ML20059G508
| ML20059G508 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/31/1990 |
| From: | Baxter J UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20059G503 | List: |
| References | |
| APA-ZZ-01003-01, APA-ZZ-1003-1, NUDOCS 9009130006 | |
| Download: ML20059G508 (198) | |
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u APA-ZZ-01003 OFFSITE DOSE CALCULATION MANUAL i 4 -
,I The, attached is-a complete copy of the Offsite m
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Calculation Manual, -APA-ZZ-01003, Revision'0, May, 1990. 1 o.
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APA-ZZ-01003; 1 lj ,- OFFSITE-DOSE CALCULATION MANUAL': I 1
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I' i s- \ > i ( Thi's procedure contains the;following: _, / Pages 1 through 191 .) L, Attachments thrtagh '
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L Tables 1 through 12-p4s I/1.i Figures 4 through 5 c, n hlh ' Appendices .through .' i,, , , l PT.. " Checkoff Lists through yt i i - INFORMAT., ION ONLY JNCON"R0__D
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h j.Hw c Table'of' Contents-
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j k" 1 Section 'Page Number. t ' n: '1.0L , Purpose and Scope ? 1
'n 2.0 Liquid Effluents . 1 !
2.1 Radioactive Effluent Controls (REC) Section : 9.1.1.1 1-2.2 . Liquid Effluent Monitors 2. 2.3 Calculation of Liquid Effluent Monitor:Setpoints. 5. M 2.4' Liquid Effluent Concentration Measurements- 11' l2.4.1- REC Section 9.3.1.1 11' ~!
- 2.4.2 Liquid Effluent Concentration Measurements- 11 2.5 Dose Due to Liquid Effluents -12 2.5.1' . REC Section 9.4.1'.1 12 2.5.2 The Maximum Exposed Individual 12 '
'2.5 3- Calculation of Dose from Liquid Effluents '13 t t 2. 5. 4 - Summary, Calculation of Dose Due to i lF. Liquid Effluents 15 y; , .2.6 Liquid Radwaste Treatment System 19 '
l-L 2.6.1 RECESecticn 9.5.1.1 19 12.6.2- Operability.of'the Liquid Radwaste Treatment y' . > . j System,
.20 , l L 4 l 3.0 Gaseous Efflue'nts 21' 3.1 . REC Section'9.2.1.1 21 3.2 REC Section 9.16.1.1 21 u
.'" -3. 3~ Gaseous Effluent Monitors 2 11 3
' Calculation of Gaseous Effluent Monitor
^3.4 !
Setpoints. 25 , [{f
- 3.4'.1 Total Body Dose Rate Setpoint Calculations 26:
3 '. 4: . 2 Skin, Dose Rate Satpoint Calculations- 28 3.4.3 Gaseous Effluent Monitors Setpoint' Determination 30 >
, 3.4.4 Summary,. Gaseous Effluent Monitors Setpoint .
Determination '32* i3.5 Calculation of Dose from Gaseous Effluents 32
-3.5.1 Calculation'of Dose Rate 32 l 3.5.1.1' Noble:. Gases 32 3.5.1.2 -Radionuclides Other Than' Noble Gases 34- '
- 3.5.2 -Individual Dose Due to Noble Gases 39 3; , 43.5.2.1 REC'Section 9.7.1.1 39 j 4' 3.5.2.1.1 Noble Gases 40 :!
E3.5'.2.2- REC.Section 9.8.1.1 42 , j: ' L3.5;2'.2.1 Radionuclides Other Than Noble Gases 42 , g L3.6 Gaseous.Radwaste Treatment System 77 ; REC;Section 9.9.1.1 77
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Table of Contents '
- j. s Section Page Number 3.6.2 Descript.an of the Gaseous Radwaste o Treatment _ System .
77 l 3. 6. 3_ Operability of the Gaseous _Radwaste
' Treatment System 77 4.0 pose-and Done Commitment from Uranium Fuel 1
- Cycle Sources '78 g,
L 4.1 REC.Section 9.10.1.1 78 4.2 Calculation of Dose and Dose Commitment-from Uranium _ Fuel Cycle Sources 78 4.2.1. Identification of the MEMBER OF THE PUBLIC 80 h 4.2.2
Total Dose-to the Nearest Resident 60 4.2.3 Total Dose to the Critical Receptor Within 81 the SITE BOUNDARY
;- 5.0_ Radiological Environmental Monitoring 86 15 . 1 REC Section 9.11.1.1 86
-5.2 Description of the Radiological Environmental
.A Monitoring Program 86
?" . 5.3 Performance Testing of Environmental Thermoluminescence Dosimeters 87 '
6.0 Determination of Annual Average and Short Term Atmospheric Dispersion Parameters 105 6.11 . Atmospheric Dispersion Parameters 105 6.1.1 Long-Term Dispersion Estimates 105 6.1. 2 " Determination of Long-Term Dispersion Estimates for_Special Receptor _ Locations 106 6.1. 3; Short-Term Dispersion Estimates 106 7.0- Semi-Annual Radioactive Effluent Release Report 114
- 8.0' Implementation of ODCM Methodology 120 4 9.0 Radioactive Effluent Controls (REC) 121 9.1 Radioactive. Liquid Effluent Monitoring Instrumentation 123 Radioactive Gaseous Effluent Monitoring 9.2 Instrumentation 130 x 9.3 Liquid Effluents Concentration 138 9.4 Dose 144 9.5- Liquid Radwaste Treatment System 146
- 9.6 Gaseous Effluents Dose Rate 148
; 9.7 Dose-Noble Gas 154
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; 9.8- Dose-Iodine-131_and 133, Tritium, and
- j. Radioactive Material in Particulate Form 156 19 . 9 Gaseous'Radwaste Treatment System 158 9.10 Total Dose 160 9.11 Radiological Environmental Monitoring Program 164 9.12 Radiological Environmental Monitoring Land Use Census- 180
[ 9.13 Radiological Environmaatal Monitoring Inter-l laboratory Comparison Program 183
! 10.0 Administrative Control 184 10.1 Major Changes to Liquid and Gaseous Radwaste Treatment Systems 184 10.2 Changes to the offsite Dose Calculation Manual (ODCM) 185, 11.0 References 186
- Figure 4.1 Site Area Closed to Public Use 85.
Figure 5.1A Airborne & TLD Sampling Network 100 ' Figure 5.1B Airborne & TLD Sampling Network 101 L Figure 5.2A. Location of Aquatic Sampling Stations 102 Figure 5.23 Location of Aquatic Sampling Stations 103 Figure 5.3 Food Products Sampling Locations 104 1 l l l l a a i
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Table of Contents Section Page Number
- Table.1 Ingestion Dase Commitment Factor (Ag ,) for idult Age Group 16-17 Table 2 Bioaccumv.lation Factor (BFg ) Used in the Absence of Site-Specifi>. Data 18 Table 3 Dose Fa<: tors for Expos" a to A Semi-Infinite-
. Cloud of Noble Gases 31 Table 4 Dose Parameter (Pg ) . tor Radionuclides Other Than Noble Cases 36-38 Table 5 Pathway Dose Factors (R g ) for Radionuclides other Than Noble ca es 46-76 Table 6 Radiological Envirenmental Monitoring Program 88-95 Table 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 96 Table B Maximum Values for the Lower Limits of Detection 97 Table 9 Highest Annual Average Atmospheric Dispersion Parameters - Radwaste Building Vent 110 Table 9.1-A Radioactive Liquid Effluent Menitoring Instrumentation 125-127 .
Table 9.1-B Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 128-129 Table 9.2-A Radioactive Gaseous Effluent Monitoring Instrumentation 132-134 Table 9. 2-B Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 135-137 Table 9.3-A' Radioactive Liquid Waste Sampling and Analysis Program 140-143 Table 9.6-A Radioactive Gaseous Waste Sampling and Anslysis Program 150-153
' Table 9.11-A Radiological Environmental Monitoring Program 168-174 Table 9.11-B Reporting Levels for Radioactivity Concentrations In Environmental Samples 175 Tablo 9.11-C Detection Capabilities for Environmental Sample Analysis 176-179 Table 10 Highest Annual Average Atmospheric Dispersion Parameters - Unit Vent 111 Table 11 Short Term Dispersion Parameters 112 Table 12 Application of Atmospheric Dispersion Parameters 113
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Rov. 0 1 Socord of Revisions R;v. 6- May 1989 Revised methodology'for calculating. maximum permissible liquid effluent discharge rates and liquid effluent monitor setpoints, provided methodology for calculating liquid effluent monitors response
.. correction factors, provided an.
-enhanced description of controlsLon.
liquid monitor background limits, provided additional liquid & gaseous dose conversion factors ~and bioaccumulation factors (Tables 1, 2, 4 & 5), provided description of
- the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added.
discussionfof gaseous & liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Wasta Gas . Decay Tanks, revised dispersion' parameters & accompanying description per FSAR Change Notice,88-42.
' APA-ZZ-01003 August 1989 Radiological Effluent Technical Rov. O. Specifications were moved from the Callaway Plant Standard Technical.
Specifications to Section 9.0, Radioactive Effluent Controls, of 1 the ODCM as per NRC Generic Letter b 89-01. At the same time, in order
'- 4 to formalize control of the entire ODCM, it was converted to APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL.
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, 1.0 PURPOSE AND SCOPE i
1.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from-
. radioactive gaseous and liquid.effluer.ts, in the calculation of gaseous and liquid effluent -
monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM also contains the
. Radioactive-Effluent Controls and Radiciogical Environmental Monitoring Programs required by Technical Specification 6.8.4, and descriptions of the information that should be included in the Annual: Radiological Environmental Operating and
- Semi-annual Radioactive Effluent Release Reports reqcired by TechnicaA Specifications 6.9.-l.6 and 6.9.1.7. The ODCM also contains a list and c 'm description of the specific sample locations for the radiological environmental-monitoring .
program. 2.0 LIQUID EFFLUENTS 2.1 RADIOACTIVE EFFLUENT CONTROLS (REC) SECTION 9.1.1.1 41838 The radioactive liquid effluent monitoring instrumentation channels shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 9.3.1.1 are not exceeded. The 41840 alarm / trip setpoints of these channels shall be adjusted to the values determinad in accordance with the methodology and paramet.ers in the ODCM. 2. 1
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k; ' APA-ZZ-0.1003 I Rav.-0 I. l ( 2.2 Liquid Effluent Monitors e 4,, , 3 Gross radioactivity monitors which provide for Q automatic termination of liquid _ effluent releases ll are present on the liquid effluent lines. rate measurement devices are present on the Flow liggid effluent lines and the discharge line. y (cooling tower blowdown). Setpoints, h , precautions, _and limitations applicable to the O operation of the Callaway Plant liquid effluent 1 monitors - are provided .in tlut appropriate Plant i4-Procedures.- Setpoint values?are calculated to
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assure that alarm and trip actions occur prior.to exceeding the Maximum Permissible Concentration (MPC)the point.to limits in 10 CFR Part UNRCSTRICTED 20 at the release AREA.. The calculated alarm and trip actionisetpoints for the liquid y effluent line monitors and flow measuring devices nuct: satisfy the following equation: 9 1 . 1
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< C F+f (2.1) ,
Whores C= the liquid effluent concentration limit
- (MPC) implementing Section 9.3.1.1 for the site in (uci/ml).
e= The setpoint, in (uci/ml), of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint,
, related to the volumetric flow of-thewhich is inversely effluent line and directly related to the volumetric flow of the dilution stream plus the effluent stream, represents a value, which, if exceeded, would result in concentrations exceeding the limits of 10 CFR Part 20 in the UNRESTRICTED AREA.
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i f= The flow setpoint as measured at'the ] radiation monitor location,.in. volume per j unit time, but in the same units as F, ! below. ) i 1 F= The dilution water flow setpoint as ! i L ' measured prior to:the release point,' in volume per. unit time. (If (F) is large i compared to (f), then F + f = F). i . (Ref. 11.8.1) p , If no dilution is provided,. then c 5 C. The radioactive liquid warce_ stream is diluted by 1 the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is " 1 obtained from the cooling tower blowdown, but j should this become unavailable, the-plant water . treatment facility supplies the necessary 1 dilution flow via.a bypass line. The batch i release limiting concentration-(c) which corresponds to the. liquid.radwaste effluent line ;
,' monitor setpoint is to be calculated using l methodology from'the expression above. '
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I Thus, the expression for determining the setpoint h o on the liquid radwaste effluent line monitor [; A<, becomes: L' j c$ C(F + f) (vCi/ml) lt f (2.2) SL. . f The alarm / trip setpoint calculations are based on-the minimum. dilution flow rate (cooling tower blowdown, 5000 gpm), the maximum effluent stream flow rate, and the actual isotopic analysis. Due . U to the possibility of a simulataneous release , from more than one release pathway, a portion of the total site release limit is allocated to each
. pathway. The determination and usage of the-allocation factor is discussed in Section 2.3.
, In the event the alarm / trip setpoint~1s. reached, f"
an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis.to ensure that Section 9.3.1.1 limits were not exceeded. , i 2.2.1 Continuous Liquid Effluent Monitors - I The radiation-detection monitors associated with
. continuous liquid affluent releases are (Ref. ;
11.6.1, 11.6.2): ; Monitor I.D. Description 7 BM-RE-52 1 Steam Generator Blowdown Discharge Monitor j LE-RE-59 Turbine Building Drain : Monitor b
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, .a l. These affluent streams'are not considered to be
- 1 radioactive unless radioactivity has been ! detected by the associated effluent radiation monitor or by laboratory analysis. The. sampling 3
frequency, minimum' analysis frequency, and type an of analysis performed are as per Table 9.3-A.
' Since the Turbine Building Drain is not a
, designated liquid radioactive affluent discharge l' point, its setpoint is established as a function of background.
2.2.2 . Radioactive Liquid Batch Release Effluent Monitors The two radiation monitors which are associated with the liquid effluent batch release systems are (Ref, 11.6.4, 11.6.5):
) MONITOR I.D. Description i-EB-RE-18 Liquid Radwaste Discharge
. Monitor-r, HF-RE-45 Secondary Liquid Waste. ,
System Monitor LThese s! fluent streams are normally considered to be radioactive. The: sampling frequency, minimum
, analysis frequency, and the type of analysis performed are as per Table 9.3-A.
L 2.3 calculation of Liquid Effluent Monitor Setpeints The dependence of the setpoint (c), on the radionuclide distribution, yields, calibration, and monitor parameters, requires daat several variables be considerec in setpoint calculations. (Ref. 11.8.1) - II r 1 I y 5 s I m & 9*-
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- 2.3.1 Calgu_lation of the MPC Sum .i I
The isotopic concentration of the release (s) being considered must be determined. This is > obtained from the analyses required per Table 9.3-A,.and is used to calculate an MPC sum
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(MPCSUM): : i s,, MPCSUM = .
-(I(C 9)g/(MPC g)g)+(C,/MPC,)+(C,/MPC,)+(C /MPC t g)+(C g/MPCg) (2. 3 ).
i' Where I (Cg )g = - the concentration (C )g of eachLmeasured j gamma emitting nuclide, 1, observed by 4- gamma-ray spectroscopy of the waste =; sampte. ., , C,* = the measured concentration (C,) of alpna ' emitting nuclides observed by gross alpha ' analysis.
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C,* = the measured concentrations of Sr-89 and -
+
Sr-90 as determined by analysis of the quarterly composite sample, , l Ct * = the measured concentration of H-3 in liquid , effluents. Cf * = the measured concentration of Fe-55 in liquid waste as determined by analysis of the quarterly composite sample. ,
- Values for these concentrations will be based on ;
previous composite sample analyses as required by Table 9.3-A. , t ( *r ( b _ , .. . . , e
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R0v. O i k ' i 3 J. - . ! i MPCg, MPC,, MPC,, MPCg, MPC t = are ths limiting I concentrations'of the appropriate radionuclides ! 4 from 10CFR 20,' Appendix-B, Table II,. Column 2. ! For dissolved or entrained noble gases, dua 4" cencontration shall be ' limited to 2x10~' VC1/mi ) ' total activity, j n- SF = the safety factor; an administra;ive factor O.c used to compensate for statistical j l' , fluctuations and errors.of measurements. l This factor also.provides a margin of. !
!L safety in the calculationoof the maximum
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[,' liquid affluent discharge flowrate (f,,x). ') E, The value.of SF should be <1. ! 1
' For the case lMPCSUM $ 1, the monitor tank . 1 effluent concentration meets the limits of ;
r' ..Section 9.3.1.1Lwithout dilution and the effluent may be released at any desired flow rate. If- ) MPCSUM > 1 then dilution is required to ensure 2 f compliance with Section 9.3.1.1' concentration limits.- If' simultaneous releases are occuring or l l + are anticipated, an allocation fraction, N, must t l be applied so that available dilution flow may be ., '1 apportioned among simultaneous discharge J pathways. The value of N may be any value ; between 0 and 1 for a particular discharge point! ,
, provided:that the sum total allocation fractions for all discharge-points must be $_1.
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1 l: 2.3.2 Calculation of the Maximum Permissible Liquid ! y' Effluent Discharge Flowrate 3 The maximum permissible liquid effluent discharge l flowrate is calculated;by: pj fmax 5 (F + f ) p(SF)~(N) + (MPCSUM) (2.4) hp Where: R , lj g ' f = Maximum permissible liquid affluent' max j e ' discharge ~flowrate, in (gallons / minute); f = the expected undiluted liquid effluent l p 1 flowrate, in gpm. A. N= the allocation fraction which apportions' i g dilution flow among simultaneous discharge i q' pathways (see discussion above) ; +, F, SF, & MPCSUM, are as previously defined. The minimum value of F is-5000 gpm, which is used ., as a default value. The dilution water supply is , l: ftenished with a flow' monitor which isolates the. l L liquid effluent discharge if the, dilution flow
, rate falls below the 5000 gpm minimum value. ;
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} In the event that f,,x is less than f p, then the f value of f,,x.is substituted into.the equation jl 7 for f p and a new value of f,,x is calculated. This substitution is performed for three iterations in' order to calculate the correct value of f,,x. >. 1 hl ). .O. b i 3- . s- - %. .cs : ..-.: M W q e t N- . .
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'2.3.3 Calculation of Liquid Effluent Monitor Setpoint The liquid effluent monitors are NaI(Tl) based systems and respond primarily to gamma radiation.
Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides.in the effluent: e = BKG + (I(Cg)g + SF) pCi/ml (2.5) i
.Where:
c= the monitor setpoint as previously defined, in (vCi/ml); BKG = the monitor background prior to discharge, in ;(vCi/ml) ; C g and SF are as previously defined. The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity. Utilizing the methodology of ANSI N13.10-1974-
-(Ref. 11.21), the background must be maintained-at a value of less than or: equal to 2.23E-6 vCi/mL (relative to Cs-137) in order.tct detect a change of 1E-7 VCi/ml of I-134 (the most restrictive nuclide in Table 1 of reference 11.21).
In the event that there is no detectable gamma activity in the effluent or if the value of-(I(Cg)g+SF) is less than the background of the monitor, then the monitor.setpoint will be set at twice the current background of the monitor.
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El APA-ZZ-01003-7 . R;v. O 1 j ('. j l As previously stated, the monitor's response is j dependent on the gamma emitting radionuclide ! distribution of the effluent. Accordingly,. a new f database conversion factor is calculated for each release based upon the results of the gamma
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spectrometric analysis'of the. effluent sample.and j the measured response of the monitor to the ! 4 National Bureau of Standards (NES) traceable f 1 calibration sources: i 9
;. DBCF, = (I(C )g g )+ (CMR) x (ECF) _(2.6) !
l Where: , e DBCF c
= the monitor data base conversion factor ;
- f. which converts count rate into l j concentration (yCi/ml);
H i , r:m CMR = the calculated response of the radiation monitor to the liquid effluent; , ECF = the conversion factor for Cs-137, which converts count rate into concentration ll. (pci/ml). L } C 9 isLas previously defined. l [ The new value of the DBCFe is calculated and entered into the monitor data base prior to'each discharge. A more completa discussion of-the derivation and calculation of the CMR is given in - reference 11.14.7. ' 1 > 1 j. p. ~ 5 g u-j ) 1-1- i i
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- 2.4 Liquid Effluent Concentration Measurements i'
'41846 2.4.1 REC Section 9.3.1.1 4160
- The concentration of radioactive material
[ released in liquid affluents to UNRESTRICTED AREAS shall be limited to the concentrations 3 specified in 10 CFR Part 20,-Appendix B, 1 - Table II, Columu 2 for radionuclides other than
, dissolved or entrained noble gases. For I dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 vCi/ml total activity.
L 2.4.2 Licuid Effluent Concentration Measurements-Liquid batch releases-are discharged as a e discrete volume and each release is authorized j based upon the sample analysis and the dilution
, flow rate existing in'the discharge line at time j- of release. To assure representative sampl-ing, each. liquid monitor tank is isolated and
, se thoroughly mixed by recirculation.of tank contents prior to sample collection. The methods ,
for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures. The. allowable release rate limit is calculated for each batch based upon the pre-release analysis, dilution flow-rate, and other procedural
._ conditions, prior to authorization for release.
The radwaste liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm / trip
- setpoint is exceeded. Concentrations are determined primarily from the gamma isotopic, H-3, & gross alpha analyses of the liquid batch sample. For Sr-89, Sr-90, & Fe-55, the measured
- concentration from the previous composite h analysis is used. Composite samples are collected for each batch release and quarterly analyses are performed in accordance with Table 9.3-A.
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APA- Z-01003 R;v. 0 l' Doses from'l'i quids discharged as continuous releases are calculated by utilizing the last measured values of samples required in accordance with Table 9.3-A. 2.5 Dose Due to Liquid Effluents l j 141849 2.5.1 REC Section 9.4.1.1 4160' L . The dose or dose commitment to a MEMBER'OF THE l PUBLIC from. radioactive. materials in liquid effluents released, to UNRESTRICTED AREAS shall be limited:
- a. During any calendar quarter to less than or h; equal to 1.5 mrem to the whole body and less 4
than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal-to 3 mrom to the total body and to less than or equal to 10 mrem to any organ.
2.5.2 The Maximum Exposed Individual 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 exposed individual. (Ref. 11~.8.3) The Callaway Plant's liquid effluents are
- discharged to the Missouri River. As there are l no potable water intakes within 50 miles of the I discharge point (Ref. 11.7.1, 11.6.6),_this l pathway does not require routine evaluation.
l Therefore, the_ dose contribution'from fish (' consumption is expected to account for more'than 95% of the total man-rem dose from discharges to l the Missouri River. Dose from recreational activities-is expected to contribute the X additional 5%, which is considered to be (Ref. 11.6.7) negligible. l l-I l- 7. I
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r are calculated at least once each 31 days and a -l J[' cumulative summation of the total body and. _
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individual organ doses is maintained for each ,
. calendar quarter. These dose contributions are 6
- calculated for all radionuclides identified in ;
liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref. 11.8.3). > 4 j.
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$' 94 , g D, = I ( Ag , I Atg C gg F) g (2.12)' [ 1 4 l; t=1 '
'f j: Where:
l D t = the cumulative dose commitment to the total
- body or any organ, t, from the. liquid ' '
effluents for the total period i
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J' APA-ZZ-01003: p[g Rov. O f ;_;; 1 4 Atg = the length of the Eth time period over which Cgg and Fg are averaged for all liquid releases, in hours. Atg. corresponds to the actual duration of the release (s). C3g = the average measured concentration of radionuclide, 1, in undiluted liquid-effluent during time period At g from any 1iquid release, in (vCi/ml). Ag , = the site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma end beta emitter listed in Table 9.3-A, (in mrom/hr) per (VCi/ml). The calculation of the A gg
. values is detailed in Ref. 11.14.5 and are given in Table 1.
rn Ft = the near field average dilution factor for 3 -C gg during any liquid effluent release. . I I t= max
. (F + f,,3) 89.77 Where:
f,,x = maximum undiluted effluent flow rate during the release F= average dilution flow 89.77 = site specific applicable factor for the mixing effect of the discharge structure. (Ref 11.5.1) The term C gg is the undiluted concentration of i radioactive material in liquid waste at the common release point determined in accordance c with-Section 9.3.1.1, Table 9.3-A, " Radioactive Liquid Waste Sampling and Analysis Program". All
; dilution factors beyond the sample point (s) are 1 included in the Fg term.
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. The nearest municipal potable water intake downstream from-thefliquid' effluent discharge point into the Missouri River is located near the city of St. Louis, Mo., approximately 78 miles downstream. As there.are currently 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. 11.6.6). 1 2.5.4 Summary, calculation of Dese Due to Liquid i Effluents , The dose contribution for the total time period l 9 m Iat g j t=1 is determined by calculation at least once per 31' ) days and a cumulative summation of the~ total body j and organ dosos is maintained for each calendar quarter. The projected dose contribution from ! liquid effluents for which radionuclide i concentrations are' determined by periodic ! composite and grab sample analysis, may.be approximated by using the last measured value. j
- Dose contributions are' determined for all i radionuclides identified 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 Lower Level of Detection (LLD) level.for that nuclide. The "less than" values are not used in the required dose calculations. i i , 'O
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. TABLE 1 INGESTION DOSE COMMITMENT TACTOR (Ap ) TOR ADULT AGE CROUP l4 (aram/hr) per (sci /al) '
t
'l i l l Total- l =l l l l 'l' lNuclidel Bona l liver I Body I Thyroid 1 Kidnev l Lunt 1 GI+LE! I lH3 lNo Data l2.26E+01 l2.26E 01l2.06E 01 l2.26E*01l2.26E+01l2.26E 011 s l Be*7 ll.30E+0212.98E 02 11.45E 02lNo Data. l3.15E-02lNo Data 15.16E+001-l C 14- 13.13E+0416.16E+03 l6.26E+03l6.26E+03 l6.26E+03l6.26E+0316.26E+03l ;
l Na 24 14.07E+02l4.07E+02.l4.07E+0214.07E+02 14.07E+02l4.07E+0:l4.07E+02 I P 32 14.6E+0712.87E+06 l1.78E+06lNo Data lNo Dats lNo Data l5.19E+06 I I Cr*51 lNo Data (No Data 11.27E+0017.6:E*01 l2.81-01 l1.69E+00l3.20E+02l c Mn 54 lNo Data 14.38E+03 l8.35E+0:No Data l1.30E+03lNo Data 11.34E+04l l Mn+56 lNo Data l1.10E+0: 11.95E+01 hs Data l1.40E+0:lNo Data l3.52E+031 , Te 55 16.57E+0:14.54E+02 l1.06t+02 'o Data INo Data l2.53E+02l2.61E+021 i l To 59 l1.04E+03l:.44E+03 19.34F.*aS Go Data INo Data 16.81E+0:18.13E+031 r l Co 57 lNo Dats l:.09E+01 13.48E+01lNo Data lNo Date lNo Data lt.31E+021 ' l Co 58 the Data 18.94E+01 12.00E+02lNo Data lNo Data INo Data 11.81E+03
- j l Co*60 (No Data 12.57E+02 l5.66E+02lNo Data lNo Dats lNo Data 14.82E+03 I Ni-63 13.11E+04l2.15E+03 l1.04E+03lNo Data lNo Dats lNo Data 14.49E+021 f, 1 Ni 65 11.26E+02' 64E+01 l7.48E+00lNo Data INo Data lNo Data 14.16E+02; l Cu 64 INO Data 1.00E+01 14.69E+00lNo Data l .52E+01lNo Data I8.5:E+02!
L: a. l Zn-65.10.3 E+f 7.38E+04 l3.33E+04lNo Data l4.93E+04lNo Data 4.65E+04' l In 69 l4.93E+ 1l9.44E+01 16.56E+00lNo Data. 16.13E+011No Data 1.42E+01l i l Br 82 (No Data lNo Data l2.27E+03lNo Data (No Data lNo Data 2.60E+03] ,
. I Br*83 lNo Data lNo Data l4.04E+01lNo Dats lNo Data lNo Data l$.81E+01l -
l Br-84 lNo Data (No Data 15.26E+01tNo Date lNo Data lNo Data l4.13E-041 l Br 65 lNo Data lNo Data l2.15E+00lNo Data [No Data INo Data l 0 ' l Rb 66 lNo Dats l1,01E+05 l4.71E+04lNo Data INo Dats lNo Data l1.99E+04 l; = l Rb 88 lNo Data 12.90E+02 l1.54E+02lNo Data lNo Data lNo Date l6.00E 09 l Rb 89 lNo Data l1.9:E+02 11.35E+02lNo Data INo Data (No Data 11.1:E.11 l St 89 12.21E+04)No Data l6.35E+02 No Data lNo Data lNo Data I3.55E+03l
-l Sr 90 15.44E+05lNo Date l1.34E+05 No Data lNo Data lNo Data l1.57E+04l F l Sr 91 14.07E+02lNo Data 11.64E+01lNo Data lNo Deta lNo Data 11.94E+03l l Sr 92 11.54E+02tNo Data !6.6BE+00lNo Data INo Data lNo Data l3.06E+03l l Y.90 15.75E 011No Data 1.54E*02lNo Data lNo Data lNo Data 16.10E+03l l Y 91M l5.44E 031Mo Data 12.10E*04]No Data lNo Data lNo Data 11.60E 021 l l Y 91 l8.43E+00lNo Data 12.25E 01]No Data lNo Data lNo Data l4.64E+03) l Y 92 15.0$E 02lNo Data 11.48E-03lNo Dats lNo Data lNo Data l8.85E+02l
[ l Y 93 11.60Er01lNo Data l4.42E 03lNo Data lNo Data INo Data 15.08t+03 , J l Zr 95 12.40E 0117.70E 02 15.21E 02lNo Data 11.21E 01lNo Data l2.44E+02 [ l Zr 97 l1.33E 0:l .68E-03 11.22E 03lNo Data 14.04E 03tNo Data '8.30E+021 ' j Nb*95 14.47E+02l .48E+0: l1.34E+0 lNo Data l2.46E+02lNo Data 1.51E+06l Ho 99 lNo Data l1.03E+02 l1.96E+01lNo Data 12.33E+02lNo Dats 2.39E+02l Tc-99Ml8.87E-0312.51E-02 13.19E 01lNo Data 13.81E=01l1.23E-02il.48E*01l Tc.10119.11E 03l1.31E 02 l1.09E-01lNo Data 12.36E*01l6.70E 03l 0 I 0 l Ru 103l4.4 E+00lNo Data 11.90E+00lNo Data 11.6$E+01lNo Data l5.1*E+021
, l Ru 10$l3.68E 01lNo Data l1.45E 01lNo Data l4.76E+00lNo Data 12.05E+0:l l Ru 10el6.57E+01lNo Data 18.32E+00lNo Data 11.27E+02lNo Data l4.25E+031 s .'A l Cd 109lNo Data l5.54E+02 11.94E+011No Data 15.31E+02lNo Data 15.59E+03l a W*d l Sn M 315.66E4 l1.61E3 l3.26E3 l9.18E: lNo Data (No Data l1.69E3 l l Sb :;el6.69E+00l1.26E 01 12.65E+00l1.62E 02 !No Data l5.21E+00ll.90E+02l 1
r . 16 , b ,. . L . ._ _ ., .
u e >%.m Rev. O { ) h n , TABLE 1 (Continued) INGESTIONDOSECO.T!!D!r.NTTACTOR(Af)TORADULTAGEGROUP I ( (mrom/hr) per (vci/ml) l i l i Total l l l lNue11 del ?one ! Live r 1 Bede Thyroid i Kidney I Luna 1 07 Ltf
$b 125 l4.28E+00 4.78E 02 l1.02E+0014.35E 03 lNo Data l3.30E+00,4.71E+011 h
- To 125Ml2.57E+03 9.30E+02 13.44E+0217.72E+02 l1.04E+04lNo Data 1.02E+04l lTo 127Mj6.47E+03l2432E+03 l7.90E+02l1.66E+03 12.63E+04lNo Data 2.17E+041-h" ; lTo 127 11.0$E+0213.78E+01 12.28E+0117.80E+01 14.29E+02lt6 Data l 8.30E+03]
ri lTo 129 Mil.10E+0414.11E+03 l1.74E+03l3.78E+03 ja.60E+04lNo Data l5.54E+04l lTe-129 l3.01E+0111.13E+01 l7.33E+0012.31E+01 l1.26E+02lNo Data 2.27E+01l ITe 131Mll.66E+0318.09E+02 l6.75E+02l1.28E+03 18.21E+03lNo Data .8.03E+041=
-lTe 131 l1.89E+01,7.88E+00 15.96E+00l1.55E+01 18.25E+01lNo Data ll2.67E+00l lTe 132 - l2.41E+03 1.56E+03 11.47E+03 l1.72E+03 l1.50E+041No Data 7.38E+04l.
lI 130 l2.71E*c118.01E+01 l3.16E+01!6.79E+03 11.25E+02lNo Data 6.89E+01l ll 131 1.49E+02l2.14E+02 l1.22E+02l7.00E+04 3.(6E+02lNo Data 15.64E+01
!! 132 7.29E+00ll.95E+01 16.82E+00l6.82E+02 3.11E+01lNo Data l').66E+00 11 133 5.10E+0118.87E+01 12.70E+0111.30E+04 1.55E+02lNo Data 17.97E+01 11 134 l3.81E+00ll.03E+01 l3.70E+00l1.79E+02 'll.64E+011No Data l9.01E 03l lI 135- l1.59E+01l4.16E+01 l1.54E+01l2.75E+03 l6.68E+01lNo Data 14.70E+01l s
4 lCs 134 l2.98t+0) '7.09E+05 15.80E+05lNo Data l2.19E+0517.62E+04l1.24E+04l lCs 136 l3.12E+04 1.23E+05 l8.86E+04lNo Data l6.85E+04l9.39E+0311.40E+04l ' lCs 137 13.82E+05 5.22E+05 13.42E+05lNo Data , 1.77E+05l5.89E+04l1.01E+041
- lCs 138 l2.64E+0215.22E+02 l2.59E+02lNo Data 3.84E+0213.79E+01l2.23E 031 lBa 139 l9.29E 01l6.62E-04 12.72E 02lNo Data 6.19E-04l3.76E 04l1.65E+00l lBo 140 1.94E+02 2.44E 01 11.27E+01lNo Data 18.31E 02l1.40E 01l4.00E+02l IBa 141 : 4.50E 01 3.40E 04 11.52E 02lNo Data 13.16E 0411.93E 0412.12E 10l
$ lBa 142 l 2.04E 0112.09E-04 11.28E 02lNo Data l1.77E-04l1.19E 04l 0 l @ ILa 140 'll.50E 0117.53E 02 11.99E 02lNo Data INo Data l H Data 15.53E+031 l lLa 142 17.65E 0313.48E 03 l8.66E 04lNo Data (No Data lh. Data 12.54E+01) ] lCo 141 l2.24E 0211.51E-02 1.72E 031No Data l7.03E 03lNo Data 15.78E+01l lCo 143 l3.94E 0312.92E+00 3.23E 04lNo Data- 1.28E-03lNo Data 1.09E+02l s lCo 144-l1.17E+00l4.8tE 01 6.26E 02 No Data 2.89E-01lNo Data . 3.94E+02l I lPr 143 l5.50E 01l2.21E-01 2.73E 02 No Data 1.27E 01]No Data ' 2.41E+03' ) i lNd 147 13.76E 0114.35E-01 l2.60E 02lNo Data 2.54E-01]No Data 2.09E+03 C leu 154 l3.67El l4.52I0 l3.21E0 INo Data l2.16El lNo Data l3.27E3 l lHf 181 13.99E 0211.94E 01 l1.80E-02lNo Data l4.17E-02lNo Data l2.21E+021 4 lV 187 12.96E+02l2.47E+02 18.64E+01lNo Data- lNo Data lNo Data 8.09E+04l lNp 239 12.84E 02l2.80E 03 11.54E 03lNo Data 18.72E 03lNo Data 5.74E+021 i-fa 5 g 1 { r 1
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APA-ZZ-01003 L . Rev. O , j- ,: '
. TABLE 2 BIOACCUMULATION FACTOR-(BF g ) USED IN M ' ABSENCE
.OF SITE-SPECIFIC DATA"
. (pCi/kg) per (pC1/11ter)
_BF g Element Fish (Freshwater) l H 9.0 E - 01 Be 2.0 E + 00 C 4.6 E + 03 L. Na' - 1.0 E + O2 P 1.0 E + 05 Cr 2.0 E + O2
.Mn 4.0 E + O2-y Fe- 1.0 E + O2 Co 5.0 E + 01
.Ni 1.0 E + O2 Cu 5.0 E + 01 l 2n 2.0 E +.03 Br 4.2 E + O2 Rb 2.0 E + 03 Sr 3.0 E + 01
~
Y. 2.5 E + 01 Zr 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 Cd 2.0 E + O2 Sn 3~.0 E + 03 y Sb 1.0 E + 00 al Te 4.0 E + O2
!! I 1.5 E + 01 I Ca 2.0 E + 03- [ Ba 4.0 E + 00 e La 2. 5 E + 01 l- Ce 1.0 E + 00 l- Pr 2.5 E + 01 ,
- p. Nd 2.5 E + 01 Eu 2.5 E + 01 Ef 3.3 E + 00 W 1.2 E + 03 ;
'Np 1.0 E + 01 L .
I (a) Values from Regulatory Guide 1.109, Rev 1, t Table A-1 and References 11.14.4 and 11.14.8. a , a E
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APA-ZZ-01003- ' s f: R;v, 0 Y .p _ - 2.6 LIQUID RADWASTE TREATMENT SYSTEM 4160. 2.6.1 REC Section 9.5.1.1 41851 L The LIQUID RADWASTE TREATMENT SYSTEM shall be
, OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid r effluent, to UNRESTRICTED AREAS, would exceed
- l. 0.06 mrem to the total-body or 0.2 mrem to any-organ in a 31 day period.
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p' - , AP 2-01003 { , j Rev. 0-i% L 2.6.2< OPERABILITY Of The LIQUID RADWASTE TREATMENT , SYSTEM P . The LIQUID RADWASTE TREATMENT SYSTEM is capable
; of varying treatment, depending on waste type and i' product desired. It is capable of concentrating, gas stripping, and distillation of liquid wastes through the use of the evaporator system. The , domineralization system is capable of removing h
radioactive ions from solutions to be reused as makeup water. Filtration is performed on certain t- liquid wastes and it may, in'some' cases, be the
~
only. required treatment prior:to release. The system 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 l! in liquid effluents will be kept "As Low As i Reasonably Achievable" (ALARA).
! @ The OPERABILITY of the LIQUID RADWASTE TREATMENT 4 SYSTEM ensures this system will be available for a use when liquids require treatment prior to their release to the envi*onment. OPERABILITY is demonstrated through compliance with Sections j; 9.3.1.1 and 9.4.1.1.
k Prcjected doses due to liquid releases to i UNRESTRICTED AREAS are determined each 31 days by i dividing the cummulative annual total by the
, number of elapsed months.
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a 2902 3.0 , GASEOUS EFFLUENTS [ (q i 41842 3.1 REC Section 9.2.1.1
'>4
- 4160 3
The radioactive gaseous 1effluer. mA- 2ng 1 instrumentation channels shall 'e 0? ALE with l' 4 their Alarm / Trip Setpoints set o ens.re that the limits of Section 9.' .1.1 are' no; ,x:: eeded. The ! 4 Alarm / Trip Setpoints of these channels shall be
, adjusted to the values determined in accordance ,
with the methodology and parameters in the ODCM. !
