ML20154E510
| ML20154E510 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/29/1988 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20153E975 | List: |
| References | |
| PROC-880229, NUDOCS 8809190025 | |
| Download: ML20154E510 (121) | |
Text
- - - - - - -
UN70y Rev.5 Eticrluc O
33 CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL l
February,1988 1
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G809190025 000G31 PDR ADOCH 05000403 R
Rev.s E
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL February,1988 O
Approved:
J Jf /2 9
Chaban, Onsite Review domrtIlttee ORC meeting number Roview e d:
A b
T!
Superikt<>ndent, Health Physics p 2345g Prepared by:
[M *' * -
E/29/Se f
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Supervisor, HP Technical Support f
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Reav. 5 O
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This document contains the following:
Pages 1
through 105 Tables 1
through 12 Figures 4.1, 5.1A, 5.1B, 5.2A, 5.2B, 5.3 O
O
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5
- (
N.J Table of Contents Page 1.0 PURPOSE AND SCOPE 1
2.0 LIQUID EFFLUENTS 2
2.1 TECHNICAL SPECIFICATION 3.3.3.10 2
2.2 LIQUID EFFLUENT MONITORS 3
l 2.3 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS 7
2.4 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS 13 2.4.1 Technical Specification 3.11.1.1 13 2.4.2 Liquid Effluent Concentration Measurements 14
)
l 2.5 DOSE DUE TO LIQUID EFFLUENTS 14 2.5.1 Technical Specification 3.11.1.2 14 2.5.2 The Maximum Exposed Individual 15 1 2.5.3 Calculation of Dose from
]
Liquid Effluents 15 l 2.5.4 Summary, Calculation of l
Dose Due to Liquid Effluents 20 2.6 LIQUID RADWASTE TREATMENT SYSTEM 24 2.6.1 Technical Specification 3.11.1.3 24 2.6.2 Operability of the Liquid Radwaste Treatment System 24 3.0 OASEOUS EFFLUENTS 25
( 3.1 TECHNICAL SPECIFICATION 3.3.3.10 25 O
CALLAWAY PLANT OFFSITE DOSF CALCULATION MANtfAL Rev. 5 Table of contents (continued)
Page 3.2 TECHNICAL SPECIFICATION 3.11.2.1 25 3.3 GASEOUS EFFLUENT MONITORS 25 l 3.4 CALCULATION OF GASEOUS EFFLUENT MONITOR SETPOINTS 29 3.4.1 Total Body Dose Rate Setpoint Calculations 29 3.4.2 Skin Dose Rate Setpoint Calculations 31 3.4.3 Gaseous Effluent Monitors Setpoint Determination 32 3.4.4 Summary, Gaseous Effluent Monitors Setpoint Determination 34 l 3.5 CALCULATION OF DOSE FROM GASEOUS EFFLUENTS 34 j 3.5.1 Calculation of Dose Rate 34 3.5.1.1 Noble cases 34 3.5.1.2 Radionuclides other Than Noble Cases 36 3.5.2 Individual Dose Due to Noble Cases 41 3.5.2.1 Technical Specification 3.11.2.2 41 3.5.2.1.1 Noble Cases 41 3.5.2.2 Technical Specification 3.11.2.3 43 3.5.2.2.1 Radionuclides other Than Noble Gases 43 3.6 CASEQUS RADWASTE TREATMENT SYSTEM 66 3.6.1 Technical Specification 3.11.2.4 66 3.6.2 Description of the Gaseous Radwaste Treatment System 66 O
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CALLAWAY PLANT OFFS 7TE DOSE CALCULATION MANUAr.
Rev. 5
,s Table of Contents (continued)
Page 3.6.3 operability of the Gaseous Radwaste Treatment System 67 4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 68 4.1 TECHNICAL SPECIFICATION 3.11.4 68 l 4.2 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 68 4.2.1 Identification of the MEMBER 70
^
0F THE PUBLIC 4.2.1.1 Utilization of Areas Within the SITE BOUNDARY 70 l 4.2.2 Total Dose to the Nearest Resident 70 l 4.2.3 Total Dose to the Critical Receptor 71
)
l Within the SITE BOUNDARY l 5.0 RADIOLOGICAL ENVIRONMENTAL
]
MONITORING 74 l 5.1 TECHNICAL SPECIFICATION 3.12.1 74 l
5.2 DESCRIPTION
OF THE RADIOLOGICAL l
EINIRONMENTAL MONITORING PROGRAM 74 l 5.3 PERFORMANCE TESTING OF E!NIRONMENTAL 75 l
THERM 0 LUMINESCENCE DOSIMETERS l 6.0 DETERMINATION OF ant!UAL AVERAGE l
AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS 88 l 6.1 ATMOSPHERIC DISPERSION PARAMETERS 88 6.1.1 Long-Term Dispersion Estimates 88 l 6.1.2 Determination of Long-Term Dispersion l
Estimates for Special Receptor l
Locations 89 6.1.3 Short-Term Dispersion Ertimates 89 O
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. CALLAWAY PLANT 0FFSITE DOSE CALCULATION MANUAL Rev 5
i t
Table of Contents (continued) t Page 8.0 IM?LEMENTATION OF ODCM METHODOLOGY 98 l
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9.0 REFERENCES
99 l
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CALLAWAY PLANT i
OFFSITE DOSE CALCULATION MANUAL Rev. 5 a
}
List of Fiqures i
Figure 4.1 Site Area closed to Public Use i
Figure 5.lA Airborne & TLD Sampling Network Figure 5.1B Airborne & TLD Sampling Me'. work f
Figure 5.2A Location of Aquatic Sampling Stat 16ns Figure 5.2B Location of Aquatic Sampling Stations Figure 5.3 Food Products Sc.mpling Locations f
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i CALLAWAY PLANT OFFSITE DOSE CALCULATION MAWAL Rev. 5 l
.LJ t
List of Tables Page f
Table 1 Ingestion Dese Commitment Factor (Ag) for Adult Age Group 21 j
Table 2 Bioaccumulation Factor (BF ) Used g
in the Absence of Site-Specific Data 23 Table 3 Dose Factors for Exposure to A i
Semi-Infinite Cloud of Noble Gases 33 Table 4
, Dose Parameter (Pg) for Radio-nuclides Other Than Noble cases 38 i
Table 5 Pathway Dose Factors (R ) for g
Radionuclides Other Than Noble l
Cases 47 i
Table 6 Radiologi al Fnvironmental Monitoring Program 76 Table 7 Reporting Levels fcr Radioactivity Concentrations in Environmental Samples 84 i
Table 8 Maximum Values for the Lower k
Limits of Detection 85 t
Table 9 Highest Annual Average Atmospheric Dispersion Parameters - Radwaste l
Building Vent 92 l
t 10 Highest Annual Average Atmospheric Dispersion Parameters - Unit Vent 93
'5.;4e 11 Short Term Dispersion Parameters 94 l
Table 12 Application of Atmospheric Dispersion Parameters 95 I
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n 4
CALLAWAY ELANT OFFSITE DOSE CALCULATION MANUAL Rev. S i
t i
Record of Revisions t
i i
j '
Revision Reason i
l Number Data for Revision Rev. O March 1983 l
i r
Rev. 1 November 1983 Revised ta support the current RETS submittal and to incorporate NRC i
Staff comments
~
i Pev. 2 March 1984 Revised to Ancorporate NRC Staff I
comments i
Rev. 3 June 1985 Revised t1 incorporate errata iden-tified by ULNRC-803 and changes to
[
the Environmental Monitoring Program..
Incorporate results of 1984 Land use Census.
Rev. 4 February 1987 Minor clarifications, incorporated q
31-day projected dose methodology.
Change in the utilization of areas within the Site Boundary.
i i
I Rev. 5 January 1988 Minor clarifications, revised j
I descriptions of liquid and gaseous l
rad monitors, revised liquid set-1 peit.t mothodology to incorporate i
monitor background, revised dose I
calculations for 4CCFR190 require-l ments, Reviced Table 6 and Figures l
5.1A and 5.1B to refine descrip+
l tions of environmental TLD sta-l tions, incorpo.9'cd description of i
1 environmental 1.+ testing required I
by Reg. Guide 4.13, revised l
Taties 1, 2, 4,
and 5 to add addi-f I
cional nuclides, deleted redundant l
material from Chapter 6.
)
-vii-J p
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. S 7-ss 1.0 P,U,RPOSE AND SCOPE The Offsite Dose Calculation Manual (CDCM) describes the methodology and parameters used in the calculation of offsite doses and dose rates due to radioactive t
liquid and gaseous effluents and in the calculation of l
liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.
The CDCM also contains a list and description of the specific sample locations for the radiological environmental monitoring program, i
I Changes in the calculational methodologies or paramet-e ers'will be 4.ncorporated into the CDCM and documented in the Semi 1.nnual Radioactive Effluent Release Report.
The CDCM does not replace any station implementing procedures.
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CALLAWAY PLANT OFFCITE DC.9E CALCULATION MANUA L Rev. 5 c
2.0 LIQUID EFFLUENTS l 2.1 Technical Specification 3.3.3.9 The radioactive liquid effluent monitoring instrumenta-I 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 exceedad.
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.
I l
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 O
2.2 Li_ quid 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).
Setpoin s, precautions, and limitations applicable to the operation af the callaway Plant liquid effluent monitors are provided in the appropriate Plant Proce-dures, which are contained in Volume 6 cf the Plant Operating Manual.
Setpoint values are calculated to assure that alarm and trip actions occur prior to ex-ceeding the Maximum Permissible concentration (MPC)
[
limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA.
The calculated alarm and trip ac-tion setpoints for the 'iquid effluent line monitors and flow measuring devices must satisfy the following equation:
ef O
- C F+f (2.1)
Where:
C=
the liquid effluent concentration limit (MPC) implementing Technical Specification 3.11.1.1
'or the site in (uCi/ml). O
l CALLAWAY PLANT f
OFFSITE DOSE CALCULATION MANUAL Rev. 5
]
c=
The setpoint, in (uci/ml), of the radioactiv-ity monitor measuring the radioactivity l
concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and
(
directly proportional to the volumetric flow of the dilution stream plus the effluent i
stream, represents a value, which, if ex-ceeded, would result in concentrations exceed-ing the limits of 10 CFR Part 20 in the UNRES-TRICTED AREA.
f=
The flow setpoint as measured at the radiation monitor 1,ocation, 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+fa F).
(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.
1 4-m
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 I,_')
\\/
Thus, the expression for determining the setpoint on the liquid radwaste effluent line monitor becomes:
c5 C(T + f)
(uCi/ml) f (2.2) 2.2.1 Continuous Liquid Effluent Monitors The radiation detection monitors associated with conti-nuous liquid effisent releases are (Ref.
9.6.1, 9.6.2):
Monitor I.D.
Descrietion BM-RE-52 Steam Generator Blowdo T1 Discharge Monitor LE-RE-59 Turbine Building Drain Monitor These effluent streams are not considered to be radi-eactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis.
The sampling frequency, minimum analysis L
frequency, and type of analysis performed are as per Technical Specification Table 4.11-1.
I i
l The alarm / trip setpoints are determined through the use I of Equation (0.2) methodology to ensure that the limits I of Technical Specification 3.11.1.1 are not exceeded at the UNRESTRICTED AREA.
The alert setpoints have been administratively established below the alarm / trip set-pointe. thus providing an additional margir. of safety.
5 O
l CALLAWAY PLANT j
OFFSITE DOSE CALCULATION l
MANUAL Dev. 5 i
i
)
i The-alarm / trip setpoint calculations are based on the minimum dilution flow rate (cooling tower blowdown, i
5000 gpm), the maximum effluent stream flow rate, and I
the actual isotopic analysis.
Due to the possibility l
of a simulataneous release from more than one release i
pathway, a portion of the total site release limit is allocated te, each pathway.
The determination and usage of the allocation factor is discussed in Section 2.3.1.
4 In the event the alarm / trip setpoint is reached, the radiation monitor setpoint (c), will be reevaluated us-i
]
ing the actual dilution flow rate (F), the actual of-
[
fluent stream flow rate (f), and the actual isotopic l
analysis.
This evaluation will then be used to ensure i
that Radiological Effluent Technical i
Specification 3.11.1.1 limits were not exc.eeded.
I 2.2.2 Radioactive Liquid Satch Release Effluent l
Monitor The two radiation monitors which are associated with the liquid effluent batch release systems are (Ref.
i 9.6.4, 9.6.5):
q MONITOR I.D.
Description i
HB-RE-18 Liquid Radwasto Discharge l
Monitor i
HF-RE-45 Secondary Liquid Waste l
)
System Monitor l
4 I
l l
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l The setpoint for these monitors to determined according to the methodology described by Equation (2.2) and is a
[
i function of the di'ution flow rate (F), the radioactive effluent line flow rate (f) and the tank liquid ef-
[
fluent concentration, as determined by a pre-release i
isotopic analysis.
Based on these factors, a setpoint is calculated for the appropriate monitor to ensure l that the limits of Technical Specification 3.11.1.1 are not exceeded at the UNRESTRICTED AREA (Figure 5,2A).
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CALLAWAY PLANT 0FFSITE DOSE CALCULATION I
MANUAL
- ev. 5 i
j l 2.3 Determination of Liquid Effluent Monitor Setpoints The dependence of the setpoint (c), on the radionuclide l
4 a
distribution, yields, calibration, and monitor paramet-ers, requires that several variables be considtred in setpoint calculations.
(Ref. 9.8.1)
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l i
The isotopic concentration of the release being consid-ered must be determined.
This is obtained from the sum of the measured concentrations as determined by the j
l analysis required per Technical Specifications i
Table 4.11-1:
3 I
i C = (I (C9)g) + C, + C3+Cg F
+C (2.3)
T l
\\
t L
Where:
C7=
the total concentration of radionuclides as f
determined by the analysis of the waste I
sample.
l l
I(C9)g = tha sum of the concentrations (C ) of each 9
measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample.
]
C,*
=
the measured concentrations (C,) of alpha em-itting nuclides observed by gross alpha analysis.
l
)
C,*
=
the measured concentrations of Sr-89 and Sr-90 l
in liquid waste as determined by analysis of the quarterly composite sample.
.i i
C* =
the measured concentration of H-3 i l
g liquid waste, j
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CALLAWAY PLANT OFFS 7.TE DOSE CALCULATION f-~3 MANUAL.
Rev. 5
!v)
C*=
the measured concentratien of Fe-55 in liquid F
waste as determined by analysis of the quar-terly composite sample.
The C term is included in the anhlysis of each batch; 9
terms for alpha, Sr-89, Sr-90, Fe-55, and tritium are included as appropriate.
- Values for these concentrations will be based on previous composite sample analyses as required by Table 4.11-1 of Technical Specifications.
The measured radionuclide concentt.tiens aro used to calculate a Dilution Factor (E )'
'hi#h 18 th' #"*10 I
d total dilution flow rate to tank tiew rate required to assure that the limiting concentrations of Technical Specification 3.11.1.1 are met at the point of discharge.
This is referred to as the required Dilu-tion Factor and is determined according to:
I l
gi C,
- C, C
C t
F Ed*I 4 t' IS g
l (MPCg)g
i Wheret C,
C,, C,, C, CF=
measured c ncentrations as 9
g defined in 2.3.1.1.
Terms C,, C,,
C and C 7,
t will be included in the calculation as appropriate.
= are limiting concentra-g, 7
g tions of the appropriate radionuclides from 10CFR 20, Appendix B, Table II, Column 2.
For i
dissolved or entrained noble gases, the concentration chall be limited to 2x10 uCi/ml total activity.
F,=
the safety factor: a conservative f actor used to compensate for statistical fluctuations and errors of measurements.
(For example, F3 = 0.5 corresponds to a 100 percent i
variation.)
Default value is F3 = 0.9.
.s.
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CALLAWAY PLANT i
OFFSITE DOSE CALCULATION MANUAL Dev. 5 For the case Fd < 1, the monitor tank effluent concen-tration teets the limits of Radiological Effluent Tech-nical Specification 3'.11.1.1 without dilution and the effluent may be released at any desired flow rate.
If Ed > 1 then dilution is required to ensure compliance l
with Technical Specification 3.11.1.1 concentration limits.
If simultaneous releases are occuring or are anticipated, a modified dilution factor (Fdn), must be determined so that availablu dilution flow may be ap-portioned among simultaneous discharge pathways, s
Edn
- Id*'a (2.5) m Where:
F, =
the allocation factor which will modify the required dilution factor such that rimultaneous liquid releases may be made without exceeding the limits of Technical Spe-cification 3.11.1.1.
The most straight-forward determination of the alloca-tion factor 1s:
i 1
r'a n
(2.6)
Where:
n=
the number of liquid discharge pathways for which Ed > 1 and which are planned for simultaneous release.
9
CALLAWAY PLANT Ot'FSITE DOSE CALCULATION MANUAL Rev. 5 l
Howe' re r, thir value for F, may be unnecensarily res-trictive in that all release pathways are apportioned the same fraction of'the available dilution stream, regardless of the relative concentrations of each of 4
the sources.
4 Since the radionuclide concentration of the two conti-nuous sources is less than that of the batch release source, it is acceptable to allocate smaller portions of the dilution stream to the continuous releases and a larger portion,to the batch releases.
]
Therefore, F, is necessarily defined as a flexible i
l quantity with a default value of 1/q, however, the sum of the allocation factors assigned to pathways for the j
l simultaneous release must be $ 1.
l The calculated maximum permissible waste tank effluent j
flow rste, (fmax), is based on the modified dilution factor, (Fdn), and the effective dilution flow
- ste,
)
(F,gg).
The effective dilution flow rate is gis.n by:
q F,gg = (0.9)F, (2.7)
Where:
F, =
the cooling tower blowdown flow rate and/or bypass dilution flow.
1 A concervative value for F, is the minimum allowable cooling torer blowdown of 5000gpm, which is used as a default value.
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CALLAWAY PLANT OFFSITE DOSE CALCULt. TION MANUAL Rev, 5 C\\
U dn and F,gg, the cal-Having established the values of E culated maximum permissible waste tank flow rate can be calculated by:
F
+f F
f I
- If D
'II II # Ip << F,f f)
(2.8) max s-F F
dn dn I
Where f
= the expected undiluted effluent flow rate.
p Thus, the effluent flow rate is set at or below f max
- Even though the value of f may be larger than the max
()
actual effluent pump capacity, (f ),
it does represent p
the upper limit to the effluent flow rate whereby the requirements of Technical Specification 3.11.1.1 may stall be met.
If Ed<1, the effluent flow rate set-point may be assigned any value since the waste tank effluent concentration meets the limits of Technical Specification 3.11.1.1 without dilution and the release may be made without regard to the setpoints for other release pathways.
For those discharge pathways selected to be secured during the release under consid-eration, the flow rate setpoint should be set at as low a value as practicable to detect any inadvertent release.
The liquid radiation monitor setpoint may now be deter-mined based en the values of C and f,,x, which were 7,
specified to provide compliance with the limits of Technical Specification 3.11.1.1.
i The menitor response is primarily to gamma radiation, therefore, the actual setpoint is based on I(C9)g.
The
(
g calculated menitor se point concentration is determined i
i as follows:
l
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11 -
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CALLAWAY PLANT OFFSITE BOSF CALCUI.ATION MANUAL Fav. 5 l
c = B + A t(c )g uCi_
i 9
ml (4.9)
Where:
Ie=
setpoint as previously defined (see Section l
2.2) l B=
monitor background prior to release initiation I
(uci/ml).
l NOTE l
The monitor background is controlled I
at an appropriately small fraction
('
l of the limiting MPC of gamma emit-l ting radionuclides to ensure that
+
l adequate monitor sensitivity is I
maintained.
A=
Adjustment factor which will allow the set-point to be established in a practical manner for convenience and to prevent spurious alarms.
A=Imax (2.10) f P
1 If A > 1; Calculate the monitor setpont and proceed with l
the release.
O CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. E
\\m /
If A < 1:No release may be made.
This condition must be flagged and the operator instructed to re-evaluate E and F,gg (i.e.,
reduce effluent dn flow rate or return radwaste for reprocessing).
NOTE l
If fd<1, the release may be i
made without regard to availa-l ble dilution or simultaneous l
releases, and the Adjustment l
Factor may be calculated as I,,
follows:
(
A=
1 (2.11)
E i
l g
l 1 The methodology described above is used t6. determine
(~')N sa points for each of the radiation monitors assigned
(,
an effluent monitoring function.
The limiting release cor. entration can be increased by reducing the dis-charge flow-rate and by increasing the cooling tower I
l blowdown flow-rate.
2.4 Liquid Effluent Concentration Measurements 2.4.1 Technical Specification 3.11.1.1 The concentration of radioactive material released in l
liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix S, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 uC1/ml total activity.
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CALLAW1Y PLANT OFFSITE DOSE CALCULATIoft MANUAL Rev. 5 N,/
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2.4.2 Liquid Effluent concentration sM._arements Liquid batch releases are dircharged as a discrete volums and each release is authorised based upon the sample analysis and the dilution flow rate existing in the discharge line at time of release.
To assure re-presentative 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 analy:ing 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, and other procedural conditions, prior to authorisation for release.
The radwante 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, St-90, & Fe-55, the measured concentration from the previous composite analysis is used.
Compo-site samples are collected for e.a.ch batch release and O
quarterly analyses are performed in accordance with Technical Specification Table 4.11-1.
I Doses from liquids discharged as continuous releases i are calculated by utill:1ng the last measured values of samples required in accordance with Technical Specif1-cations Table' 4.11-1.
l l 2.5 Dese Due to Liquid Effluents i 2.5.1 Tecinical Specification 3.11.1.2 The dose or dose ecmmitment to a MEMSER OF THE PUSLIC from radioac?,1ve materials in liquid effluents released, to UNRESTRICTED AREAS shall be limited:
l 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 l
to 10 mrem to any organ.
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CALLAWAY PL.WT OFFSITS DOSE CALCULATION t
HANUAL Rev. 5 t
2.5.2 The Maximum Exposed Individual I
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-t posed individual.
(Ref. 9.8.3, 9.8.4) l The Callaway Plant's liquid effluents are discharged to the Missouri River.
As there are no potable water in-takes within 50 miles of the diJeharge point (Ref.
9.7.1, 9.6.6), this pathway does not require routine h
evaluation.
Therefore, the dose contribution from fish consumption is expected to account for more than 95% of
(
the total man-rem dose from discharges to the Missouri i
' River.
