ML20059D264
| ML20059D264 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/30/1990 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20059D256 | List: |
| References | |
| PROC-900330, NUDOCS 9009060191 | |
| Download: ML20059D264 (89) | |
Text
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Hope Creek Generating-Station
/ v ReviAion' Number 11 of the'ODCM.-
Revision Date: 3/30/90; 4 Docket No. 50-354.
". Operating License No. NPF !.
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'OFFSITE DO8E CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY EOPE CREEK GENERATING STATION l'
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- Revision 11 i Narch 1990
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-' Approval:
J SORC Chairman: / L - Date: 30 70 Mtg.# 70'03 6
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BOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL i l
TABLE OF CONTENTS ;
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INTRODUCTION.............................................. 1
~1 1.0 LIQUID EFFLUENTS '
1.1 Radiation Monitoring Instrumentation and Controls................... 2 1.2 Liquid Effluent Monitor q Setpoint Determination......................... 3 1 1.2.1 Liquid Effluent Monitors................ -4 1 1.2.2 Conservative Default Values............. 5 l 1.3 Liquid. Effluent Concentration : ]
Limits -10'CFR 20.............................. 7 !
R 1.4 Liquid Effluent Dose Calculations - 10 CFR 50. .. ................. 8 3 1.4.1 Member of the Public Doso -
Liquid Effluents.............. ......... 8
.1.4.2 Simplified Liquid Effluent '
Dose Calculation....................... 10 1.5 Liquid Et' fluent Dose Projection................ 11 1 2.0 GASEOUS EFFLUENTS Radiation Monitoring 1
2.1
= Instrumentation and Controls................... 12 .:
i 2.2 Gaseous Effluent Monitor Setpoint Determination........................ 13 2.2.1 Plant Vent and.FRVS Monitors............ 13 2.2.2 Conservative Default Values. . . . . . . . . . . . . 15 2.3 Gaseous Effluent Instantaneous Dose Rate Calculation - 10 CFR 20.............. 17 2.3.1 Site-Boundary Dose Rate -
Noble Gases............................. 17 2.3.2 Site Boundary Dose Rate -
Radiciodine and Particulates............ 19 3
o-2.4- ' Noble Gas Effluent Dose Calculations - 10 CFR 50....................... 21 2.4.1 UNRESTRICTED AREA Dose -
Noble Gases............................. 21 2.4.2 Simplified Dose Calculation for Nobel Gases.......................... 22 2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50......................._23 2.5.1 UNRESTRICTED AREA Dose -
Radioiodine and Particulates............ 23
2.5.2 Simplified
Dose Calculation for Radioiodines and Particulates........... 24 2.6 Gaseous Effluent Dose Projection............... 26 3.0 SPECIAL DOSE-ANALYSIS 3.1 Doses Due to Activities Inside the SITE BOUNDARY.............................. 28 3.2 Doses to MEMBERS OF THE PUBLIC -
40 CFR 190.................................... 129 3.2.1 Effluent Dose Calculation............... 30 3.2.2 Direct-Exposure Determination........... 30 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. . . . . . . 32 4.1 Sampling Program.................-.............. 32
- 4. 2- Interlaboratory Comparison Program............. 33
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L. TABLES 1-1 ~ Parameters for Liquid Alarm Setpoint Determination........................ 36 1-2 Site Related Ingestion Dose Commitment Factors, Aio....................... 37' 1-3 Bioaccumulation Factors (BFi).................. 39 2-1 Dose Factors for Noble Gases................... 42' 2-2 Parameters for Gaseous Alarm Setpoint Determination. . . . . . . . . . . . . . . . . . . . . . . . 43 2-3 controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations.........................-..... 41 L2-4 Pathway Dose Parameters -
Atmospheric Releases........................... 42 A-1 Calculation of Effective MPC................... A-4 B-1 Adult Dose-Contributions Fish and Drinking Water Pathways........................ B C-1 Effective Dose Factors......................... C-5 D-1 Infant Dose Contribution Fraction of Dose...... D-4 D-2 Fraction of Dose Contributions by Pathway...... D-4 E-1 Sample Locations............................... E-3 APPENDICE8 Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents.............. A-1 Appendix B - Technical Basis for Effective Dose
Factors - Liquid Radioactive Effluents...... B-1 Appendix-C - Technical Basis for Effective Dose Factors - Gaseous Radioactive Effluents..... C-1
. Appendix D - Technical Basis for Effective Dose
-Parameters - Gaseous Radioactive Effluents., D-1 1.
Appendix E - Radiological Environmental Monitoring Program - Sample Type, Location and Analysis E o
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Hope Creek ODCM_3/28/90 o
NOPE CREEK GENERATING STATION
.OFFSITE DOSE CALCULATION NANUAL TNTRODUCTION -
The Hope Creek Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in: '1) - the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints; and 2).the calculation of radioactive liquid and-gaseous concentrations, dose rates and cumulative quarterly.and yearly doses. The methodology stated in
,this manual is acceptable for use in demonstrating compliance
.with 10 CFR 20.106, 10 CFR 50, Appendix I and 40 CFR 190.
,More conservative calculation methods and/or conditions-(e.g.,
location and/or exposure pathways) expected-to yield higher computed doses' teat appropriate for the maximally exposed person n may be assumed in the dose evaluations.
The ODCM will be maintained at the station for use as a reference
, guide and training document of accepted methodologies and
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. calculation. Changes will be made to the ODCM calculation methodologies and parameters as is deemed necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.
NOTE: As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Hope Creek Technical Specifications.
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_ Hope Creek ODCM-3/28/90 j
1 1.0 LIQUID EFFLUENTS j 1.1- Radiation Monitorina Instrumentation and' Controls l l
The: liquid effluent monitoring instrumentation and
] i controls-at Hope Creek for controiling and monitoring normal radioactive material releases in accordance with the l Hope Creek Radiological Effluent Technical Specifications I are summarized as follows:
f1) Alarm -(and Automatic Termination) - Liquid Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by Technical Specification 3.3.7.9.
g 2) Alarm (Oniv) - The Cooling-Tower Blowdown Effluent Monitor (RE8817) provides an Alarm function only for releases into ;
the environment as required by Technical Specification 3.3.7.9.
Liquid radioactive waste flow diagrams with the applicable, i associated radiation monitoring instrumentation and controls are presented in Figure 1-1.
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Hope Creek ODCM 3/28/90:
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- 1. 2 L Lieuid Effluent Monitor Setnoint Determination
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Per c the requirements of Technical Specification 3.3.3.8, alarm'setpoints shall be established for the liquid monitoring instrumentation to ensure that the release m.
. concentration-limits of Specification 3.11.1.1 are met (i.e.,-the concentration of radioactive material released-in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B. Table 11, column 2, for radionuclides =end 2.0E-04 uCi/ml for dissolved or entrained noble gases). The following equation *',must-be satisfied to meet the liquid effluent restrictions:
C (F + f) c5 -------------
(1.1) f where:
C =
the effluent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml.
c' = .the setpoint, in uci/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent.line prior to dilution and sub-sequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA.
- Adopted from NUREG-0133 3
f Hope; Creek ODCM 3/28/90 l ~,
f =
the flow rate at the radiation-monitor location, in u
. volume per unit time, but the same units as F,-below. 1 8
l F. =
the dilution water. flow rate as' measured prior to the.
-release. point, in volume per unit time.
.[ Note that if-nofdilution is provided, c 5 C. Also, note that '
when . (F) 'is large compared to . (f) , then (F + f) = F. )
1.2.1 Liruid Effluent Monitors The setpoints for the liquid' effluent monitors at the Hope Creek Generating Station are determined by the following equation:~ l' MPC, *' CTBD 1
SP $ --------------- + bkg (1.2) l l
RR' l
I with:- *
'l 1
IC. 1 MPC- = ------------
(1.3) l I L(Ci/MPC1 )
where:
I SP =- alarm setpoint correnpondirig to the maximum allowable release rate-(uci/ml).
MPCs = an effective MPC value for the mixture of radionuclides in the. effluent' stream, (uci/ml).
=
Ci the concentration of radionuclide in~the liquid effluent (uci/ml)*.
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NOTE: -The concentration mix must include the most recent composite of alpha emitters, Sr-89, Sr-90, Fe-55 and H-3 as per Technical Specification 3.11.1.1. <
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MPCi = the-MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 Iuci/ml). .
CTBD = the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min).
RR -= the liquid effluent release-rate (gal / min) at the monitor location (i.e., at the-liquid radwaste monitor or at the CTBD monitor).
bkg = the background of the monitor.(uci/ml)..
The radioactivity monitor setpoint equation (1.2) remains valid during. outages when the Cooling-Tower Blowdown dis-charge is potentially as its lowest value. Reduction of the waste stream flow (RR) may-be necessary during these periods to meet the discharge criteria. Procedural restrictions prevent simultaneous liquid releases.
1.2.2 Conservative Default Values Conservative' alarm setpoints may be determined through the use of default parameters. . Table 1-1~ summarized all current default values in use.for Hope Creek.'They are.
based upon the following:
a) substitution of the effective MPC value with a default value of 5.00E-05 uCi/ml for radwaste releases (Refer
-to Appendix A for justification) ;
b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal / min; and, c) substitutions of the effluent release rate with the highest allowed rate, in gal / min.
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-With preestablished alarm setpoints, it is possible to-- -i .
1 control ~the radwaste release rate (RR) to ensure the-inequality.of equation (1.2) is maintained under changing 'l values for MPCe and for differing Cooling-Tower Blovdown discharge.
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-1.3 Lieuid Effluent concentration' Limits - 10 CPR 20' Technical Specification 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Cooling-Tower Blowdown Discharge System)'to less than.
the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases.
' Noble gases are limited to a diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled and radiation monitor alarm setpcints are established as addressed'above to ensure that these concentration limits are not exceeded.
However, in the event any liquid release results in an alarm setpoint being' exceeded, an evaluation of compliance-with the concentration limits of Technical Specification 3.11.1.1 may be performed using the following equation:
Ci RR 51 (1.4)
MPCi CTBD + RE o
where:
cpi = actual concentration of radionuclide i as measured in the undiluted liquid effluentf(uci/ml).
MPCi = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml).
= 2E-04 uCi/ml for dissolved or entrained noble gases.
RR = the actual liquid effluent release rate (gal / min)
CTBD = the actual Cooling-Tower Blowdown discharge at the i
time of release (gal / min).
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- Hope Creek ODCM 3/28/90-1.4- Lieuid Effluent' Dose Calculation - 10 CFR 50
! 1. 4 .1' MEMBER OF TRE'PUBLIC Dose - Licuid Effluents Technical Specification 3.11.1.2 limits the dose or dose- -
commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Hope Creek Generating Station to:
- during any calendar quarter:
$ 1.5 mrem'to total body
$ S.0 mrem to any organ
- during any calendar year:
1 3.0 mrem to total body 5 10.0 mram to any organ Per the surveillance requirements to Technical Specification.4.11.1.2, the following calculation methods shall be used for determining the dose or dose commitment-due-to the liquid radioactive effluents from Hope Creek.
8.35E04 * .VOL Do = --------------------
- I (ci Aio) 1.5 CTBD where:
D o- = dose or dose commitment to organ o, including total body (mrem).
Aoi
= site-related ingestion dose commitment factor to the total body or any organ o for radionuclide l' (arem/hr per.uci/ml).
= average concentration of radionuclide i, in Ci undiluted liquid effluent representative of volume VOL (uCi/ml).
VOL = volume of liquid effluent released (gal).
CTBD = Average Cooling-Tower Blowdown discharge rate y during release period (gal / min).
8.35E-04 =
conversion factor (1.67E-2 hr/ min) and a near field dilution factor of 0.05 (refer to Appendix B, Page B-4 for definition).
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4 Hope Creek ODCM 3/28/90 The site-related' ingestion dose / dose commitment factors (Aio).are presented in Table 1-2 and have been derived i..
accordance'with'a NUREG-0133 by the equation:
Aio = 1.14E5 ((UI
- BII) + (UF
- BFi )) DFi (1.6) where:
Aio = composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrato ingestion pathways (mram/hr per uci/ml).
1.14E5 = conversion factor (pci/uci
- ml/kg per hr/yr).
UI = adult invertebrate _ consumption (5 kg/hr) .
BIi = bioaccumulation factor for radionuclide i in invertebrates from Table 1-3 (pCi/kg per pCi/1).
UF = adult fish consumption (21 kg/yr).
=
BFi bioaccumulation factor for nuclide i-in fish from Table 1-4 (pci/kg per pCi/1).
=
DFi dose conversion factor for nuclide i for adults in preselected organ, o, from Table E-11 of Regulator Guide 1.109 (mrem /pCi).
The radionuclides included in the periodic dose assessment per the requirements of Technical' Specification 3/4.11.1.2 are those as identified by gamma rpectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11.1.1.1-1.
Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Technicel Specification Table 4.11.1.1.1-1.
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a Hope Creek ODCM 3/28/90 !
1.4.2 RiRBMf141.Liguid Effluent Dome Calculation ;
In lieu of Ne individual radionuclide dose assessment as ;
presented 'n section 1.4.1, the following simplified dose -
calculation equation may be used for demonstrating compliance Wjth the dose limits of Technical Specification 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.)
Total Body i
1.94E+02 * 'f0L
=
1 Dtb ------------------
- EC1 (1.7)
CTBD Maximum oraan 4.28E+02-
- VOL D max " ~~~~~~~~~~~~~~~~~~ * (1.8)
EC1 CTBD 4
where Dtb = conservatively evaluated total body dose (mrem).
Daax == evaluated maximum organ dose (mrem).
Ci average concentration of radionclide i, in undiluted liquid effluent representative of the volume VOI (uci/ml).
VOL = volume of . liquid effluent released (gal).
CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min).
1.94E+02 =
conversion factor (1.677-2 hr/ min) the con- .
version factor (2n-65, total body -- 2.32E5 mrom/hr per uCi/ml), and the near field dilution factor of 0.05 (See Appendix B). t
.4.28E+02 =
conversion factor (1.67E-2 hr/ min) the conversion maximum organ dose conversion factor (Zn-65, Liver
, -- 5.13E5 mrem /hr per uCi/ml), and the near field dilution factor of 0.05 (See Appendix B).