~
41853 3.2 REC Section 9.6.1.1
, i L 4160 The dose rate due to radioactive materials' I released in gaseous effluents from the site to l areas at and beyond the SITE BOUNDARY shall be j limited to the following: l f
4
- a. For-noble gases: Less-than or equal to 500 mrem /yr to the total body and less than or 1 h '
equal.to 3000 mrom/yr to the skin, and s
- b. For Iodine - 131 and 133, for tritium, and for ',.
i all radionuclides in particula.te form with ; half lives greater than 8 days: Less than or equal to 1500 mram/yr. to any organ,.from the- r inhalation pathway only. 4: P 3.3 Gaseous Effluent Monitors [ Noble gas activity monitors are present-on the L containment building ventilation system, plant ; L unit ventilation system, and radwaste building l ventilation system. t The alarm / trip (alarm & trip) setpoint for any gaseous effluent radiation monitor is determined
'=
based on the instantaneous noble gas total body and skin dose rate limits.of Section 9.6.1.1, at the SITE BOUNDARY location with the highest. ' annual average X/Q value. (Figure 5.1B)
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{ , V w l Each monitor channel is provided with a two level ; system which:provides sequential alarms on . [ increasing radioactivity levels. These setpoints
). are designated as-alert setpoints and alarm / trip ;
setpoints. (Ref. 11.6.3) ,
; The radiation monitor alarm / trip setpoints for l each release point are based on the rat's native .
; noble gases in gaseous effluents. It is :.ot -
. considered practicable to apply instantaneous' .
7 alarm / trip setpoints to integrating radiation monitors sensitive to radiciodines, radioactive
; materials in particulate form and radionuclides other than noble gases. Conservative assumptions ' , .may be necessary in establishing setpoints to account for system variables, such as.the. ' ^
measurement system efficiency and detection capabilities during normal, anticipated, and ;
- unusual operating conditions, the variability in
- p. release flow and principal radionuclides, and the ,
time lag between alarm / trip action and the final ya isolation of the radioactive effluent. (Ref. 4 - 11.8.5.) Table 9.2-B provides'the instrument , y surveillance' requirements,'such as. calibration, ., , L source checking, functional testing, and channel L checking. l 3.3.1 Continuous Release Gaseous Effluent Monitors The> radiation: detection monitors associated with' l continuous gaseous effluent releases are (Ref. ) 11.6.8, 11.6.9): Monitor 1.D. Description-l , GT-RE-21 Unit Vent h . GH-RE-10 Radwaste Building Vent ! J' Each'ofethe above continuously monitors gaseous + ', . radioactivity concentrations downstream of the last point of potential influent, and therefore T ' measures affluents and not inplant , a concentrations. . c , l'*'% T. 'I.
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b t .- i v . 11 l The' Unit V6nt monitor continuously monitors the' ' effluent from the unit vent for gaseous [
$=
radioactivity. The Unit Vent, via' ventilation exhaust systems, continuously purges various , tanks and sumps normally containing low-level ) radioactive aerated liquids that can potentis11y l generate airborne activity. f; c The exhaust systems.which supply air to;the unit ,
. vent are from the fuel building, auxiliary n buildin'g, the access control area,,the' '
[ containment purge, and the condenser air [ [ discharge. ! The Unit Vent monitor provides alarm functions 1 i s- -only, and does not terminate releases from the Unit Vent. F } 'j[ The Radwaste Building Ventilation effluent monitor continuously monitors for gaseous' y
. ' radioactivity in the effluent duct downstream of >~' ,
the exhaust filter and fans. The' flow. path
;42N
~
r provides ventilation exhaust for all parts of the: building structure and components within the . . building and provides a discharge path for the I waste gas decay tank release line. .These . components represent potential' sources.for the'. ; (, release of gaseous and air 1 particulate.and iodine. activities-in addition to the. drainage sumps, [ tanks,Jand' equipment purged by the vaste processing system. [ t
. This monitor will' isolate the waste gas decay i tank discharge line upon a high gaseous
[ radioactivity alarm. , 4 t . 1
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i L The continuous gaseous effluent monitor setpoints j L are established using-the methodology described ;
!. in Section 3.4. Since there are two continuous j
[ gaseous affluent release points, a fraction of
! the total dose rate. limit (DRL) will be allocated. i f to each-release point.- Neglecting the-batch i p- releases, the. plant Unit Vent monitor has been f allocated 0.7 DRL and the Radwaste Building Vent }8' moniter has been allocated 0.3 DRL. These i allocation factors may be changed as required to f support plant operational needs, but shall not be allowed to exceed. unity (i.e. 1.0). Therefore, a r . ;
y particular monitor reaching the setpoint would ' not necessurily mean the dose rate limit atithe SITE BOUNDARY is being exceeded; the alarm only indicates,that the specific release point is contributing a greater fraction of the dose rate ' limit than was allocated to the associated nonitor, and will necessitate an evaluation of i E both systems. , 7 3.3.2 Batch Release Gaseous Monitors ; The radiation monitors associated with batch a y release gaseous effluents are (Ref. 11.6.9, 11.6.10, 11.6.11): ,. Monitor I.D. Description GT-RE-22 Containment Purge System
, GT-RE-33 h GH-RE-lO Radwaste Building Vent The Containment Purge System monitors continuously monitor the containment purge exhaust duct during purge operations for gaseous radioactivity. The primary purpose of these monitors is to isolate the containment purge i system on high gaseous activity via the ESEAS.
3 The sample points are located outside the containment between the containment isolation 1.
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W /!) Yi The Radwaste(Building Vent monitor was previously; ' p, g described in.Section 3.3.1. $.+' . t f 'Setpoints for the batch gaseous effluent monitors l f( t%
- are calculated'using the methodology described in Section>3.4.
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'A pre-release isotopic' analysis is-performed.for- M M
k>, each batch release to determine the-identity-and; '
~
quantity of the principaliradionuclides. The. a. Sk alarm /tripisetpoint(s) is. adjusted'accordingly to ;l f" ensure that the limits of Section 9.6.1.1 are~not ! q , exceeded. 3.4 -Determination of Gaseous Effluent Monitor 'j y ,
, Setpoints
' 't sThe alarm / trip.setpoint for gtseous effluent m:
m'nitors-is' o determined based on the lesser of.the- l 0- total body dose rate and. skin' dose rate, as- )' i
calculated for'the SITE BOUNDARY.
.1 p During coce alterations, the setpoint:for-the ' -
Containment Purge Monitors, GT-RE-22 and GT-RE-33. :
..^' is set iati a value ofl less than or equal to . SE-3 L pCi/ce,:as required by Technical-Specification'
;t e 4'.9.4.2. The actual.setpoint value will.be l
reduced 1 according to the : Instrument Loop p : Uncertainty Estimate (ILUE):. " This-value.will - a p
. also be= utilized.in'the event that there-is no 1'
/
detectable noble gas activity-in the1 containment
; - atmosphere sample o analy::ed- in. accordance with:
' Section 9.6.1.1. The full derivation-of-this
..value is discussed in reference 11.14.6.
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- p. -.
L . 1 S tb 5D g R. tb F ,F, ( 3 .1 )' g .-Q b Where: 4
- (
sh=the' alarm / trip'setpointbased.onthetotal-
~
t ; body dose rate' (pCi/cc) . l fj Dg = Section 9.6.1.1 limit of 500 mrom/yr, -!
.c 1 conservatively interpreted as a continuous release.over'a one year period.
y
.., pn.,t
-- F s ': - the , safety factor; a conservative f actor used to compensate for statistical ., ,
'i fluctuations.and errors of-measurement. 'l (For. example, F, = 0.5 corresponds-to a e 100%. variation.) I
- g. Defaultcvalue is l's =- j 1.0. -*
4 f ' [' . g -F, =- the allocation factor which will modify the, h^ required: dilution factor-such that.
~s imultaneouscgaseous releases may be made-.
. -i without exceeding.the limits of Section 9 . 6 .1'.1. The default value is 1/n, where:n-
, is the number of' pathways planned for "elease.
- L .
p.. 1 3 , 1 !E ! i
,L
- %',5
- $ w w
C -4
.h v N:. f Ojii'; e _l _ _
p;c 7gV /g'q _ , LAPA-32-01003:
<"^
i; S V di.H - y,; Rov.-Oi t' ! . i; \
. t); 3 ' t 11 i fW ;
W ,
.Rtb;= factor _used to cenvert dose-rate to the L W '
effluent concentration as measured byLthe" s' effluent monator, in:(pci/cc) perL(mrem /yr) n ,
, to.the. total' body, determined according: tot p '
w
;g s
f 5 I
.,' + !.e tb=C+i(X/Q)IK[Q)
(3.2)
.d i- R g 1
k Where: a
,. , i
- Ce monitor reading of a noble gas monitor
. . corresponding to-the sample radionuclide
= concentrations-for the batch to-be I
released. Concentrations are determined in a> '
, accordance with Table'9.6-A;. -The. mixture-
^
of' radionuclides determinedLvia grab sampling of the affluent stream or source' .. J niz correlated to a calibration factor.to~ '
.{
f- ' determine' monitor; response.: 'The monitor- s q , responseiis basedLon concentrations ^, not j
.j. release-rate, and-is in units of-(uci/cc).
I X/Q = the highest eniculated': annual average relative En . concentration for any area at-oribeyond the. SITE BOUNDARY in (sec/m 8 )'. Refer to .!
, = Tables 9, 10, and 12.
mi Kg= 7( the total body dose factor due to gamma {_, emissions for each identified noble gas !,
, radionuclide, in (mrem /yr) per (uci/m*).
g (Table 3) 1 f , Q1= rate of release of noble gas radionuclide, k- g 4 1, in (vCi/sec). N y, ( j v1 1 4% #, f\ [f Ad}i
~M .
w Ify
.( --
3' L '
\,il
- W
) Yh APA-ZZ-01003~ V !';c . - Rov. O n f 3 . f**N
'a ,
i Qfiscalculatedas'the' product'ofithe= s ventilation-path design flow-rateland the1 measured activity of:thefeffluent stream as-determined by: grab sampling.. Flow 1 rates- ! for.the ventilation pathways can.be:foundi U< in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21'.
~
3.4.2 Skin-Dose
Rate Setpoint Calculation
, To' ensure that;the limits of Section.6.6.1.1~are met, theLal' arm / trip setpoint based on thecskin dose' rate is calculated according to
, S,5 D,R,F,F, (3.3).
~.,;
2.,..-e Whore:- F,.and'F, are as previously defined in Section- 1-13.4.1.1. (S, =~cthe alarm / trip setpoint-based on the: skin dose rate. D, = Section 9.6.1.1' limit of.3000 mrem /yr, conservative 1y ' interpreted as - a continuous: release over a one year period. , i 1 4 5 t 4
%e It . 41, +
~7 I
a;- 1 f " **W* w - j y , , ,. ows *$'
, r qh[ >
lf 3%. ; b].ijy
' y:+
f ApA-gg.01003-4": , 7 Rsv . . 0 - p i tw l;:n , y ,;+ , ,- 3 ,
'R,.=- factor used'to convert dose? rate tolthe offluent concentration:as measured-by the .
effluent monitor, in (yCi/cc) per..(mrem /yr): to the skin, determined'according to: g
, l
' ~
.Rfa.C+ '((X/Q)ili(L g tli1M).Qgp g. 13. 4 )_L i;
Where:1 LL'g:= (the skin dose' factor due to beta' emissions' for each. identified noble gas:radionuclide,; 3 in.(mrem /yr),per.(pCi/m ). (Table 3); r.Df - 1.1'= conversion factor: -l'.mradimir dose ='1.1- ;. mrem-skin dose. M{ = .the air dose-factor.due to gamma emissions
~
> -for each. identified; noble gascradionuclide, in'.(mrad /yr) per (pCi/m )., (TableL3)
,1
.. C, ....( X / Q ) a n d' Q g aresas.previously defined, i
Y
.f' 1 .. $k .
)
.g j. ' ,
C _ _ _ . _ . . -.J
> f!- , Q;
, m "
.;l.5
.q . ,8
-APA-ZZ-01003' $ ,i
~ p; Rav. 0 4 ;,
+
.b '.$ {
lyj%M i
- 3 '. 4 ' 3 Gaseous Effluent Monitors:Setpoint: Determination-
;P '
The results of Equation (3.1) and^ Equation (3.3) M < are: compared. The setpoint'is then selected =as w' ' , the-lesser of the two values.- 3 s
._ f f)s k
1 f - 1t,
<k n
t r n f\'l . 1 1, t
) ,
.Yp;-
t s ,
* - so -
i.. 3, .
!,e L , . _ . ,-
.mg'
F
- y. . , , ,
z .: - ~. .-
~
~ . 3: :.,
* - i. d& - & ~ .f,
~
_j . -
~ ; c ; pg . . :.g . -
xAPA-ZZ-OiOO3I '
... = g- 3...
Rev.' .O '- ' ,.
.C 4 .. . ;-
~
[' 'n
.%5i) '
~
p.s-TABLE 3'
~
.j
' POSE FACTORS TOR EXPOSURE ~TO A-SEMI-INFINITE CLOUD OF NOBLE CASES" .y ~j Total Body. . Comma Air- ' Beta Air ...: WT
' Dose Factor Skin Dose Factor . Dose Factor '.' ~' "Dese Factor.
K La. - M s .' . N . .-- Radionuclide (arem/yr) per (18CI/m3) (aren/yr) per (18CI/m3)l (mrad /yr) per.(18CI/m3) - (arad/yr) per (laci/m3) N K r-83m 7.56 E-02 -~- - . 1.93 E401' 2.88 E+02 - Kr-85m .'1.17 E+03 1.46 E+03 "1.23 E+03 -
-1.97 E+03 Kr . 1.61'E+01. 1.3ft E+03 ~1.72 E401 1.95 E+03 -
Kr-87~ 5.92 E+03 .9.73 E+03 '6.17 E+03: .1.03.E+04-Kr-88 1.47 E+08 2.37.E+03- 1.52 E+04 '.2.93 E+03~ > - K r-89 1.66 E+04' 1.01'E404 1.73 E+04 1.06 E+04 ^ Kr-90 1.56'E+088 7.29 E+03 1.63 E+04: :7.83 E+03 ~~ Xe-131m 9.15 E+01 4.76 E402 1.56 E+02 '1.11 E+03 Xe-133m 2.51 E402 ' 9.94 E+02- '3.27.E+02 't.48 E+03 - _ Xe-133 2.94 E+02 3.06 E+02 3.53 E+02. 1.05 E+03 - Xe-135m 3.12.E+03 7.11 E402 - 3. 36 - E+03 -- 7.39 E+02 ' - Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.8e6 E+03 - '-' _ ^ 2u., Xe-137 .1.42 E+03' 1.22 E+04 1.51 E+03 1.27.E+04 Xe-138 8.83.E+03 4.13 E403: 9.21 E+03 4.75 E*03- - - A r-Is t 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E403 .._. 1 (a) The listed dose factors are derived from Reg. Guide 1.109, Table B-1 (Rev. 1, 1977). _ M w 9 Y T 9 e 4
+- _ .
."'..s.,-
w .
- .-.:._ ,, , . ,. , . - ;<.~ . , w. .,- --- ^
z---. e --, .c.__. .:._, . , _ _ - . _
. , _ _ . ~ . - . _ . , - _ _ _ _ _ . .,
p rpp 4 a w . i f;13@ y"@, -APA-ZZ-01003-- -! F ' , i ?9 .m . Rcv . : 0 ' ;
, W. gmt j - in
,c p ;;gi .
1 g%
~ '
. s .
't 4 ,
,; c. L3.4.43 -Summary,' Gaseous Effluent Monitors Setpoint' -f UE . Determination
- a q; "!f l Ig
- The gaseous effluent' monitors setpoints are i
+ cal.culated according to equations (3.1) and- ! as "
.(3.3),.as described in Section~3.4. However, it- 1 Ei should be,noted that a batch-release will; alter !
the' flow: rate characteristics at the Unit. Vent" j 1
- and therefore the concentration as sensed by the- _l .- . . monitor.. For example, in the case.of.a mini-~ j
,J - purge, the setpoint for the. Unit Vent monitor j
' mustLbe re-calculated to include both the M continuous land batch sources.- if s
, . 3.5 Calculation of Dose From' Gaseous Effluents s
Dosotrate calculations are performed for gaseous *
- effluents to ensure compliance with-Section. ,
9.6.1.1. a J 3 . 5 .1. Calculation-of Dose Rate "i o *
"f-" The following methodology is'applicabletto the. .
. location l(SITE BOUNDARY or beyond)1 characterized: ,
i
;by;the' values of'the parameter (X/Q) which i resultsLin the maximum total-body oriskin dose 1
' rate. -In the event thatethe analysis indicates:a- O f"
different loc'ation for the total' body and: skin:
< dose limitations,Ethe location selected:for-consideration is that~which minimizes the<
' allowable release, values. (Ref.: 11.8.6) ,
-Theifactors K ,g.L, g and M g; relate 1the 's c' .
radionuclide airborne concentrations to various' > _ ne dose rates, . assuming a4 semi-infinite cloud.model, , and are tabulated in Table 3. 3.5.1.l' Noble cases , . n* The release rate limit for= noble gases is determined according to the'itilowing general relationships (Ref. 11.8.6): k
, 4 7,,
. 'us.
$)
. . . . . _ 4 -.
^^
We d' o x :, , APA-ZZ-01003'
-- Rov . - 0 :
i-
- 9N, -
't
~
DtbI* I IE ((X/Q)Qg)) i 5 500 mrem /yr (3.5) i-c .
.n 9
. D, . = I ' [ ( L g + .'l'.1 M )((X/Q)Qg))
g -5 3000 mrem /yr -(3.6) it c
'Where:
S :. Dtb = Total body dose rate, conservativelyf averaged-over a period-ofione year.
+ .o g,g Kg =- Total body. dose factor due to. gamma
emissions for each identified noble. gas. . ,
- radionuclide, in (mrem /yr) per (pCi/m ).
(Table 3) r vi: V
.(X/Q) = .The, highest calculated-annual average relative concentration'forvany area at or U beyond the SITE; BOUNDARY. Referi to - Table s
'9, 10,'and 12.
Qg-= .The release ~ rate:of noble gas .
. radionuclides, i, in gaseous' effluents, from all' vent releases in (yci/sec) .
Q g =x is calculated-as the product of the ventilation path' design flow rate'andlthe measured activity:of the effluent stream'as determined by grab 1 sampling. Flow' rates; for the ventilation pathways can be,found in references 11.6.18,.11.6.19, 11.6.20, and 11.6.21. D, = Skin dose rate, conservatively averaged
, Q),;:jg . over a period of one year, w
C - -
, g. ;
2 . ._._ _ __
^
* ?
Q) lYi
- 3 k,, o ,
,, ,APA-ZZ-01003' ;
$ Rtv 0 -! (iQ A , g:L y y{
- g.
L=g . Skin = dose? factor due'to beta: emissions for if each identified noble' gas radionuclide, in. 'I h (mrem /yr) pert (pCi/m ) (Table 3). 3 a h p 1.1 = Units conversion factor; 1 mrad air dose = T 1.1. mrem skin dose, .u. d; f - M'=g Air dose factor due to gamma emissi6ns-for
)
y 1 each identified noble gas'radionuclide, iny - (mrad /yr) per.(vCi/m8 ) (Table 3). ;
!i 7.;.
3.5.1.2 Radionuclides other Than Neble Gases , g.' TheLrelease rate limit for Iodine-131 and-133, ( h for - tri tium, and-for all; radioactive materials in-
,, particulate form with half lives greater than 8- q 9 days is determined according to.(Ref. 11.8.7):- t a
v
,. ,' m D,;=1P[WQ)QgJg 5 1500 mrem /yr ( 3 . ,7 ) ,. [
4,.
'4 1 Where:
b } h' Do = Dose rate to any crit.ical organ, in v (/ (mrem /yr).
- Pg= Dose parameter for radionuclides other'than
' noble gases for the inhalation pathway for d- '
.s the child,- based on the critical organ, in i y
(mrem /yr).per (vC1/m'). (Table 4). i g Qg= The-release ratetof radionuclide, 1, -. in
! gaseous effluents, from all vent releases,-
1 -in (uci/sec). Q 3 is~ calculated as the ! y product of the ventilation. path design flow 3 rate.and the measured activity of the & effluent stream as determined by grab l
; sampling. Flow rates for the ventilation g( ,
pathways can be found-in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21. F{/ y@;.f. - v a q-a: fo ,
' r
. i.
,1 n p,' >
f l.. l ,
, , APA-ZZ-01003' Rsv.. 0' '
[F P' g f~~ik . ; c ,. m
- n L (if i-p -,
(X/Q) is'as previously defined.
,{ The-dose parameter (P )'
g includes the' internal l~ :dosimetryiof radionuclide,-i, and;the receptor's~ breathing rate, which:are functions of the receptor.'s age. Therefore the-child-age groupi e- has-been selected as the limiting age group.
~
g For the child exposure, separate values-of Pg are tabulated in Table 41for the-inhalation l pathway.
.These values were calculated according to=(Ref.
11.8.8):'
- j. 13 , 8 ) '
'P[=K' (BR) DFA g
;u
'Where:
. . -[' . K '. = Units conversion-factor: IvCi = 1E06 pCi.
-BR=' The breathing rate of the maximum; exposed' n'
child-age group, 3700 m 2/yr. .(Regulatory Guide-1.109, Table E-5). DFA g = .The maximum organ inhalation dose ^ factor for the child age group for-the ith: h radionucl'ide, iny(mrem /pci).. The total-body:is considered as-an organ in the selection of-DFA g. (Ref. 11.11,5 and 11.14.4) Note:.Allradiciodines are assumed to be released in elemental form. (Ref.11.8.7) r
-x ,. .
, :j L . . . . . .- . _ . _ _ y
- ~ ^
4 y APA-ZZ-01003 c ' Rev 0 3 %
, l,%
L TABLE 4-DOSE PARAMETERf(Pg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" Inhelation Pathway '
~(mrem /yr) per (VCi/m8 ) !
W
.l Total- l
> l1 l l l _
l l- l ,
..y ~lNuclidel Bone l' Liver l' Body l Thyroid l Kidney l Lung i GI-LLI l '
u
'l H-3 l ND- l1'12E3 l1.12E3 l1.12E3, l1.12E3 'l1.12E3 l1.12E3- l ;
y; ; l Be l8.47E2 -l1.44E3 -l9.25E2 l ND l- ND. l6.4SE4' 12.55E3 l
-l C-14. l3.59E4- 16.73E3: l6.73E3 16.73E3 l6.73E3 16.73E3 16.73E3 l l_Na'-24 l1.61E4 l1.61E4 11.61E4 'l1.61E4 - ll.61E4 l1.61E4 l1.61E4 ;;
l.P-32 l2.60E6 l1.14E5 l ND l9.88E4 l ND _l ND l4.22E4 -l l'Cr-51-l ND l ND J1.54E2 l8.55El' l2.43E1 l1.70E4 l1.08E3' l !? >l Mn-54 l ND .l4.29E4 l9.51E3 l ND l1.58E6 ;l2.29E4 l1.00E4 l l-Mn-56;l ND l 11.66E0 l3.12E-1 l ND l1.67E0 l1.31E4 l 1. 23E5.i l L F,' .l Fe-55.l4.74E4 - l2.52E4 l7.72E3 l ND l ND l1.11E5- l2.87E3 Ll l Fe459 l2.07E4 l 3 . 34E4 -' -l1.67E4 l ND l ND l1.27E6 l7.07E4 'l . l Co-57 l- ND l9.03E2 .l1.07E3 l ND l ND l5.07E5 l1.32E4 l j Co-581l' ND l1.77E3 13.16E3 l ND _l ND. l1.11E6 l3.44E41 ,1 l Co-60 l ND ~l1.31E4 l2.26E4 l ND l ND l7.07E6~ l9.26E4 l l-Ni-63-l8.21ES- l4.63E4 12.80E4 l ND l ND- l2.75ES -l6.33E3' l
- l'Ni-65 l2.99E0 l2.96E l1.64E-1 l ND l 'ND l8.18E3 l8.40E4 l L
- l Cu-64'.l ND l 1'. 99E0 l1.07E0 l ND- l6.03E0 19.58E3- l3.67E4: l I' < l..Zn-65 l4.26E4 'll.13E5 l7.03E4 l ND l7.14E4 l9.95E5 l1.63E4 l 1
l , l~Zn-69 l6.70E-2 l9'.66E-2 l 8 '. 9 2E -3 l = ND ~l5.85E-2-l1.42E3- l1.02E4 l , -l.Br-82 l ~ND l ND- l2.09E4 l ND l . ND l- ND l ND l. L ll Br-83 l ND 'l ND' l4.74E2 l ND -l_ ND- l ND l' O l. 1 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 l: Rb-86 > l ND -- l1.98E5- l1.14E5 l ND l ND l ND l7.99E3 l
'lrRb-88 l ND l5.62E2 l3.66E2 l ND l ND l ND l1.72E1 l-l Rb-89 l -ND l3.45E2 l2.90E2 l ND l 'ND' _l ND l1.89E0 'l u
, s
. l- Sr-89 l5.99E5 l ND l1.72E4 l ND l ND l2.16E6 l1.67E5 ~l
", :liSr-90 l1.01E8 l- ND l6.44E6 l ND l -ND l1.48E7 l3.43E5 l 7
lcSr-91ll1.21E2 l ND l 4.5 9E's l ND l ND 15.33E4 l1.74E5 l ,
-l Sr-92 l1.31El l ND 15.25*-1 l ND l ND l2.40E4 l2.42E5 -l ll Y-90 -l4.11E3 -l ND -l1.14E2 .l ND l ND l2.62E5 l2.68E5 l
[ l l- ! L 4
1 o a
< l#
"{" ,. ~ { ' ' " " ~ .
t m
; TABLE 4 -
K, DOSE PARAMETER (Pg ) FOR' RADIONUCLIDES OTHER THAN NOBLE GASES" ; , [-, L ;j y
" 4 Inhalation Pathway [
u f, (mrem /yr) per (uCi/m') h .l l- , l-: l. Total- l l l l. l-
-lNuclidel Bone- l= Liver i Body l Thyroid i Kidney l Lung i GI-LLI l .l i
3 f l7H-3 l ND- -l1.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 j ,- !
, l Be-7f l8.47E2 l1.44E3 l9.2SE2 'l ND l ND l6.48E4. 12.55E3: l i l-C-14':l3.59E4' l6.73E3 l6.73E3 l6.73E3 l6.73E3 l6.73E3 l6.73E3 l ;
l . Na-24--l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4- l1.61E4' l l P-32 l2.60E6..l1.14ES- 19'88E4
. l ND l ND l ND' l4.22E4: l' l Cr-51 l ND l :ND. l1.54E2--l8.55El l2.43E1 l1.70E4 l1,08E3 l~
l1,- l Mn-54 l 'ND 'l4.29E4 l9.51E3 l ND l1.00E4 l1.58E6 l2.29E4 l-1 i Mn-56 l .ND . l1.66E0 l3.12E-1 l ND l1.67E0 l1.31E4 -l1.23E5 .l-
, l Fe-55 l4.74E4 l2.52E4 17.72E3 l ND l ND l1.11E5 12.87E3 l l Fe-59 l2.07E4 l3.34E4 l1.67E4 l ND l ND l1.27E6 l7.07E4 l 5 .:C+
l'Co-57.l ND: l9.03E2 l1.07E3 l ND l ND l5.07ES -l1.32E4L l , f
.l Co-58-l ND. l1.77E3. l3.16E3 l ND l ND 11.11E6 l3.44E4 l
.l:Co-60 l~ ND l1.31E4 l2.26E4 l ND l ND l7.07E6 l9.26E4 l
?l:Ni-63 18.21E5' l4.63E4 l2.80E4 l ND -l ND l2.75ES .l6.33E3 =l ,
l Ni-65 l2.99E0 .l2.96E-1 [1.64E-1 l ND l: ND l8.18E3 l8.40E4-l 1 h * : l'Cu-64 l ND -l1.99E0 l1.07E0' l ND- 16.03E0 19.58E3 l3.67E4 , p - l(Zn-65 l4.26E4 l1.13E5 l7.03E4 'l ND l7.14E4.l9.95E5 l1.63E4 l l- 1l Zn-69 16.'70E-2 l9.66E-2' l8.92E-3'l ND l5.85E-2 l1.42E3 - l 1'. 02E4 l
. .l Br-82'-l .ND l ND. l2.09E4 l ND l ND l ND l- ND l ,
- l Br-83 l ND l ND l4.74E2 l ND l ND l ND l- 0 l l Br-84:l- ND l ND l5.48E2 l ND l ND. l ND l 0 l lLBr-85 l' 'ND l ND l2.53E1 -l ND l ND l ND . l' O l .l'
.l'Rb-86 l. ND l1.98E5 l1.14E5 l ND l ND l ND l7.99E3 l l Rb-88 l ND 'l5.62E2 13.66E2 l ND l ND l ND -l 1. 72E1. l
, .-l :Rb l ND l3,45E2 l2.90E2 l ND l MD l ND l1.89E0 l I
- l'Sr-89-j5.99ES l- ND l1.72E4 l ND .I ND l2.16E6 l1.67ES l
$s '
<l Sr-90 l1.01E8 .l ND l6.44E6 l ND l ND l1.48E7 l3.43E5 l '
' llSr-91 l1.21E2 ] ND~ l4.59E0 l ND l ND l5.33E4 l1.74E5 l S< l Sr-92 l1.31El l ND 15.25E-1 l ND l ND l2.40E4 l2.42E5 l jl Y l4.11E3 'l ND l1.11E2 l ND l ND l2.62E5 l2.68E5 'l a$slO) nv .
lis / y_ 1 i ! i.
- b. . . . -*
t c e ' R:v. : i ' i # s n N~#
@ , TABLE 4:(Cont'd.).
t~ 9 g DOSE PARAMETER (Pg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" 6 % ' b w j Inhalation Pathway
- (mrom/yr) per (pC1/m ) 8 l._ l Total j. .l y(
- lNuclidel ln Bone l .
l- Liver i Body l l L Thyroid l Kidney l -Lung l _ i GI-LLI'l ] j s'... '
.llY-91m'l5.07E-1l ND l1.84E-2 ll ND l ND~ l2.81E3 11.72E3 'l y l:Y-91 l9.14E5 l ND- l2.44E4 l ND l ND l2.63E6 l1.84E5 l p -l.Y l2.04E1 .l ND l5.81E-1 l ND l ND- l2.39E4_-l2.39E5 .l l
_. l t Y-93: l1.86E2 l- ND l5.11E0 l ND l ND- l7.44E4 l3.89ES l; ,
, _l Zr-95 l1.90ES- l4.18E4 l3.70E4 l ND. l5.96E4 l 2. 23E6 - 'l 6.1 %.4 <l=
l_Zr-97 l1.88E2 l2.72E1 "l1.60E1 l ND _l3.89El l1.13E5. l3.51E5 l
- g. l Nb-95 l2.33E4- l9.18E3 l6.55E3 l ND l8.62E3 l6.14E5 l3.70E4 l.
4 lLMo-99.IND. :l 1'. 72E2 l4.26El .1 ND l3.92E2 l1.35ES l1.27E5 tl A l Tc-99mjl.78E-3 l3.48E-3 l5.77E-2 l ND l5.07E-2 l9.51E2 l4.81E3.-l l Tc-10118.10E-5 18.51E-5 .ll.08E-3.l ND l1.45E-3 l5.85E2 -l1.63El' l
+
m ; l~Ru-103l2.79E3 l ND -jl.07E3 l ND l7.03E3 l6.62E5 .l4.48E4 l , _l.Ru-105l1.53E0 l ND. :l5.55E-1 l ND l1.34E0 l1.59E4- l9.95E4 l_ is l Ru-106l1.36ES l ND' l1.69E4 l ND l1.84E5 l1.43E7 l4.29ES' l-lAg 110 mil.69E4 l1.14E4 l9.14E3 l; ND' l2.12E4 l5.48E6- l1,00E5 l l Cd-109l ND 15'48E5 '_ l 2. 5 9E4 l -ND l4.96E5 - l 1.'05 E 6 l2.78E4 l
, l-Sn-113l1.13E5 l3.12E3 l8.62E3 l2.33E3 l ND l1.46E6 l2.26ES l
-l.Sb-124l5.74E4 l7.40E2 l2.00E4 l1.26E2 l ND l3.24E6. l1.64E5 l h '
l Sb-125l9.84E4 l7.59E2 12.07E4 19.10E1 1 l ND l2.32E6 l4.03E4 l- l
-lTe-125ml6.73E3' l2.33E3 l9-14E2- l1.92E3 l ND' l4.77ES l3.38E4 l ,
H lTe-127ml2.49E4 l8L55E3 l3.02E3 . l 6. 07E3 . l6.36E4 l1.48E6 l7.14E4 l } f n
.- l Te- 127 -- l 2. 7 7E0 - l 9.515- 1~ l6.11E-1-l1.96E0 17.07E0. l1.00E4 'l5'62E4 .
l: lTe-129ml1.92E4 l6.85E3 l3.04E3- l6.33E3 l5.03E4 l1.76E6 l1.82E5 -l , f -lTe-129 l9.77E-2 13.50E-2 l2.38E-2 l7.14E-2 l2.57E-1 l2.93E3 12.55E4 -l j .lTe-131ml1.34E2 _ l5.92E1. . 15.07El -l9.77El l4.00E2 12.06E5 l3.08E5 l lTe-131,l2.17E-2 l8.44E-3'.l6.59E-3 l1.70E-2 15.88E-2 l2.05E3 -l1.33E3- l- J t' lTe-132 l4.81E2 l2.72E2 l2.63E2 l3.17E2 11.~ 77E3 l3.77ES l 1.~38E5 l , l i ., b .lI-130 l8.18E3 l1.64E4 [8.44E3 l1.85E6 l2.45E4- l ND -l5.11E3- l lI-131 l4.81E4. 14. 81E4 l2.73E4 l1.62E7 l7.88E4 l ND l2.84E3 l h- lI-132 12.12E3 l4.07E3 l1.88E3- l1.94E5 l6.25E3 l ND l3.20E3 -l 7' lI-133 l1.66E4 =l2.03E4 l7.70E3 l3.85E6 l3.38E4 l ND l5.48E3 l p- lI-134 - l1.17E3 12.16E3' l9.95E2 'l5.07E4 -l3.30E3 l ND 19.55E2 l ( , lI-135 l4.92E3 - l 8 '. 73E3 -j4.14E3 l7'92E5 l1.34E4 l ND l4.44E3 l
.rs I.
s QNd N.[ : J 37 - t
. y , -. . . . . - . - . - ,
4 V 7 pA-ZZ-01009-E <
<, Rov. 0-f
- f' '
, TABLE 4-(Cont'd.)-
D0'SE PARAMETERg_ (P ) FOR RMWCMDES OTHER M NOBE GASES Inhalation Pathway
;g -(mrem /yr) per (UC1/m3 ) ;l i e l; .,.I l. l Total l l [ j .
l _q _ ,lNuclidelt Bone I Liver I Body i Thyroid 1 Kidney l Lung 1 GI-LLI l-lCs-134 16.51E5 -'ll.01E6- l2.25E5 l ND l3.03E5 11.21E5 ' l3.85E3 l
' l Cs - 136 ' ~ l 6. 51E4 l1.71ES l1.16ES- l ND l9.55E4 11.45E4 14.18E3 l-
.lcs-137 l9.07E5- l8.25ES l1.28ES. l ND .l2.72E5 l1.04E5 l3.62E3 l
'lCs-138-l6.33E2 18.'40E2. 15.55E2 l ND l6.22E2 l6.81El 12.70E2 l
- y. _l Ba-139 - l 1. 84E0 -- l9.84E-4 l5.37E-2 l ND l8.62E-4 l5.77E3 l5.77E4 ll
- lBa-140 : l 7.40E4 ' l6.48E1 ~
l4.33E3 l ND 12.11El 11.74E6 ll1.02r5 l lBa-141L]2.19E-1 l1.09E-4 l6.36E-3 l ND l9.47E-5 l2.92E3 12.75E2 -l jBa-142 l5;00E-2 l3.60E-5 l2.79E-3 l ND ' l 2. 91E-5 l 1. 64E3 ' l2.74EO, l-
,)
lLa-140 16,44E2,-l2.25E2 l7.55El -l ND l ND ll.83E5 l2.26ES l Ni lLa-142ol1.30E0 l4.11E-1: l1.29E-1 l ND l ND l8.70E3-~l7.59E4 l ,
.lCe-141Cl3.92E4 l1.95E4 l2.90E3 l ND l8.55E3 l5.44E5 l5.66E4 l
-lCe-143;13.66E2 l1.99E2 12.87El l ND l8i36El l1.15ES 11.27ES l
.lCe-1441l6.77E6- l2.12E6- l3.61E5 l ND l1.17E6 l1.20E7' ]3.89E5' l lPr-143 11.85E4 15.55E3 '. . l9.14E2 l ND- l3.00E3 l4.33E5 _l9.73E5 l lPr-144 : l5.96E-2 l1.85E-2 l3.00E-3 l ND 19.77E-3 l1.57E3 ;l1.97E2- l
'lNd-147:l1.0SE4 ]8.73E3 16.81E2 l ND l4.81E3 l3.28E5 -18.21E4- !
elEu-1544 l1.01E7- l9.21E5 l8.40E5 l _ND I4.03E6 l6.14E6 .l1.10E5
,lHf-181-l2'78E4 11.01ES.
l1.25E4 l .ND l2.05E4 ll.06E6- 16.62E4
, lW-187 l 1'. 63E1 l9.66E0 l4.33E0 l ND_ l - ND l4.11E4 l9.10E4 r
;lNp-239ll4.66E2 l3.34E1 l2.35El l ND- l9.73E1 l5.81E4 l6.40E4 -l (a) jThe child age group; refer to reference 11.14.5.
1 i a 7.,
)
l
-. L.
_--.l - _ _ _ _ _ _ _ _ _ - _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ - - _
3 - -- A
~
a >
-ApA.gg.oloo3 o-R3v. 0;
- t. . .
J; ;.:.~c * ;
+; .;
i 1
, 3.5.2 . Dose-'Due To Gaseous Effluents- !
M - '4185'8 315.2.1 REC Section 9.7.1.1~ j ;- T 4160 The.airedose dueito noble gases released-in ' l' gaseous affluents, to areas at and'beyond the- .- ! p .
. SITE BOUNDARY-shall.be' limited to the. followings: .
E4 a'. .During'any calendar; quarter: Less--(than or-1- , equal to 5 mrad for gamma radiation'.and - less than or. equal'to 10 mrad for beta -; f- . radiation and, s
- b. During any calendar year: _Less than-or !
equal to 10 mrad for gamma; radiation and ll less than or equal to 20 mrad for beta- 3 ? 1 radiation. - I 'Ir y ki ' ,. ?$}', '! i e i lc . b -. ! ( !)' . .
~L F d
1 S l= ll e b i: b I
\ . <nr . 39 i
l ?(Q @d . ~, f r . . p . . . . .
- w. , i
- t. ;r '
ill ' '
-APA-ZZ-01003 i-- * <
- Rav.JO~
ii;
, > j ,4 7 ,
[lf: J- ' we
, 3. 5'.2. 1. 1' N dle Gases.