Dose from recreational activities is e'xpected to contribute the additional 5%, which is considered to I
be negligible.
(Ref. 9.6.7) l 2.5.3 Calculation of Dose Frem_ Liquid Effluents i
2.5.3.1 Calculation of Dese contributions The dose contributions for the total time period 1
7 6
n l
IAt t tal L
i i
are calculated at least once each 31 days and a cumula-tive summation of the total body and individual organ doses is t.aaintained for each calendar quarter These 1
dose contributions are calculated for all radionuclides l
identified in liquid effluents released to UNRESTRICTED i
i AREAS using the following expression (Ref. 9 S.3) l l
i i
i I
i E
1 i
c I
i l I
l I
f
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CALLAWAY PLANT CiFSIfE DOSE CALCULATION MANUAL Aev. 5
. [s\\
L./
m I [A, I atg gg C
F)
(2.12)
D, a g
g 1
t=1 I
Where:
Dt =
the cumulative dose commitment to th& total body or any organ, t,
from the liquid ef-fluents for the total period m
Iat t
t=1 in mtem.
the length of the tth time paried over which l
at
=
g l
C and F are averaged for all liquid l
gg t
releases, in hours.
(
the avetage measured concentration of l
C
=
gg radionuclide, i, in undiluted liquid effluent during time period at from any liquid g
I release, in (tC1/ml),
t A,=
the site.related ingestion dose commitment y
f actor to the total body or any organ t for each identified principal gamma anu besa emit-ter 1 Lted in Te:hnical Specifications, Table 4.11-1, (in mrem /hr) per luci/ml).
These factors are given in Table 1, as derived through the use of Equation (2.16).
O 16 -
CALLAWA't PLANT OCFSITE DOSE CALCULATION MANUAL Rev. 5 7
\\
s_
Ft =
the near field average dilution factor for Cgg during any liquid effluent release.
I I
t=
max (f,+ f,,x) 69.77 Where:
1 maximum undiluted effluent flow rate during f
=
max the release f, =
average flow rate from the site discharge structure to unrestricted receiving waters (dilution flow) j 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-gg tive material in liquid waste at the common release point determined in accordance 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 s
F term.
l g
l i
I i
I 17 -
t i:
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAI.
Rev. 5 l
2.5.3.2 Dose Factor Related to Liquid Effluents l Cal ulating dose contributions via Equation (2.12) requires the use of a dose f actor A, for each nuclide, g
i i, which embodies the dose factors, pathway transfor factors (e.g, bicaccumulation factors), pathway v. sage factors, and dilution factors for the points of Fathway origin.
'me adult total body dose f actor and the maxi-mum adult orgra dose factor for each radionuclide is used f rom Table E-11 of Regulatory Guide 1.109: thus, i
Table 1 contains critical organ dose factors for various organs.
The dose factor is calculated accord-ing to (Ref. 9.8.4):
i; 1
i l'
A, = k,(U /D
+ U BF )DF (3.13) g y g F
1 g
n i
Q where:
A,a composite dose parameter for the total body or
]
g i
critical organ of an adult for nuclide, 1, for
)
all appropriate pathways, as (mrem /hr) per i
(uci/ml).
i 5
k, =
units conversion factor, derived according toi j
4 1.14E05 = (1E06pci/pci x 1E03ml/kg) + 8760 hr/yr.
(
I UF=
adult fish consumption factor, equal i
I to 21kg/yr (Reg. Guide 1.109, Table E-5)
{
c l
Bioaccumulation factor for nuclide, i, in fish BF u
g l
(Table 2), as (pci/kg) por (pci/t).
i l
Di g=
Dose conversion factor for nuclide, i, for j
adults in pre-selected organ, t,
as (mrem /pC1)
I (Ref. 9.11.4 and 9.16.5).
receptor individual's water consumptien by age U
=
y group as per Regulatory Guide 1.109, Table E-5.
For adults, V
= 730kg/yr.
y I
18 -
CALLAWAY PLANT OFFSITE DOSE CALCULATION
.htANUAL Rev. 5 y
-s
(
(v dilution factor from the near field area D
=
y within one-quarter mile of the release point to the potable water 11.take for the adult water consumption, bOTE 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 arc 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 exposed individual, or in dose estimates to the population.
Should future water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates.
(Ref. 9.6.6).
Therefore, it is not necessary to evaluate (U /D ) at this time, and y y Equation (2.13) simplies to:
V)
(2.14)
A
= k, (U 5F )DFg g
F i
l Inserting the appropriate usage factors into Equation (2.14) yields the following expression:
(2.15)
Ah = 1.14E05 (21BFg)DFg x DF (2.16) or Ah = 2.39E06 x SFg g
i O
- le -
CALLAWAY PLANT OtFSITE DOSE CALCULATION MANUAT.
Rev. 5 L) l 2.5.4 Summary, Calculation of Dose Due to Liquid Effluents The dose contribution for the total time period m
Iat g tal 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 radionuclide concentrations are determined by periodic composite and grab sample analysis, may be ap-proximated by using the last measured value.
Dose con-4 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 s
than" values are not used in the required dose
()
I calculations.
l es(J
- 2o -
_ _ _ = - -.
CALLAWAY PLANT CTTSITE DCSE CALO*.u T 0N 4
PM.".* A t 8ev. 5 3
TA!!I 1 e
INCISTION DCSE 00Tt! M NT TA0 TOR ( g ) TCR AOCI.* AGE GR XP tare **mt ter vet el) l
)
i e
i i Total i l
l 1
l j
JNuclide! lany f Liver i ledy. TNyrets t K1deev i Luna ! GI.Lt! 1 i
I M*3 INo Oata.:.:6t*01 12. 6t *01):. 6t *01 12. *4t*0112.*61 0112.26t*011 I le ! 11. 3 1 02 I 2. lit *02 11.65t *021No Dat a 13.151 0:lNo Casa 15.16t+001 1 C 16 13.13t+0416. *6t+03 16. 26t+0 316. 6t *03 14. 6t+0316.26t+0314.*6t*031 I No.24 fe.0!!*C:la.0?t+01 16.0?t+0:16. 0 !!+C le.0?t+0:14.0?!+0:16.0!!+0 t i P 32 14.6:1+0!! ;. 8 ? t +C 6 11.78t+C6lNo Data INo Data INo Osta 15.19t+C41
! Cr*51 INo Data INo Oata (1.17t+00lf.6:1 01 11.41 01 11. 6 9t +0013. 2*t+0 21 i
i Ma 54 INo Cata 16.38t+03 18.35t+02the sta 11.30t*031No Casa 11.34E+04) i nn le INo *ata 11.10t+02 11.95T*01tNo *sta 11.40E+02lNo Cata 13.5 1+03l 1 Te 55 16.5?t+0 Is.54t+01 11.061*3: Iso Cata INo "sta 12.53t+02)2.61t+0:1 I Te 19 11.04t+0311.66t+03 19.3eE+C:INo,Cata INo sta le,. lit +0216.13t+031 c
1 Co 5? INo Casa 12.09t+01 13.48t+011No Osta Iso Data INo Data 15.31E+c:l l 0o 18 INo *sta 18.9.t+01 12.00E+0:lNo *sta INo :sta INo Osta 11.Ilt+C31 l Co*60 INo Osta 12.5?t+C: 13 3et+C:lNo Casa INo "sta INo Data le.8:1 +031 i N1 63 13.11t+0612.15t*03 11.04t+031No Ossa Iso "ata (No Osta le. sit +C2]
! Ni 65 11.:st+0:11.6.t+01 17. 81+CC INo Casa INo :sta INo Data 1+.16t+021 i Ca 6e INO *ata 11.00t+01 16.69t+00lso "ata 12.3:E+01lNo Casa 18.5:!*01)
! *nael 12.3*t+04l?.38t+0 13.33t+04lNo *ata 14.9:1+041No Data la 63E+C41 1 In s9 le.93t+0119.4.t+01 16.56t+00lNo Osta it.131+011No :sta 11..:1+011
/~\\
l Ital: lNo "sta INo Cata 12.87t+031No Cata INo :sta INo Osta 12.6:1+03l
(
)
l It 43 INo *ata INo Osta 16.0&t+01 iso Casa INo Cata INo Ossa (5.811*011 i Ir*li iNo Casa INo 04:4 15.6t+011No *at a INo Oata INo :ste is.13t 01 i tr*45 1No Oata INo Oata I.13t+00lNo Osta INo Osta INo "sta 1 0
1 1 Rbal6 INo Osta 11 01t+05 !. ?lt+0&lNo Osta INo *sta 1No Osta 11.99t*04i I Rb 48 lNo *ata 12.90t+0: 11.3.t*C:!No :sta INo :sta INo Osta 14.0;t*091 1 Rb st INo Osta 11.9;t >0211.331+C:lNo Casa INo Osta Iso :sts 11.1:1 111 1 3r 89 12. lt+0.INo Osta 16.35t+011No Osta INo :sta !No *ata 13.351-031 1 3res: 13...t+0 31 No *at a 11.3.t+C3;No Osta INo :sta 1No Osta 11.!!E+041 I ar 41 la.0*t*0*lNo Cate !1.6.t+011No Osta INo Osta INo Osta 11.961*03l I fr e* 11.3*t+0*tNo Osta lo ett+00tNo Cats !No Osta INo Data 13.06t+031 1 Y 40 15.?31 01INo 04ta I;.3 1 ::lho *ata (No :sta Iso :sta lo.101+C3t
! YealM tl..t=23tNo Osts 10.10t*0.lNo Osta ;No Osta LNo *sta 11.60ta 21 i Y 91 I4 3t+3 Iso Osta !. 51 01'No Osta iNo :sta iso Osta I..o.I-03!
5
! Y 9; 15.0!I 0;INo Data ti..ll 03.No *sta INo *ata INo :sta ll.t!!*O*1
! Y*t) 11.o:E* 11No Oata 14..;1 23;to Osta INo Osta IN6 sta 65.;6t+33I i :r*95 I
.;t 3117.*:t=0; ll 11 0 iNo Osta 11.;;1 01tNo Ossa 12...t+0:1 1
r*t? 11.33t*0:l; ett J3 11.* t 031No sta Is.0.I.;3tNo Osta It.3;E+0*i l Nb 95 le..it+0:1:. 8t+
11.3.t+::lNo Ost a 12..et+::!No Ossa 11.111* e; 1 90 99 !No :ste ;1.031*:: !L9et+01.No :sta 10.: t+::!No :sta i;.39E*0:1 1 *; so3lq g?t.23t,311 0: 13.;9t*:ltNo :sta 13.!!!*;111 ;31*::11. 41*011 1 ?; '0119.'11 0?l1.311 0 11.;t1 011No Casa I.:st*:146.*:i J.!
C i
l Ra 1 3!4.. 1+C0iNo Osta ll.9 1+00lNo *sta 11.ett+:llNo 04:4 15.1?t +C: l l Sa 1:313.elt*011No Sata
- 11. 51 011No Osta t..?tt* 0lNo Casa I 05t*0:1 f Ra*10616.57t+:1!No Cata ll.3:!*00lNo Osta (1.;71.
lNo Oata le.:St+ 31 1 ;4 109;so Casa ll.34t+0: 11. 9 1+01:No Casa 5.31t+::.No Oata 13.591+;31 i Sb 1;.ie.39t+0311. 61 01 II.elt*00ll t:t :: Iso :sta 15.211+ ll.N1*::i
-s N
/
21
CALIX 4AY F1 ANT OTTSITI D0lt OALOVLA:!:N
%NUAL tev. 3 g.
(
)
TAILE 1 (Continued)
IN0t3TNNOCSECCMITM.INTTACTOR(Ag) TOR A ULT AGE GROUP nrev ar ser m m u j
i 6 latal i i
i i
i Ivutidel fece ! tiver i lody i Thyrett i Kidrey 1 tun f St.tt! [
l Ib l*316.:lt*0:16.74102 61.0*1+0014.33103 (No Osta 13.30!M016 f tt+01l ITe*1:3MI:.3?t*0319.30t+0 (3.ast+0:lf.?:1+0 11.061+041No Osta 11.0:1+04l ITe*1;?MI6.6f t*03;;.3*E*03 If.90L*0:ll.66t*03 1163t+04 f No Oata 12. tit +26f ITe*1** 11.*lt+;;13, ?lt+01 1:.:$t0117. 8:t+31 14.29t+0;IM :sta 18.3:E+031 lie 129 Mil.1*t+0616.11t+03 11. f at+0313.78t+03 ls.60t+0'lNo Data 13.34t+06l ITe*1:9 13.011+0111.131*01 if.33t*0012.31t+01 11.:tt+0.lNo Osta 11.27t+011
!?s*131 Mil.66t+0318.09t+0 16.75t+C11.*lE*03 18.01E+03 tNo sta 18.03t+041 ITe.131 11.49t+0117.88t*00 13.96t+00ll.35t+01 18.13t+31lNo Osta 11.6f t+001 ITe*13 12.41t*0311.34t*03 11..f t+0311.?:E+03 11.30t+041No Oata 17.381+04)
!!*130 12.711+0114.01E*01 13.14t*3116. 9t*03 11.:st+02lNo Casa 16.89E*011
!!*131 l1.49t+0:l:.14E+02 11.211+C:17.00t+04 13.66t+0:lNo Oata 13.64t*011
!!*13 I?.29t+cCll.95t+01 16.4 1+00;6.8:14 13.111+011No Cata 13.661*301
!!*;33 13.1:1+0 ll e,87 t41 11. ?:E+0111. ):I+0. 11. 33t+0:l No Oata 17. 9 ?t*011
!!*134 13.811+3011.03t*01 13.70!+00ll.?ft*0: 11.a.t 31lNo Cata 19.01E.031 I!*133 11.39t*0114.16t+01 11. 34t+0112.?lt+03 16.64t*211No Osta 16.? L+011 ICs *134 12. 94t+3 317. 09t+33 13. 80t+03 lNo Ost a 12.29EC317.6:1+04 l 1.
- at ** 41 10s.s3e 13.1*E*0411.;3t+03 14.8aE+04lNo Osta 16.431+469.3914311..;t*061 1Ca*137 13.8 t+0313.2:1+03 13.4;t*031No Casa 11.*?tC313.89t+04tl.01t+041 C) 10a*138 12.66t+0:13.**E*0: 12.39t*0:lNo Osta 13. 84t<:13. M t+0112. 23 t *031 l
/
134 131 19.29t*0116.e:L*0s l!.?;t*:: Iso ata 16.19 t * :.13. ? 6 t
- 3 11. 6 3 tN01 O
lla*143 11.ta!+0:12.4.t*01 11.*?t+011No Osta 18.31t*0:11.4*t.0116.0014 21 JIn let 1. 3:t*0113.601 06 11.3 !*0 Iso sta 13.16t*0 11.93t*04l2.1*E*101 lla 14 l'.0-t*0112.091 04 11.:st*0:lNo Osta 11.??t*.41.19E*041 0
l JLo 140 11.3 L*0117.33t*0 11.99t*0:lNo Osta Iso Cata INo Oata 13.33t+03)
Ita*16 17.65t*0313..St*03 18.66t*04)No Osta INo Osta Iso Casa 12.34t*011 l
Ice *141 12.:.t*0:11.315 01 11.?:E*031No Esta l!.03t*03tNo Osta 13.78t+011 Ice *1 3 l3.9st*03 2.9:1+00 13.;31*04lNo Osta 11.:8t*031No Otta 11.0ft 4 21 1:e et.
11.1!!+00l. 44t*01 t e.;et*0 Iso Oata l'.45t*311No ata 13.9.t+0:1 ipr *1 3 13.!CE*0112.21E*01 12.?3t*: lso 04ta 11.:*t* 311No :sta 10.1t+031 l
Isaal.* 13.?st*011. 35t*01 10.e:E*0:lNo Cata 12.3.t*:ltso Osta I;.09t*03l i
iMt 141 13.99t*0:ll.9 E*01 11.80t*0 Iso Oata la.1?!.::lNo 04ta I.:lt-0 1 W.18? i :. 9 t!*0:12. s't*0: 18.e t*011No 04:4 INO :sta bo Cata iS MEdil l
isp*;4v,;.4.t 0;i;.4;t*03 tl.31*C3 Iso 04ta 18.? 1*c3(No tats i/.*.tC:t r
l f
CALLAWAY PLANT ChFSITE DOSE CALCULATION MANUAI.
Rev. 5 (3
)
.\\J TABLE 2 BI0 ACCUMULATION FACTOR (BF ) USED IN THE ABSENCE 1
OF SITE-SPECIFIC DATA" (pC1/kg) per (pC1/ liter)
BF g Olement Fish (Freshwater)
H 9.0 E - 01 l
Be 2.0 E + 00 C
4.6 E + 03 Na 1.0 E + O2 P
1.0 E + 05 Mn 2.0 E + O2 Cr 4.0 E + O2 Fe 1.0 E + O2 l
Co 5.0 E + 01 i
Ni 1.0 E + O2 Cu 5.0 E + 01 2n 2.0 E + 03 Br 4.2 E + O2 Rb 2.0 E + 03 S *.-
3.0 E + 01
(
Y 2.5 E + 01 2r 3.3 E + 00 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 l
Cd 2.0 E + O2 I
Sb 1.0 E + 00 Te 4.0 E + O2 I
1.5 E + 01 Cs 2.0 E
- 03 l
Ba 4.0 E
- 00 La 2.5 E + 01 Co 1.0 C + 00 i
Pr 2.5 E + 01 Md
- 2. 5 E + 01 i
1 Hf 3.3 E + 00 W
1.2 E
- 03 f
Np 1.0 E + 01 i
i I
(a)
Values from Regulatory Guide 1.109, Rev i
l Table A-1 and UE Safety Analysis Calculation SS-002-00-F.
h) i G
CALLAWAY PLANT OFFSITE DOSE CALCULA!!ON MANUAL Rav. 5 2.6 LIQUID RADWASTE TREATMENT SYSTEM 2.6.1 Technical Seecification 3.11.1.3 The LIQUID RAT *1ASTE TREATMENT SYSTEM Shall be OPERABLE and appropriate portions of the system shall be used to l
reduce releases of radioactivty when the projected doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
2.6.2 OPERABILITY Of The LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is capable of i
varying treatment, depending on waste type and product desired.
It is capable of concentrating, gas strip-ping, and distillation of liquid wastes through the use of the evaporator system.
The deminerali:ation system i
is capable of removing radioactive ions from solutions to be reused as makeup water.
Filtraticn is performed on certain liquid wastes and it may, in some cases, be l
the orbf required treatment prior to release.
The sys-O tem has the ability to absorb halides through the use 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 i
ensures this system will be available for use when liquids require treatment prior to their release to the environ: int.
OPERASILITY is demonstrated through com-l pliance ith Technical Specifications 3.11.1.1 and 3.11.1.2.
I Projected doses due to liquid releases to UNRESTRICTED j
AREAS are determined each 31 days by dividing the cum-j mulative annual total by the number of elapsed months.
)
I l
24 -
l
=
t i
I
CALLAWAY PLANT l
0FFSITE COSE CALCULATION MANUAL Rev. 5
/N
\\s-)
3.0 CASEQUS EFFLUENTS l 3.1 Technical Seecification 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 in accordance with the methodology and,
smeters in the CDCM.
3.2 Technical Specification 3.11.2.1 The dose rate due to radioactive materiale released in gaseous effluents from the s'ite to are'as at and beyond i
the SITE SOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr i
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 l
s l
mrem /yr. to any organ, from the inhalation pathway 1
only.
3.3 Casecus Effluent Monitors 1 Noble gas activity monitors are present on the contain-i ment building ventilation system, plant unit ventila-tion system, and radwaste building ventilation system.
The alarm / trip (alarm & trip) setpoint l'or any gaseous effluent radiation monitor is determined based on the i
instantaneous noble gas total body and skin dose rate l
limits of Technical Specification 3.11.2.1, at the SITE l
BOUNDARY location with the highest annual average X/Q value, (Figure 5.13) l Each monitor channel is provided with a two level sys-I tem which provides sequential alarms on increasing radioactivity levels.
These se: points are designated as alert setpoints and alarm /tr:p setpoints.
(Re' 9.6.3) i !
I l
i
.-.,.--w..
-._,,n
,....y-.-,,_,
..n_--av,
_-_g-~v
,, w
CALLAWAY PLANT OFFSITE DOSE CALCULATACM MANUAL Rev. 5 The radiation monitor alarm / trip setpoints for each release point are based on the radioactive noble gases in gaseous offluents.
It is not considered practicable to apply instantaneous alarm / trip setpoints to inte-grating radiatien monitors sensitive to radiciodines, radioactive materials in particulate form and radionu-clides other than noble gases.
Conservative assump-tiens may be necessary in establishing setpoints to ac-count for system variab.!es, such as tne 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 Specificatiens Table 4.3-13 provides the instrument surveillan:e' requirements, such as cali-bration, source 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 i Each of the above continuously monitors gaseous radi-l cactivity concentrations downstream of the last point I of potential influent, and therefore measures effluents I and not inplant cencentrations.
The Unit Vent monitor continuously monitors the ef-l fluent fr:m the unit vent for gaseous radioactivity.
The Unit Vent, via ventilation exhaust systems, conti-nuously purges various tanks and sumps normally con-ta:ning low-level radioactive aerated liquids that can potentially gene: ate airborne activity.
26 -
CALLAWAY PL' ANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 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.
l The Unit Vent monitor provides alarm functions only, l and does not terminata releases frcm the Unit Vent.
l The Radwaste Building Ventilation effluent monitor con-l tinuously monitors for gaseous radica:tivity in the ef-fluent duct downstream of the exhaust filter and fans.
I 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-I charge line upon a high gaseous radioactivity alarm.
The continuous gasecus effluent monitor setpoints are establiahed using the meth:dology described in Section 3.4.
Since there are two continuous gaseous effluent I release points, a fraction of the total dose rate limit I (DEL) will be allocated to each release point.
Ne-glecting the batch releases, the plant Unit Vent ment-I ter has been allocated 0.7 DEL and the Radwaste Build-l :ng Vent monitor has been allocated 0.3 D2L.
These al-I location factors may be changed as required to support I plant operational needs, but shall not be allowed to i exceed unity (i.e.
1.0).
