ML20212B717
| ML20212B717 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/25/1987 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20212B645 | List: |
| References | |
| PROC-870225, NUDOCS 8703030627 | |
| Download: ML20212B717 (93) | |
Text
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O i
OFFSITE DOSE CALCULATION MANUAL FOR I
l PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION i
4 Revision 6 February 1987
/
l l
l 1
Approval:
SORC Chairman: ~
Date: J/NG[#7Mtg.4 8 7- M G.
/
Rev. 6 8703030627 870227 PDR ADOCK 050003S4 PDR p
HOPE CREEK GENERATING STATION
(}
L' OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . 1 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls . . . . . . . . . . 2 1.2 Liquid Effluent Monitor Setpoint Determination . . . . . . . . . . . . . 3 1.2.1 Liquid Effluent Monitors . . . . . . . . 4 1.2.2 Conservative Default Values . . . . . . . 5 1.3 Liquid Effluent Concentration Limits -10 CFR 20 . . . . . . . . . . . . . . . 7 1.4 Liquid Effluent Dose Calculations - 10 CFR 50 . . . . . . . . . . . . 8 1.4.1 Member of the Public Dose -
(N Liquid Effluents . . . . . . . . . . . . 8
(_) 1.4.2 Simplified Liquid Effluent Dose Calculation . . . . . . . . . . . . 10 1.5 Liquid Effluent Dose Projection . . . . . . . . 12 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls . . . . . . . . . . 13 2.2 Gaseous Effluent Monitor Setpoint Determination . . . . . . . . . . . . . 15 2.2.1 Plant Vent and FRVS Monitors . . . . . . 15 2.2.2 Conservative Default Values . . . . . . . 18 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 . . . . . . . 19 2.3.1 Site Boundary Dose Rate -
Noble Gases . . . . . . . . . . . . . . . 19 2.3.2 Site Boundary Dose P. ate -
Radiciodine and Particulates . . . . . . 21 O
- -_ ,. .- - , . - - , , . . . . , . - - . - , - - .---,_-..r . -.. , . _ ..__ , _ --
l l
2.4 Noble Gas Effluent Dose '
Calculations - 10 CFR 50 . . . . . . . . . . . 24
[~')
V 2.4.1 UNRESTRICTED AREA Dose -
Noble Gses . . . . . . . . . . . . . . . 24 2.4.2 Simplified Dose Calculation for Noble Gases . . . . . . . . . . . . . 25 2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50 . . . . . . . . . . . . 27 2.5.1 UNRESTRICTED AREA Dose -
Radiciodine and Particulates . . . . . . 27 2.5.2 Simplified Dose Calculation for Radiciodines and Particulates . . . . . . 29 2.6 Gaseous Effluent Dose Projection . . . . . . . . 31 3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities Inside 33 the SITE BOUNDARY . . . . . . . . . . . . . . .
3.2 Doses to MEMBERS OF THE PUBLIC -
40 CFR 190 . . . . . . . . . . . . . . . . . . . 34 3.2.1 Effluent Dose Calculations . . . . . . . 35 3.2.2 Direct Exposure Determination . . . . . . 35
(} . . . . 36 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling Program . . . . . . . . . . . . . . . . 36 4.1 Interlaboratory Comparison Program . . . . . . . 37 4.2 TABLES 1-1 Parameters for Liquid Alarm Setpoint Determination . . . . . . . . . . . . . 39 l-2 Site Related Ingestion Dose Commitment Factors, Aio . . . . . . . . . . . . 40 42 1-3 Bioaccumulation Factors (BFi) . . . . . . , . ,
45 2-1 Dose Factors for Noble Gases . . . . . . . . . .
2-2 Parameters for Gaseous Alarm Septoint Determination . . . . . . . . . . . . . 46 2-3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations . . . . . . . . . . . . . . . 47 2-4 Pathway Dose Parameters -
Atmospheric Releases . . . . . . . . . . . . . . 48 n
v
A-4
(~ A-1 Calculation of Effective MPC . . . . . . . . . .
( B-1 Adult Dose Contributions Fish and B-4 Drinking Water Pathways . . . . . . . .. . . . C-5 C-1 Effective Dose Factors . . . . . . . . . . .. ... . D-4 D-1 Infant Dose Contribution Fraction of Dose . . . D-4 D-2 Fraction of Dose Contributions by Pathway APPENDICIES Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents . . . . . . . . A-1 Appendix B - Technical Basis for Effective Dose B-1 Factors - Liquid Radioactive Effluents . . . .
Appendix C - Technical Basis for Effective Dose C-1 Factors - Gaseous Radioactive Effluents . . . .
Appendix D - Technical Basis for Effective Dose . . D-1 Parameters - Gaseous Radioactive Effluents.
Appendix E - Radiological Environmental Monitoring E-1 Program - Sample Type, Location and Analysis. .
O O
Hopa Crook ODCM 1/9/87 (
O HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Hope Creek Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in: 1) the calculation of radioactive liquid and gaseous ef fluent 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 CPR 50, Appendix I and 40 CFR 190.
-~g More conservative calculation methods and/or conditions (e.g.,
\_) location and/or exposure pathways) expected to yield higher computed doses than appropriate for the maximally exposed person 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 calculations. 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.
O 1 Rev. 6
Hopa Crook ODCM 1/9/87
\/ 1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Effluent Technical Specifications are summarized as follows:
- 1) 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.
) 2) Alarm (Only) - The Cooling-Tower Blowdown Effluent Monitor (RE4817) provides an Alarm function only for releases into the enviroment as required by Technical Specification 3.3.7.9.
Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figure 1-1.
2 Rev. 6 I
Hope Crook ODCM 1/9/87 O 1.2 Liquid Effluent Monitor Setpoint De te rmina tion 1
1 Per the requirements of Technical Specification 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release 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 II, Column 2, for radionuclides and 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) c< ------------- (1.1)
{
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 subsequent release, the setpoint, represents a value which, if exceeded, would result in 1
concentrations exceeding the limits of 10 CFR 30 in the UNRESTRICTED AREA.
- Adopted from NUREG-0133 O
3 Rev. 6 l
i
Hope Craok ODCM 1/9/87 C~N f = the flow rate at tr> radiaton monitor location, in volume per unit ime, but in the same units as F, below F = the dilution .ater flow rate as measured prior to the release point, in volume per unit time.
[ Note that if no dilution is provided, c 1 C. Also, note that when (F) is large compared to (f), then (F + f) = F.]
1.2.1 Liquid Effluent Monitors The setpoints for the liquid effluent monitors at the Hope Creek Generating Station are determined by the following equation:
MPCe
- CTBD O, SP i ------------- + bkg (1.2)
RR with:
i l~_ Ci MPCe = ------------- (1.3)
[_ (Ci / MPCi) where:
SP = alarm setpoint corresponding to the t
maximum allowable release rate (uci/ml) i MPCe = an effective MPC value for the mixture of radionuclides in the effluent stream (uci/ml)
O 4 Rev. 6
Hopa Creak ODCM 1/9/87 O Ci = the concentration of radionuclide i in the liquid effluent (uCi/ml)*
- NOTE: The concentration mix must include the most recent quarterly composite of alpha emmitters, Sr-89, Sr-90, Fe-55, Fe-59, and H-3.
MPCi = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml)
CTBD = the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min)
RR = the liquid effluent release rate (gal / min)
(\ bkg = the background of the monitor (cpm) b The radiouctivity monitor setpoint equation (1.2) remains valid during outages when the Cooling-Tower Blowdown discharge is potentially at 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 summarizes all current default values in use for Hope Creek.
!O Rev. 6 l 5 l
t
Hope Crook ODCM 1/9/87 O They are based upon the following:
a) substitution of the effective MPC value with a default value of 1.4E-5 uCi/ml for radwaste releases (Refer to Appendix A for justification);
b) substitutions of the Cooling-Tower Blowdown discharge rate with the lowest flow, in gal / min; and, c) substitutions of the effluent release rate with the highest allowed rate, in gal / min.
With pre-established alarm setpoints, it is possible to control the radwaste releace rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and for differing Cooling-Tower Blowdown
' discharge.