C Y The air dose at,the. SITE BOUNDARY due to noble-pr: gases released from the siteLis calculated ~ according to'the following methodology-(Ref. > by 11.8.9):. A . During any' calendar quarter,-for-gamma-radiation:
;plt[S '
- d. R
[f - LI g =I 3.17E-08 I [Mg { G/Q) Qg<+ G/q) q.g}) 55 mrad.. (3.9)' g
,Q,
+.
-During any calendar quarter, for beta radiation:.
;1 p
6)! ... .. D bi = > 3.17E-081 I [N g { G/Q) Q1 - + G/q) q g)) 5 10 mnd . J3.10)f _{ ', i
'i During,any-calendar year, for gamma! radiations-1.
.D g = .3.17E-08 :I- [M g .L { @/Q) Qg + p/q). q g )) $ 10 mrad' (3.11)_.
.A During any calendar year,"for-beta radiation:-
- ,U -
;/ .,
- D3 = . 3.17E-08 I (N g { p/Q) Qg .+- p/q) 3g))-5 20 mrad (3.12)
__ y s g j y' p
'S'
. l ,
.n w y, ?$s_ l
- - wI s i{2
[; ); , L . . . . . ~ . . _ . . . . -~
c 1 9? APA-ZZ-01003 Rtv.-0 g & ll 0 ' i Wheren l l D =: Air dose from gamma radiation due to. noble gases released in' gaseous effluent. o Db;= Air dose from beta 1 radiation due to noble l [ m gases? released in1 gaseous effluents.;
't f
. (X/q) =
~
The1 relative-concentration for areas ~at i f. " or beyond the SITE BOUNDARY for. H- - short-term releases'(equal to or.less- 1 than 500 hrs / year)-.- Refer ~to. Tables 9, - 10, 11, and'12. , q3 = .The average release of noble gas as radionuclides, i, in gaseous-effluents from [
* .all. vent releases-for.short-term releases- (
l (equal to;or less than.500 hrs / year), in 1 R- ( pci ) .- Releases are cumulative over the~ M calendar: quarter'or year,fas appropriate.-
.nr N=.
g The: air dose factor due to beta' emissions . for each. identified noble-gas 1radionuclide, 1, in (mrad /yr); per (pCi/m ) . (Table =3) 8 Qg=, The average release of: noble gas l ;{ radionuclides, i,--in gaseous-effluents from- 'i l all vent releases for long-term releases i
.(greater than'500 hrs / year), in1(pC1).
A Releases are-cumulative cVer the. calendar.
- quarter or year, _as appropriate.
~
1 (X/Q) = The highest calculated-annual average i ! _. relative concentration for
="
L areas at or beyond the . i
- SITE. BOUNDARY'for long-term releases ;
L (greater than 500 hrs /yr). Refer'to- '
, Tables 9, 10, and 12. .
H , t
'3.17E-08 = 'The inverse of the number of seconds H
y < per year, (. M g is as previously defined. (Refer to Section-p .. 3.4.1.2)' ' if) L If L
,,(. ,
,- b~ g 1> APA-ZZ-01003-- 1 m
g g3y,1 .o-pu f. m o
.? .o . ,
s , ty . .
'f.f , s 9 .41860.E3.5.2.2
.,2,, REC Sect i on'9.8,._1J iv 4160.
b, The dAse to a MEMBER OF THE PUBLIC from
~
i?" 76 Iodine-131-and-133, tritium, and all- , ' radionuclides in particulate form with half-lives-- , greater ~than 8 days in gaseous effluents ; released,'to. areas at and beyond the SITE ' W BOUNDARYeshall be limited to the following'(Ref.. ., p-.
-11.8.9):
y a. During.any calendar quarter: Less than or- 1 ( equal to 7.5 mrem to any organ and,y ; 4-b' 'During any calendar year: Less than or' ; L . equal 4to~15 mrem to any organ. -l
.n a B' 3.5.2.2.1- Radionuclides Other Than~ Noble Gases k '
The dose to a MEMBER OF.THE PUBLIC.from j 'iL Iodine-131 and 133, tritium, and all y' radionuclides in particulate form with half-lives t
.. greater than 8 days in gaseous effluents fN 1- released, to areas atiand beyond the. SITE (
D M BOUNDARY,~is. calculated according to the' . i f i.
~following' expressions: '
, .During any calendar quarter: i t
, li D g3 =
'3.17E-08 I R g.,(W Q3 + w q1) 5 7.5 mrem. (3.13)' [
i s During any-calendar year: D1 = 3.17E-08 I Rg (W g g + w q )g <_ 15 mrem -( 3 .14 ) ' ; L i li t l' 'i : ' Ll + > Where: g' i [$ D.= g Dose to a MEMBER OF THE PUBLIC from I radionuclides other than noble gases. 7
+ ,a y) .,ig-B L
u r m 1: ,
, L. . _ _. _ ...
h
m
~
/ ,' ( '
APAi2Z iO1003-
~ -!
g Rov. OL L 8 4s ' B W % M:s E, r
.,- Qg;= 'Theireleases.of radiolodinesi; radioactive materials in particulate form, Hand- 1 s .
~ 9~ .
radionuclides _other.than noble gases, 1;"in' ' C -gaseous effluents,Efor allolong-term. vent c i h, releases-(greater than 500, hrs /yr), in .;
& ( 9C1 ) .. Releases are cumulative over the !!
calendarfquarterior year as appropriate.. w , h q The releases.of radiciodines, radioactive
. .g=
E -materials in particulate form and: *i F j radionuclides other than. noble gases, i=, . in n gaseous effluents for.all5short-term vent. i 7' releases (equal to or less: than 500 . hrs /yr), in (uci). Releases are cumulative :l over the calendar quarter or year-as ~ appropriate. j h 1- - Ri= - The: dose factor for.each identifiedt ;; [ 2 radionuclide, i, in m (mrem /yr);per:. .
'(vC1/sec) or (mrem /yr) per (pC1/m') . ;(Table i g ,' :fy .5 )
r , < .. , W =- The dispersion parameter'for estimating /the- 0; Lc dose to an individual at thefcontrolling-M i, ' . y ' location 1for11ong-term releases (greater-p , than 500 hrs /yr): '!
- b pr .
W = (X/Q) for.the inhalation and tritium. pathways, h
- r. .
in(sec/m'). '! p$N ' , W =1(D/Q) for the-food.and ground. plane pathways, in(meters'2) . L Refer to Tables 9, 10, and 12. 4 y l, Y' R v
~
$4 . I h lf i t 4 gi? , _en , ,. .. [ . t 4
u." *
, . Rov J 0 ;
.& ^ W . 4 _ w= L The: dispersion _ parameterz for estimating the;
,g dose co an individual at1the controlling;
- location.for short-term releases'(equal _to:
- or less :than 500 hrs /yr):- _
w= _'X/q, for the inhalation pathway,-
' i: in(soc /m')
-w=' (D/q)^for-the food:and ground planet-l paths'ay,'in (meters ~8). ' Refer to-_ Tables 9,.
. 10, : 11, and 12.
l3.17. E-08 = The inverse of:the number-of seconds per: year. (D/Q) = the average relative deposition"ofLthe
- effluent-at or beyond_the. SITE-BOUNDARY,-
= considering-depletion of the:plumet during transport, for: long term' releases
. (greater.than 500 hrs /yr),Lin:(meters" 2),
en" v- (D/q) = the' relative deposition of the. effluent at or beyond the SITE-. BOUNDARY,y .- considering depletion of the-plume during: transport, for.short term releases (less than or equal to 500 hrs /yr),. in (meters 2). f T 1 0 45' r hh
^
. en se c
L.
- i s, ++
n ..... ....
, se , j7 rov 0 "D 4 k[$ < W Q 1 6: Q,ll l -
ti
, ; , ; Note:i:For the' direction sectors: With' existing .
pathways.within15 miles from-thessite,.the {j, ,
. appropriate:R{ values are;used.: Ife not real-.
B LE (" 4 pathway: exists within 5 miles from the 4 center of the building complex, the_ cow-- ,} milk R g .value is used,fand it is assumedi . that this pathway exists at the-4.5.to 5.0- J mile: distance in the limiting-case 1 sector.' '! '.{ .( ' If the Rg,for'.an existing pathway'within 55 f ", . mi'les is less than a cow-milk'R g at:4.5 to s q d 5.01 miles, then the1value of the' cow-milk' ; L* Rg - at 4.5 to. 5.0 milesnis used. (Rev. : ;
, 9.8.10.) Lt
[ ~Althoughlthe annual average relative . _ I
, concentration (X/Q) and the average relative'.. ,
deposition rate (D/Q) are generally considered to' *
- f s 'be
- at:the approximate-receptor-location in lieu' I of- the SITE BOUNDARY for these calculations,: iti
[,'s is acceptable to consider the ingestion, . ? ' inhalation, and ' ground plane pathways to: coexist-
'6 "at the location of the nearest = residence with the
,,, . highest value'of (X/Q). (Ref. .ll.8.9): The Totalt , Body; dose from ground plane deposition.isuadded kg to the dese for each individual organ. -(Ref, f p 11.11.3) i The cumulative criticaln organ' doses ~ for a :
~ monthly, quarterly orEannual evaluation:are based ;
e on1the calculated dose. contribution from each ; [, " specified time period occurring during-.the reporting period. ] ai
' ~
y.; s 7 m.
- l. -f
+
fi
+
p- , d 1 [{; 4 W ,
, /
.! . a 1
f
, ,' h, , , =+= * * -
D.' i -.
& ^
[g T 0 'APA-ZZ-01003 Rsv. 0 4: a g-TABLE 5 PATHWAY DOSE FACTORS (Rg )_FOR RADIONUCLIDES OTHER THAN NOBLE GASES *' i
^
Inhalation Pathway
(mrem /yr) per (11Ci/m')
l l; l l Total l l l lNuclidel Bone' -l Liver l Body l Thyroid l Kidney Lung GI-LLI l'
'l H-3 _.l ND l1.12E3 -l1.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 l l Be-7 l8.47E2 l1.44E3= l 9 '. 25E2 l ND l ND l6.48E4 l2.55E3 l_
'l.C-14 l3.59E4' l6.73E3 16.73E3 l6.73E3; 'l6.73E3 l6.73E3 l6.73E3 . l'
- l-Na-24 l1.61E4 11.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 -l-p l P-32-ll2.60E6 l1.14E5 _19.88E4: l ND l ND l ND 14.22E4 .l 1
E l Cr-51 l ND ~l ND l1.54E2 18.55El l2.43E1 l1.70E4 l1.08E3 ll l!Mn-54 l ND ~ .l4.29E4 l9.51E3 l ND l1.00E4 l1.58E6 l2.29E4 ll i +..:,
, l Mn-56-l . ND -11.66E0 13.12E-1 l .ND l1.67E0 'l1.31E4 l1.23E5' l
'l Fe-55 l474E4 ~ l 2.:;2E4~ ~l7.72E3 'l ND l ND l1~.11ES l2.87E3 l l Fe-59-12.07E4 .l3.34E4 -]1.67E4 ~l ND l ND l1.27E6 l7.07E4 l i ,' ~l Co-57 l.-ND' l1,07E3 19.03E2 l ND- l ND l5.07ES .ll.32E4 l l'Co-58'li ND l1.77E3 13.16E3 l- ND l ND 'l1.11E6 l3.44E4 l' l Co-60Ll ND ll.31E4 -l2.26E4 'l ND l- ND l7.07E6 'j9.26E4 l
, .l'Ni-63: 18.21ES 14.63E4_ ;l2.80EA l ND. l. ND- l2.75E5; l6.33E3 .l l Ni-65 l2.99E0 l2.96E-1 l1.64E-1 l ND l ND l8.18E3 l8.40E4- l if k l.Cu-64?] ND _ l1.99E0 l1.07E0 l ND 16,03E0 l9.58ES- l3.67E4 -l U" ltZn-65 l4.26E4 11.13E5 l7.03E4 l ND l7.14E4 l9.95E5 ;[1.63E4'-]-
l Zn-69~l6.70E-2 l9.66E-2 l8.92E-3 i ND. 15.85E-2 l1;42E3 11.02E4 l
.l.Br-82 l ND l.ND= l2.09E4 l ND l _ND~ l ND l ND l 4
.l Br-83.'lND l ND l4.74E2 l ND l ND l ND l 0 l
]; Br-84.: l ND l ND ' l 5,.48E2 l ND l ND l ND l 0 l
, *].Br-85El1 ,ND l ND l2.53E1 l ' ND l ND l - ND l 0 l-f: El}Rb-86-l= ND' - l l'. 9 BE5 11.14E5 l - ND l ND l ND 17.99E3 l P l Rb-88 l ND l5.62E2 13.66E2 ! ND l ND l 'ND 11.72E1 l
. l Rb-89 l- ND -l3.45E2' l2.90E2 l ND l ND l ND l1.89E0 1
- g. l Sr-89;l5.99E5 l. ND l1.72E4 l ND l ND l2.16E6 ll.67E5 l C -l ;Sr-90 l1.~01E8: l _ ND l6.44E6 l ND l ND l1.48E7 l3.43E5 -l h l Sr-91 l1.21E2 l ND l4.59E0 i ND l ND 15.33E4 l1.74ES. l in: 1: Sr-92 l1.31El -l ND 15.25E-1 l ND l ND l2.40E4 l2.42E5 l g'?'g-lY-90 14.11E3 l ND l1.11E2 l ND l ND l2.62E5 l2.68E5 l
; =?f -
e.g, -
*S
k 'APA-ZZ-08009
-, Rev. O y
~
[ TABLE 5 (Cont'd.)
' PATWAY. DOSE FACTORS -(R g ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" y 4 Inhalation Pathway i;
.(mrem /yr) per (yCi/m ) 8 l1 . l..
- l. l Total l l .l . l . . l' lNuclidel Bone. I Liver' l Body l Thyroid l Kidney l Lung l GI-LLI-l
=
. 'l~Y-91m '5.07E-1 l' ND.
~
'l1.84E-2 l ND l' ND l2.81E3 l1.72E3 l~
l Y 9.14E5 l ND l2.44E4 l ND l ND l2.63E6 -l1 84ES- l
.-l Y-92 l2.04E1 l ND l5.81E-1 l ND l ND l2.39E4 l2.39E5- l-l Y-93 l1.86E2 lz ND l5.11E0 l ND l ND l7.44E4 l3.89ES. l.
- l1 Zr-95 . l 1'. 90E5 - l4.18E4 l3.70E4 l ND l5.96E4 -l2.23E5 ~ l 6.~11E4 l l Zr-97--l1.88E2 l2.72E1 l1.60E1 l ND l3.89El 11.13E5 -l3.51E5 l j.Nb-95 l2.33E4 l9.18E3 .l6.55E3 l ND l8.62E3- l6.14E5 l3.70E4 l l Mo-99 l- ND- l1.72E2 l4.26El l ND l3.92E2: l1.35ES l1.27ES l.
l Tc-99mll'.78E-3 l3.48E-3 l5.77E-2 l ND l5.07E-2 l9.51E2 l4.81E3 l
'l Tc-101l8.10E-3.l~,. . -5 l1.08E-3 l ND l1.45E-3 l5.85E2 l1.63E1 l il:Ru-103l2.79E3 l~ ND- l1.07E3 l -ND l7.03E3 16,62E5 l4.48E4' l
.l.Ru-105{1.53E0 l ND l5.55E-1 l ND l1.34E0 l1.59E4 l9.95E4 l
.I Ru-106l1.36ES..l ND l1.69E4- l ND l1.84E5 l1.43E7 14.29ES -l
..l Ag-110m l1.69E4 l1.14E4 l9.14E3 .l' . ND l2.12E4 l5.48E6 l1.00E5 l
'lLCd-109l.yND. -l5.48E5 .l2.59E4 'l ND 14.96E5 =l1.05E6 l2.78E4 l s l Sn-113l1'.13E5L l3.12E3 l8.62E3 l 2. "33E3 l ND l1'.46E6 l2.26E5 -l Jl Sb-124l5.74E4 -l7.40E2 l2.00E4 l1.26E2 l ND l3.24E6 l1.64E5= l
'l1Sb-125l9.84E4 -l7.59E2 -l2.07E4 19.10E1 l ND l2.32E6 l4.03E4 l 1
-lTe-125ml6.73E3 l2.33E3 19.14E2 l1.92E3 l ND l4.77ES 13.38E4- l-
-g lTe-127ml2.49E4 l8.55E3 l3.02E3 l6.07E3 l6.36E4 11.48E6 l7.14E4' l
. l Te-127 l 2. 7 7E0 l9.51E-1 16.11E-1 l1.96E0 l7.07E0 l1.00E0 15.62E4 l
'lTe-129ml1.92E4 l6.85E3 l3.04E3 16.33E3 l5.03E4 l1.76E6 l1.82E5 l l Te-129 .' l 9 '. 77E-2 : 13.50E-2'-l2.38E-2 l7.14E-2 l2.57E-1 l2.93E3 -l2.55E4 l-lTe-131ml1.34E2 l5.92E1 l5.07El l9.77El l4.00E2 -l2.06E5 l3.08E5- l
'lTe-131 l2.17E-2 l8.44E-3 l6.59E-3 l1.70E-2 l5.88E-2 l2.05E3 l1.33E3 -l
'lTe-132;l4'81E2 12.72E2 l2.63E2 -l3.17E2 l1.77E3 13.77ES l1.38E5 l-
<l I'-130.' . l 8.18E3 - l1.64E4 l8.44E3 ll.85E6 l2.45E4 l ND l5.11E3 l
;lI-131 -l4.81E4 l4.81E4 l2.73E4 11.62E7 l7.88E4 l ND l2.84E3 l
- lI-132 l2.12E3- l4.07E3 11.88E3 l1.94E5 l6.25E3 l ND [3.20E3 l 3 :lI-133~ l1.66E4 l2.03E4 17.70E3 l3.85E6 13.38E4 l ND l5.48E3 l d3Qy-'lI-134 .l1.17E3 l2;16E3 19.95E2 l5.07E4 l3.30E3 l ND l9.55E2 l E _ _ _
fl;! % v R v.. O f}m ,
+ j!
~
, c p:, ,
~1 i -
TABLE 5'(Cont'd.) i 9 g -. PATHWAY. DOSE. FACTORS.(R g ) FOR RADIONUCLIDES OTHERLTHAN NOBLE GASES" -f g ' 1 S Inhalation Pathway' q (mrem /yr)-per (pCi/m8 ) [ ;f t .
..I l . l l Total l. l l l- .
.l- ;
4 lNuclidsi' Bone l Liver i Body l Thyroid l Kidney l Lung l GI-LLI l. -e, $ lI-135_l4.92E3 l8.73E3 l4.14E3 17,92E5 l1.34E4 -l ND l4.44E3 l l
- j. . lCs-134.l6.51ES -l1.01E6 l2.25ES l ND l3.03E5 l1.21E5- l3.85E3 -l ,
llCs-136 l6.51E4 l1.71ES l1.16E5' l ND l9.55E4 l1.45E4 l4.18E3 l ; _lCs-137 l9.07E5 l8.25ES: l1.28E5 l ND l2.72E5 -l1.04E5 l3.62E3 l ~'
.lCs-138 l6.33E2'.l8.40E2 l5.55E2 l ND l6.22E2 l6.81El -l2.70E2 _l ,
T lBa-139 l1.84E0- l9.84E-4 l5.37E-2 l ND 18.62E-4:l5.77E3 l5.77E4 tl i l?s-140 l7.40E4- l6.48E1 14.33E3 I ND .l2.11El l1.74E6 .l1.02E5 l'
-.J lba-141 l2.19E-1-l1.09E-4 .l6.36E-3 1. ND-
'l9.47E-5-l2.92E3 _l2.75E2 ~l-I lBa 142.l5.00E-2 'l3.60E-5 l2.79E-3l ND l 2. 91E-5 -- l 1. 64E3 -l2.74E0~.l j .sp-lLa-140=l6.44E2 l2.25E2 l7.55El l ND l ND. l1.83E5 l 2.26ES . : l' '!
lLa-142 l1.30E0 l4.11E-1 l1.29E-1 l ND 'l ND [8.70E3 l7.59E4' l '.
. lCe-141'j3.92E4 l1.95E4 l2.90E3 l- ND l8.55E3 15.44E5 -l5.66E4 l-lCe-143 l3.66E2 l1.99E2 l2.87El l ND l8.36El l1.15E5 'll.27E5 j l <
_lCe-144-l6.77E6 .l2.12E6 l3.61E5 l ND l1.17E6 l1.20E7 l3.89E5 l q J lPr-143 l1.85E4l5.53E3 ~ l9.14E2 .l ND. 'l3.00E3- l4.33E5 l9.73E4 l- [ k lPr-144 l5.96E-2-l1.85E l3.00E-3 l ;ND .'j9.77E-3 [1.57E3 11.97E2 l
.lNd-147 l1.08E4' l8.73E3 l6.81E2 -l - ND l4.81E3 l3.28E5 l8.21E4 l t
; leu-154 l1.01E7e ir.21ES l8.40E5 l ND l4.03E6 l6.14E6 ll.10E5 l .i
~lHf-181 l2.78E4 l1.01E5' l1.25E4 l- ND l2.05E4 l1.06E6 l6.62E4 l 1
" lW-187 :l1.63E1 l9.66E0 l4.33E0 l ND~ 'l ND l4.11E4 l9.10E4- l d
- lNp-239 l4.66E2 l3.34El' l2.35El l ND 19.73E1 l5.81E4 l6.40E4 l (a)" The child. age group; refer to reference 11.14.5.
,f s 7 o p
^
n r! .
- 9) .
H :: . ri - i 4 ll m ; t! a, r , 3 ;,
' 1 y
P3 N'?
,. Rsv. 0-OM; , J >
. v. ,
y fjjl > s
, . TABLE 5 (Cont'd.)
5+ PATWAY DOSE FACTORS'-(Rg): FOR RADIONUCLIDES' OTHER.THAN' NOBLE GASES" y s <w i 1 ,;'!; \ Ground Plane Fachway i(m8 . mrem /yr) per (1:01/sec) ki ' Nucifde Total Body' -Skin i b ' B'e -7 2.24E7 3.21E7 i ~Na-24 1.19E7- 1.39E7-1 Cr-51 4.55E6 5. 51E6 '
<Mn-54, 1.39's.9 1.63E9 Mn-56' 9.03E5 1.07E6 Fe-59 2.72E8 3.20E8 s 'Co-57' '2.98E81 4.37E8' i Co-58 3.79E8 4.44E8 Co-60 2.15E10- 2.53E10~ .. Ni-65 .2.97E5 3.45ES
[., fi , N Cu-64 Zn-65 6.07ES. 7.47E8. 6.88E5' ' 8.59E8 .. Br-82 3.14E7 4.49E7 Br-83' 4.87E3 7.08E3 Br-84 2.03E5 2. 36E5.' -Y ' Rb-86 8.99E6- 1.03E7 < ~Rb-88 3. 31E4 3.78E4 L .. , Rb-89' 1.23E5 1.48E5 c Sr-89 2.16E4 2.51E4
?l Sr-91 2.15E6- .: .51E6 j
'i r -9 2 - 7.77E5 8.63E5
'.-90 4.49E3 5.31E3 Y-91m 1.00E5 1.16ES Y-91 1.07E6 1.2126 <
0 Y-92 1.80E5 2.14E5 1.
' U Y-93 1.83E5 2.51ES g
d Zr-95 2.45E8 2.84E8 Zr 2.96E6 3.44E6 Nb-95 1.37E8 1.61E8 ci gj ' Mo-99 ~3.98E6 4.62E6 -- Q : 7, i: .<...
.i n '.
- 7 ' 7 ;
fj _ '"' h 8 Y,
. - --- ~<
,e fij Roy. 0 g1 m
S: E' '
} , Eh .
g:E
- TABLE 5 (Cont 'd. ) -
, i j
;L S; PATIN&Y DOSE FACTORS -(R ):g FOR RADIONUCLIDES OTHER THAN NOBLE GASES"'
Ground Plane Pathway! d,' <
- (m2 mrem /yr) per (UC1/ss')
Nuclide- -Total-Body: __ skin
* 't Tc-99m' 1.84E5 2.11ES
( Tc-101- 2.04E4: 2.26E4 ,
'p 'Ru-103 1.08E8 1;26E8 ,
Ru-105' -6.36ES 7.21E5' , Ru-106 4.22E8 5.07E8 j 1
/Ag-110m' '3.44E9 4.01E9 '!
- 6. Cd-109 3.76E7 1.54E8 ;
Sn-113' 1;43E7 4.09E7 .I Sb-124 8.74ES= 1.23E9 Sb-125 3.57E9, '5.19E9
.Te-125m 1.55E6 2.1'3E6 < ,i Te-127m: 9.16E4 .1.08E5 1 Te-127
~ 2.98E3 3.28E3 Te-129m- 1.98E7 2.31E7 Te-129 2.62E4 3.10E4 Te-131m 8.03E6 9.46E6- i Te-131 ~2.92E4 3.45E4
.Te-132 4.23E6 4.98E6 <
33 I-130 5.51E6 '6.69E6 I-131
'~
1.72E7 2.09E7 I-132 1.23E6 1.45E6 - J I-133 2.ASE6 2.98E6-T I-134 .4.,7ES 5.30E5 l I-135 '2.51E6 2.93E6 Cs-134, 6.86E9 8.00E9 4 a Cs-136 1.53E8 1.74E8, Cs-137 1.03E10 1.20E10 Cs-138 3.59E5 4.10E5 Ba-139 1.06E5 1.19E5 Ba-140 2.05E7 2.35E7
\
4 *g
., f e
g m: -g T Y
I1 , s .Q ' > p m:; zw ..... .. .. ..
~
t nwy R:v. 0 - l ( . j.' , in .A LF , . b u-
< , TABLE 45-(Cont'd.) .
,r 3
,i . .
, LPATHWAY> DOSE FACTORS;(R g
)sFOR RADIONUCLIDES 0THER THAN NOBLE GASES".
- . c t >y Ground Plane Pathway
, ,.i
.h
-)
(m* mrem /yr) per (pCi/sec). i a
,, 'Nuclide- Total Body. -Skin ,
'Ba-141 4.15E4 4.73E4.
Ba-142 4.44E4 5.06E4 >
'La-140 -1.92E7- 2.18E7 La-142 7.40E5 8.89E5 1 Ce-141 11.37E7 1.54E7 >
Ce-143 .2.31E6 2.63E6 i Ce-144 6.96E7- 8.04E7 Pr-144- 1. 84F.3 .- 2.11E3' Nd-147 8.41E6 [ 1.01E7
- Eu-154. '2.21E10 3.15E10 4 ; '
Hf-181. l'.97E8 2.82E8 ' W-187 2.36E6 2.74E6 ., < Np-239 1.71E6 1.98E6 -!
', - (a)" Refer. to- reference 11.14.5 for calculational details. T, 1
i l 2- -l l p o , ft I 9. f aq 20) 4 y- __ i i 1.- I
.# m . .,. . . _ . . ~
i '
.i -
_ . _ _ _ _ _ _ _ _ _ , _ _ _ _ . . , .l
). R v. 0 1
TABLE 5 (Cont'd.)
$ PATHWAY DOSE FACTORS (R g ) FOR' RADIONUCLIDES OTHER THAN NOBLE GASES" ; Meat Pathway f (m8 mrom/yr) per (VCi/sec) t I I I I Total l l l l l lNuclidel Bone l Liver l Body i Thyre,id 1 Kidney 1 Luna 1 GI-LLI l I, -
l H-3 L ND l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l l Be-7 1 7.37E3 l1.26E4- l8.06E3 l ND l1.23E4 l ND l7.00E5 l
-; - l C-14 3.83E8 17.67E7 l7.67E7 l 7. 67E'! l7.67E7 l7.67E7 17.67E7- l Na-24 1.78E-3 l1.78E-3, l1.78E-3 l1.78E-3 1.78E-3 l1.78E-3 l1.78E-3 l P" l7.41E9 l3.47E8- l2.86E8 l ND ND l ND l2.0$E8- l-l Cr 51-l ND l ND 18.79E3 l4.88E3 l1.33E3 l8.91E3 l4.66ES l l Mn 54 ND- l8.01E6 l2.13E6 ND l2.25E6 l ND l6.72E6 l
- l Mn-56 l ND l 0 l. O ND l 0 l ND l 0 l P
l Fe-55 l4.57E8 .l2.42E8 l7.51E7 i ND l ND l1.37E8 l4.49E7 l-i Fe-59.l3.76E8 l6.09E8 13.03E8 l ND 1 ND l1.76E8 l6.34E8 l
. s, l Co-57 l ND l5.92E6 l1.20E7 l ND l ND l ND l4.85E7 l '
l Co-58 l= ND l1.54E7 l5.02E7 l ND l ND l ND ! 9.58E7 .l l Co-60 l ND l6.93E7 l2.04E8 l ND l ND l ND 1 3.84E8- l
, Ni-63.l2.91E10 l1.56E9 -l9.91E8 l ND l ND l ND L1.OSES l l Ni-65'l, O l 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 l ND 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 1 0 l' O l ND l 0 l ND l 0 l l Br-82 ND l ND l1.52E3 l ND l ND l FD l ND l l Br-83 l ND l ND l ND l ND l ND l ND l ND l l,Br-84 l ND l ND l ND l ND l ND l ND l ND l 4 Br 85 I ND l ND l ND l ND l ND l ND l ND l l Rb-86' ND l5.82E8 l3.58E8 l ND l ND l ND l3.74E7 l
.- l Rb-88 ND l 0 l. 0 l ND l ND l FD l 0 l
[ l Rb-89 l~ ND l 0 l 0 l ND l ND l hD l 0 l (. l.Sr-89.'4.82E8 l ND l1.38E7 l ND l ND l ND ll.86E7 l l 3r-90 l1.04E10 l ND l2.64E9 l ND l ND l ND l1.40E8 l
-l Sr-91 l2.40E-10l ND l 0 l ND l ND l ND [5.29E-10l
,; l Sr-92 l 0 l ND l 0 l ND l ND l ND l 0 l j
l Y-90 l1.71E2 l ND l4.59E0 l ND l ND l ND l4.88E5 l p 1 s l' M W
$ ' .i J
~ ~
R$v. ~b TABLE 5 (Cont'd.) L [ PATINAY DOSE FACTORS (Rg ),FOR RADIONUCLIDES OTHER THAN NOBLE GASES" Meat Pathway
. (m8 mrem /yr) per (pC1/sec) l l l l Total l l l l l lNuclidel Bone l Liver I tody i Thyroid l Kidney l Luna i GI-LLI l l Y-91m l 0 l ND l 0 l ' ND l ND l ND l 0 l l Y-91 l1.00E6 l ND l4.82E4 l ND l ND l ND l2.40E8 l l-Y-92 l 0 l ND l 0 l ND l ND ND l 0 l l Y-93 l 0 l ND l 0 l ND l ND d ND l1.55E-7 l l Zr-95 l2.66E6 l5.85ES l5.21E5 l ND l8.38E5 l ND l6.11E8 l l Zr-97 l3.20E-5 l4.63E-6 l2.73E-6 l NP l6.65E-6 l ND l7.02E-1 l l Nb-95 l3.09E6 l1.20E6 18.61E5 l Nb l1.13E6 l ND l2.23E9 l l Mo-99 l ND l1.15ES l2.84E4 l ND l2.46E5 l ND l9.51E4 l l Tc-99ml 0 l 0 l 0 ND l 0 l 0 l 0 l l.Tc-101l 0 'l 0 l 0 ND l 0 l 0 l 0 l l Ru-10311.55ES l ND l 5.96E7 l ND l3.90E8 l ND l4.01E9 l .,
l Ru-105ll 0 l ND' , O l ND l 0 l ND l 0 l l Ru-106l'4.44E9 l ND H5.54E8 l ND l5.99E9 l ND l6.90E10 l lAg-110m 8.40E6 l5.67E6 l4.53E6 l ND l1.06E7 l ND l6.75E8 l lCd-109 ND l1.90E6 l8.83E4 l ND l1.70E6 l ND l 6.18T,6 l
- lSn-113 l2.18E9 l4.48E7 l1.24E8 l3.31E9 l ND l ND l1.54E9 l lS6-124 12.93E7 l3.79E5 l1,02E7 l6.45E4 l ND l1.62E7 l1.83E8 l
- lSb-125-l2.85E7 l2.20E5 l5.97E6 l2.64E4 l ND l1.59E7 l6.80E7 l
- lTe-125ml5.69E8 l1.54E8 l7.59E7 l1.60E8 ND l l ND l5.49E8 l
- lTe-127ml1.77E9 l4.78E8 l2.11E8 l4.24E9 l5.06E9 l ND l1.44E9 l
. lTe 127 l4.11E-10l1.11E-10 l 0 l2.85E-10 l1.17E-9 l ND l1.61E-8 l Te-129mll.79E9 l4.99E8 l2.77E8 l5.76E8 l5.2SE9 l ND l2.18E9 l
- Te-129 l_ 0 l 0 l 0 l 0 _l 0 l ND l 0 l lTe-131ml7.00E2 l2.42E2 l2.58E2 l4.98E2 l2.34E3 l ND l9.62E3 l
- lTe-131~i 0 l 0 l 0 l 0 l 0 l ND l 0 l .
lTe 132 l2.09E6 l9.26ES l1.12E6 l1.35E6 l8.60E6 l ND l9.33E6 l ! lI-130. l3.04E-6 16.13E-6 l3.16E-6 l6.76E-4 19.17E-6 l ND l2.87E-6 l lI-131 l1.66E7 l1.66E7 19.46E6 l5.50E9 l2.73E7 l ND l1.48E6 l lI-132 l 0 l 0 l 0 l 0 l 0 l ND l 0 l lI-133 l6.16E-1 l7.61E-1 l2.88E-1 l1.41E2 l1.27E0 l ND l3.07E-1 l
. lI-134 l 0 l 0 l 0 l 0 l 0 l ND l 0 l l ' %
m, ul .
~
L ,
= Av t
QXx ' R*V 0 l l3 ! . ,
!I j , -c L + ;
L "- TABLE 5 (Cont'd.) i
. . l
< PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" 1
," , i Meat Pathway )
.c l
,1 (m8 mrom/yr) per (VCi/sec) iT l l l l Total l l l l :l ,
I
.alNuclidel Bono 1 Liver I Body l Thyroid I Xidney I Lung l GI-LLI i i f
p i I-135 l- 0 Cs 134 l9.22E8 l 0 1 0 l 0 1 0 -l ND l 0 l
- l1.51E9 l3.19E8 l ND. l4.69E8 11.68E8 L8.16E6 O Cs-136 l1.61E7 l4.43E7 l2.86E7 l ND ;l2.36E7 13.51E6 '1.56E6- j i L Cs-137 l1.33E9 l1.28E9 1.88E8 l ND 14.16E8 l1.50E8 7.99E6. l 'i
- p. 1 IC 138 l- 0 1 0 0 l ND l 0 j 0 1 0 l -
s! lBa-139 l 0 l 0 l 0 ND 0 0 0 l l l l !
-lBa-140 [4.38E7 l3.84E4 2.56E6 ~1 ND l1.25E4 l2.29E4 12.22E7 l lBa-141 l 0 l .0 0 ND l 0 l 0 'l 0 ;
3 'jBa-142 l O' l. 0 l 0 ND l 0 l 0 lt 0 l ', r lLa 140'l5.69E-2 l1.99E-2 l6.70E-3 ND l ND l ND l5.54E2 l !
,g !
g . lLa-142 l 0 ^l 0 l 0 l ND l ND l ND l 0 l lCo-141 l2.22E4 ;ll.11E4 . 1 1.64E3 l ND l4.85E3 l ND l1.38E7 l- : lCo-143. 3.17E-2 l1.72E1 2.49E-3 l ND l7.21E-3 l ND l2.52E2 l-
-lCo-144 ; 2.32E6 l7.26E5 l1.24E5 l ND l4.02E5 l ND l1.89E8 1 i lPr-143 l3.35E4 l1.' 00E4 '1.66E3 l ND l5.44E3 l ND l3.61E7 l lPr-144 1 0 l _0 l 0 l ND L 0 ND l 0 l lNd-147 1.17E4 l9.50E3 17.35E2 l ND '5.21E3 ND l1.50E7. l- i lEu-154 1.12E7 l1.01E6 l9.20E5 -l ND :l4.42E6 ND l2.34E8 l .
.-lHf 181 l 4.76E6 l1.73E7- l2.15E6 l ND 1 3.52E6 l ND l6.40E9 l
.lW-187 l3.35E-2 l1.98E-2 l8.91E-3 l ND ND. ND l2.79E0 l ;
lNp-239 l4.20E-1 l3.02E-2 l2.12E-2 l ND l:8.72E-2 , ND l2.23E3 l i
, (a)- The child age' group; refer to reference 11.14.5.
y 1 b ! ? b i & w ) 1 q;;. . l \ r a
-)
b .R;v. 0-k- n y, , s L TABLE 5 (Cont'd.) PATHWAY DOSE FACTORS (R g ) FOR RADIONUCLIDES OTHER THAN NC8LE GASES"
^
Grass-Cow-hilk Pathway
.. (m8 mrem /yr) per (VCi/sec).