Therefore, a particular moni-l ter reaching the setpoint would not necessarily mean I the dose rate limit at the SITE SOU::DARY is being ex-ceeded the alarm only indicates that the specific release point is contributing a greater fraction of the i dose rate limit than was allocated to the associated monitor, and wil. necessitate an evaluation of heth systems.
I 1
CALLAWAY PLANT OFFSITE DOSE CALCULATION bWMAL Rev. 5 O
1 3.3.2 Batch Release caseous Menitors The radiation monitors associated with batch release gaseous effluents are (Ref. 9.6.9, 9.6.10, 9.6.11):
Monitor I.D.
Description l
GT-RE-22 Containment Purge System l
GT-RE-33 I
t f
GH-kE-lO Radwaste Building Vent l The Containment Purge System monitors continucusly menitor the containment purge exhaust duct during purge l operations for gaseous radioactivity.
The primary pur-pose of these moniters is to isolate the containment j
l purge system en high gaseous activity via the ESFAS.
1 i
The sample points are located cuttide the containment between the containment isolation dampers and the con-tainment purge filter adsorber unit.
l l
l The Radwaste Building Vent monitor was previcusly described An Section 3.3.1.
il l Setpoints for the batch gaseous effluent monitors are l calculated using the methodology described in Section 3.4.
I i
A pre-release isotopic analysis is performed for each i
batch release to determine the identity and quantity of I
the princ pal radienuclides.
The alarm / trip i setpoint(s) is adjusted accordingly to ensure that the l
2
) limits of Technical Specification 3.11.2.1 are not j
j exceeded.
t l
I t
I l
i 1
. l l
l l
1
i t
CALLAWAY PLANT OFFSITE D0dE CALCULATION MANUAL Rev. 5 l 3.4 Determination of Gaseous Effluent M_o ni t o r S e tp o i n_t_s i
i I
The alarm / trip setpoint for gaseous effluent monitors l
1s determined based on the lesser of the total body dose rate and skin dose rate, as calculated for the SITE BOUNDARY.
3.4.1 Total Body Cose Rate Setpoint Calculations I
To ensure that the limits of Technical Specification 3.11.2.1 are met, the alarm / trip setpoint based on the 1
total bcdy dose rate is calculated according to l4 c
l f
tb tb,F, (3.1)
S 1O R
F tb 1
1 Where:
Stb =
the alarm / trip setpoint based on the total
{
body dose rate (uCi/cc).
Te:hnt:al Specification 3.11.2.1 limit of O
=
tb 500 mrem /yr, conservatively interpreted as a continuous release over a ene year period, i
F,=
the safety factor; a conservative factor used to compensate for statistical fluctuations and i
orrors of measurement.
(For example, F, = 0.5
(
j corresponds to a 100% variation.)
Default value is F
= 1.0.
l s
i t
the allocation factor which will modify the F
=
a r
required dilution factor auch that simultaneous gaseous releases may be made i
without exceeding the limits of Radiological
[
Effluent Technical Specification 3.11.2.1.
L The default value is 1/n, where n is the num-l ber of pathways planned for release.
f t
]
i l
CALLAWAY PLANT OFFSITE DOSE CAI.CULATION MANUAL Rev. 5
\\_/
Rtb =
actor used to convert dose rate to the effluent concentration as measured by the ef-fluent monitor, in 'uci/cc) per (mrem /yr) to s
the total body, determined according to:
Rtb = C + [(X/Q) I K Qg)
(3.2) g i
Where C=
monitor reading of a noble gas monitor cor-responding to the sample radionuclide 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 es is correlated to a calibration factor to
(
)
determine monitor response.
The monitor i
response is based on concentrations, not release rate. and is in units of (uC1/cc).
X/Q =
the highest calculated annual average relative concentration for any area at or beyond the 8
SITE SOUNDARY in (sec/m ).
Refer to Tables 9, 10, and 12.
the total body dose factor due to gamma K
=
g emissions for each dentified noble gas radienuclide, in (mrem /yr) per (uC1/m').
(Table 3) rate of release of noble gas radionuclide, Q
=
1, in (uC1/sec).
fM
(-,)
- 2a.
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 l
)
xs' 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, 3.4.2 Skin Dose 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 i
S, < D,R,F,F, (3.3)
Where
()
F, and F, are as previously defined in Section 3.4.1.1.
v S,=
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 ever a one year period.
l l
1 l
1 1
0 l l
l I
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev 5
r R, a factor used to convert dose rate to the effluent concentration as measured by the ef-fluent monitor, in (uci/cc) per (mrem /yr) to the skin, determined according to R,=C+
((X/Q) 1 (Lg
- 1.1M ) Qg]
(3.4) g i
Whore Lg=
the skin dose factor due to beta emissions for each identified noble gas radion.~clide, in 3
(mrem /yr) per (uci/m ).
(Table 3) 1.1 = conversion factor:
1 mrad air dose =
1.1 mrem skin dose.
i Mg=
the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad /yr) per (uci/m ).
(Table 3)
C, (57d) and Q are as previously defined.
g 3.4.3 Gaseous Effluent Monitors Se point Determination The results of Equation (3.1) and Equation (3.3) are 00mpared.
The setpoint is then selected as the lesser f
of the two values, I
l i
! r i
l
4 N.s I
E So
-$i te o
r0 a
)=
-=
<W
- i 2
a(_5 w
.. s n--g!g?????fri?---~ g--
$37 it t
?!?: :
___...____.m o.
a
-s s
?. O. e. O. M. **. #. c.. #. N. % N.
.~.,-- -..
ee~e.
q 8.8 E >e W@
s
.~ ~. ~,.,.,,
u C
4 s.
~
.s.
gi R
.J
.E u
ga,~y~000000
~b 0 0 0 0.. 0 0 0.
< a.
1 e
us,
=
r
~~--e~-os..O 1,l
~
- n. ~.. e. ~.. e. n. e... c. n..
e I
3 3,.
4..---.,
o s
_ _.i
=
4
< w 8me
.~ w w
s i
e e
1 e
s.
=l 3
2 o 4 A 2
t gerge:dege:<=g a
s E
5j, 4l 9
S u
4 d.
. N.. O. W. N e. g*.* @ N - >
4 X - % = {% 4 #
9 4
_. C N.
4 E
i gl g
s h
4..,N.%aS-~
.= a N 8
wi
-s a
o 8 s
w g,
s e
e d.
=
0 0
s 9
"5 1
L,3
~
g 1
dr:rges:eS ::::
6 2
e o
9 4
es 4 %.= P. % g* 4 e.= s P, s. N an a w
==-
- 4. e. X. w. eS a e. P. **. G. #. #. C.
.e
- 9. t 4, o'.=
s
-c
.p r,e,- - g g 3J h
"$ S 0
9 5
=
T
=
58 5 EE
- - *.%.% % e
=
g
,% J4 % C $ 0 M - M M M M M e q
ccccccd==.====
g i e e e e e e i e e e
e e g
b = = * * * * % % $ 5 4 % *e *
=
a444aaxxAnA4Ax<
- 3 e.
9 4
w
CALLAWAY PLANT OFFSITE DOSE CALCULATICH
. MANUAL Rev. S 1
s I
3.4.4 Summary, Gaseous Effluent Monitors Setpoint
^
Determination The gaseous effluent monitors setpoints are calculated according to equations (3.1) and (3.3), as described in Section 3.4.
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, i
the setpoint for the Unit Vent monitor must be re-calculated to include both the continuous and batch sources.
l 3.5 calculation of Dese From Caseous Effluents Dose rate calculations are performed'for ' gaseous ef l fluents to ens.re compliance with Technical Specifica-I tion 3.11.2.1.
l 3.5.1 Calculation of Dese Rate The following methodology is applicable to the location (SITE BOUNDARY or beyond) characteri:ed by the values l
of the parameter (X/Q) which results in the maximum total body or skin dose rate.
In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable j
4 release values.
(Ref. 9.9.7)
The factors K,
L, and M relate the radionuclide air-g g
g borne concentrations to various dose rates, assuming a i
semi-infinite cloud model, and are tabulated in Table 3.
l i
3.5.1.1 Noble Gases The release rate limit for noble gates is determined I
according to the following general relationships (Ref.
i 9.3.7):
l l
Dtb
- I IK ((X~2I9 )I 5 BOO *#'"/Y#
(3'0I I
1 i
i i
I l
CALLAWAY PLANT O?FSITE DOSE CALCULATION MANUAL Rev 5
g + 1.1 M )((X/Q)Qg)] 2 3000 mrom/yr (3.6)
D,
= ! [(L g
i Where:
Dtb =
Total body dose. rate, conservatively averaged over a period of one year.
Kg=
Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in 3
(mrem /yr) cer (uci/m ).
(Table 3) l l
iX/Q)
The highest calculated annual average relative
=
concentration for any area at or beyond the SITE SOUNDARY.
Refer to Tables 9, 10, and 12.
The release rate of noble gas radienuclides, Q
=
1, in gaseous effluents, from all vent eleases in (uci/sec).
Q is calculated as the product of the ven-g 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 a period of one year.
Skin dose factor due to beta emissions for L
=
each identified neble gas radienuclide, in (mrem /yr) per (sci /m') (Table 3),
1.1 =
Units conversion factor; 1 mrad air dose = 1.1 mrem skin dose. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l CALLAWAY PLANT l
CFFSITE DOSE CALCULATION MANUAL Rev. 5 Mg=
Air dose factor due to gamma emissions for each identified noble gas radionuclide, in 3
(mrad /yr) per (uC1/m ) (Table 3).
l 3.5 1.2 Radionuclides other Than Noble Gases The release rate limit for Iodine-131 and-133, for tri-tium, and for all radioactive materials in particulate form with half lives greater thsn 8 days is determined a; cording to (Ref. 9.8.8):
D, = I P [(X/Q)Qg] $ 1500 mrem /yr (3.7) g 1
Where:
D, =
Dose rate to any critical organ, in (mrem /yr).
Pg=
Dose parameter for radionuclides other than I
noble gases for the inhalation pathway for the i
child, based on the critical organ, in (mrem /yr) per (uci/m').
(Table 4)
[
Q=
The release rate of radionuclide, i, in l
g gaseous effluents, from all vent releases, in (uCi/sec).
Qg is calculated as the product of the ventilation path design flow rate and the measured activity of the effluent stream as i
determined by grab sampling.
Flow rates for i
the ventilation pathways can be found in ref-l erences 9.6.21, 9.6.22, 9.6.23, and 9.6.25, (X/Q) is as presiously defined.
[
The dose parameter (P ) includes the internal dosimetry g
cf rcdi:nuclide, 1.
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 i
age group.
l l
t I !
I
CALLAWAY FLANT 0FFSITE DOSE CALCULATICH tRNUAL Rev. 5
\\
I For the child exposure, separate values of P are tabu-g lated in Table 4 for the inhalation pathway.
These values were calculated according to (nef. 9.8.9):
i I
Pg = K' (BR) DFA (3.8) g Where K' =
Units conversion factor: luci = IE06 pC1.
l ER=
The breathing rate of the maximum exposed 8
child age group, 3700 m /yr.
( Re gulato ry j
J Guide 1.109, Table E-5).
l DFAg=
The maximum organ inhalation dose factor for 1
4 the child age group for the ith radionuclide, i
j in (mrem /pci).
The total body is considered l
t as an organ in the selection of DFA.
(Ref.
[
g
]
9.11.5 and 9.16.5) l Note:
All radioiodines are assumed to be released in i
elemental form.
(Ref.9.8.8) i l
i i
I s
r I
t l
l l
l
,l i 1
J
CALIMAY PLANT OFFSITE DOSE CALCULATION
!!ANUAL Rev. 5 TABLE 4 DOSE PARAMETER (P,) FOR RADIONL'CLIDES OTHER THAN NOBLE GASES" Inhalation Pathway 8
(mrem hr) per (uci/m )
l l
l l Total l
l l
l l
lNuc11 del Bone i Liver i Body i Thyroid i Kidney l Lunt i GI-LLI l lH3 l ND ll.10E3 11.12E3 11.12E3 11.12E3 l1.12E3 l1.12E3 l l Be 7 14.47E2 11.44E3 19.25E2 l ND l ND 16.48E4 12.55E3 l l C 14 13.59E4 16.73E3 16.73E3 16.73E3 l6.73E3 16.73E3 16.73E3 l l Na 24 11.61E4 l1.61E4 11.61E4 11.61E4 l1.61E4 l1.61E4 11.61E4 l l P-32 12.60E6 11.14E5 19.88E4 l ND l ND l ND 14.22E4 l l Cr-51 l ND l ND l1.54E2 18.55El 12.43E1 11.70E4 11.08E3 l
3 l Mn-54 l ND 14.29E4 19.51E3 i ND ll.00E4 l1.58E6 12.29E4 l l Mn-56 l ND l1.66E0 13.12E-1 1 ND (1.67E0 11.31E4 11.23E5 l
O l Fe-55 14.74E4 l2.52E4 17.72E3 l ht l ST 11.11E5 12.87E3 l l Fe-59 l2.07E4 13.34E4 l1.67E4 i ND l 53 11.27E6 17.07E4 l l Co-57 l ND l9.03E2 11.07E3 l ND l ND l5.07ES l1.32E4 l l Co-58 l 53 11.77E3 13.16E3 l ND l St l1.11E6 l3.44E4 l l Co 60 l ND 11.31E4 12.26E4 l 53
! ND 17.07E6 l9.26E4 l l Ni-63 18.21E5 14.63E4 12.80E4 l ND l ND 12.75E5 16.33E3 l
1 Ni 65 12.99E0 12.96E 1 11.64E 1 1 ND l ND 18.18E3 l8.40E4 l l Cu 64 l St 11.99E0 11.07E0 l 53 l6.03E0 19.58E3 13.67E4 l l 2n-65 le.26E4 l1.13E5 17.03E4 l St 17.14E4 l9.95E5 11.63E4 l l 2n 69 16.70E-2 19.66E 2 18.92E-3 l St 15.85E-2 l1.42E3 11.02E4 l l Br 62 1 ND l ND
{4.18E3 1 ND l ND l ND l ND l
l Br 83 l ND l ND 14.74E2 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 ND l ND l ND l
0 l
l Rb 86 1 ND 11.95E3 11.14E3 l ND i ND I SD l7.99E3 l
l Rb 88 l St 15.62E2 l3.66E2 i ND l St l ND l1.72E1 l
l Rb-89 l St 13.45E2 l2.90E2 l ND l ht l ND l1.89E0 l l Sr 89 15.99E5 l ND l1.72E4 l ND l ND l2.16E6 l1.67E5 I
l Sr-90 11.01ES l ND 16.44E6 l ND l ND 11.48E7 13.e3E5 l
l Sr 91 11.21E2 l
St l4.59E0 l St l ND 15.3?E4 l1.74E5 l
l Sr 92 11.31El l ND l5.25E 1 l ND l ND 12.4CE4 12.42E5 l
l Y 90 14.11E3 i ND 11.11E2 l ND l ND 12.62E5 12.6SF5 1
0 =
CALLAVAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 TABLE 4 (Cont 'd. )
f DOSE PARAMETER (P ) FOR. RADIONUCLIDES OTHER THAN NOBLE GASES' g
Inhalation Pathway (mrem hr) per (uci/m')
l I
l 1 Total i
i l
i l
lNuclidel Bone i Liver l Body i Thyroid i Kidney I Lung l GI-LLI l l
1 l Y 91m 15.07E 1 l ND 11.84E 1 ND l ND 12.81E3 l1.7 E3 l
l Y 91 $9.14E5 l ND 12.44E4 i ND l ND 12.63E6 l'1. 84E5 l l Y 92 12.04E1 l ND l5.81E 1 l ND l ND 12.39E4 12.3955 l
4 1
l Y 93 11.86E2 l ND 15.11E0 l ND l ND l7.44E4 13.89E5 l
I Zr 95 11.90E5 14.18E4 13.70E4 l ND 15.96E4 12.23E6 16.11E4 l l Zr-97 l1.88E2 l2.72E1 l1.60E1 l ND 13.89El l1.)3E5
[3.51E5 l l
l Sb 95 l2.33E4 19.18E3 16.55E3 l ND 18.62E3 16.14E5 13.70E4 l l Mo 99 i ND ll.7 E2 l4.26El l ND l3.9 E2 11.35E5 11.27E5 l
i l Tc 99 mil.78E-3 13.48E 3 15.77E 2 l ND l5.07E-2 19.51E2 14.81E3 l
1 j
(
l Tc-10118.10E-3 l8,51E 3 11.0$E 3 1 ND 11.45E 3 15.85E: 11.63E1 l
l Ru 103l2.79E3 l ND ll.07E3 l ND l7.03E3 l6.62E5 14.48E4 l l
l l Ru 10511.53E0 l ND 15.55E 1 l ND ll.34E0 l1.59E4 l9 95E4 l j
l Ru-106l1.36E5 i ND l1.69E4 l ND 11.84E5 11.43E7 l4.29E5 l
IAg 110 mil.69E4 l1.14E4 l9.14E3 l ND l0.12E4 15.48E6 l1.00E5 l
[
I l Cd-1091 ND 15.48E5 12.59E4 l ND la.96ES 11.05E6 12.78E4 l
l 1
l l Sb 12415.74E4 l7.40E2 10.00E4 11. 6E2 1 ND l3.04E6 l1.64E5 l
f l Sb 1 519.84E4 ]7.59E2 12.07F.4 19.10E1 l ND 12.3 E6 14.03E4 l t
1 lTe-125ml6.73E3 12.33E3 19.141 2 l1.9:E3 i ND 14.77E5 13.38E4 l
a
),
ITe 127ml'. 49E4 l$ 53E3 l3.0 E \\ 16.07E3 16.36E4 ll.48E6 17.14E4 l l
lTe 127 12.'7E0 (9.51E-1 l6.11E 1 11.96E0 17.07E0 11,00E4 15.6:E4 l
l I
lTe 129 mil.90E4 l6.85E3 13.04E3 16.33E3 15,03E4 11.76E6 l1.8:E5 l
i j
ITe 129 19.77E-13.50E 2 12.38L*2 17.14E 2 12.57E 1 12.93E3 l0.55E4 l
i lTe 131 mil.34E 15.9:El 15.07El l9.77El i4.00E: 12.06E5 13.08E5 l
ITe 131 12.17E 2 18.44E 3 16.59E 3 l1.70E 2 15.88E 2 12.05E3 11.33E3 l
lTe 13: 14.81E: 12.7:E:
l2.63E2 13.17E:
11.17E3 13.77E3 11.38E5 l
lI 130 IS.1$E3 11.e4Ee
!!.ut3 11.35E6 145!4 I ND 15.11E3 l
11 131 14.81E4 14.81E4 12.73E4 11.6:E7 17.88E4 i ND 12.84E3 l
i j
II-132 l2.1:E3 l4.07E3 l1.SSE3 11.94E5 i6.0$E3 i SD 13.00E3 l
J II 133 11.66E4 l:.03E4 l7.70E3 13.85E6 13.3CI4 l ND 15.48E3 l
l i
lI 134 l1 17E3 10.16E3 l9.95E l5.0'E4 13.3043 i ND 19.55E2 l
l 11 135 14.9 E3 18.73E3 le.14E3 l7.9 E5 11.34E4 l ND
- 14. 4E3 l
l f
t o
i t
39 -
l i'
CALLAVAY PLAST OFFSITE DOSE CALCULATION MANUAL Rev. 5 TABLE 4 (Cont'd.)
DOSE PARAMETER (P ) FOR RADIONUCLIDES OTHER THAN NOSLE CASES" g
Inhalation Pathway (mrem hr) per (uci/m')
l l
l l Total l
l l
l l
lNuclidel Bone !
Liver l Body i Thyroid 1 (,idney I Luna l GI LLI l lCs-134 16.51E5 11.01E6 l2.25E5 l ND l3.03E5 11.21E5 l3.85E3 l lCs-136 l6.51E4 l1.71E5 l1.16E5 l ND 19.55E4 l1.45E4 1,4.18E3 l
lCs-137 l9.07E5 ls.25E5 11.2SES l ND l2.72E5 l1.04E5 l3.6*E3 l
lCs 138 l6.33E2 18.40E2 l5.55E2 l ND l6.22E2 l6.81El l2.70E2 l lBa-139 11.84E0 19.84E 4 l5.37E 2 l St 18.62E-4 15.77E3 15.77E4 l lBa 140 l7.40E4 16.48E1 14.33E3 l ND l2.11El 11.74E5 l1.02E5 l
lBa 141 12.19E 1 11.09E 4 16.36E 3 l St 19.47E 5 12.92E3 12.75E2 l lBa-142 15.00E 2 13.60E 5
[2.79E-3 l ht 12.91E 5 11.64E3 12.74E0 l lLa-140 16.44E2 l2.25E2 l7.55El l ND l ND 11.33E5 12.26E5 l lLa-142 11.30E0 l4.11E-1 11.29E 1 l ND l ND IS 70E3 17.59E4 l lCo-141 13.92E4 l1.95E4 l2.90E3 I ht 18.53E3 15.44E5 15.66E4 l lCo 143 13.66E2 l1.99E2 l2.87El I ht l8.36El 11.15ES 11.27E5 l
lCo-144 16.77E6 12.12E6 l3.61E3 l ND ll.17E6 ll.20E7 13.89E5 l
lPr 143 11.85E4 l5.55E3 l9.14E2 l ND l1,00E3 14.33E5 19.73E4 l lPr 144 15.96E 2 11.85E 2 13.00E 3 l ND 19.77E-3 11.57E3 11.97E2 l lNd 147 11.0$E4 l8.73E3 l6.81E2 l ND 14.81E3 l3.28E5 18.21E4 l lHf 181 12.78E4 l1,01E5 ll.25E4 l ND l2.05E4 l1.06E6 16,62E4 l lV 187 11.63E1 19.66E0 14.33E0 l ND l ND 14.11E4 19.10E4 l lNp 239 l4.66E2 l3.34E1 12.35El l ND 19.73E1 15.81E4 16.40E4 l (a) The child age group; Table E 9 Reg. Guide 1.109. Rev. 1, 1977 and UE Safety Analysis Calculation 88 002 00-T.
O 40 -
i CALLAWAY PLANT I
0FFSITE DOSE CALCULATION MANUAL Rev. 5 i
l 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 of-fluents, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
t i
a.