4 6 Rev. 6
Hopo Crack ODCM 1/9/87 1.3 Liquid Effluent Concentration Limits - 10 CFR 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. Releaso rates are controlled and radiation monitor alarm setpoints 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 g Specification 3.11.1.1 may be performed using the
\_/ following equation:
Ci
\ *
[
, < 1 (1,4)
MPCi/ (CTBD+RR) where:
Ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (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 time of release (gal / min) l 7 Rev. 6
Hopa Croek ODCM 1/9/87 l
[)
1.4 Liquid Effluent Dose Calculation - 10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose - Liquid 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:
< l.5 mrem to total body 1 5.0 mrem to any organ
- during any calendar year:
1 3.0 mrem to total body 1 10.0 mrem to any organ
(')]
Per the surveillance requirements of Technical Specification 4.11.1.2, the following calculation methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Hope Creek.
i
- VOL
' l.67E-02 Do = ---------------- *{_(Ci
- Aio) (1.5)
CTBD where:
! Do = dose or dose commitment to organ I c ., including total body (mrem)
O 8 Rev. 6 l
- _ _ - . . , __..._.-._m,. .,__.___- - ,___ . - . - . . _ . . . . _ . . - . , _ . , _ . . _ ~ _ , . . _ - , . - - - _ _ . - _ . . - . _ . _ . - _ _ _ , _ _ _ - - _ , - . _ _ _ . -
Hope Creek ODCM 1/9/87 Aio = site-related ingestion dose j commitment factor to the total body or any organ o for radionuclide i (mrem /hr per uCi/ml)
Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uCi/ml)
VOL = volume of liquid effluent released (gal)
CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min) 1.67E-02 = conversion factor (hr/ min)
() The site-related ingestion dose / dose commitment factors (Aio) are presented in Table 1-2 and have been derived in accordance with a NUREG-0133 by the equation:
Aio = 1.14E+05 [(UI
- Bli) + (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 invertebrate ingestion pathways (mrem /hr per uCi/ml) 1.14E5 = conversion factor (pCi/uCi
- ml/kg per hr/yr)
UI = adult invertebrate consumption (5 kg/yr)
BIi = bioaccumulation factor for radionuclide i in invertebrates from Table 1-3 (pci/kg
{~')
per pCi/1) 9 Rev. 6
i l
l Hop 3 Creek ODCM 1/9/87 UP = 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 pre-selected organ, o, from Table E-ll 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 spectral 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 Technical Specification Table 4.11.1.1.1-1.
1.4.2 Simplified Liquid Effluent Dose Calculation In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of Technical Specification 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.)
O
. 10 Rev. 6 1
' Hop 2 Crook ODCM 1/9/87 O Total Body
- VOL 1.08E3 Dtb = -------------- *7~Ci (1.7)
CTBD Maximum Organ 2.52E4 VOL Dmax = --------------
- 2'. C i (1.8)
CTBD where:
Dtb = conservatively evaluated total body dose (mrem)
Dmax = conservatively evaluated maximum organ dose (mrem)
{} Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uci/ml)
VOL = volume of liquid effluent released (gal)
CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min) 1.08E3 = conversion factor (hr/ min) and the conservative total body dose conversion factor (Cs-134, total body -- 6.48E4 mrem /hr per uCi/ml) 2.52E4 = conversion factor (hr/ min) and the conservative maximum organ dose conversion factor (Nb-95, GI-LLI --
1.51E6 mrem /hr per uCi/ml)
O 11 Rev. 6
Hop 3 Crook ODCM 1/9/87 n
i 1.5 Liquid Effluent Dose Projections 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 exceed:
- 0.06 mrem to the total body, or
- 0.2 mrem to any organ.
The applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and deminerilizers as delineated in Figure 1-1.
Dose projections are made at least once per 31-days by the following equations:
Dtbp = (Dtb / 91d)
- 31d (1.9)
Dmaxp = (Dmax / 91d)
- 31d (1.10) where i
Dtbp = the total cody dose projection for current 31-day period (mrem)
Dtb = the total body dose to date for current calendar quarter as determined by equation (1.5) or (1.7) (mrem)
Dmaxp = the maximum organ dose projection for current 31-day period (mrem)
Dmax = the maximum organ dose to date for current calendar quarter as determined by equation (1.5) or (1.8) (mrem) 91d = the number of days in a calendar quarter
() 31d = the number of days of concern 12 Rev. 6
Hopo CrGok ODCM 1/9/87 O 2.0 Gaseous Effluents 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are summarized as follows:
- 1) Filtration, 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 monitoring is provided by RE-4811A.
- 2) South Plant Vent - The SPV receives discharge from the radwaste evaporator, reactor building purge, auxiliary building radwaste area, condensate demineralizer, pipe cht.se, feedwater heater, and untreated ventilation so'.wces. Effluents are monitored (for noble gas) by the RE-4873B monitor.
- 3) North Plant Vent - The NPV receives discharges from the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources.
Effluents are monitored (for noble gases) by the l
RE-4873B monitor.
i O
13 Rev. 6
Hops Crook ODCM 1/9/87 O A gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figures 2-1 and 2-2.
O O
34 Rev. 6
Hops Cresk ODCM 1/9/87 2.2 Gaseous Effluent Monitor Setpoint Determination
) 2.2.1 Plant Vent and FRVS Vent Monitors Per the requirements of Technical Specification
- 3.3.3.10, alarm setpoints shall be established 1
for the gaseous effluent monitoring instrumentation to ensure that the release rate l of noble gases does not exceed the limits of l Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrom/ 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 FRVS, pipe chase, i gaseous radwaste treatment system air, etc.),
the radiation monitoring alarm setpoints may be
/ established by the following calculation
}
I method. The measured radionuclide
- concentrations and release rate are used to i calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by I the equations i
I FRAC = [4.72E+02
- X/Q
- VF * (Ci
- Ki)] / 500 (2.1) i FRAC = [4.72E+02
- X/Q
- VF * (Ci * (Li + 1.1 Mi))) / 3000 (2.2) where:
I FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and i the release flow rate
$ X/O = annual average meterological dispersion to the controlling site boundary location (sec/m3) 15 Rev. 6
}
)
f Hopa Crook ODCM 1/9/87 O
V VF = ventilation system flow rate for the applicable release point and monitor (ft3/ min)
Ci = concentration of noble gas .
radionuclide i as determined by radioanalysis of grab sample .
(uci/cm3)
Ki = total body dose conversion factor for noble gas radionuclide i (mrem /yr per uCi/m3, from Table 2-1)
Li = beta skin dose conversion factor for noble gas radionuclide i (mrem /yr per uCi/m3, from Table 2-1)
Mi = gamma air dose conversion factor for noble gas radionuclide i
(} (mrad /yr per uCi/m3, from Table 2-1) 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) 4.72E+02 = conversion factor (cm3/ft3
- min /sec) 500 = total body dose rate limit (mrem /yr) 3000 = skin dose rate limit (mrem /yr)
I 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:
SP = [AF * {Ci / FRAC) + bkg (2.3) 16 Rev. 6
_ _ . _ _ _ . . ~ . . _ _ . . - . . _ . . _ _ _ _ _ _ _ _ . . ,
H:p2 Crask ODCM 1/9/87 10 where:
SP = alarm setpoint corresponding to the maximum allowable release rate (uCi/cc)
FRAC = highest fraction of the allowable release rate as determined in equation 4
(2.2) bkg = background of the monitor (cpm)
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 rate limits of Technical Specification 3.11.2.1). Normally, s_)
the combined AF value for Salem Units 1 and 2 is 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 allocation factors for all units do not exceed 1.0.
I O
' 17 Rev. 6
t Hopa Crook ODCM 1/9/87
%)
2.2.2 Conservative Default Values
. I A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.
These values are based upon:
- the maximum ventilation (or purge) flow rate;
- a radionucide 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 do not exceed the maximum
- allowable release rate.
For the noble gas radionuclide distribution from i
ANSI N237-1976/ANS 18.1 (Note Table C-1), the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2-2.
- Adopted from ANSI N237-1976/ANS-18.1, Source Term i Specifications, Table 6 -
<(
- 18 Rev. 6 1
[
Hop 2 Crook ODCM 1/9/87
(
b) 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations -
10 CFR 20 2.3.1 Site Boundary Dose Rate - Noble Gases Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to i 500 mrem /yr, total body and i 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 being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release may be performed using the following equations:
Dtb = X/O * { (Ki
- 01) (2.4) and Ds = X/O * [_((Li + 1.lMi)
- Qi) (2.5) where Dtb = total body dose rate (mrem /yr)
Ds = skin dose rate (mrem /yr)
X/O = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3) 01 = average release rate of radionuclide i over the release period under evaluation (uci/sec)
O 19 Rev. 6
1 l
Hope Crask ODCM 1/9/87 ;
O 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 (mrem /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 = mrem skin dose per mrad gamma air dose (mrem / mrad)
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 Monitor indications (readings) may
- O setpoints.
be averaged over a time period not to exceed 15 minutes when determining noble gas release rate 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 be excluded from the analysis.
O Rev. 6 20
Hopa Creek ODCM 1/9/87
(~y%
\' NOTE: For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed.