'l- l l Total l l. l l l
;lNuclidel Bone Liver l Body i Thyroid i Kidney I Luna l GI-LLI l 7' l'H 3 l:ND l1.57E3 l1.57E3 l1.57E3 l1.57E3- l1.57E3 '1.57E3 l I Be-7 l7.49E3 l1.28E4 l8.19E3 l ND l1.25E4 ND 7.11ES I
.' I C 14. l1.19E9 l2.39E8 l2.39E8 l2.39E8 12.39E8 ; 2.39E8 l2.39E8 Na-24 l8.89E6 l8.89E6 l8.89E6 l8.89E6 8.89E6 l8.89E6 18.89E6 h, P 32 l7.77E10 l3.64E9 l3.00E9 l ND l ND l ND l2.15E9 l
i: l'Cr51' ND ll ND l1.03E5 5.65E4 l1.56E4 l1.04E5 l5.40E6 a
.l Mn-54 i ND- 2.10E7 l5.59E6 ND l5.88E6 l ND l1.76E7 I h; l Mn 56.i ND- 1.29E-2 l2.90E 3 l ND l1.56E-2 l ND 1.86E0
- o. .l?Fe-55 i1.12E8 5.93E7 l1.84E7 l ND l ND l3.35E7 1.10E7 f l Fe 59 l1.20E8 .1.94E8 l9.69E7 l ND l ND l5.64E7 l2.02E8 I
~Y l Co-57 ' ND l3.84E6 1 7.76E6 l ND l ND l ND 13.15E7 )
l Co-58' ND -l1.21E7 i 3.71E7 l ND l ND l ND 17.07E7 l Co-60; ND- l4.32E7" 1.27E8 l ND l ND ' ) ND - 2.39E8 l
-Ni-63 l 2.96E10 l1.59E9 1.01E9 l ND l ND l ND 1.07E8 1 . l:Ni 65'll.66E0 -l1.56E-1 l9.01E-2 l ND l ND l ND l1.91El ,
3 Cu-64'! ND l7.46E4 l4.51E4 l ND l1.80E5 l ND' l3.50E6 l [ Zn-65R 4.13E9 l1.10E10 l6.85E9 l ND' l6.94E9 l ND l1.93E9 l 0 2n 69_, O l 0 l 0 l ND l 0 l ND l1.12E-9 l 3 i Br 82 l' ND l ND l1.15E8 l ND l ND l ND ND l'Br 83'l ND l ND l ND l ND l ND l ND- ND l Br 84 l ND' l ND l ND l ND l ND l ND ll ND l
- 1. 4 - l Br 85 l ND l ND l ND l ND l ND l ND l ND l l Rb-86 ND l8.80E9 l5.41E9 l ND l ND l ND : 5.66E8 l 1 l Rb-88 , ND l 0 l 0 l ND l.ND l ND 0 l f l Rb 89 ) ND l 0 l'O l ND l ND l ND l: 0 l ,
V W l.Sr-89=l6.62E9 l ND l1.89E8 l ND l ND i ND l2.56E8 l [ 'l Sr 90-l1.12E11 l . ND l2.83E10 l ND l ND l ND l1.51E9 l , l<St-91'l1.30E5 l ND l4.92E3 l ND l ND l ND l2.88E5 l L, . l Sr-92 l2.18E0: l ND l8.75E-2 l ND l ND l ND 14.13E1' l l Y-90 l3.22E2 l ND l8.62E0 ND l ND ' l ND l9.17ES { l l y p .J
, -i
, . v ~
n . . , , . , -
~
l- 'APA-ZZ-01003 R;v. 0 l' TABLE 5 (Cont'd.) a i' PATWAY DOSE TACTORS. (Rg) TOR RADIONUCLIDES OTHER THAN NOBLE GASES i Grass-Cow-Milk Pathway (m8 mrem /yr) per (VCi/sec', l l l l Total l l l l l 3 p lNuclidel Bone i Liver l Body l Thyroid l Kidney l Lung l GI-LLI l l b - l.Y-91m l 0 l ND l 0 ND l ND ND l 0. l l Y-91 l3.90E4 l ND l1.04E3 ND l ND ND 15.20E6 l Y-92, l2.53E-4 l ND l7.24E-6 l ND l ND ND 17.31E0 , l Y-93 l1.0$E0 l ND l2.90E-2 l ND l ND ll ND l1.57E4 l l 2r-95 l3.85E3 l8.42E2 l7.50E2 l ND l1.21E3 l ND l8.79E5 l 1 l Zr47 l1.92EO. l2.77E-1 l1.64E-1 l ND l3.98E-1 l ND l4.20E4 l l Nb-95 l3.18E5 l1.24E5 l8.84E4 l ND l1.16ES l ND l2.29E8 l i l Mo-99 l ND l8.14E7 l2.01E7 l ND l1.74E8 l ND 16.73E7 -; l'Jc-99ml1.32E1 l2.59El l4.29E2 l ND l3.76E2 l1.32E1 l1.47E4 ' 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 t l Ru-105l3.82E-3 l ND l1.39E-3 l ND 13.36E-2 l ND l2.49E0 l Ru-106l9.24E4 ND l1.15E4 l ND l1.25E5 l ND l1.44E6 , lAg-110ml2.09E8 . 1.41E8 l1.13E8 l ND l2.63E8 l ND l1.68E10 l lCd-109'l ND l3.86E6 l1.79ES l ND l3.45E6 l ND l1.25E7 l lSn-113 l6.10E8 l1.25E7 l3.48E7 l9.27EB l ND l ND l4.31E8 l lSb-124 l1.08E8 l1.41E6 l3.81E7 l2.40E5 l ND l6.03E7 l6.79E8 l lSb-125 l8.70E7 l6.71ES l1.83E7 l8.06E4 l ND l4.85E7 l2.00E8 l lTe-125ml7.38E7 l2.00E7 l9.84E6 l2.07E7 l ND l ND l7.12E7 l lTe-127ml2.08E8 l5.60E7 12.47E7 l4.97E7 l5.93E8 l ND l1.68E8 l ! lTe 127'l3.05E3 l8.22E2 l6.54E2 l2.11E3 l8.67E3 l ND l1.19ES l lTe-129ml2.71E8 l7.57E7 l4.21E7 l8.74E7 l7.96E8 l ND 13.31E8 l lTe-129 l 0 l 0 l '0 l 0 l2.90E-9 l ND l6.17E-8 l , lTe-131ml1.60E6 l5.53E5 l5.89ES l1.14E6 l5.35E6 l ND l2.24E7 l l- lTe-131 l 0 l 0 l 0 l 0 l 0 l -ND l 0 l , lTe-132 l1.02E7 l4.52E6 15.46E6 l6.58E6 l4.20E7 l ND 14 35E7 l l lI-130.:ll.73E6 l3.49E6 l1.80E6 l3.84E8 l5.22E6 l ND l1.63E6 l lI-131 l1.30E9 l1.31E9 l7.45E8 l4.33E11 l2.15E9 l ND l1.17E8 l lI-132 l6.02E-1 l1.11E0 l5.08E-1 l5.13E1 11.69E0 l ND l1.30E0 l _lI-133 l1.74E7 l2.15E7 l8.13E6 13.99E9 l3.58E7 l..ND l8.66E6 l q3 lI-134 l 0 l 0 l 0 l 0 l 0. l ND l 0 l 1
-s: 3 I
56 -
APA.ZZ-01003 ; Rw. 0 , ( TABLE 5 (Cont'd.)
?ATHWAYDOSEFACTORS(Rj)'FOR~RADIONUCLIDESOTHERTHANNOBLE~ GASES" Grass-Cow-Milk Pattway r (m' mrem /yr) per (VCi/sec) l l l l Total l l l l l lFuelfdel Bone l Liver i Body l Thyroid l Kidney l Lunz l GI-LLI l l1-135 l5.40E4' l9.72E4_ l4.60E4 i8.61E6 l1.49E5 l ND 17.40E4 l lCs-134 12.26E10 l3.72E10 l7.84E9 l ND l1.15E10 l4.13E9 l2.00E8 l i lCs-136 l1.01E9 12.77E9' l1.79E9 l NL l1.48E9 l2.20E8 l9.74E7 l lCs-137 l3.22E10 13.09E10 l 4 '. 56E9 l ND l1.01E10 l3.62E9 l1.93E8 l lCs 138 l- 0 l 0 l 0 l ND l 0 l 0 l 0 l lBa-139 11.89E-7 l 0 l5.48E-9 l ND l 'O l 0 l1.09E-5 l lBa-140 l1.17E8 11.03E5 l6.84E6 l ND l3.34E4 l6.12E4 l5.93E7 l lBa-141-l 0 l 0 l 0 l ND l 0 1 0 l 0 l 4 '-
lBai142 l 0 l 0 l 0 l ND l 0 l 0 1 0 l lLa-140 l1.95El l6.80E0 l2.29E0 l ND l ND -l ND l1.90E5 l . ; lLa-142. l- 0 l 0 l 0 l ND l ND l ND l2.90E-6 l l lCe-141-l2.19E4 l1.09E4 l1.62E3 l ND l4.78E3 l ND l1.36E7 l l1,02E5
' lCe-143 l1.87E2 l1.47El l ND l4.26El l ND l1.49E6 l ;
lCo-144 l1.62E6 l5.09ES 18.66E4 l ND l2.82E5 l ND l1.33E8 l lPr-143 l7.19E2 l2.16E2 l3.57El l ND ' l1.17E2 l ND 17.75ES l Pr-144 l 0 l 0 l 0 l ND l 0 l ND l 0 l
!Nd-147-l4.45E2. l3.61E2 l2.79El l ND l1.98E2 l ND l5.71ES .l lEu-154 l9'41E4 l8.47E3 l7.73E3 l ND 13.72E4 l ND l1.97E6 l lHf-181 16.43E2 l2.35E3 l2.90E2 l ND l4.75E2- l ND l8.65E5 l lW-187 l2.91E4 11.73E4 l7.73E3 l ND l ND l ND l2.42E6 l lNp-239 l1.72E1 l1.23E0 l8.68E-1 l ND 13.57E0 l ND l9.14E4- l (a) The child age group; refer to reference 11.14.5.
E p .
- u. ,
Np
~
j s
'" APA-ZZ-01003 Rev. O i
TABLE 5 (Contd.) PATHWAY DOSE TACTORS'(R g ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES
- Grass-Goat Milk Pathway ,
[ r (m' arem/yr) per (VCi/sec) t I l l l l Total l l l l l' [ lNuclide1 Bone l Liver i Body l Thyroid I-Kidney I Lung l GI-LLI l l H-3 l ND l3.20E3 l3.20E3 l3.20E3 l3.20E3 l3.20E3 l3.20E3 l l Be-7 {8.98E2 l1.53E3 19.82E2 l ND l1.50E3 l ND 18.53E4 l ; F l C-14 l1.19E9 l2.39E8 l2.39E8 l2.39E8 l2.39E8 l2.39ES l2.39E8 l l Na-24 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l1,07E6 l1.07E6 l l P-32 l9.33E10 l4.37E9 l3.60E9 l ND l ND l ND l2.58E9 l
-l Cr-51 l ND l ND l1.23E4 l6.78E3 l1.87E3 l1.25E4 16.48E5 l
-l Mn-54 l ND l2.52E6 l6.70E5 l ND l7.06ES I ND l2.11E6 l
_' , g", l Mn-56 ND l1.54E-3 l3.49E-4 l ND l1.87E-3 l ND l2.24E-1 l l Fe-55 1.45E6 l7.71E5 l2.39ES l ND l ND 14.36ES l1.43E5 l l.Fe-59 11.56E6' l2.53E6' ll.26E6 l ND l ND l7.33E5 l2.63E6 l .- 4 l Co-57 l ND l4.60ES. l9.31ES l ND l ND l ND 13.77E6' l - l Co-58 l ND l1.45E6 l4.45E6 l ND l ND l ND l8.49E6 l
-l Co-60-l ND l5.18E6 l1.53E7 l ND l ND l ND l2.87E7 l l Ni-63 l3.56E9 l1.90E8 l1.21ES l ND l ND l ND l1.28E7 l l:Ni-65.l1'.99E-1 l1.87E-2 l1.09E 2 l ND l ND l ND l2.29E0 l i l Cu-64 l ND l8.31E3 l5.02E3 l ND l2.01E4 l ND l3.90E5 l
+
l Zn 65 l4.96E8 l1.32E9 l8.22E8 l ND l8.33E8 l ND l2.32E8 l , l.Zn 69 l 0 0 l 0 l ND l 0 l ND l1.35E-10l 5 l Br-82 l ND ND l1.38E7 l ND l ND l ND l ND l l Br-83 l lND 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. I ND l ND l l Br-85 l ND l ND l ND l ND l ND l ND l ND l 3
.l'Rb-86 l ND l1.06E9 l6.50E8 l ND l ND l ND l6.80E7 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 l1.39E10 l ND 13.97E8 l ND l ND l ND l5.38E8 l l'Sr-90 l2.35E11 l ND l5.95E10 l ND l ND l ND l3.16E9 l l Sr-91 l2.74E5 l ND l1.13E4 l ND l ND l ND l6.04E5 l C ,
.. i
T ., t r APA ZZ-01003 i [ R v. 0 l 4: , l' TABLE 5 (Contd. ')
^ '
PATHWAY DOSE TACTORS (Rg ) TOR RADIONUCLIDES OTHIR~THAN' NOBLE GASES * [s 7 Grass-Goat-Milk Pathway
!. (m8 mrom/yr) per (VCi/sec)
!.' a p ..
~
U l . l l . l Total l l l l" - lNuclidel Bone l Liver l Body l Thyroid Kidney l . Luna l GI-LLI I .' l Sr 92-l4.58E0 l ND l1.84E-1 ND l ND l ND. l8.6SE1 l p; l-Y-90 l3.87El l . ND l 1.03E0 ND l ND :l ND l1.10E5 l
! l Y-91m l 0 ND 0 ND l ND l ND l 0 l l Y 91 l4.68E3 ND : 1.25E2 ND l ND ND l6.24E-5 l Y 92 l3.04E-5 ll ND 18.69E-7 l ND l ND L ND l8.77E-1
.l Y 93 l1.27E 1 l ND l3.48E-3 l ND l ND l ND l1.89E3 .l.
F ll 2r-95 l4.60E2 l1.01E2 '9.00El- ND l1.45E. l ND l1.05ES 2r-97-l2.30E-1 l3.33E 2- l1.96E-2 ND l4.78E-2 l ND l5.04E3 Nb-95 l3.81E4 l 1.48E4 '. l1.06E4 l ND l1.39E4 l ND l2.75E7 1 Mok99 l ND l9.76E6 l2.42E6 i ND l2.09E7 l ND .l8.08E6 l . l Tc-99ml1.59E0 3.11E0 15.15El l ND l4.52E1 1.58E0 l1.77E3 l Tc-101l 0 0 l 0 l ND l 0 0 l 0
-l Ru-103l5.14E2 ND l1.98E2 l'ND l1.29E3 l ND l1.33E41 1 Ru-105l4.58E-4 l ND l1.66E-4 l ND 14.03E-3 ND l2.99E-1 l i l Ru-106l1.11E4 l ND l1.38E3 l ND= l1.50E4 ND l1.72E5 l lAg-110ml2.51E7 l1.69E7 l1.3527 ND- l3.15E7 ND l2.01E9
-lCd-109 l ND- 14.63E5 l2.15E4 ,
ND 14.13E5 ND 1.50E6
,lSn-113 7.32E7 .l1.50E6 l4.17E6 1.11E8 .! ND H ND , 5.17E7 ;
lSb-124- 1.30E7 l1.69E5 l4.56E6 2.67E4 ND [7.22E6 1 8.14E7 I L lSb-125 l1'.04E7 l8.04E4 l2.19E6 19.66E3 ND l5.81E6 l 2.49E7 1 lTe-125ml8.85E6 l2.40E6 l1.18E6 12.48E6 ND l ND l8.54Ee lTe-127ml2.50E7 l6.72E6 l2.96E6 l5.97E6 7.12E7 l ND l2.02E7 l slTe-127.l3.66E2 l9.86El l7.85E1 l2.53E2 ,'1.04E3 l ND . l1.43E4 l
'lTe 129ml3.25E7 l9.09E6 l5.05E6 l1.05E7 l9.55E7 l ~ ND l3.97E7 'l lTe-129 l- 0 l. 0 l 0 l ) l 0 l ND l7.40E-9 l
- - 16,64E4 lTe-131ml1.92E5 l7.07E4 l1 IES l6.43E3 l ND l2.69E6 l lTe-131 l- 0 l 0 l 0 l :) l 0 l ND l 0 l 0 lTe-132 l1.23E6 l5.42E5 l6.55E5 l7.90E5 15.04E6 l ND l5.46E6 l
[ lI-130 l2.07E6 l4.19E6 l2.16E6 l4.61E8 l6.26E6 l ND l1.96E6 l 3
,~,,
h 1' 4 b . . - .:
() APA*ZZ-01003 4 i n-s R:v. 0 : y: ; p j TABLE 5 (Contd.)
" " ~
PATHWAY DOSE FACTORS g (R ) FOR MOWCUDES OMR M NOBLE GASES" n t i
; Grass-Goat-lillk Pathway ,
[J (28 mrom/yr) per (VCi/sec) I l' l l Total l l l l l' t lNucifdel Bone l Liver i Body l Thyroid l Kidney l Lung l GI LLI l m ,
-}
M lI-131 .l1.56E9 l1.57E9 8.94E8 4 l5.20E11 l2.58E9 l ND 1.40E8 .l .i lI-132 l7.22E-1.l1.33E0 ;6.10E 1 l6.15El l2.03E0 l ND 1.56E0' l' ! lI-133 l 2.09E7 l2'58E7 . l9.76E6 l4.79E9 l4.30E7 l ND ; 1.04E7 l i L
'i lI-134 0 l_0 l 0 l 0 O l ND 0 -l lI 135 6.48E4 l1.17E5 l5.52E4 l1.03E7 1.79E5 l ND l 8.88E4 l: :
lCs 134 l6.79E10 l1.11E11 l2.35E10 l ND l3.45E10 l1.24E10LJ6.01E8 [ lCs-136'l3.03E9' l8.32E9 .115.58E9 l ND -l4.43E9 l6.61E8 2.92E8 i lCs-137 l9.67E10 19.26E10 l 1.37E10 l ND l3.02E10 1.09E10 5.80E8 ! ai lCs-138 l 0 0 0 l ND l 0 0 0 '! lBa-li9 12.27E-8 0 0 l ND l 0 1 0 1.31E-6 ,_ l l B a-140.. l l . 41E7 , 1.23E4 l 8.20E5 l ND L4.01E3 l 7.^4E3 l7.12E6 l : jBa-141 0' l 0 0 l ND 0 l l 0 , I Ba-142 0 0 O l ND 0 l a 0 l 1 La 140 l2.34E0 18.17E-1 2.75E 1 l ND ND ND l2.28E4 1
,La 142.l. 0 [ 0 0- l ND ND i ND- l3.49E-7 l
- lCo-141-l2.62E3 l1.31E3 l1.94E7 iD 13.74E2 ND l1.63E6 l f
lCo 143 l2.25El .l1.22E4 l1.77Er ND- : 5.12E0 ND l1.79E5 lCo 144 l1.95ES :l6.31E4 l1.04E4 ND 3.38E4 ND l1.59E7 lPr 143 l8.62E1 l2.59El 14.28E0 l ND 1.40E1 ND l9.30E4 ; lPr-144 l. O ~l 0 l 0 l ND r 'O ! ND l 0 l lNd-147 l5.34E1 14.33E1 l3.35E0 l ND l2.37El ND l6.85E4 i f i lEu 154 l1.13E4 l1.02ES. I 9 27E2 l ND l4.46ES , ND l2.36E5 ! l-l lHf 181 l7.71El l2.81E2 1 3.48E1 l ND ' -l5.70E1 l ND -l1.04E5 ! lV-187 l3.49E3 12.07E3 9.27E2 l ND l ND 'l ND l2.90E5 ! lNp-239 l2.06ED l1.48E 1 ,l1.04E 1 l ND l4.28E 1 l ND l1.10E4 i > (a) The child age group; refer to reference 11.14.5. I 1.
'/
. w .' .
+
7 ' L
y APA=22-01003 R;v. 0 l i TABLE 5 (Contd.) ' PATHWAY DOSE'TACTORS (Rg)' TOR' RADIONUCLIDES OTHER THAN' NOBLE GASES" i Vegetation Pathway (m8 mrem /yr) per (UCi/sec) '
"l l l l Total l l l l lNuclidel Bone I Liver 1 Body l Thyroid I l*fdney l Lung l GI-LLI
)' lH3 l ND l4.01E3 l4.01E3 l4.01E3 l4.0;E3 l4.01E3 l4.01E3 ): j l Be-7 l3.38E5 l5.76E5 l3.70E5 l ND l$.64E5 l ND l3.21E7
-l C 14 l8.89E8 l1.78E8 1.78E8 -i l l1.78E8 l1.78E8 l1.78E8 l1.78E8 l Na-24 l3.75ES 'l3.75E5 , 3.75ES l3.75ES l3.75E5 l3.75ES l3.75ES ;
l P-32 l3.37E9 l1.57E8 l1.30E8 l @ l @ l ND l9.30E7 l ll Cr-51'l ND l @ l1.17E5 l6.50E4 l1.78E4 1.19E5 '16.21E6 l ll Mn 54 l -ND l6.65E8 ll.77E8 l ND l1.86E8 ND 5.58E8 l Mn-56'l ND l1.88E1 l4.24E0 l ND l2.27El l ND 2.72E3 l fx Fe-55 l8.01E8 14.25E8 l1.32E8 l ND l ND l2.40E8 L7.87E7 l
'I Fe-59 l3.97E8 l6.43E8 l3.20E8 l ND l ND l1.86E8 l6.69E8 l , y l Co-57 l ND l2.98E7 l6.04E7 l ND l ND l ND l2.45E8 l l Co-58-l ND l6.44E7 11.97E8 l ND l ND- l ND l3.76E8 l l Co-60 l ND l3.78E8 l1.12E9 l ND l ND l ND l2.10E9 l l Ni-63 l3.95E10 l2.11E9 l1.34E9 l ND l ND ND l1.42E8 l ,l
.l Ni 65 l1.05E2 l9.89E0 l5.77E0 l NL l ND ND l1.21E3 l l Cu-64 ' ND l1.10E4 l6.64E3 l ND l2.66E4 ND l5.16E5 l l Zn-65-;8.12E8' l2.16E9 l1.35E9 l ND l1.36E9 . ND l3.80E8 l l 2n-69 11.09E-5 l1.57E-5 l1.45E-6 l ND 19.52E-6 l @ l9.11E 4 l i l Br-82 ND ND- l2.04E6 l ND l ND 1 ND l ND l l Br 83 ND ND l5.37E0 l ND l ND l ND l 0 l l Br 84 l ND l ND l 0 l ND l ND l ND l 0 l_ .
l Br-85 l ND l ND l 0 l ND l ND l ND l 0 l } l Rb-86 l ND l4.58E8 12.82E8 l ND l ND l @ l2.94E7 l ' l Rb-88 l 'ND -l 0 l' O l ND l ND l ND 0 l
-l Rb-89 l ND l 0 l 0 l ND l ND l ND , O l .
-l Sr-89 l3.59E10 l ND 11.03E9 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 p l Sr-91 l5.24E5 l ND l1.98E4 l ND l ND l ND ll.16E6 l l Sr-92 l7.28E2 l ND l2.92E1 l ND l ND l ND ll.38E4 l l Y-90 l7.31E4 l ND l6.18E2 l ND l @ l ND l6.57E7 l [h: r
. . w_
7 ' y.g Rev.'O-p l w [ > 1 TABLE 5 (Contd.) !
. PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES" h
o .. y Vegetation Pathway l 1 (m8 mrom/yr) per (uci/sec) l i:
-l_ .l l l. Total l . l _l l l lNuclidel Bone I Liver I Body l Thyroid I Xidney 1 Lunn -l GI-LLI l _
L Y-91m l8.87E 9' ND- l3.23E-10l ND l ND l ND 1 1.74E-5 [ !! Y 91~ l1.86E7_ ND 'l4.99ES l ND l ND 1 ND 2.48E9 '!'
, Y-92 l1.58E0 ND l4.53E-2 l ND l ND ND 4.58E4 Y 93 l3.01E2 i ND- l8.25E0 l ND l ND ND 14.48E6 l Zr-95 l3.86E6 l 8.45ES- -l7.55E5 l ND l1.21E6 l 'ND l8.84E8 l ;
Zr-97'l5.70E2 l8.24E1 [4.86El l ND l1.18E2 l ND l1.25E7 l ! Nb 95 l4.10E5 l1.59ES 1 1.'14E5 l ND l1.50E5 l ND l2.95E8 , Mo-99 l ND l7.71E6 1.91E6 l ND fl.65E7 l ND l6.38E6 Tc 99ml4'.71EO -l9.24EO. ;1.53E2 l ND l1.34E2 l4.69E0 5.26E3 l 1 Tc-101l- 0 l 0 [ 0 l ND l 0 l 0 0 ! p ., Ru-103l1.54E7 l ND 5.90E6 ND 3.87E7 l ND l3.97E8 l ; Ru-105l9.16El l--ND 3.32E1 ND 8.05E2 l ND ,15.98E4 l ;
) Ru-10617.45E8 ,1 ND 1 9.30E7 l ND 1.01E9 l ND l1.16E10 l .i' l,' ; Ag 110ml3.22E7 'l2.17E7 1.74E7 l ND .l4.03E7 l ND l2.58E9 l Cd-109;l ND 2.45E8 l1.13E7 l ND l2.18E8 l ND l7.94E8 l l Sn-113 . l 1.58E9 l 3.25E7 l9.00E7- l2.40E9 l ND l ND l1.12E9 l I Sb-124 l3.52E8 l4.56E6 1.23E8 l7.76ES l ND - 1.95E8 l2.20E9 .l Sb-125 l 4.99E8 l3.85E6 . 1.05E8 l4.62E5 '
ND - 2.78E8 l1.19E9 l
, Te 125m. 3.51E8 l9.50E7 L4.67E7 l9.84E7 ND l ND l3.38E8 l lTe 127mll.32E9 l3.56E8 11.57E8 l3.16E8 3.77E9 l ND l1.07E9 l lTe-127 l1.00E4 l2.69E3 l2.14E3 l6.41E3 l2.84E4 l ND l3.90E5 l.
.lTe 129ml8.38E8 l2.34E8 1.02E9 l1.30E8 l2.70E8 l2.46E9 l ND l LITE-129-l1.16E-3 l3.23E-4 l2.75E-4 l8.26E-4 l3.39E-3 l ND ,7.20E-2 l
^
llTo-131 mil.54E6- l5.33E5 -l5.68E5 l1.10E6 l5.16E6 l ND l2.16E7 l- ; lTo-131'l' 0 -l 0 l 0 l 0 0 l ND l 0 ;
, :lTo-132 l6.98E6 l3.09E6 l3.73E6 l4.50E6 2.87E7 l~ ND l3.11E7 + _lI-130 l6.16ES l1.24E6 l6.38E5 l1.37E8 l1.86E6 l ND 5.79ES l
~ lI-131 l1.43E8 1A 44E8 l8.17E7 l4.75E10 l2.36E8'l ND 1.28E7 l : I-132 l8.58E1 .{1.58E2 j 7.25El l7.31E3 l2.41E2 l ND l1.86E2 l I-133 ; 3.56E6 l4.40E6 1.67E6 l8.18E8 l7.34E6 l ND l1.77E6 l l l I-134 1.55E-4 l2.88E-4 1.32E-4 l6.62E-3 l4.40E-4 l ND l1.91E-4 l ; lI-135 ; 6.62E4 l1.13E5 l 5.33E4 l9.97E6 l1.70E5 l ND -l8.58E4 l } l /< y , Y y
, Rev. 0 y i TABLE 5 (Centd.) PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOB 1.E GASES" Vegetation Pathway
?
I
. (m8 mrem /yr) per (DCi/sec) 4 l l l Total l l l l .l llpuclidel Bone Liver l Body l Thyroid l Kidney 1 Lung l GI-LLI l lCs-134 l1.60E10 l2.63E10 l5.55E9 l ND l8.15E9 12.93E9 11.42E8 L lCs-136 8.17E7 l2.25E8 l1.45ES l ND l1.20E8 1.78E7 l7.90E6 l lCs 137 2.39E10 l2.29E10 l3.38E9 l ND 17.46E9 2.68E9 l1.43E8 lCs-138 1 0 l 0 0 l ND -l 0 l 0 l 0 lBa-139 14.80E-2 l2.56E-5 1.39E-3 l ND l2.24E-5 11.51E-5 l2.77E0 lBa-140 l2.77ES l2.42E5 l1.62E7 l ND l7.89E4 l1.45E5 l1.40E8 l lBa*141 l 0 l 0 l 0 l ND l 0 l 0 l 0 l lBa-142 l 0 l 0 1 0 l ND l 0 l 0 l 0. l lLa-140 l3.25E3 l1.14E3 ! 3.83E2 l ND l ND l ND l3.17E7 l lLa-142 l2.50E-4 l7.98E-5 '2.50E-3 l ND l ND l ND l1.58E1 l lCo-141-l6.56ES l3.27E5 l4.86E4 l ND l1.43E5 l ND l4.08E8 h '.
lCo-143 l1.72E3 l9.31E5 l1.35E2 l ND 13.9152 l ND l1.36E7 lCo-144 l1.27E8 l3.98E7 16.78E6 l ND l2.21E7 l ND l1.04E10 , lPr-143 11.46E5 l4.38E4 17.25E3 l ND l2.37E4 l ND l1.58E8 l lPr-144 l 0 l 0 l 0 .l ND l 0 l ND l 0 l lNd-147 17.17E4 l5.81E4 14.50E3 ND l3.19E4 l ND 19<20E7 l lEu-154 1.66E8 l1.50E7 l 1.37E7 ND l6.57E7 l ND 13.48E9 l i lHf-181 1 4.90E5 l1.79E6 2.21ES , ND l3.62E5 l ND l6.59E8 l
' l W- 187- l6.47E4 l3.83E4 ll.72E4 l ND l ND l ND l5.38E6 l
-lNp-239 l2.55E3 l1.83E2 l1.29E2 l ND l5.30E2 l ND l1.36E7 l (a) The child age group; refer to reference 11.14.5.
t g. w s:A
I
......m..,
R:v. O k' L TABLE 5 (Contd.) I j .; ADULT PATHVAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES f Inhalation Pathway l (mrem /yr) per (pCi/m') , l . I I I 1otal l l l l l
.lNuclidel Bone l Liver l Body l Thyroid i Kidney I Lung l GI-LLI l 0 lH-3 l ND ll.26E+03 l1.26E+03 l1.26E+03 l1.26E+03,l1.26E+03 l1.26E+03 l >
lBe-7' l4.27E+02 l9.68E+02 l4.70E+02 l ND l ND l4.21E+04 l5.35E+03 l , lC-14 l1.82E+04 l3.41E+03 l3.41E+03 13.41E+03 l3.41E+03 l3.41E+03 l3.41E+03 l > lNa-24 l1,02E+04 l1.02E+04 l1.02E+04 jl.02E+04 l1.02E+04 l1.02E+04 l1,02E+04 l
.lP-32 11.32E+06-l7.71E+04 l5.01E+04 l ND l ND l ND l8.64E+04 l lCr-51 l ND l ND l1.00E+02 l5.95E+01 l2.2SE+01 l1.44E+01 l3.32E+03 l .
IMn-54 l ND l3.96E+04 l6.30E+03 l ND l9.84E+03 l1.40E+06 l7.74E+04 l lMn-56 l ND l1.24E+00 11.83E-01 l ND l1.30E+00 l9.44E+03 l2.02E+04 l lFe-55 ! 2.46E+04 11.70E+04 13.94E+03 l ND l ND l7.21E+04 l6.03E+03 l lFe-59 11.18E+04 l2.78E+04 l1.06E+04 l ND l ND l1,02E+06 l1.88E+05-l e'# lCo-57 l ND l6.92E+02 l6.71E+02 l ND l ND l3.70E+05 l3.14E+04 l lCo-58 l ND ll.58E+03 l2.07E+03 l ND l ND 19.28E+05 l1.06E+05 , lCo-60 l ND l1.15E+04 l1.48E+04 l ND l ND l5.97E+06 l2.S$E+05 lNi-63 l4.32E+05 13.14E+04 l1.45E+04 l ND l ND l1.78E+05 l1.34E+04 l lNi-65 l1.54E+00 l2.10E-01 l9.12E-02 l ND l ND 15.60E+03 l1.23E+04 l
'lCu-64 l ND l1.46E+00 l6.15E-01 l ND 14~.62E+00 16.78E+03 l4.90E+04 l t
-lZn-65 l3.2/sE+04 l1.03E+05 l4.66E+04 l ND l6.90E+04 18.64E+05 l5.34E+04 ,
lZn-69 l3.38E-02-l6.51E-02 14.52E-03 l ND l4.22E-02 19.20E+02 l1.63E+01 lBr-82 l ND l ND l1.35E+04-l ND l ND l ND l1.04E+04 lBr-83 l ND l ND l2.41E+02 l ND l ND l ND l2.32E+02 lBr-84 l ND l ND l3.13E+02 l ND l ND l ND l1.64E-03 l l lBr-85 l ND l ND l1.28E+01 l ND l ND l ND l0.00E+00 l lRb-86 l ND l1.35E+05 l5.90E+04 l ND l ND l ND l1.66E+04 l
'lRb-88 l ND l3.87E+02 l1.93E+02 l ND l ND l ND l3.34E-09 lRb-89 l ND l2.56E+02 l1.70E+02 l ND l ND l ND l0.00E+00 lSr-89 .l3.04E+05 l ND [8.72E+03 l ND l ND l1.40E+06 l3.50E+05 l lSr-90 l9.92E+07 l ND l6.10E+06 l ND l ND l9.60E+06 l7.22E+05 l 1 lSr-91 l6.19E+01 l ND 12.50E+00 l ND l ND l3.65E+04 l1.91E+05 l
.lSr-92 16.74E+00 l_ ND l2.91E-01 l ND l ND l1.65E+04 l4.30E+04 l lY-90 12.09E+03 l ND l5.61E+01 l ND l L l1.70E+05 l5.06E+05 l MTn! .
ly n. 1
\.,
Rev. 0 TABLE 5 (Contd.) 7 ADULT PATE'AY DOSE FACTORS (R g) FOR RADIONUCLIDES OTHER THAN NOBLE GASES E Inhalation Pathway (mrem /yr) per (UC1/m8 ) l l l l Total l l l l l ) -lNuclidel Bone l Liver i Body l Thyroid l Kidney l Lunt i GI-LLI l t
; lY-91m l2.6'1E-01 l ND l1.02E-02 l ND l ND l1.92E+03 l1.33E+00 l r lY-91 14.62E+05'l ND ll.24E+04 l ND l ND l1.70E+06 l3.85E+05 l
( lY-92 l1.03E+01 l ND l3.02E-01 l ND J ND l1.57E+04 l7.35E+04 1 r lY-93 l9.44E+01 l ND l2.61E+00 l ND ND l4.85E+04 l4.22E+05 l lZr-95 l1.07E+05 l3.44E+04 l2.33E+04 l ND '5.42E+04 11.77E+06 l1.50E+05 l lZr-97 l9.68E+01 l1.96E+01 19.04E+00 l ND l2.97E+01 17.87E+04 l5.23E+05 l i: lNb-95 l1.41E+04 l7.82E+03 l4.21E+03 l ND l7.74E+03 l5.0$E+05-l1.04E+05 l
- j. lMo-99 l ND l1.21E+02 l2.30E+01 l ND l2.91E+02 l9.12E+04 l2.48E+05 l
$ lTc-99m l1.03E-03 2.91E-03 l3.70E-02 l ND l4.42E-02 l7.64E+02 l4.16E+03 l lTe-101 l4.18E-05 6.02E-05 l5.90E-04 l ND l1.08E-03 l3.99E+02 10.00E+00 l ( c'. lRu-103 il.!?M !