During any calendar quarter:
Less than or equal to l
5 mrad for gamma radiation and less than or equal 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 a
20 mrad for beta radiation.
r 3.5.2.1.1 Noble cases The air dose at the SITE SOUNDARY due to noble gases j
l released from the site is calculated according to the l
following raethodology (Ref. 9.8.10):
i l
During any calendar quarter, for gamma radiation:
1 L
D
= 3.17 E-08 t [Mg ((X/Q) Qg + (X/q) q1)] $5 mrad (3.9) 9 1
1 1
During any calendar quarter, for beta radiation:
}
\\
Dg = 3.17 E-03 I [Ng ((X/Q) Q
+ (X/q) q )) 1 10 mrad (3.10)
[
g g
]
i
[
l l
j During any calendar year, for gamma radiations
.,(
t 1
k j
(X/q) q )] 5 10 mrad (3.11)
D
= 3.17 E-OS 1 [M
((X/Q) Q
+
g 9
g g
l l
i During any calendar year, for beta radiation:
I l
i (Xcq) g )] ! 20 mrad (3.12) l D
= 3.17 E-OS I [N. ((X/Q) Q j
l s
1 q
1 41 -
f
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL R4v. 5 Where:
Air dose from gamma radiation due to noble D
=
9 gases released in gaseous effluent.
Db=
Air dose from beta rediation due to noble gases released in gaseous effluents.
=
The relative concentration 'or areas at or (X/q)
~
beyond the SITE BOUNDARY fo:, short-term releases (equal to or less than 500 hrs / year).
Refer to Tables 9, 10, 11, std 12, qg=
The average release of noble gas radionu-clides, 1 in gaseous effluents frem all vent releases for short-term releases (equal to or less than 500 hrs / year), in (901).
Releases l
are cumulative over the calendar quarter or l
year, as appropriate.
l Ng=
The air dose factor due to beta emissions for each identified noble gas radionuclide, 1,
in (mrad /yr) per (aci/m'). (Table 3)
Qg=
The average release of noble gas radionu-
/lides, i, in gaseous effluents frem t.11 vent releases for long-term releases (greater than 500 hrs / year), in (sci).
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-C5 = The inverse of the number of seconds por year.
M is as prev:ously defined. (Refer to Se:::en 3.4.1.2) g l
l l
4:
CALLAWAY PLAltr i
0FFSITE DOSE CALCULATION MANUAL Rev. 5 gx
\\~)
3.5.2.2 Technical Specification 3.11.2.3 t
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 gasecus of-7 fluents released, to areas at and beyond the SITE BOUN-DARY shall be limited to the following (Ref. 9.8.10):
l a.
During any calendar quarter Less than or J
equal to 7.5 mrom to any organ and, i
b.
During any calendar year:
Less than or equal l
to :S mrem to any organ.
I 3.5.2.2.1 Radienuclides other Than Neble cases The dose to a MEMBER OF THE PUBLIC frem 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-j l DARY, is calculated according to the following expressions:
I j
During any calendar quarter:
g + v q ] $ 7.5 mrum (3.13)
Dg = 3.17E-CB 1 Rg iW Q g
i 4
J During any calendar year (W Q
- v g ] $ 15 mrem (3.14)
Dg = 3 17E-08 I R1 g
g 1
i Where:
3 Cose to a MEMBER OF THE FUBLIC fren D
=
3 radienuclides other than noble gases.
i I
I
- i I
i CALLAWAY PLANT OTTSITE DOSE CALCULATION MAMUAL Rev. 5 l Qg =
The releases of radioiodines, radioactive materials in particulate form, and radionu-clides other than noble gases, 1,
in gaseous effluents, for all vent releases for long-term l
releases (greater than 500 hrs /yr), in (uci).
Releases are cumulative over the calendar quatter or year as appropriate.
Igg =
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 release? (equal to or less than 500 hrs /yr),
$n (901).
Releases are cumu(ative over the calendar quarter or year as appropria';e.
R
=
The dose factor for er.cn identified 3
8 radionucl' de, i, in m (mrem /yr) per (uci/sec) 8 or (mrem /yr) per (9C1/m ). (Table 5)
N=
The dispersion parameter for estimating the dose to an individual at the controlling loca-O tion for long-term releases (greater than 500 hrs /yr):
W = (X/Q) for the inhalation and tritium pathways, 8
in( sec/m ).
W= (D/Q) for the food and ground plane pathways, in(meters"8).
Refer to Tables 9, 10, and 12.
O
- 44
CALLAWAY PLANT OnTSITE COSE CALOUT.ATION MANUAL Rev. 5 v=
The dispersion parameter for estimating the dose to an individual at the controlling loca-tion for short-term releases (equal to or less than 500 hrs /yr):
w = (X/q) for the inhalation pathway, in(sec/m')
w = (D/q) for the food and ground plane pathway, in (meters *8).
Refer to Tables 9, 10, 11, and 12.
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).
O 1
1 I
45 l
l CALLAHAY PLANT ofFSITE DOSM CALCULATION MAMfAL Rev. 5 (D/q) =
the relative deposition of the effluent at or l
beyond the SITE BOUNDARY, considering deple-l tion of the plume during transport, for short term releases (less than or equal to 500 hrs /yr), in (meters *8).
Note:
For the direction sectors with existing pathways within 5 miles from the 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
vr.lue 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 R at '4.5 to 5.0 miles, g
then the value of the cow-milk R at 4.5 to 5.0 miles g
is used. (Rev. 9.8.10.)
Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q) are generally censidered to be at the approximate O
receptor location in lieu of the $1TE BOUNDARY for these caleviattens, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residenen with the highest value of (X,'Q).
(Ref. 9,8.10)
The Total Sody dose from grcund plane deposition is added to the dose for each individual organ.
(Ref. 9.11.3) l 0,
i I
CALLAWAY PLANT OTTSITE DOSE CALCULATICN MASTA T-Rev. 5 i 3 i
l b
TABLE 5 l
PATHVAY DOSE TACTORS (R ) TOR RADIONUCL!DE5 UTHER THAN NOBLE GASES" l
g i
l l
l Inhalation Pathway (mrem hr) per (wC1/m')
i 1
i l'
i l
i Totst i
l l
l l
i l
lNuclidel Bene l Liver i Body l Thyroid l Kidney l Luna 1 GT LLI l F
lH3 l ND l1.10E3 11.1 E3 11.1:E3 11.1:E3 l1.12E3 11.1:E3 i I
i le 7 18.47E2 11.%4E3
- 19.25E2 i ND l ND l6.4SE4 l2.55E3 l
l l C 14 13.59E4 16.73E3 16.73E3 16.73E3 l6.73E3 16.73E3 16.73E3 l
j l Na 04 11.61E4 l1.61E4 l1.61E4 11.61E4 11.61E4 l1.61E4 l1.61E4 l 1 P 32 12.60E6 ll.14E5 19.8SE4 l ND l ND l ND l4.22E4 l r
t t
I l Cr 51 l St i ND 11.54E2 l$.55El l2.43E1 11.7CE4 11.08E3 I
[
l Mn 54 i ND 14.29E4 19.51E3 l ND 11.00E4 l1.5SE6 12.29E4 l l
l r: 56 l ND l1.66E0 13.1 E 1 l.sD 11.67E0 11.31E4 11.23E5 1
1 Ca 57 l ND l9.03E2 11.0tE3 i ND l ND 15.07ES 11.3:E4 I
(
l Tr 55 la 74E4 10.5:E4 17.7 E3 l ND i St 11.11E5 12.87E3 1 t
l To 59 I:.07E4 l3.34E4 11.67E4 l ND l ND it.27E6 17.07E4 l
}
I Co a I ND 11.77E3 t3.16E3 i SD 1 ND 11.11E6 13.44E4 l l Co 60 I ND 11.31E4 12.:6Ea i ND l ND 17.07E6 19.26E4 l l Ni 63 la.21E5 l4.63E4 12.80E4 l ND 1 ND 12.75E5 16.33E3 l l
l Ni 65 I:.99E0 12.96E 1 11.64E 1 1 ND i ND is.18E3 18.40E4 i I
l Cu 64 l ND l1.99E0 11.07E0 l St 16.03I0 19.5sE3 13.67E4 l l n 65 14.:6E4 11.13E5 17.03E4 i ND 17.14 t '. 19.95E5 11.63E4 l l :n 69 (6.70E 2 l9.66E 2 l4.92E 3 l St 15.S$E 2 11.a:E3 11.0:E4 l l Br 3: 1 ND l ND 14.18E3 I ND l C l ND 1 ND l
t f
I tr 83 i ND l ND l4.74E2 i ND l ND I ND l
0 l
l St s4 l ND 1 ND 15.4&E2 l ND l ND l ND l
0
(
r I sr 55 i ND 1 ND 12.53E1 I st i ND l ND 1
0 t
j t Ab s6 i ND 11.9sE5 ti.14t3 i ND 1 ND l ND 17.99E3 i
i Rd ss I ht 15.6:E:
13.66E:
1 ND I ND 1 SD l1.7:El I
l l Rd s9 i ND 3.e5E2 1:.scE:
I ND
t i Sr 90 11.01E$ l ND 16.44E6 l ND 1 ND 11.45E7 13.43E5 l
l l St 91 11.21E2 1 ND 14.59EO l ND l ND 15.33E4 11.74E5 1 1 St 9
[1.31El I ht 15.05E 1 i St l ND 10.40E4 12.4:E5 1
1 Y 90 14.11E3 I ND l1.11E:
l ND i ND 10.6:E5 10.65E5 l
l
[
[
l 47 -
I l-5
h CALLAVAY PLANT t
OTT.9tTE DOME CALCt'LATION I
ttAN11AI.
Rav. 5 l
TABLE 5 (Cont'd.)
PATWAY DOSE TACTORS (R ) TOR RADIONi,'CEIDES OTHER THAN NOST.E GA5ES' f
g l,
Inhalation Pathway l
8 (arem hr) per (sci /m )
i t
l l
l l Total i
i i
l l
l lNuclidel Bone l
Liver i Body i Thyroid i Kidney l Luna i G! I.L! !
l l Y 91m 15.07E 1 l ND 11.84E : 1 ND l ND 12.81E3 11.7;E3 l h
l Y 91 19.14E5 l ht l2.44E4 l ND -
i ht l2,63E6 l1,84E5 i
r l Y 9: 10.04E1 l ND l5.SIE 1 l ND l ND 12.39E4 12.39E3 l
i l Y 93 l1.86E2 l ND l5.11E0 l ND l ND l7.44E4 l3.89E5 l j
i Zr 95 l1.901.5 l4.1SE4 l3.70E4 l ND l5.96E4 l:.23E6 l6.11E4 l t
l 3r 97 l1.88E 12.7 El 11.60E1 l ht l3.39El 11.1*ES l3.51E5 l l Nb 95 I: 33E4 19.18E3 16.53E3 l ND is.62E3 16.14E5 l3.70E4 1 l !!o 99 l ND 11.7 E2 l4.26El l ND l3.9 E 11.35E5 11.27E3 l
(
l Tc 99mit.78E 3 13.4SE 3 15.77E 2 l ht 15.07E 2 19.51E2 14.31E3 l
j l Tc 10118.10E 5 18.51E 3 11.05E 3 i ND 11.45E 3 15.85E:
[1. OE1 1 l Ru 103):.79E3 l St 11.07E3 l St 17.03E3 16.62E5 l4.4SE4 l l Ru 105l1.53E0 1 ND l5.53E 1 l ND 11.34E0 l1.59E4 19.95E4 l l Ru 106l1.3dE5 l ND 11.69E4 l ND (1.84E5 l1.43E7 l4.29ES l lAg 110 mil.69I4 11.14E4 19.14E3 I ND l0.1:E4 15.45E6 11.00E5 l
t l Cd 1091 ND 15.eSE5 l2.59E4 l ND 14.96E3 11.05E6 l:.78E4 l l Sb 10415.74E4 17,40E:
12.00E4 11.06E:
I ht 13.24E6 11.64E5 l
l Sb.1:519.84E4 (7.59E:
1:.07E4 19.10E1 i ND 12.3 E6 14.03E4 I
ITe l*5ml6.73E3 12.33E3 19.14E: 11.9:E3 i ND 14.77E3 13.38E4 l ITe 1:7ml:.49E4 15.55E3 l3.0 E3 14.07E3 l6.3sE4 11.4SE6 I?.14E4 1 ITe 127 I:.77E0 19.51E 1 (6.11t 1 11.96E0 17.07E0 11.00Ee 15.6:E4 l ITe 1:9sti.9:Ee (6.s5E3 13,0eE3 16.33E3 15.03E4 11.76E6 11.t:E5 1
- 17. 1:9 19.7?E : 13.50E : 12.3st.: 17.14E :
12.57E 1 1:.93E3 1:.55E4 1
{
ITe 131sti.34E:
15.9:E1 15.0'El 19.77El le.ccE:
12.06E5 13.Osts ITe 131 12.17E : IS.aeE 3 16.59E 3 11.70E 2 15.85E 2 10.05E3 11.33E3 l
[
- 17. 13: 14.81E: 1:.7:E:
1:.63E:
13.17E:
11.77E3 13 7?Es 11.3sts I
!! 130 is.tsE:
11.eete is.eeE3 11.55E6 1:.45E4 i ND 15.11E3 l
l' 11 131 le.31Ee le.s1E4 12.73E4 11.6:E7 17.s5E4 i ND la.SeE3 l
I II 13:
1:.1:E3 te 07E3 11.s5E3 11.9eE5 le.:5E3 i
ND 13.::E3 i
i 11 133 11.e6E4 I:.c3E4 I?.70E3 13.85E6
- 13. sE4 ! ND 15.e5E3 1 I
!! 134 11.1?I3
- 10. lit 3 19.95E:
15.0?I4 13.3cE3 i ND 19.55E: 1 43 -
I
i i
l CAL.AWAY PLANT OTT41TE DOSE CALCULATION
.9ANUAL Rev. 5
[
f TASLE S (Cont'd.)
f PATWAY DOSE TACTORS (R ) TOR RADIONUCLIDES OTHER TMAN NOBLE CASE.S g
i Ir.halation Pathway f
f (arem hr) per (WC1/a')
f l
I l
i Total l
l 1
lNuclidel Bene
! J tver I; Body 1 Thyroid i Kidney l Luna l G! LLY l II 135 i4.9E3
- 18. 7 3 t.3 14 rE3 17.9 E5 11.34E4 l ND 14.44E3 l
[
ICs 134 l6.51E5-11.01E6 (2.25ES l ND l3.03E5 H.21E5 13.35E3 l t
ICs 136 16.51E4 11.71E5
!!.16ES l ND 19.55E4 11.45E4 14.13E3 l f
ICs 137 19.07E5 la.:sts (1.:sE5 l ND 8t.7 E5 11.04E5 13.6 E3 i
{
lCs 133 16.23E:
18.40E:
15.55E: l NP
.2 E:
16.81El 12.70E l
[
.6:E 4 15.77E3 15.77E4 l l
154 139 11.84E0 19,84E 4 15.37E.: I Ila 140 17.40E4 l6.4SE1 l4.33E3 l
,0.11El l1.7'E6 11.0;E5 l 134 141 12.19E 1 11.09E 4 16.36E 3 l 13.47E 5 l:.?:E3 10.75E: l l
O (las 142 15.00E 2 13.6:
E5 I 79E 3 I 12.91E 5 11.64E3 12.74I0 l i
Lo 140 l6.44E:
10.25Z:
17.55El i ND l ND 11.53E5 12.26E3 l f
Ita 14: 11.30to 14.11E 1 11.:9E 1 I a i ND ts.70E3 17.59E4 l lCo 141 13.9:E4 11.95E4 12.9:E3 i N3 IS.55E3 15.44E5 15.66E4 l lCo 143 13.66E: 11.90E2 12.87El l St l8.36El 11.15ES 11.27E5 l lCo 144 16.7?E6 12.!:56 13.61ES l ND 11.17E4 l1.20E7 13.89E5 l
lPr 143 11.65E4 l5.55E3 19.14E l SD l3.00E3 14.33E5 19,73E4 l ipr 144 15.96E-2 11.85E 2 l3.00E 3 i SD 19,77E 3 11.57E3 11.97E:
1 (No.147 11.0$E4 is.73E3 16.81E' l ND la.$1E3 13.:SE3 14.01E4 l lxt 1st 12.7sta 11.01:5 11.25E4 ! ND 1:.05E4 tt.ceE6 16.6:E4 t IV 1s?
12.63E1 19.66t0 le.33E0 1 ND 1 No 14.11E4 19.10E4 l lNp 039 li 66E: 13 34E1 la.35El I ND 19.73E1 15.81E4 16.40E4 )
[
(a) The child age group; Table E 9 Reg. Nide 1.109, Kev.1,1977 and VI Safety Analysis Calculation 88 00 00 T.
I i
I i
49 -
{
1 f
i CALLAYAY PLANT OTTS!TE DOSE CALCULATION MANUAL Rev. 3 TABLE 5 (Cent'd.)
l a
PATWAY 003E TACTOR $ (R ) ICR RADIONUCLIDES OTKER THAN N08LE GA5Es g
Ground Plane Pathway
[
(M ares /yr) per (VCi/sec) l 8
l Nuclide Total Body Skin L
Na 24 1.19E7 1.39E7 Cr 51 4.65E6 5.51E6 l
!!n 54 1.39E9 1.6!E9 1.07E6 i
Mn 56 9s03E5 Te 59 2.7:ES 3.00E8 l
- I Co 58 3.79ES e.44ES I
Co 60 2.15E10 2.53E10 1
Ni 65 2.97E5 J.45E5 l
i Cu 64 6.07E5 6.4815 l
- n 65 7.47ES 4.59ES i
I Br 83 4.37E3 7.0$E3 l
Br 54 2.03E5 0.36E5 J
Rb.3 8.99E6 1.03E7 l
I j
'b 88 3.31E4 3.78E4 l
Rb $9 1.23E5 1.48E5
$r 89
.16E4
- .51E4 I
$r 91 2.15E6
.51En i
Sr 9 7.77E5 S.63E5 Y 90 4.49E3 5.31E3 Y 91m 1.0 E5 1.16E3
[
2 i
1 Y 91 1.07E6 1.:1E6 t
Y 9:
1.50E5
. lee 5 l
Y 93 1.83E5 0.51E5 l
]
lr 95 2.45Es
. SEES j
7.r 97 2.96E6 3.44E6 lc j
t i
Nb 95 1.37ES 1.61El
'!o 99 3.95E6 4.6:E6 Tc 99m 1.SaE5
.11E5 l
Tc 101 2.04E4
. 6E4 1
Ra 103 1.0$ES 1.:eES i
l 1
I i
i [
4 t
I
CALLAVAY PLANT OTTSITE COSE CALCULATION MANUAL Rev. 5 TABLE 5 (Cont'd.)
l PATXVAY DOSE TACTORS (R ) TOR RADIONUCLICES OTHER TRAN NCILE GASES' g
Ground Plane Pathway l
( 118 ares /yr) per (9Ct/:ec)
Nuclide Tots 1 fedy Sktn Ru 105 6.36E5 7.21ES Ru 106
- 4. :E8 5.07E8 Ad*110m 3.44E9 4.01E9 To 1 5m 1.55E6 2.13E6 Te.1 7m 9.16E4 1.0$E5 Te+127 2.98E3 3.28E4 Te.129m 1.98E7 2.31E7 Te 109 2.i' 3.10E4 Te.131a 4.( >
9.46E6 To.131
. 9. r.
3.45E4 Te 13:
4.23E6 4.9tE6
! 130 5.51E6 6.69E6 I 131 1.7:E7 2.09E7
! 13:
1.23E6 1.45E6
! 133 0.45E6
- .98E6 1 134 4.47E5 5.30E5 1 135
.51E6 2.93E6 Cs+134 6.86E9 8.00E9 Cs 13e 1.53E6 1.74E4 Cs.137 1.03E10 1.20E10 l
Cs 138 3.59E5 4.1CES 54 139 1.06E5 1.19E5 34 140 2.05E7
.35E7 14 141 4.15E4 4.73E4 34 14:
4.44E4 5.06E4 L4 140 1.9:E7
.18E7 L4 14:
7.40E5 4.69E5 Ce+141 1.37E7 1.54E7 Ce 143 0.31Es 0.e2E6 Ce+144 6.9ett 8.04E7 51 -
'U:
CALLAWAY PLANT OFFSITE DOSE CALCULATION HANUAI.
Rev. 5
(_)
x TABLE 5 (Cont'd.)
PATHVAY D05E FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Ground Plane Pathway 8
(M mrem /yr) per (uCi/sec)
Nuclide Total Body Skin Pr-144 1.84E3 2.11E3 Nd 147 8.41E6 1.01E7 W-187 2.36E6 2.74E6
.ip 239 1;71E6 1.98E6 (a) Data from Reg. Guide 1.109, Appendix E.
O
(.
f
CALLAWAY PLAST OFFSITE DOSE CALCULATION
?!ANUAL Rav. 5 kh TABLE 5 (Cont'd.)
PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" 1
!! EAT PATHVAY 8
(m mrem /yr) per (uCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone l Liver l Body l Thyroid i Kidney l Lung l GI-LLI l lH3 l ND l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l l Be-7 l7.37E3 11.26E4 IS.06E3 l ND l1.23E4 l ND l7.00E5 l
l'.67E7 l
l C-14 l3.83E8 l7.67E7
-l7.67E7 l7.67E7 l7.67E7 17.67E7
/
l Na-24 l1.78E-3 l1.78E-3 l1.78E-3 l1.78E 3 l1.78E-3 l1.78E-3 l1.78E-3 l l P 32 17.41E9 l3.47E8 12.86E8 i Nn l ND l ND l2.05ES l
l Cr-51 l ND l
ND l8.79E3 l4.88E3 l1.33E3 l8.91E3 14.66ES l
l !!n-54 l ND 18.01E6 l2.13E6 i ND l2.25E6 1 ND 16.72E6 l
l !!n-56 l ND l
0 l
0 l ND l
0 l ND l
0 l
l Fe-55 14.57E8 12.42E8 l7.51E7 j ND l ND l1.37E8 l4.49E7 l
l Fo-59 13.76E8 l6.09E8 l3.03E8 l ND l
ND l1.76E8 l6.34E8 l l Co-57 l ND 15.92E6 l1.20E7 l ND l ND l ND 14.85E7 l
l Co-58 l ND l1.64E7 15.02E7 l ND l ND l ND 19.58E7 l
l Co-60 l ND l6.93E7 l2.04E8 i SD l ND l ND l3.84E8 l l Ni-63 l2.91E10 l1.56E9 l9.91E8 l ND l ND l ND l1.05E8 l
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 l1.79E-7 l ND l7.17E-7 i SD l1.39E-5 l l Zn-65 l3.75E8 ll.00E9 l6.22E8 l ND l6.30E8 l ND l1.76E8 l
l Zn-69 l 0
l 0
l 0
l ND l
0 1 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 Be 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 15.82ES l3.58E8 l ND l ND l
ND l3.74E7 l
l 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 l4.82E8 l ND ll.38E7 l ND 1 ND l ND l1.86E7 l
l Sr-90 l1.04E10 l NO
[2.64E9 l ND l ND l ND l1.40E3 l
l Sr 91 12.40E-10l ND l
0 l
ND l ND l ND l5.29E 10l i
l l Sr-92 l 0
1 ND l
0 l
ND l ND l ND l
0 l
l Y 90 l1.71E2 l ND l4.59E0 l
ND l ND l
ND l4.88E5 l
0 -
CALLAVAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5
[_h v
TABLE 5 (Cont'd.)
PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
MEAT PATINAY 8
(m mrem /yr) per (uCi/sec) l l
l 1 Total l
l l
l l
lNuclidel Bone i
Liver !
Body 1 Thyroid l Kidney l Lung l GI-LLI 1 l Y-91m l 0
l ND l
0 1 ND l ND l ST l
0 l
l Y-91 l1. SOC 6 l ND l4.S2E4 l ND l ND l ND l2.40ES l
l Y-92 l 0
l ND l
0, l ND l ND
.I ND.
l 0
l l Y-93 l
0 l ND l
0 l ND l ND l ND l1.55E-7 l l Zr-95 l2.66E6 l5.85E5 l5.21ES l ND l8.38E5 l ND l6.11E8 l
l Zr-97 l3.20E-5 14.63E-6 12.73E-6 l ND l6.65E-6 i ND l7.02E-1 l I Nb-95 l3.09E6 l1.20E6 18.61E5 l ND l1.13E6 l ND (2.23E9 l
l Mo-99 l ND l1.15ES 12.84E4 l ND 12.46E5 l ND l9.51E4 l
l Tc-99ml 0
1 0
l 0
l ND l
0 1
0 l
0 l
l Tc-101l 0
l 0
l 0
l ND l
0 1
0 l
0 l
J Ru-103l1.55E8 l ND 15.96E7 l ND l3.90E8 l ND l4.01E9 l
l Ru-105l 0
l ND l
0 l ND l
0 l
ND l
0 l
l Ru-106l4.44E9 l ND 15.54E8 l ND l5.99E9 l
ND l6.90E10 l lAg-110ml8.40E6 l5.67E6 l4.53E6 l ND l1.06E7 l
ND l6.75E8 l lCd 109 l ND l1.90E6 l3.83E4 l ND l1.70E6 l ND l6.18E6 l lSb-124 l2.92E7 l3.79ES l1.02E7 16.45E4 l ND l1.62E7 11.83E8 l
lSb 125 l2.85E7 l2.20E5 15.97E6 12.64E4 l ND 11.59E7 l6.80E7 l
lTe-125ml5.69F8 l1.54E8 l7.59E7 11.60E8 l ND l ND l5.49E8 l
ITe-127ml1.77E9 l4.78E8 l2.11E8 14.24E8 l5.06E9 l ND l1.44E9 l
lTe-127 14.11E 10l1.11E-10 l 0
12.85E-10 l1.17E-9 l ND
[1.61E-8 l lTe-129 mil.79E9 14.99E8 12.77E8 15.76ES 15.25E9 l
ND l0.18E9 l
lTe-129 i 0
l 0
l 0
l 0
l 0
l ND l
0 l
lTe-131ml7.00E2 12.42E2 12.58E2 14.96E2 l2.34E3 l ND 19.82E3 l
(Te-131 l 0
l 0
l 0
l 0
1 0
l ND l
0 l
lTe-132 l2.09E6 l9.26ES 11.12E6 l1.35E6 l8.60E6 l ND l9.33E6 l
lI-130 l3.04E 6 l6.13E 6 13.16E-6 16.76E-4 l9.17E-6 l ND l2.87E-6 l 11-131
!!.64E7 l1.ce27 19.46E6 l5.50E9 l2.73E7 I ND l1.4636 l
lI-132 l
0 l
0 l
0 1
0 l
0 l
ND l
0 l
lI-133 16.16E-1 l7.61E-1 l2.88E-1 l1.41E2 l1.27E0 l
ND l3.07E 1 l l!-134 l 0
l 0
l 0
l 0
l 0
l ND l
0 i
O 54
CALLAVAY PLAST OFFSITE DOSE CALCULATION MANUAL Rev. 5
('_)'
\\J TABLE 5 (Cont'd.)
PATHVAY DOSE FACTORS (k ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
MEAT PATHWAY (m' mrem /yr) per (pC1/sec)
~
l l
l l Total l
l l
l l
lNuclidel Bone !
Liver l
Bodv l Thyroid ! Kidney l Lung l GI-LLI l lI-135 l
0 1
0 l
0 l
0 l
0 l ND l
0 l
lCs-134 19.20ES {1.51E9 l3.19ES l ND l4.69ES l1.68E8 18.16E6 1
jCs-136 l1.61E7 14.43E7 l2.86E7 i SD l2.36E7.l3.51E6 11.56E6 l
1 lCs-137 l1.33E9 l1.28E9 l1.88E8 l
ND l4.16E8 11.30E8 17.99E6 l lCs-138 l 0
l 0
1 0
1 ND l
0 l
0 l
O
\\
lBa-139 l 0
l 0
l 0
l ND l
0 1
0 l
0 l
'Ba-140 l4.38E7 l3.84E4 l2.56E6 l SD ll.25E4 l2.29E4 12.22E7 l
18a-141 1 0
1 0
l 0
1 ND l
0 1
0 l
0 l
l3a-142 l 0
1 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 l5.69E-2 l1.99L-2 l6.70E-3 l ND
! ND l ND l5.54E2 l
lLa-142 l 0
l 0
l 0
l ND l ND l ND l
0 l
lCe-141 l2.22E4 l1.1184 l1.64E3 l
ND l4.85E3 i ND l1.38E7 l
lCe-143 13.17E-2 l1.72E1 12.49E-3 l ND 17.21E-3 l ND 12.52E2 l
l lCe-144 l2.32E6 l7.26E5 11.24E5 l
ND l4.02E5 l ND l1.89E8 l
lPr 143 l3.35E4 l1.00E4 l1.66E3 l
ND l5.44E3 l ND 13.61E7 l
lPr-144 l 0
0 l
9 l ND l
0 l
ND l
0 l
lNd-147 l1.17E4 l9.50E3 l7.35E2 l
ND l5.21E3 l ND ll.50E7 l
lHf-181 la.76E6 l1.73E7 12.15E6 l
ND l3.52E6 l ST 16.40E9 l
(
lV-187 l3.35E-2 l1.98E-2 l8.91E-3 l ND l ND l ND l2.79E0 l
lNp-239 l4.20E-1 13.02E 2 l2.12E-2 l ND l8.72E-2 l ND l2.23E3 l
l (a) The child age group; data from Reg. Guide 1.109, Appendix E, and CE Safety Analysis Calculation 88-002-00 F.
O V
55 -
CALLAVAY PLAST OFFSITE DOSE CALCULATION MANUAL Rev. 5
/m)
~'v' TABLE 5 (Cent'd.)
a PATHWAY DOSE FACTORS (R ) EOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Cow-Milk Pathway 8
(m mrem /yr) per (pCi/sec) l l
l l Total i
l l
l l
lNuciidel Bone l Liver l Body i Thyroid l Kidney I Lung ! GI-LLI l l H-3 l ND l1.57E3 l1.57E3 11.57E3 11.57E3 l1.57E3 l1.57E3 l l Be-7 l7.50E3 11.27E4 ls.19E3 l ND l1.25E4 l ND l7.12E5 l l C-14 l1.19E9 12.39E8 l2.39E8 l2.39E8 12.39E8 12.39E8 12.39E8 l l Na-24 l8.89E6 l8.89Eo l8.89E6 18.89E6 18.89E6 l8.89E6 l8.89E6 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 15.40E6 l l Mn 54 l ND l 2.10F.7 l5.59E6 l ND l5.88E6 l ND l1.76E7 l
l Mn*56 l ND l1.29E-2 l2.90E-3 l ND 11.56E-2 l ND l1.86E0 l l Fe-55 11.12E8 15.93E7 l1.84E7 l
ND l
d'D 13.35E7 11.10E7 l l Fe-59 11.20E8 l1.94E8 l9.69E7 l ND l ND 15.64E7 l2.02E8 l
l Co-57 l ND l3.34E6 l7.76E6 l ND l ND l ND 13.15E7 l
l Co-58 l ND ll 21E7 l3.71E7 l ND l ND l ND l7.07E7 l
l Co-60 l ND l4.32E7 l1.27E8 l
ND l ND l ND l2.39ES l l Ni-63 l2.96E10 l1.59E9 l1.01E9 l
ND l ND l ND l1.07E8 I l Ni 65 l1.66E0 l1.56E-1 l9.01E-2 i SD l ND l ND l1.91El l l Cu-64 l ND l7.46E4 l4.51E4 l ND l1.80E5 l ST 13.50E6 l l Zn 65 l4.13E9 l1.10E10 l6.85E9 l
ND l6.94E9 I ND l1.93E9 l
l Zn 69 l 0
1 0
l 0
l ND l
0 ND l1.12E-9 l l Br 82 l ND l ND l1.15E8 l
ND l ND l ht l ND l
l Be 83 l ND l ND l ND l ND l ND I 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 l8.80E9 l5.41E9 l
ND l ND l ND 15.66E8 l
l Rb 83 i 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 16.62E9 l ND (1.89E8 l
ND l ND l ND l2.56E8 l
l Sr 90 11.12E11 l ND 12.83E10 l ND l
ND l ND ll.51E9 l
l Sr 91 11.30E5 i ND 14.92E3 l
ND l
ND l ND l2.83E5 l
l Sr 92 l2.1SE0 l ND 18.75E-2 l ND l
ND l ND l4.13E1 l
l Y 90 l3.22E2 l ND l8.e2E0 l ND l ND l ND l9.17E5 l
C\\
U i
CALLAWAY PLANT OFFSITE DQSE CALCULATION MANUAL Rev. 5 O
C/
TABLE 5 (Cont'd.)
PAT 1NAl* DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" g
Grass-Cow-Milk Pathway 8
(m mrem /yr) per (UCi/sec) l l
l 1 Total l
1 l
l l
lNuclidel Bone l
'iver 1
3edy l Thyroid l Kidney l Lung l GI-LLI l l Y-91m l 0
l ND l
0 l ND l ND l
F.D l
0 l
l Y-91 l3.90E4 l
ND l1.04E3 l ND l ND l ND l5.00E6 l l Y-92 l2.5:2-4 l ND l7.24E-6 l ND l.ND l ND
.l7.31E0 l
l Y 93 11.0$E0 l ND l2.90E-2 l ND l ND l ND l1.57E4 l
l Zr-95 13.83E3 18.42E2 l7.50E2 l ND l1.21E3 l ND l8.79E5 l
l Zr-97 l1.92E0 12.77E-1 l1.64E-1 l ND 13.98E-1 l ND l4.20E4 l l Sb-95 l3.18E5 11.24E5 l8.84E4 l ND l1.16E5 l ND l2.29E8 l
l Mo-99 l ND l8.14E7 12.01E7 i ND l1.74E8 l ND l6.73E7 l
l Tc-99 mil.32E1 12.59El l4.29E: } ND l3.76E2 11.30E1 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 l1.395-3 l ND 13.36E-2 l ND 12.49E0 l
l Ru-106l9.24La l ND l1.15E4 l ND l1.25E5 l
ND (1.44E6 l
lAg-110ml2.09ES l1.41L8 l1.13ES l ND l2.63E8 l ND l1.68E10 l lCd-109 l ND l3.86E6 11.79ES l
ND l3.45E6 l ND l1.25E7 l
lSb-104 11.08E8 l1.41E6 13.81E7 12.40E5 l ND l6.03E7 l6.79ES l
lSb-125 l3.70E7 16.71E5 l1.83E7 l8.06E4 l ND l4.85E7 l2.08E8 l
lTe 125ml7.38E7 l'.00E7 19.84E6 12.07E7 l ND l ND l7.12E7 l
[Te-127ml0.08E8 l5.60E7 l2.47E7 l4.97E7 l5.93E8 l ND l1.68E8 l
lTo-127 l3.05E3 l8.00E0 l6.54E 12.11E3 18.67E3 l NT l1.19ES l
lTe 129ml2.71E8 17.57E7 l4.01E7 18.74E7 l7.96E8 l ND l3.31ES l
lTe 129 l 0
l 0
l 0
l 0
12.90E 9 l ND l6.17E 9 l lTe 131ml1.60E6 l5.53E5 15.89E5 11.14E6 15.35E6 l ND l2.24E7 l
lTe 131 l 0
1 0
1 0
1 0
1 0
l ND l
0 l
lTe-132 11.02E7 l4.52E6 l5.46E6 16.5BE6 l4.20E7 l ND 14.55E7 l
lI-130 11.73E6 l3.49E6 l1.80E6 l3.84E8 l5.22E6 l ND l1.63E6 l
lI-131 ll.30E9 11.31E9 l7.45ES l4.33E11 l2.15E9 l ND l1.17E8 l
11 132 l6.02E-1 l1.11E0 l5.0$E 1 15.13E1 l1.69E0 l ND l1.30E0 l
II-133 l1.74E7 12.15E7 l8.13E6 13.99E9 13.58E7 l ND 18.66E6 l
lI-134 1
0 l
0 l
0 l
0 1
0 l ND l
0 l
0 CALLAWAY PLAST OFFSITE DOSE CALCULATION MANUAL Rev. 5 b
TABLE 5 (Cont'd.)
PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES
- g Grass-Cow.5111k Pathway 8
(m mrem /yr) per (UCi/sec) l 1
l Total l
I l
1 1
JNuclidel Bone l Liver I Body i Thyroid l Kidney 1 Lunt i GI-LLI I lI-135 15.40E4 l9.72E4 l4.60E4 l8.61E6 l1.49E5 l ND 17.40E4 l lCs-134 l2.26E10 l3.7 E10 17.84E9 l ND 11.15E10 l4.13E9 l2.00E8 l lCs-136 l4.01E9 12.77E9 11.79E9 l ND l1.48E9-l2.20E6 l9.74E7 l,
lCs 137 l3.22E10 l3.09E10 l4.56E9 l ND l1.01E10 l3.62E9 l1.93E8 l lCs-138 1 0
l 0
1 0
l ND 1
0 1
0 l
0 l
JBa-139 l1.89E 7 l 0
15.48E-9 l ND l
0 l
0 l1.09E-3 l lBa-140 l1.17E8 l1.03E5 l6.84E6 l ND l3.34E4 l6.12E4 15.93E7 l
lBa-141 l 0
1 0
l 0
1 ND i
0 1
0 1
0 l
lBa-142 l 0
1 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 11.95El l6.80E0 12.29E0 l ND l ND l ND l1.90E5 l
lLa-142 l 0
l 0
l 0
l ND l ND l ND 12.90E-6 l lCo-141 l2.19E4 l1.09E4 11.62E3 l ND l4.78E3 l ND l1.36E7 l
lCe-143 ll.87E2 l1.02E5 l1.47El l ND 14.26El l
ND l1.49E6 l lCe-144 l1.62E6 15.09ES l8.66E4 l ND l2.82E5 l ND 11.33E8 l
lPr-143 l7.19E2 12.16E2 l3.57El l
ND l1.17E2 l
ND l7.75ES l
lPr-144 l 0
1 0
l 0
l ND l
0 l ST l
0 l
lNd-147 l4.45E2 l3.61E2 l2.79El l
ND ll.98E2 l ND j$.71ES l
lHf 181 16.4aE2 12.35E3 l2.90E2 l ND l4.75E2 l St l8.65ES l
(V-187 l2.91E4 11.73E4 l7.73E3 l ND l ND l ND l2.42E6 l lSp-239 l1.7 El l1.23E0 18.68E 1 l ND l3.57E0 l ND l9.14E4 l (a) The child age ;;roup; data from Reg. Guide 1.109, Appendi.x E and UE Safety Analysis Calculation 88 002 00-F.
O 58 -
CALLAVAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev.
- 7 TABLE 5 (Contu.)
PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass Goat-Milk Pathway 8
(m mrem /yr) per (vC1/sec) l l
1 i Total I
I l
1 I
lNuclidel Bone I
Liver l
Body
- Thyroid i Kidney i Lung l GI-LLI l l H-3 l ND l3.20E3 l3.20E3 l3.20E3 13.20E3 l3.20E3 l3.20E3 l l C-14 l1.19E9 l2.39ES l0.39ES 12.39ES l2.39ES l2.39ES J2.39ES l l Na 24 l1.07E6 11.07E6 l1.07E6 l 1,0 7 E 5-11.07E6 l1.07E6 l1.07E6 l l P-32 19.33E10 14.37E9 l3.60E9 l ND l ND l ND l2.58E9 l
l Cr 51 l ND l
ND l1.23E4 16.78E3 l1.87E3 l1.25E4 l6.48E5 l
l Mn-54 l ND (2.52E6 l6.70E5 l ND 17.06E5 l ND l2.11E6 l l Mn-56 l ND l1.54E-3 l3.49E-4 l ND l1.87E-3 l ND 12.24E-1 l l Fe-55 11.45E6 l7.71E5 l2.39ES l ND l ND 14.36E3 11.43E5 l
l Fe-59 11.56E6 l2.53E6 l1.26E6 l ND l ND 17.33E5 l2.63E6 l l Co 58 l ND l1.45E6 14.45E6 l ND l ND l ND l8.JE6 l l Co-60 l ND l5.18E6 l1.53E7 l ND l ND l ND l2.87E7 l
l Ni-63 13.56E9 l1.90E8 l1.21ES l ND l ND l ND 11.28E7 l
[ Ni-65 11.99E-1 11.87E-2 l1.09E-2 l ND l ST l ND l2.29E0 l l Cu-64 l ND 18.31E3 l5.02E3 l ND l2.01E4 l ST l3.90E5 l
l Zn 65 14.96ES l1.32E9 l8.22E8 l ND l8.33E8 l ND l2.32E8 l l Zn-69 l 0
1 0
l 0
l ND l
0 l ST l1.35E-101 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 ST l
l Br-85 l ND l ND l
ND l ND l ND l ND l ND l
l Rb 36 l ND 11.06E9 l6.50E8 l ND l
NE l ND l6.30E7 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 SD l ND l
0 l
l Sr 89 l1.39E10 l ND l3.97ES l ND l
ND l ST 15.38E8 l
l Sr-90 12.35E11 l ND 15.95E10 l ND l
ND l ND 13.16E9 l
l Sr 91 l2.74E5 l
ND l1.03E4 l ND l ND l
NC l6.04E5 l.
CALLAk'AY PLANT OF5' SITE DOSE CALCULATION MANUAL Rev. 5 iV TABLE 5 (Contd.)
a PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Goat-Milk Pathway 8
(m mrem /yr) per (pCi/sec)
~
l l
i l Total I
l l
l l
lNuclidal Bone l
Liver I Bodv i Thyroid l *:idney l Lung l GI-LLI l l Sr 92 l4.58E0 l
ND l1.84E-1 1 ND l ND l ND l8.68E1 l l Y-90 l3.87El l ND ll.03E0 l ND l ND l ND l1.10E5 l
l Y-91m;l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-91 l4.68E3 l ND ll.25E2 l ND l ND l ND l6.24E-3 l l Y-92 13.04E-3 l ND l8.69E-7 l ND l ND l ND 18.77E-1 l l Y-93 l1.27E-1 l ND 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 53 11.0$ES l
l 2r-97 l2.30E-1 13.33E-2 l1.96E-2 l ND l4 78E-2 l ND 15.04E3 l
l Sb 95 l3.81E4 l1.48E4 l1.06E4 l ND l1.39E4 l ND 12.75E7 l
l Mo-99 l ND l9.76E6 12.42E6 l ND l2.09E7 l ND l8.08E6 l
l Tc-99 mil.59EO l3.11En 15.15El l ND l4.52E1 l1.58E0 11.77E3 l
} Tc 1011 0
1 0
l 0
l ND l
0 l
0 l
0 l
l Ru-103l3.14E2 l ND l1.98E2 l ND ll.29E3 l ND l1.33E4 l l Ru-105l4.58E-4 l ND ll.66E-4 l ND l4.03E-3 l ND l2.99E-1 l l Ru 106l1.11E4 l
ND l1.38E3 l ND 11.50E4 l ND l1.72E5 l
lAg 110ml2.51E7 l1.69E7 l1.35E7 l ND l3.15E7 l ND l2.01E9 l
lTe-125ml8.85E6 l2.40E6 l1.18E6 l2.48E6 l ND l ND 18.54E6 l
lTe-127ml2.50E7 l6.72E6 l2.96E6 15.97E6 l7.12E7 l ND l2.02E7 l
lTe 127 l3.66E2 l9.86El l7.85El l2.53E2 l1,04E3 i ND l1.43E4 l lTe-129ml3.25E7 19.09E6 l5.05E6 11.05E7 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 l Te-131m l 1. 92E5 l6.64E4 l7.07E4 l1.37E5 l6.43E5
! ND l2.69E6 l
lTe-131 l 0
l 0
l 0
1 0
l 0
l ND l
0 l
lTe-132 l1.23E6 15.42E5
{6.53E5 17.90E5 15.04E6
! ND l5.46E6 l
lI-130 l2.07E6 14.19E6 l2.16E6 ja.61ES l6.26E6 l ND l1.96E6 1
0 60
CALLAVAY PLAST OFFSITE DOSE CALCULATION MAN 1?AL Rev. 5 c()
R.