However, conditions exceeding these more j limiting alarm setpoints do not ,
necessarily indicate radioactive material release rates exceeding the dose limits of Technical Specification 3.11.2.la. ,
Provided actual releases do not result in ,
radiation monitor indications 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.
Actual meteorological conditions concurrent with p)
(_- the release period or the default, annual average dispersion parameters as presented in Table 2-4 may be used for evaluating the gaseous effluent dose rate.
2.3.2 Site Boundary Dose Rate - Radioiodine and Particulates Technical Specification 3.11.2.lb limits the dose rate to < 1500 mrem /yr to any organ for I-131, 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 O Rev. 6 21
1 /
s Hops Creek ODCM 1/9/87.; - x the sampling and analyiis tirc:e period (e.g, ,
't nominally once per 7 days).- The following .
equation may be used f6r the dese. rate f
evaluation:
Do = X/O *]~(Ri
- Qi) '(2.6) i i where:
Do = average organ dose rate over the'
' sampling time period (mrem /yr)
X/O = atmospheric dispersion to the i controlling SITE BOUNDARY' location for
, 1 the inhalagion,pathday (sec/m3) s _.,
~
Ri = dose parameter'for 'radionuclide i, (mrem /yr per uCi/m3) for the child ~ '
inhalation pachway frem Tablo 2-4
~
, Oi = average release rate over the ,
appropriate sampling period and 4
analysis frequency for radihnuclide i -- I-131, I-133, tritium or other :
radionuclide in particulate form with ,
half-live greater than 8 days i
(uci/ir.ec )
By substituting 1500 mrem /yr for Do and solving ,
4 for 0, an allowable release rate for I-131 can be determined. Based on the annual aveiage meteorological dispersion (300 Table 2-3) and j
the most limiting potential pathway, age group ,
and organ (inhalation, child, thyinid -- Ri =
1.62E+07 mrem /yr per uCi/m3), the allowable ,,
i release rate for I-131 is 34.7 uCi/sec.
Reducing this release rate by a factor of 2 t;o i
f /5 f
I 22 , Rev. 6 4
1 J
-c.,~, - - , , , , . . . . .. . . _ . . . , . . . . . . , . . _ , . ..,..r,.. - . . .__.-s,4 ,....____.,_,ym,,,..._.-.-~r ,m.. --.-,--.~_,_m-3,
1
- Hopo Creek ODCM 1/9/87
%y
'j ,
account for potential dose contributions from f t
other radioactive particulate material and other release points (e.g., Salem), the corresponding I
release rate allocated to Hope Creek is 17.4 uCi/sec. For a 7-day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 10.5 Ci.
Therefore, as long as the I-131 releass in any i 7-day period do not exceed 10.5 Ci, no additional analyses are needed for verifying compliance with the Technical Specification i
4..,
3.11.2.1.b limits on allowable release rate.
}
I l
4 b
w
,w' j
l l
1 i
i l
4 e
!O 1
b 23 Rev. 6
Hopa Creek ODCM 1/9/87 O Noble Gas Ef flue nt Dose Calculations - 10 CFR 50 2.4 2.4.1 UNRESTRICTED AREA Dose - Noble Gases Technical Specification 3.11.2.2 requires a a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of 1 5 mrad, gamma-air and i 10 mrad, beta-air and the calendar year limits i 10 mrad, I
gamma-air and i 20 mrad, beta-air. The limits are applicable separately to each generating station and are not combined site limits. The following equations may be used to calculate the gamma-air and beta-air doses:
Dg = 3.17E-08
- X/O
- E (Mi
- Qi) (2.7)
O and Db = 3.17E-08
- X/O * [(Ni
- Qi) (2.8) where:
Dg = air dose due to gamma emmissions for noble gas radionuclides (mrad)
Db = air dose due to beta emissions for noble gas radionuclides (mrad)
X/O = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3)
Qi = cumulative release of noble gas radionuclide i over the period of interest (uCi)
O 24 Rev. 6 s
, , . _ - n , ,. --
7 - . _ , , - . - - - - . - , , . _ , . - , . , , , , , . - . - - -
Hopa Creek ODCM 1/9/87 O Mi = air dose factor due to gamma emissions from noble gas radionuclide i (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) 2.4.2 Simplified Dose Calculation for Noble Gases In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification
(s 3.11.2.2. (Refer to Appendix C for the derivation and justification of this simplified method.)
3.17E-08 Dg = -----------
- X/O
- Me f f * [, Qi (2.9) 0.50 and 3.17E-08 Db = -----------
- X/O*Neff*{~Qi _
(2.10) 0.50 0 ~
Rev. 6 25
Hopa Crook ODCM 1/9/87 O where:
Meff = 8.lE2, effective gamma-air dose factor (mrad /yr per uCi/m3)
Neff = 8.5E3, effective beta-air dose factor (mrad /yr per uCi/m3)
Qi = cumulative release for all noble gas radionuclides (uCi) 0.50 = conservatism 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.
O I
O 26 Rev. 6
Hope Creek ODCM 1/9/87 f~%
b 2.5 Radiciodine and Particulate Dose Calculations -
10 CFR 50 2.5.1 UNRESTRICTED AREA Dose - Radioiodine and Particulates In accordance with requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of < 7.5 mrem and calendar year limit < 15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to release of I-131, tritium and particulates with half-lives greater than 8 days:
Daop = 3.17E-08
- W
- SFp * { (Ri
- Qi) (2.11)
[~}
V where:
Daop = dose or dose commitment via controlling pathway p and age group a (as identified in Table 2-3) to organ o, including the total body (mrem).
W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.
X/O = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3).
D/O = atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).
"\
27 Rev. 6
Hopo Creek ODCM 1/9/87
[
G 't dose factor for radionuclide i, Ri =
(mrem /yr per uCi/m3) or (m2 - mrem /yr per uCi/sec) from Table 2-4 for each age group a and the applicable pathway p as identified in Table 2-3. Values for Ri were derived in accordance with the methods described in NUREG-0133.
Oi = cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form with half-life greater than 8 days (uCi).
SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.
.Y 1) For milk and vegetation exposure pathways:
= A six month fresh vegetation and grazing season (May through
]
October).
= 0.5
- 2) For inhalation and ground plane exposure pathways:
= 1.0 l
l For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway and the child age group is controlling for the vegetation pathway. Only the controlling age group and pathway as identified in Table 2-3 need be evaluated for compliance with Technical Specification 3.11.2.3.
-~g 1
(
l 28 Rev. 6
Hopo Crook ODCM 1/9/87 2.5.2 Simplified Dose Calculation for Radiciodines and Particulates In lieu of the individual radionuclide (I-131 and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used 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).
(2.12)
Dmax = 3.17E-08
- W
- SFp
- RI-131
- E Oi where:
. Dmax = maximum organ dose (mrem)
RI-131 = I-131 dose parameter for the thyroid l
for the identified controlling pathway
= 1.67E12, infant thyroid dose parameter with the cow-milk pathway controlling (m2 - mrem /yr per uCi/sec)
W = D/O for radiciodine, 2.87E-10 1/m2 Oi = cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form with half-life greater than 8 days (uCi)
O 29 Rev. 6
~ . - . - . . . . _ . . _ _ . _ .
Hope Creek ODCM 1/9/87 O 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). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.
O 30 Rev. 6 l
Hopa Crook ODCM 1/9/87
, -n 2.6 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM by used to reduce radioactive material levels prior to discharge when 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 mrem 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 least once per 31-days by the following equations:
Dgp = ( Dg / 91d )
- 31d (2.17)
Dbp = (Db / 91d)
- 31d (2.18)
Dmaxp = (Dmax / 91d)
- 31d (2.19) where:
Dgp = gamma air dose projection for current 31-day period (mrad)
Dg = gamma air dose to date for current calendar quarter as determined by equation (2.7) or (2.9) (mrad)
Dbp = beta air dose projection for current 31-day period (mrad)
Db = beta air dose to date for current calendar quarter as determined by equation (2.8) or (2.10) (mrad)
O 31 Rev. 6
- c. . __-
Hopa Creek ODCM 1/9/87 O Dmaxp = maximum organ dose projection for current 31-day period (mrem) i Dmax = maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12) (mrem) 91d = number of days in a calendar quarter
- 31d = the number of days of concern O
i I
O 32 Rev. 6
Hopo Crook ODCM 1/9/87 O 3.0 Special Dose Analysis 3.1 Doses Due to Activities Inside the SITE BOUNDARY 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 effluents to MEMBERS OF Tl!E PUBLIC due to their activities inside the SITE BOUNDARY.
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 MEMBER OF THE PUBLIC based on the parameters from Table 2-3 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 in unavailable at the time l
of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available.