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o Hope Creek'0DCM 3/28/90 l 1.5 Lieuid affluent base Preisetions Technical Specification 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the 31-day projected doses exceedt j 0.06 mram to the total body, or ,
0.2 mram to any organ.
4 The applicable liquid waste proces: sing system for maintaining radioactive material releases AIARA are the I l
drain filters and dominerializers as delineated in Figure 1-1. l i
Dose projections are made at least onr.a per 31-days by the following equations j i
l D tbp "
(Dtb / d)
- 31d (1.9) 1 D maxp =
- 31d (Dmax / d) (1.10) l l
where:
D tbp =
the total body dose projection for current 31-day period (aram). J
=
Dtb the total body dose to date for current calendar r quarter as determined by equation (1.5) or (1.7). 1 Dmaxp = the maximum organ dose to date for current calendar quarter as determined by equation (1.5 or (1.8) (arem),
d =
the number of days in current calendar quarter at' the end of the release.
31d = the number of days of concern, L
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...- Hope Creek ODCM 3/28/90 2.0 GASEOUS. EFFLUENTS l l
2.1 Radiation Monitorina Instrumentation and controls The gaseous effluent monitoring instrumentation and controls i
at Hope Creek for controlling and mon cori) normal i radioactive material releases in acco, 'r e with the Radiological Effluent Technical Specif1.ations are j summarized as follows:
- 1) Eiltration. Recirculation, and Ventilation System -
The FRVS is maintained in a standby condition. Upon reactor building isolation, the FRVS recirculation system recirculates the reactor building air through HEPA and charcoal filters. Releases are made to the atmosphere via a reactor building vent or the South Plant Vent depending on mode of operation. Noble gas i
monitoring is provided by RE-4811A. ,
- 2) South Plant Vent - '
The SPV received discharge from the radwaste evaporator, reactor building purge, auxiliary building :
radwaste area, condensate dominorializer, pipe chase, ,
feedwater heater, and untreated ventilation sources.
Effluents are monitored (for noble gas) by the RE-4875B monitor.
- 3) North Plant Vent -
The NPV received discharges from the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources. Effluents are monitored (for ;
noble gases) by the RE-4573B monitor.
Gaseous radiohetive waste flow diagrams with the applicable, associated radiation monitoring instrumentation controls are H
presented in Figures 2-1 and 2-2.
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Hope Creek ODCM 3/28/90 o ,
t 3.3 - 3 3eus Effluent Monitor Satacint DeteralaatiOB ;
3.3.1 Plant Vent and FRVE Vent Moniterg }
- 3. L 1, i t Per the requirements of Technical Specification 3.3.3.10, j i
alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of I Specification 3.11.2.1, which corresponds to a dose rate I i
at the SITE BOUNDARY of 500 mram/ year to the total body or 3000 mrem / year to the skin. Based on a grab sample !
analysis of the applicable release (i.e., of TRVS, pipe chase, gaseous radwaste treatment system air, etc.), the radiation monitoring alarm setpoints may be established by {
the following calculation method. The measured j radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation: )
FRAC = (4.72E+02
- X/Q
- VF * (C i
- K i)) / $00 (2.1) j FRAC = (4.72E+02
- X/Q
- VF * (Ci* (Li + 1.1M1 ))) / 3000 (2.2) where:
1 FRAC = fraction of the allowable release rate based on I the identified radionuclide concentrations and the l release flow rate. !
X/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m3). J VF = ventilation system flow rate for the applicable release point and monitor (ft3/ min) . I
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= concentration of noble gas radionuclide i as Ci determined by radionnalysis of grab sample (uci/cm3)
Ki =
total body dose conversion factor for noble gas radionuclide 1 (arem/yr per uCi/m3), from Table 2-1 Li = beta skin dose conversion factor for noble gas radionuclide 1 (arem/yr per uci/m3), from Table 2-1 Mi =
gamma air dose conversion factor for noble gas radionuclide 1 (mrad /yr per uCi/m3), from Table 2-1 1.1 = mram skin dose per mrad gamma air dose (mram/prad) 4.72E+02 = conversion factor (cm3/ft3
- min /sec) 500 = total body dose rate limit (mrem /yr) 3000 = skin dose rate limit (mrem /yr)
Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:
- E Ci / FRAC) + bkg (2.3) where SP = alarm setpoint corresponding to the maximum allowable release rate (uci/cc).
FRAC = highest fract, ion of the allowable release rate as determined f.n equation (2.2).
bkg =
backornund of the nonitor (uci/cc).
AF = administrative allocation factor for the specific monitor (0.2 NPV, 0.2 SPV, 0.1 FRVS).
The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release 14 l
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i Hope Creek OCCM 3/28/90 ;
rate limits of Technical Specification 3.11.2.1). i l
Normally, the combined AF value for Salem Units 1 and 2 is '
l L 0.5 (0.25 per unit), with the remainder 0.5 allocated to -
Hope Creek. Any increase in AF above 0.5 for the Hope Creek Generating Station will be coordinated with the Salem Generating Station to ensure that the combined j 1
allocation factors for all units do not exceed 1.0. j 2.2.2 conservative Default Values l A conservative alarm setpoint can be established, in lieu )
1 of the individual radionclide evaluation based on the grab I
)
L sample analysis, to eliminate the potential of l l periodically having to adjust the setpoint to reflect L minor changes in radionuclide distribution and variations L
L in release flow rate. The alarm setpoint may be ,
l conservatively determined by the default values presented in Table 2-2.
These values are based upon:
the maximum ventilation (or purge) flow rate; >
a radionuclide distribution adopted from ANSI N237-1976/ANS 18.1 " Source Term Specifications", Table 5 and; <
an administrative allocation factor of 0.5 to conservatively ensure that any releases from Hope Creek to not exceed the maximum allowable release rate.
For the noble gas radionclide distribution from ANSI -
N237-1976/ANS 18.1 (Note Table C-1), the alarm setpoint based on the total body dose rate is more restrictive than ,
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i the corresponding setpoint based on the skin dose rate.
)
The resulting conservative, default setpoints are i
presented in Table 2-2. !
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2.3 Gassous Effluent Instantaneous bone Rate Calculations - 10_CFR 20 2.3.1' site Boundary Dose Rate - Noble GaggA '
Technical Specification 3.11.2.la limits the dose rate e,t the SITE BOUNDARY due to noble gas releases to S 500 mrem /yr, total body and $ 3000 mrem /yr, skin. Radiation monitor alarm setpoints are established to ensure that
.these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint (as determined in Section 2.2.1) being exceeded, I an evaluation of the SITE BOUllDARY dose rate resulting from the release shall be performed using the following equations:
Dtb = X/Q E (Ki
- Q) i (2.4) and Ds= X/Q
- I ((Li + 1.1M1 )
- Qi (2.5) where Dtb = Total body dose rate (mrem /yr).
Ds = skin dose rate (mrem /yr).
X/Q = atmospheric dispersion to the controlling SITE
=
BOUNDARY location (sec/m3).
Qi average release rate of radionuclide i over the '
release period under evaluation (uci/sec).
=
Ki total body dose conversion factor for noble gas radionuclide 1 (mrem /yr per uci/m3), from Table 2-1 '
Li = beta skin dose conversion factor for noble gas radionuclide 1 (mred/yr per uci/m3), from Table 2-1 Mi = gamma air dose conversion factor for noble gas radionuclide 1 (mrad /yr per uCi/m3, from
!. "able 2-1).
1.1 = mrem skin dose per arad gamma air dose (mrem / mrad) 1 17
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0 Hope Creek ODCM 3/28/90 As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.la, following any releases exceeding the above prescribed alarm setpoints. Monitor indications -
(readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate ;
A based on correlation of the monitor reading and monitor sensitivity. The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases. As identified, any electronic spiking monitor responses may
'1 be excluded from the analysis. l l
l NOTE: For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the dose limits of Technical L Specification 3.11.2.la. Provided actual releases L
do not. result in radiation monitor indications L
exceeding alarm setpoint values based on the above criteria, no further analyses are required for ;
demonstrating compliance with the-limits of Specification 3.11.2.la, l
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Hope Creek ODCM 3/28/90 F
Actual meteorological conditions concarrent with the release period or the default, annual average dispernion parameters as presented in Table 2-4 may be used for evaluating the gaseous effluent dose rate.
2.3.2 Rite Boundary Dose Rate - Ragigigline and Particulates Technical Specification 3.ll.2.lb limits the dose rate to 5 1500 mrem /yr to any organ for I-131, I-133, tritium and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The following equation shall be used for the dose rate evaluation:
Do = X/Q
- E (Rio
- Q) i (2.6) where:
Do = average organ dose rate over the sampling time period (mrem /yr) .
X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m3).
= dose parameter for radionuclide 1 (mrem /yr per Rio uCI/m3) and organ o for the child inhalation pathway from Table 2-4.
= average release rate over the appropriate sampling Qi period and analysis frequency for radionuclide i
- - I-131, I-133, tritium or other radionuclide in particulate form with half-live greater than 8 days (uCi/sec).
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Hope Creek ODCM 3/28/90 I
l By substituting 1500 mren/yr for Do and solving for Q, an j allowable release rate for I-131 can be determined.
Based on the annual average meteorological dispersion (See Table 2-3) and the most limiting potential pathway, age :
i group and organ (inhalation, child, thyroid -- Ri = l 1.62E+07 mrem /yr per uCi/m3), the allowable release rate for I-131 is 34.7 uCi/sec. Reducing this release rate by i
a factor of 2 to account for potential dose contributions from other radioactive particulate material and other release points (e.g., Salem), the corresponding release rate allocated to Hope Creek is 17.4 uC1/sec. For a 7-day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 10.5 C1.
Therefore, as long as the I-131 release in any 7-day period do not exceed 10.5 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.
! 20 l
l
Hope Creek ODCM 3/28/90 o
2.4 Moble Gas Effluent Dose calculations - 10 CFR 50 2.4.1 UNRESTRICTED AREA Dose - Moble Gases Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of 5 5 mrad, gamma-air and s 10 mrad, beta-air and the calendar year limits s 10 mrad, gamma-air and 5 20 mrad, beta-air. The limits are applicable separately to each generating station and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses.
D 9
= 3.17E-08
- X/Q
- E (Mi
- Q) i (2.7) and
= 3.17E-08
- X/Q
- E
- Q) (2.8)
Db (Ni i where:
D = air dore due to gamma emissions-for noble gas 9
radionuclides (arad).
Db
= air dose due to beta emissions for noble gas radionuclides (arad).
X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).
Qi = cumulative release of noble gas radionuclide i over the period of interest (uCi).
Mi = air dose factor due to gamma emission from noble gas radionuclide 1 (mrad /yr per uCi/m3, from Table 2-1).
Ni = air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per uci/m3, Table 2-1),
3.17E-08 = conversion factor (yr/sec).
21
Hope Creek ODCM 3/28/90 3.4.3 Simmlified Dese calculation for Moble Games In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified -
dose calculation eqtations may be used for verifying compliance with the dose limits of Technical specification 3.11.2.2 (Refer to Appendix C *or the derivation and justification of this simplified method).
3.17E-08 Dg = ------------
- X/Q
- Me gg
- E Qi (2.9) 0.50 and 3.17E-08
= *
- N,gg (2.10)
Db 0.50 X/Q
- EQi wheret Ma gg = 8.lE3, effective gamma-air dose factor (mrad /yr per uci/m3).
Ne gg = 8.5E3, effective beta-air dose factor (mrad /yr per uci/m3).
= cumulative release for all noble gas radionuclides Qi (uci) .
0.50 = conservatica factor to account for potential variability in the radionuclide, distribution.
Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.
22
f Hope Creek ODCA 3/28/90
' 2.5 Radiciodine and Particulate Dose Calculations - 1C CFR 50
. 2.5.1 tprammTRICTED hamn Dose - Radiciodine and Particulates In accordance with the requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit s 16 mrem to any organ. The following equation shall be used to evaluate the maximum organ dose due to release of I-131, I-133, tritium and particulates with !
half-lives greater than 8 days:
l D aop = 3.17E-08
- W
- SF p *E (Riop
- Q) (2.11) i wheres
- D aop =
dose or dose commitment via all pathways p l and age group a (as identified in Table 2-3) ' to I organ o, including the total body (mrem). '
W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.
X/Q = atmospheric dispersion for. inhalation pathway and H-3 dose contribution via other ,
pathways (sec/m3).
D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).
L Riop =
dose factor for radionuclide 1 (mrem /yr per l
uCi/m3 or m2 - mram/yr per uCi/sec) and organ o from Table 2-4 for each age q aup a and the applicable pathway p as identified in Table 2-3.
Values for R were derived in accordance with y themethodsbeScribedinNUREG-0133.
- cumulative release over the period of interest Qi for radionuclide 1 -- I-131, I-133, H-3 or radioactive material in particulate form with half-life greater than 8 days (uCi).
23
, i l
Hope creek ODCM 3/28/90 )
]
1 SF E
=
annn>- seasonal correction factor to account for j the fraction of the year that the applicable ;
exposure pathway does not exist. j
- 1) For mild and vegetation exposure pathways:
= A six month fresh vegetation and grazing ,
season (May through October). !
= 0.5 .
- 2) For inhalation and ground plane exposure l pathways: ,
= 1.0 '
For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway. Only the controlling ege group as identified in Table 2-3 need be l
evaluated for compliance with Technical Specification i 3.11.2.3. 5 2.5.2 Simplified Dost calculation for Radiciodines and i Particulates ;
In lieu of the individual radionuclide (I-131, I-133 and particulates) dose assessment as presented above, the
-following simplified dose calculation equation may be used 1 for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (Refer to Appendix D for the
! derivation and justification of this simplified method).
l
- W SF p Daax = 3.170-08 *
- RI-131
- EQi (2.12) j where: l 1
% = maximum organ dose (arem). j RIf31 = I-131 dose parameter for the thyroid for the identified controlling pathway.
- 1.05E12, infant thyroid dose parameter with the cow-milk pathway controlling (m2 - mrem /yr per uci/sec).
W = D/Q for radiciodine, 2.87E-10 1/m2.