TABLE 5 (Contd.)
a PATINAY DCSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Goat-Milk Pathway 8
(m mrem /yr) per (9Ci/sec) l l
l 1 Total l
l l
1 l
lNuclidel Bone f Liver l
Body l Thyroid i Kidney i Long l GI-LLI l lI-131 l1.56E9 l 1. 5 7i.9 18.94E8 l5.20E11 l2.58E9 l ND ll.40E8 l lI-132 l7.22E 1 11.33E0 l6.10E-1 16.15El l2.03E0 l ND l1.56E0 l lI-133 l2,09E7 l2.58E7 l9.76E6 l4.79E9 14.30E7 l ND l1.04E7 l 11-134 l
0 1
0 l
0 l
0 l
0 l ND l
0 l
lI-135 l6.48E4 11.17E5 15.52E4 l1.03E7 l1.79ES l ND l8.88E4 l lCs-134 l6.79E10 l1.11E11 l2.35E10 l ND l3.45E10 l1.24'd10 l6.01E8 l lCs-136 l3.03E9 18.32E9 l5.38E9 l ND l4.43E9 16.61E8 l2.92E8 l lCs-137 l9.67E10 19.26E10 l1.37E10 l ND l3.02E10 l1.09E10 15.80E8 l lCs 138 l 0
l 0
1 0
1 ND l
0 l
0 l
0 l
p lBa-139 l2.27E 8 l 0
1 0
l ND l
0 l
0 11.31E-6 l lBa-140 11.41E7 l1.23E4 l8.20E5 l ND l4.01E3 l7.34E3 17.12E6 l lBa 141 1 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
1 0
l ND l
0 l
0 l
0 l
lLa-140 l2.34E0 l8.17E-1 12.75E-1 l ND l
ND l ND l2.28E4 l lLa-142 l 0
1 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 12.25El (1.22E4 l1.77E0 l ND l5.12E0 l ND l1.79E5 l lCe 144 11.95E5 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 19.30E4 l lPr 144 l 0
l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 l5.34E1 l4.33E1 13.35E0 l ND l2.37El l ND l6.85E4 l lW-187 l3.49E3 j.:. 07 E 3 19.27E2 l ND l
ND l ND l2.90E5 l
lSp-239 l2.06E0 l1.48E 1 l1.04E 1 l ND l4.28E-1 1 ND l1.10E4 l (a) The child age group; data from Reg. Guide 1.109, Appendix E.
O 61 -
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 (V
s TABLE 5 (Contd.)
8 PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 8
(m mrom/yr) per (pCi/sec) l l
l 1 Total I
l l
l 1
l hyroid l K'idney l Lung l GI
- .',I l
lNuclidal Bone !
Liver l Body 4
l H-3 l ND 14.01E3 l4.01E3 la.01E3 14.01E3 l4.01E3 l4.01E3 l l Be-7 13.38E5 15.76E5 13.70E5 l ND 15.64E5 l ND 13.21E7 l
l C-14 l$,.89E8 l1.78E8 11.78E8 11.78E8 l1.78E8 l1.78E8 l1.78E8 l
l Na 24 l3.75E5 l3.75E5 13.75E5 13.75E5 13.75E5 l3.75E5 13.75E5 l
l P-32 l3.37E9 l1.57E8 l1.30E8 l ND I ND l ND l9.30E7 l
l Cr-51 l ND l ND 11.17E5 l6.50E4 l1.78E4 l1.19ES 16.21E6 l
l Mn-54 l ND 16.65E8 l1.77E8 l
ND ll.86E8 l ND l5.38E8 l
l Mn-56 l ND l1.88E1 l4.24E0 l ND 12.27El l ND l2.72E3 l
l Fe-55 18.01EU 14.2SES l1.30E8 l ND l ND l2.40E8 17.8,E7 l
q l Fe-59 13.97E8 16.43E8 l3.20E8 l ND l ND l1.86E8 l6.69E8 l
l Co 57 l ND l2.98E7 16.04E7 l ND l ND l ND 12.45E8 l
l Co-58 l ND l6.44E7 l1.97E8 l ND l ND l ND 13.76E8 l
l Co-60 l ND l3.78E8 11.10E9 l ND l ND l ND l2.10E9 l Ni 63 l3.a'~ 40 l2.11E9 11.34E9 l ND l ND l ND l1.42E8 i
l Ni 65 11.05E2 19.89E0 13.77EO l ND l ND l ND l1.21E3 l
l Cu-64 l ND l1.10E4 l6.64E3 l
ND l2.66E4 l ND 15.16E5 l
l En-65 18.12E8 l2.16E9 l1.35E9 i ND l1.36E9 l ND l3.80E8 l
1 En 69 l1.09E-3 11.57E-3 11.45E-6 l ND 19.52E 6 l ND l9.11E-4 l l 3r 82 l ND l ND l2.04E6 l ND l ND l ND l
ND l 3r-83 l ND l ND 15.37E0 l ND l ND l
ND l
0 l
l Br $a l ND l
ND l
0 l
ND l ND l
ND l
0 l
l Br 85 l ND l ND l
0 l
ND l ND l
ND l
0 l
l Rb 86 l ND 14.58E8 12.82E8 l
ND l ND l
ND l2.94E7 l
l Rb 88 l ND l
0 l
0 l ND l ND l ND l
0 l
l Rb 89 l ND l
0 l
0 l
ND l ND l
ND l
0 l
l Sr-89 l3.59E10 l SD l1.03E9 l
ND l ND l ND l1.39E9 l
l Sr 90 l1.24E12 l ND 13.15E11 l ND l ND l ND l1.67E10 l l Sr-91 l5.0aE5 l ND ll.98E4 l
ND l ND l ND ll.16E6 l
l Sr 92 ;7.0$E2 i ND 12.92E1 l
ND l ND l
ND l1.38E4 l
l Y 90 12.31E4 l ND l6.18E2 l
ND l ND l ND l6.57E7 l
62 -
CALLAk'AY PLAST OFFSITE 00SE CALC 11.ATION lm MANUAL Rev. 5 b)
TABLEl Nontd.)
PATINAY DOSE FACTORS (R ) FOR RADNCMDES OUER UM NOBM GASES" g
Vegetation Pathway 8
(m mrem /yr) per (lac 1/sec) l l
l l Total l
l l
l 1
lNuclidel Bene l
Liver Body i Thyr:4d i Kidney l Lung l GI-LLI i l
l Y-91m l8.87E-9 l ND l3,23E 101 ND l ND l ND ll.74E-5 l l Y-91 11.36E7 l ND l4.99ES l ND l ND i ND 10.48E9 i
l Y-92 lk.58E0 1 ND
[4.53E-2 l ND l ND l ND l 4'. 58E4 l l Y-93 l3.01E2 l ND 18.25E0 l ND i L l ND
[4.48E6 l
l Zr-95 l3.86E6 18.45ES 17.53E5 l ND l1.21E6 l ND
[8.84E8 l l Zr-97 15.70E2 l8.24E1 l4.86El i ND l1.18E2 l ND l1.25E7 l
l Nb-95 l'. 10E5 l1.59ES 11.14E5 8 ND ll.50E5 l ND l2.95E8 l j Mo-99 l ND l7.71E6 l1.91E6 l ND l1.65E7 l ND l6.38E6 l
l Tc-99ml4.71E0 l9.24E0 11.53E2 l ND ll.34E2 l4.69E0 15.26E3 l
l Tc-101l 0
l 0
1 0
l ND l
0 l
0 l
0 l
b l Ru 10311.54E7 l ND l5.90E6 l ND l3.87E7 l ND i3.97E8 l l Ru 105l9.16El l ND l3.30E1 l ND l8.05E2 l ND 15.98E4 l
l Ru-106l7. 5ES l ND 19.30E7 l ND 11.01E9 l ND 11.16E10 l lAg-110ml3.::E7 l2.17E7 il.74E7 l ND la.05E7 l ND (2.58E9 l
lCd-109 l ND l0.45E8 11.13E7 l ND l2.18E8 l ND 17.94E8 l
lSb-124 l3.52E8 l4.56E6 l1.23E8 17.76E5 l ND l1.95ES l2.00E9 l
lSb-125 l4.99E8 l3.85E6 l1.05ES I4.6055 l ND l0.78E8
!1.19E9 l
lTe-125ml3.51E8 l9.50E7 14.67E7 l9.84E7 l ND l ND l3.38E8 l
lTe-127 mil.32E9 l3.56E8 l1.57E8 l3.16E8 13.77E9 l ND ll.07E9 l
lTe-107 l1.00E4 l0.69E3 12.14E3 16.91E3 12.84E4 l ND 13.90E5 l
lTe 129ml8.38E8 l0.34E8 11.30E8 l2.70E6 10.46E9 l ND ll.0 E9 l
lTe-129 l1.16E 3 l3.23E-4 l2.75E 4 18.26E 4 l3.39E-3 l ND l7.20E 2 l lTe-131ml1.54E6 l5.33E5 l5.68E5 l1.10E6 15.16E6 l ND l2.16E, lTe-131 l 0
l 0
l 0
l 0
1 0
l ND l
0 l
lTe-132 l6.98E6 l3.09E6 l3.73E6 ja.5056 l2.87E7 l ND l3.11E7 l
lI-130 l6.16E5 l1,04E6 l6.38E5 l1.37E8 l1.86E6 l
ND 15.79E5 l
l lI-131 l1. 3E8 l1.44E8 18.17E7 14.75E10 10.36ES l ND l1.:SE7 l
lI-130 l3.58E1 11.58E2 l7.03E1 l7.31E3 12.41E2 l ND l1.86E2 l
li-133 l3.56E6 l4.40E6 l1.67E6 18.18E8 (7.34E6 l
ND ll.77E6 l
lI-134 11.55E 4 12.SSE-4 l1.3:E 4 16.62E 3 la.40E 4 l ND l1.91E-4 1 lI-135 l6.6:E4 11.13E5 l5.33E4 l9.97E6 11.70E5 l
ND 18.53E4 l
)
s 63
CALLAVAY PLA.NT OFFSITE DOSE CALCULATIOV MANUAL Rev. 5
,s TABII $ (Contd. )
a PATINAY DOSE FACTORS (R ) F.OR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 8
(m mrem /yr) per (uCi/sec)
~
l l
l l Total l
l l
l l
lNuclidel Bone l
Liver l
Body l Thyroid l Kidney l Lung l GI-LLI l lCs-134 l1.60E10 l2.63E10 l5.55E9 l ND l8.15E9 l2.93E9 l1.42E8 l lCs-136 18.17E7 l2.25ES l1.45ES l ND 11.20E8 l1.78T7 17.90E6 l lCs-137 l2.39E10 l2.29E10 l3.38E9 l ND 17.46E9 12.68E9 11.43E8.l lCs-138 l 0
{
0 l
0 l ND l
0 l
0 l
0 l
lBa-139 14.80E-2 l2.56E-5 l1.39E-3 l ND 12.24E-5 l1.51E-5 12.77E0 l lBa-140 l2.77ES 12.42E5 11.62E7 l ND l7.89E4 l1.45E5 11.40E8 l lBa-141 l 0
1 0
l 0
l ND l
0 l
0 1
0 l
lBa-142 1 0
l 0
1 0
l ST l
0 l
0 l
0 l
lLa-140 l3.25E3 l1.14E3 l3.83E2 1 ND
{ ND l ND l3.17E7 l
lLa-142 l2.s0E-4 17.98E-5 l2.50E-5 l ND l ND l ND l1.58E1 l
)
lCe-141 l6.56ES l3.27ES l4.86E4 l ND ll.43E5 l ND 14.08E8 l
lCo-143 l1.72E3 l9.31ES l1.35E2 i ND (3.91E2 l h3 11.36E7 l
lC.a 144 l1.27E8 13.98E7 l6.78E6 l ND l2.21E7 l ND l1.04E10 l lPr-143 l1.46E5 l4.38E4 l7.25E3 l ND l2.37E4 l ND l1.58E8 l lPr-144 1 0
l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 l7.17E4 15.81E4 l4.50E3 l ND l3.19E.
l ND l9.20E7 l
l lHf-181 l4.90E5 l1.79E6 l2.21ES l ND l3.62E5 l ND l6.59E8 l
lV-187 l 6. 4 7 E '. l3.83E4 il.72E4 l ND l ND l ND l5.38E6 l
lNp 239 l2.53E3 11.83E2 l1.29E2 l ND l5.30E2 l ND l1.36E7 l
(a) The child ago group; data from Reg. Guide 1.109, Appendix E, and UE Safety Analysis Calculation-88 002 00 F.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION TMNUAI.
Rev. 5 p
j TABLE 5 NOTES a
The valves presented in Table 5 were calcul,ated ac-cording to th3 methodology and guidance provided in l
NUR.".G 0133, Rev. 0 (1978).
Specific parameters utilized ares I
Parameter Value Reference SF 0.7 Ref. 9.11.2 f,
1.0 Ref. 9.8.2 e
f, 1.0 Ref. 9.8.2 H
8.0 g/m' Ref. 9.8.2 f
1.0 Ref. 9.8.5 g
f 0.76 Ref. 9.8.5 i
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e-
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,,- - m ve,,-r--wwr----=
l CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5
-s I
The cumulative critical organ doses for a monthly, quarterly or annual evaluation ate based on the calcu-lated dose contribution from each specified time period occurring during the reporting period.
3.6 Gaseous Radwaste Treatment System 3.6.1 Technical Soecification 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate pottions 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 weuld exceed:
a.
0.2 mrad to air from gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 mrem to any organ of an Individual 3.6.2 Description of the Gaseous Radwaste Treatment System O
(_
The gaseous radwaste treatment system and the ventila-tion exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment.
The gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system.
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 shutdown conditions.
These systems will provide reas-onable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.
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.I CALLAWAY PLANT
)
0FFSITE DOSE CALCULATION 4
i MAMUAL Rev. 5 s
3.6.3 OPERABILITY of the Gaseous Radwaste Treatment Sys_ tem The OPERABILITY of the gaseous.radwaste treatment sys-j.
tem ensures this system will be available for use when
{
gares require treatment prior to their release to the 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 tot.al by.the number of elapsed months.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 I
4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES t
4.1 Technical Speci51 cation 3.11.4 I
The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactiv-
{
ity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which sh.11 be limited to less *han or equal to 75 mrom.
l 4.2 Calculation of Dose and Dose Commitment from Ura-nium Fuel Cycle Sources s
e
]
The annual dose or dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as:
4 I a)
Dose to the total body and internal organs due l
to gamma ray exposure from submersion in a l
cloud of radioactive noble gases, ground plane-exposure, and direct radiation from the Uni and outside storage tanks; i
i b)
Dose to the skin due to beta radiation from i
i submersion in a cloud of radioactive noble l
gases, and' ground plane exposure; c)
Thyroid dose due to inhalation and ingestion f
l of radioiodines; and i
d)
Organ dose due to inhalation and ingestion of radioactive material.
I j
l It is assumed that total body dose from sources of l gamma radiation irradiates internal body organs at the t
I same numerical rate. (Ref. 9.12.5)
I j
l The dose from gaseous effluents is considered to be the
[
I summation of the dose at the individual's residence and r
i I the dose to the individval from activities within the i SITE SOUNDARY.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 3
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 l radioactive liquid release pathways.
Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiatien 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 Skm of the Callaway Plant.
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5 4.2.1 Identification of the MEMBER OF THE PUBLIC 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-tiens of the plant site for recreational or other pur-1 poses not associated with the plant.
(Ref. 9.4 and 9.8.11.)
Accordingly, it is necessary to characteri:e this individual with respect to his utilization of areas both itithin and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions l which could be reevaluated if necessary to demonstrate l continued compliance with 40 CFR 190 through the use of I more realistic assumptions.
(Ref. 9.12.3 and 9.12.4) l The evaluation et' Total Dose from the Uranium Fuel Cy-l cle should consider the dose to two Critical Receptors:
l a) The Nearest Resident, and b) The Critical Receptor l within the SITE BOUNDARY.
l 4.2.2 Total Dose to the Nearest Resident l The dose to the Nearest Resident is due to plume expo-O l sure from noble gases, ground plane exposure, and in-l halation and ingestion pathways.
It is conservatively I assumed that each ingestion pathway (meat, milk, and l vegetation) exists at the location of the Nearest i Resident.
l It is assumed that direct radiation dose from operation I of the Unit and outside storage tanks, and dose from i gaseous effluents due to activities within the SITE l BOUNDARY, is negligible for the Nearest Resident.
The I total Dose from the Uranium Fuel Cycle to the Nearest l Resident is calculated using the methodology discussed l in Section 3, us.1ng concurrent meteorlogical data for I the location of the Nearest Resident with the highest i valus of X/Q.
l The location of the Nearest Resident in each meteorlog-l ical sector is determined from the Annual Land Use Cen-I sun conducted in accordance with the Requirements of l Technical Specification 3.12.2.
CALLAWAY PLANT OFFSITE DOSE CALCULATION
- MANUAT, Rev. 5 l 4.2.3 Total Dose to the Critical Receptor Within I the SITE BOUNDARY Thc Union Electric Company has entered into an agreement with the State of Missouri Department of Con-n i
servation for management of the residual lands sur-r:Loding the callaway Plant, including some areas t
within the SITE BOUNDARY.
Under the terms of this r
agreemonc, certain areas have been opened to the public for lov intensity recreational uses (hunting, hiking, sightaccing, etc.) but recreational use is excluded in j
sa trea immediately surrounding the plant site (Refer to FAqure 4.1).
Much of the residual lands within the SITE BOUNDARY are leased to area farmers by the Depaht-i ment of Co,nserv.ation to provide income to support l'
management and development costs.
Activities conducted under these leases are primarily comprised of farming 7
(animal feed), grazing, and forestry.
(Ref 9.7.2, i
j 9.7.4, 9.14, 9.14.1).
I Based on the utili:ation of areas within the SITE BOUN-a l DARY, it is reasonable to assume that the critical r
]
l receptor within the SITE BOUNDARY is a farmer, and that J
! his dose from activities within the SITE BOUNDARY is j
i due to exposure incurred while conducting his farming l activities.
The current tenant has estimated that he
.j spends approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in i
this area (Ref 9.5.6).
Occupancy of areas within the.
i SITE BOUNDARY is assumed to be averaged over a period I
I of one year.
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 l
simultaneously exist at each point of maximum i
l exposure).
)
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CALLAWAY PLANT OFFSITE NOSE' CALCULATION MANUAL Rev. 5 0_s l 4.2.3.1 Total Dose to the Farmer from Gaseous Ef-l fluents l The Total Dose to the farmer from gaseous effluents is l calculated using the methodology discussed in Section l 3, utilizing concurrent meteorlogical data at the l farmer's residence and historical meteorlogical data l from Table 10 for activities within the SITE BOUNDARY.
l These dispersion parameters were calculated by assuming i that the f armer's time is equally distributed over the l areas farmed within the SITE BOUNDARY.
l The residence of the current tenant is located at a 1 distance of 2380 meters in the SE sector.
No meat or l milk animals or vegetable gardens were identified by l the 1987 Land Use census for this location, therefore, I the gaseous effluents dose at the f armer's residenca is l due to plume exposure from Noble Cases and the ground l plane and inhalation pathways.
l It is assumed that food ingestion pathways do not exist I within the SITE BOUNDARY, therefore the gaseous ef-l fluents dose within the SITE BOUNDARY is due to plume O
l exposure from Noble Gases and the ground plane and in-l 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 significant 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.)
I Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Caner Contrelled Area fence which is not obscured by signifi-cant plant structures.
This has been determined to be 450 meters from the RWST.
O V
CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev.
5.
l 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.)
l The direct radiation dose from the RWST is calculated l based on the tank's average isotopic content and the l parameters discussed above, considering buildup and at-l tenuation within the volume source.
Appropriate metho-I dology for calculating the dose rate from a volume l source is given in TID-7004, "Reactor Shielding Design l Manual" (Ref. 9.19).
The computer program ISOSHLD l (Ref. 9.20, 9.21, 9.22) will normally be utilized to i perform this calculation.
I 4.2.3.2.2 Direct Radiation Dose from the Reactor The maximum direct radiation done 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 T
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 attenuatien.
No l credit was allowed for shielding by other structures or l 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 l from LWR Nuclear Power Plant 1979", which considers at-tenuation and buildup in air.
The final value is cased 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 mrada per year, as-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 OFFSITE DOSE CALCtJLATION MANUAL Rev. 5 fs IV) 5.0 RADIOLOGICAL E!NIRONMENTAL MCMITORI!!G 5.1 Radiological Effluent Technical Specification 3.12.1 The radiological environmental monitoring program shall I be conducted as specified in Technical Specification l Table 3.12-1.
5.2 Description of the Radiological Environmental Monitoring Program The Radiological Enviormental Monitoring Program is in-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-g cific pathways and direct radiation can be adequately evaluated by this program.
I Some deviations from the sampling frequency may be i
necessary due to seasonal unavailability, hasardous conditions, or other legitimate bases.
Efforts are i
made to obtain all required samples within time frame 1
outlines.
Any deviation (s) in sampling frequency or location is documented in the Annual Radiological En-vironmental Coerating Report.
1
'l The Environmental samples are collected and analy:ed at the frequency outlined in Table 6.
Reporting levels l and lower limits of detection (LLD) are given in Tables 7 and 8.
l Airborne, waterbore, and ingestion samples collected under the monitoring program are analysed by an inde-pendent, third-party l aboratory.
This laboratory is required to participate in the Environmental Protection i
Agency's (EPA) Environmental Radioactivity Laboratory
)
Intercomparison Studies (Crosschock) Program or an equivalent program.
Participation includes all of the determinations (sample medium - radionuclido combina-l tion) that are offered by the EPA and that are also in-l Oluded in the m:nitoring program.
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i CALLAWAY PLANT i
OFFSITE DOSE CALCULATION MANUAL Rev. S 5.3 Performance Testing of Environmental Thermolu-m nescence Dosimeters j
Thermoluminescence Detectors (TLD's) used in the En-vironmental Monitoring Program are tested for accuracy l
and precision to demonstrate compliance with Regulatory Guide 4.13. (Ref. 9.18),
s Energy dependence is tested at several energies between i 30 kev and 3MeV corresponding to the approximate ener-
[
gies of the predominant Noble cases (80, 160, 200 kev),
i Cs-137 (662 kev), Co-60 (1225 kev), and at least one energy less than 80 kev.
Other testing is performed i
relative to either Cs-137 or Co-60.
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CALiAWAY PtANI O'
OffSil[ DOS [ CAtCULAllON
(
)
V MANUAI.
Hev.