I (O
l 33 Rev. 6 l
l
Hopo Crook ODCM 1/9/87 O 3.2 Total Dose to MEMBERS OF THE PUBLIC - 40 CFR 190 The Radioactive Effluent Release Report (RERR) submitted within 60-days after January 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Generating Station and the Hope Creek Generating Station: No othr fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.
/% The dose contribution from the operation of Hope Creek U Generating Station will be estimated based on the methdos 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 used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.
O 34 Rev. 6
Hopa Crcok ODCM 1/9/87 Effluent Dose Calculations 3.2.1
~} 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 Hope Creek Generating Station may be performed using the calculation methods contained within the ODCM; the conservative controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.2) may be used. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.
3.2.2 Direct Exposure Dose Determination Any potentially significant direct exposure
() contribution to off-site individual doses may be evaluated based on the results of the LL environmental measurements (e.g., TLD, ion
}fh
" chamber measurements) and/or by the use of a radiation transport and shielding calculation method. Only during a typical conditions will i there exist any potential for significant on-site sources at Hope Creek that would yield potentially significant of f-site deses (i.e. , in
~
excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance 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 l will be used for determination of dose for
() assessing 40 CFR 190 compliance.
I i
35 Rev. 6
1
' Hops Creek ODCM 1/9/87 rh U Radiological Environmental Monitoring Program 4.0 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirernents 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 changes 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 are presented in Appendix E.
O 36 Rev. 6
l Hopa Creek ODCM 1/9/87
\
4.2 Interlaboratory Comparison Program 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 Program provides a check on the precisness of measuremets of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursant to Technical Specification 6.9.1.7.
i l
l l
O 37 Rev. 6 i
b FIGURE l-1 LIQUID RADWASTE TREATMENT SYSTEM Cooling Il Il Tower -
D Basin I Collector Z lL _
EE Tanks (2)
U Equipment Equipment Equipment 05 U
-o. Drain -, Drain o Drain Sample = ;
Surge h Filter b Demineralizer Tanks (2) g a .-o, _
Tank p Condensate Storage -
Tank il
(?
ty ir a Floor Floor Floor Floor Floor Drains : Drain _+ Drain d+ Drain Demineralizer
_+ Drain Sample
-+
Collector h Filter Tanks (2) Tanks (2)
Decon
= Vapor to Solutions, Lab Chemical Decontamination South Vent Drains-.- , Waste e Solution Tank IL Evaporator
> Bottoms to Solid
' Laundry Waste
! cnd Detergent Detergent I U-U Dzcen % Drain Drain Drains Tanks (2) Filter RE 4861 j Loggsd: RE = Effluent Radiation Monitor RE 8817 )
l D
C ToDelawar$
t River 38 (offsite)
"') ,
(d TABLE l-1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION Actual Default Parameter Value Value Units Comments MPCe Calculated 1.4E-5 uCi/ml Calculated for each batch to be- released MPC I-131 3E-8 N/A uCi/ml I-131 MPC conservatively used for HC CTBD and
- liquid radwaste monitor setpoints Ci Measured N/A uCi/ml Taken from gamma spectral analysis of liquid effluent MPCi As N/A uCi/ml Taken from 10 CFR 20, Determined Appendix B, Table II, Column 2 CTBD As 2.53E4 gpm Cooling tower blowdown Determined discharge RR As 176 gpm or Determined prior to De te rmined 1300 gpm (CST) release; release rate can be adjusted for Technical Specification compliance SP A) RE4861 Calculated 2E-3 uCi/m1* Default alarm setpoints; more conservative values RE8817 Calculated 2E-3 uCi/ml* may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA B) RE4861 Calculated 2.71E-04 uCi/ml These setpoints are for condensate storage tank RE8817 Calculated 2.71E-04 uCi/ml releases
- These setpoints are more conservative for Detergent Drain Tank releases.
For lower conservative default setpoints multiply setpoint by 7.04 for DDT releases.
l O
39
TAB m 1-2 i SI'IE RELAIED INGESTION DOSE 00PMI'IMNT FACIOR, Ait j (FISH AND INVEKnERNIE CONSLMPI'IO4)
(MRDVhr per uCi/ml)
Page 1 of 2 Nuclide Bone Liver T. Body ' Thyroid ,f Kidney Lung GI-LLI H-3 -
2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.82e-1 C-14 1.45e 4 2.90e 3 2.90e 3 2.90e 3 2.90e 3 2.90e 3 2.90e 3 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 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 A Fe-59 8.06e 4 1.90e 5 7.27e 4 - -
5.30e 4 6.32e 5 Co-58 -
6.03e 2 1.35e 3 - - -
1.22e A Co-57 -
1.42e 2 2.36e 2 - - -
3.59e 4 Co-60 -
1.73e 3 3.82e 3 - - -
3.25e 4 Ni-63 4.96e 4 3.44e 3 1.67e 3 - - -
7.18e 2 Ni-65 2.02e 2 2.62e 1 1.20e 1 - - -
6.65e 2 Cu-64 -
2.14e 2 1.01e 2 -
5.40e 2 -
1.83e 4 2n-65 1.61e 5 5.13e 5 2.32e 5 -
3.43e 5 -
3.23e 5 2n-69 3.43e 2 6.56e 2 4.56e 1 -
4.26e 2 -
9.85e 1 Br-82 - -
4.07e 0 - - -
4.67e 0 Br-83 - -
7.25e-2 - - -
1.04e-1 Br-84 - -
9.39e-2 - - -
7.37e-7 Be-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-89 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 l Y-90 6.06e 0 -
1.62e-1 - - -
6.42e 4 Y-91m 5.72e-2 -
2.22e-3 - - -
1.68e-1 j
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 l
Zr-97 8.81e-1 1.78e-1 8.12e-2 -
2.68e-1 -
5.51e 4 Nb-95 4.47e 2 2.49e 2 1.34e 2 -
2.46e 2 -
1.51e 6 Nb-97 3.75e 0 9.49e-1 3.46e-1 -
1.11e 0 -
3.50e 3 Mo-99 -
1.28e 2 2.43e 1 -
2.89e 2 -
2.96e 2 l Tc-99m 1.29e-2 3.66e-2 4.66e-1 -
5.56e-1 1.79e-2 2.17e 1 Tc-101 1.33e-2 1.92e-2 1.08e-1 -
3.46e-1 9.81e-3 5.77e-14 l
l 40
l l
TABIE l-2 O- SITE RE1EITD INGESTION DOSE 00PMI1 MENT FACIOR, Ait IFISH AND INVERIEBRAIE (X)NSLMPTICN)
(MRDVhr per uCi/ml)
Page 2 of 2 T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone Liver
.. .________...___.... __________._____..______________ 4.07e 2 - __________
1.25e 4 ____
Ru-103 1.07e 2 - 4.60e 1 -
5.44e 3 3.51e 0 -
1.15e 2 -
Ru-105 8.89e 0 -
3.06e 3 -
1.03e 5 Ru-106 1.59e 3 - 2.01e 2 -
Rh-103m - - - - - -
Rh-106
- 2.85e 3 - 5.91e 5 Ag-110m 1.56e 3 1.45e 3 8.60e 2 - 2.15e 2 7.86e 3 Sb-124 2.77e 2 5.23e 0 1.10e 2 6.71e-1 1.36e 2 1.95e 3 1.77e 2 1.98e 0 4.21e 1 1.80e-1 Sb-125 - 8.66e 2 Te-125m 2.17e 2 7.86e 1 2.91e 1 6.52e 1 8.82e 2 - 1.84e 3 Te-127m 5.48e 2 1.96e 2 6.68e 1 1.40e 2 2.23e 3
- 7.03e 2 Te-127 8.90e 0 3.20e 0 1.93e 0 6.60e 0 3.63e 1 - 4.69e 3 Te-129m 9.31e 2 3.47e 2 1.47e 2 3.20e 2 3.89e 3 - 1.92e 0 Te-129 2.54e 0 9.55e-1 6.19e-1 1.95e 0 1.07e 1 - 6.80e 3 Te-131m 1.40e 2 6.85e 1 5.71e 1 1.08e 2 6.9de 2 1.31e 0 6.99e 0
- 2.26e-1 Te-131 1.59e 0 6.66e-1 5.03e-1
- 6.2de 3 m Te-132 2.04e 2 1.32e 2 1.24e 2 1.46e 2 1.27e 3 - 1.01e 2 I-130 3.96e 1 1.17e 2 4.61e 1 9.91e 3 1.82e 2 - 8.23e 1 1-131 2.18e 2 3.12e 2 1.79e 2 1.02e 5 5.35e 2 - 5.35e 0 I-132 1.06e 1 2.85e 1 9.96e 0 9.96e 2 4.54e 1
- 1.16e 2 I-133 7.45e 1 1.30e 2 3.95e 1 1.90e 4 2.26e 2 -
1.32e-2 1-134 5.56e 0 1.51e 1 5.40e 0 2.62e 2 2.40e 1 - 6.87e 1 I-135 2.32e 1 6.08e 1 2.24e 1 4.01e 3 9.75e - 5.27e13 1.75e 3 2.85e 2 Cs-134 6.84e 3 1.63e 4 1.33e 4 - 1.57e 3 2.16e 2 3.21e 2 Cs-136 7.16e 2 2.83e 3 2.04e 3 8.77e 3 1.20e 4 7.85e 3
~
4.07e 3 1.35e 3 2.32e 2 Cs-137 6.07e 0 1.20e 1 5.94e 0 8.81e 0 8.70e-1 5.11e-5 Cs-138 -
5.23e-3 3.17e-3 1.39e 1 Ba-139 7.85e 0 5.59e-3 2.30e-1 -
7.02e-1 1.18e 0 3.38e 3 Ba-140 1.61e 3 2.06e 0 1.08e 2 2.68e-3 1.63e-3 1.80e-9 Ba-141 3.81e 0 2.88e-3 1.29e-1 -
1.72e 0 1.77e-3 1.08e-1 1.50e-3 1.00e-3 2.43e-18 Ba-142 - - 5.83e 4 1.57e 0 7.94e-1 2.10e-1 La-140 - - - 2.68e2 La-142 8.06e-2 3.67e-2 9.13e-3 - 1.08e 0 - 8.86e 3 Ce-141 3.43e 0 2.32e 0 2.63e-1 1.96e-1 - 1.67e 4 6.04e-1 4.46e 2 4.94e-2 Ce-143
- 4.43e 1 - 6.04e 4 Ce-144 1.79e 2 7.47e 1 9.59e 0 -