24 l
l
I Hope Creek ODCM 3/28/90 i I
= cumulative release over the period of interest Qi i for radionuclide 1 -- I-131 or radioactive I material in particulate from with half-life !
greater-than 8 days (uci).
The location of exposure pathways and the maximum organ dose calculation r.ay be based on the available pathways in 1
the surrounding environment of Hope Creek as identified by I the annual land-use census (Technical specification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.
1 l
l I
25
0 Hope Creek ODCM 3/28/90 1
2.4 Gaseous _ Effluent Dome Proiection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge wnen ,
projected doses in 31-days exceed:
0.2 mrad to air from gamma radiation, or 0.4 mrad to air from beta radiation, or 0.3 mrad to any organ of a MEMBER OF THE PUBLIC The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2.
Dose projection are performed at leaTt once per 31-days by f I
the follcwing equations l
Dgp =
(Dg / d)
- 31d (2.17)
Ddp "
(Dd / d)
- 31d (2.18)
)
D maxp =
(Dmax / d)
- 31d (2.19) l l
where:
l Dgp = gamma air dose projection for current 31-day period (mrad).
D = gamma air dose to date for current calendar 9
quarter as determined by equation (2.7) or (2.9) l (mrad).
Dbp = beta air dose projection for current 31-day period (mrad).
= beta air dose to date for current calendar quarter Db as determined by equation (2.8) or (2.10) (mrad).
26 1
Hope Creek ODCM 3/28/90 o
Daaxp =
maximum organ dose projection for current 31-day period (arem).
Daax = maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12)
(arem).
d = number of days in current calendar quarter at the end of the release.
-31d = the number of days of concern.
I e
p I
9
l l
a Hope Creek oDCM 3/28/90 ,
3.0 SPECIAL DOSE ANALYSIS i
3.1 Doses Due to Activities Inside the SITE BOUNDARY l In accordance with Technical Specification 6.9.1.7, the Radioactive Effluent Release Report (RERR) submitted within 60-days after January 1st of each year shall include an assessment of radiation doses from radioactive liquid and .
gaseous effluants to MEMBERS OF THE PUBLIC due to their ;
activities inside the SITE BOUNDARY.
1 l
There is one location on Artificial Island that is accessible to MEMBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities. This location is the Second Sun (visitor's center) located near the contractors gate in the Salem Generating Station.
The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a i t
MEMBER OF THE PUBLIC based on the parameters from Table 2-3 i and 2-hours per visit per year. The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the l time of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available. t 28
i l
, Hope Creek ODCM 3/28/90 l
'o f
3.3 ggigi Deze to ununnas OF TER PUBLIC - 40 CFR 190 l l
The Radioactive Effluent Release Report (RERR) submitted within 60-days after January 1st of each year shall also _ )
include an assessment of the rodiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle courses (including dose i i
contributions from effluents and direct radiation from on-l site sources). For the likely most exposed MEMBER OF THE ;
PUBLIC in the vicinity of Artificial Island, the sources of j exposure need only consider the Salem Generating station and the Hope Creek Generating Station: No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.
The dose contribution from the operation of Salem Generating Stations will be estimated based on the methods t
as presented in the Salem Offsite Dose Calculation Manual (SGS ODCM).
As appropriate for demonstrating / evaluating compliance with
( the limits of Technical Specification 3.11.4 (40 CFR 190),
the results of the environmental monitoring program may be i I used for providing data on actual measured levels of ;
L radioactive material in the actual pathways of exposure.
29
1 i
1 i
i i
_ Hope Creek ODCM 3/28/90 l 9
3.2.1 pffluent Dose calculations For purposes of implementing the surveillance requirements of Technical Specification 3/4.11.4 and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the j Hope Creek Generating Station may be performed using the 1
calculation methods contained within the ODCM; the conservation controlling pathways and locations of Table i i
2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.1) may be used. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.
1 3.2.2 Direct Ernosure Dose Determination Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the i results of the environmental measurements (e.g., TLD, ion chamber measurements) and/or by the use of a radiation '
transport ar.d shielding calculation method. Only during a i
typical condition will there exist any potential for significant on-site sources at Hope Creek that would yield potentially significant off-site doses (i.e.., in excess of 1 mram per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance 30
xugd - _ _ _ _ _ . . _ . _ .
Hope Creek ODCM 3/28/90 0
with 40 CFR 190. However, should a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance.
. 31
- -- ___-_____=-___--_---------_______------ - - --- - - - -
l l
Hope Creek ODCM 3/28/90 4.0 RADIOLOGICAL BWVIRONMENTAL MONITORING PROGRAM 4.1 sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirementL of Appendix A Technical Specification 3.12.
The objectives of the program are:
To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; To determine if the operation of the Hope Creek Generating Station has resulted in any increase in the inventory of long lived radionuclides in the environment; To detect any changen in the ambient gamma radiation levels; and To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment.
The sampling requirements (type of samples *, collection frequency and analysis) and sample locations ara presented in Appendix E.
- WOTE: No public drinking water samples or irrigation water samples are taken as these pathways are not directly effected by liquid affluents discharged from Hope Creek Generating Station 32 l
4 i
L i
i Hope Creek ODCM 3/28/90 l t
l' 4.2 Interlaboratory Connarison Procram j L
l Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory comparison.
Participation in an approved Interlaboratory Comparison I Program provides a check on the preciseness of measurements of radioactive materials in' environmental samples. A l
summary of the Interlaboratory Comparison Program results .)
I will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specifications 6.9.1.7. )
l l
r i
l.
l l:
33 1
l Hope Creek ODCM 3/28/90 FIGURE 1-1 LIQUID RADWASTE TREATMENT SYSTEM COOLING TOWER -
BASIN d6 AL COLLECTOR
+ -
TANKS (2)
EQUIPMENT EQUIPMENT EQUIPMENT
+ DRAIN FILTER p DRAIN DEMINERLIZER
> DRAIN SAMPLE >
TANKS (2)
SURGE
+
TANK CONDENSATE STORAGE -
TANK AL dk FI40R FLOOR
& DRAIN FLOOR FLOOP. DRAIN COLLECTOR p DRAIN - q,> T' RAIN DFMINERLIZER
--* SAMPLE ->
TANKS (2) FILTER l TANKS (2)
CHEMICAL DECONTAMINATION --> VAPOR TO
> WASTE SOLUTION SOUTH PLANT TANK d' D EVAPROATOR VENT
> BOTTOMS TO SOLID WASTE DETERGENT DETERGENT 373pq,
> DRAIN -
DRAIN >
TANKS (2) FILTER RE 4861 LOG: RE = EFFLUENT RADIATION MONITOR RE 4861 = LIQUID RADWASTE MONITOR 8817 8817 = COOLING TOWER BLOWDOWN MONITOR T
TO DELAWARE RIVER
Hop 3 Crook ODCM Rovision 11 3/28/90 s
IE d
t
$k s-b f 5
I a
E
$5 5
$I$ El vu s a
gem
.e di f a E 9
hk 8 :
gE EE gi tie -
Ej! j c*i
.o.
lg d
S seg is t
b le s
~
h Ih g- s B se .
l 1
g N
<!/ dig s
i s
8 y
8
. k
.e
, Hope Creek ODCM 3/28/90 ;
l l
TABLE 1-1 PARAMETERS FOR LIQUID ALARN SETPOINT DETERMINATION Actual Default Egrameter Value Value Units Comments MPCe Calculated 5.00E-5 uCi/ml* Calculated for each batch I to be released 1 MPC I-131 3.0E-08 N/A uCi/ml I-133 MPC conservatively used for HC CTBD and 1 liquid radwaste monitor i setpoint ,
4 Ci Measured N/A uCi/ml Taken from gamma spectral analysis of liquid i effluent l MPCi As N/A uCi/ml Taken from 10 CFR 20, Determined Appendix B, Table II, i Column 2 CTBD As 1.20E4 gpm Cooling tower blowdown Determined discharge i l
RR- As 176 gpm or Determined prior to '
Determined 1300 gpm (CST) release; release rate ;
can be adjusted for Technical Specification '
compliance SP !
A) RE4861 Calculated 3.41E-03 uCi/ml. Default alarm setpointor l more conservative values !
RE8817 Calculated 5.00E-05 uCi/ml may be used as deemed appropriate and desirable for ensuring regulatory compliance and for main-taining releases ALARA L 3 B) RE4861 Calculated 4.62E-04 uCi/ml These setpoints are for {
i condensate storage tank !
RE8817 Calculated 5.00E-05 uCi/ml releases
- See Appendix A for basis 36 l
+ - . . .. . .
- ~ _ . - .
Hope Creek ODCM 3/28/90 TABLE 1-2 SITE RELEATED INGFJTION DOSE COMMITMENT FACTOR, Ago (FISH AND INVERTEBRATE CONSUMPTION)
(mrem /hr per uCi/ml)
Nuclide Bono Liver T. Body Thyroid Kidney Lung GI-LLI H-3 -
2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2 . 8 2 L'- 1 C-14 1.45Es4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 4 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 P-32 4.69E+6 2.91E+5 1.81E+5 - - -
5.27E+5 Cr-51 - -
5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 l
Mn-54 -
7.06E+3 1.35E+3 -
2.10E+3 -
2.16E+4 Mn-56 -
1.78E+2 3.15E+1 -
2.26E+2 -
5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 - -
1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 - -
5.00E+4 6.32E+5 l Co-57 -
1.42E+2 2.36E+2 - - -
3.59E+3
.Co-58 -
6.03E+2 1.35E+3 - - -
1.22E+4 1 Co-60 -
1.73E+3 3.82E+3 - - -
3.25E+4 ;
Ni-63 4.96E+4 3.44E+3 1.67Et3 - - -
7.18E+2 1 Ni-65 2.02E+2 2.62E+1 1.20E+1 - - -
6.65E+2 i Cu-64 -
2.14E+2 1.01E+2 -
5.40E+2 -
1.83E+4-Zn-65 1.61E+5 5.13E+5 2.32E+B -
3.43E+5 -
3.23E+5 Zn-69 3.43E+2 6.56E+2 4.56E+1 -
4.26E+2 -
9.85E+1 l Br-82 - -
4.07E+0 - - -
4.67E+0 1 Br-83 - -
7.25E-2 - - -
1.04E I Br-84 - -
9.39E-2 - - -
7.37E-7 !
Br-85 - -
3.86E-3 - - - -
Rb-86 -
6.24E+2 2.91E+2 - - -
1.23E+2 Rb-88 -
1.79E+0 9.49E-1 - - -
2.47E-11 Rb-89 -
1.19E+0 8.34E-1 - - -
6.89E-14 Sr-SS 4.99E+3 -
1.43E+2 - - -
8.00E+2 Sr-90 1.23E+5 -
3.01E+4 - - -
3.55E+3 Sr-91 9.18E+1 -
3.71E+0 - - -
4.37E+2 Sr-92 3.48E+1 -
1.51E+0 - - -
6.90E+2 Y-90 6.06E+0 -
1.63E-1 - - -
6.42E+4 Y-91m 5.73E-2 -
2.22E-3 - - -
1.68E-1 ..
Y-91 8.88E+1 -
2.37E+0 - - -
4.89E+4 Y-92 5.32E-1 -
1.56E-2 - - -
9.32E+3 Y-93 1.69E+0 -
4.66E-2 - - -
5.35E+4 Zr-95 1.59E+1 5.11E+0 3.46E+0 -
8.02E+0 -
1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 -
2.68E-1 -
5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 -
2.46E+2 -
1.51E+c Nb-97 3.75E+0 9.49E-1 3.46E-1 -
1.11E+0 -
3.50E+3 MD-99 -
1.28E+2 2.43E+1 -
2.89E+2 -
2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.662-1 -
5.56E-1 1.79E-2 2.17E+1 Tc-101 1.33E-2 1.92E-2 1.88E-1 -
3.46E-1 9.81E-3 5.77E-14
l s Hope Creek ODCM 3/28/90-
- o; TABIE 1-2' (cont'd)
SITE RELEATED INGESTION DOSE COMMITMENT FACTOR, Aio (FISH AND INVERTEBRATE CONSUMPTION)
(arem/hr per uCi/ml)
Nuclide- Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ru-103: 1.07E+2 -
4.60E+1 -
4.07E+2 -
1.25E+4 Ru-105 8.89E+0~ -
3.51E+0 -
1.15E+2 -
5.44E+3' Ru-106 1.59E+3 -
2.01E+2 -
3.06E+3 -
1.03E+5 Rh-103m - - - - - - -
Rh-106 - - - - - - -
Ag-110m 1.56E+3 1.45E+3 8.60E+2 -
2.85E+3 -
5.91E+5 Sb-124 2.77E+2 F.23E+0 1.10E+2 6.71E-1 -
2.15E+2 7.86E+3 Sb-125- 1.77E+2 .1.98E+0 4.21E+1 1.80E-1 -
1.36E+2 1.95E+3 Te-125m - 2 .17 E+ 2 ' 7.86E+1 2.91E+1 6.52E+1 8.82E+2 -
8.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23E+3 -
1.84E+3 Te-127 8.90E+0~ 3.20E+0 1.93E+0 -6.60E+0 3.63E+1 -
7.03E+2 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 -
.4.69E+3 Te-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+1 -
1.92E+0 Te-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 -
6.80E+3 Te-131 1.59E+0 6.66E-1 5.03E-1~ 1.31E+0 6.99E+0 -
2.26E-1 Te-132 2.04E+2 1.32E+2- 1.24E+2 1.46E+2 2.27E+3 -
6.24E+3 I-130- 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 -
1.01E+2 I-131 2.18E+2 3.12E+2 1.79E+2' 1.02E+5 5.35E+2 -
8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 -
5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 '1.90E+4 2.26E+2 -
1.16E+2.