! AltLL6 MAU 8 0LM! CAL 1WlHfMMIMI At MOM U 9H I NG_!110 GRAM E RPo*A8mt PAllsWAY seasMet4 R of kI Pst151 NI AIIVE SAMrt t.S SAMi* TING AND IYP[ AND flitOUtleCY Antiloa SAMrt L_
Astit SAMhi_1MA1!LMS 09tLLELLmt.lMU20L8tGY of ANALYSIS 3., Derect Sudsatiu 40 s outisse aussa torism3 stat sosa citteer At least orece geer 92 days Gamma Dose wi t te two or nos e dos s me ter s or w e tta osses einst rumeest for measaarssig ased recordigny dose rate cositianuous sy. plaed as f ollows:
Asa eswaer riews of si era stations, cenes ist eat to mar teoro t us3 6 ca p
- ctor i st tiae gester al area of Lise 58It E M Y.
Statson CaN M teLr Se e ge wriptisp, t oqa tion, o4 A
u.3 Males tast ol' ilwy O ased CC Jusict lors, Cantaway 1.9 mi. # 349' N tacetric Coop. U t i l i t y Po s e eso. 18e92 47 as Cousity Hoad 448, o.9 Mi ses Soutes or etwy o, Ca s saway o.9 me. e tr* NNE taectrac Coop. util6ty Pole No. 2a t *,1 4s C
Co.m.ty Road 44a, t.S Mi ses Soutes or etwy 0, rl$iit o.4 me. e 45' NE Security Area 5'gra Post e t's D
Primary Meteorological lower 1.3 mi. # 78* ENE 49 t.
Casusity koad 448 Ca 8 laway i terctric Coop ut i s s ty 1.7 al. W 98* E Pole No. Of,9*>9. Heress Wi14 8 i fe Massagemerat Partieng Area S2 I
toght Po le Nea r t ast Plaset Security fence 0.4 mi. # 184* [SE St G
tocated ise the *'V" or stae abaredoned Railroad spsar.
0.7 mi. # 137' SE enortiswest of sludge l agoosa So is Couesty Hoad 4*;9,
- 1. 3 Miles Nortte of Itwy 94, Ca 81 mway 0.9 mi. # 163* SSE 88ectrac Co.,p. Uti8ity Pole No. 3 SOS 6 of J
Couenty
.e 4*>9. 2.6 Miles Nortta of Itwy 94, Callaway 1.3 mi. # 181* 5 1Icctsic sep. U t i l i ty Pu t es No. 35091 3r IL Cuausty Hoad 4*#9, 0.9 Mi les South of ilwy CC, Ca I *away o.F me. # 202* SSW 1Rectroc Cuop. UtaIity Polo No.
3*>O T T l
41 1.
Cousaty Road 4*j9. o.1 Miles Sonatte of ifwy CC, 411away 0.$ mi. W 230* SW I
itectrsc Cesp UtiIiLy role No. 3*Ae F 3 1
44 M
asegisway CC. l.0 M e t er s Sou t ta o f Coassa t y Road 4*>9, 8.7 mi. # 2Sl* WSW l
CaI8aw.sy Ilatetric Coop. UtiIity Po3e No. I S f(,9 l
1
- it,-
CALi AW4Y PtA80I
~
ofISIl[ DOSE CALCCLAll0st MA8BMA4_
8tev.
S j AB1E 6 LGaMaLi!*ised)
R._AMlOLOGlCAUflYLkj0 Rete AL pe_r)st?iOHIM PHOCRAft Station (odg "ggger
$jgg,W igtjpgjig 8,gM;a11gg 06 88 Coosity Road 428 l.2 Miles West of Hwy CC, Ca t taway 2.0 al. G 2 Fl* b8 88ectric Coop. Ut s 8 i ty Polo 800 18609 4S P
County Head 428 O.I Miles West of 8ho CC, Callaway 1.43 el. S 290* WOIW tlectric Coop. Utility Pole Ito. 18S80 03 Q
- u. I Miles West of alwy CC est Gravel Iscad 0.8 Miles 3.3 ei. W 308' IIll South towy O. Callaway [Iectric Coop. Utelity role 80 0 18*>S9 46 M
horth-fast side of Hwy CC aged Cousity Road 446 1.$ mi G 333' 01098 entarsectson Cat 84way [lectric Coop.
Ut 6 8 4 ty Polo 800 28242 Are outer riesg of siateest stations, orm ase eacts meteorologict ". Sector in the 6-to 8-km raenge f rom the site.
e 36 A
County Road ISS o.8 Milea South of Cousity Hoad 132 S. 2 m i. W l' II Callaway Electrac Coop. Utitity role 800 19131 25 8
Cousaty No.sd ISS, 1.9 miles snortis of Hwy 0, Callaway 4.0 mi S 23' 3000[
tIeectric Coop. Ut s a 4 ty Pole 860 19500 20 C
Magtsway D, u.4 Miles Nortis of Stwy 8(, Callaway 4.8 mi. # 4 7' 800
[sectrec Coop. Utility Pole 900 12830 IS D
Hagisway D u.4 Ma les Soutte of etwy O. Catasway 3.8 mi G 63* EleC itectric Camsp. Utility Pole 900 129S2 IF
[
Couesty Road 40S3 o.3 Males fast of Hwy D, kisegdom 4.0 mi. 4 89* [
leleptiosse Company P 31e sto. 3 X 12 I4 5
Soesth-t a st Side of Itwy 94 ased Hwy D Intersectiest 3.0 ml 4 121* ESE Callaway (Iectric Coop. Utstity role 800 11940 la C
City of Portland, Callaway Electri(. Coop. Utility 4.8 al. # 139* SE Pole 860 12332
- 0 H
Higtsway 94 l.8 Miles tast of Cousaty koed 4',9 4.0 al. # IS7* SSE 4.e88away t'lectric Coop. Utility Polo 800 32582 49 J
Sk rtle-West Side of sky 94 asad County Road 4S9 3.7 mi. # 183* S Ja.sacteen, Cattaway [sectric Coop. Utility Pule leo. 061*>4
=ll~
CattAWay etAlet j
sMrsatt oost CALCULAT1001 1
sv438AL flow.
S 1
I AMLt _icontins.s1 2
- Mt19ti'GKAL (*itiMasingtI AL!agsg!Jgn esic syggajag station feast Geiler Min _9aMrJ etien Location su m
wst sede er County Road 4ast at the Junction 4.6 me. e 208* ssW wath c.nety Hoad 463. eter m an resepseene rway i
Pole W. 2hl i
42 L
County Road 441. 2.6 Miles soortis of County Hoad 463 4.4 mi. # 233* SW Ca 8 laway [Iuctric Coop. Utisity role 800 06326 1
3/
M tiieg8 sway W. 0.6 Miles West of County Road 441 3.4 al. # 231' WSW Ca s taway Electric Coop. Utility role 800 27031 45 et 8segway AD. 2.8 M4 8cs tast or etwy C. Callaway 4.8 al. # 219' W ileCtric Coop. UtiliLy Pwle $$o, IS239 4e r
8torth-fast Sielo of Coenity Head 112 and b y 0 4.2 mi. G 294* WIIW Jusectiosa Ca a laway L tectric Coop. UtiIity Pole seu. 06126 39 Q
4'eaunty Mead I12, U. i Miles Iest of Cosmety Road Ii1 S.4 mi. e 31S' She Ca 8 8 away 1. Iarc t r o c Coop. Uti8ity Pole 100 17S16 38 at Coussty Road 133 1.*> Miles Soutta af $4wy UU 4.8 mi. e 337* IIIIW Catsaway Eteletrsc Coop. Utility Pole 300 34108 t egtet Stat oeses to tem placent in spec sa t senterest areas saatte as populatiews cessters. sierae by eesedersaces. schaeo I s.
ased ies I or 2 assas to serve as control st a t teens.
33 II city or stans Prairie, South-tast of the etwy C 7.4 mi. # 213* W and W y AD Jusactiose 31 1.
Ci ty or Wh see, Ca 8 8 away 8. 4ect ric Coop. Ut i l i ty F.4 ml. # 234* SW Pule h. 06419 26 I
lawse of Americus. Ce laway Electric Coop. Uti 8 ity 12.1 al. e 82* [
reIe 860 I I l*,9 2l f
town of Illuf f tose, Cat taway [tectric Coop. Istility 9.6 mi. e 110' ESE role 800 15496 3*,
F.
City or Boledo. C488away Electric Coop. Utility S.8 mi. # 342* IIIIW rois ano. 17684 23 a
City or Yucatan, Callaway Electric Coop. Utility
- 6. 8 mi. # 16* IISBC Fo 8 e 300 I?telo
.y3 a
i
[(m
['
CAL &AWAY PtANT
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\\
0(ISIIE DOSE CALCULATIOft
- v/
MANUAL.
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1^t$tLft1&ontifmd)
HAOios OGICAL t MYLHONM[MI ALtW)3[lO3 LNG PIM) GRAM station Codq aggor ste_ Luc riptj en Lesaging c
City or rortsand, Castaway teectric Coop. Utisity 4.8 mi. e 139' st Pole No. 12112 20 C
City of Readsviste, Callaway flectric Coop. Utelity 4.8 me. # 41* NE Pole No. 12830 3as P
Not tis-t ast Si.1c of etwy C and County Road 8eOS 9,f mi. # 293* WhW
( P-Corst so l )
Ja.rar t ! on pl Q
iligtsway I, 0.8 Miles f ast of flusiness S4, Callaway 11.0 mi. # 312' NW
( Q-Coret ro l )
[Iectric Coop. Utility s'ose too. 21544
?.
Ai rtso rem Eaqioj od iyJan[gigf1 8 tad s o soelism and Samples from five locations Co.itinuous operations of Analyze at least once Pa r t icia l a t e s sampler witte sample per i days for 3-131.
Colsection as requered try dust loading, bu t a t least once per I days.
If e r ee samples from close to the tierce $818 ftOUNDAHY locations, ff f_14Gdate Samp[qi des different sectors, of tfm te s gtse s t ca lcas t a ted annua l ave rage Analyze for gross beta y e oused Ieve1 D/Q.
radicactiwi ty > 28s imurs following filter cleange.
Perform isotopic arealysisgamma on ttmse samples for which the gross ben.a activity is >10 timos t'ae yearly mean of control semples. Perform gamma isotopic analysis 8 on composite samples (by locatiosal at least once per 92 days.
Al 1)
Prim 4ry Heteorological lower 1,3 mi. # 18* [NE A8 il County Road 41s8,
..n Miles South of etwy 0 0.8 mi e 24' NN[
11 3 A
- 0. 3 Hiles l ast of stwy 0 and itwy CC Junction 1.9 mi. # 349' N.
')
CAI8AWAY PtAMI Of f S4If DOSI CAL cut AllOes
\\
MANUAt_
Rev.
b/
I A811 L6_ t! ont Ls!"ed )
M AD 8 M 8E I CAL _{Ifyjh0NHi td I AL. NOMl10M I WC ftOGRAN Statiosa Ct")2 LeCl"f Ellf_I M E!d pkiP'?
LM t ios!
Ovie sample f rom the cmsnity with trae toegteest D/Q.
, *J H
Commeas:ity of Mrform 1.7 mi. # 338' NNW Osse saanp le f asam a capot rol I ota t iose, as for enample l*s-30 km distant asms its the
- east prevaleret w e sui d i rec t icas.
j l
Al Q
C. tiartley farm 9.S mi. # 312* NW
{
- 3. Wa te s tnes sar a.
Saa r i ac e' Osse sample upstseam Come*.->si te sample f Casama isotopic analysis 8 ove r a pe r iod of eacta samples.
of less than or I r i t iases assa lysi s o f composite equal to 31 days, sample at least once per 92 days.
Sol II 84 feet opstream of discisarge, riortin tsank 4.8 mi, # 144' S[
One sample dowsestseam Sat?
G 1.1 miles downstream of discharge, reortis tsarik S.2 mi. # 133* SE Is. Ur ! s:k e spj Osse sample of each Composite samples over 8-131 analysis on each osse to three of f lee 2-week period when composite wfeese the dose secarest water ssapplies 1-131 analysis is calculated for Line w e t te s se let miles downstrea, pe r fo r mett, monthly conssamptiers of the water (fea t could t#e a f f ected tsy composite ottiervise.
is greater than 1 area its discleasge.
pe r yea r. Compos i te f or gross teets and gamma isotopic analysis Osse sample f rom a cositrol sonthly.
Composite for location.
tritium avtalysis quarterly.
As tteere are soo driseking water isitabes withise 10 miles dowrestream of stie discharge point, tioe dresekiseg t.ater pattsway is currently not iracluded as part of the Callaway Plant Radiological
- f vau ld future water erstakes tee cosestructed witlein 10 river f rivi rotemersta l Moset tor s teg Program.
males dowrestream of tha d i s.c ha rge pt. e nt, these glie program will t>e revised to ireclode this 3.a t tswa y.
(Hef.
- 9. 6. (3 )
l
- cd imeset Osse sample f rom dowsest ream Semiasessua l ly Camma isotopic analysis (d)
I c.
Is sse area with eaistiseg or sea d asneaua l ly.
Stoo s et t i sees pote tial recreat60348 value.
l l
-so-1
_m.
.__.m__.
s
.m-CAtiAWAY PtAsII Of8SIIE DOSL CALCULAil0It pWusuAL liev.
S JMit t 6_lPJnij.fsejg;q)
EAi!1_Olog[GA(_18lyJMolent 96i AL P!geglIOHIIgG NtOGHAM Sta t lose Cod t EfE3 *f El LE_Q!t1C F.lRiiuff LofE1198}
i C
G 1.0 river mi to downestream of discharge, north bank S.1 mi. et 13'n* SC t-a.
f as9estiose n
- a. Milk Samples f eon milking arsimals Semisurathly wteers Camma isotopic 8 ared 0-131 ese three locat soes wittaire artimals are ora analysis semimoesthly wteen
't be distassce tsaving time pasture, monthly at animals are on pasture; toegisest dose potentia 89 6tteer times.
monthly at other times.
It tieere are esosses. tieces osee F
sample from mi8kersg aresmals
&n eacts of three areas Isettwaers $ to 8 km distaret wtarre doses are calculated tes tse greater tiaan I arem
[
per year la.se to a lack of milk assimals wisich satisf y tieese reqirements, stie milk pattsway is cesrrently smt stoctuded as a part of the Callaway Plant f(adiological issvirosamesetal Mussitorireg Program.
l Stsousd ttee Antessal land Use Censaas idesatify the existence of milkisest animals its locations which
[
Sat' sty timese regass remerssts, tiaers Etee program wil 8 he revised to isscluele this pathway.
41 I i sle Osse sample of eacts Sample its season, or Camma isotopic analysis 8 commeecially ared semiasmyla 5 8y if tleey on edible portions.
[
secreatiersally imgwa r tant are saut sea sotaa l.
j species in vicisesty of plarat discisarge area.
Stations iltqL ggEjpLjist) 1.pga Lj.gg l
Ogde fr ggnf D
e
$.1 mi, di 13'n' St C
C 1.0 river miles downstream of discisarge, nortte bar.*n Oise sample of same species its areas not l
inflesersca d by plant discharge.
i a 9 mi. 4 134* SSE
[
A H
- 0. (s river al acs sapstream of discharge, saas tle bank n
M
+85-I t
r
.--v--..,----,,,-#,---
r.-
r
-~ <. = -,
2-
---.--+=m
. _.. --. - - ~- ~..-
.a
~
m.
CAABAWAY PtAssI i
off581[ DOST CAtCU4AI80N I
84AssuAt.
stev. 5 l
.- l i
IABLL6_1&orttintadi EAD10tOGICAL IID(IficepigI AL Pet _MIOMl peg PfeOCHAft Sta t lose t'odg fetinr ifte Deser42L19D Loca t iatt c, food Products Osse sample of each At timo or taarvest (h)
Camme isotopic analysis 8 principas esass or on edibse portion, pecducts f rom assy area that is irrigated by water in wtaicts 8 equid plarat wastes tsave 4,eers dasotiarged.
As tieere are sie areas irrigated by water its wisich Iiquid plasst wastes leave been dewisarged within 50 river miles downstream of tree discliarge point, this sample type is not ca.rrently isscluded as part of the Callaway Flarit Radiological trivirosaneestia plosen torisag Program.
50sould t estsare i rrigat iose water intakes be conse.rascted wittsin 10 river miles downstream of the disefsarge point, Etien the program will ne revised to irac 8 ande th i s samp le type. (Mef. 9.7.6 mand 9.T.7)
Samples of three 14osithly when available Gamma isotopic 8 anst 3-131 dif ferent kiseds of analysis broad teaf vegatatioen grow.e nearest eac6e of two different offsite loca t iotes of higleest predicted arwessal average groutad-level D/Q if milk sampling i s root i
perrotmed.
Statson I
Code Lestest 111e__JMtigr_jPL129 tocatiore l
l V6 ft Becker's f ara 1.8 al. e 3aa* HIN ss 1
l VI A
stechan's fare 1.8 mi. e 356* 88 l
l Osse sample of emets of 99pntisly where available Camma asotopic8 l
similar broad s e a t' ana lysi s.
(
vegetatiets grown 15 to l
30 km distasat its the teast prevalent wind i
directiore (if milk sampa iswa is viot performed).
Station Cd9 hsstor 31Lc._DutrJ et199 tacati9n v3 t.
mearney's far.
15.0 mi e 227* sW
-a2-r t
-.. ~ - - - - - - -. - -. - _.,- -,.. -,-.-. - - -.. -. -.
n-CAS4AWAY PtNEl b
OFi51I[ DOSE cat Cut AI 8 Oft k'
MAlltaAL Rev.
'e MH8_Ur_igun j pocafj j
f Allt t P60l Al J O9)
(a)
(sev i a t ioses a v et pe e m e t ted F e sem tiest seagesired samplir p schedule if specimesas are eersubtainable due to hazardots canul e t iosos, seasonal usea v4 4 8 atsi s Ry, ma l fsarac t o nes e.' automa t ic sampl itsg equipmeest, csad othes' legitimate reasores, If t.pec issurses a v es ensuitsta istat>Ier due to sampling equeget malf unctiosas, every ef fort shall tse pade to complete cas s ec tive act asass prior to time esus est (fee seers t sampsityg perie-l.
All deviatiosas f'resa time sampl iseg sched.se t sina 8 4 tees documeset**d e en tteer Anseual Hadiolw34 cal ( sevi s osementa l Ope ra t iseg Report.
It is recogssited tisat, a t t omes, it may seu t Ise postatste or practacal to cositisseee to ots t a i re samp les o f tree mesdia of claoice at Etee most desired locatiose or t i nes.
S ee a fwesse i se s t asec e s, snai tats les a I te s saa t i vet media ared locat ioses stay tse clussen for the gearticular pattaway ist quest ines asul appropr iate sastsst i tant sawis made we thise 30 days in tiar Radiological i ssv i roswenta l Morsi to risag Prog ra m.
Idesst i f y tips cassw of tiae ennavai lats s 4 4 t y of samples for tisat pa tieway asad ideratify time new location (s) for j
uts t a i ss e sej s ep l acemeset samples in ?fut see s t $ca s - Arwissa l Radioactive E fflasent Release keport ared also include in the report a s erv i sed i'igurer( s) asui table for the ODCM re f l ec t ing t he surw loca t ios:( s ).
(Is )
Osw, or sewst er i sos t r asmeset s, such as a psessaarlieef iose chaatser, for measurissg asut recordiseg dose rate cositinuously may taer eased isa place of, or en addition to, isategratiseg dosimetes s f or time pearpose of stais table, a t$ees muleane rnesca ret dosimeter { IL D) is cosesidera d to tse osse pinospisor; two or more plassphors in a packet are cosesidered as two or more dosimeters.
I ils tsadges staall samt tse a: Sed as dosimeters for measurisig direct a o statiores e s sent ass atssolestes naaminer, llae nasatser of direct rad ia t iote morei to r e nt; stations may be radsatauss.
Etws s
verdew ed accosdisig to geogr aphical l e as t a t iosts; e.g.,
at ass occaso site, some sectors will tse ove r wa te r so tisa t s tes: suanteer of dossmeters may tse reduced accordingly.
Itse fregasesecy of' analysis or readuist for IID systems will depesnt espost itu criaracteristics of tiec speci fic system used ased sterwid tse selected to otstaisi optimum dose i sel o r saa t iasse w i t ts mi ss e ma t rad i suj.
(c)
I tset postpow of tteis samp'e i s tes utstairs backgs esund i te f'o r ma t iose.
If it is anot practical to establiste control locations iss accordasece wi tte the d e starece arms wasis! direction criteria, ottser sites that. provide valid backgroused da ta may Ise tastesti tasted.
(d)
Camma e sot op s e; a rea l ys i s a s de f'issed a s (twe identi f'ica t iose ased quassti fication of gamma-eme tting radiossesclides traa t ma y tee a t t r e tnes t a ts * *e to the ef f 8 uent s f rom time facility, (c)
Ilut "espstream" sampic staa l l Ise ta&cre at a distassce tseyond significant influersce of tiae discharge.
Tise 3'downstacan" sampic stea l l tse talien ise are a rea lecyosuf, taut seca r time me xiseg Iswie.
(f)
Ise thes psogsam, const aret volasme st ump f e a l iquots a r e co I Iec ted a t time inte rva l s tisa t a f'e sho r t (e.g., musitte ly).
(9) f lee dose shall tse calcaslated for tien manimum orgast asul age group, usisag ttee mettusdalogy ased parameters in (Bus DiWM.
( te )
If f a.o rves t occiar s mute tisasa oncer a yea r, samp l ing sisa l l tar pe r fo s med dia r i ng eacte d i sc re t er tsa rve s t. I f ina rves t uu sers ceaset iseewens ly, sampleng shall tse musethly.
At tesit iose sina l t tse paid to iracludessg samples of tutsesous and root fwn! psoducts..
l 4
[N cat t AbdAY F1 ANI
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)
OffSlif DOSL CAtCULAT80ft t
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MANUAL Rev.