1.34e 0 - 2.54e 4 Pr-143 5.79e 0 2.32e 0 2.87e-1 - 4.44e-3 - 2.73e-9 Pr-144 1.90e-2 7.87e-3 9.64e-4 - 2.68e 0 - 2.20e 4 Nd-147 3.96e 0 4.58e 0 2.74e-1 - - 2.51e 3 O
W-187 9.16e 0 7.66e 0 2.68e 0 1.08e-2 - 7.11e 2 3.53e-2 3.47e-3 1.91e-3 No-239 41
(j)
('
TABLE l-3 BIOACCUMULATION FACTORS (pci/kg per pCi/ liter)*
ELEMENT SALTWATER FISH SALTWATER INVERTEBRATES H 9.0E-01 9.3E-01 C 1.8E+03 1.4E+03 NA 6.7E-02 1.9E-01 P 3.0E+03 3.0E+04 CR 4.0E+02 2.0E+03 MN 5.5E+02 4.0E+02 FE 3.0E+03 2.0E+04 CO 1.0E+02 1.0E+03 NI 1.0E+02 2.5E+02 CU 6.7E+02 1.7E+03 2N 2.0E+03 5.0E+04 BR 1.5E-02 3.lE+00 RB 8.3E+00 1.7E+01 SR 2.0E+00 2.0E+01 Y 2.5E+01 1.0E+03 2R 2.0E+02 8.0E+01 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 1.0E+01 5.0E+01 Os TC RU 3.0E+00 1.0E+03 RH 1.0E+01 2.0E+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 CS 4.0E+01 2.5E+02 BA 1.0E+01 1.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+01 6.0E+02 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 3.0E+01 3.0E+01 NP 1.0E+01 1.0E+01
- Values in Table 2.2-2 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.
O 42
FIGURE 2-1 GASEOUS RADWASTE TREATMENT SYSTEM Main or Auxiliary Steam SJAE Offgas l Recombiner I
N N Preheater Recombiner Condenser I
h Condenser Offgas Typical of 2 Recombiner Packages y
N Holdup Pipes q
l
= Cooler Reheater - Guard l Condenser Bed L
I Absorber N To North e HEPA Filter -
l Plant Vent Train (Figure 4.1-2)
Ambient Charcoal System l
O e l
FIGURE 2-2 Ci
\'- VENTILATION EXHAUST TREATMENT SYSTEM ,
RE*
Gaseous Radwaste RE Treatment System = 4875A (from Figure 4.1-3) North
Plant Vent Untreated Ventilation
Air Sources Radwaste Decon. =
Evaporator Reactor Building R H =
Purge Air (Typ. of 3)
RE Auxiliary Building 4814A Radwaste Area R H = Gouth Ventilation Air = Plant
- (Typ. of 3) Vent ondensate -e Demineralizer Room Air Pipe Chase Air = R H C H --4 Feedwater Heater :
Room Air Untreated Ventilation Air Sources (Recirculation) RE O rRVS Reactor = H C H = C H = System Vent Building Air (Typ. of 6) (Typ. of 2)
Legend: R = Roughing Filter C = Charcoal Filter H = HEPA Filter I ) RE = Effluent Radiation Monitor
-/ * -- This Foot-Treatment Monitor is not an effluent monitor as designated by the RETS.
44
(J .
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 per (mrad /yr 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.-O l E + 0 4 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.llE+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.35E+02 1.05E+03 Xe-135m 3.12E+03 7.llE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 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 45
TABLE 2-2 .
PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION HOPE CREEK Actual Default Parameter Value Value Units Comments X/O Calculated 2.67E-6 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 f t 3/ min Maximum Operation AF (NPV) Coordinated 0.2 Unitless Administrative with SGS allocation factor to ensure releases AF (SPV) 0.2 Unitiess do not exceed release rate limit
) Unitless vAF (FRVS) 0.1 Ci Measured N/A uCi/m 3 Ki' Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m3)
Li Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m 3)
Mi Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m3)
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 values may be used as deemed appropriate for ensuring ALARA and regulatory compliance Sv(0) NPV Calculated 4.8E3 uCi/sec Determined by SPV Calculated 4.8E3 uCi/sec multiplying setpoint FRVS Calculated 2.4E3 uCi/sec (uci/cc) times vent flow rates (cc/sec)
O 46
() TABLE 2-3 CONTROLLING LOCATIONS,' PATHWAYS AND ATOMSPHERIC DISPERSION FOR DOSE CALCULATIONS
- Controlling X/O D/O Tach. Spec. Location Pathway (s) Age Group (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 Residence / Dairy milk and Infant 7.2E-08 2.87E-10 O' l . 2. 3 (4.9 Mile's, W) ground plane Second Sun direct exposure N/A 8.22E-06 N/A 6.9.1.7 (0.21 Miles, SE) and inhaltion
- The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.
O 47 l
p l 4 TABLE 2-4
\_)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - ADULT (arem/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total 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 1.00E+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 Fo-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 e3
( ;-86 -----
1.35E+5 ----- ----- -----
1.66E+4 5.90E+4 Nor-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 Zr-95 1.07E+5 3.44E+4 -----
5.42E+4 1.77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 -----
7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+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 Ag-110m 1.08E+4 1.00E+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 To-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 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -----
6.28E+3 2.05E+4 Cs-134 3.73E+5 8.48E+5 -----
2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -----
8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+5 -----
2.22E+5 7.52E+4 8.40E+3 4.26E+5 Ba-140 3.90E+4 4.90E+1 -----
1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ce-141 1.99E+4 1.35E+4 -----
6.26E+3 3.62E+5 1.20E+5 1.53E+3 3.43E+6 1.43E+6 -----
8.48E+5 7.78E+6 8.16E+5 1.84E+5
('Ce-144 i-143 9.36E+3 3.75E+3 -----
2.16E+3 2.81E+5 2.00E+5 4.64E+2
\~j-147 5.27E+3 6.10E+3 -----
3.56E+3 2.21E+5 1.73E+5 3.65E+2 48
,m s- ,
TABLE 2-4 PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - ADULT (mrem /yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total 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 1.00E+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 Fo-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 ----- 6.90E+4 8.64E+5 5.34E+4 4.66E+4
-65 3.24E+4 1.03E+5 ----- 6.90E+4 8.64E+5 5.34E+4 4.66E+4
-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 Zr-95 1.07E+5 3.44E+4 ----- 5.42E+4 1.77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 ----- 7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+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 Ag-110m 1.08E+4 1.00E+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 1.0lE+5 1.26E+4 To-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 To-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 ----- 6.28E+3 2.05E+4 C3-134 3.73E+5 8.48E+5 ----- 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -----
8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+5 ----- 2.22E+5 7.52E+4 8.40E+3 4.26E+5 Ba-140 3.90E+4 4.90E+1 -----
1.67E+1 1.27E+6 2.18E+5 2.57E+3 Co-141 1.99E+4 1.35E+4 ----- 6.26E+3 3.62E+5 1.20E+5 1.53E+3 3.43E+6 1.43E+6 ----- 8.48E+5 7.78E+6 8.16E+5 1.84E+5 C<)-144 J 143 9.36E+3 3.75E+3 -----
2.16E+3 3.56E+3 2.81E+5 2.21E+5 2.00E+5 1.73E+5 4.64E+2 3.65E+2 Nd-147 5.27E+3 6.10E+3 -----
48
~
i
,- g
( ,) ,
TABLE 2-4 (Con't) ,
i PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - TEENAGER (mrem /yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Pody H-3 -----_ l.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 ,3.00E+3 1.35E+2 Mn-54 -----
5.llE+4 -----
1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fo-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 2n-65 3.86E+4 1.34E+5 -----
8,. 6 4 E+4 1.24E+6 4.66E+4 6.24E+4 s,,3-86 -----
1.90E+5 ----- ----- -----
1.77E+4 8.40E+4 Sr-89 4.34E+5 ----- ----- -----
2.42E+6 3.71E+5 1.25B+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 Zr-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 -----
1.00E+4 7.51E+5 9.68E+4 5.66E+3 '
Ru-103 2.10E+3 ----- -----
7.43E+3 7.83E+5 ' l.09E+5 8.96E+2 Ru-106 9.84E+4 ----- -----
1.90E+5 1.61L'+7 9.60E+5 1.24E+4 Ag-110m 1.38E+4 1.31E+4 -----
2.50E+4 6.75E+4 2.73E45 7.99E+3 i Sb-124 4.30E+4 7.94E+2 9.76E+1 -----
3 385E+6 3.98E+5 1.68E+4 !