I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 -
-1.32E-2 I-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 -
6.87E+1
'Cs-134 6.84E+3 1.63E+4 1.33E+4 -
5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 - 1.57E;'~-2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 -
4.07E+3 1.35E+3 2.32E+2-Cs-138 6.07E+0 1.20E+1 5.94E+0 -
8.81E+0 8.70E-1 5.12E-5; Ba-139 7.85E+0 '5.59E-3 2.30E-1 -
5.23E-3 3.17E-3 1.39E+1' Ba-140 1.64E+3 2.06E+0 1.08Et2 -
7.02E-1 1.18E+0 3.38E+3 Ba-141- 3.81E+0 2.88E-3 1.29E-1 -
2.6BE-3 1,63E-3 1.80E Ba-142 1.72E+0 1.77E-3 1.08E-1 -
1.50E-3 1.00E-3 2.43E-18 La-140 1.57E+0 7.94E-1 2.10E-1 - - -
5.83E+4-
'La-142 8.06E-2 3.67E-2. 9.13E-3 - - -
2.68E+2
- Ce-141 3.43E4 9 2.32E+0 2.63E-1 -
1.08E+0 -
8.86E+3
- Ce-143 6.04E-1 4.46E+2 4.94E-2 -
1.97E-1 -
1.67E+4 lCe-144- 1.79E+2 7.47E+1 9.59E+0 -
4.43E+1 -
6.04E+4 Pr-143 5.79E+0. 2.32E+0 2.87E-1 -
1.34E+0 -
2.54E+4 Pr-144 1.90E-2 7.87E-3 9.64E-4 -
4.44E-3 -
2.73E-9 Nd-147 3.96E+0 4.58E+0 2.74E-1 -
2.68E+0 -
2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 - - -
2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 -
1.08E-2 -
7.11E+2 1
.. - . - . - . . ~ -
x i
Hope Cr:0k ODCM 3/28/90- 2 0 ,
l TABLE 1-3 BIOACCUMULATION FACTORS 1 (pCi/kg per pC1/ liter)*
ELEMENT SALTWATER FISH SALTWATER INVERTEBRATES
-H- 9.0E-01 9.3E-01 H
-C 1.8E+03 1.47.+03 R
< NA 6.7E-02 1.9E-01
.-P.
'n CR. 4.0E+02 2.0E+03 MN 5.5E+02 4.0E+02 FE- 3.0E+03 2.0E+04 CO 1.OE+02~ 1.OE+03 HI 1.0E+02 2.5E-02 CU 6.7E+02 1.7E+03.
ZN 2.0E+03 5.0E+04 U
-BR 1.SE-02 3.1E+00 l RB' 8.3E+00~ 1.7E+01 -
SR- 2.0E+00 2.0E+01 Y< J.5E+01 1.0E+03 ;
ZR- 2.0E+02 8.0E+01~ l NB- 3.0E+40 1.0E+02-MO' 1.0E+01. 1.0E+01 1
TC 1.0E+01 5.0E+01 ,
. RU - 3.0E+00 1.0E+03
.RH 1.OE+01 2.OE+03
'AG 3.3E+03 3.3E+03 Sb 4.0E+01 5.4E+00 TE' 1.0E+01 1.0E+02
, .I' 1.0E+01 5.0E+01 L' CS 4.0E+01 2.5E+02 L BA 1.0E+01 1.0E+02 l ?lA 2.SE+01 1.OE+03 l .CE' 1.0E+01 6.0E+02 L PR 2.5E+01 1.0E+03 ND '2.5E+01 1.0E+03 .!
.W' 3.0E+01 3.0E+01-m-
NPi 1.0E+01 1.0E+01 -!
,%I
, 'o- .
Values-in this table are taken from Regulatory Guide'1.109 except for phosphurus (fish) which is-adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL-50564,'Rev. 1, October 1972.
39 4-
i Hope Creek ODCM.3/28/90-FIGURE-2-1 GASEOUS RADWASTE TREATMENT SYSTEM .4 Main or !
Auxiliary Steam SJAE r~~ ~ - - - - - - - - - - --
7 Offgas >
'l l } l 2
Preheater !~- I Recombiner Recombiner l Condenser l Condenser - l 'l Offgas Typical of 2 Recombiner Packages Holdup Pipes 1
r- -'- - - - - - - - - - - - - - - - 1
-l Cooler Reheater Guard 'l Condenser Bed l l l i
.l To North l: HEPA Filtler Absorber -
l Plant Vent. Train l 9
(Figure 2-2) l ,
L _ _ Ambient
_ _ _ _Charcoal S '
_ _ _ystem ____ J 1
l i
40
Pr - j p w, f , -1 ,
i i
\ '
( '
,X
. . . Hope Creek ODCM-3/28/90; y 30 Ei# o i l FIGURE 2-2 ,
VENTILATION EXHAUST TREATMENT SYSTEM RE*
RE Gasecus Radwaste i
. Treatment System 4573B el N, (from Figure'2-1)
North !
fv ' ' --Plant Vent
. Untreated Ventilation I A ' Air Sources l
l
'l Radwaste Decon.
Evaporator L' Reactor Building R H l- . Evaporator I l (Typ. of 3) RE 1
Auxiliary Building 4875B l
.Radwaste Area R li --
South Ventilation Area- Plant (Typ. of 3) Vent Condensate Domineralizer Room Air Pipe Chase Air --
R --
H -
C --
H --
Feedwater Heater Room Air Untreated Ventilation
' Air Sources ~ RE (Recirculation) 4811A 4 Reactor Building Air H C H C H~ FRVS System >
(Type. of 6) (Typ. of 2) Vent
~
- Legend:' R= Roughing' Filter C- Charcoal Filter H.= HEPA Filter
, RE'= Effluent-Radiation Monitor
- -- This Foot-Treatment Monitor is not effluent monitor as designed by the RETS.
41
9 '.
1 Hope Creek OLCM 3/28/90 w
TABLE 2-1 DOSE. FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air.
Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni (mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per Radionuclide uCi/m3) uCi/m3) uCi/m3) uCi/m3 Kr-83m 7.56E-02 -----------
1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04-Kr-90 1.56E+04 7.29E+03 1.63E+40 7.83E+03.
Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-153 1.81E+03 1.86E+03 1.92E+03. 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04
'Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 42 l
l
S Hope Creek ODCM 3/28/90 lo TABLE 2-2 PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION HOPE CREEK Actual Default y Parameter Value Value Units Comments
.h X/Q Calculated 2.67E sec/m3 From FSAR Table 2.3-31 0.5 mile, N
VF (NPV) Measured 41900 ft /3 min Maximum Operation VF (SPV) Measured 440,180 ft /3 min Maximum Operation VF (FRVS)' Measured 9000 ft /3 min Maximum Operation AF (NPV) Coordinated 0.2 Unitless Administrative with SGS allocation factor to ensure releases-
-AF'(SPV) '
0.2 Unitless- do not exceed release rate limit AF (FRVS) 0.1 Unitless C1 Measured N/A uCi/cm 3 Ki .Nuclide N/A (mram/yr Table 2-1 Specific per uCi/m 3 Li Nuclide N/A (arem/yr . Table'2 Specific per uCi/m 3)
- M. i Nuclide. N/A mrad /yr Table 2-1 Specific per uci/m 3 Sv: NPV Calculated 2.43E-4 uCi/cc Default alarm SPV Calculated 2.31E-5 uCi/cc Setpoints; more FRVS . Calculated 5.56E-4 uCi/cc conservative valves may be used as deemed appropriate for ensuring ALARA &
regulatory com-pliance SV (Q) NPV Calculated 4.8E3 uCi/sec Determined by SPV Calculated 4.8E3 uCi/sec multiplying set-FRVS Calculated 2.4E3 uCi/sec point (uCi/cc) times vent flow rates (cc/sec) 43
l 1.
, __ Hope Creek ODCM 3/28/90 L
o TABLE 2-3 CONTROLLING LOCATIONS, PATHWAYS AND ATOMSPHERIC DISPERSION FOR DOSE. CALCULATIONS
- Controlling X/Q D/Q Tech Soec Location Pathway (s) hae Gre'in (sec/m3) (1/m2) 3.11.2.la Site Boundary Noble Gases N/A 2.67E-06 N/A 0.5 Mile, N direct exposure 3.11.2.lb Site Boundary Inhalation Child 2.67E-06 N/A 0.5 Mile, N 3.11.2.2 ' Site Boundary Gamma-Air N/A 2.67E-06 N/A 0.5 Mile, N Beta-Air '
3.11.2.3 Residence / Milk, ground Infant 7.2E-08 2.87E-10 Dairy - 4.9 plane and ;
Miles, W inhalation ,
6.9.1.7 Second Sun Direct exposure N/A 8.22E-06 N/A 0.21 Miles, and inhalation SE e The' identified controlling. locations, pathways and atomspheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.
g-I o
44 1
l 1
4 i
Hope Creek ODCM 3/28/90 o
n.+
Table 2-4 1 Pathway Dose Factors - Atmospheric Releases R(lo), Inhalation Pathway Dose Factors - ADULT (mrem /yr per uC1/m3)
Nuclide Bone Liver Thyroid Kidney Lung 'GI-LLI T. Body H-3 -
1.26E+3 1.26E+3 1.26E+3- 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 '3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 !
P-32 1.32E+6 7.71E+4 - - -
8.64E+4. 5.01E+4 Cr-51 5.95E+1 '
2.28E+1 1.44E+4 3.32E+3 1.OOE+2 Mn-54 -
3.96E+4 -
9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 - -
7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 - -
1.02E+6 1.88E+5 1.06E+4 Co-57 -
6.92E+2 - -
3.70E+5 3.14E+4 6.71E+2 Co-58 -
1.58E+3 - -
9.28E+5 1.06E+5 2.07E+3
- Co-60 -
1.15E+4 - -
5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 - -
1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+5 -
6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 -
1.35E+5 - - -
1.66E+4 5.90E+4.
Sr-89 3.04E+5 - - -
1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 - - -
9.60E+6 7.22E+5 6.10E+6 Y-91. 4.62E+5 - - -
1.70E+6 3.85E+5 1.24E+4
\ l l- Zr 1.07E+5 3.44E+4 -
5.42E+4 1.77E+6 1.50E+5 2.33E+4 l l
- Nb-95 1.41E+4 7.82E+3 -
7.74E+3 5.05E+5 1.04E+5 4'.21E+3 l Ru-103 l'.53E+3 - -
5.83E+3 5.05E+5 1.10E+5 6.58E+2-
- Ru-106 6.91E+4 - -
1.34E+5 9.36E+6 9.12E+5 8.72E+3 l- l Ag-110m 1.08E+4 1.OOE+4 -
1.97E+4 4.63E+6 3.02E+5 5.94E+3'
' Sb-124 3.12E+4 5.89E+2 7.55E+1 -
2.48E+6 4.06E+5 1.24E+4 ,
- Sb-125 5.34E+4 5.95E+2 5.40E+1 -
1.74E+6 1.01E+5 1.26E+4 1 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 -1.50E+5 1.57E+3 l
' Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 l I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -
6.28E+3 2.05E+4 H C3-134 3.73E+5. 8.48E+5 -
2.87E+5 9.76E+4 1.04Et4 7.28E+5
]
Cc-136 3.90E+4 1.46E+5 -
8.56E+4 ~ 1.20E+4 1.17E+4 1.10E+5 l C3-137 4.78E+5 6.21E+5 -
2.22E+5 7.52E+4 8.40E+3 4.28E+5
- Ba-140 3.90E+4 4.90E+1 -
1.67E+1 1.27E+6 2.18E+5 2.57E+3
_ C3-141 1.99E+4 1.35E+4 -
6.26E+3 3.62E+5 1.20E+5 1.53E+3 Co-144 3.43E+6 1.43E+6 -
8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 -
2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Nd-147 5.27E+3 6.10F&3 -
3.56E+3 2.21E+5 1.73E+5 3.65E+2 3
45 i
L l
Hope Creek ODCM'.,/28/90 - -
Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - TEENAGER (arem/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney ~ Lung GI-LLI T. Body H-3 -
1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+5 - - -
9.28E+4 7.16E+4 Cr-51 - -
7.50E+1 3.07E+1 2.10E+4 3.OOE+3 1.35E+2 Mn-54 -
5.11E+4 -
1.27E+4 1.96E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 - -
1.24E+5 6.39E+3 5.54E+3 Fe-59 1.~59E+4 3.70E+4 - -
1.53E+6 1.78E+5- 1.43E+4-Co-57 -
6.92E+2 - -
5.86E+5 3.14E+4 9.20E+2 Co-58 -
2.07E+3 - -
1.34E+6 9.52E+4 2.78E+3 Co-60 -
1.51E+4 - -
8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 - -
3.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 -
8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 -
1.90E+5 - - -
1.77E+4 8.40E+4 Sr-89 4.34E+5' - - -
2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 - - -
1.65E+7 7.65E+5 6.68E+6 Y-91: 6.61E+5- - - -
2.94E+6 4.09E+5 1.77E+4 JZr-95' 1 46E+5 4.58E+4 -
6.74E+4 2.69E+6 1.49E+5 3.15E+4
'Nb-95 1.86E+4 1.03E+4 -
-1.OOE+4 7.51E+5 9.68E+4' 5.66E+3
.Ru-103 -2.10E+3 - -
7.43E+3 7.83E+5 1.09E+5 8.96E+2-
'Ru-106- 9.84E+4 - -
1.90E+5 1.61E+7. 9.60E+5 1.24E+4 Ag-l'10m 1.38E+4 1.31E+4 -
2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -
3.85E+6 3.9CE+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -
2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3- -
5.36E+5 7.50E+4 6.67E+2
'Te-127m '1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.2SE+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 -
6.49E+3- 2.64E+4 Cs-134 '5.02E+5 1.13E+6 -
3.75E+5 1.46E+5 9.76E+3 5.49E+5
- Cs-136 5.15E+4 1.94E+5 -
1.10E+5- 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 -
3.04E+5 1.21E+5 8.48E+3 3.11E+5
' Ba-140 5.47E+4 6.70E+1 -
2.28E+1 2.03E+d 2.29E+5 3.52E+3
~ Ce-141 -- 2.84E+4 1.90E+4 -
8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 -
1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 -
3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 -
5.02E+3 3.72E+5 1.82E+5 5.13E+2
,, 46
f '
w s
hop
- g ODCg 3/28/
g '
_aan ~ :
m w.. aas : -
a
.Nuclid* Be:
'H-3
p.32 2. Pathway Dose FactTable 2-4
'Cr-51 :R(io), (cont'd) 1Mn 541 Nuclid Inhalation . Pathway Dors -Atmosph eases- C' ye-55; 4 . . . .e Bone (mrem /yr per Liver (
Fe*59 1 2
- - Thyroi uCi / m3)ose Factors - IN 1 Co*57.
t P-32 2 65E+4 6.47E+2 6.47E+2
.d .. Kidne ..y . .Lun
. .g
~
.Co.58 Cr-51 2.03E+6 5.31E+3 .