- i6.58E+02 l ND l5.83E+03 ;5.05E+05 l1.10E+05 l lRu-105 l7.90E-01 l ND 13.11E-01 l ND l1.02E+00 l 1.10E+04 14.82E+04 l ,
1Ru-106 l6.91E+04 l ND l8.72E+03 l ND l1.34E+05 l9.36E+06 19.12E+05 lAg-110ml1.08E+04 l1.00E+04 l5.94E+03 l ND l1.97E+04 l4.63E+06 l3.02E+05 ,- t lCd-109 l ND l3.67E+05 l1.31E+04 l ND l3.57E+05 l6.83E+V5 l5.82E+04 l ISn-113-l5.72E+04 l2.18E+03 l4.39E+03 l1.24E+03 l ND 19.44E+05 l1.18E+05 l lSb 124 l3.12E+04 l5.89E+02 l1.24E+04 l7.55E+01 l ND l2.48E+06 l4.06E+05 l lSb-125 15.34E+04 l5.95E+02 l1.26E+04 15.40E+01 l ND l1.74E+06 l1.01E+05 l l lTe-125ml3.42E+03 l1.58E+03 l4.67E+02 l1.05E+03 ll.24E+04 13.14E+05 l7.06E+04 l lTe-127ml1.26E+04 l5.77E+03 l1.57E+03 13.29E+03 14.58E+04 19.60E+05 l1.50E+05~l lTe-127 l1.40E+00 l6.42E-01 l3.10E-01 l1.06E+00 l5.10E+00 l6.51E+03 15. 74E+04 l lTe-129ml9.76E+03 l4'67E+03 l1.58E+03 l3.44E+03 l3.66E+04 l1.16E+06 l3.83E+05 l l lTe-129 l4.98E-02 l2.39E-02 l1.24E-02 l3.90E-02 l1.87E 01 l1.94E+03 l1.57E+02 l lTe-131ml6.99E+01 l4.36E+01 12.90E+01 l5.50E+01 13.09E+02 11.46E+05 l5.56E+05 l lTe-131 l1.11E-02 l5.95E-03 13.59E-03 19.36E-03 l4.37E-02 l1.39E+03 l1.84E+01 l lTe-132 l2.60E+02 l2.15E+02 l1.62E+02 l1.90E+02 l1.46E+03 l2.88E+05 l5.10E+05- l 1 lI-130 l4.58E+03 l1.34E+04 l5.28E+03 l1.14E+06 l2.09E+04 l ND 17.69E+03 l
- lI131 l2.52E+04 l3.58E+04 l2.05E+04 l1.19E+07 l6.13E+04 l ND j6.28E+03 l lI-132 -l1.16E+03 l3.26E+03 11.16E+03 l1.14E+05 15.18E+03 l ND l4.06E+02 l lI-133 l8.64E+03 l1.48E+04 l4.52E+03 l2.15E+06 l2.58E+04 l ND l8.88E+03 l
, lI-134 l6.44E+02 l1.73E+03 l6.15E+02 l2.98E+04 l2.75E+03 l ND l1.01E+00 l l uy
- m. :
i . l
- i. ..
i
r
*i I h APA*2Zs01003 , , Rev. 0
( [ TABLE 5 (Contd.) ADULT PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES.*
~
Inhalation Pathway l 8
, (mrem /yr) per (1:Ci/m )
-l l Total l l l l l lNuclide ' Bone l Liver Body l Thyroid i Kidney l Lung l GI-LLI l lI-135 l2.68E+03 l6.98E+03-l2.57E+03 !4.48E+05 l1.11E+04 l ND 15.25E+03 l lCs-134 l3.73E+05 l8.48E+05 l7.2BE+05 l ND l2.87E+05 19.76E+04 l1.04E+04 l' lCs-136-l3.90E+04 l1.46E+05 l1.10E+05 l ND l8.56E+04 11.20E+04 l1.17E+04 l
- .lCs-137 l4.78E+05 l6.21E+05 l4.28E+05 l ND l2.22E+05 l7.52E+04 l8.40E+03 lCs-138 l3.31E+02 l6.21E+02 l3.24E+02 l ND l4.80E+02 l4.86E+01 l1.86E-03 lBa-739 19.36E-01 6.66E-04 l2.74E-02 l ND 16.22E-04 l3.76E+03 l8.96E+02 l lBa-140 l3.90E+04 4.90E+01 l2.57E+03 l ND l1.67E+01 l1.27E+06 l2.18E+05 l lBa-141 l1,00E 01 l7.53E-05 l3.36E-03 l ND l7.00E-05 l1.94E+03 l1.16E-07 l.
lBa-142 l2.63E 02 l2.70E-05 l1.66E-03 l ND l2.29E-05 l1.19E+03 10.00E+00 l lLa-140 l3.44E+02 l1.74E+02 l4.58E+01 l ND l ND l1.36E+05 l4.58E+05 l: [ lLa-142 l6.83E-01 l3.10E-01 l7.72E-02 l ND l ND l6.33E+03-l2.11E+03 l lCo-141 l1.99E+04 l1.35E+04 l1.53E+03 l ND l6.26E+03 13.62E+05 11.20E+05 l , Ice-143 l1.86E+02-l1.38E+02 l1.53E+01 l ND 16.08E+01 17.98E+04 l2.26E+05 l lCo-144 l3.43E+06 l1.43E+06 l1.84E+05 l ND l8.48E+05 l7.78E+06 l8.16E+05 l ipr-143 l9.36E+03 13.75E+03 l4.64E+02 l ND l2.16E+03 l2.81E+05 l2.00E+05 l lPr-144 13.01E 02 l1.2SE-02 l1.53E-03 ND l7.05E-03 11.02E+03 12.15E 08 l lNd-147 15.27E+03 l6.10E+03 l3.65E+03 ND l3.56E+03 l2.21E+05'll 73E+05 l lEu-154 l5.92E+06 l7.28E+05 15.18E+05 l ND l3.49E+06 14.67E+06 l2.72E+05 l lHf-181 l1.41E+04 l6.82E+04 l6.32E+03 l ND l1.48E+04 l6.S5E+05 11.39E+05 l lW-187 l8.48E+00 l7.08E+00 l2.48E+00 l ND l ND l2.90E+04 11.55E+05 l lNp-239 12.30E+02 l2.26E+01 l1.24E+01 l ND [7.00E+01 l3.76E+04 l1.19E+05 l 6 . y l l
APA-Z2-01003 Rev 0 [ , TABLE 5 (Contd.) ADULT PATINAY DOSE TACTORS g -(R ) FOR MOWCEES OMR N WE WES
' ' '~
Inhalation Pathway (mrem /yr) per (VCi/m8 ) l l l l Total l l l l .l lNuclidel Bone -l Liver i Body i Thyroid l Kidney I Lung l GI-LLI l lI-135 10.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 1 ND l0.00E+00 l Cs-134 16.57E+08 ' 1.56E+09 l1.28E+09 l ND l5.06E+08 'II.68E+08 l2.74E+07 l Cs-136 l1.20E+07 4.76E+07 :.3.42E+07 l ND l2.65E+07 ' 3.63E+06 l5.40E+06 l
'Cs-137 l8.71E+08 L1.19E+09 7.81E+08 l
, ND l4.04E+08 'l1.34E+08 l2.31E+07 lCs 138 l0.00E+00 'l0.00E+00 '.0.00E+00 l ND l0.00E+00 10.00E+00 l0.00E+00-lBa-139 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l lBa-140 l2.87E+07 13.61E+04 l1.88E+06 l ND l1.23E'04 '2.07E+04 l5.91E+07 l lBa 141 l0.00E+00 0.00E+00 l0.00E+00 l ND l0.00E+00 0.00E+00 l0.00E+00 l lBa-142 0.00E+00 0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00.
lLa-140- 3.71E-02 l1.87E-02 l4.95E-03 l ND l ND l - ND l1.37E+03 l m ' lLa 142 l0.00E+00 l0.00E+00 l0.00E+00 l ND l ND l ND 10.00E+00 l. . lCo-141 l1.40E+04.l9.49E+03 l1.0BE+03 l ND l4.41E+03 ' ND 13.63E+07 l
.lCo-143 l2.01E 02-l1.49E+01 l1.64E-03 l ND l6.54E-03 ND l5.55E+02 lCo-144 l1.46E+06'l6.09E+05 l7.82E+04 l ND l3.61E+05 l. ND 14.92E+08 lPr-143 12.10E+04 l8.40E+03 l1.04E+03 l ND l4.85E+03 l ND l9.18E+07 l
'lPr-144 l0.00E+00!l0.00E+00 10.00E+00 l ND l0.00Z+00 ND l0.00E+00 lNd-147 l7.07E+03 l8.17E+03 l4.89E+02-l ND l4.77E+03 ND. l3.92E+07 lEu-154 18.02E+06 19.86E+05 l7.01E+05 l ND l4.72E+06 ND l7.14E+08 '
lHf-181 13.01E+06 l1.46E+07 1.35E+06 l ND l3.14E+06 !i ND l1.66E+10 lW-187 l2.07E-02 11.73E-02 ' 6.05E-03 l ND l ND l ND l5.67E+00 lNp-239=l2.63E-01 l2.59E-02 l'1.43E 02 l ND 18.07E-02 l ND l5.30E+03 L C ,
0 APA-ZZo01003 9" Rev. O p li , lt TABLE 5 (Contd.,), ,[ ADULT PATWAY DOSE TACTORS (R g) TOR RADIONUCLIDES ,0THER THAN NODLE GASES
, Grass-Cow Milk Pathway l-(ta8 mrem /yr) per (VCi/sec)
). l l l Total l l l l .l lNuclidel Bone ! Liver i Body l Thvreid l Kidnev l Lung i GI-LL7 I
', lH-3 l @ .l7.63E+02 l7.63E+02 17.63E+02 l7.63E+02 l7.63E+02 17.63E+02 l i- lBe-7 l1.63E+03 l3.72E+03 l1.81E+03 l ND l3.93E+03 l ND ! 6.45E+05 l lC-14 l2.63E+08 15.27E+07 l5.27E+07 l5.27E+07 l5.27E+07 l5.27E+07 5.27E+07 1
'lNa 24 l2.44E+06 l2.44E+06 l2.44E+06 l2.44E+06 l2.44E+06 l2.44E+06-l2.44E+06 lP-32 l1.71E+10 l1.06E&O9 l6.61E+08 l ND l ND l ND l1.92E+09 lCr-51 l 'ND. l. ND l2.86E+04 l1.71E+04 l6.30E+03 l3.79E+04 l7.19E+06 l (0 lMn-54 l ND' 18.42E+06 l1.61E+06 l ND l2.50E+06 l ND l2.5BE+07 l lMn-56 l ND l4.20E-03 l7.45E-04 l ND l5.33E-03 l ND l1.34E-01 l
[ IFe-55 l2.51E+07-ll.74E+07 4.05E+06 l ND l ND l9.68E+06 19.96E+06 l
,. p., lFe-59 l2.97E+07 l6.98E+07 ,2.68E+07 l ND l @ l1.95E+07 l2.33E+08 l lCo 57 l ND l1.28E+06 l2.13E+06 l ND l ND l ND 13.25E+07 i e lCo-58 ND l4.72E+06 l1.06E+07 l. ND l ND l ND - 19.56E+07 lCo-60 l ND l1.64E+07 13.62E+07 1 ND l ND l ND l3.0BE+08 ,
lNi-63 l6.73E+09 l4.76E+08 l2.26E+08 ND .l ND l ND 19.73E+07 l lNi-65 l3.71E-01 l4.82E-02 l2.20E-02 ND l ND l ND l1.22E+00 1 l .l0u-64 l ND l2.39E+04 l1.12E+04 l ND 16.01E+04 l ND l2.03E+06 l 4 lZn-65 l1.37E+09 l4.37E+09 l1.97E+09 l ND .l2.92E+09 ; ND l2.75E+09 l 1 lZn-69 l0.00E+00 l0.00E+00 l0.00E+00 l ND ~l0.00E+00 ' ND' l0.00E+00 l
'lBr-82 l ND l ND l3.23E+07 l ND l ND l ND l3.71E+07 I
.lBr-83 l ND l ND l9.75E-02 l ND l ND l ND 1.40E-01 l lBr-84 l ND l ND 10.00E+00 l ND l ND l ND l0.00E+00 l lBr 85 l ND l ND l0.00E+00 l ND l ND l ND l0.00E+00 l lRb-86 ll ND l2.60E+09 11.21E+09 l ND l ND l ND l5.12E+08 l lRb-88 l ND l0.00E+00 10.00E+00 l ND l ND l ND 10.00E+00 l
[ lRb-89 l ND 10.00E+00 l0.00E+00 l .ND l ND l ND l0.00E+00 l b lSr-89 l1.45E+09 l ND 14.17E+07 l ND l @ l ND l2.33E+08-l lSr-90 l4.68E+10 l ND l1.15E+10 l ND l ND l ND l1.35E+09 l
- lSr-91 l2.90E+04 l ND l1.17E+03 l ND l ND l ND l1.38E+05 l
]L lSr-92 l4.90E-01 l ND l2.12E-02 l ND l ND l ND l9.71E+00 l
)-
lY-90 l7.09E+01 l ND l1.90E+00 l ND l ND l ND l7.52E+05 l
+
l 68 -
e
' 4 i
APA-ZZ 01003 R v. 0 TABLE 5 (Contd.) ADULT PATINAY DOSE FACTORS g . (R ) FOR RAMOMWES OHER HM N GASES i . m Grass-Cow-Milk Pathway (m8 mrem /yr) per (pCi/sec) L l l. l l. Total l l l l l , lNuclidel Bone i Liver l Body l Thyroid l Kidney l Lung i GI-LLI I l l0.00E+00 l ND l0.00E+00 l ND l ND l ND l0.00E+00 l lY-91m lY 91 _ 18.59E+03ND ll2.30E+02 l ND l ND. l ND l4.73E+06 l
- lY-92 l5.59E-05 l ND l1.63E-06 l ND i ND l ND 19.80E-01 l lY-93 l2.24E-01 l ND l6.18E-03 l ND l ND l ND l7.09E+03 l lZr-95 l9.44E+02 l3.03E+02 l2.05E+02 l ND l4.75E+02 l ND l9.59E+05 l-lZr-97 l4.34E 01 l8.75E-02 l4.00E-02.l ND l1.32E-01 l ND l2.71E+04 L
lNb-95 l8.26E+04 l4.59E+04 l2.47E+04 l ND l4.54E+04 l ND l2.79E+08 lMo-99 l ND l2.48E+07 l4.72E+06 l ND l5.61E+07 l ND l5.74E+07 ? lTc-99m l3.33E+00 l9.40E+00 l1.20E+02 l ND 1.43E+02 l4.61E+00 l5.56E+03 lTc-101 l0.00E+00'l0.00E+00 l0.00E+00 l ND 0.00E+00 l0.00E+00 10.00E+00 I, lRu-103 l1.02E+03-l' ND l3.89E+03 l l1.19E+05 l l4.39E+02 l ND ND lRu 105 l8.58E-04 l ND l3.39E-04 l ND l1.11E-02 l ND l5.25E-01 l .
~lRu-106 l2.04E+04-l ND l2.58E+03 l ND -l3.94E+04 l ND l1.32E+06 l lAg-110ml5.82E+07 l5.39E+07 l3.20E+07 l ND l1.06E+08 l ND l2.20E+10 l lCd-109 l .ND l1.13E+06 l3.95E+04 l ND l1.08E+06 l ND l1.14E+07 l lSn-113 l1.34E+08 l3.81E+06 l7.73E+06 l2.18E+06 l ND l ND l4.02E+08 l ,
ISb-124 l 2.57E+07 14.86E+05 l1.02E+07 l6.24E+04 l ND l2.00E+07 l7.31E+08 lSb 125 l2.04E+07 12.28E+05 l4.87E+06 l2.08E+04 l ND ll.58E+07 l2.25E+08 l lTe-125ml1.63E+07 [5.90E+06 l2.18E+06 l4.90E+06 l6.63E+07 l ND l6.51E+07 lTe-127ml4.58E+07 l1.64E+07 l5.58E+06 l1.17E+07 l1.86E+08 l ND l1.54E+08 ,. lTe-127 l6.54E+02 12.35E+02 l1.41E+02 l4.84E+02 l2.66E+03 l ND 15.16E+04 'l lTe-129ml6.02E+07 l2.25E+07 l9.53E+06 l2.07E+07 l2.51E+08 l ND l3.03E+08 l lTe-129-l2.84E-10 l1.07E-10 l0.00E+00 l2.18E-10 l1.19E-09 l ND j2.15E-10 l lTe-131ml3.61E+05 l1.77E+05 l1.47E+05 l2.80E+05 l1.79E+06 l ND l1.75E+07 l lTe-131 l0.00E+00 10.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l
-lTe-132 l2.40E+06 l1.55E+06 l1.46E+06 l1.72E+06 l1.50E+07 l ND l7.35E+07 l lI-130- l4.21E+05 l1.24E+06 l4.91E+05 l1.05E+08 l1.94E+06 l ND l1.07E+06 l lI-131,- l2.97E+08 14.25E+08 l2.43E+08 l1.39E+11 l7.28E+08 l ND l1.12E+08 l l1-132 l1.65E-01 l4.42E-01 l1.55E-01 l1.55E+01 l7.04E-01 l ND 18.30E-02 l lI-133 l3.88E+06 l6.75E+06 l2.06E+06 l9.92E+08 l1.18E+07 l ND l6.07E+06 l lI-134 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l l
C
APA*ZE-01003 R:V 0 TABLE 5 (Contd.) ADULT PATHWAY DOSE TACTORS g (R ) FOR REOMIDES OMR M NOBE GASES
~
l Grass-Cow Milk Pathway (m8 mrem /yr) per (tic 1/sec) l l l l l Total- l l l l l l
.lNuclidel* Bone l Liver l Body l Thyrofd l Kidney l Lung l G1-LLI l lI-135 l1.29E+04 l3.37E+04 l1.25E+04 l2.23E+06 l5.41E+04'l ND i 3.81E+04' I
lCs-134-l5.65E+09 l1.35E+10 l1.10E+10 l _ ND l4.35E+09 l1.45E+09 l 2.35E+08 lCs-136 12.63E+08 l1.04E+09 l7.48E+08 l ND l5.79E+08 l7.93E+07 l 1.18E+08 l : lCs-137 l7.38E+09 l1.01E+10 l6.61E+09 ND l3.43E+09 l1.14E+09 l 1.95E+08 l ! lCs-138 l0.00E+00 l0.00E+00 l0.00E+00 ND l0.00E+00 10.00E+00 LO.00E+00 l l lBa-139 l4.44E-08 l0.00E+00 l1.30E-09 [ ND l0.00E+00 l0.00E+00 l7.88E-08 l i lBa-140 l2.69E+07 l3.38E+04 l1.76E+06 ND l1.15E+04 l1.93E+04 l5.54E+07-l lBa-141.l0.00E+00-l0.00E+00 l0.00E+00 , ND 10.00E+00 l0.00E+00 l0.00E+00 l ! lBa-142 l0.00E+00 l0.00E+00 l0.00E+00
~
ND 0.00E+00 10.00E+00 l0.00E+00-
..,. lLa-140 l4.51E+00 l2.28E+00 l6.01E-01 ND I ND l ND l1.67E+05 '
lLa-142 l1.87E-11 18.49E-12 l2.12E-12 l .ND l ND l ' ND 6.20E-08'll lCo-141 l4.85E+03 l3.28E+03 l3.72E+02 l ND l1.52E+03 l ND 1.25E+07 lCo-143 l4.16E+01 l3.08E+04 l3.40E+00 l ND l1.35E+01 l ND l1.15E+06 , ; lCo-144 l3.58E+05 l1.50E+05 l1.92E+04 l ND l8.87E+04 l ND l1.21E+08 l , lPr-143 l1.58E+02 l6.34E+01 l7.83E+00 l ND: l3.66E+01 l ND l6.92E+05 l ! lPr-144 l0.00E+00 l0.00E+00 l0.00E+00'l ND l0.00E+00 l ND l 0.00E+00 l ; lNd-147 l9.42E+01 l1.09E+02 l6.51E+00 l ND 16.36E+01-l ND l 5.23E+05 l lEu-154 l2.37E+04 l2.91E+03 l2.07E+03 ND l1.39E+04 l ND L2.11E+06'l , lHf-181 l1.42E+02 16.92E+02 l6.41E+01' ND l1.49E+02-l ND- l7.87E+05 l lW-187 16.52E+03 l5.45E+03 l1.91E+03 ND l ND l ND l1.78E+06 l , lNp-239-l3.69E+00 l3.62E-01 l2.00E-01 ND l1.13E+00 l ND l7.43E+04 l i l T I
.m.
L
} 1 APA*%Z 01003 ,
I t R ,v. : 0 )
>M' 1 , m .
TABLE 5 (Contd.') g$. ... - ADULT PAT)NAY DOSE FACTORS. (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES k; Grass-Goat-Milk Pathway (m8 mrem /yr) per (pC1/sec)
', l .. l. . l Total- l l l . .l .l g [Nuclide Bone- l -Liver l Body l Thyroid l Kidney = l Lung ~l GI-LLI l r
N" lH-3 l ND: . l1.56E+03 11.56E+03 l1.56E+03 l1.56E+03 l1.56E+03 l.1.56E+03 l l4.72E+02-l 7.74E+04'l l
}lBe-7~ l1.96E+02 l4.47E+02 l2.17E+02 l ND ND - ,
' I e lC-14' l2.64E+08Ll5.27E+07 l5.27E+07 l5.27E+07 l5.27E+07 l5.27E+07 l 5.27E+07 J E '
lNa 24' 'l2.93E+05 l2.93E+05 l2.93E+05 l2.93E+05 l2.93E+05 l2.93E+05 2.93E+05 lP-32: l2.0$E+10 l1.28E+09 l7.94E+08 l ND l ND l ' ND - l2.31E+09 j l
.lCr-51 ! ~ ND l ND I;3.43E+03 l2.05E+03 l7.56E+02 l4.56E+03 l8.63E+05 l ;
Mn-54' i ND' .l1.01E+06 l 1.93E+05 l ND l3.01E+05 l ND l3.10E+06 Mn-56 l ND . l5.04E-04 18.94E-05 l ND. -l6.40E 04 l 'ND- l1.61E-02 , Fe-55 l3.27E+05-l2.26E+05 l5.26E+04 l ND l- ND- l1.26E+05 {1;30E+05 l~ r j![y .
; Fe 59 .l3.87E+05 19.08E+05 l3.48E+01 ); ND l ND -l2.54E+05 l3.03E+06 l l I
( lCo-57' l- ND' l1.54E+05 l2.56E+05 l ND l ND l ND l3.90E+06 l qP1 lCo-58.,l' ND l5.66E+05 l1.27E+06 l ND l ND- ~l ND , 1.15E+07 l . (
'Co-60?.l . ND . l1.97E+05'14.35E+06 l ND l ND l ND '3.70E+07 l ,
4 Ni-63 -l8.08E+08 l5.60E+07 12.71E+07 l ND l ND l ND l1.17E+07-l' .; l Ni-65 l4.46E-02 l5;79E-03.l2.64E-03 l ND l ND l ' ND l1.47E-01-l K lCo-64 l ND l2.66E+03 l1.25E+03 l ND l6.71E+03;l ND 'l2.27E+05 l lZn;65. l1.65E+08 l5'.24E+08 l2.37E+08.l ND l3.51E+08'l ND- -l3.30E+08 l' l lZn-69 l0.00E+00-l0.00E+00 l0.00E+00 l ND l0.00E+00 l ND l0.00E+00 l ,
- - lbr-82 l :ND l- ND l3.88E+06 l ND l ND l ND l4.4SE+06 l i lBr-83 l' ND l: ND. l1;17E-02 l ND l - ND : l ND l1.69E-02 l lBr-84: l ND l ND' l0.00E+00 l ND l ND l ND -l0.00E+00 l q lBr-85 l .ND l ND l0.00E+00 l ND l ND l ND- l0.00E+00.l s
i '
.lRb-86 l ND l3.12E+08 l1.45E+08 l ND l ND l ND l6.15E+07 l'-
'lRb l- ND l0.00E+00 l0.00E+00 l- ND l ND l ND l0.00E+00 l. ;
a
.' lRb-89 l. ND l0.00E+00.l0.00E+00 l ND .l. ND l ND l0.00E+00 l-f ,
lSrA89 l3.05E+09 l- ND 'l8.75E+07 l ND l ND l ND l4.89E+08.l' ,
- Sr-90" l9.84E+10 l. -ND l2.41E+10 l ND l ND l ND l 2 '. 84E+09 - l Sr-91 l6.09E+04 l ND l2.46E+03 l ND J ND l ND l2.90E+05 l
.lSr-92 l1.03E+00 l ND l4.45E-02 l ND- l ND l ND l2.04E+01 l- l lY l8.51E+00 l' ND l2.28E-01'l ND l ND l ND 19.03E+0il ,
4
/k c/ ,
. 'I q. f - p.
- v. ,
- s. ,
y
C APA$ZZ-01003
- i ,
TABLE 5 (Contd.) , 2 ADULT PATHn'AY DOSE FACTORS .(Rg ) FOR RADIONUCLIDES OTHER TRAN NOBLE GASES Grass-Goat-Milk Pathway , (.0 8 mrem /yr) per (VCi/sec) ' f V I l l l . l Total l l l l l. lNuclidel Bone l Liver l Body l Thyroid l Kidney I Lung I GI-LLI' l L lY-91m l0.00F+00 l ND l0.00E+00 l ND l ND l ND l0.00E+00 l lY-91 l1.03E+03 i ND l2.76E+01 l ND l ND l ND l5.68E+05 l lY-92 l6.72E-06 i ND l1.96E-07 l ND l ND l ND l1.18E-01 q lY-93 l2.69E-02 l ND l7.42E-04 l ND l ND l ND l8.52E+02.
-lZr-95 l1.13E+02 [3.63E+01 l2.46E+01 l ND l5.70E+01 l ND l1.15E+05 ll
; lZr-97 ,l5.21E-02 l1.05E-02 'l4.80E-03 l ND l1.59E-02 l ND l3.2SE+03 l E lNb-95_ l9.92E+03 l5.52E+03 l2.97E+03 l ND l5.45E+03 l ND l3.35E+07 l lMo-99 l ND' l2.98E'06 l5.66E+05 l ND l6.74E+06 l ND 16.90E+06 1 p lTc-99m l3.99E-01 l1.13E+00 l3.44E+01 l ND l1.71E+01 l5.53E-01 l6.68E+02 l ,
~
[ lTc-101 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l [ lRu-103 l1.22E'+02 l ND l5.27E+01 l ND l4.67E+02 l ND l1.43E+04 l , lRu-105 l1.03E-04 l ND l4.07E-05 l ND l1.33E-03 l ND l6.31E-02 l , lRu-106 l2.45E+03 l. ND l3.10E+02 l ND l4.73E+03 l ND l1.59E+05 l 1 lAg-110ml6.99E+06 l6.47E+06 l3.84E+06 l ND l1.27E+07 l ND l2.64E+09 l ; lCd-109 l ND l1.36E+05 l4.74E+03 l ND l1.30E+05 l ND l1.37E+06 l lSn-113 l1.61E+07 l4.58E+05 l9.28E+05 l2.62E+05 l ND l ND l4.83E+07 l
-lSb-124.l3.09E+06 l5.84E+04 l1.23E+06 l7.50E+03 l' ND l2.41E+06 l8.78E+07 l lSb-125 l2.46E+06 l2,74E+04 l5.84E+05 l2.50E+03 l ND l1.89E+06 l2.70E+07 l ,
lTe-125ml1.96E+06 l 7.09E4 05 l2.62E+05 l5.89E+05 l 7.96E+06 ! ND l7.81E+06 l lTe-127ml5.50E+06 11.97E+06 l6.70E+05 l1.41E+06 l2.23E+07 l ND l1.84E+07 l
'lTe-127 l7.85E+01 l2.32E+01 l1.70E+01 l5.82E+01 l3.20E+02 l ND [6.19E+03 l lTe-129:rl7.23E+06 l2.70E+06 l1.14E+06 l2.48E+06 l3.02E+07 l ND l3.64E+07 l lTe-129 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l1.43E-10 l ND l6.00E+00 l '
lTo-131ml4.34E+04 l2.12E+04 l1.77E+04 l3.36E+04 l2.15E+05 l ND l2.11E+06 l lTe-131 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 10.00E+00 l ND l0.00E+00 l 1Te+132-l2.89E+05 l1.87E+05 l1.75E+05 l2.06E+05 11.80E+06 l ND l8.83E+06 l-130 'l5.05E+05 l1.49E+06 l5.88E+05 l1.26E+08 l2.32E+06 l ND l1.28E+06 l , lI-131 l3.56E+08 15.09E+08 12.92E+08 11.67E+11 l8.72E+08 l 59 l1.34E+08 l lI-132 l1.98E-01 l5.29E-01 i!.85E-01 l1.85E+01 18.43E-01 l ND l9.95E-02 l lI-133 l4.65E+06 l8.09E+06 l2.47E+06 l1.19E+09 l1.41E+07 l ND l7.27E+06 l , lI-134 l0.00E+00 l0.00E+00 l0.00E+00 l1.15E-10 l0.00E+00 l ND l0.00E+00 l gw .- fl : n,
~
L
+ -
APA ZZ-01003-Pcv. 0 V -:
), TABLE 5 (Contd.)
ADULT PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m8 mrem /yr) per (VCi/sec) ! l -l . l. l Total l l l l lNuclidel Bone l Liver i Body 1 Thyroid i Kidney l Lung GI-LLI I lI-135 l1.54E+04 ;14.04E+04 l1.49E+04 l2.67E+06 l6.48E+04 l ND l4.57E+04 l Cse 134 l1.70E+10 4.04E+10 l3.30E+10 l ND l1.31E+10 l4.34E+09 l7.07E+08 iCs-136 l7.91E+08 3.12E+09 l2.25E+09 l ND l1.74E+09 l2.38E+08 l3.55E+08 lCs-137 12.22E+10 13.03E+10 l1.99E+10 l 4 , ND l1.03E+10 l3.42E+09 l5.87E+08-l
\Cs-138 l0.00E+00']O.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l
- ' lBa-139 l5.34E-09 l3.08E-12 l1.56E-10 l ND l3.55E-12 l2.16E-12 l9.46E-09 l' lBa-140 '3.23E+06'l4.06E+03 l2.12E+05 l. ND l1.38E+03 l2.32E+03 l6.65E+06 lBa-141 ,0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00
,lBa-142_l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 .0.00E+00 ,
- e. lLa-140 l5.42E-01 l2.73E-01 l7.22E-02 l ND l ND l ND l2.01E+04 [.
( , lLa-142 l0.00E+00~l0.00E+00 l0.00E+00 l ND .l ND l ND l7.45E-09 lCo-141 l5.82E+02 l3.94E+02 l4.46E+01 l ND l1.83E+02 l ND l1.50E+06 lCe-143 l4.99E+00 l3.69E+03 l4.09E-01 l ND l1.63E+00 l ND l1.38E+05 l lCe-144 l4.30E+04 l1.80E+04 l2.31E+03 l ND l1.07E+04 l ND l1.45E+07 l lPr-143 l1.90E+01 l7.61E+00 l9.40E-01 l ND l4.39E+00 l 'ND l8.31E+04 l lPr-144 l0.00E+00 l0.00E+00 l0.00E+00 l ND- l0.00E+00 l ND 0.00E+00 l lNd-147-l1.13E+01 l1.31E+01 l7.82E-01 l ND 17.64E+00 l ND 6.28E+04 l- i lEu-154 l2.84E+03 , 3.49E+02 l2.49E+02 l ND 1.67E+03 l ND ; 2.53E+05 l
- lHf-181 l1.71E+01 l 8. 31E+01 l 7.' 70E+00 - l ND 1.79E+01 l ND ;
9.46E+04 ! lW-187 l7.83E+02 16.54E+02 l2.29E+02-l ND ND l ND 2.14E+0F l
, 'lNp-239 l4.43E-01 l4.35E-02 l2.40E-02 l ND l1.36E-01 l ND l8.93E+03 l 4
Jh. v 4 r; g
~ _ _ _
= RCv. 0 '!
,n i
f TABLE 5 (Contdj y ADULT PATH'iAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway j (m8 mrem /yr) per (VCi/sec)
, 3, i l
l l l l Total l l l l l ,
,jNuclidel Bone l Liver ! Pody l Thyroid l Kidney I Lung l GI-LLI l lH-3 l ND-. l2.26E*03 l2.26E+03 l'2.26E+03 12.26E+03 l2.26E+03 l2.26E+03 l }
l B e -7 .. l9.24E+04.l2.11E+05 l1.03E+05 l ND l2.23E+05-l ND l3.66E+07-l
-lC-14 l2.28E+08 14.55E+C7 l4.55E+07 l4.55E+G l4.55E+07 l4.55E+07 l4.53E+07 ' [ !
, lNa-24 l2.69E+05 l2.69E+05 l2.69E+05 l2.69E% 5 l2.69E+05 '2.69E+05 l2.69E+05 lP-32 l1.40E+09 l8.74E+07 l5.43E+07 l is l ND l ND l1.58E+08 lCr-51 l ND l NO l4.64E+04 l2.78E+04 l1.02E+04 l6.16E+04 l1.17E+07 l j lMn-54 l ND l3.13E+08 l5.97E+07 l ND 19.31E+07 l ND l9.59E+08 l .
i lMn-56 l ND l1.60E+01 l2.84E+00 l- ND l2.03E+01 l ND l5.10E+02 l l lFe-55 l2.10E+08 l1.45E+08 l3.38E+07 l ND l ND l8.08E+07 l8.31E+07 l lFe l1.26E+08 l2.96E+08 l1.14E+08 l ND l ND l8.28E+07 l9.88E+08 [ .: .. Co-57 Co-58 l l ND ND l1.17E+07 l1.95E+07 l 13.07E+07-l6.89E+07 l ND ND l l ND ND l l ND ND l2.97E+08 l6.23E+08' , Co-60 l ND l1.67E+08-l3.69E+08 l ND l ND l ND l3.14E+09 - lNi-63 l1.04E+10 l7.21E+08 l3.49E+08 l ND l ND l ND l1.50E+08 lNi-65: l6.16E+01 18.00E+00 l3.65E+00 l ND l ND 'l ND. l2.03E+02 V ' lCu-64' l ND .l9.20E+03 l4.32E+03 l ND l2.32E+04 l ND 17.84E+05 l ! l lZn-65 l3.17E+08 l1.01E+09 l4.56E+08 l ND l6. 75E+08 l ND l6.36E+08 l l- .lZn-69 l5.52E-06 l1.05E-05 l7.34E-07 l ND l6.85E-06 l ND l1.59E-06 l lBr-82 'l ND 'l ND l1.50E+06 l ND l ND l ND l1.72E+06 l
, lBr-83 l ND l ND l3.11E+00 l ND l ND l ND 14.48E+00 l lBr-84 l ND l ND l0 00E+00 l ND l ND l ND l0.00E+00 i
-lBr-85 l ND l ND l0.00E+00 l ND l ND l ND 10.00E+00 I
lRb-86 l ND l2.19E+08 l1.02E+08 l ND l ND l ND 14.33E+07 l lRb-88~ l ND 0.00E+00 l0.00E+00 l ND l ND l ND -l0.00E+00 l lRb-89 l ND l0.00E+00 l0.0GE+00 l ND l ND l ND l0.00E+00 l lSr-89 l9.97E+09 l ND l2.86E+08 l ND l ND l ND l1.60E+09 l
-lSr-90 l6.05E+11 l ND l1.48E+11 l ND l ND l ND l1.75E+10 l
- 9. .lSr-91 3.05E+05 l ND l1.23E+04 l ND l ND l ND l1.45E+06 l
.ISr-92 '4.27E+02 l ND l1.85E+01 l ND l ND l ND l8.46E+03 l lY-90 l1.33E+04 l ND l3.57E+02 l ND l ND l ND l1.41E+08'l
)
b , L % k
. 74 i
L ' f
p - 1 L x APA-ZZe01003 R;v. 0 , p i , l TABLE 5 (Contd.) i
' ADULT PATHWAY DOSE FACTORS (Ry ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES ]
~
L Vegetation Pathway (m8 mrem /yr) per (pCi/sec) i f I l l Total l l l l. l lNue;idel 9ene l Liver Body l Thyroid l Kidney l Lung l GI-LLI l- l lY-71m l5.24E-09 l ND l2.03E-10 l ND l ND l ND. l1.54E-08 lY 91 l5.11E+06 l ND l1.37E+05 l ND l ND l ND l2.81E+09 lf-92 l9.16E-01 l ND l2.68E-02 l ND l ND ND .ll.60E+04 g lY-93 l1.70E+02 l ND l4.68E+00 l ND l ND ND 15.38E+06 P lZr-95 :l1.17E+06 l3.77E+05 l2.55E+05 l ND l5.91E+05 i ND l1.19E+09 .; lZr-97 l3.37E+02 l6.81E+01 l3.?.1E+01 ND l1.03E+02 l ND 2.11E+07 l lNb-95 l1.42E+05 l7.92E+04 l4.26E+04 ND l7.83E+04 l ND 4.81E+08 l .i f'- lMo l0.00E+00 16.15E+06 l1.17E+06 l ND l1.39E+07 l ND l1.43E+07 ( lTc-99m l3.10E+00 l8.77EWO l1.12E+02 l ND l1.33E+02 l4.30E+00 l5.19E+03 lTc-101 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 10.00E+00 l ; I ~ l2.06E+06 l l1.82E+07 l ND l5.57E+08 l lRu-1031l4.77E'+06 l ND ND lRu-105 l5.39E+01 l ND l2.13E+01 l ND l6.97E+02 l ND l3.30E+04 l e lRu-106 1.93E+08 l ND l2.44E+07 l. ND l3.72E+08 l ND l1.25E+10 l lAg-110m 1.05E+07 19.75E+06 l5.79E+06 l ND l1.92E+07 l ND l3.98E+09 l , lCd-109 l0.00E+00 l8.36E+07 l2.92E+06 l ND l8.00E+07 l ND l8.43E+08 l l lSn-113 l4.16E+08 l1.18E+07 l2.40E+07 l6.75E+06 l ND l ND l1.25E+09 l lSb-124 11.04E+08 l1.96E+06 l4.11E+07 l2.51E+05 l ND l8.07E+07 l2.94E+09 l lSb-125 1.37E+08 l1.53E+06 13.2SE+07 l1.39E+05 l ND l1.05E+08 l1.50E+09 l , lTe-125m 9.66E+07 l3.50E+07 l1.29E+07 l2.90E+07 13.93E+08 l ND l3.86E+08 l , lTe-127ml3.49E+08 11.25E+08 l4.26E+07 l8.92E+07 l1.42E+09 l ND l1.17E+09 l J lTo-127-l5.66E+03 l2.03E+03 l1.23E+03 l4.20E+03 l2.31E+04 l ND l4.47E405 l , lTe-129ml2.51E+08 l9.38E+07 l3.98E+07 l8.64E+07 l1.05E+09 l ND l1.27E+09 l lTe-129 l7.65E-04 l2.87E-04 l1.86E-04 l5.87E-04 l3.22E-03 l ND l5.77E-04 l lTe-131ml9.12E+05 l4.46E+05 l3.72E+05 l7.07E+05 l4.52E+06 l ND l4.43E+07 l lTo-131 l0.00E+00 l0.00E+00 l0.00E+00 l0.00E+00-l0.00E+00 l ND 10.00E+00 l lTe-132 l4.30E+06 l2.78E+06 l2.61E+06 l3.07E+06 l2.68E+07 l ND l1.32E+08 l lI-130 l3.93E+05 11.16E+06 l4.57E+05 l9.81E+07 l1.81E+06 l ND l9.97E+05 l l' lI-131' l8.08E+07 1.16E+08 l6.62E+07 13.79E+10 l1.98E+08 l ND l3.05E+07 l lI-132 l5.77E+01 1 1.54E+02 l5.40E+01 l5.40E+03 l2.46E+02 l ND l2.90E+01 l
, 'lI-133 l2.09E+06 3.63E+06 l1.11E+06 l5.33E+08 l6.33E+06 l ND l3.26E+06 l i
> 'lI-134 l9.69E-05 ,2.63E-04 l9.42E-05 l4.56E-03 l4.19E-04 l ND l2.30E-07 l l t
t A ., Y l t l' L. .
f O _ m .. ',, e n R;v. O TABLE 5 (Contd.) ADULT PATHVAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE CASES Vegetation Pathway (m8 mrom/yr) per (itC1/sec)
=l. l l l Total l l l l l lNuclidel Bone I Liver l Bodv l Thyroid l Kidney I Lung l GI-LLI l
'lI-135 l3.90E+04 l1.02E+05 l3.77E+04 l6.74E+06 l1.64E+05 l~ ND l1.15E+05-l lCs-134 l4.67E+09 l1.11E+10 19.08E+09 l ND l3.59E+09 l1.19E+09 :1.94E+08 l lCs-136 l4.27E+07 l1.69E+08 l1.21E+08 l ND 19.38E+07 1.29E+07 1.91E+07 l lCs-137 l6.36E+09 18.70E+09 l5.70E+09 l ND l2.95E+09 ;9.81E+08 [1.66E+08 l lCs-138 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l lBa-139 l2.86E-02 l2.04E-05 l8.39E-04 l ND l1.91E-05 l1.16E-05 l5.08E 02-l lBa-140 11.29E+08 l1.61E+05 l8.42E+06 l ND l5.49E+04 l9.24E+04 l2.65E+08 l lBa-141 l 0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 0.00E+00 l0.00E+00 l
-lBa-142.! 0.00E+00 l0.00E+00 10.00E+00 l 'ND l0.00E+00 0.00E+00- 0.00E+00 l lLa-140 11.9sE+03.l9.97E+02 l2.63E+02 l ND l ND l ND 7.32E+07 l lLa-142 l2.03E-04 l9.21E-05 l2.29E-05 ND l ND l ND 6.72E-01 lCo-141 l1.97E+05 11.33E+05 l1.51E+04 ND 16.19E+04 l ND 5.10E+08 .
lCo-143'l9.98E+02 l7.38E+05 l8.17E+01 ND 13.2SE+02 ND l2.76E+07 lCa-144 13.29E+07 l1.38E+07 l1.77E+06 l ND l8.16E+06 ND l1.11E+10 l lPr-143 l6.26E+04 l2.51E+04 l3.10E+03 l ND l1.45E+04 l . ND l2.74E+08 l lPr-144-l0.00E+00 l0.00E+00 10.00E+00 l ND l0.00E+00 [. ND l0.00E+00 l lNd-147 l3.33E+04 l3.85Ecv4 l2.31E+03 l . ND l2.25E+04 l ND l1.85E+08 l lEu-154,14.85E+07 l5.97E+06 l4.25E+06 l ND l2.86E+07 l ND l4.32E+09 l lHf-181 L l1.40E+05 l6.82E+05 l 6.32E+04 l ND l1.47E+05 l ND l7.76E+08 l lW-187 l3.80E+04 l3.18E+04 l1.11E+04 l ND l ND l ND. l1.04E+07 l lNp-239 l1.43E+03 l1.41E+02 l7.76E+01'l ND l4.39E+02 l ND l2.89E+07 l 4
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, 3.6- Caseous Radwaste Treatment System 41862 3.6.1 REC-9.9.1.1 h 4160 i: The VENTILATION EXHAUST TREATMENT SYSTEM and the
'i - WASTE GAS HOLDUP SYSTEM shall be OPERABLE and or appropriate portions of these systems shall be used to reduce releases of radioactivity when the
. projected doses in 31 days due to gaseous effluent releases, Crom each unit, to areas at ; and beyond the SITE BOUNDARY would exceed:
- a. 0.2 mrad to air from gamma radiation, or 7
,1 b. 0.4 mrad to air from beta _ radiation, or
- c. 0.3 mrem to any organ of,an Individual 5 3.6.2 Description of the Gaseous Radwaste Treatment
[
~
System i' I"# 5 The gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gascous effluents require treatment prior to being released to the environment. The r gaseous radwaste treatment system is designed to allow for the retention of all. gaseous fission 1 products to be discharged from the reactor. (" coolant system. The retention system consists of eight (8) waste gas decay tanks, six-(6) for uso d; during normal operations and two-(2) for use I during shutdown conditions. Normally, waste o gases will be retained for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA. 1y 37 l1 L L 1 [w.k V 1 L I L M it c o
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i: i u - 1 I' 3.6.3 Operability of the' Gaseous Radwaste Treatment-System l j n
-The OPERABILITY of the gaseous radwaste' treatment j system' ensures this system will be available for ;
use when. gases require treatment prior to their release to the environment. OPERABILITY is '! e demonstrated through compliance with Sections l 9.6.1.1, 9.7.1.1, and 9.8.1.1. I Projected deses (gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the t SITE BOUNDARY are determined each 31 days by ) L dividing,the cumulative annual total by the :
? number of elapsed months. l P : ! 4.0 DOSE AND DOSE COMMITMENT FROM URANIUM TUEL CYCLE SOURCE _S h 41864 41 REC Section 9.10.1.1 4160 f:
3 The annual (calendar year) dose or dose t commitment to any MEMBER OF THE PUBLIC due to - i
'., releases of radioactivity 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 shall be limited to less than or equal to 75 mrem. ' t 4.2 Calculation of Dose and Dose Commitment from ! ,. Uranium Fuel Cycle Sources 1
I The annual dose or' dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as: L a) Dose to the total body and internal organs due j to gamma ray exposure from submersion in a cloud of radioactive noble gases,. ground plane exposure, and direct radiation from the Unit o and outside storage tanks; a > d l
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b) Dose to the skin due to beta radiation from submersion in a cloud of radioactive noble-gases, and ground plane exposure; i
- c) Thyroid dose due to inhalation and ingestion of radioiodines; and i d) organ dose due to inhalation and' ingestion of radioactive material.