Sb-125 7.38E+4 8.08E+2 7.04E+1 -----
2.74E+6 9.92E+4 1.72E+4 To-125m 4.88E+3 21. 2 4 E+ 3 1.40E+3 --t-- 5.36E+3 7.50E+4 6.67E+2 To-127m 1.80E+4 8.16E+3 4.38E+3 6.545+4 1.66E+6 1.59E+5 2.18E+3 To-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+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 5.4$E+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.llE+5 Ba-140 5.47E+4 6.70E+1 -----
2.28E+1 2.03E+6 2.29E+5 3.52E+3 Co-141 2.84E+4 1.90E+4 -----
8.88E+3 6.14E+5 1.26E+5 2.17E+3 144 4.89E+6 2.02E+6 -----
1.21E+6 1.34E+7 8.64E+5 2.62E+5
(~'7
(_ . J -14s 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 -----
3.02E+3 3.72E+5 1.32E+5 5.13E+2 49
p)
( .
TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - CHILD (arem/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body 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-32 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 -----
1.00E+4 1.58E+6 2.29E+4 9.51E+3 Fo-55 4.74E+4 2.52E+4 ----- -----
1.llE+5 2.87E+3 7.77E+3 Fo-59 2.07E+4 3.34E+4 ----- -----
1.27E+6 7.07E+4 1.67E+4 Co-57 -----
9.03E+2 ----- -----
5.07E+5 1.32E+4 1.07E+3
-Co-58 -----
1.77E+3 ----- -----
1.llE+6 3.44E+4 3.16E+3 Co-60 -----
1.31E+4 ----- -----
7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 ----- -----
2.75E+5 6.33E+3 2.80E+4 Zn-65 4.26E+4 1.13E+5 -----
7.14E+4 9.95E+5 1.63E+4 7.03E+4 86 -----
1.98E+5 ----- ----- -----
7.99E+3 1.14E+5 sr-89 5.99E+5 ----- ----- -----
2.16E+6 1.67E+5 1.72E+4 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 Zr-95 1.90E+5 4.18E+4 -----
5.96E+4 2.23E+6 6.llE+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 -----
8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.??E+3 ----- -----
7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+3 ----- -----
1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4, 1.14E+4 -----
2.12E+4 5.48E+6 1.00E+5 9.14E+3 SD-124 5.74E+4 '
7.40E+2 1.26E+2 -----
3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -----
2.32E+6 4.03E+4 2.07E+4 To-125m 6.73E+3 2.33E+3 1.92E+3 -----
4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 7.14E+4 6.07E+3 6.36E+4 1.48E+6 3.02E+3 Te-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 Cs-134 6.51E+5 1. ole +6 -----
3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 -----
9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-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.llE+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 77 144 6.77E+6 2.12E+6 -----
1.17E+6 1.20E+7 3.89E+5 3.61E+5 1.85E+4 5.55E+3 -----
3.00E+3 4.33E+5 9.73E+4 9.14E+2 (wo[143
-147 1.08E+4 8.73E+3 -----
4.81E+3 3.28E+5 8.21E+4 6.81E+2 50
( TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - INFANT (aren/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body H-3 -----
6.47E+2 6.47E+2 6.47E+2 6.47E+2 G.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+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 1.00E+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.llE+4 1.82E+3 Co-60 -----
8.02E+3 ----- -----
4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 ----- -----
2.09E+5 2.42E+3 1.16E+4
-65 1.93E+4 6.26E+4 -----
3.25E+4 6.47E+5 5.14E+4 3.11E+4 b-86 -----
1.90Eh5 ----- ----- -----
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.llE+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. 67t+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -----
Pst E'6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -----
1.f(C+: 1.47E+4 1.09E+4
, Te-125m 4.76E+3 1.99E+3 1.62E+3 -----
1.47v." 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 To-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 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 (Dj-144 g 3.19E+6 1.21E+6 -----
5.38E+5 9.84E+6 1.48E+5 1.76E+5
'v r- 14 3 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 5.00E+2 l l
51
. _L
)
\__/ TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FACTOR - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- arem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total 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-32 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 Fo-59 2.98E+7 7.00E+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
-65 1.37E+9 4.36E+9 -----
2.92E+9 -----
2.75E+9 1.97E+9 Rb-86 ----- 1.35E+5 ----- ----- -----
1.66E+4 5.90E+4 Sr-89 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 1.07E+5 3.44E+4 -----
5.24E+4 1.77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 -----
7.74E+3 5.05E+5 1.04E+5 4.21E+3 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 8.58E+8 1.62E+7 2.08E+6 -----
6.68E+8 2.44E+10 3.40E+8 Sb-125 6.81E+8 7.61E+6 6.93E+5 -----
5.25E+8 7.50E+9 1.62E+8 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 To-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 r~
(,;-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 52
f~)
\s l TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FACTOR - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Liver Thyroid Kidney Luna GI-LLI Total Body Nuclide Bone 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 H-3 -----
1.34E+5 1.34E+5 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 3.15E+10 1.95E+9 ----- ----- ----- 2.65E+9 1.22E+9 P-32 8.40E+6 5.00E+4 Cr-51 ----- ----- 2.78E+4 1.10E+4 7.13E+4 1.40E+7 ----- 4.17E+6 ----- 2.87E+7 2.78E+6 Mn-54 -----
1.37E+7 7.36E+6 Fe-55 4.45E+7 3.16E+7 ----- ----- 2.00E+7 1.21E+8 ----- 3.82E+7 2.87E+8 4.68E+7 Fe-59 5.20E+7 -----
3.76E+6 2.25E+6 ----- ----- ----- 4.19E+7 Co-57 ---- ,
7.95E+6 ----- ----- ----- 1.10E+8 1.83E+7 Co-58 -----
6.26E+7 Co-60 ----- 2.78E+7 ----- ----- ----- 3.62E+6 8.35E+8 ----- -----
1.33E+8 4.01E+8 1.18E+10 -----
3.41E+9
- ~Ni-63 2.11E+9 7.31E+9 ----- 4.68E+9 ----- 3.10E+9 N._)h-65 7.00E+8 2.22E+9 Rb-86 ----- 4.73E+9 ----- ----- -----
----- 3.18E+8 7.66E+7 Sr-89 2.67E+9 ----- -----
6.10E+6 9.92E+7 ----- ----- ----- 9.60E+6 7.22E+5 Sr-90 ----- ----- 6.48E+6 4.24E+2 Y-91 1.58E+4 ----- -----
5.22E+2 7.67E+2 ----- 1.20E+6 3.59E+2 Zr-95 1.65E+3 -----
4.30E+4 1.41E+5 7.80E+4 ----- 7.57E+4 ----- 3.34E+8 Nb-95 1.52E+5 7.75E+2 Ru-103 1.81E+3 ----- ----- 6.40E+3 -----
7.23E+4 ----- 1.80E+6 4.73E+3 Ru-106 3.75E+4 ----- -----
9.11E+7 1.74E+8 ----- 2.56E+10 5.54E+7 Ag-110m 9.63E+7 -----
3.08E+10 5.97E+8 Sb-124 1.53E+9 2.82E+7 3.47E+6 ----- 1.34E+9 1.33E+7 1.16E+6 ----- 1.07E+9 9.48E+9 2.85E+8 Sb-125 1.22E+9 8.86E+7 4.02E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 ----- -----
2.99E+7 2.01E+7 3.42E+8 ----- 2.10E+8 1.00E+7 Te-127m 8.44E+7 1.75E+7 1.11E+8 4.10E+7 3.57E+7 4.62E+8 ----- 4.15E+8 Tn-129m 1.49E+8 4.04E+8 I-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -----
2.31E+10 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-134 9.81E+9 -----
1.75E+9 9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-136 4.45E+8 -----
6.20E+9 1.34E+10 1.78E+10 ----- 6.06E+9 2.35E+9 2.53E+8 Cs-137 4.00E+4 7.49E+7 3.13E+6 Ba-140 4.85E+7 5.95E+4 ----- 2.02E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-141 1.99E+4 1.35E+4 -----
(\
(_ fe-144 6.58E+5 2.72E+5 ----- 1.63E+5 ----- 1.66E+8 3.54E+4 l
6.77Etl ----- 9.61E+5 1.45E+1 Pr-143 2.92E+2 1.17E+2 -----
7.11E+5 1.18E+1 Nd-147 1.81E+2 1.97E+2 ----- 1.16E+2 -----
53
f~
(h,) TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FACTOR - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Bone Liver Thyroid Kidney Lung GI-LLI Total Body!
