITE DOSE. CALCULATION i
MANUAL
-Rev. 6 9.6.20~
Table'11.1-6 9.6.21:
Table.9.4-6
~
Jy,
9.6.22-Table 9.4-8 h>
9.6.23
. Table 9.4-11 l"
9. 6. 2 4.-
Table 9.4-12 9.6.25 (Reference Deleted)-
.9.6.26 Table 2.3-68:
Union Electric Company Callaway Plant Environ :
- 9. 7.
mental Report, Operating -' License. Stage.
- 9. 7.1 -
Table 2.1-19 9.7.2
'Section 2.1.2.3 9 7.3
'(Reference Deleted) l9. 7. 4 Section 2.1.3.3.4 y-
[
9.7.5
.(ReferenceLDeleted) 9.7.6 Section 5.2.4.1 9.7.7 Table 2.1-19 9.8 U.S. Nuclear' Regulatory Commission,
" Preparation of Rac11ological Effluent Techni-cal. Specification For Nuclear Power Plants",
USNRC NUREG-0133, Washington, D.C. 20555,.Oc-tober 1978.
9.8.1 Pages AA-1 through AA-3 9.8.2 Section 5.3.1.3 9.8.3 Section 4.3
?
l 9.8.4 (Reference Deleted) r -(-v_. -
L__._.--_.--_._--_----____
p__
.3 n jr 1,
e
+
VQ g~j
?'
CALLAWAY PLANT dis ;' j: "
^
..OFFSITE DOSE CALCULATION 7--
MANUAL '
Rev.' 6 py h
-R n,-'
Y, 9.8.5
- Section 5.3.'1.5 9.8.6-Section'5.1.1-9 '. 8 '. 7 Section 5.'l.2'
' 9. 8. 8.
Section. 2.1
-u -
9.8.9
'Section Si2.1.3 M
19.8.10 Section 5.3.1 9.8."11; L Sectionf3.8
'9.8.12
'Section 3.3 9.9' U 5.' Nuclear Regulatory Commission, "XOQDOQ,.
'. Program For the Meterological Evaluation of
' Routine Effluent' Releases At: Nuclear-Power Stations",;USNRC NUREG-0324L Washington, D.C.-
s i
-20555.
t9.9.1, Pages 19-20 Subroutine PURGE WE 9.10,
. Regulatory Guide 1.111, ' " Methods. For Estimat-
- f '
ing Atmospheric. Transport And' Dispersion'of
-Gaseous Effluents'In Routine' Releases From.
Light-Water-Cooled Reactors", Rovision 1, U.S.
Nuclear Regulatory Commission, Washington, D.C. 20555, - July, :1977.
9.10.1 Section c.1.b-c
-9.10.2
-(Reference' Deleted) 9.10. 3' Figures 7 through 10
-9.10.4 (Reference Deleted)
~ 9.10.5 Section c.4 n
~'
15 I W.
96 -
\\c) i f..
x....
~ _ _ _ - -
- f. '
CALLAWAT' PLANT-
[-
OFFSITE DOSE. CALCULATION b
MANUAL Rev. 6 y..
t L'
a-~
9.11 Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases-Of Reactor Effluents-For the Purpose <Of. Evaluating Com-pliance With-10 CFR'Part 50, Appendix I",
Revision 1,. U.S. Nuclear Regulatory' Commis--
sien, Washington, D.C. 20555,. October ~1977.
},
"9.11.1 Appendix'C, Section.3.a 9.'11.2 Appendix E, Table E-15
.9.11.3 Appendix C, Section 1 9.11.4 Appendix E, Table E-11 9.11.5 Appendix E, Table E-9 9.12' U.S. Nuclear Regulatory' Commission, " Methods for Demonstrating LWR Compliance with'the EPA Uranium' Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C.
20555, January 1980.
9.12.1L Section I, Page 2 lf,
9.12.2-
~Section IV, Page 8 9.12.3 Section IV, Page 9 9.12.4 Section III, Page 6 9.12.5-Section III, Page 8 9.13 (Reference Deleted) 9.14 Management Agreement for the Public Use of Lands, Union Electric Company and the. State of Missouri Department of Conservation, December 21, 1982.
9.14.1 Exhibit A 0.15 (Rafarancs Dslated) p+
(; ~.. -
_ _ _ _ _. _ _ _ _ _. _. _ _ _. _ _ _ _.... =. _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _
CALLAWAT PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 6 9.16 Miscellaneous References 9.16.1 Drawing Number M-109-0007-06, Revision 5.
l 9.16.2 (Reference Deleted) l 9.16.3 Callaway Plant Annual Environmental Operating
]
Report (updated annually).
9.16.4 UE Safety Analysis Calculation 87-001-00.
] 9.16.5 Calculation zz-48, " Calculation of Inhalation l
and Ingestion Dose Commitment Factors'for the l
Adult and Child", January, 1988.
l 9.16.6 HPCI 89-02, " Calculation of ODCM Dose Commit-l ment Factors", March, 1989.
l 9.16.7 HPCI 87-04, " Calculation of the Limiting Set-l point for the Containment Purge Exhaust Moni-l tors, GT-RE-22 and GT-RE-33", March, 1987.
[ 9.16.8 HPCI 88-10, " Methodology for Calculating the l
Response of Gross NaI(TE) Monitors to Liquid
'~
j Effluent Streams", June, 1988.
s I 9.16.9 Calculation zz-57, " Dose Factors for Eu-154",
l January, 1989.
9.17 U.S. Nuclear Regulatory Commission, "XOQDOQ:
Computer. Program for the Meterological Evalua-tion of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2929, Septem-ber, 1982, Washington, D.C. 20555.
9.17.1 (Reference Delted) 9.17.2 (Reference Deleted) 9.17.3 (Reference Deleted) 9.17.4 Section 4, " Subroutine PURGE", pages 27 and 28.
l 98 -
_____._________.__.____......____---.__m-._
- - - - ^ ~ ~ - - - - - - - - - - - - - - - - - ' - - - - ^ - - - -
E CALLAWAY PLANT l
OFFSITE DOSE CALCULATION-MANUAL Rev. 6 9.18 Regulatory' Guide 4.13,'" Performance, Testing, and procedural specifications for Thermolumin-iscence. Dosimetry:. Environmental Applications:
."(Revision 1), July 1977; USNRC,.
Washington, D.C. 20555 i-9.19 TID-7004, " Reactor Shielding Design Manual",
Rockwell, Theodore, ed; March 1956.
' 9.20; BNWL-236, "ISOSHLD - A computer code for Gen-l eral Purpose Isotope Shielding Analysis",
- Engel, R.C.,
Greenberg, J., Hendrichson, M.M.;
June 1966.
.9.21 ENWL-236,-Supplement 1, "ISOSHLD-II: Code Revision to include calculation of Dose Rate from Shielded Bremsstrahlung Sources",
-Simmons, G.L.,
et al; March 1967.
9.22 BNWL-236, Supplement 2, "A Revised Photon Pro-bability Library for use with ISOSHLD-III",
Mansius, C.A.; April 1969.
l 9.23' ANSI N13.10-1974, " Specification-& Performance
-l of on-Site Instrumentation for Continuously x
l Monitoring Radioactivity in Effluents"; Sep-
.l.
tember, 1974.
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