* - It is assumed-that total body dose from sources of gamma radiation irradiates internal body _
organs at the same numerical rate. (Ref.-11.12.5)
~
The dose from gaseous: effluents is considered to be the summation of the dose at the ndividual's residence and the dose to-the indivioual from-activities within'the SITE BOUNDARY.
" - Since the doses via liquid releases.are very conservatively evaluated, there is reasonable assurance that no real individual will receive,a significant: dose from radioactive liquid-release 7 pathways. Therefore, only doses to individuals via airborne pathways:and doses resulting from
direct radiation are considered in determining compliance to 40 CFR 190. (Ref. 11.12.3)- It should be noted-that there are no other j Uranium' Fuel Cycle Sources within 8km of the Callaway Plant. y i .s L l 79
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U [' The MEMBER OF THE PUBLIC is considered to be a real' individual, including all persons not
, occupationa31y associated with the Callaway j Plant, but wa.o may use portions of the plant site
- for recreational or other purposes not associated 1 with the plant. (Ref. 11.4 and 11.8.10.)
Accordingly, it is necessary to characterize this
;- individual with respect to his utilization of f
areas both within and at or beyond the SITE ' L BOUNDARY and identify, as far as possible, major assumptions which couJd be reevaluated if I necessary to demonstrous continued compliance with 40 CFR 190 through the use of more realistic assumptions. (Ref. 11.12.3 and 11.12.4) The evaluation of Total Dose from the Uranium
- Fuel Cycle should consider the dose to two ! Critical Receptors: a) The Nearest Resident, and ] b) The Critical Receptor within the SITE BOUNDARY.
j .,,, 4.2.2 Total Dese to the Nearest Resident The dose to the Nearest Resident is due to plume ' exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident. It is assumed that direct radiation dose from operation of the Unit and outside storage tanks, and dose from gaseous effluents due to activities within the SITE BOUNDARY, is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q. 3 i
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w .... -- ..... Rev. O b. [ g ~~ The location of the Nearest Resident in each
! meteorological sector is determined from the I'
Annual Land Use Census conducted in accordance with the Requirements of Section 9.12.1.1. l- 4.2.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for manage. tent of the residual f lands surrounding the Callaway Plant, including i some areas within the SITE BOUNDARY. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing,
, etc.) but recreational use is excluded in an area immediately surrounding the plant site (Refer to Figure 4.1). Much of the residual lands within
; the SITE BOUNDARY are leased to area farmers by a
the Department of Conservation to provide income to support management and development costs. Activities conducted under these leases are
- primarily comprised of farming (animal feed),
grazing, and forestry. (Ref 11.7.2, 11.7.3, 11.13, 11.13.1). ' Based on the utilization of areas within the SITE BOUNDARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The current tenant has estimated that he spends approximately 1100 hours per year working in this area (Ref 11.5.5). Occupancy of areas within the SITE BOUNDARY is assumed to be Averaged over a period of one year. Any reevaluation of assumptiona should !nclude a
; reevaluation of the occupancy perded - L the locations of real exposure (e.g. a real 1 individual would not simultaneously exist at each
! point of maximum exposure).
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__._.._m..._......;. M,, Rev. O V E Q 4.2.3.1 Total Dose to the Farmer from Gaseous Effluents
, The Total Dose to the farmer from gaseous +
effluents is calculated using the methodology discussed in Section 3, utilizing concurrent
?
meteorological data at the farmer's residence and j
- historical meteorlogical data from Table 10 for activities within the SITE BOUNDAR'l. These dispersion parameters were calculated by assuming
'r
. that the farmer's time is equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of 1100
! hours / year factored into their value (Ref.
t 11.5.6). The residence of the current tenant is located at a distance of 3830 meters in the SE sector. No
- meat or milk animals or vegetable gardens were identified by the 1987 Land Use Census for this location, therefore, the gaseous effluents dose 2 at the farmer's residence is due to plume t '
exposure from Noble Gases and the ground plane and inhalation pathways, t
. It is assumed that food ingestion pathways do not exist within the SITE BOUNDARY, therefore the '
gaseous effluents dose within the SITE BOUNDARY = is due to plume exposure from Noble Gases and the ground plane and inhalation pathways, o 4.2.3.2 Total Dose from Direct Radiation 4
.i 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 radioactive materials, and constitutes the only potentially significant source of direct radiation dose from outside storage tanks to a MEMBER OF THE PUBLIC. (Ref. 11.6.14, 11.6.15, y 11.6.16, and 11.6.17.)
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;4 '
c .hasibeen determined-to be 450 meters from the RWST.
% :The'RWST=is alright' circular cylinder 4
.1
- approximately 12 meters in diameter, 14 meters in height with a-capacity;of approximately~1,514,0004 1> , 1 . y liters. _(Ref. .11.6.'17.,)- The.-walls are of type:
304 stainless steel and have-an~~ average-thicknessi '
/ *
-of1.87 cm. (Ref. 11.14.1.)
T' The' direct radiation dose'from the-RWST'is
., calculated based on the. tanks average.. isotopic t content and the parameters discussed above, .
considering buildup.and. attenuation within'the
,,. volumeisource.. Appropriate methodology for calculating the dose. rate from a volume'nource'is given in TID 7004, " Reactor Shielding'Deuign.
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+ '. Manual" (Ref. 11.17). The computer prog::am ISOSHLD (Ref. 11.18, 11.19, 11.20)'will<normally-711 be utilized to perform this calculation.
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- t. The maximum. direct radiation dose;from the Unit-W :" 4 to a MEMBER OF'THE PUBLIC has been determined to 1 be 7E-2 mrads/ calendar' year, based on a point
, . source:of primary coolant,N-16 in the steam.
3 . generators. This source term was then projected-o, onto the.inside surface of:the containment, dome, b-- .taking.. credit for.. shielding provided by the W; ' containment dome andifor distance attenuation. F: , No credit'was allowed:for shielding,by.other- [ .. structures or componen?.s'..The number of. gammas. per second was generatedLand~then' converted'to;a s I , dose ~ rate at the given'd! stance by use of ANSI /ANS-6.'6.1, "Calculatien and Measurement of , Direct and Scattered = Gamma Radiation from LWR .! n'
-Nuclear Power Plant 1979", whi-h considers . ,
attenuation'and buildup in' air. The final value: -i S ,
=1s' based on one'= unit operating at 200% Power.
The distance was1 determined to be 367 meters, i 1
--which is approximately the closest point of the f boundary:of.the Owner Controlled-Area fenceiwhich--
1s not obscurred by significant plant structures. c[. 4 . - (Ref. 11. '14. 3 . ) , y The maximum direct radiation dose,from the-Unit l to':a MEMBER OF-THE-PUBLIC due toLactivities-ij - within the-SITE BOUNDARY is thus arproximately i 9E-3 : mrads per -year, assuming:a maximum occupancy q of 1100: hours per yea.. q- [- i a; l l -i }
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' 141835--5,0 - RADIOLOGICAL ENVIRONMENTAL MONITORING:
< ,' ;3535
'418661 15 ; 1- REC Section'9.11.1.1.
_Thefradiologicalcenvironmental monitoring program:
.shall' be conducted asJapacified ~1n Table 9.11-A. .
5.2 Description of-the Radiological Environmental 1 m ~ Monitoring Program
,The~ Radiological Environmental. Monitoring: Program,
, is intendedLto.act_as7a: background data base for-
- preoperation and-to supplement the radiolog' cal-effluent release monitoring program during plant operation. Radiation exposure':to-the public-~from -
'the various specific-pathways land direct L _
radiation can be adequately evaluated by this-program, Some deviations.from.the. sampling frequency may-be: necessary due' to: seasonal unavailability,- hazardous 1 conditions, or.otherLlegitimate bases.- Effortsaare made to obtain all required samples > withinutime frame outlines. Any deviation (s)Linn samplingsfrequency,or location'is documented.in-
'the AnnualjRadiological Environmental Operating
~
Report. r The Env'ironmentalisamples are collected,and' analyzedLat the frequency _ outlined in Table 6. Reporting levelsLand lower limits of detection. Hg (LLD) are given in:Tabl'es 7 and 8. N' c5;. 4 3 -- . Y \
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Airborne,1waterbore, and ingestionJaamples:
, collected >under.the monitoring program _are-analyzed byLan independent, third-party
, n' laboratory. This. laboratory-is' required to
. participate in the Environmental Protection-Agency's (EPA)-Environmental _RadioactivityL_
Laboratory Intercomparison Studies-(Crosscheck)- eb v Program or an equivalent program. Parti ~cipation ine)udes all of the determinations (sample: medium , g". - _ . g'
-:radionuclide combination) thattare offered byJ s
P tthe. EPA'andLthat are alsolincluded i'n thei "
"*? '
'renitoring program. +
p '& , h, 5.3 Performance Testine of-Environmental
,-g . Thermoluminescence Dosimeters
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-Thermoluminescence Detectors.'(TLD's) usedtin the
. Environmental Monitoring Program-are tested for-accuracy and precision to demonstrate compliance with Regulatory Guide 4.13.-(Ref. 11.16)'.
ma Energy dependence is tested at-several energies,
. ,: between'30 kev and-3MeV.correspondingnto',the!
approximate. energies of~the predominant Noble. ' n: Gases-(80, 160, 200 kev),-Cs-137 (662 kev),.Co-60 (1225: kev), and at least one energy lesn'than 80
" kev. 'Other testing is performed 1 relative to" E >
either'Cs-137 or'Co-60. t.e p l T i, 3
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RADIOLOGICAL ENVitt0NMf MI AL MONIlottlNG PitOCRAM SAMPLING AND TYPE AND TREQU(NCYi
. NUMBER Of REPHISENTATIVE SAMPLES L> POSult[ PATilWAY COttfCil0M fittOUINCY Or ANALYSIS BM0/ Oft SAMPLE AND SAMPL E l OCAllONS
-At least once per 92 days Camma Dose
. (' 1. Direct Radiation fa0 routine monitorin9 stations either '
witti two or more dosimeters or with one
. Instrument for measuring and recording
- dose rate continuously, placed as follows:
An inner ring of sixteen stations, one in each meteorological sector in the general area of; the SilE BOUNDARY. Sta t iors - locating Code Sector
~
Site Descriptions . 0.3 Miles East or llwy 0 and CC Junction, Callaway 1.9 mi. # 38a9' M Oss A Electric Coop. Utility Pole No. 18892 8 County Road 42:8, 0.9 Miles Soutti or.etwy 0, Callaway O.9 mi. # 17' NME 47 Electric Coop. Utility Fole No. 28151 ~ C Cour,ty Road 8stio, 1.5 Miles Soutta or Itwy 0, Plant 0.ts mi. @ 45' lee _
. 48 Security Area Sign Post 0 Primary Meteorolo
- $ ation Code. Sec_lo r : . Sjte DeseripGon Locali_o_rj . y 8:5 P Cosenty fload 8:28,- 0.1 Hiles West or- etwy CC, Callaway+
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- 2. Airborne 3arij sjgtrl . .
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- 3. Waterborne
- a. Sie r fa ce' One sample espst ream ' Composite saemplef Camena isotopic areadysisd .y over a period - of each sample,
- b. Drink i sig One sample of cacts Compasite sample over 8-131 analysis on-one to t!ree of Llie .
- a. Misk . Samples from milking animals 8-131 analysis-in three 'locatioss withis asilmals are oss pasture, monthly at semimonthly weten
- b. Fish one sample of each analysisd on commercially ared semiannytally if they r ecrea tional ly. important are riot seasonaf. edible portions.
- p. z =- - gm 7 L 'm ;=&-~-
- y ,
- l. I i Z r-Nb-95 400 ** i i 0.9 3 -100 l l 1-831 2 . l I 1,000
- For drinking water samplus. f or sus f' ace water' samples a value of' 30,000 pCi/l is used.
- f or sist-face water samples, a valise of 3000 pCi/l ~is'used.
- 9]n '" ,
- APAi22-01003I
- radioactive: material'in a. sample that.will; (fA %
- 2.22 'Y ' exp l (-let) if.N[
- nuclides-are to:be considered. Other peaks .
- y. .
- a. ac n e
- w. g' r .
- h. .: M p T"\,/./yy*s g"
- t. lij f N -=C E N L . !
- 5
- w. .
- i * '-
- ~ .
- p. ,, ;. .- 3 *, ~ ~ '
- - s Ig:us..- '
- 6. % .L. \ c- o a
- c ' 2 3 7:n:FI 5.13 FE /. 6 l
- LOGAN REEK O/ ~
- . m., _
- 6~- . TOWNS , '
- i. o i h MILES l-UNION ELECTRIC CO.
- 8-
- (s x 1 ,
- e. .
- if N
- q. ; j' gi /ja. v.;.!. w r
- t1 .
- ll e8 e
- gg0~ t-w m i I Ia i ! !
- t. i
- w .
- gy .,"
- r. G g,s e m. ;
- ?
- 1-e
- year. pe::1od of May 24,3 1973-to May 5, 1975 and- '
- ( I 105 _
- l performed for.22: standard distances.-to obtain'the-
- 3. ~ m d1 nk y,
- quarter. Short. term dispersion estimates _are determined by multiplying the: appropriate.long-term dispersion estimate'by accorrection factor
- d. s ,
- T 3 = ' The total number of hours'of the short term 4 >
- pui,
1 ^withintthel SITE BOUNDARY arefintended for'a~ narrow scope; application: .That of calculating the- . dose to the current'tennant farmer'from-gaseous
- p '6.2 Atmospheric Dispersion' Parameters for Farming Areas Within The SITE BOUNDARY-Thei dispe'sion:parametersffor r farming areas-
- m. ,
j. I 1 - ( w. - . - 108 - a t 1_ - - -- - -.-:=. ,. . 4 y - APA-ZZ-01003 . Rov. 0 .For the purpose of these calculations, i t w4...% 'L [ 'N ., assumed that all of the farmer's time, L approximately 1100. hours per yeat, is spent on croplands within the SITE BOUNDARY, and that hds time is divided evenly over all of.the cropland:A. Fractional acreage / time - weighted dispersion parameters were calculated for each plot as described in reference 11.5.6. The weighted = dispersion parameters for each plot were.then [~ ~ summed (according to type) in order to produce a composite value of.the dispersion parameters. The dispersion parameters presented in Tables 9 &
- effluents'while1he conducts farming activities; 1 within the-SITE BOUNDARY.
=. m s-s L n.. t gr ., - 109 - ;7 L. 4 er.,* ' 42 / ' i ~ ' Ara-zz-01oo3 '.[ek; u nev. o . _ .: T ABt f 9 tilMtfJ! AM8tOAt. Ay[ RAGE AIMOSPitf RIC DISPf HSION PARAME TERS (M ^ exowASIE Bustc No vt:(1 , 11BSIANCE ' X/4 N/Q [ j .xg t ayett/2sideeieted r pecayed/ pen s e te<f g/9 -tocAtiotu bj SfesoR IMrstRSI _ , (sec/mi) {sec/m3) ~ (sec/m3) - (m 2) . 2200 1.3E-6. 1.30-6 .1.1E-6 4.3E-9 SITE BOUNDARY N00W 2112 5.7E-T 5.7E-T 4.90-1 1.60-9 Nea re s t Cow ( c ) WSW WSW n:T2 5.7E-7 5.7E-7 4.9E-T t.60-9 Nearest coat (c) '2864 8.7E-7 8.TE-T 7.2E-T 2.6E-9 Nearest Meat AnimaI (d) NW Nearest Vegtable (c) T.2E-T 2.6E-9 Carden NW 2864 8.7E-7 8.TL-/ NNW 2864 8.7E-7 8.7E-T' 7.2E-7 2.6E-9' Iscarest Itesidence(c) 'N/A 2.9E-7 2.9E-7 2.6E-7 1.lE-9 Farming Areas Wittiin 8s/A - Site Boundary (c)(c) (a) Va l ues g i ven a re f rom I SAR Ta b l e 2. 3-84 (b) Data rrom 1988 L.and use Census (c) values derived f rom TSAR 1able 2. 3-81, usirare time mettsudology presented in Equation (6.i) (Her. 11.5.6) (d) Ihe nea res t mea t assima l is assemed to exist at tiie incation of ttee seearest resident. (e) The$a valtees were derived for a narrow scope appli- E xtreme caution stenld be exercised whess Jetermissing tfieir suitability t'or use in otteer .3 4 ,ca t i osas, i Basilding Stiape Pa rameter (C) = 0.5 (Her. 11.5.3 ) Vertical Heigtet or Highest Adjaceset f$uilding (V) = 19.96 meters (Ref. 98.5.3) 1 l 1 -110- . ,. -a f. . . . . if i +- _ APA.ty-o1003 Q ~ 'Mey. O .. T Allt i . ]88__ tilGilfSI ant (UAL. A\rtitAGI AIMOSP11t hic _ Dl}ff_RSlON l'ARAMf f f RS f aJ tillii VI NI , DfSIAtH;L X/Q X/4 f SICIOf t (K[t (I Sj 3/g tycayed]tedypteigd Decaye_dfik ple ge_d D_fg 1 OCAI 8 08(_{tt ) _ (sec/m3) {sec/m3) {sec/m3) {m 2) . ~ NNW 220s8 1.0L-6 9.98-( 8.$E-T 4.3E-9 SIIE BOUNDARY 88 .s 1-1 3. 81 - T I.6E-9 Nea res t Cow (c ) WSW 2112 8.4t-T 8 3.80-1 1.60-9 Nearest Coat (c) .W 2112 4.4E-7 4.se l-T 2868: 6.8E-T 6.8L-/ 5.70-T 2.6E-9 Nearest Heat Areimal (d) h80W Nearest Vegtable (c) S.it-7 2.6E-9 NNW 28684 6.8E-7 6.80-1 Garden NNW 286ss 6.8E-7 6.8E-T $.TE-T 2.6E-9 Nearest Residence (cl f arming Areas Wittein the 2.Il-1 f.9L-l 3.1E-9 Site Boundary (c)(c) N/A N/A 2.1E-f (a) Va l eee s g i ven a re from ISAR Table 2.3-82 (b) Data f rom 1988 Iand Use Censtes (c) Valucs derived f rom ISAft lable 2.3-83, using tree metliodology peeser,ted in E qua t ioes ( 6.1 ) ( He r. 13.5.6 ) (d) (e) line lleesenearest valisesmeat wereanimat derivedis fassiemed or a narrow to exist scope atapplication. (fee locatiers or steecaution Extreme riearestAliould resident. be exercised wieers detegnining tiseir suitability for esse ire utleer applicatisms. Basildirig Sloape Parameter (C) 0.3 (ite r. i t .$. ~ t Vertical lleigitt or itiginest Adjaceret basilding (Vi e 66.D meters (Het". 18.3.3) -Ill-' - - - -- m el - i , m. . .! 'f "' , i f,I[';W ApA.ZZ-01003- ' t , fa ' Y
- 10 therefore represent the distributed activities of the farmer within'the SITE BOUNDARY and his estimated occupancy period.
.n. l 3.- ii ' i 7- >, ; (.- V :o } ' P '
- R;v. O !
K.',.,m. 1. , c, , ..SHORT' TERM DISPERSION PARAMETERS;,(a) (e) i l l 1., t . ,, .. Slope Factor (S) . , l - Location (b) Sector. Distance Unit Vent: Radwaste ! (meters) Building.- cc , Vent 1
- TABLE 11 !
a y a Site Boundary S 1300 .328 .320- -l J- - ' cia , Nehrest Cow NW 5053 .263 .266 i 's . . . N'er4 rest Goat
- 11;"a -. a ;
'L - Nearest' Meat NNW 2736 .262 .268 >', i; Animal 1 3 1 Nearest Vegetable NNW 2865 .264 .268. '! 'L ; 4,< Garden , - , j , g.. . o .!! Nearest Residence NNW 2865 .264 .268 , (a)ic Reference 11.5.3 i > cc L(b)f Data from'1987 Land Use Census .. - .i (c}l Recirculation Factor = 1.0 .q n-f t \ f .i c s /- 4 [- , 1 " ; - 112 - l %Q$.! 7:p.: u 2 l > 1 s ! ,
- NW 5053 .263 .266 1
s A Y. .. u . . i . . , _ _ . . . ._ . . _ _ _ _ . . , , . lll l i i u I ' E .~ * ^ ') . ['. . At'A-18-0100 ) ' . ~ _ - - Rev. 0 .l.~, & LAULL_t2 APft ICAllOff UF AIMOSPl!IHIC DISPERSIOf( PARAMEI[RS DISPIRSION CON I Rot I 19tG CONIHOttING tOCAllON, {. lyse PAIlfW/.Y ODCM ltiffRINCF PARAMillM AGE GROUP. X/Q, decayed /enwicpleterd -- Site Botandary Noble Cas, Beta Air 3.$.2.1 (2.26 day fiafffife) . X/Q, decayeeffewsifepleted -- Site Soutwfary Noble Cas, Casmaa Air 3 . *> . 2.1 (2.26 day feaffiife) X/Q, decayed /assalepicterd --- Si te it.asanda ry Nots t e Ca s, total Body 3 . fs .1 & 3.$.I.1 (2.26 day featiidre) X/Q, decayed /assujepleted -- Site Boterodary Noble Gas, Skin 3.8s.? Sc 3.S.I.1 (2.26 day faa e rf ire) D/Q ~ Nearest Resident Grotend Plasse Deposition 3.$.2.2 X/Q, decayed / depleted Cini8d Nea re s t Residevit intia la t iott 3.5.2.2 ( 8 day f ra t ri i re) 3.3.2.2 D/Q* Cini ld Nearest Ressdent Uegetatiorn D/Q* Ctsild Nearest Resident Milk 3.$.2.2 3.$.2.2 D/Q* Clai ld fece res t Residerot Meat *For 11-3 afed C-las, X/Q, decayed / depleted is assed isostead of D/Q (Hereretace 11.11.1). -113- .. , . . _ ~ . m (I 4 <APA-ZZ-01003 i , . R;v. O j P _ l' , 1 7.0 f9 PORTING REQUIREMENTS i 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l Routine Annual Radiological Environmental Operating Reports covering the operation of the t unit during the previous calendar year shall be ! submitted prior to May 1 of each year. The ' initial report shall be submitted' prior.to May 1 ' of the year-following initial criticality.- 'x . , The Annual Radiological' Environmental Operating ; Reports shall include summaries, interpretations, and an analysis of trends of the results of the l p radiological environmental-surveillance. i activities for the report period, including a .; comparison with preoperational' studies, with operational controls and'with previous environmental surveillance reports, and an assessment cf the observed impacts of the plant , operation on the environment. The reports shall. l also include the results of Land Use Censuses required by'Section 9.12. The Annual Radiological Environmental Operating . Reports shall include the results of analysis of ; all radiological environmental samples and of all- i environmental radiation measurements taken during the period pursuant to the locations specified in r the Table and Figures in the ODCM, as well as a summarized the tabulated results of these analyses and measurements in the format of the , table in the Radiological Assessment Branch . Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be. submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a. supplementary report. i h - 114 - ,w.R~ l ** i T r:,J L Fh ' " o APA-ZZ-01003 i 'Rcv. O I 3 The reports shall also include thS followings a summary, description of the radiological ! environmental monitoring program; at least two legible. maps
- A ('
Comparison Program and the_ corrective action , being taken if the specified program is not being . ', performed.as required by Section 9.13.1; reasons ! for not conducting the Radiological Environmental ! Monitoring. Program as required by Section 9.11'.1 1 and discussion of all deviations-from tho' , sampling schedule of Table 9.11-A, discussion of environmental sample measurements that exceed the I reporting levels of Table 9.11-B, but are not the ; ' result of-the. plant effluents, pursuant to Section 9.11.1; and discussion of all analyses ~in which the LLD required by. Table 9.11-C was not achievable.- a 4?' , { I i k i i o *0ne map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. , ; ., -115- ,9MJ.A G,+'.s!..? 1 i. F ? APA-ZZ-01003 L- R;v. O b, y 7.2 SEMIANNUAL RADIOACTIVE EFFLUENT' RELEASE REPORT. Routine Semiannual Radioactive Effluent Release.
- covering all sampling 11ocations heyed to-a-table giving distances and directions from the centerline of one reactor; the results i of licensee. participation in the Interlaboratory.
/ 1 of each year. The period of the first report 1 shall begin with the date of initial criticality. s The Semiannual Radioactive Effluent Release o Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and [J ' solid waste released from the unit as. outlined in F Regulatory cuide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in folid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear h Power Plants, " Revision 1, June 1974, with data summarized on a quarterly basis following the format of Apper.31x B thereof. For solid wastes,. the format,for Table 3 in Appendix B shall be ' supplemented with three additional categories: "' class of solid waste (as defined by 10 CFR Part 60), type of container (e.g., LSA, Type A', Type B, Large Quantity), and SOLIDIFICATION agent or e absorbent (e.g., cement, urea formaldehyde). (, ? I 1 ? m 89 - N.f z . (_ m
- i. Reports. covering the operation of the unit,during F' the previous 6 months of operation shall be submitted within 60 days'after January 1 and July
- y < n
(H. +
- APA-ZZ-01003 1]1-g Rov. O py -
", t measured),:or in the form of joint frequency distributions of wind speed, wind direction, and . atmospheric stability *.' This same report shall include an assessment of.the. radiation doses due
- i The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in tha form oC an hour-by-hour listing on magnetic tape-of wind speed, wind direction, w atmospheric stability, and precipitation (if
conditions concurrent with the time of release of , radioactive materials in gaseous effluents, as determined by sampling frequency and meesurementi shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). a ' o '* *In lieu of submission with the Semiannual Radioactive Effluent Release Report, Union Electric has the option of retaining this sun? ary of required meteorological data on site in a file that shall be provided to the NRC upon request. . . . -117- ,4Q r - . '%d' l L. + + hN 6 1'7- , APA-ZZ-01003-Rcv.'O' lkqll jl Hd V
- A,. to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents.to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Technical Specifications, Figures 5.1-3 and 5.1-4) during the report period using historical average atmospheric conditions. All assumptions.used in making these assessments, i.e., specific activity, exposure time and location, shall be-included in these reports. The meteorological '
V= \ The Semiannual Radioactive Effluent Release Jyy! i Report to be submitted within 60 days after i..e
- D)
.ihi', tal n f exposed MEMBER OF-THE PUBLIC'from Reactor '
- January-1 of each year shall also include-an assessment of radiation. doses to the likely most
M)1, Acceptable methods for calculating the dose. contribution from liquid'and gaseous effluents JWM, are given in, Regulatory Guide 1.109, Rev; 1, 4; *ti October 1977. ; , 4 " The Semiannual Radioactive. Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting p period. + W D '" ' The Semiannual Radioactive Effluent Release UK Reports shall include any major changes made
- releases and other nearby uraniumffuel cycle sources, including doces from primary effluent Ny pathways'and direct radiation, for the previous A(f" calendar year to show conformance with 40 CFR Dil > a Part 190, " Environmental-Radiation Protection Standards for Nuclear Power Operation."
- V}
?C environmental monitoring identified byfthe Land sm Use Census pursuant to'Section 9.12.1. w ll)h The Semiannual Radioactive Effluent Release 11, Reports shall also include the following W pg information: An explanation as to why the 14 4 inoperability of liquid or gaseous effluent 44 , monitoring instrumentation was not corrected apb within the time specified in Section 9.1.1 or N[o 9.2.1, respectively;.and description of the 7 events leading to liquid holdup tanks or gas *!! storage tanks exceeding the limits of Technical ,fQ Specification 3.11.1.4 or 3.11.2.6, respectively. .c,. \< p_ 7 oOm.,. .. -118-sa. gy WL. \ ; :, ' ~ 4 i ti "hE ' ~. " I . APA- Z-01003 i: 1-Rov. O
- F-( during the reporting period to any Liquid or Op Gaseous Treatment Systems, pursuant to Section yf 10.1. It shall also include a listing of new i locations for dose calculationc and/or
i'. .$f ' I 2815 The Semiannual. Radioactive Effluent Release = . Reports shall also include as a part of or submitted concurrent with, a complete and legible o' copy.of all revisions;of the 0DCM that occurred during the reporting period pursuant to Specification 6.14.2. , n', -119- ;hfa r, 's M' l C o [j;i[j_'h p!.%' 7- v 'i arn-4,4-vivua M i ye , ':. R':v. O i, , 4 L,. 1s J i . % ,; 8.0 IMPLEMENTATION OF ODCM METHODOLOGY [R 'n h_ ,M!:, . The ODCM ; ovides the' mathematical relationships 1 j ,' used,to implement the Radioactive _ Effluent Controls. For routine effluent release and dose assessment, pp 4 computer codes are utilized to implement the ODCM !M methodologies.. These' codes have been evaluated by a qualified independent reviewer to ensure %'"P . . ~that they produce'results consistent with the B-- methodologses_ presented in the ODCM. (Ref. p 11.5.4.) e I- il I' .a 0-I i _i / ,f,I ' i ' , O .X c , 41 1 w s , h i e . h, -120-p . ? (. - o n; <4i t lJ h d' l c ~e 1 3. . - ^ C AFA-ZZ-01003 4"y Rov. 0 9.Q RADIOACTIVE EFFLUENT CONTROLS (REC) i ir NOTE 1. The terms in this section that appear in CAPITALIZED TYPE are defined in Technical 5pecifications. 2..All frequency notations are per Table 1.1 of Technical ' Specifications. 9.O.1 Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall 'be met. 9.0.2 Noncompliance with a; Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is' restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 9.0.3 When a Control is not met, except as provided in -the associated ACTION requirements, within 1 hour ACTION shall be initiated to place the unit in a MODE in which the Control does not apply by placing it, as applicable, in
- r. * '
Where ' corrective measures are completed that permit operation under the ACTION requirements, the l act:.on may be taken in accordance with the ,' specified time limits as measured from the time of fai*eure to meet the Control. Exceptions to these requirements are stated in the individual Controls. _This Control is not applicable in. MODE 5 or 6. Ah 5:J. -121- i ) ,, N- f , APA-ZZ-01003 ! Rcv. 0 j' l1 t in - 9.0.4 Entry into an OPERATIONAL MODE or other specified i condition shall not be made unless the conditions for the Cor. trol are met *.sthout reliance on provisions contained.in'the. ACTION requirements. This provision shall not prevent passage through r or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls. 9.0.5 Operability of equipment included in Section 9.0 +. > ' 'must be tracked.in the Equipment out-of-service-Log (EOSL) as per ODP-ZZ-00002, Equipment Status Control. I-4 + a l-ch s {is 4 1 i' A53T 1 Ip' p -122-1 -gg o . ' w nre.44-vauvs R;v. O ( l [ [ 9.1 RADIOACTIVE' LIQUID EFFLUENT MONITORING INSTRUMENTATION 41838 9.1.1 Controls
- a. At least HOT STANDBY within the next 6 hours,
- b. At least HOT SHUTDOWN within the following 6 hours, and
- c. At .'. east COLD SHUTDOWN within the subsequent 24 hours.
), are not exceeded. The Alarm / Trip Setpoints of . these channels shall be determined and adjustodi in accordance with the methodology and parameters l e' in the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: At all times, t. c ; ACTION:
- 9.1.1.1 The~ radioactive liquid effluent monitoring instrumentation. channels shown in Table 9.1-A 7 shall be OPERABLE with their Alarm / Trip E:tpoints f' set to ensure that the limits of Section 9.3.1.1.
. monitoring instrumentation. channel Alarm / Trip Setpoint less conservative than
- a. With a radioactive liquid effluent
< effluents monitored by the affected channel, or declare the channel inoperable, ,
- required by the above Control, immediately suspend the release of radioactive liquid.
" pursuant to Section 7.2, why this inoperability was not corrected within the time specified.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 9.1-A. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, L
,are not applicable. 41839 '9.1.2 Surveillance Requirements 9.1.2.1 -Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated
- c. The provisions of Sections 9.0.3 and.9.0.4
.' 1 ' SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown 3 in Table 9.1-B. .. i g .T1 ) 3-E f.ii- -123-l AFA-22-01003 ' rov. O. , s n , .41840 9.1.3 Bases , j H9.l.3.1 Radioactive Licuid Effluent Monitorine ! Instrumentation- I The radioactive. liquid effluent instrumentation l 1s provided to monitor and control, as. applicable, the releases of-radioactive materials: . in liquid effluents during actual or potential releases of' liquid effluents. The Alarm / Trip- . Setpoints for these. instruments shall be calculated and adjusted in accordance with the-methodology.and parameters in the ODCM to ensure 3 that the alarm / trip will occur prior.to exceeding' i .the limits of 10 CFR Part.20. The OPERABILITY andLuse of this instrumentation is consistent 2 with the requirements of General Design Criteria 60, 63,.and 64 of Appendix A to 10 CFR Part 50. , -i h1 i P r i , l . ! i l l-i' h 4 h I I i AP. o. .i - :3' , i. -124-s- ; 5 g[djy : . APA-ZZ-01003 Rev. O TABLE 9.1-A ( 2ADl0 ACTIVE LIQUID EFFLUEMT EDlIITORING INSTRUMENTATIost MINIMUM CHAM 80ELS OPERABLE ACTIOlt IllSTRtMENT 1 Radioactivlty Monltors Providing Alam and Automatic Temination of" Release .. 3T
- OPERABLE by the performanceoof the CHANNEL CHECK,
Turbine Building Drain Monitor (LE-RE-59) T 32 c. Secondary Liquid Waste System Monitor-(HF-RE-45) 1 33
- a. Litfuld Redwaste Discharge Monitor (H6-RE-16) 1 Steam Generator Blowdown Discharge Monitor (BM-RE-52) ' T 32
- b. ..
b. 1 3%
- d. R Flow Rate Measurement Devices 2.
- s. Liquid Radweste Discharge Line 34
- 1) Waste Monitor Tank A Discharge Line T 34
- 2) Weste Monitor Tank 8 Discharge Line 1 Steam Generator Blowdown Discharge Line 1 3%
-125- .-m APA-ZZ-01003 l
- c. Secondary Liquid Weste System Discharge Line Combined Cooling Tower Blowdown and Bypass Flow 1 34 d.
R;v. 0 - Y m , ! I.i N I h0)q , Table 9.1-A (Continued) ! W ACTION STATEMENTS r, ! i k"yu n ACTION 31 - With the number of channels OPERABLE less than I t required by the Minimum Channels OPERABLE l ! requirement, effluent releases via this pathway e , may continue'for up to 14 days provided that prior to initiating a release: ' $: a. At least two independent skmples are analyzed ; in accordance with Section 9.3.2.1, and i t
- 9. (.
; "- i ACTION 32 - With the number of channels OPERABLE Less than required by the Minimum Channels OPERABLE ! y requirement,. effluent releases via'this pathway , may continue for up to 30 days provided grab & samples are analyzed for principal gamma emitters , iT and I-131 at a lower limit of detection as p ' specified in Table 9.3-A .o : e
- b. At least two technically qualified members of f i1 the facility staff independently verify the i if release rate calculations and discharge line valving. '
- 6 otherwise, suspend release of radioactive 4 effluents via this pathway. .
j'e activity of the secondary coolant is. greater than 0.01 microcurie / gram DOSE EQUIVALENT
- a. At least once per 12 hours when the specific.
.I-131, or 1 , b. At least once per 24 hours when tha specific ! 1 activity of the secondary coolarc is less than , or equal to 0.01 microcurie / gram DOSE r EQUIVALENT I-131. h ' a .r P ) + .. '4 , 9:m ' G. '/{y: b i F' -126-y .. r s_ [3, ' !+ t u APA-ZZ-01003 L@g; y Rov. O J 6 l ' 4 Tsble 9.1-A (Continued) .c ACTION STATEMENTS ? - p Il $ ACTION 33 - With the number of channcis OPERABLE Less than - L.f.c < ' ' required by the' Minimum Channels. OPERABLE ; requirement, effluent releases via this pathway ,f , may continue for uplto 30 days provided that f prior to initiating a release: .n a. At least two independent. samples are analyzed ]p in accordance with Section 9.3.2.1, and ib b. At least two technically qualified members of d the facility staff 1 independently verify the release rate calculations and discharge line . valving. Otherwise, suspend-release of radioactive ).3 , effluents via this pathway. ACTION 34 - With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, effluent releases via this pathway
- i
; generated in place may be used to estimate flow. s m n E % M f a = .. ] N. .s;. _ -127-e $ _- f- .% a.e aw . ,: .3, . _ ~ ------ - -- -w . .,. % - . - m.. m7- -, ,,. . .~ .s a
- _' may continue for up to 30 days provided the flow rate is estimated at'least oace per 4 hours during actual releases. Pump performance curves
, i' r ' ; L. > 9.2.3 Bases 41844 9.2.3.1' Radioactive Gaseous Effluent Monitoring Instrumentation O 1 The radioactive gaseous effluent instrumentation' is-provided to monitor and control, as j . applicable, the releases of radioactive :, e ' materials in gaseous effluents during actual.or. , potential releases of gaseous effluents. The. of c ' Alarm / Trip Setpoints for these. instruments shall. l be calculated and adjusted in accordance with the methodology and parameters in the ODCM.to , o ensure that the alarn/ trip will-occur prior to exceeding the limits of 10 CFR Part 20. The ] OPERABILITY and use of this instrumentation is -< consistent with the requirements of-General j' Design Criteria 60, 63, and 64 of Appendix-A to 10 CFR Part'50. The sensitivity of any noble 4 gas. activity ~ monitor used to show compliance' f - with the gaseous effluent release requirements j i -of Section 9.7.1.1 shall be such that ! concentrations as low as 1 x 10 8 pCi/cc are 4 measurable. 1 k i 9. 3 -k i l l ? i P G l f- , s / t f %\'j/ + 131-o l i 'k , p Og- ' APA-ZZ-01003~ Rev. O TABtf 9.2-A RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTROMEMTATION . min 1 HUM CllANNELS APPLICABILITY. ACT1016 UPL f(AltLE B STRUMENT
- h. - ,- o R;v. 0
- 1. Unit Vent System 1
- 40
Providing Alarm (CT-RE-21) i
- a. . Noble Gas Activity Monitor -
- 43
* .43
- b. todine Sampler 1
-* 45'
- c. Particulate Sampler 1
- d. Flow Rate
- 39
- e. Sampler Flow Rate Monitor 1
- 2. Containment Purge System
- a. Noble Gas Activity Monitor' - Providing Alarm and Automatic Termination or ftelease 2
- 41 (CT-RE-22, CT-RE-33) 1
- 43
- b. todine Sampler 1
- 43
- c. Particulate Sampler N.A.
- 45
- d. Flow Rate I
- 39
- e. Sampler Flow Rate Monitor
- 3. Radweste Building Vent System 1
- 38, 40
- a. Noble Gas Activity Monitor Providing Alarm and Automation Termination of' Release (Gil-RE-101 1
- 43
*- 43
- b. todine Sampler i
- c. Particulate Sampler N.A.