S I Atil L1 HI M* ! M.l l Yl L5_f 0H_ EA080ACI 8 V11Y C(MIN !fi A! 80NL 18LI NYlfoNMIM LAI SNL LS 6(eport s ang t esvo l s i
i i
Wa t es r Ai rima rsso Pa r t icia 8 a te f i sts Milk food Product i
I Assa lysi s
( g.0 4 / 0 )
or Cases (pCi/mI }
(pCi/kg ), wet (pCi/8)
(pCi/kg, wet)
I I.__...___..__
I 1
08-3 24,(mms
- I I
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Mes *f s I,(MHb 3(s,8 M N)
I a
i I
i n e *j9 e,e n s to,esM)
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I i
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Co-6o 3 na so,ooo I
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I f r -tite -9*>
- esMi **
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I I
I-13 e.9 3
500 l
I I
l CL-9380 348 to I,4.M M)
(>O 1,000 I
I I
I Cs.31 w
2o 2,000 70 2,000 1
I I
l _su-t a-18 o D a. ' *
- 31to*
- I t
f or eg r e ssk s es9 wa ter samples.
f or bestf aces wa ter samples a valase of 30,000 pCi/8 is used.
- l es t r. 8 actsvety, pa r erst plass daugf ater act s v e ty.
O
-Sa -
s
CA4&AWAY PtAMI offSII[ DOSE CAtCULAIION MANUA1.
Rev.
- y
!A!54 LO MA? !Mug VA{tif $,_f sH _lgjk{Wy{ljM[jl_p(Q({f CIlpgJ(({M*,b, j
I I
I Water A s e teos sie Pa s t icula te f i sie MiIk food Product sediment I
l Assa lysi s (pCi/t) o r Ca ses ( pC i/m 3 )
(pCi/kg), wer t (pCi/1)
(pCi/kg, wet) (pCi/kg, dry) I l _ _ _ _ _ _..
Pa 01 I
I IGross tieta I
I l
so-3 2000
- l l
l 5
I I c
- >4 l *s 130 l
I I
l e c a,9 su n,o i
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l Co-Sn.6o SS 13o i
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I t r-nti-95 l a, I
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I 8-139 f(d)
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60 150 l
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18 06 I *>O 18 80 ISO I
L l
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sia-a a-ts n 33 **
13 *
- I e
- But sus tate water samples, a value or 3000 pCi/ 8 is used.
l
- total act ivi ty, pa rcent plus daugteter act ivi ty.
1 i.
4
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1 CALLAWAY PLANT CIFSITE DOSE CALCULATION MANUAL Rev. 5 TABLE S (CONTINUED)
TABLE NOTATION (a)
The LLD is defined for purposes of compliance with the Radiological Effluent Technical Spe-cifications as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, j
that will be detected with 95ll probability with 57; probability of falsely concluding that t
a blank observation represents a "real" signal.
For a particular measurement system (which may i
include radiochemical separation):
I LLD =
4.66 Sb i
E *V*
2.22
'Y
- exp (-lat) j i
Where:
LLD =
The lower limit of detection as defined e
above (as picoeurie per unit mass or i
volume).
l Sb=
The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
E=
The counting officiency (as counts per disintegration).
V=
The sample si:e (in units of mass or volume).
2.22 =
The number of d'.-integrations per minute per picecurie.
Y=
The fractional radicchemical yield (whe-applicable).
I O
- So.
CALLAWAY PLANT OFFSITE DobE CALCULATION MANUAL Rev. 5 A=
The radioactive decay constant isr the par-ticular radionuclide and, At =
the elapsed time between sample collection (or end of the smaple collection period) and time of counting (for environmental samples, not plant effluent samples).
Typical values of E, V, Y and at shall be used in the calculations.
It should be recogni:ed that the LLD is defined as a a priori (before the fact) limit representing the capa-bility of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses ara performed in such a manner that the stated LLDs are achieved under routine conditions.
Occassionally background fluctuations, unavoidable small sample sizes, the presence of inter-fering nuclicas, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
(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 anlay:ed and reported in the Annual Radiological Environ-4 mental Operating Pepcrt.
1 (c)
Required detection capabilities for thermolu-minescent dosimeters used for envirenmental measurements shall be in accordar.co with the reccommendations of Regulatory Guide 4.13,
)
Revision 1,. July 1977.
(Refer to Section 5.3) e
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CALLAWAY PLANT O~'
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CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL
- ev. 5 6.0 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM l
l ATMOSPHERIC DISPERSI0(I PARAMETERS 6.1 Atmospheric Dispersien 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, f
1979.
l 6.1.1 Leno-Term Dispersion Estimates The PUFF (fluctuating plume) model and the straight-line Gaussian (congtant mean wind direction) model were used for determination of the long-term' atmospheric dispersion parameters.
A more detailed discussion of the methodology and data utili:ed to calculate these parameters can be found elsewhere (Ref. 9.6.12).
l The Unit Vent and Radwaste Building Vent releases are 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 located, and the Unit Vent is equipped with a rain cover which effectively eliminates the possibility of the exit velocity exceeding five times the hori: ental
}
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)
- SS -
i
i CALLAWAY PLANT OFFSITE DOSE CALCULAT' ION m
MANUAL Re'r. 5 t
l 6.1.2 Determination of Long-Term Dispersion Esti-l mates for Special Receptor Locations Calculations utilizing the PUFF model were performed for 22 standard distances to obtain the desired disper-sien parameters.
Dispersion parameters at the SITE SOUNDARY and at special receptor locations were esti-mated by logarithmic interpolation according to (Ref.
9.6.14):
g g )B (6.2)
[
d X=X d y Where:
s in (X;/X )/in (d /d ).
B=
g 2
g and
[
X,X2 = Atmospheric concentrations at distances dg 1
d, respectively, from the source (in 2
C1/m ).
l sg The distances d and d were selected such that 3
2 d1 <d<d,.
l 6.1.3 Short Term Diseersien Estimates Airborne releases are classified as short term if they are less than or equal to 500 heure 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 dispersten estimate by a cor-rection factor (Ref. 9.9.1 and 9.17.4):
l I
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CALLAWAY PLANT 0FFSITE DOSE CALCULATION l
MANUAL P9v. 5 l
s s-Where:
T3=
The total number of hours of the short term
- release, T, =
The total number of hours in the data collee-tion period from which the long term diffusion i
estimate was determined (Refer to Section t
6.1),
i Values of the slope factor (S), are presented in TABLE 11.
l Shott term dispersion estimates are applicable to short l
term releases which are not su'fficiently random in both time of day and duration (e.g.,
the short term release r
periods are not dependent solely on atmospheric condia 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).
i The general approach employed by subroutine PURGE of I
k XOQD0Q (Ref. 9.17.4) was utili:ed to produce values of i
the slope of the (X/Q) curves (Slope Factor (S)) for both the Radvaste Building Vent and the Unit Vent.
t However, instead of using approximation procedures to produce the 15 precentile (X/Q) values, the 15 percer.-
s tile (X/Q) value for each relcase and at each location was determined by ranking all the 1-hour (X/Q)g values for that release and at the location in descending order.
The (X/Q)g value which corresponded to the 15
[
percentile of all the calculated (X/Q) values within a j
see;or was extracted for use in the intermittent I
release (X/Q) calculation.
I r
l I
i t I
l CALLAWAY PLANT OrFSITE DOSE CALCULATION MANUAL Rev. 5 l
The intermittent release (X/Q) curve was constructed using the calculated 1-hour 15 percentile (X/Q)g and its corresponding annual average (X/Q),.
A graphic re-l presentation, of how the computational procedure works j
is illustrated by Figure 4.8 of reference 9.17.4.
The l
straight line connecting these points represents (X/Q)g j
3
' values for intermittent teleases, ranging in duration 1
from one (1) hour to S760 hours.
The s' ope (S) of the j
j curve is expressed as:
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/
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== e. g m -J =E 8 4 e a 6 6 I I g A = E. 3 3 3 E E. 3 'g 4 .ar = -gg i ? - - + 4. 8 N w l 0y . E ~ ( .I. J I 2 i E en w = = >
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== -{ 4= 5 =.w. =. 4 w { g w $' p 3 >s>w St ia t W w w w w = y a S A S e e 4 E. 8 46 8 4 ga 4 1 4 4w .=== 9 g g y = t
i CALLAWAY PLANT 0FFSITE DOSE CALCULATICN MANUAL Rev. 5 j TABLE 11 SHORT TERM O!SPERSION PARAMETIRS_(a) (c) i Slope Tactor (s) [ Location (b) Sector Distance Unit Vent Radwaste l (meters) Building Ve.nt Site Boundary S 1300 .328 .320 l llearest Cow NW, 5053 .263 .266 { Nearest coat NW 5053 .263 .266 Nearest Meat !aiW 2736 .262 .268 Animal [ 11earest Vegetable tiNW 2865 .264 .268 [ Carden Nearest Residence taiW 2865 .264 . 268 l I (a) Reference 9.5.4 l ! (b) Data from 1987 Land Use Census (c) Recirculation Tactor = 1.0 t l I i I l i i i f i 94 - f z-.-.--,-------_-.--
CAa8AldA7 F1 Aft! \\ 08858If EsOS( CAA Cut Al son / j 8eAansAa. new. S I AtllI _._If i APM ((A{jfq_d)$ A l %W( 18 9 f, _j) f 'ff[ M $ R f,ANAft{ { ff 6aILt-i M58(ses CostiStot t 8 88G CD88INOR & 8seC j $ sO*f( __ F A 818WA Y f 8f 88 Ji Pl 8 ( 9 (198 { FA8' APil { { M. . AR4#1M8C _l DC AI j {88t_ 8 i foote l ev 4.a s, 4 tete Aes 5.%?. 8 N/4 den:ayed/emedepleted Site es,==edary j 9eestalw t.as, Gamma Ace B.% 7. 9 E/4. detayed/+wedepleted Site Eloesndary
- 4.de l ev 4.a s, lutal Hudy 3.4.8 & 3.% 8. 8 N/4, det ayed/6asadeple ted 54 te Stonesedary foute t e? 4.a s.
- A e ss
- 5. ae. l & 3.% I.3 M/4 des ayed/*eeedep setees si te h=%ry La uemmt F 4 4eees Gegnes s t esese 3. *e. ?. ?.
- 18/ 4 tacasest Mes eeaent ledsa t a t s on
- 3. *p. ? ?. 8 E/q, dew a yre8/etep le t ed 08e s les secasest Resedeset veesc a a t s eees
- 1. *s. ?. ?. 3 88/ 4
- Ua4 8d Steea s e s t Sles &desat et e 8 es 3.%?.?.t 88/Q*
C3e ee.g gecasest 8sesedeset Wat
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'8 ese 80-5 and L.3s, 3/g, detapeJ/depseted eS essed seestcad es is/q l 84cierre est e 9. I1.1). e l l l i .n_ l =
CALLAWAY PLANT OTFSITE DOSE CALCULATION MANUAL Re" 5 7.0 SEMI-ANNUAL RADICA0TIVE EFFLUENT RELEASE REPORT Routine Radioactive Effluent Release Reports covering l the operation of the unit during the previous 6 months of operation are submitted within 60 days a.*ter January I 1 and July 1 of each year. The period of the first report begins with the date of initial criticality. The Radioactive Effluent Release Ruports 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 Liqu.id and Gaseous Effluents from Light-Water-Cool'ed Nuclear Power a Plants," Revision 1, June 1974, with data summariced on a quarterly basis following the format of Appendix B t thereof. For solid wastes, the format for Table 3 in [ Appendix B is supplemented with three additional l categories: class of solid waste (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Type B, f 1 Large Quantity), and SOLIDIFICATICN agent or absorbent (e.g., cement, urea formaldehyde). l 4 1 i The Radioactive Effluent Release Report to be submitted l within 60 days after January 1 of each year includes an i annual summary of hourly meteorolegical data collected l 1 over the previous year which may be either in the form 1 of an hour-by-hour listing on magnetic tape of wind t speed, vand direction, atmospheric stability, and pre-l capitation, or in the form of joint frequency distribu-f tions of wind speed wind direction, and atmospheric f stability.' This same report includes an assessment of 6 the radiation doses due to the radicactive liquid and gaseous effluents released frem the unit or station r during the previous calendar year. This same report also includes, the asessment of the radiatien doses frcm radioactive liquid and gasecus effluents to MEM-2 .1 EERS OT THE fUBLIC due to their activities inside the L I l SITE BOUNDARY during the report period. All assump-tions used in making these assessments, i.e., specific t activity, exposure time and loca' tion, is included in t these reports. Acceptable methods for calculating the dose ecntribut:cns frcm liquid and gasecus effluents are given in Regulatory Guide 1.109, and the CDCM. l 4 l r t l l ( r i 4
CALLAWAY PLANT OFFSITE DOSE CALCULATICN MANUAL Rev. 5 O v The Radioactive Effluent Release Report to be submitted 60 days after January 1 of 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 PUBLIC frem 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 CTR Part 190, "Environmental Radiation Protection Standards for Nuclear Power operation". The Radioactive Effluent Release Reports include a liat and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. i The Radioactive Effluent Release Reports include any changes made during the reporting period to the PROCESS CCNTROL PROGRAM and to the CDCM, 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 O 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 informatien An explanation as to why the in:perability of itquid or gaseous effluent mont-toring instrumentation was not corrected within the time specified in Spectitcation 3.3.3.10 or 3.3.3.11 respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.5, respectively.
- !n lieu of submission, the Union Electric Company has the optien of retaining this summary Of required meteorological data en site in a file that shall be provided to the NRC upon request.
(Ref.9.4) - 9? -
CALLAWAY PLANT OFFSITE DOSE CALCULATION MA! CAL ,Rev. 5 I 8.0 DIPLEME:47ATIC:10F 000M ?!ETHODOLCGY [ + The CDCM provides the mathematical relationships used [ to implement the Radiological Effluent Technical l Specifications. For routine effluent release and dose assessment, ccm-puter codes are utili::ed to implement the CDCM methodologies. These codes have been evaluated by a qualified independent reviewer to ensure that they pro-duce results consistent with the methodologies pre-i sented in the 00CM. (Ref. 9.5.5) i O i l i L 1 i I I h t l f I l l l J i i l . t l l 1 1 ) l
.l CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. 5
9.0 REFERENCES
9.1 Title 10, "Energy", Chapter 1, Code of Federal Regulations, Part 20 U.S. Oovernment Printing i office, Washington, D.C. 20402. t 9.2 Title 10 "Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I U.S. Govern-l J ment Printing Office, Washington, D.C. 20402 9.3 Title 40, "Protection of Environment", Chapter 1 Code of Federal Regulations, Part 190: U.S. Covernment Printing office, Washington, D.C. 20402. e t l 9.4 U.S. Nuclear Regulatory Commission, "Technical l Specifications Callaway Plant, Unit NO. 1", NUREC-1058 (Rev. 1), October 1984. J I 9.5 Communications } l' 9.5.1 Letter NEO-54, D.W. Capone to S.E. Milten-berger, dated January 5, 19832 Union Electric Conpany correspondence. l f 1 9.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q 1 and D/Q Values", J. H. Smith (Bechtel Power l Corporation), to D. W. Capene (Union Electric ] Co.), dated February 27, 1984. l 1 9.5.3 (Reference Deleted) l I 9.5.4 Letter SLUE 1232, "Callaway Annual Average X/Q Values and "S" Values" J. H. Smith (Bechtel i Power Corporation) to D. W. Capone (Union l Elecetric Co.), dated February 9, 1984. [ 9.5.5 Letter SLUE 1356, "Comparisen of Callaway Plant Offsite Dose Calculations for Routine Effluents", J.H. Smith (Sechtel Pcwor Corpora-tion) to D W. Capone (Union Electric Ccepany), dated March 22, 1984. 9.5.6 Private C:mmunication, H.C. Lindeman & B.T. I 1 Holderness, August 6, 1986 I 1 l 1 1 I [ t 'l i I i 1
l k r I CALLAWAY PLANT OFFSITE DOSE CALCULAi!ON l MANUAL Rev. 5 f 1 l 9.5.7 Letter, M. C. Slaten to A. C. Passwater, i "Commercial Use of Lands Inside the Callaway l l Plant Site Ecundary", dated August 25, 1987. I (UENE Safety Analysis calculation 87-050-001) l t ! 9.5.8 Letter, N. C. Slaten to C. C. Graham, "Farming l Meteorlogical Parameter, Restricted Area", I l dated December 14, 1987, i 1 1 9.6 Union Electric Company Callaway Plant. Unit 1, l Final Safety Analysis Report. 9.6.1 Section 13.5.2.2.3.1 l 9.6.2 Sec, tion 11.5.2.2.3.4 l i 9.6.3 Section 11.5.2.1.2 9.6.4 Section 11.5.2.2.3.2 l l 9.6.5 Section 11.5.2.2.3.3 l 9.6.6 Section 11.2.3.3.4 1 l 9.6.7 Section 11.2.3.4.3 i 1 9.6.8 Section 11.5.2.3.3.1 f 9.6.9 Section 11.5.2.3.3.2 f 9.6.10 Section 11.5.2.3.2.3 L 9.6.11 Section 11.5.2.3.2.2 L 9.6.12 Section 2.3.5 l I 1 1 9.6.13 (Reference Deleted) I 1 l 9.6.14 Section 2.3.5.2.1.2 l 1 l 1 9.6.15 (Reference Deleted) l r 9.6.16 (Reference Celeted) t l 9.6.17 Se:tien 9.2.5 l T 1 i i i 1 \\ r - 120 - l l \\ l 1
CALLAWAY PLANT CTFSITE DOSE CALCULATION MANUAL Rev. 5 9.6.18 Section 9.2.7.2.1 9.6.19 Section 6.3.2.2 9.6.20 Table 11.1-6 9.6.21 Tab's 9.4-6 9.6.22 Table 1.4-8 9.6.23 Table 9.4-11 ) 9.6.24 Table 9.4-12 l 9.6.25 (Reference Deleted) i 9.6.26 . ble 2.3-68 9.7 Union Electric Company Callaway Plant Environ-mental Report, Operating License Stage. 9.7.1 Table 2.1-19 9.7.2 Section 2.1.2.3 9.7.3 (Reference Celeted) 9.7.4 Section 2.1.3.3.4 9.7.5 (Reference Ooleted) 9.7.6 Section 5.2.4.1 l 1 9.7.7 !able 2.1 19 l 9.3 U.S. Nuclear Regulatory Cce. mission, "Preparatten of Radiological Iffluent Technt-cal Specif; cati n Ter Nuclear Power Plants", US!;EO UUREG-0133, Wa shingt:n 3.C. 20555, oc-
- ber 1978.
9.6.1 Pages AA-1 th. ugh AA-3 9.S.2 Se:::cn 5.3.1.3 - 101 - l
1 '.6 i CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAT. Rev. 5 i 9.8.3 Section 4.3 9.8.4 Section 4.3.1 9.8.5 Section 5.3.1.5 9.8.6 Secticn 5.1.1 9.8.7 Section 5.1.2 i 9.8.8 Section 5.2.1 9.8.9 Section 5.2.1.1 9.8.10 Section 5.3.1 9.8.11 Section 3.8 1-9.c 12 Section 3.3
- 'i 4
9.9 U.S. Nucinar Regulatory Commission, "XOQDOQ, i Program For the Meterological Evaluation of Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington, D.C. 20555. 9.9.1 Pages 19-20 Subroutine PURGE 9.10 Regulatory Guide 1.111, "Methods For Esti'.nat-ing Atmospheric Transport And Dispersioa of 2 Gaseous Effluents In Routine Releases From } Light-Water-Cooled Reactors", Revision 1, U.S. Nuclear Regulatory Commission, Washington, ) D.C. 20555, July, 1977. I 9.10.1 Section col.b P [ 9.*0 2 (Reference Deleted) l 9.10.3 Figures 7 through 10 l 9.10.4 (Reference Deleted) ,1 9.10.5 Section c.4 l \\ i - 102 - i l
i CALLAWAY PLANT '0FFSITE DOSE CALCULATION MANUAE. Rev. 5 9.11 Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Com-I pliance With 10 CFR Part 50, Appendix I", Revision 1, U.S. Nuclear Regulatory Commis-sion, 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 l 9.11.4 Appendix E, Table E-11 l 9.11.5 - Appendix E,' Table E-9 I 9.12 U.S. Nuclear Regulatory Commission, "Methods for Demonstrating LWR Compliance with the EPA t Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C. 20555, January 1980. 9.12.1 Section I, Page 2 9.12.2 Section IV, Page 8 9.12.3 Section IV, Page 9 9.12.4 Section III, Page 6 i 9.12.5 Section III, Page 8 l 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 i 9.15 (Reference Deleted) i - 103 - l
yl, e CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL Rev. S 9.16 Miscellaneous References 9.16.1 Drawing Number M-109-0007-06, Revision S. F 9.16.2 HPCI 87-01, "Determination of Annual Average Dispersion Parameters at the owner Controlled Area Fence", January 28, 1987. 9.16.3 HPCI 87-02, "1986 Land Use Census and Disper-sion P-smeters", January 28, 1987. l 9.16.4 UE Sa:,ry Analysis Calculation 87-001-00. i I 9.16.5 UE Safety Analysis Calculation 88-002-00-F. 9.17 U. S', Nuclear Regulatbry Commission, "XOQDOQ: Computer Program for the Meterological Evalua-t i tion of Routine Effluent Releases at Nuclear Power Statior.s", USNRC NUREG/CR-2929, Septem-ber, 1982, Washington, D.C. 20555. l 9.17.1 (Reference Delted) [ l 9.17.2 (Reference Deleted) I j l 9.17.3 (Reference Deleted) i I j 9.17.4 Section 4, "Subroutine PURGE", pages 27 and i l 28. l 9.18 Regulatory Guide 4.13, "Performance, Testing, l and procedural specifications for Thermolumin-l l 1 sconce Dosimetry: Environmental Applications l l "(Revision 1), July 1977; USNRC, i Washington, D.C. 20555 i i 4 l 9.19 TID-7004, "Reactor Shielding Design Manual", 1 Rockwell, Theodore, ed; March 1956. l 9.00 SNWL-236, "ISOSHLD - A computer code for Gen-I eral Purpose Isotope Shielding Analysis", l
- Engel, R.C.,
Greenberg, J., Hendrichson, M.M.; l June 1966. j I t 104 - l h I
=. - - CALLAWAY PLANT OFFSITE DOSE CALCULATION I MANUAL Rev. 5 9.21 BNWL-236, Supplement 1, "ISOSHLD-II: Code Revision to include calculation of Dose Rate l from Shielded Bremsotrahlung Sources", l
- Simmons, G.L.,
et al; March 1967. l 9.22 BNWL-236, Supplement 2, "A Revised Photon Pro-l bability Library for use with ISOSHLD-III", l
- Mansius, C. A. ; April 1969.
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