GI-LLI.
Co-60, 1.12E+5 5.31E+3 6 47E+2 . .. ~. S
- - 5,31E+3 6 47E+2 .
Wi-63' N Mn-54 -
5.31E+3' 6.47E+2 l
Fe-55 - 5.75E+1 6
'Zn-65 ye-59 1 32E+1 5.31E+3.~5 2.53E+4
) ~1.97E+4 -
1 28E+4 1.61E+4 7, Rb-86 Co-57 1.36E+4 1.17E+4 3.57E+2 t
2.35E+4 4 98E+3 8.
'Sr',99 - --
1.OOE+6 Sr 90 i Co-58 6.51E+2 - -
8.69E+4 7.06E+3 4.
1 -91' Co-60 -
1.02E+6 1.09E+3. 3 ". ;
Ni-63 -
1.22E+3 - 3.79E+5 2 48E+4 9.4 f%r,95' Zn-65 3.39E+5- 8.02E+3 - - 4 86E+3 -6.4 '
'. B b ,9 5 1 93E+4 2 04E+4 - -
.7.77E+5 Ru-103 Rb-86 6.26E+4 SrkB9 -
'4 51E+6' ~1 11E+4 =1 81 Rg,106 3 25E+4- .2 09E+5 3.19E+4 E1 18
~
Sr-90 '3 98E+5 1.90E+5 - '6 47E+5 2 42E+3 1.16 Y-91 4 09E+7 A9'1 5 88E+5 5 14E+4'~3 111 Sb,12 - - -
1 iSb 12 Zr-95 -
2 03E+6 3.04E+3- 8.82E T*'l 5 Nb-95 1 15E+5 -
'1.12E+7 ~ 6.'40E+4 1.14E
'Ru-103 1.57E+4 2.79E+4 - 2.45E+6 1.31E+5 J 2.59E-T**1 Ru-106 2.02E+3 6.43E+3 7.03E+4 3 11E+4 1
8 68E+4 1.57E4
' i T*'N Ag-110m - --
4 72E+3 1~.75E+6-1~ -
4 24E+3 - 4.' 79E+5 1.27E+4- 2 17E+4 Sb-124 9.98E+3 ,2.03E+
Cs-13 Sb-125 3.79E+4 7 22E+3 1.07E+5 5 52E+5
- 1 16E+7 -1.61E+4 3.'78EM iCs* Te-125m 5 17E+4 5.56E+2 1 64E+5 6'79E+1 4.76E+3 4.77E+2 1.01E+2 1.09E+4 1.09E+4
'Cs % 1 1 99E+3 6 23E+1 3 67E+6
.Ba-l Te-127m -
2.65E+6 3.30E+4 s
Te-129m- 1.67E+4 1.62E+3 C#~1 I-131 1.64E+6 5 91E+4 5 OOE+3 1 41E+4 6.90E+3 4 47E+5 1.47E+4 1.20E+4 Cs-134 3.79E+4 6.09E+3 4.87E+3 1 29E+4 1.09E+4 Ce* 5.47E+3 3.75E+4 Pr- 3.96E+5 4 44E+4 3 18E+4 1 31E+6 6.58E+2 Cs-136 7.03E+5 1.48E+7 2.73E+4
'Ndi Cs-137 5 18E+4 1 68E+6 4 83E+4 6.90E+4 2.07E+3 Ba-140 5.49E+5 1.35E+5 1.90E+5
- 7.97E+4 1 06E+3 2.23E+3 Ce-141 5.60E+4 6 12E+5 1.33E+3 1.96E+4 2.77E+4 5.60E+1 5.64E+4 7 45E+4 W -
1.72E+5 1 18E+4 Ce-144 1.67E+4 1.43E+3 Pr-143 3.19E+6 1.34E+1 7.13E+4 5.25E+3 1.60E+6 3.84 1 33E+3 5.29E+4-Nd-147 1 40E+4 1 21E+6 5 17E+5 2 *E+4 2.W 4 55E+
- 7. 9d D
- 5. 24 EM -
" ' '4 !
4 Hope Creek ODCM 3/28/90c ,
9 ,
Table 2-4-(cont'6)
Pathway Dose Factors - Atmospheric Releases R(lo), Inhalation Pathway Dose Factors - CHILD (areaa'r per uci/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body i H-3 -
1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3' C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P 2.60E+6 1.14E+5 - - -
4.22E+4 9.88E+4'
. Cr-51 - -
8.55E+1 2.43E+1 1.70E+4 1.08E+3- 1.54E+2-Mn-54 -
4.29E+4 -
1.OOE+4 1.58E+6 2.29E+4 9.51E+3 !
Fe-55 4.74E+4- 2.52E+4 - -
1.11E+5 2.87E+3 7.77E+3 i Fe-59 2.07E+4 3.34E+4 - -
1.27E+6 7.07E+4 1.67E+4 l
-Co-57 -
9.03E+2 - -
5.07E+5 1.32E+4 1.07E+3 H l
Co-58 -
1.77E+3 - -
1.11E+6 3.44E+4 3.16E+3 l
- i. Co-60 -
1.31E+4 - -
7.07E+6 9.62E+4 2.26E+4 q L Ni-63 8.21E+5 4.63E+4 - -
2.75E+5 6.33E+3 2.80E+4 L Zn-65 4.26E+4 1.13E+5 -
7.14E+4 9.95E+5 1.63E+4 7.03E+4
! Rb-86 -
1.98E+5 - - -
7.99E+3 1.14E+5 Sr-89 5.99E+5 - - -
2.16E+6 1.67E+5 1.72E+4 l Sr-90 1.01E+8 - - -
1.48E+7 3.43E+5 6.44E+6 !
Y-91 9.14E+5 - - -
2.63E+6 1.84E+5 2.44E+4 l
-2r-95 1.90E+5 4.18E+4 -
5.96E+4 2.23E+6 6.11E+4 3.70E+4 l Nb-95 2.35E+4 9.18E+3 -
8.62E+3 6.14E+5 3.70E+4 6.55E+3 L Ru-103 '2.79E+3- - -
7.03E+3 6.62E+5 4.48E+4 .1.07E+3 I L
Ru-106 1.36E+5 - -
1.84E+5 1.43E+7 4.29E+5 1.69E+4' l Ag-110m 1.69E+4 1.14E+4 -
2.12E+4 5.48E+6 1. OOE+ 5 - 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -
3.24E+6 1.64E+5 2.OOE+4 Sb-125 19.84E+4 7.59E+2 9.10E+1 -
2 32E+6 4.03E+4 2.07E+4 T3-125m 6.73E+3 -2.33E+3 1.92E+3 -
4.77E+5 3.38E+4 9.14E+2 P T3-127m- 2.49E+4- 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 TG-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 ,
I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 -
2.84E+3 2.73E+4 C3-134 6.51E+5 1.01E+6 -
3.30E+5 1.21E+5 3.85E+3 2.25E+5 C3-136' 6.51E+4 1.71E+5 -
9.55E+4 1.45E+4 4.18E+3 1.16E+5 CO-137 9.07E+5 8.25E+5 -
2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 .7.40E+4 6.48E+1 -
2.11E+1 1.74E+6 1.02E+5 4.33E+3 Co-141 3.92E+4 1.95E+4 -
8.55E+3 5.44E+5 5.66E+4 2.90E+3 i
JC3-144 6.77E+6 2.12E+6 -
1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.~85E+4 5.55E+3 -
3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1.08E+4 8.73E+3 -
4.81E+3 3.28E+5 8.21E+4 6.81E+2 47 4
< -.--.-----,._--_a ..-e -,-
k C!
Hope Creek ODCM 3/28/90 Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - INFANT (arem/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI- T. Body H -
6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 6.31E+3 5.31E+3- 5.31E+3 5.31E+3 P-32 2.03E+6 1.12E+5 - - -
1.61E+4 7.74E+4-Cr-51 - -
5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1
. Mn-54 -
2.53E+4 -
4.98E+3 1.OOE+6 7.06E+3 4.98E+3 Fe-55 1.97E+4 1.17E+4 - -
8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 - -
1.02E+6 2.48E+4 9.48E+3 Co-57 -
6.51E+2 - -
3.79E+5 4.86E+3 6.41E+2-Co-58 -
1.22E+3 - -
7.77E+5 1.11E+4- 1.82E+3 Co-60 -
8.02E+3 - -
4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39Er5 2.04E+4 - -
2.09E+5 2.42E+3; 1.16E+4 Zn-65 1.93E+4 6.26E+4 -
3.25E+4 6.47E+5 5.14E+4 '3.11E+4-Rb-86 -
1.90E+5 - - -
3.04E+3 8.82E+4 Sr-89 3.98E+5 - - - '
2.03E+6 6.40E+4 1.14E+4 Sr-90 '4.09E+7 - - -
1.12E+7 1.31E+5 2.59E+6' Y-91 5.88E+5 - - -
2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 -
3.11E+4 1.75E+6 2.17E+4 '2.03E+4
' Nb-95 1.57E+4 6.43E+3 -
4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 - -
4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 - -
1.07E+5. 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3. -
1.09E+4 3.67E+6 3.30E+4 5.OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -
2.65E+6 5.91E+4 1.20E+4
- Sb-125 5.17E+4 4.77E+2 6.23E+1 -
1.64E+6- 1.47E+4 1.09E+4-Te-125m 4.76E+3 1.99E+3 1.62E+3 -
'4.47E+5 1.29E+4 6.58E+2 Te-127m. 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3
- Te-129m. 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+31 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -
1.06E+3 1.96E+4 Cs-134 3.96E+5 7.03E+5 -
1.90E+5 7.97E+4- 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -
5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137- 5.49E+5 6.12E+5 -
1.72E+5 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 -
1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 -
5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-144 3.19E+6 1.21E+6 -
5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 -
1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 -
3.15E+3 3.22E+5 3.12E+4 5.OOE+2 48
Hope Creek ODCM'3/28/90-on Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - ADULT (arem/yr per uci/m3) for H-3 and C-14 (m2
- mrem /yr per,uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -
7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P 1.71E+10 1.06E+9 - - -
1.92E+9- 6.60E+8 Cr-51 - -
1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -
8.40E+6 -
2.50E+6 -
2.57E+7 1.60E+6 Fe-55 2.51E+7 1.73E+7 - -
9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.OOE+7 - -
1.95E+7 2.33E+8- 2.68E+7 Co-57' -
1.28E+6 - - -
3.25E+7 2.13E+6 Co-58 -
4.72E+6 - - -
9.57E+7 1.06E+7 Co-60 -
1.64E+7 - - -
3.08E+8 3.62E+7.
Ni-63 6.73E+9 4.66E+8 - - -
-9.73E+7 2.26E+8
-Zn 1.37E+9' 4.36E+9 -
2.92E+9 -
2.75E+9. 1.97E+9 1Rb-86 -
2.59E+9 - - -
5.11E+8 1.21E+9 Sr 1.45E+9 - - - -
2.33E+8 4.16E+7 Sr-90 4.68E+10 - - - -
1.35E+9 1.15E+10-
.Y-91 8.60E+3 - - - -
4.73E+6 2.30E+2 Zr-95 9.46E+2 3.03E+2 -
4.76E+2 -
9.62EtS' 2.05E+2 Nb-95 8.25E+4 4.59E+4- -
4.54E+4 -
2.79E+8 2.47E+4-
~Ru-103. 1.02E+3 - -
3.89E+3 -
1.19E+5 4.39E+2
-Ru-106- -2.04E+4 - -- 3.94E+4 -
1.'32E+6 2.58E+3
- Ag-110m .5.83E+7 5.39E+7 -
1.06E+8 -
2.20E+10 3.20E+7 Sb-124 2.57E+7- 4.86E+5 6.24E+4 -
2.00E+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 -
1.58E+7 2.25E+8 4.86E+6 Te-125m- 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -
6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -
1.54E+8 ~5.58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -
3.04E+8 9.57E+6 I-131. 2.96E+8 4.24E+8 1.39E+11 7.27E+8 -
1.12E+8 2.43E+8' Cs-134 5.65E+9 1.34E+10 -
4.35E+9 1.44E+9 2.35E+8 1.10E+10
'Cs-136 2.61E+8 1.03E+9 -
5.74E+8 7.87E+7 1.17E+8 7.42E+8'
'Cs-137 7.38E+9 1.01E+10 -
3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ba-140 2.69E+7 3.38E+4 -
1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ce-141 4.84E+3 3.27E+3- -
1.52E+3 -
1.25E+7 3.71E+2 Ce-144 3.58E+5 1.50E+5 -
8.87E+4 -
1.21E+8 1.92E+4 Pr-143 .1.59E+2 6.37E+1 -
3.68E+1 -
6.96E+5 7.88E+0 Nd-147 9.42E+1 1.09E+2 -
6.37E+1 -
5.23E+5 6.52E+0 49
a- Hope Creek ODCM 3/28,'90 l
Table 2-4 (cont'd).
Pathway Dose Factors - Atmospheric-Releases ;
-R(io), Grass-Cow-Milk-Pathway Dose Factors - TEENAGER
? (mrem /yr per uC1/m3) for H-3 and C-14 -
(m2
- mrem /yr per uCi/sec) for'oth cs Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body .