- 45
- d. Flow Rate I
- 39
-132- ^ L.a. 4 g![ ' APA-ZZ-01003 @g Rtv O l i k "N , w w x I is? - i OV E' . i' h is . TABLE 9.2-A (Continued) i TABLE NOTATIONS At all times. ' ? ACTION STATEMENTS F i m ; fi ACTION 38 - With the number of channels OPERABLE less than i ? - required by the Minimum Channels OPERABLE ~ 9 requirement, the contents of the tank (s) may be 3.' released to the environment-for up to 14 days , en providea that prior to initiating the release: ; a. At least two independent samples of the tank's , contents are analyzed, and ' 3
- e. Sampler Flow Rate Monitor
the, facility staff independently. verify the relense rate calculations and discharge valve lineup. Otherwise, suspend release of radioactive effluents via this pathway. i ACTION 39 - With: the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway , may continue provided the flow rate-is estimated based on fan status and operating curves or
- b. At least two technically qualified members of ,
! ACTION 40 - With the number of channels OPERABLE less than l required by the Minimum Channels OPERABLE t requirement, effluent releases via this pathway ; l may continue for up to 30 days provided grab l1 samples are taken at least once per 12 hours and , L these samples.are analyzed for radioactivity within 24 hours. ! ACTION 41 - With'the' number-of channels OPERABLE less than required by the Minimum Channels OPERABLE E requirement, immediately suspend PURGING of L radioactive effluents via this pathway. p \. jfk' w , -133-
- actual measurements at least once per 4 hours.
, ., v, . . . . I APA-ZZ-01003 ' R;v. 0 - '( a , i i TABLE 9.2-A (Continued) i TABLE NOTATIONS i ACTION 43 - With the number of channels OPERABLE less than ; ( required by the Minimum Channels OPERABLE requirement, effluent releases via the affected ' pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling. equipment as requir.ed in Table 9.6-A. ; ACTION 45 - Flow rate for this system shall be based on far' status ' and operating curves or actual , L measurements. ! k + 0 E k b b 5 d%:% t : . .O MO' -134- 'A . =..~--.~.ew ~., .m7 vgy - ;=7- -.: -- - - 7 ~ - ~= 3 q p ;3 - n 7_ m--n+K. fi , l '" *W_ l . ~yy . 7 3.= ^ 3 ' y. y x- _ ;.-- E=R2, L~ j ;g 3 f;'. - . 3: j' . - 2g } L = ' T-[ 1- ^ ~ ' ^ ~ .
- 9. L
lT' ~ ~ L . ,; , ^' ~" ^ T_'r,T' ; , ; .:- s.' 'l ,.,
- .~- ~ "_. q=e -;
n * ' h ...,e '.'q -; f? - APA-ZZ-01003 Rev. O TABLE 9.2-8 RADIDACTIVE CASEOUS EFFLUENT M ITORING INSTRUMENTATION SURVEft_ LANCE REQUIREMENTS ANAt0C *QtANftE t_ MODES FOR WHiQt. GIANffEL SOURCE- QlAINtEL OPERATloftAL SURVEftt.ANCE' f C11ECE CIIECK cat _l8 RAT t088 1EST IS REQUIRED INST RUMLI(T
- M'l:: : ,.
Providing Afstw (GT-RE-21)
- 1. Unit Vent System
- a. Noble Gas Activity Monitor D M R(3) Q(2).
M.A. *
- b. todine Sampler W N.A. M.A. N.A.
~
- c. Particulate Sampler W M.A. M.A.
- d. Flow Rate. M.A.: M.A. R(4) Q R .Q *
- e. Sampler Flow Rate Monitor D N.A.
- 2. Containment Purge System
Providing Alarm and Automatic
- m. Noble Gas Activity Monitor ~
(GT-RC-22. GT-RE-33) _ _ W N.A. M.A. M.A. -*
- Termination or Release D P R(3) Q(f)
M.A. *
- b. Iodine Sampter -
N.A. *
- c. Particulate Sampler W- N.A. N.A.
- d. Flow Rate M.A. N.A. R(4) M.A.
Providing Afarm and Automatic Termination or Release (Of-RE-10)
- e. Sampler Flow Rate Monitor D N.A. R
- 3. Radweste Building Vent System
- a. Moble' Cas Activity Moni tor - D, P M, P R(3) Q(1) ~
M.A. *
- b. Iodine Sampler W N.A. M.A. N.A.
N.A.
- c. Particulate Sampler W N.A. N.A.
- d. Flow Rate M.A. M.A. R(4) N.A. l 1
-135-4 .A- . APA-ZZ-01003 p -- Rov. O i - 4 1 TABLE 9.2-B (Continued) I TABLE NOTATIONS 41845
- Sampler Flow Rate Monitor D N.A. .R e.
(1) 'The-ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions-exists:
- At all times.
' Alarm / Trip Setpoint (isolation and alarm), or
- a. Instrument indicates measured levels above the
;: (alarm only). (2), The ANALOG CHANNEL OPERATIONAL IIST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions. exists: '
- b. Circuit failure (alarm only), or
- c. Instrument indicates a downscale failure (alarm only), or
- d. Instrument controls not set in operate mode
-Alarm Setpoint, or ,
- a. Instrument indicates measured levels above the :-
l 9 s 1 4 s,q<g~.; ,< -136- , w. o ; $i " 4 APA-ZZ-OlOO3 iN:, Rev. 0 w n TABLE 9.2-B (Continued) o- TABLE NOTATIONS (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas
- b. Circuit failure, or
- c. Instrument indicates a downscale failure, or
- d. Instrument controls not rat in operate mode.
, standkrds that have been obtained from suppliers that participate in measuremr-t assurance activities with NBS. These standards shall' ; permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATION. NBS traceable standard (gas, liquid, or solid) may be used; or j a gas, liquid, or solid source that has been y calibrated by relating it to equipment that was Q previously (within 30 days) by the same geometry and type of source traceable to NBS. (4) If flow rate is determined by exhaust fan status and fan performance curves, the following surveillance operations shall be performed at least once per 18 months: ,
- i or liquid and solid) standarc.s certified by the National Bureau of Standards (NBS) or using
" flow-AP" curve, or
- a. The specific vent flows by direct measurement, or
- b. The differential pressure across the exhaust fan and vent flow established by the fan's
" flow-horsepower" curve. a m 6 ?w ]M Yp' 137-e L. __%gm * , l:$ APA-ZZ-01003 Rev. 0 2881 9.3 LIQUID EFFLUENTS CO N 'NTRATION 41846 9.3.1 Controls 4160 9.3.1.1 The concentration 'f 20ctive material released in liquid v' ..nte to UNRESTRICTED AREAS (see Technical Specif. cation's Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10- ' microcurie /ml total activity. APPLICABILITY: At all times. ACTION:
- c. The fan motor horsepower mea ured and vent flow established by the fan's
41847 9.3.2 Surveillance Recuirements 2895 9. 3 . 2 .1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 9.3-A. 9.3.2.2 The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained witi.in the limits of Section 9.3.1.1. *-t S. -138-t 9% g' "g APA-ZZ-01003 Rev. O g; 3e 9.3.3 Bases 9.3.3.1 This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.h design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. 9.3.3.2 The required detection capabilities for radioactive materials in liquid waste samples are . tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-3OO (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques", Atlantic Richfield 11anford Company Report ARH-SA-215 (June 1975). , O:P k*s -139-L.
- a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
- b. The provisions of Sections 9.0.3 and 9.O.4 are not applicable.
gf .[q mQ APA-ZZ-01003; { *gfl '3;l} p gfl .ge - TA9LE 9.3-A- ~ Rev.; O' f[l , f 7.Y;i g jili i ' =RADI0 ACTIVE LIQUID WASTE SAMPLING'AND ANALYSIS PROGRAM-g i My m, QlT , ,. ; .l l l l_ l= LOWER LIMIT l af f , ". :l. , l .~ l MINIMUM -l l OF DETECTION-l t , .
- . .@/- m .
"'i ' T L1 ... l l l; I -l [ ', L ,. l 1.' Batch Waste l1 P l P l l l n .y C O'u' l: Release- ' leach Batch lEach Batch l' Principal-Gamma l 5x10 :l' l- Tanks ( ) l 'l l Emitters ( )' l l p +, '
- - Ll LIQUID RELEASE l_ SAMPLING l ANALYSIS- 'lTYPE OF ACTIVITY l (LLD)(1) j 4 (( ' q, l TYPE I FREQUENCY l l'REQUENCY l' ANALYSIS- l (uCi/ml) l lm
l l l: m.t . . 3 Monitor l l l l . l -5 l' Tank 'l l P l. M lDiasolved and 1x10 am l lOne - Batch /t!l lEntreined Gases l l .a '~' 'l- l l- l(Gamma Emitter.) l l l' b. Secondary l 1 l l l ,_ .l~ '. Liquid .l l l l l Waste -5 [ 1 :l -l .P l M l H-3 -l 1x10 1 % l- Monitor lEach Batch l Composite )l l l L- . l Tank l l Gross Alpha- l 1x10' ' l- [ "'D -
- l. l l l l . -l bO4', (( -6 l l l I-131 l- 1x10 -l c e l- a. Waste -l 1 _
. ~ 1;- P l Q lSr-89, Sr-90 l- 5x10 g i Monitor leach Batch l Composite (')l: Fe-55' -6 -l . l 1x10 l .y y j Tank I l l l l. t - T ._j- -j l l l .l [, Y, l-2. Continuous l- l W lPrincipal Gamma l 3x10'7 l , y, -l. : Releases (5) l Daily (6) lCorspositeb)l Emitters (3) l l V . l l Grab _ Sample l l 1 l -6 h ,t 1l' l- l l I-131 l 1x10 -l - S_ team l l ~ l' l l ^ ' ' 'i l Generator l l l l l Blowdown -5 s, lL l M l M l Dissolved and i 1x10 g s _l- _ l Grab Samplel l Entrained Gases l ~l h .i l l l(Gamma Emitters) l ll %4 i ,, - 4 l- [ l I l l ' -5 I _p l l l M .l H-3 l 1x10 l_ E :p X (l l Daily (6) l Composite (')l- l l + h , lL l Grab Samplel l Gross Alpha l 1x10" l {@> ~ l l l l lSr-89, Sr-90 I ~0 l l l l Q l 3x10 l j;(.g -l l Daily (6) Composite (')l l l ' -6
- l l 1 I l
- c. Discharge l -8. d'
{ -140-4 .Y. hhg , ,' C 4 ApA.ZZ-01003 -Rev.:0
- l. l Grab Sample l lFe-55 l 1x10 g l l l I l l c
'fc q - , ? Wim ; j . . "M. - ' . TABLE 9.3-A (Continued): g-;fy,p; - q. n d . c .- .y ],
- )$,]fy
~ _The LLD;is defined, for purposes of these .g4lT f. . controls; as the smallest concentration of-
- TABLE NOTATIONS M , ip (1)
_g .a. net count, above system background, that will if -be detected with 95% probability with only 5%- probability,.of falsely. concluding that a blank-P_ . observation represents a "real" signal.- A -- For a particular measurement system, which may1 J. - -include 1 radiochemical.separationi '4.66 s ' , -LLD'= b 5 Ea V
- radioactive material in a sample that:Will' yield'
Where: -! l. LLDT= the "a priori" lower limit of detection .(microcuries per unit mass of. volume), .s b =:the.. standard deviation.of..the. background . , _ counting rate or of the counting rate of.'a 1 ., ' blank; sample as appropriate (counts per ' q minute), : E m the counting efficiency (counts per I _l l 'V
- 2. 22 x 10'
- Y
- exp .- (- Aat)
V;=6theisample, size (units of mass.or volume), "i I k 2.22 x n108 = the number of-disintegrations per- , minute per, microcurie, _se Y = the fractional radiochemical-yieldL when , applicable, ] q A = the radioactive decay constant for.the -i __ particular radionuclide (s 2), and ,At m..thecelapsed time between the> midpoint of- ; sample collection and the: time of counting- j -(s). 3 4' Typical values of E, V, i, and At should be 1 2s s , used.in the calculation. q T '. ; . j . ,1'l'f + ( 4 N.iM h -141- , =- L-i r. c .; ., . p . k' APA-ZZ-01003 Rev. O ma A i s TABLE 9.3-A (Continued) s TABLE NOTATIONS
- disintegration), !
(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to aampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. ~ (3) The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, . 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides 3 are to be considered. Other gamma peaks that are identifiable, together with those of the above r.uclides, shall also be anal:lned and reported in the Seminannual Radioactive Effluent Release Report pursuant to Technical . Specification 6.9 1.7, in the format outlined in Regulatory Guide 2.21, Appendix B, Revision 1, June 1974. (4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for _ the composite samples to be representative of the effluent release. (5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow dur.ag the continuous release. i I d -142- .y n p ' > cv < /' APA-ZZ-01003 W;. ;+ i Rev.; 0. U .. . . 4 .P! :Jl [? g p. - t 9u - 4 ..,i. TABLE 9.3-Al(Continued) i -b s TABLE NOTATIONS i . 4 -.M _(6)' Samples shall be taken at the, initiation-of - 1 effluent- flow and attleast once per 24 hours i iDF t "- ' thereafter:- while : the release is occurring. To be representative,of the liquid-effluent, the sample- ?@c;u volumetshall be proportioned To:the effluent- -!i' stream. discharge volume.. The retio of sample , U volume to effluent' discharge volume shall be . maintained constant for all samples takenlfor the composite. sample.- f:; _- [11 f-, ' b. , ,{- o .f -- ). '; ) .p I? -i. ) .. a _\ s Wp s -h'- e '.0, _* .h .l. '? t '1 i v.A ' _I; ; /;S ". 'f,'g - N h.[ i. s -143-i w . f U ;t7 WbD m c;Rp' s ' AJ I3 , . ; 3 APA-ZZ-01003_ h , %l % ' q[4 _ as Rcv. 0 ~ ,w ;g , o !"n '"'" s : 1 m. L 4%,M , ! y e . 4 l [4 g, 4 9.4 DOSE '; y n .. ~41849 .9.4.1 Controls u 4160: 9.4.1.1 The' dose or dose' commitment to a MEMBER OF THE-PUBLIC from radioactive materials in' liquid-effluents. released,' from each unit,-to 'I 1 . U m i UNRESTRICTED AREAS-(see, Technical Specification's y* Figure'5.1-4) shall-be limited: ] e -
- 41848 It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
equal'to_l.5 mremseto the whole body and to i T < _less than or equal to=5 mrems to any organ,< ,; and h, _b. During any calendar year to less;than or equal. [> gy to 3 mrems to the whole body and_to lessithan H-, 1 f ' or equal to 10 mrems to any organ. ,h APPLICABILITY: At all times. 3 C' ,} 4 ACTI ON': A- , , g- a. With the calculated dose from the. release of' , M radioactive materials in liqpid-effluents- . ' exceeding any of the above-limits, preparet and' submit tosthe Commission within 30. days,- 1 pursuant to; Technical Specification 6.9.2, a; #- ', Special Report- that nidentifies the cau- ) ; me for exceeding the. limit (s) and defines <the- . ut : corrective; actions that.have been.taken-to .! y JIR reduce the releases and the proposed-- J' U ; m ' corrective actions-to be taken to. assure-that j k it subsequent releases'will be in compliance with7 ob the'above limits. This Special Report _shall i k also include: (1) the results of radiological 1 's Y analyses of<the drinking water source, and 9,' , (2) the radiological impact on finished a m drinking water supplies with regard to-the requirements-of 40 CFR Part 141, Clean > Drinking-Water Act.* 4 1 ,MUt '
- a. During any calendar' quarter to less than or O
f Ag,. ,W:g ;s: 11 i 2 ei J h.a *The requirements of ACTION a.(1) and (2) are applicable only if g15 %v? drinking water supply is taken from the receiv3pg water body within ' WUff 3Lmiles of the plant discharge. In the case et river-sited plants , gh this~is 3 miles downstream only. 'c y .; -144-u i, l, 3.) 'Tk' MS i tn .a!, >J. 4 y%, y\ Wu' !alo n
- b. The provisions of Sections.9,0.3 and-9.0.4 are not applicable.
E4 APA-ZZ-01003 Rev. 0 9.4.2 Surveillance Requirements 9.4.2.1 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. 41850 9.4.3 Bases 9.4'.3.1 This section is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinxing water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I which specify that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for thc Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977. -145-L. ^ MgdMSY'd . , h" a i Tj , APA-ZZ-01003' ., R$v( OL @f M3CN{u@f hW 7 ,$7plp l y d 4 M g,r > 9.5: LIQUID RADWASTE TREATMENT +SYSTEMi y" h,b 1 , [j 3 g ; 41851 9 . 5 '.1_ Controls ' gx: n '4160 9 . 5 .1'.1 The :: Liquid : Radwastie- Treatment) System shall bA ' - p$V( OPERABLE and appropriate < portions of the system { p shall be used to reduce releases of radioactivity e{d C* when the projected doses due=to the liquid- .s. effluent, from each unit,.to UNRESTRICTED AREAS = f;
- m. . __ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -- t
p > -
- %}h[
ap 0.2.mram to any organ =in,..a 31 day.' period .; [ IQW APPLICABILITY: At.all times. < t k -ACTION: yD g ' I
- (see Technical Specification's Figure 5.1-4) would exceed 0.06; mrem to the whole body.or:
k -limits andiany portion of.the Liquid Radwaste ; b Treatment System not in operation-, prepare t.nd- a $ -submit to the Commission within 30' days, &q pursuant to Technical Specification'6.9.2,'a-: go_ Special Report that-includes the following. 4 dF .information: c ' Q' 3 Q! l'. Explanation of why linuid radwaste was 1%, 7 being discharged without treai.ecnt, . . 4i identification of any inoperable equipment. {p$ g p '"g or subsystems,-and theLreason.for,.the. p (, inoperabilityp 'f5 ., & y\ 2.' Action (s) taken to~ restore the--inoperable a J7S equipment to. OPERABLE status, and-W pp 3.-Summary description of action (s) takenito $gi , prevent-a recurrence. m Ll b. The. provisions of Sections 9.O.3,and 9.O.4 are @? g$: - not applicable. g,' $V 41852- 9.5.2 Surveillance Recuirements 5 9.5.2.1 Doses due to liquid releases from each unit to @M} ; f , UNRESTRICTED AREAS shall be projected at-least 4;p once per 31' days inLaccordance with the methodology and parameters in the CDCM when .' pghg _ Liquid Radwaste Treatment 1 Systems-are not being &L fully utilized. @ 'Q:.%._ ,. . p- 9 ;g' ; M fig , -146- - h, ( \tp f g!b h n _ . -- , C;p I APA-ZZ-01003 h Rev. O k
- a. With radioactive liquid waste being' discharged C without treatment.and in excess of.the above -
[ Sections 9.3.1.1 and 9.4.1.1. . -i 9.5.3 Bases ! 9.5.3.1 The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. . The requirement that the appropriate portions of a this system be used when specified provides assurance that the releases of radioactive i materials in liquid effluents will be kept "as low as is reasonabley echievable". This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design j objective given in Section II.D of Appendix I to -j 10 CFR Part 50. The specified limits governing ;! the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section 11.A of Appendix 1, , 10 CFR Part 50, for liquid effluents. R k M ?, e + -'I 9 $ g i _m j -147-L. ~ u-- y$' is APA-ZZ-01003 !yOMW , Rev. O mg. 5Nd, nv ' ' y;p)A ?j 9.6 GASEOUS EFFLUENTS DOSE RATE h,d% E a m, s. 41853 9.6.1 Controls %l Nif , :4160 9.6.1.1 The dose rate:due to radioactive materials .M creleased in gaseou.3 effluents from the site to Yif- , areas et-and beyond the SITE BOUNDARY (see m' -Technical Specification's; Figure.5.1-3) shall be 3W." s limited to the following~: }i , ;)]
- f. _t 9.5.2.2 The installed Liquid Radwaste Treatment System i shall be considered OPERABLE by meeting
- u:t j b. For' Iodine-131 and133, for tritium, and for j{$p ' all radionuclides-in particulate form with M half-livesLgreater than 8 days: LessEthan or y equal to 1500 nrems/yr to any organ. _(> APPLICABILITY: At all times,
- a. For noble-gases: -Less than;or equal"to ht 500 mrems/yr to the:whole,' body and less than-IM L', or equal to 3OOOl.mrems/yr tolthe skin, and'
a.,With the dose rate (s) exceeding the above , limits, immediately restore the release' rate .to within.the'above limit (s). ~ L. The provisions'of Sections 9.O.3 and 9.0.4 are r.s t applicable. '41854 9.6.2 -Surveillance Recuirements a -9.6.2.1 1 The dose rate due to noble gases in gaseous. effluents shall be determined.to be within the above limits!in accordance.with theemethodology and parameters in the ODCM. i :9.6.2.2 - The dose: rate due to Iodine-131 and 133, tritium, and-all-radionuclides.inl particulate. form ^with = half-lives greater than 8. days-in gaseous affluents shall-be determined-to be withincthe . above limits in accordance with the methodology and parameters in.the CDCM.by obtaining ' representative samples and performing analyses in. "accordance~with the sampling and analysis program specified in Table 9.6-A. t ! e;,;p - m -148- . }[ 3p ' 1,[ , . g '( b 3 4 ^ ~y ~ ' APA-ZZ-01003. c? l', Rov. O' A.P+ m es ' , s . b u.m jN , 4 i ~- ( ? l;i d , 'l ' 9.6.3! Bases i -- . . - 1 . . n? L41855 L9.6i3.'1 This;section is provided to ensure that the dose-a n# uat any! time at and'beyond'the SITE BOUNDARY from (ig ' ' ;b l gaseous ~ effluents from all units on the site willL "g o.' ' 'be within the' annual dose limits of- o hw " ' 10 CFR Part 20 to UNRESTRICTED AREAS. The: annua 1J s l dose limits are -the ' doses; associated with the h concentrations of 10 CFR-Part 20, Appendix'B, . Tab 1ccII, Column 1. These. limits provide _ -rcasonable assurance that radioactive material ! discharged in= gaseous effluents will1not' result. 3 i ? in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA ~, either within or outside-the- 'q , 14 SITE BOUNDARY, to-annual average concentrations j exceeding the limits specified in Appendix'B,; Table II of 10-CFR Part 20 (10 CFR 20.106(b)). , For MEMBERS OF THE PUBLIC who may at timesL be j 4* within the-SITE BOUNDARY, the.occupancyxof that o MEMBER >OF THE'PUBLIC will usually be'sufficientlyf low'to compensate,for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for?such-5 g , MEMBERS OF THE PUBLIC, with the appropriate , occupancy factors, shallibe given in the ODCM, V 1 The specified release rate limits ^ restrict,- at 4 m" all times, the> corresponding gamma and betacdose g rates above background'to a MEMBER OF THE~PUBLIC w y .at-or beyond SITE BOUNDARY!to less'than--or equal to 500 mrems/ year to theLwhole body or toiless than or equal:to 3000 mrems/ year to-the skin. : .These releaserrate' limits also restrict, atrall times, the corresponding-thyroid dose rate above i background to a child via thecinhalation1 pathway ; to less than or equal to:1500 mrems/ year. [' 9'.6.3.2- .The required detection capabilities.for radioactive materials ~in gaseous waste samples-i are tabulated in terms:of the lower limits of-detection (LLDs). Detailed discussion of the a LLD, and other-detection limits'can be found in . HASL Procedures' Manual, HASL-300 (revised 9( annually), Currie, L. A., " Limits for Qualitative-ym Detection and Quantitative Determination-- ' mf ' Application to Radiochemistry"', Anal. Chem. 40, 3 586-93-(1968), and Hartwell, J. K., " Detection . Limits for Radioanalytical Counting Techniques", Atlantic Richfield Hanford Company Report ' pq ARH-SA-215 (June 1975). . ,e y k' 7, , -149-r , w mammass- . - ~~ -- ' +- ~ ~ ~ ~ = ' *^ " ~~~ * " ' " *: - * * * ? ,., - - . - c - - i l APA-ZZ-01D03 Rev. O TABLE 9.6-A !LADIOACilVE GASIDOS WASTE SAMPL!!!G_AJD ANALYSIS PROGRAM i 1 IMi51 MUM i i IOWER I.lMil 0F I l l SAMPLING IANALYSIS I TYPE OF l DEIECilON (LlD) (8)l l CAST 0uS RtttASE IYPE FRLQUENCY lTREQUENCY 1ACityliY ANALYSIS l (PCifall I P l P l (2) 1 - 8s l l Irrincipal Gamma Emitters 1xto i
- t. ACTION:
I or Vent l Sa ng i g__ l__M -4 (2) I I ( 3 ),14 ) I (3) I 1
- 11. Waste Cas Decay i Iach Tank l Each Tank l l Tank l Grab Sample l l l 1 i P I P l l l I -4 I I (3) 1 (3) I (2) 1 1
- 12. Containment Purge llach PilRGE ffach PURCE Princip_a1 Gamma [mitlers i lxlO I ICrab l -6 I I (3) l H-)_Loxidej i lxte !
~ I (5) l l (2) -4 l
- 13. Unit Vent lH l M Camma Emitters tx10 l l l Grab Sample I (4) l' F rinc ipa l -6 l
- j. I M l18-3 (oxidej 1x10 1
[xhaust IGrab Sample I (5) 1 -6 l l l l l M lit-3 (oxide) l 1x1Q l (2) I I : i 1 -4 l
- 14. Spent fuel Building i M i M jPrincipal Gamma Emilters 1x1Q_ l
i IContinuous 1 W l Principal Gamma feltters i 1x10 I I IParticulate i i l I i Isample i i i i I (6) (8) I M I i -11 i e IContinuous IComposite ICross Alpha l lx10 l trarticulate i I I 1 I l Sample 1 I I l (6) (8) I Q l 1 -11 I 1 I IComposite ISr-89, Sr-90 1x10 l I IContinuous 1 I I l l l Particulate i f j ISamole I _1 1 -150: Q.S MJE , W ; W .p.+ i ' ' ..[ W.: y; +AP!m '4 Wu , < APA-ZZ-01003- 3 i up ( g ' ;w ; ' R;v. O- ;} 5 dh ' g+fly E w, et ; ,4, J, ' ..~. TABLE'9.6-A-(Continued). J/ ,, R. , g- ., y 1 s p ib. ', .s , , q , 'Y g > ,, TABLE NOTATIONS (Continued) -j e. a 'y oY E - (1)s The LLD is definedk for purposes of these j +' + s' -controls,.as the smallest concentration of y
- 15. Radwaste Building l M i IPrincipal Gamma Emitters ! Ex10 l l___yent l Grab Sr.pple l M i I i i I (6) (8) 1 (7) I i -12 1
- 16. All Release Types IContinuous l W ll-131 l 1x10 I as listed in I., i lCha rcoa l l l -10 I l ix10 l I 2.. 3., 88 . . and I. ISamate 11-111_ l (1) (2) 1 -11 I l 5. above 1 (6) (8) l 1 l
&4 gn '
- g. ,j , radioactive material in a sample'that:will' yield' '
W.g * > probability of. falsely; concluding that:a' blank. %.y i : observation represents a'"real" signal. l . ,.a (g F For a particular measurement system,~ which:may ,7 j i include radiochemical separation: j{ .66 s 4 H! LLDE= b f.[ a.y.p E
- a. net count, above system background, that will; R l -be detected with 95% probability with only 5% '
;f ,?A a Where gn ;w j, ,1 , q, uM # %',' ~ LLD = the "a priori"' lower' limit of detection- ' M 4 o -( (microcuries per: unit massLof-. volume),. j, 7+ ,a 'j ' sb = the standard deviation of the background
- V
- 2.22 x'1081* Y
- exp ' (-Mt) y
j minute), , w , ~ h
- mL counting rate or of'the Jcounting rate of a- , li p "J y" ' r blank sample as appropriate:(counts per- w [
q, a. j , e V = the7 sample size-.(units.ofimass or volume), ,.4 t. d ;^ 2.22 x'1081= the number of disintegrations per! j~ 1 y s ' minute pertmicrocurie, .- y . r X Y = the fractional radiochemical yield, when . applicable, j .s. -s .
- E 4 =:the counting. efficiency'(counts per ,d 9 , ' disintegration), , ,.j p ,
,, particular radionuclide-(s 2), and k If i y H. At = the elapsed time between the midpointLof l g'; L < m sample collection _and the time of counting (s). , y, ,, ,
- X = the radioactive decay _ constant _for the
n used in the calculation. ;' %[ d .i 5! & ;ul' % Th ' 4 J l ji 1 -151-l ,
- c+' < L ; Typical val m of E, V,- Y, and At should be ;[
, i ~ ! i . 1 1,
- u :n
c u b ,* s .,( ff [f[; , , IAPA-ZZ201003" d' Rev . = 0 :- P x , Y TABLE 9;6-A (Continued)' ' ', " m -j;tw;y ' ? I TABLE' NOTATIONS (Continued)- t* 3 , ~ 41857 i' ' It;should be. recognized-that.the LLD-is' defined J" as a-a priori (before the fact) limit -representing the capability of a' measurement-system and not as an a posteriori-(after the-p ;g fact) limit'for;a particular measurement. - [_ - ( 2 )r : 'The principal. gamma emitters-for,which:the--LLD .
- _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ , - ______.___.m.________;
Xe-135,'and Xe-138 in noble gas-releases and' Mn-54,-Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131,' Cs-134,-Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not.maan; 1. that only.these nuclidesiare to be considered. Other gamma peaks that are identifiable,~ together: EJ . withEthose'ofs the above nuclides,.shall-also'be:. . analyzed and reportedLin-the Semiannual +*- . Radioactive Effluent Release Report pursuantito' ~ Section 7.2, in the format outlined in Regulatoryl ' Guide 1.21, Appendix B, Revision'1, June 1974. (3) Sampling =and analysis shall also,be! performed I! following shutdown, startup, or a THERMALLPOWER change exceeding 15% of RATED-THERMAL POWER; within i hour period. (4). 1 Tritium: grab: samples shallibe.taken.and analyzed at least once per 24 hours when_ the refueling' . canal is flooded. (5). Tritium- grab samples shall be taken and analyzedi at least once per 7 days _from the ventilation exhaust.from the spent fuel pool area,: whenever spent fuel is in the spent fuel-pool. Grabu . samples;need to be taken only when spent: fuel ~1s in.the spent' fuel pool. (6) The-ratio of the sample flow rate to:the samplodi streamiflow rate shall be known for the time' period covered by each dose or dose' rate. calculation made in accordance with Sections 9.6.1.1, 9.7.1.1, and 9.8.1.1. ,iM . .(jhY -152- l l t [' , ', 1 + LAPA-ZZ-01003 ' Rov. 0 p~ . ,w l l . aTABLE 9.6-A (Continued) 1: .s L' 3: TABLE NOTATIONS (Continued) i-(7) :Samplestehall be changed at least once'per 7 days e< and; analyses. shall be completed within 48 hours: ;t . after changing, or'after removal from-sampler, c , For'unitLvent, sampling shall also be performed at leastfonce per 24 hours for.at least 7 dayw followingJeach shutdown, STARTUP or THERMAL POWER. t
- r uspecification applies; include.the following - i radionuclides:, Kr-87, Kr-88,'Xe-133,.Xe-133m,- ,
;~ completed within 48 hours of. changing. When samples-collacted for 24 hours-are analyzed, .the ' corresponding;LLDs may be increased by a. factor of 10..This. requirement does not apply:if: .(1) analysis shows that the DOSE EQUIVALENT'I-131 concentration;in the1 reactor coolant has not increased more thanca factor of 3, and (2) the , : noble; gas monitor:shows that effluent' activity I '- has.not increased more than a factor of 3. (8) ~Continuousisampling of the spent fuel building-exhaust needs'to be performed only;when: spent- ~ Lfuelt isLin;the spent fuel pool. i A L 1 L i t 4 ; Tube - 153- , X_ ws 3ln r P %. ' APA-ZZ-01003 ft Rov. 0 - %%;a,,' . , x. M@ W* y &v lK(h D . [ q; < ih. hiEP1 yR' 9.7' DOSE - NOBLE' GASES 9.7'.1- Controls p#f
- change: exceeding 15% of RATED THERMAL POWER withinLacl-hour period and analyses shall be
~ gaseous effluents, from each unit-, to areas at-Q@ f~ ' and beyond the SITE. BOUNDARY (see Technical- - W t' . , Specification's Figure,5.1-3) shall be limited to .the following [fyi% h ep a. During anyLcalendar. quarter: Less than'or - E,M k equal to'5:mrads for gamma radiation and less N ' -. . than.or equal <to 10 mrads fer beta radiation, 4 and (liq 4 (
- w. / 141858 jb i . 4160- -9.7.1.1- - .The. air dose due:to. noble gases-released in
@K< or equal to 20 mrads for beta radiation.- 1% r/M APPLICABILIH : At all times. , lg b b; . ACTION: ss
- b. During-any calendar years Less than or equal h.K % to 10 mrads for gamma radiation and less than
@&s ' noble gases in. gaseous effluetns exceeding-any. of the above limits, prepare and submit to the i Corrmission within 30 days,- pursuant to @h@jf Q 1 Technical- Specification 6.9.2, -a . Special % ' Report that identifies-the:cause(s) for y -exceeding the-limit (s) and defines the Uif , . corrective.~' actions that have been takenito- 'yF reduce the? releases and the proposed corrective' actions to be taken to' assure that subsequent releases will be;in compliance with the above limits..
- a. With the' calculated air dose from radioactive
41859- 9.7.2 Surveillance Recuirements 9.7.2.1 Cumulative dose, contributions :for the current N calendar quarter-and current calendar year for M',- noble gases shall.be determined in accordance with the' methodology and parameters in the ODCM j$u;b# ", at least once per 31 days. M Vq 4 i 1 3 4 , -154-I, i ,.iw--r. d p% E APA-ZZ-01003 L' ? Rev. O N ,l.f 2 < . 9.7.3 Bases _.o 9.7.3.1 This section is provided to implement the requirements of Sections II.3, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation implements the guides i, set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". j The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be
- b. The provisions of' Sections 9.0.3 and 9.0.4 are not applicable.
The dose calculation methodology and parameters established in the ODCM for calculating the doses . due to the actual release rates of radioactive - noble gases in gaseous effluents are consistent with the methodology provided in Regulatory > Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for i the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average '* atmospheric conditions. J d ~~ -- J' \ , ../ - -155- ~ . . . . . . . , . , , . , . , . . . . . . . , , . . . , . . . . . . . , . . y f'% N .APA-ZZ-01003 Qb Q::V ', Boy. OL h6 1:s , WiR ' # kl gig Pn RE , 9.8 DOSE --IODINE-131 AND-133, TRITIUM l AND' . // RADIOACTIVE MATERIAL IN PARTICULATE FORM s 41860, 0 -4. 1< Controls. jl 4160; 9.8.1.1 The dose-to a MEMBER OFLTHE PUBLIC from em . Iodine-131'and 133,, tritium,-and~all-radionuclides in particulate form with' half-lives greater:than_8 days in' gaseous effluents released, from each. unit, to' areas at and_beyond-the.SITELBOUNDARY (see. Technical Specification's-y Figure 5.1-3) shall be : limited' to the following:
- shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated, i
Less than-or equal to-7.5 mrems to any organ,- and h b. During any calendar year Less than or-equal to 15 mrems to any organ. I APPLICABILITY: At all times. L I ACTION: v V - a. With-the calculated dose from the release of Iodine-131 and 133, tritium, and-radionuclides.. in particulate form.with. half-livescgreater' s , daan 8 days, in gaseous 1 effluents exceeding ,, , any of the above limits,fpreparenand submit to [ the Commission within 30 days, pursuant to-ii Technical Specification 6.9.2,,a Special 4' .Reportcthat identifies.the cause(s)1for R -exceeding-the' limits and defines the k ' corrective- actions that have been taken- to reduce the releasen and the proposed corrective actions'to be taken to assure'that subsequent releases will be in compliance with the above limits, f b. The. provisions of Sections 9.0.3-and 9.0.4 are not applicable. [ 41861 9.8.2- Surveillance Recuirements 9.8.2.1 ' Cumulative dose contributions for the current .. calendar quarter and current calendar year for [ Iodine-131 and-133, tritium, and radionuclides in [, particulate form with half-lives greater than 8, days.shall be determined in-accordance with the c! . methodology and parameters in the ODCM at least
- a. During any_ calendar quarter:
idfR..s . a - [ D.7 -156-L. 1 c*, , , -= - ic o. o 4 o - .o a M< c Ri.ps+ ' '~ -APA-ZZ-OlOO3- ' f, .Rev 30' f1' +, l > .ii 8 + .' , f 918.3: Bases L; 9.8'3'.l. . ~ This section is provided'to implement'the ,, requirements of Sections ~II'.C, III.A, andLIViA of- .c Appendix I, 10 CFR;Part 50.- .The Limiting; . _ . p :- 1 -Conditions for Operation are the: guides set forth< .in'Section:II.C of Appendix-I. The ACTION L' statements. provide-the; required operating: 1 flexibility and at the'same time implement:the! guides setsforth in Section-IV.A=of. Appendix?Ilto ' na - assure that the: releases of radioactive materiali ' .in gaseous ~ effluents to, UNRESTRICTED 4 AREAS!willa , be-kept."as low as is' reasonably. achievable". 1The Surveillance Requirements implement.in-Section III. A of Appendix I that conformance witn ~the guides of Appendix I be'shown by . calculational procedures based on models andidata such that the actual exposure of a MEMBER.0FJTHE PUBLIC through appropriate: pathways is unlikely 1( L to be substantially underestimated. .Theidose' ' calculation methodology and. parameters-established in.the-ODCM for calculating:theLdoses-p due to the actual release rates of radioactive;, i . noble ga~ses in gaseous effluents'arefconsistent' with the methodology provided inLRegulatory . . Guide 1.109, " Calculation.of. Annual Dosesito Man? from Routine Releases of Reactor Effluents'for . the Purposenof= Evaluating Compliance 0with610 CFR' Part:50, Appendix'I", Revision 1,10ctoberJ1977' F and Regulatory Guide:1.111, " Methods for . o . Estimating Atmospheric TransportLand Dispersion = }; of-Gaseous Effluents.in Routine:ReleasesLfrom 1: Light-WaterfCooled Reactors",~ Revision 1,. July 1977. These equations also provide for. determining the actual doses based upon the; . historical average--atmospheric-conditions. .The - release rate controls for Iodine-131 andl133, tritium,-and radionuclides in particulate forml with half-lives greater than 8 days are dependent upon .the existing radionuclide; pathways to' o man, '~ in the areas at and beyond.the SITE BOUNDARY. . .The-pathways that.were, examined in the p development of'these calculations were: (1) individual inhalation of' airborne radionuclides, (2). deposition of radionuclides onto-green leafy i vegetatier. with subsequent consumption- by' man, 4 (3) desposition of radionuclides onto grassy if . areas where milk animals.and meat-producing [ animals graze with consumption of the milk and
- j. once per 31 days.
with subsequent exposure of man. r l -157- ,j- .u (, I + "- !APA-ZZ-01003' ~~ . Rov.'O { , We i; . - '6 9.9 GASEOUS RADWASTE TREATMENT SYSTEM 1 i 41862., 9.9,1 Controls 4160' 9;9.l'.1. ThelVENTILATION:, EXHAUST TREATMENT SYSTEM-and the' WASTE. GAS'HOLub'? SYSTEM'shall-be OPERABLE.and-appropriate portions of these systems shallibe used to reduce releases of radioactivity whenzthe. . : projected' doses in(31. days-due to gaseous effluent releases,-'from each unit, to areas at ,and beyond the SITE BOUNDARY (see Figure. Technical Specification's 5.1-3):wouldLexceed:-
- i. 1 meat by man, and (4) deposition on the ground-F i; -
b.10.4Lmrad to air from beta radiation, or-
- a. 0.2 mrad to air from gamma radiation, or'-
.PUBLIC. t > ' APPLICABILITY: At all times. JACTION: -a. With' radioactive gaseous. waste being -,- discharged without treatment and in. excess of. the abovei limits,. prepare and submit-to the Commission within 30: days, pursuant to Technical Specification 6.9.2, a Special' Report that: includes the following informations- .1. Identification offany inoperable equipment-or. subsystems, and the reason for the inoperability,
- c. 0.3 mrem to-any organ-of a MEMBER OF:THE
not applicable. ;kW kj/ -158-L 4 , 4' , APA-ZZ-01003 O { Rav. O p 9.9.2 Surveillance Requirements i 41863 9.9.2.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be y projected at least once per 31 days in accordance j with the methodology and parameters in the ODCM 4 when Gaseous Radwaste Treatment Systems are not being fully utilized. 9.9.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEMS shall be
- 2. Action (s) taken to. restore the inoperable equipment to OPERABLE status, and 3.> Summary description of action (s) taken:to prevent a recurrence,
- b. The provisions of Sections 9.0.3 and 9.0.4 are g ,
9.9.3 Bases 9.9.3.1 The OPERAPILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM . ensures that the systems will be available for 1 use whenever gaseous effluents require treatment 1 prior to release to the environment. The requirement that the appropriate portions of ! these systems be used, when specified, provides
- considered OPERABLE by meeting Sections 9.6.1.1 L and 9.7.1.1 or 9.8.1.1.
be kept "as low as is reasonably achievable". This control implements the requirements of 10 CFR Part 50.3Ga, General Design Criterion 60
- ' reasonable assurance that the releases of radioactive materials in gaseous effluents will >
, objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing s the use of appropriate portions of the systems were specified as a suitable fraction of the dose _'i design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for. gaseous q effluents. N' 2 6 i k }. 3:3) -159-
- of Appendix A to 10 CFR Part 50, and the design
n ni, d,". $~ig p 4 APA-ZZ-01003 pg;. *; ;1g;g;) 1 Rov.:0' p:- .m . - , 4,..;: ' i i > i ~~ n M pt o , , l/n, '-W. , m,u n_ ~. , k,[ 9.10- l TOTAL" DOSE: . . ,:n p;,)fjpj .; ' 41864' 9.10.1 . Controls k i, ., g - . . 7 . 4 9.10.1,l' The: annual;(calendar year) dose orcdose hy 'iw commitment to any. MEMBER OF THE PUBLIC due to- . releases;of. radioactivity and:to. radiation from. W ,+g , . Luraniumifuel cycle sources shall be limited to-- '" L[. ! J. > t..less-.than or equal to 25 mrems to the whole body.l ', ,N < ~ ,ortany organ,-.except the-,thyroidj~which shall.be~. n, Elimited to less the or e4Gil'.te 75,mrems. ,+ .w ' .o C: . L ' ~ APPLICABILITY: At all times. \g ( , 4
- pm
- , , .