H-3' -
9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5- <
P-32 3.15E+10 1.95E+9 - - -
2.65E+9 1.'22E+9 ,
Cr-51 - -
2.78E+4 1.10E+4 7.13E+4 8.40E+6- 5.OOE+4 Mn-54 -
1.40E+7 -
4.17E+6 -
2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 - -
2.OOE+7 1.37E+7 7.36E+6 ,
Fe-59 5.20E+7 1.21E+8 - -
3.82E+7 2.87E+8 4.68E+7-Co-57 -
2.25E+6 - - -
4.19E+7 3.76E+6 Co-58 -
7.95E+6 - - -
1.10E+8 1.83E+7 Co-60' -
2.78E+7 - - -
3.62E+8 6.26E+7-
.Ni-63 1.18E+10 8.35E+8 - - -
1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 -
4.68E+9 -
3.10E+9 3.41E+9
'Rb-86 -
4.73E+9 - - -
7.OOE+8 2.22E+9- -i l' Sr-89 2.67E+9 - - - -
3.18E+8 7.66E+7 "
Sr-90' 9.92E+7 - - -
9.60E+6 7.22E+5 '6.10E+6 l Y-91 1.58E+4- -- - - -
6.48E+6 4.24E+2 Zr 1.65E+3 5.22E+2 -
7.67E+2 -
-1.20E+6 3.59E+2 Nb 1.41E+5 7.80E+4 -
7.57E+4 -
3.34E+8 4.30E+4 I Ru-103 -1.81E+3 -
6.40E+3 -
1.52E+5 7.75E+2- l L
i
~Ru-106 3.75E+4 - -
7.23E+4 -
1.80E+6 4.73E+3 )
Ag-110m 9.63E+7 9.11E+7 -
1.74E+8 -
2.56E+10 5.54E+7-Sb-124= 4.59E+7 8.46E+5 1.04E+5 -
4.01E+7 9.25E+8- 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 -
3.21E+7 2'.84E+8 8.54E+6-
~Ts-125m 3.OOE+7 1.08E+7 8.39E+6 - -
8.86E+7 4.02E+6 1
To-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -
2.10E+8 -1.OOE+7 T3-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 -
4.15E+8 1.75E+7- d I-131- 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -
1.49E+8 4.04E+8
-CD-134- 9.81E+9 2.31E+10 -
7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136' 4.45E+8 1.75E+9 -
9.53E+8 1.50E+8 1.41E+8 1.18E+9. i C2-137 1.34E+10 1.78E+10 -
6.06E+9 2.35E+9 2.53E+8 6.20E+9 BS-140 4.85E+7 5.95E+4 -
2.02E+4 4.OOE+4 7.49E+7 .3.13E+6 C3-141 8.87E+3 1.35E+4 -
2.79E+3 -
1.69E+7 6.81Er2 ,
1 Co-144- 6.58E+5 2.72E+5 -
1.63E+5 -
1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -
6.77E+1 -
9.61E+5 1.45E+1 i Nd-147 1.81E+2 1.97E+2 -
1.16E+2 -
7.11E+5 1.18E+1 l 50 l
l
__ Hope Creek ODCM 3/28/90 o
Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Grase-Cow-Milk Pathway Dose Factors - CHILD (rrem/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -
1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5-P-32 7.77E+10 3.64E+9 - - -
2.15E+9 3.OOE+9 Cr-51 - -
5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5-Mn-54 -
2.09E+7. -
5.87E+6 -
1.76E+7 5.58E+6
'Fe-55 1.12E+8 5.93E+7 3.35E+7 1.10E+7 1.84E+7
-Fe-59 1.20E+8 1.95E+8 - -
5.65E+7 2.03E+8 9.71E+7 Co-57 -
3.84E+6 - - -
3.14E+7 7.77E+6 Co-58 -
1.21E+7 - - -
7.08E+7 3.72E+7 Co-60 -
4.32E+7 - - -
2.39E+8 1.27E+8'
.Ni-63 2.96E+10 1.59E+9 -- - -
1.07E+8 1.01E+9
-Zn-65 4.13E+9-1.10E+10 -
6.94E+9 -
1.93E+9 6.85E+9-
'Rb-86 -
8.77E+9 - - -
5.64E+8 5.39E+9 Sr-89 6.62E+9 - - - -
2.56E+8 1.89E+8 Sr-90 1.12E+11 - - - -
1.51E+9 2.83E+10
-Y-91 3.91E+4 - - - -
5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 -
1.21E+3 -
8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 -
1.16E+5 -
2.29E+8 8.84E+4 Ru-103 4.29E+3 - -
1.08E+4 -
1.11E+5 1.65E+3 Ru-106 9.24E+4 - -
1.25E+5 -
1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 -
2.63E+8 -
1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -
6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -
4.85E+7 2.08E+8 1.82E+7.
-Te-125m 7.38E+7 2.OOE+7 2.07E+7 - -
7.12E+7 9.84E+6
.Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -
1.68E+8 2.47E+7.
Te-129m 2.72E+8 '7.61E+7 8.78E+7 8.OOE+8 -
3.32E+8 4.23E+7' I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -
1.17E+8 7.46E+8 Cs-134- 2.26E+10 3.71E+10 -
1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 1.OOE+9 '2.76E+9 -
1.47E+9 2.19E+8 9.70E+7- 1.79E+9 Cs-137' 3.22E+10 3.09E+10 -
1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 -
3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 -
4.78E+3 -
1.36Ev7 1.62E+3 Ce-144- 1.62E+6 5.09E+5 -
2.82E+5 -
1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -
1.17E+2 -
7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 -
1.98E+2 -
5.71E+5 2.79E+1 51 l
0 Hope Creek ODCM 3/28/90 Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - INFANT l (arem/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI 'T. Body H-3 -
2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 9.42E+9 - - -
2.17E+9 6.21E+9 '
Cr-51 - -
1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 -
3.89E+7 -
8.63E+6 -
1.43E+7 8.83E+6-Fe-55 1.35E+8 8.72E+7 - -
4.27E+7 1.11E+7 2.33E+7 g Fe-59 2.25E+8 3.93E+8 - -
1.16E+8 1.88E+8 1.55E+8 ,
L Co-57 -
8.95E+6 - - -
3.05E+7 1.46E+7 ;
Co-58 -
2.43E+7 - - -
6.05E+7 6.06E+71 Co-60 -
8.81E+7 - - -
2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 - - -
1.07E+8 1.21E+9 Z n-6 5 - 5.55E+9 1.90E+10 -
9.23E+9 -
1.61E+10 8.78E+9- 1 Rb-86 -
2.22E+10 - - -
5.69E+8 1.10E+10
'Sr-89 1.26E+10 - - - -
2.59E+8 3.61E+8
.Sr-90 1.22E+11 - - - -
1.52E+9 3.10E+10 ;
Y-91 7.33E+4 - -
5.26E+6 1.95E+3 I i' Zr-95 6.83E+3 1.66E+3 -
1.79E+3 -
8.28E+5 1.18E+3 Nb-95 5.93E+5 2.44E+5 -
1.75E+5 -
2.06E+8 1.41E+5
-Ru-103 8.69E+3 - -
1.81E+4 -
1.06E+5 2.91E+3 Ru-106 1.90E+5 - -
2.25E+5 -
1.44E+6 2.38E+4 Ag-110m 3.86E+8 2.82E+8 -
4.03E+8 -
1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -
1.31E+8 6.46E+8 -6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 -
9.38E+7 1.99E+8 3.07E+7 l To-125m 1.51E+8 5.04E+7 5.07E+7 - -
7.18E+7 2.04E+7 l i
To-127m 4.21E+8 1.40E+8 1122E+8 1.04E+9 -
1.70E+8 5.10E+7 To-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -
3.34E+8 8.62E+7 I I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -
1.15E+8 1.41E+9- 1 Co-134 3.65E+10 6.80E+10 -
1.75E+10 7.18E+9 1.85E+8 6.87E+9 Co-136 1.96E+9 5.77E+9 -
2.30E+9 4.70E+8 8.76E+7 2.15E+9
- Ca-;.3 7 5.15E+10 6.02E+10 -
1.62E+10 6.55E+9 1.88E+8- 4.27E+9 )
Ba-140 2.41E+8 2.41E+5 -
5.73E+4 1.48E+5 5.92E+7 1.24E+7 Co-141 4.33E+4 2.64E+4 -
8.15E+3 -
1.37E+7 3.11E+3 Co-144 2.33E+6 9.52E+5 -
3.85E+5 -
1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 -
2.08E+2 -
7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 -
3.49E+2 -
5.74E+5 5.55E+1 52
"t Hope Creek ODCM 3/28/90 Table 2-4 (cont'd).
Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - ADULT (arem/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others
. Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -
2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 1.40E+9 8.73E+7 - - -
1.58E+8 5.42E+7 Cr-51 - -
2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 -
3.11E+8 -
9.27E+7 -
9.54E+8 5.94E+7
- Fe-55 2.09E+8 1.45E+8 - -
8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 - -
8.35E+7 9.96E+8 1.14E+8
. Co-57 -
1.17E+7 - - -
2.97E+8 1.95E+7 Co-58 -
3.09E+7 - - -
6.26E+8 6.92E+7
- Co .
1.67E+8 - - -
3.14E+9 .3.69E+8 Ni-63 1.04E+10 7.21E+8 - - -
1.50E+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 -
6.75E+8 -
6.36E+8 4.56E+8 Rb-86 -
2.19E+8 - - -
4.32E+7 1~.02E+8 Sr-89 9.96E+9~ - - - -
1.60E+9 2.86E+8
= Sr-90 6.05E+11 - - - -
1.75E+10 1.48E+11 Y 5.13E+6 - - - -
2.82E+9 1.37E+5 Zr-95 1.19E+6- 3.81E+5 -
5.97E+5 -
1.21E+9 2.58E+5 Nb-95 1.42E+5 7.91E+4 -
7.81E+4 -
4.80E+8 4.25E+4
' Ru-103 4.80E+6 - -
1.83E+7 -
5.61E+8 2.07E+6
' Ru-;O6 1.93E+8 - -
3.72E+8 -
1.25E+10 2.44E+7-
' Ag-110m 1.06E+7 9.76E+6- -
1.92E+7 -
3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 -
8.08E+7 2.95E+9 4.11E+7 cSb-125 1.36E+8 1.52E+6 1.39E+5 -
1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -
3.86E+8 1.29E+7 Te-127m- 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -
1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -
1.28E+9 4.03E+7
-I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -
3.05E+7. 6.63E+7 Cs-134 4.66E+9 1.11E+10 -
3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136. 4.20E+7' 1.66E+8 -
9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 -
2.95E+9 9.81E+8 1.68E+8- 5.70E+9 Ba-140 1.29E+8 1.62E+5 -
5.49E+4 9.25E+4 2.65E+8 8.43E+6
'Ce-141 l'.96E+5 1.33E+5 -
6.17E+4 -
5.08E+8 1.51E+4
! Ce-344 3.29E+7 1.38E+7 -
8.16E+6 -
1.11E+10 1.77E+6 Pr !43 6.34E+4 2.54E+4 -
1.47E+4 -
2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 -
2.25E+4 -
1.85E+8 2.31E+3 l
I 53 !
Hope Creek ODCM,3/28/90 i
ON Table 2-4 (cont'd)-
Pathway-Dose Facters - Atmospheric Releases R(io), Vegetation Pathway Dose Fcctors - TEENAGER (mram/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -
2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5-P-32 1.61E+9 9.96E+7 - - -
1.35E+8 6.23E+7 Cr - -
3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 -
4.52E+8 -
1.35E+8 -
9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 - -
1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 - -
1.33E+8 9.98E+8 .1.63E+8-Co-57 -
1.79E+7 - - -
3.34E+8 3.OOE+7 Co-58 -
4.38E+7 - - -
6.04E+8 l'.01E+8-Co-60 -
2.49E+8. - - -
3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 - - -
1.81E+8 5.45E+8-Zn-65 4.24E+8 1.47E+9 -
9.41E+8 -
6.23E+8 6.86E+8 Rb-86 -
2.73E+8 - - -
4.05E+7 1.28E+8 Sr-89 1.51E+10 - - - -
1.80E+9 4.33E+8 Sr-90 7.51E+11 - - - -
2.11E+10-1.85E+11 Y-91 7.87E+6 - - - -
3.23E+9 2.11E+54
- Zr-95 1.74E+6 5.49E+5 -
8.07E+5 -
1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 -
1.03E+5 -
4.55E+E- 5.86E+4
' Ru-103 6.87E+6 - -
2.42E+7 -
5.74E+8 2.94E+6
'Ru-106 3.09E+8 - -
5.97E+8 -
1.45E+10 3.90E+7-
'Ag-110m 1.52E+7 1.44E+7 -
2.74E+7 -
4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 -
1.35E+8 3.11E+9 6.03E+7 s Sb-125 2.14E+8 2.34E+6 2.04E+5 -
1.88E+8 1.66E+9 5.OOE+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 - -
4.37E+8 1.98E+7-Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -
1.37E+9 6.56E+7-Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -
1.38E+9 5.81E+7 I-131' 7.70E+7 1.OBE+8 3.14E+10 1.85E+8 -
2.13E+7- 5.79E+7
'Cs-134 7.09E+9 1.67E+10 -
5.30E+9 2.02E+9 2.08E+8 7.74E+9
.Cs-136 4.29E+7 1.69E+8 -
9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -
4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8' 1.69E+5 -
5.75E+4 1.14E+5 2.13E+8 8.91E+6
-Ce-141 2.82E+5 1.88E+5 -
8.86E+4 -
5.38E+8 2.16E+4
_Ce-144 5.27E+7 2.18E+7 -
1.30E+7 -
1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 -
1.65E+4 -
2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 -
2.32E+4 -
1.42E+8 2.36E+3 54
Hope Creek ODCM 3/28/90-O Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - CHILD (arem/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5" P-32 3.37E+9 1.58E+8 - - -
9.30E+7 1.30E+8 Cr - -
6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -~ 6.61E+8 -
1.85E+8 -
5.55E+8 1.76E+8
.Fe-55 8.OOE+8- 4.24E+8 - -
2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 - -
1.88E+8 6.76E+8 3.23E+8 Co 57 -
2.99E+7 - - -
2.45E+8 6.04E+7 Co-58 -
6.47E+7 - - -
3.77E+8 1.98E+8 Co-60 -
3.78E+8 - - -;
2.10E+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 - - -
1.42E+8 1.34E+9-
.Zn 8.12E+8 2.16E+9 -
1.36E+9 -
3.80E+8 =1.35E+9 Rb-86 -
4.52E+8 - - -
2.91E+7 2.-78E+8 Sr-89 3.59E+10 - - - -
1.39E+9 1.03E+9 Sr-90 1.24E+12 - - - -
1.67E+10 3.15E+11 Y-91 1.87E+7 - - - -
2.49E+9 5.01E+5 Zr 3.90E+6 8.58E+5 -
1.23E+6 -
8.95E+8 7.64E+5 Nb-95 4.10E+5 1.59E+5 -
1.50E+5 -
2.95E+8 1.14E+5 Ru-103 1.55E+7 - -
3.89E+7 -
3.99E+8 5.94E+6 Ru-106 7.45E+8 - -
1.01E+9 -
1.16E+10 9.30E+7 Ag -110m 3.22E+7 2.17E+7 -
4.ME+7' -
2.58E+9 1.74E+7-Sb-124 3.52E+8 4.57E+6 7.78E+5 --
1.96E+8 2.20E+9 1.23E+8' Sb-125 4.99E+8 3.85E+6 4.62E+5 -
2.78E+8 1.19E+9 1.05E+8 Te-125m- 3.51E+8 9.50E+7 9.84E+7 - -
3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -
1.07E+9 1.57E+8-Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -
1.04E+3 1.33E+8 I-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -
1.28E+7 8.18E+7 Cs-134 1.60E+10 2.63E+10 -
8.14E+9 2.92E+9 1.42E+8 5.54E+9-Cs-136 8.06E+7 2.22E+8 -
1.18E+8 1.76E+7 7.79E+6 1.43E+8
'Cs-137 2.39E+10 2.29E+10 -
7.46E+9 2.68E+9 1.43E+8 3.38E+9 Ba-140 2.77E+8 2.43E+5 -
7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 6.35E+5 3.26E+5 -
1.43E+5 -
4.07E+8 4.84E+4 fCe-144 1.27E+8 3.98E+7 -
2.21E+7 -
1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -
2.41E+4 -
1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 -
3.18E+4 -
9.18E+7 4.49E+3 I
l 55 e
g..