~' g -- U ,' m . t ,ko, ~ s a 's [ e .! ( I i t e' yn \, " l c ,gy -160-i (, W @ 7 *O. ,. .w eA *J NS1 ~ 1 lj _ 4^ " 4 N . - 1: - !*' ' s~ 'APA-ZZ-010037 '? 4. Rod. , 0 q
- l. - A
s h% M a. Withithe. calculated doses ~from the release of, - O . radioactive materials,in liquid or gaseousi y' ! sdf;w"' effluentsfexceeding.twice the limits,of; , C Section,9'.4.1 la., 9.4.1.lb, 9.7.1.la., x SW ' 9.7.1.1b., 9.8.1.la., or.9.8.1.lb.,. -i nv c'alculations should be made including direct i Ui radiation contributions;from the units!and t jyn from outside storage tanks to determinei ! 1p whether the: above limits, of Section 9.10.1.1 j 'm p" have been exceeded. 'If = such ,is. thei case, .- J' ~ prepare and submit tolthe~ Commission within', ON ' 30: days, pursuant to Technical. y ' Specification 6.9.2, a Special-Report-that
- flgm: ." [ ,d k h;. " , ,M i ACTION:1 k[ht; ,
3 L recurrence of exceeding the above-limits and 't H includes the schedule for achieving . .conformance with'the above limits. J This Special Report,- as defined in 10 :CFR 20.405c, shall include an analysis that estimates.the
- f. ' defines the corrective action.to be taken to reduce subsequent releases.to prevent . ,
PUBLIC from uranium fuel cycle sources, , ,, including all effluent pathways andidirect .1 L radiation, for :the ' calendar- year thatDincludes t u, :the release (s) covered by this; report. It: , ,n -shall also describe l'evels of radiation and - 4 E '. concentrations of radioactive material , '; involved,--'and-the cause of the exposure levels. ' b' sor concentrations. .If the Lestimated dose (s)' ;; H exceeds the:above limits,<and if-the release L = condition: resulting in violation sof _40c CFR Part~190 has not"already been corrected, the, .Special Report shall include:a request for a: variance in accordance with the. provisions ~of 40.CFR Part 190. Submittal of the report:is'- f considered a timelyfrequest,' and a variance is, granted until staff action on:the' request"is complete. . b..The provisions of. Sections 9.O.3 and 9.0.4 are (7 not applicalbe. t lY$b asr x -161-s ~%. . 'i e - - . ._____-__-.____L._.-.--_-_-_----_.-.--__-.-__.____---.__.___---__.--___-- . _ _ - - - . _ -- _ - ~- %g , ,. ,o q; E , g APA-ZZ-01003? ,Rev. O q- , ~ 41865' 9.10!21 Surveil 1an'ce i Recuirements i 9.10.2#.1: ' cumulative doseEcontributions from liquid;and gaseous _ effluents shall be' determined in' 'accordance withl Sections 9.4.2.1, 9.7.2.1 and 9.8.2.1,= and in accordance :with the methodology and parameters in the.ODCM, - 9.10.2.2-Cumulative. dose, contributions from direct radiation from the units and'from radwaste storage tanks:.shall.be: determined in-accordance with the' methodology:and-parameters in-.the:ODCM. This requirement..is-applicable only under conditions. set forth in ACTION a. of-Section 9.10.1.1 ) L g a 'I .i' i ! L I f' i \ ~ w -162-s ,c X _ _ - _ _ _ _ _ _ _ _ _ _ - - t '~~ ~ ~'~ ~ ~ ~~~ ~ ~ spun :J kkf[' ' " APA-ZZ -01003 -. hhh N: pnp 3 Rov. 0 7 ;w , , [. t yt' h hhhhM hDO g}$ ' -9.10.3 'IBases %%r 9.'10.3.1 This'section is provided to meet-the dose., limitations of 40 CFR Part 190 that have:been p% T ' -incorporated.into 10 CFR Part 20 by 46 FR 18525. hM MS W' The' control requires-the preparation'and submittaltof a Special Report whenever the _. T 1" calculated doses'due to releases of radioactivity and the-radiation from uranium fuel-cycle' sources K@ _ - . exceed 25 mrems to the whole body or any organ,. dW 4 except the thyroid, which shall.be' limited.to y f "3 less than'or; equal to-75 mrems.- For sites. g containing up to four reactors, it is highly; i, unlikely that the resultant-dose to a MEMBERLOF c', THE PUBLIC will exceed the dose limits.of.40'CFR-M@! , Part 190 if the indiv1 dual reactors remain within1 gf twice the dose design objectives of Appendix I,7 f* < , and if direct. radiation-doses from the. reactor-units and-from outside storage tanks-are kept; !,1 i small. .The Special Report will. describe a, course f , &, .of action that should result in the' limitation of %{ the annual, dose to a MEMBER OF'THE PUBLIC toi 1within the-40 CFR Part 190 limits. For-the o1 fil ", > l purposes of the Special Report, it may be assumed , # that:the dose commitment to'the MEMBER,OF THE .L.?,W PUBLIC from^other uranium fuel cycle sources is- ' Q. ' negligible, with the exception.that' dose contribution from other nuclear fuel cycle #( !/ facilities at the same site.or within a radius of- $t gm g h 8 km must be' considered. If-the dose:to any . MEMBER,OF?THE;PUBLIC is. estimated'toiexceed'the-pp requirements lof 40 CFR~Part'190,'thefSpecial: fp4 Report with-a request for a variance'(provided E .z y the' release conditions-resulting in violation-of-R !" , 40 CFR Part 190 have not already been corrected), gy in accordance:with-the-provisions'of 40 CFR 190.11 and 10 CFR 20.405c, is considered-MS '? ,J to be a' timely' request and fulfills the. . . y7 "I requirements of 40 CFR Part 190 until,NRC staff M :.S actionLis completed. The-variance only. relates'. M to the limits of 40 CFR Part 190, and does not k$l! apply in=any way.to the other requirements <for M"o F dose limitation of.10 CFR Part'20, as addressed in. Sections 9.3.1.1 and.9.6.1.1. An individual. 6[y%"{' is not considered a MEMBER 0F THE PUBLIC during? any period in which he/she is enetaged in carrying bM* S .out any operation that is part of the nuclear ,y' . fuel cycle, ah,s .s) e W f -163-ax I Y. . x , ,r+ ' l } AP55ZZ-010031' :;, [ o Rew 0 - , p l 1 :, - i t: , e ^1 c9.11 RADIOLOGICAL ENVIRONMENTAL MONITORING' PROGRAM' ;i. l 41866 9.11.1' -Controls 1 9.11 - 1.1'- . The Radiological Environment Monitoring Program'.: 0-O shall'be conducted-as-specified in Table 9.11-A. t .. APPLICABILITY: At.all times. ' ' ACTION: n ;; .a. ; With the Radiological. Environmental MonitoringJ Program not being_ conducted as'.specified.in. Table 9.4-A, prepare and submit to the: . Commission, in the Annual Radiological: . ; Environmental Operating Report required by. , .section 7.1, a description-of the reasons for. + not conducting.the program as required'and the? W plans for preventing a recurrence., ,7' '+ h, '}i' a.i ,p s'y, E 1 ! l 'i s + ~ ;g ; y,ti ([ . $57\ - e ;Yf. -164- 1 s ' M, ",7 u; i Y ( apt.-ZZ-01003 rov . 0 - /. t i o - 3 _, b. With t a level of radioactivit; as the result of plant effluents in an onvironmental sampling medium at a sperat.ad location exceeding the reporting levels of Table 9.11-A s, hen averaged over any calendar quarter, prepare and submit to the Commission within 30 days,-pursuant to Technical. 4 Specification 6z9.2, a Spe-ial Report that identifies the cause(s) for exceeding the J , limit (si and defines tAe corrective actions to be taken to reduce radioactive effluents'so that t'ae pot.ential annual dose *.to a MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 9.4.1.1,19.7.1.1, or 9.8.1.1. When more than one of the radiocuclides in Table 9.11-B are detected in the e:Ep?ing medium, this report thall be submitted'ift concentration (1) concentration (2) reporting level (1) + reporting level (2) + ...> 1.0 When radionuclides other than those in Table 9.11-B are detected and are the result ' of plant effluents,othis report shall be submitted if the potential annual' dose
- radiation exposure ~(dose):to a MEMBER.OF THE: -
9.8.1.1..This report is not required if:the measured level'of radioactivity _was-not the - result of plant effluents; however, in such an event, the condition shall ha reported Lnd described in the Annual Radiological Environmental Operating Report, required by Section 7.1. 4 40g; *The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report._ -165-Y. p 1 P , APA-E -01003 j " Rtv. 0 , H : 1 - 1
- to A MEMBER OF THE PUBLIC.from all' radionuclides is aqual to or greater.than the calendar year limits of Sections 9.4.1.1, 9.7.1.1 or.
identify specific locations for obtaining l replacement samples and add them within ^ 30 days to the Radiological Environmental g Monitoring Program given in the ODCM.** The if 4 specific locations from which samples were-unavailable may then be deleted from the ; monitoring program. Pursuant to Technical ! Specification 6.14,-submit as part of, or 1 cor.aurrent with, the next Semiannual- Radioactive Effluent Release Report a complete ; and legible' copy of the entire ODCM, including i the revised figure (s) and table . reflecting the ; new location (s) with supporting information : identifying the cause of the unavailability'of l samples and justifying the selection of new location (s) for obtaining samples. .
- c. With milk et fresh leafy vegetable samples l unavailable from one or more of the sample 2 locations required by the Table 9.11-A, !
not applicable. ( 41867 9.11.2 Surveillance Requirements 9.11.2.1 The radiologica1' environmental monitoring samples shall be collected pursuant to Table'9.11-A from' .i p the specific locations given in the table and ' r figure (s) in the ODCM, and shall be analyzed K pursuant to the requirements of Table 9.11-A and the detection capabilities required by l Table 9.11-c. , 9.11.3 Bases 9.11.3.1 The Radiological Enviernmental Monitoring Program . required by this section provides representative ; i measurements of radiation and of radioactive - i materials in those exposure-pathways-and for l those~ radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE I f PUBLIC resulting from the station operation. : l This monitoring program implements Section IV.B.2 ' l~ of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring . Program by verifying that tha measurable < concentrations of radioactive materials and levels of radiation are notthigher than expected , on the basis of the effluent measuremunts and the f.y?) ** Excluding short term. or temporary unavailability. -166-b, 3 APA-ZZ-01003 f., ' Rov. 0 / 5 y j.- ' R 1 i- modeling of the environmental exposure pathways. l ;; Guidance for this monitoring program is provided f q by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, l' November 1979. The initially specified , monitoring program will be effective for at least the first 3 years of commercial operation. , r Following this period, program changes may be initiated based on operational experience. L: The required detection capabilities for
- d. The provisions of Sections 9.0.3 and 9.0.4 are. -
{ K terms-of tne lower limits of detection (LLDs), f The LLDs required by Table 9.11-C are considered l [ optimum for routine environmental measurements in industrial laboratories. It should be recognized : that the LLD is defined as a priori (before the fact) limit representing the capability of a .- measurement system and not as an a posteriori (after the fact) limit for a particular : measurement. , i * ~ Detailed discussion of the LLD, and other detection limits, can be found in NASL Procedures Manual, HASL-300 (revised annually),
- p . environmental sample analyses are tabulated in
and Quantitative Determination - Application to Radiochemistry", Ane.l. Chem.'40, 586-93 (1986), and Hartwell, J. K., " Atlantic Richfield Hanford , , ' Company Report ARH-SA-215 (June 1975). t 3 j; ' , h a ; E . F
- Currie, L. A., " Limits for Qualitative Detection >
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RAD iot.OGICA1 LffVIR00EMEMTAt_ Moltt10RiffG PftOGRMt r .. 98UNH(R or Rf PfttSENI AT IVE [XPOSUltE PAllf4 FAY SAMPI[S AND SAMPt.190C ASID AssozoR sAMPtc TYPE A800 IREQtMIOCY - sAMPir tocArsonst') cott tcitow rntastsscy or ANatyses i 8s . Ingestion (Continued)
- APA-ZZ-01003 Rev. O Inst 2 _2 d!-^tcont!rnrd)
- c. food Samples of three dirrerent Morithly when Proelucts k4 rids or broad tear vegetatiors Gamma isotopic (S) sewt available. 8-131 analysis, (continued) ir available grown r*carest each i of two dirrerent arrsite
One sample or each or Elie Monthly wesers similar broad tear vegetation Camma !sciopic(S) ated available. 3-13 8 area tysis. growen 15 to 30 km (10 to 20 mile) distant in the tedst prevalent wired di rection i t alik sampfing is not pe r ro71ssed. 1 4 -171r __v v m _o _c,_ --xw -*-n m +-+ - emp-- 1e--r +y *y e'+- e+w-f ---
- locations of tilghest predicted arsensal everage grownd-levet U/ft it' milk sampffwp is not performed.
' ' ' ' ~ ' ' " ' '~ ' '" " " ' ' ' ^WT ""(([ - a, ' ' if " ' ' " w1 it . . , APA-ZZ-01003 s * ,, Rsv. O BE \ > ,: , t L a.Tp f i-TABLE 9.ll-A (Continued) ,, c TABLE NOTATIONS 41868 (1) Specific parameters of distanca and direction sector from the centerline of one unit,. and 4 . additional description where pertinent, shall be provided for each and every sample location in Table 9.11-A in a-table and figure (s) in the . ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of au'.omatic sampling equipment, and other legitimate reasons. If-specimens are unobtainable due to sampling equipment malfunction, every effort sha.ll be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section 7.1. 7t.is recognized that, at times, it may not be possible or practicable to continue.to obtain samples of the media of choice at the most desired location or , time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the-Radiclogical Environmental Monitoring Program given in the ODCM. Pursuant touTechnical Specification 6.14, submit as part of,'or concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible . copy of tne entire ODCM including-the revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway-and justifying tht selection of the new location (s) for obtaining samples, n: o e l 3-. -172-s. -_m 4 1 ,. , . l* < APA-ZZ-01003 ir R0v. 0 ] i b .. I TABLE 9.11-A (Continued) j TABLE NOTATIONS ) L : \ I-(2) One or more instruments, such as a pressurized 1 h L ion chamber, for measuring and recording dose j rate continuously may be used in place of, or in -l addition to, integrating dosimeters. For the' -; y purposes ' of this table, a thermoluminescent cosimeter-(TLD) is considered to be one phosphor; ; two or more phosphors in a packet are considered l l as two or n. ore dosimeters. Film badges shall net - p - be used as dosimeters for measuring direct ' i radiation. The 40 stations is not an absolute # h number. The number of direct radiation , monitoring stations may be reduced according to i geographical limitations; e.g., at an ocean site, some sectors will'be over water so that the l number of dosimeters may be reduced accordingly. , }_ The frequency of analysis or readout for.TLD ' systems will depend upon the characteristics of the specific system used and,should be selected ' to obtain optimum dose information with minimal j fading, i (3) The purpose of this sample is to obtain l' background information. If it.is not practical to establish control locations in accordance with l the distance and wind' direction criteria, other I sites that provide valid background data may be i ! substituted. (4) Airborne particulate sample filters _shall be L analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron , I. daughter decay. If gross beta activity in air ! particulate samples is greater then 10 times the yearly mean of control samples, gamma isotopic : analysis shall be performed on the individual samp1'es. ; (5) Gamma isotopic analysis means the identification ; and quantification of gamma-emitting , radionuclides that may be attributable to the : effluents from the facility. , (6) The " upstream sample" shall be taken at a distance.beyond significant. influence of the discharge. The " downstream" sample shall be fii+ rg taken in an ar a beyond but near the mixing zone. L 1 vy:a l -173-4 e', $1N' APA- g-cloos *Y Rov. O q' TABLE 9.11-A'(Continued) . TABLE NOTATIONS x (7) In this program composite sample aliquets shall [ ,o' be collected at time intervals that are very short (e.g., hourly) relative _to the compositing ' period (e.g., monthly).in order to assure obtaining a representative sample, ti [' (8J1 rGroundwater samples shall'be:taken when this-1 source is. tapped for drinking or irrigation purposes in areas where the' hydraulic-gradient or , ,- recharge properties are suitable for contamination. (9)' The dose chall be calculated for the maximum organ and age group, using the methodology and partmeters in the ODCM. (10)- .If hirvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harJest occurs continuously, sampling shall be monthly.. Attention shall be paid to including samples'of tuberous and root food products.- 1 -174-L. y ~ 1 .- )~, - I' 3 0 0 1 0 ZO Z . Av Pe " AR S) e I t u Ce l a S Uw E O v L O , f Rg 0 0 0 a M Pk 1 0 0 0 , A / 0, 0, s S )i 8 0c . 1 2 l e t 0p p T A 6( m . 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; TABLE NOTATIONS' 41869 (1) This list does not mean that only these'nuclides are to be considered. 'Other peaks-that are identifiable, together with those of the above .nuclides, chall=also be analyzed and repo:ted in the Annual Radiological Environmental Operating Report pursuant to Section 7.1. (2) Eequired detection capabilities for thermoluminescent dosimeters used-for environmental measurements shall be in accordance .with'the recommendations'of-Regulatory Guide 4.13, Revision 1, July 1977. 9 I dt' $ 5 9 v r ((; c,. -177- .s. 3 L. U b i APA-ZZ-01003 ! i Rcv. O K i t , TABLE 9.11-C (Continued) ! 5 : y , TABLE NOTATIONS i (3) The LLD is defined, for purposes of.these- ) controls, as the smallest concentration of , radioactive material in a sample that will yield i o a-net count, abovo. system' background, that will' be detected with 95% probability with only 5% ?' . probability of falsely: concluding that a blank observation represents 'a "real" signal. !' For a particular measurement _ system, which may l l include radiochemical separation: LLD = 4.66 s b E
- APA-ZZ-01003 Rov. O TABLE 9.11-C (Continued),
Where: , LLD = the "a priori" lower limit of detection (microcuries per unit mass or volume), ; 9 sb = the standard deviation of the-background -, counting rate or of the counting rate of a L blank sample as appropriate (counts per minute), E = the counting efficiency (counts per i disintegration), i V = the sample size-(units of mass or volume), 2'.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, > T 1.= the radioactive decay constant'for the particular radionuclide (s 8), and at = the elapsed time between the sample collection, or and of the sample collection , period, and the time of counting (s). Typical values of-E, V, Y, and At should be used in the calculation. O?bh p v.s ~ -178- ~ L = , , y , , ;. ? 4 a APA-ZZ-01003 i l a. Rov. , 0 g- ~ , , ' f .~ , *' ' 'i . i (;: A m l I,.,
- V 2.22
- Y
- exp (- AAt)
TABLE 9.11-C (Continued) , I,1 , TABLE NOTATIONS' a 'It should be recognizedithat the LLD'is' defined 4 h. as a.a priori (before the fact)-limit- . H n representing the capability of a measurement . ; system and'not as an a posteriori.(after.the .! ! , fact);11mit for-a particular measurement. .. Analyses shall be. performed in.such-a. manner that' l [. ' the stated LLDs will be achieved under routine ! L Lconditions, occasionally background . . i 6- fluctuations, unavoidable small sample'aizes, the [o < presence of interfering nuclides,-or other l l uncontrollable circumstances may_ render these- ! [ LLDs unach.tsvable. In such cases, the ! D , , . contributing factors shall be identified and I l' . described in the. Annual Radiological _ { Environmental Operating Report pursuant to ; ;' section 7.1. ; I ,' -(4). LLD for drinking water samples. For surface r water samples, the LLD of gamma isotopic analysis j may be used. , I I 'k i$ ' if ' l I 2 1 1 ,.. 't i.I -j a s i 0; ,,1 0 ' . 1 a=~ \ [ ihf' 4 1. p -179- l 1 \,- , E , d e ..APA-22-01003 l R0v. 0 . i , 4 9.12 RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE s CENSUS , 41870. 9.12.*. Controls t l 9.12.1.1' A Land Use Census shall be' conducted and shall , identify within a distance of 8 km (5 miles) the. i location in each of the 16 meteorological sectors , of the nearest milk animal, the nearest residence- i and the nearest garden
- h , ,
1 APPLICABILITY: At all times. ACTION:
- of greater than 50 m 8 -i (500 ft8 ) producing broad leaf vegetation.
location (s) that yields a calculated dose or ; dose commitment greater than the values' . currently being calculated in Section 9.8.2.1, ; identify the new location (s) in the next c Semiannual Radioactive Effluent-Release ( Report, pursuant to Section 7.2. : 1 I i l t 1 I i I l 1 1 l . i
- a. With a Land Use Census identifying a :
..c,. vegetation may be--performed at..the SITE. BOUNDARY..in.each of two , of ffer'ent direction sectors with the highest predicted D/Qs in lieu of l g.Ap. .the garden census. Specifications for broad leaf vegetation sampling ( ",,- in Table 9.11-A, Part 4.c. shall be followed, including analysis of-control samples. -180-1 %. c w APA-ZZ-01003 y Rov. 0 ^ ?' b. With a Land Use Census identifying a o location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from j which samples are currently being obtained in ',' accordance with Section 9.11.1.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the c - ODCM. The sampling location (s),~ excluding the control station location, having the lowest , calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from-this. monitoring program after october 31.of-the year in which this Land Use Census was conducted. Pursuant to Technical Specification 6.14, submit as part of, or-concurrent with, the next Semiannual
- Broad loaf vegetation sampling of at least three different kinds of i
; and legible copy of the entire ODCM, including j- the revised figure (s) and table (s) reflecting L ' the new location (s) with information supporting the change in sampling locations,
- Radioactive Effluent-Release Report a complete
not applicable. . 41871 9.12.2 Surveillance Requirements 9.12.2.1 The Land'Use Census shall be conducted during the growing' season at least once per .- 12 months:using that information that will provide the best. ; results, such as by a door-to-door survey, aerial survey, or by consulting local. agriculture authorities. The'results of the Land Use Census shall be included in the Annual Radiological Environmental operating Report pursuant to Section 7.1. l' !~ ; g3 3 N.h -181- %. i APA-22-01003 R^v. 0 1 j I r F i ; [ 41872 9.12.3 Bases . ( i. 9.12.3 1 This section is provided to ensure that changes - in the use of areas at and beyond the SITE ; BOUNDARY are identified and that modifications to . the Radiological Environmental Monitoring. Program f, given in the ODCM are made if required by the l results of this census. Information that will 3 t provide'the best results,-such as door-to-door ! survey, aerial survey, or consulting with -local agricultural authorities, shall be used. Thir census satisfies the_ requirements of . Section IV.B.3 of Appendix I to 10 CFR Part'50. l' Restricting the census to gardens of-greater'than , 50 m8 provides assurance that significant L exposure pathways via. leafy vegetables,will be > f identified and monitored since a garden of this g size is the minimum required to produce the J- quantity-(26 kg/ year) of leafy vegetables assumed i in Regulatory Guide 1.109 fo'r consumption by a , ') child. To determine.this minimum garden size, [ the following assumptions were maden (1) 20% of - g; the garden was used for growing broad leaf- ; vegetation (i.e., similar'te lettuce and ' cabbage), and (2) a vegetation yield of 2 kg/m 8. I l~ ly v, 4 \ 3 9 ll I e:: ') s, A fd % - 's.l h Q -182- 'I? m , ~ L t U ' 'APA-ZZ-01003 l R;v. 0 . I' ! L 9.13 RADIOLOGICAL ENVIRONMENTAL MONITORING l INTERLABORATORY COMPARISON PROGRAM j 41873 9.13.1 Controls -9.13.1.1 Analyses shall be performed on radioactive. i materials supplied as part of an Interlaboratory ; l Comparison Program that has been approved by the , g Commission. j r e APPLICABILITY: At all times, ACTION: .
- c. The provisions of Sections 9.0.3 and 9.O.4 are '
above, report the corrective actions taken'to i prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.1. ]" i b..The provisions of Sections 9.0.3 and 9.0.4 are , not applicable. l 41874 9.13.2 Surveillance Requirements , i 9.13.2.1 The Interlaboratory Comparison Program.shall be described in this procedure. A summary of the results obtained as part of~the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental ! Operating Report pursuant to Section 7.1. , 9.13.3. Bases 9.13.3.1 The requirement for participation in an approved Interlaboratory Comparison Program is'provided to ensure that independent checks on the precision ; and accuracy of the measurements of radioactive t material in environmental sample matrices are performed as part of the quality assurance = program for environmental monitoring in order to' demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. t P k b \ Le 1 l I- -183-L. i [. - 'APA-Z2-01003 M Rov. 0 (, ' L , s 10.0 ADMINISTRATIVE CONTROLS 10.1. ~ MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE ! TREATMENT SYSTEMS
- a. With analyses not being performed as reqaired ,
l
- l 10.1.1 Licensee-initiated major changes to the Radwaste
- Treatment Systems (liquid and gaseous):
). for the period in.which the evaluation was ! [ reviewed by the On-Site' Review Committee a (ORC). The discussion of each= change shall + [. contain:
- a. Shall be reported to the Commission in tP1 l' h[ . Semiannual Radioactive Effluent Release Report
determination that the change could be made in accordance with 10 CFR 50.59; ; 2) Sufficient detailed information to totally 1 support the reason for the change without ' benefit of additional or supplemental l 4 - information; , I
- 1) A summary of the evaluation that led to the !
components and processes involved and the t interfaces with other plant systems; .; l 4) An evaluation of the change, which shows , i the predicted releases of radioactive i f . materials in liquid and gaseous effluents and/or quantity of solid waste that differ i , from those previously predicted in the . [ License. application ~and~ amendments thereto; L 5) An evaluation of the change, which shows L 2 the expected maximum exposures to a MEMBER , OF THE PUBLIC in the UNRESTRICTED AREA and ' E , to the general population that differ from l' those previously estimated in the License . application and amendments thereto; l7 h 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to l the actual releases for the period prior to when the changes are to be made; ai.. L .r v;9 + i hi#'
- 3) A detailed description of the equipment,.
4 , p -184-L ' L LAPA-ZZ-01003 g, rov.1 0- j b y 1 .i . i , N-
- Union Electric Co. may choose to submit the information called for in this specification as part of the annual FSAR update.
[ operating personnel as m' result of the i change; and I i , 8) Documentation of the fact that the change l was reviewed and found acceptable by the ; o ORC. 1 k,
- 7) An estimate of the exposure to plant !
?. Technical Specification 6.5.3.1. 2: 10.2 CHANGES TO THE OFFSITE DPSE CALCULATION MANUAL I ( (ODCM) 1' 2815 10.2 1 . All changes in the ODCM shall be completed pursuant to Technical Specification 6.14.2 and < r approved as per APA-ZZ-00101, Preparation, - j; Review, Approval And Control Of Procedures, i > b 2815- 10.2.1.1 All changes shall be approved by.the ORC PRIOR to ! O implementation.' , i; > q , 10.2.2 Cross Disciplinary Review for each' revision of ,, L' the.ODCM must include, as a minimum,cHealth ; Physics, Quality Assurance, and Radiological , I' ' Engineering. - '2815 '10.2.3. A complete and' legible copy of each revision of - a, the CDCM that became effective during.ite.last ?_ semiannual period shall be submitted as:a part. I d of, or concurrent with that periods Semiannual 0 Radioactive Effluent' Release Report pursuant to: Technical Specification 6.14.2. p 51' . ? g , r . , , 1 v 1 .
- b. Shall become effective-upon review,and 1 i .- approval by the. ORC an;in accordance with
. V-, 8
- a:., j
] '.i1 9 -185- 1 M l i- y.: APA-ZZ-01003 Rsv. O ; I
- . x t
- P
11.0 REFERENCES
i' 11.1 Title 10, " Energy", Chapter 1, Code of Federal t Regulations,-Part 20; U.S.^ Government Printing : Office, Washington, D.C. 20402. ; 11.2 Tit'.e 10, " Energy", Chapter 1, Code of Federal
.Regalations, Part 50, Appendix I; U.S. Government 'Printing Office, Washington, D.C. 20402. ! 11.3 Title.40, " Protection'of Environment", Chapter.1, . Code of Federal Regulations,.Part 190; U.S. Government Printing Office, Washington, D.C. l 20402. ! I 11.4 U.S. Nuclear Regulatory Commission, " Technical ^ Specifications Callaway Plant, Unit NO. 1", NUREG-1058 (Rev. 1), October 1984. i 11.4.1 Section 6.8.1 (2791) 11.4.2 Section 6.8.4f (41834) , 11.5 Communications
. 11.5.1 Letter NEO-54, D.W. Capone to S.E. Miltenberger, dated January 5, 1983; Union Electric Company ,correspondenco.
'11.5.2 Letter BLUE.1285, "Callaway Annual Average X/Q ;and D/Q Values", J. H. Smith (Bechtel Power ' Corporation), to D. W. Capone (Union Electric , Co.), dated February 27, 1984. . 11.5.3 Letter BLUE 1232, "Callaway Annual Average X/Q . ! Values and "S" Values", J. H. Smith (Bechtel : Power Corporation) to D. W. Capone (Union i Elecetric Co.), dated February 9, 1984. , 11,5.4 Letter' BLUE 1358, " Comparison of Callaway Plant - Offsite Dose Calculations for Routine Effluents", J.H. Smith (Bechtel Power Corporation) to D.W. Capone (Union Electric Company), dated March 22, . 1984. l 11.5.5 Private Communication, H.C. Lindeman & B.F. I Holderness, August 6, 1986
,^* _11.5.6 Calculation ZZ-67, " Annual Average Atmospheric Dispersion Parameters", April 1989.
-186-Ds
} ' "4 APA-ZZ-01003 0 " ' rov. O y .I ~
.11.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis-Report.11.6.1 Section 11.5.2.2.3.1 l 11.6.2 Section 11.5.2.2.3.4 ; r 11'.6.3 Section 11.5.2.1.2 *
) 11,.6.4 Section 11.5.2.2.3.2[ f 11.6.5 .Section 11.5.2.2.3.3 ' l 11.6.6 'Section 11.2.3.3.4 ' 11.6.7 Section 11.2.3.4.3 > L
.11.6.8 Section 11.5.2.3.3.1 -11.6.9 Section- 11.5.2.3.3.2 11.6.10 Section 11.5.2.3.2.3 i. ! 11.6.11 Section 11.5.2.3.2.2 .11.6.12 Section.2.3.5 1 11.6'13
. Section 2.3.5.2.1.2 11.6.14' Section 9.2.6, s ,: 11.6.15 Section 9.2.7.2.1 11.6 16 Section 6.3.2.2 11.6.17 Table 11.1-6 11.6.18 Table 9.4-6 11.6.19 Table 9.4-6 e
'11.6.20 Table.9.4-11 t11.6.21- Table 9.4-12 11.6'.-22 Table 2.3-68.
$ g, ?F.D Ji
. {Cd/ ~ -187- )m APA-ZZ-01003' [j , O R;v. O. , t i ! l- 11.7 Union Electric Company Callaway Plant l' t Environmental Report, Operating License. Stage. V .. :
', 11.7.1- . Table 2.1-19 ,11.7.2 Section 2.1.2.3 ! 11.7.3 Section 2.1.3.3.4 11,.7.4, Section 5.2.4.1 , 11.7.5 Table 2.1-19 11.8 U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Technical Specification For Nuclear Power Plants", USNRC NUREG-0133, Washington, D.C. 20555, October 1978. 0 11.8.1 Pages AA-1 through AA-3 ,
- p. 11.8.2 Section 5.3.1.3 i 3 ,
11.8.3 Section 4.3 11.8.4 Section 5.3.1.5 11.8.5 Section 5.1.1 11.8.6 Section 5.1.2 i I- 11.8.7- Section 5.2.1-11.8.8 Section 5.2.1',1 11.8.9 Section 5.3.1-11.8.10 Section 3.8 .
. 11.8.11 Section 3.3 ;.F 11.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, f Program For the Meterological Evaluation Of 3 Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington, D.C. 20555. J 11.9.1 Pages 19-20 Subroutine PURGE lh' I p ..>
-188- !L. IL O
i n .
+ 'APA-ZZ-01003 Rov. 0 11.10 Regulatory Guide 1.111, " Methods For Estimating Atmospheric Transport And Dispersion of Gaseous
. Effluents In Routine Releases.From Light-Water-Cooled Reactors", Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, July, 1977.11.10.1 Section c.1.b 11.,10.2 Figures 7 through 10 11.10.3 Section c.4 11.11 Regulatory Guide 1.109, " Calculation of Annual' Doses to Man From Routine Releases of Reactor
< Effluents For the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I",Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1977. 11.11.1 Appendix C, Section 3.a 11.11.2 Appendix E, Table E-15 11.11.3 . Appendix C, Section 1 11.11.4 Appendix E, Table E-11. 11.11.5 Appendix E,-Table E.9 11.12 U.S. Nuclear Regulatory. Commission, " Methods for Demonstrating ~ LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C. 20555, January 1980.
'11.12.1 Section I, Page 2 -11.12.2. Section IV,.Page 8 11.1. 3 Section IV, Page 9 11.12.4 Section III, Page 6 11.12.5 Section III, Page 8 -189-LAPA-ZZ-01003 rov. O g. L 7 11.13 Management Agreement for the Public Use of Lands, E b Union Electric Company and the State of Missouri Department of Conservation, December. 21, 1982. 11.13.1 Exhibit A 11.14 Miscellaneous References [ 11.14.1 Drawing Number M-109-0007-06, Revision 5. 11".14.2 Callaway Plant Annual. Environmental Operating Report (updated annually). [ 11.14.3 UE Safety Analysis Calculation. 87-001-00. i 11.14.4 Calculation 22-48, " Calculation of Inhalation and Ingestion Dose Commitment Factors for the Adult [ and Child", January, 1968. 11.14.5 HPCI 89-02, " Calculation of ODCM Dose Commitment Factors", March, 1989. q 11.14.6 HPCI 87-04, " Calculation of the Limiting Setpoint for the Containment Purge Exhaust Monitors,
, GT-RE-22 and GT-RE-33",. March, 1987. '11.14.7 HPCI 88-10, " Methodology for Calculating the p ' Response of- Gross NaI(TE) Monitors to Liquid Effluent Streams", June, 1988. 11.14.8 Calculation ZZ-57, " Dose Factors for Eu-154", January, 1989. 4 11.15 U.S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meterological Evaluation of Routine Effluent Releases at Nuclear Power e Stations", USNRC NUREG/CR-2929, September, 1982, Washington, D.C. 20555. n 11.15.1- Section 4, " Subroutine PURGE", pages 27 and 28.- 0 i 11.16 Regulatory Guide 4.13, " Performance, Testing, and [ ' procedural specifications for Thermoluminiscence Dosimetry: Environmental Applications
"(Revision 1), July 1977; USNRC, Washington, D.C. 20555 11.17 TID-7004, " Reactor Shielding Design Manual", .y , .7 , Rockwell, Theodore, ed; March 1956. , (791; -( . w
-190-i( , t
n , m-k% * ' - < APA-ZZ-01003 A, Roy. 0 l} U: 11.18 ENWL-236, "ISOSHLD - A computer code'for General
- s Purpose _ Isotope Shielding Analysis", Engel, R.C.,
k Greenberg, J., Hendrichson, M.M.; June 1966. 11.19- BNWL-236, Supplement 1, "ISOSHLD-II: Code i} , Revision to include calculation of Dose Rate from
?'Shielded Bremsotrahlung Sources", Simmons, G.L., et al; March 1967. p T 11.20 BNWL-236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD-III", Mansius,-C.A.;-April 1969. (f
" 11.21 ANSI N13.10-1974, " Specification & Performance of-On-Site Instrumentation for Continuously Monitoring Radioactivity in Lffluents";September, 1974. a 11.22 Nuclear Regulatory Commission Generic
- q. Letter 89-01, " Guidance for the Implementation of Programmatic Controla for RETS in the Administrative Controls Section of Technical
< Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose 'Calculation Manual or Prccess Control Program",
-January 1989.11.23 ODP-ZZ-00002', Equipment Status Control.-
.d; ,30 . u
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- 3. .
4
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+ s. -); - , -191-t i.f~t (}}