4 s
Hope Creek ODCM 3/28/90.
m '
t Table 2-4 (cont'd)
Pathway Dose-Factors'- Atmospheric Releases R(io), Ground Plane Pathway Dose Factors-r (m2
- mrem /yr per uCi/sec)
Nuclide Any. Organ i H-3 -
C-14 -
P-32 -
Cr-51 4.68E+6 Mn-54 1.34E+9 Fe-55 -
Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 -
Zn-65 7.45E+8 Rb-86 8.98E+6 l r Sr-89 2.16E+4 '
Sr-90 -
l Y 1.08E+6 L Zr-95 2.48E+8 l U
l -Nb-95 1.36E+8 l Ru-103 1.09E+8 Ro-106- 4.21E+8 Ag-110m 3.47E+9 Te-125m 1.55E+6 l Te-127m ~9.17E+4 Te-129m 2.OOE+7 .,
I-131 1.72E+7 l Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10 Ba-140 2.05E+7 l l
Ce-141 1.36E+7 Ce-144 6.95E+7 q
)
Pr-143 - 1 Nd-147 8.40E+6 1
l' 56 l
__x_:_x____:____ _ ____-___. . - -,
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.. Hope Creek ODCM 02/05/90- ,
v.
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1 2
i APPENDIX A EVALUATION OF DEFAULT MPC VALUES '
FOR LIQUID EFFLUENTS s
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Hope Creek ODCM- 02/05/90 APPENDIX A Evaluation of Default MPC Value for Liquid Effluent In accordance with the requirements of Technical Specification 3.3.3.10 the radioactive effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10-CFR 20, Appendix B, Table II, Column 2. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established. This default setpoint-can be based on an evaluation of the radionuclide distribution from the 1987 to 1989 release data of the liquid effluents from Hope Creek and the effective MPC value for this distribution.
The effective MPC value for a radionuclide distribution is calculated by the equation:
MPC, =
Ci / (Ci/MPC1 ) (A.1) where:
MPC, = an effective MPC value for a mixture of
=
radionuclides (uci/ml)
Ci concentration of radionuclide i in the mixture MPCi
= the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide (uci/ml)
Considering the average effective MPC values from 1987 thru 1989 releases it is reasonable to select an MPC value of SE-05 uCi/ml as typical of liquid radwaste discharges. This value will be reviewed and adjusted as necessary based on the ditribution history of effluents frcm Hope Creek. Using the value of uCi/ml
.to calculate the default klarm setpoint, results in a setpoint that:
A-2 Rev. 11
-t Hope Creek ODCM 02/05/90
-o -
-)
])1 -variations' Will not.re quire.
in thefrequent nuclide re-adjustment due toare distribution which minor .
typical of routine plant operations, and;
- 2) ~ tiilll-provide for'a liquid radwaste discharge rate (as evaluated-for each batch release) that is compatible with plant operations (Refer to Table 1-1).
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1
ll L Hope Creek ODCM- 02/05/90 oL TABLE-A-1 CALCULATION OF EFFECTIVE MPC HOPE CREEK 1987 ACTIVITY 1988' ACTIVITY 1989-ACTIVITY NUCLIDE 'MEQ- REfrASED (C1) REYTASED (Ci) REJJASED (Ci)-
Na 3.0E-05 5.7E-01 1.25E-01 9 2SE-03
-Cr-51~ 2.0E-03 4.5E-01 5.95E-02 1.85E-01 Mn-54' 1.0E-04 6.3E-02 3.21E-02 2.02E-01
'Mn 1.0E-04 1.3E-04 N/D N/D Co-58 9.0E-05 9.5E-02 7.58E-03 1.69E-02 Fe-59 =6.0E-05 5.2E-02 1.11E-02 5.77E-02 Co-60 3.0E-05 3.8E-02 1.53E-02 4.56E-02 Cu-64 3.0E-04_ 9.6E-04 8. 93 E -04 N/D Ni-65 _1.OE-04 3.3E-05 N/D N/D Zn-65 l'.0E-04 1.7E-01 1.92E-01 3.22E-01' Zn-69. 2.0E-03 '3.4E-03 1.53E-04 N/D Se-75 3.0E-04 4.0E-04 N/D N/D Y-91m 3.0E-03 - 2.8E-02 2.01E-03 N/D Y-91' 3.'OE-05 2.8E-03 6.95E-06 N/D
-Sr-92 7.0E-05 3.1E-05 2.63E-05 3.83E-04 Nb-95 1.0E-04 1.3E 3.47E-05 4.33E-06
=Zr-95 6.0E-05 1 ~. 4 E-0 4 N/D N/D Nb-97 9.0E-04 1.9E-03 2.90E-04 2.14E-05
'Zr-97 2.0E-05 2.7E-05 2.84E-04 -N/D Mo-99 =-4.0E-05 1.2E-02 3.82E-04 N/D Tc-99m 6.0E-03 1.3E-02 1.18E 4.61E-04 Tc-100 3.0E-06 3.7E-05 N/D N/D Ru-106 1.0E-05 1.1E-05 N/D N/D Sb-122 3.0E-05 7.7E-04 8.54E-06 N/D Sb-124 2.0E-05 6.5E-03 N/D N/D Sb-125 1~.0E-04 1.7E-04 N/D 5.82E-05.
I-131' 3.0E-07 1.8E-04 2.19E-05 1.33E-05 Te-132 3.0E-05 2.6E 1.60E-05 N/D I-133 1.0E-06 2.9E-03 3.84E-04 N/D Cs-137 -2.0E-05 1.2E-05 1.43E-06 3.94E-03 Ba-139 3.0E-06 1.3E-05 8.22E-05 N/D Ce-141 9.0E-05 1.0E-05 1.21E-05 N/D Co-143 4.0E-05 7.4E-06 3.55E-06 N/D Ce-144. 1.0E-05 1.3E-03 N/D N/D Np-239: 1.0E-04 '1.3E-03 4.40E-05 N/D Hg-203 2.0E 1.9E-04 1.65E-05 N/D Total- 1.58+00 4.53E-01 8.43E-01 ,
,m SUM (Ci/MPC1) k.,77Et04. 7.73E+03 8.56E+03 MPCe (uCi/ml) 4.19E-05 5.80E-05 9.85E-05 N/D=Not detected ,
A-4 Rev. 11
, , _ . , - _ . - _ = . . _ . .
,_.,4_
<') >2 'I \
-Hope Creek ODCM~ 02/05/90 ;
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i APPENDIX B TECHNICAL BASIS FOR EFFECTIVE. DOSE-FACTORS-LIQUID RADIOACTIVE EFFLUENT 1
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=
Hope Creek ODCM. 02/05/90 APPENDIX B Technical Basis for Effective Dose Factors -
Liquid Effluent Releases The radioactive liquid effluents from Hope Creek ~from 1987 through 1989 were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to cvaluate the use of a limited dose analysis for determining i onvironmental doses, providing a simplified method of determining l compliance with the dose limits of Technical Specification I 3.11.1.2. For the expected radionuclide distribution of effluent from Hope Creek during 1987 to 1989, the controlling organ is the liver. The calculated liver dose is predominately a functicn of the Zn-65 and Fe-59 releases. The radionuclides, Zn-65 and Fe-59 clso contribute the large majority of the calculated total body dose. The results of this evaluation are presented in Table B-1.
For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation process to the use of the' dose conversion factor for this nuclide.
I Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose _ calculation method that is simplified while also being conservative.
For the evaluation of the maximum organ dose, it is conservative to use the Zn-65 dose conversion factor (5.13E5 mrem /yr per liver). By this approach, the maximum organ dose will be l overestimated since this nuclide has the highest organ dose fraction of all tha radionuc?fdes evaluated. For the total body calculation, the 2n-65 dose factor (2.32E5 mrem /hr per uCi/ml, total body) is the highest among the identified dominant nuclides.
For evaluating compliance with the dose limits of technical Specification 3.11.1.2, the following simplified equations may be uned:-
Total Body 8.35E-04
- Vol
~Dtb " ----------------
CTBD Airtb
- Ci (B.1)
B-2 Rev. 11
l Hope Creek ODCM 02/05/90 o
j Where:
Dtb = dose to the total body (mrem)
A i ,tb = 2,32ES, total body ingestion dose conversion factor-for Zn-65 where A is dose conversion factor, i is isotope which is Zn-65, and TB is the total body (mrem /hr per uCi/ml) '
VOL = volume of liquid. effluent released (gal)
C.
= total concentration of all radionuclides.(uci/ml)
COBD = average cooling tower blowdown discharge rate during release period (gal / min) 8.35E-04 = conversion factor (1.67E-2 hr/ min) and the near field dilution factor 0.05 Substituting tho value for the Zn-65 total body dose conversion factor, the equation. simplified to:
1.94E2
- VOL
=
Dtb ------------------
- EC1 (B.2)
CTBD Maximum QISAD 8.35E-4
- VOL
- Aio, Liver Dmax = --------------------------------
(B.3)
CTBD
- IC1 Where:
Dmax = maximum organ dose-(arem)
Aio, = 5.13ES, liver ingestion dosa conversion factor for Liver Zn-65 where A is dose conviersion factor, i is isotope which is Zn-65 and O is mr.ximum organ which is the
-liver (mrem /hr per uci/ml).
Substituting the valui for Aio the aquation simplifies to:
4.28E2
- VOL Dmax = - - - - - - - - - - - - - - - - - -
- I (B.4)
C1 CTBD I
B-3 Rev. 11
Hope Creek ODCM 02/05/90
-O -
! Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.
Near Field Dilution Factor The near field dilution factor stems from NuReg-0133, Section 4.1. For plants with cooling towers, such as hope Creek, a dilution factor is applicable so that the product of the average blowdown flow (in CFS) and the dilution factor is 1000 cfs or less. The average minimum cooling tower blowdown for Hope Creek is 1.90E4 GPM from FSAR 11.2). This converts to 42 CFS, for conservatism a(dilution factor of 20 will be used, giving a dilution flow of 880 CFS. This near field dilution factor of 20 is inverted to a multiple of 0.05, multiplied times the 11guld effluent dose equations.
B-4 Rev. 11
1 Fope Creek ODCM 02/05/90 TABLE 8 1 Aealt Dose Contributions Flah and Invetebrate Pethessys Hope Creek 1989 1988 1987 T8 Cl LLI' Liver 18 Cl LLI Liver il Cl LLI Liver Redlo- Reteese Dose Dose Dose Release Dose Dose Dose Release Dose Dose Dose nuclide (Cl) Frec. Frec. free. (Cl) Frec. Frec. Frec. (Cl) Frec. Frec. Frac.
Cr 51 1.8t 1 * *
- 6.0E 2 * *
- 4.$t 1
- Mn 54 3.2t 2 -. * *
- 3.2t 2
- 0.01
- 6.3t 2 -
0.01
- Co 58 1.?t 2 * * .* 7.6t*3 * *
- 9.St 2
- 0.01
- Fe 59 5.8t 2 0.05 0.26 0.06 1.it 2 0.02 0.10 0.02 $.2t 2 0.08 0.35 0.10 Co 60 4.6E 2
- 0.01
- 5.$t 2
- 0.01
- 3.8E 2
- 0.01
- 2n 65 3.2t 1 0.94 0.72 0.94 1.96 1 0.98 0.88 0.98 1.7t 1 0.91 0.58 0.89 kb 95 4.3t 6 * *
- 3.$t'* T * *
- 1.3t 3
- 0.02 *
- = Less than 0.01, B-5 Rev. 11
Hope Creek ODCM 02/05/90 APPENDIX C TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADIOACTIVE EFFLUENT C-1 Rev. 11
1 I
Hope Creek ODCM O2/05/90 0
APPENDIX C Technical Basis for Effective Dose Factors -
Gaseous Radioactive Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on typical radionuclide distributions of releases, can be applied to the total radioactivity releases to approximate the dose in the environment. Instead of having to perform individual radionuclide dose analysis only a single multiplication (i.e.,
Keff, Meff, or Neff times the total quantity of radioactive material releases) would be needed. The approach provides a '
reasonable estimate of the actual dose while eliminating the need for a detailed calculation technique.
Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:
Kegg =
E (Ki
- f) i (C.i)
' nere:
K,gg = the effective total body factor due to gamma emissions from all noble gases released.
=
Ki the total body dose factor due to gamma emissions from each noble gas radionuclide i released,
= the fractional abundance of noble gas radionuclide i fi relative to the total noble gas activity.
(L + 1.1M) gg =I ((Li + 1.1 M1)
- f) t (C.2)
Whore:
(L + 1.1M) g f =
the effective skin dose factor due to beta and gamma emissions from all noble gases released.
(Li+ 1.1 M1) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released.
C-2 Rev. 11
Hope Creek ODCM 02/05/90 Meff E (Mi f)i (C.3)
Where:
) Meff = the effective air dose factc* due to gamma emissions from all noble gases released.
Mi =
the air dose factor due to gamma emissions from each noble gas radionuclide i released.
Neff =
E (Ni
- f) i (C.4)
Where:
Negg =
the effective air dose factor due to beta emissions from all noble gases released.
Ni =
the air dose factor due to beta emissions from each noble gas radionuclide i released.
Normally , it would be expected that past radioactive effluent data would be used fo. the determination of the effective dose factors. However, the noble gas releases from Hope Creek he.ve a short history and continued excellent fuel performance, which has a direct relation, has hampered efforts in collecting and detecting noble gas appreciable mixes of radionuclides. So, to provide a reasonable basis for the derivation of the effective noble gas dose factors, the source terms from ANSI N237-1967/ANS-18.1, " Source Term Specifications", Table 5 has been used as representing a typical distribution. The effective doss factors as derived are presented in Table C-1.
Acolication To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process whein the effective dose transfer factor is used. This conservatism providen additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.
C-3 Rev. 11
L l Hope Creek ODCM 02/05/90 o
For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:
3.17E-08 l D = *
- 9 X/Q M,ff
- IQi (C.5) 0.50 and 3.17E-08
= *
- Db X/Q Neff
- EQi (C.6) 0.50 Where:
Dg = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)
Db
=
air dose due to beta emissions for the cumulative release of all. noble gases (mrad)
X/Q =
atmot . ric dispersion to the controlling site boundary (sec/m-)
Mcff =
8.1E3, effective gamma-air dose factor (mrad /yr per uCi/g ) 3 N,gf =
8.5E3, effective beta-air dose factor (mrad /yr per uCi/m>)
= cumulative release for all noble gas radionuclides (uci)
Qi 3.17E-08 = conversion factor (yr/sec) 0.50 =
conservatism factor to account for the variability in the effluent data combining the constants, the dose calculational equations simplify to:
Dg = 5.14E-4
- X/Q
- IQi (C.7)
Db
= 5.39E-4
- X/Q
- IQi (C.8)
The effective dose factors are to be used on a limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.
C-4 Rev. 11
Hope Creek ODCM 02/05/90 TABLE C-1 Effective Dose Factors Noble Gases - Total Body and Skin Total Body Effective Skin Effective Keff (L + 1.1 M) eff 3 Radionuclide f.i* (mrem /v Der uCi/m3) (mrem /v Der uCi/m y Kr83m 0.01 ----- -----
Kr85m 0.01 1.0E1 2.8E1
~
Kr87 0.04 2.4E2 6.6E2 Kr88 0.04 5.9E2 7.6E2 Kr89 0.27 4.5E3 7.9E3 -
Xe133 0.02 5.9EO 1.4E1 Xel35 0.05 9.0E1 2.0E2 Xe135m 0.06 1.9E2 2.6E2 Xe137 0.31 4.4E2 4.3E3 Xe138 0.19 1.7E3 2.7E3 Total 7.8E3 1.7E4 Noble Gases - Air j Total Body Effective Skin Effective Keff (L + 1.1 M) eff Radionueljdg Li* (mrem /v Der uCi/m3) (mrem /v oer uCi/m 3)
Kr83m 0.01 ------
3.0E0 Kr85m 0.01 1.2E1 2.0E1 Kr87 0.04 2.5E2 4.1E2 Kr88 0.04 6.1E2 1.2E2 Kr89 0.27 4.7E3 2.9E3 Xe133 0.02 7.0E0 2.1El Xe135 0.05 9.6El 1.2E2 Xe135m 0.06 2.0E2 4.4E1 Xe137 m 0.31 4.7E2 3.9E3 Xe138 0.19 1.8E3 9.0E2 Total 8.1E3 8.4E3 ,
o Based on noble gas distribution from ANSI N237-1976/ANS-18.1,
" Source Term Specification".
C-5 Rev. 11 E
17k m.m . . . . .,, , , , . . . . . . . . . . . , . . . . . . . ., ,.
- Hope Creek ODCM 02/05/90 N
i.t APPENDIX D TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETER GASEOUS RADIOACTIVE EFFLUENT D-6 Rev. 11 a
i
Hope Creek ODCM 02/05/90 Io m APPENDIX D Technical Basis for Effective Dose Parameter -
Gastous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, orgsn and radionuclide. This analysis was performed to provide a _ _
simplified method for determining compliance with Technical Specification 3.11.2.3. For the infant age group, the controlling pathway is the grass - cow - milk (g/c/m' pathway.
An infant receives a greater radiation dose from thE g/m/C pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide I-131. The results of this evaluation are presented in Table D-1.
For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. Multiplication of the total release (i.e ,
cumulative activit/ for all radionuclides) by this dose -
conversion factor provides for a dose calculation method that is simplified while also being conservative.
For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/m/c, thyroid, I-131 pathway dose factor (1.67E12m2 mrem /yr per uCi/sec). Bv this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.
For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used:
D max = 3.17E-8
- W
- RI-131
- E (D.1)
Qi Where:
D max = maximum organ dose (mrem)
W =
atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.
X/Q =
Atmospheric dispersion for inhalation gathway ESTET dose contribution via other pathways (sec/m )
D-7 Rev. 11
M I Hope Creek ODCM 02/05/90 b --
fR D/Q =
atmosphericdispositionforvegetagion, milk and ground ground plane exposure pathways (m- )
Qi = cumulative release over tha period of interest for radioiodines and particulates (uci)*.
3.17E-8 = conversion factor (yr/sec) l!
RI-131 = I-131 dose parameter for the thyroid for the identified __
controlling pathway. -
=
1.05E12, infantthyroiddoseparamagerwiththecow-milk - grass pathway controlling (m mrem /yr per e uC1/sec) ___
The ground plane exposure and inhalation pathways need rot be -
considered when the above simplified calculational meth m is tsed _s because of the overall negligible contribution of these nathw ys to the total thyroid dose. It is recognized that for son.e -
particulate radionuclides (e.g., co-60 and Cs-137), the ground -
exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the -
organ dose calculation, especially considering that no other radionuclides has a higher dose parameter for any organ via any -
pathway than I-131 for the thyroid via the milk pathway.
The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census (Technical Specification 3.12.2). Othe rwise , the dose will be evaluated based on the predetermined controlling -
pathways as identified in Table 2-3.
D-8 Rev. 11
l Hope Creek ODCM 02/05/90 0
TABLE D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Tarcet Oraans Grass - Cow - Milk Ground Plane Total Body 0.n2 0.15 Bone 0.23 0.14 Liver 0.09 0.15 Thyroid 0.59 0.15 Kidney 0.02 0.15 Lung O.01 0.14 GI-LLI 0.02 0.15 TABLE D-2 Fraction of Dose Contribution by Pathway Pathway _L_
Grass-Cow-Milk O.92 Ground Plane 0.Go Inhalation
- D-9 Rev. 11
r 1
Hope Creek ODCM 02/05/90 10 APPENDIX E RADIOLOG.~:AL ENVIRONMENTAL MONITORING PROGRAM -
SAMPLE TYPE, LOCATION AND ANALYSIS E-10 Rev. 11
i l
Hope Creek ODCM 02/05/90 O
APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.
AIO = Air Iodine IDM = Immersion Dose (TLD)
APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)
ESF = Edible Fish PWT = Potable Water (Treated)
ESS = Sediment RWA = Rain Water (Precipitation)
FPB = Beef SWA = Surface Water FPL = Green Leafy Vegetables VGT = Fodder Crops (Various)
FPV = Vegetable (Various) WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the cite. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENG, etc. The next digit is a letter which represents the radical distance from the plant:
S = On-site location E = 4-5 miles off-EAte A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G= 10-20 miles off-site C = 2-3 miles off-site H = > 20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,... For example; the designation SA-WWA-5D1 would indicate a sample in the SGS program (SA),
consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radical distance of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 indicated that this is sampling station #1 in that particular sector.
E-11 Rev. 11
l Hope Creek ODCM 02/05/90 o
SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E. Maps E-1 and E-2 show the locations of sampling stations with respect to the site.
TABLE E-1 l STATION CODE STATION LOCATION SAMPLE TYPEji 2S2 0.4 mi. NNE of vent IDM 3S3 700 ft. NNE of vent; fresh water WWA holding tank I SS1 1.0 mi. E of vent; site access road AIO, APT, IDM -.
6S2 0.2 mi. ESE of vent; observation IDM building 7SI 0.12 mi. SE of vent; station personnel IDM gate 10S1 0.14 mi. SSW of vent; site shoreline IDM 11S1 0.09 mi. SW of vent; site shoreline IDM 11A1 0.2 mi. W of vent; outfall area ECH, ESF, ESS, SWA 15A1 0.3 mi. NW of vent; cooling tower ESS blowdown discharge line 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12C1 2.5 mi. WSW of vent; west bank of ECH, ESF, ESS Delaware River SWA 4D2 3.7 mi. ENE of vent; Alloway Creek IDM Neck Road -
SD1 3.5 mi. E of vent; local farm AIO, APT, IDM, WWA 10D1 3.9 mi. SSW of vent; Taylor's Bridge IDM Spur E-12 Rev. 11 mum-is- --m--
l Hope Creek ODCM 02/05/90
.o TABLE E-1 (Cont'd)
STATION CODE STATION LOCATION SAMPLE TYPES 11D1 3.5 mi. SW of vent GAM 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 2E1 4.4 mi. NNE of vent; local farm IDM 3E1 4.1 mi. NE of vent; local FPB, FPV, GAM, IDM, VGT, WWA 3E2 5.7 mi NE of vent; local fqarm FPV 7El 4.5 mi. SE of vent: 1 mi. W of Mad ESF, ESS, SWA Horse Creek 9El 5.0 mi. SW of vent IDM 11E2 5.0 mi. SW of vent IDM 12E1 4.4 mi. WSW of vent; Thomas Landing IDM 13E1 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. W of vent; local VGT 16El 4.1 mi. NNW of vent; Port Penn AIO, APT, IDM 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT, IDM 1F2 7.1 mi. N of vent; midpoint of SWA Delaware 1F3 5.9 mi. N of vent; local farm FPL, FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO, APT, IDM, RWA 2F3 8.0 mi. NNE of vent; local farm FPV 2F4 6.3 mi. NNE of vent; local FPV 2F5 7.5 mi. NNE of vent; Salem High School IDM E-13 Rev. 11
l Hope Creek ODCM 02/05/90 o
TABLE E-1 (Cont'd)
STATION CODE STATION LOCATION SAMPLE TYPES 2F6 7.3 mi. NNE of vent; Southern Trei ning IDM Center 2F7 5.1 mi. NNE of vent; local farm MLK, VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge IDM Municipal Building 3F3 8.6 mi NE of vent; Quinton Township IDM School SF1 6.5 mi. E of vent FPV,IDM SF2 7.0 mi. E of vent; local farm VGT 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, NJ IDM 10F2 5.8 mi. SSW of vent IDM 11F1 6.2 mi. SW of vent; Taylor's Bridge IDM Delaware 11F3 5.3 mi. SW of vent; Townsend, DE MLK, VGT 12F1 9.4 mi. WSW of vent; Townsend Elem. IDM School 13F2 6.5 mi. W of vent; Odessa, DE IDM 13F3 9.3 mi. W of vent; Redding Middle IDM School, Middletown, DE 13F4 9.8 mi. W of vent; Middletown, DE IDM 14F1 5.5 mi. WNW of vent; local farm MLK, VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi WNW of vent; local farm FPV 15F3 5.4 mi. NW of vent IDM E-14 Rev. 11
l Hope Creek ODCM 02/05/90 TABLE E-1 (Cont'c)
STATION CODE STATION LOCATION SAMPLE TYPES 16F1 6.9 mi. NNW of vent; C&D Canal ESS, SWA 16F2 8.1 mi. NNW of vent; Delaware City IDM Public School 1G1 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, DE IDM 2G1 12 mi. NNE of vent; Mannington FPV Township, NJ 3G1 17 mi. NE of vent; local farm IDM, MLK, VGT 10G1 12 mi. SSW of vent; Smyrna, DE IDM 16G1 15 mi. NNW of vent; Greater Wilmington IDM Airport 3H1 32 mi. NE of vent; National Park, N,7 IDM 3H3 110 mi. NE of vent; Research and AIO, APT, IDM Testing 3HS 25 mi. NE of vent; local farm FPL, FPV
.j E-15 Rev. 11
l l
Hope Creek ODCM 02/05/90 0
SAMPLES COLLECTION AND AlALYSIS Samole Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change, be perfouned if gross beta exceeds 10 times the yearly mean of the control station value. As well one sample is analyzed > 24 hrs after sampling to allow for radon and thoron daughter decay. Gamma isotopic analysis
, on quarterly composites.
Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on connected to air each weekly sample.
particulated air sampler and is collected weekly at filter change.
Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and frozen portion on collection, semi-annually or when in season.
sediment A sediment sample is Gamma isotopic taken semi-annually, analysis semi-annually.
Direct 2 TLL s will be Gamma dose quarterly collected from each location quarterly.
E-16 Rev. 11
Hope Creek ODCM 02/05/90 o
SAMPLI COLLECTION AND ANALYSIS (Cont'd)
Samole collection Method Analysis Milk Sample of fresh milk Gamma isotopic is collected for each analysis and I-131 farm semi-monthly when analysis on each cows are in pasture, sample on collection, monthly at other times.
Water (Rain, Sample to be co1.lected Gamma isotopic Potable, monthly providing winter monthly H-3 on Surface) icing conditians allow. quarterly surface sample, monthly on ground water sample.
E-17 Rev. 11
l FIGURE E-1 l OFFSITE SAMPLING LOCAllONS O
1 16 PENNSVILLE t ae 2 6 'Y 71DWm ,_ f MANNINGTON
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FIGURE E-2 ONSITE SAMPLING LOCATIONS
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