Nuclide i
H-3 ----- 1.57E+3 1.57E+3 1.57Ev3 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 3.00E+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 l Fe-59 1.20E+8 1.95E+8 ----- ----- 5.65E+7 2.03E+8 9.71E+7 l Co-57 ----- 3.84E+6 ----- ----- -----
3.1dE+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
/"'p-65 4.13E+9 1.10E+10 ----- 6.94E+9 ----- 1.93E+9 6.85E+9 U 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 9.14E+5 ----- ----- ----- 2.63E+6 1.84E+5 2.44E+4 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.llE+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 3.62E+9 4.70E+7 7.99E+6 ----- 2.01E+9 2.26E+10 1.27E+9 Sb-125 2.90E+9 2.24E+7 2.69E+6 ----- 1.62E+9 6.93E+9 6.08E+8 Te-125m 7.38E+7 2.00E+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 8.00E+8 ----- 3.32E+8 4.23E+7 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -----
1.17E+8 7.46E+8 I-131 Cs-134 2.26E+10 3.71E+10 ----- 1.15E+10 4.13E+9 2.00E+8 7.83E+9 i Cs-136 1.00E+9 2.76E+9 ----- 1.47E+9 2.19E+8 9.70E+7 1.79E+9 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-137 -----
5.94E+7 6.84E^6 Ba-140 1.17E+8 1.03E+5 ----- 3.34E+4 6.12E+4 Ce-141 2.19E+4 1.09E+4 ----- 4.78E+3 ----- 1.36E+7 1.62L '
1.62E+6 5.09E+5 2.82E+5 ----- 1.33E+8 8.66E+4
( ,;e-144 -----
1.17E+2 7.80E+5 3.59E+1
_ Pr-143 7.23E+2 2.17E+2 ----- -----
2.79E+1 4.45E+2 3.60E+2 1.98E+2 ----- 5.71E+5
, Nd-147 -----
54
1 1
f
/3
\/ )
TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FACTOR - INFANT (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid K id ney Lung GI-LLI Total 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.llE+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 ----- -----
1.16E+8 1.88E+8 1.55E+8 Co-57 ----- 8.95E+6 ----- ----- ----- 3.05E+7 1.46E+7 Co-58 ----- 2.43E+7 ----- ----- ----- 6.05E+7 6.06E+7 Co-60 -----
8.81E+7 ----- ----- ----- 2.10E+8 2.08E+8
- Mi-63 3.49E+10 2.16E+9 ----- ----- ----- 1.07E+8 1.21E+9
! /~'3-65 5.55E+9 1.90E+10 -----
9.23E+9 -----
1.61E+10 8.78E+9 l s) 5.69E+8 1.10E+10 Rb-86 -----
2.22E+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 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 6.98E+9 1.03E+8 1.85E+7 -----
4.37E+9 2.15E+10 2.16E+9 Sb-125 4.98E+9 4.82E+7 6.24E+6 -----
3.13E+9 6.64E+9 1.02E+9 Te-125m 1.51E+8 5.04E+7 5.07E+7 ----- -----
7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -----
1.70E+8 5.10E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -----
3.34C+8 8.62E+7 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -----
1.15Z+8 1.41E+9 Cs-134 3.65E+10 6.80E+10 ----- 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 ----- 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 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 Ce-141 4.33E+4 2.64E+4 ----- 8.15E+3 -----
1.37E+7 3.11E+3
( e-144 2.31E+6 9.52E+5 ----- 3.85E+5 ----- 1.33E+8 1.30E+5 Pr-143 1. AGE +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 55
O iI TABLE 2-4 (Con't)
\_/
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) VEGETATION PATHWAY FACTOR - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Thyroid Kidney Lung GI-LLI Total Body, Nuclide Bone Liver 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 H-3 -----
1.79E+5 1.79E+5 1.79E+5 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 8.73E+7 ----- ----- 1.58E+8 5.42E+7 P-32 1.40E+9 -----
1.17E+7 4.66E+4 2.79E+4 1.03E+4 6.19E+4 Cr-51 ----- -----
3.11E+8 ----- 9.27E+7 ----- 9.54E+8 5.94E+7 Mn-54 -----
8.06E+7 8.29E+7 3.37E+7 Fe-55 2.09E+8 1.45E+8 ----- -----
2.99E+8 ----- 8.35E+7 9.96E+8 1.14E+8 Fe-59 1.27E+8 -----
2.97E+8 1.95E+7 Co-57 ----- 1.17E+7 ----- -----
i 3.09E+7 ----- ----- ----- 6.26E+8 6.92E+7 I Co-58 -----
3.14E+9 3.69E+8 !
Co-60 ----- 1.67E+8 ----- -----
3.49E+8 7.21E+8 ----- ----- 1.50E+8 !
1.04E+10 -----
6.36E+8 4.56E+8 !
I Ni-63
$n-65 3.17E+8 1.01E+9 ----- 6.75E+8 -----
(/ ----- 4.32E+7 1.02E+8 !
Rb-86 ----- 2.19E+8 ----- -----
2.86E+8 '
9.96E+9 ----- ----- ----- ----- 1.60E+9 Sr-89 ----- ----- 1.75E+10 1.48E+11 Sr-90 6.05E+11 ----- -----
----- 2.82E+9 1.37E+5 Y-91 5.13E+6 ----- -----
3.81E+5 5.97E+5 ----- 1.21E+9 2.58E+5 2r-95 1.19E+6 -----
4.80E+8 4.25E+4 Nb-95 1.42E+5 7.91E+4 ----- 7.81E+4 -----
1.83E+7 ----- 5.61E+8 2.07E+6 Ru-103 4.80E+6 ----- -----
1.93E+8 ----- 3.72E+8 ----- 1.25E+10 2.44E+7 l Ru-106 -----
1.06E+7 9.76E+6 ----- 1.92E+7 ----- 3.98E+9 5.80E+6 f Aq-110m 2.95E+9 Sb-124 1.04E+8 1.96E+6 2.52E+5 ----- 8.08E+7 4.11E+7 l 1.36E+8 1.52E+6 1.39E+5 ----- 1.05E+8 1.50E+9 3.25E+7 l Sb-125 3 86E+8 1.29E+7 !
Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -----
l 1.25E+8 8.92E+7 1.42E+9 ----- 1.17E+9 4.26E+7 i Te-127m 3.49E+8 4.03E+7 2.55E+B 9.50E+7 8.75E+7 1.06E+9 ----- 1.28E+9 To-129m 3.05E+7 6.63E+7 l I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -----
4.66E+9 1.llE+10 ----- 3.59E+9 1.19E+9 1.94E+8 9.07E+9 j Cs-134 1.66E+8 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-136 4.20E+7 -----
1.68E+8 5.70E+9 Cs-137 6.36E+9 8.70E+9 ----- 2.95E+9 9.81E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ba-140 1.29E+8 -----
5.08E+8 1.51E+4 Ce-141 1.96E+5 1.33E+5 ----- 6.17E+4 -----
b Am Co-144 3.29E+7 1.38E+7 ----- 8.16E+6 -----
1.llE+10 2.78E+8 1.77E+6 3.14E+3 Pr-143 6.34E+4 2.54E+4 ----- 1.47E+4 -----
I 2.25E+4 ----- 1.85E+8 2.31E+3 Nd-147 3.34E+4 3.86E+4 -----
56
N_ ' TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) VEGETATION PATHUAY FACTOR - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luna GI-LLI Total 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-51 ----- ------ 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 3.00E+7 Co-58 -----
4.38E+7 ----- ----- -----
6.04E+8 1.01E+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
-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.llE+10 1.85E+11 Y-91 7.87E+6 ----- ----- ----- -----
3.23E+9 2.llE+5 2r-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+8 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 ----- 1.48E+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.llE+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 -----
1.88E+8 1.66E+9 5.00E+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 1.08E+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 Bs-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 w ec-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 57
A
')
i TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) VEGETATION PATHWAY FACTOR - CHILD (mrem /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 Total 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. ole +5 P-32 3.37E+9 1.58E+8 ----- ----- -----
9.30E+7 1.30E+8 Cr-51 ----- -----
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 a.00E+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
-Mi-63 3.95E+10 2.llE+9 ----- ----- -----
1.42E+8 1.34E+9 8.12E+8 2.16E+9 1.36E+9 -----
3.80E+8 1.35E+9 (v -65 k
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-95 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 -----
4.05E+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+9 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 2.29E+10 2.29E+10 ----- 7.46E+9 2.68E+9 1.43E+8 3.38E+9 Bc-140 2.77E+8 2.43E+5 ----- 7.90E+4 1.45E+5 1.40E+8 1.62E+7 1.23E+5 6.14E+4 -----
2.69E+4 -----
7.66E+7 9.12E+3 4e-141 e-144 1.27E+8 3.98E+7 -----
2.21E+7 2.41E+4 1.04E+10 1.60E+8 6.78E+6 7.37E+3 Pr-143 1.48E+5 4.46E+4 ----- -----
Nd-147 7.16E+4 5.80E+4 ----- 3.18E+4 -----
9.18E+7 4.49E+3 58
TABLE 2-4 (Con't)
PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GROUND PLANE PATHWAY FACTOR (m2
- mrea/yr per uCi/sec)
Nuclide Any Organ 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 2.16E10 Ni-63 -----
Zn-65 7.45E 8 Rb-86 8.98E 6 Sr-89 2.16E 4 Sr-90 -----
Y-91 1.08E 6 Zr-95 2.48E 8 Nb-95 1.36E 8 Ru-103 1.09E 8 Ru-106 4.21E 8 Ag-110m 3.47E 9 Te-125m 1.55E 6 Te-127m 9.17E 4 Te-129m 2.00E 7 I-131 1.72E 7 i Cs-134 6.75E 9 l Cs-136 1.49E 8 Cs-137 1.04E10 Ba-140 2.05E 7 Ce-141 1.36E 7 Ce-144 6.95E 7 Pr-143 -----
Nd-147 8.40E 6 O 59
9 O
APPENDIX A EVALUATION OF DEFAULT MPC VALUES FOR LIQUID EFFLUENTS O
O A-1
'{W3 _ sg
~
s p
g r^s s
~- APPENDIX A Evaluation of Def ault MPC Value ,
for Liquid Effluents _
.m fl In accordance with the requirements of Technical Specification 4 3.3.3.10 the radioactive ef fluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed tha 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 radionuclide distribution and corresponding MPC values.
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 Hope Creek FSAR, Section 11.2, Table 11.2-11 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:
= (A.1)
MPCe
{"Ci/[(Ci/MPCi) where:
MPCe = 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 1 (uCi/ml)
O A-2
4 1O Pased on the above equation and the radionuclide distribution in the effluents for Hopa Creek from FSAR Table 11.2-11 (Expected Yearly Activity Released from Liquid Radwaste Management).
Results are presented in Table A-1.
I Considering the average effective MPC values from FSAR Table r
j 11.2-11 it is reasonable to select an MPC value of 1.4E-05 uCi/ml as typical of liquid radwaste discharges. Tnis value will be
{
reviewed and adjusted as necessary based on the distribution history of effluents from Hope Creek. Using the value of uCi/ml to calculate the default alarm setpoint, results in a setpoint that:
1
- 1) Will not required frequent re-adjustment due to minor i variations in the nuclide distribution which are i
typical of routine plant operations, and; l
- 2) will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (Refer to Table 1-1).
i i
I l
l 1
l 1
i l
i l r 3
1:
A-3 i
.,,__,__..._s..._,. , . _ - , _ , , _ , _ _ . _ _ . . , . . _ , _ _ , , . _ . , . . . . , _ _ . . . _ , . , . _ _ _ _ . , _ _ . . . . _ . . _ , _ . . _ - , _ _ ._,,.,,.-_.,__.___.,...___,,_,.,,_._m.,._. , _ _
I l
- t.g TABLE A-1 l CALCULATION OF EFFECTIVE MPC HOPE CREEK r
EXPECTED ACTIVITY
- NUCLIDE MPC RELEASED (Ci)
Na-24 2.0E-04 9.3E-03
} P-32 2.0E-03 7.0E-04 Cr-51 1.0E-04 2.3E-02 Mn-54 1.0E-04 1.3E-03 Mn-56 1.0E-04 5.4E-03 2
Fe-55 8.0E-04 4.3E-03 Fe-59 6.0E-05 1.2E-04 Co-58 1.0E-04 4.8E-03 O Co-60 5.0E-05 1.0E-02 Ni-65 1.0E-04 3.2E-05 Cu-64 3.0E-04 2.4E-02 2n-65 1.0E-04 8.5E-04 2n-69m 7.0E-05 1.7E-03 2n-69 2.0E-03 1.8E-03 2r-95 6.0E-05 1.4E-03 i Nb-95 1.0E-04 2.0E-03 W-187 7.0E-05 4.lE-04 i Np-239 1.0E-04 1.5E-02 Br-83 3.0E-06 3.6E-04 Br-84 3.0E-06 1.4E-05 Sr-89 3.0E-06 4.lE-04
! Sr-90 3.0E-07 3.0E-05 t
Y-90 2.0E-05 1.4E-05 Sr-91 7.0E-05 2.4E-03 (Cont'd)
A-4
1 O
TABLE A-1 (CONT'D)
CALCULATION OF EFFECTIVE MPC HOPE CREEK EXPECTED ACTIVITY
- NUCLIDE MPC RELEASED (Ci)
Y-91m 3.0E-03 1.5E-03 Y-91 3.0E-05 2.6E-04 Sr-92 7.0E-05 1.2E-04 Y-92 6.0E-05 2.9E-03 Y-93 3.0E-05 2.6E-03
= Nb-95 1.0E-05 3.4E-05 Nb-98 3.0E-06 4.5E-05 l Nb-99 2.0E-04 4.7E-03
- Tc-99m 6.0E-03 1.lE-02 Ru-103 8.0E-05 2.2E-04 i Rh-103m 1.0E-02 7.9E-05 Tc-104 3.0E-06 1.4E-05 Ru-105 1.0E-04 4.8E-04 Rh-105m 3.0E-06 4.8E-04 Ru-106 1.0E-05 4.3E-04 Rh-106 3.0E-06 2.4E-03 l
, Ag-110m 3.0E-05 1.3E-05 Te-129m 3.0E-05 4.4E-04 Te-129 8.0E-04 1.6E-04 Te-131m 6.0E-05 1.0E-04 Te-131 3.0E-06 1.6E-04 I I-131 3.0E-07 2.9E-05 Te-132 3.0E-05 1.0E-01 I-132 8.0E-06 2.5E-05 (Cont'd)
O A-5
O TABLE A-1 (CONT'D)
CALCULATION OF EFFECTIVE MPC HOPE CREEK ,
EXPECTED ACTIVITY
- NUCLIDE MPC RELEASED (Ci)
I-133 1.0E-06 3.4E-03 I-134 2.0E-05 4.4E-02 Cs-134 9.0E-06 9.lE-04 I-135 4.0E-06 1.3E-02 Cs-136 9.0E-05 1.lE-02 Cs-137 2.0E-05 1.lE-03 Ba-137m 3.0E-06 2.4E-02 Cs-138 3.0E-06 2.7E-04 Ba-139 3.0E-06 3.0E-04 Ba-140 2.0E-05 1.4E-03 x_ La-140 2.0E-05 7.3E-04 La-141 3.0E-06 1.7E-04 Ce-141 9.0E-05 1.3E-04 La-142 3.0E-06 2.5E-04 Ce-143 4.0E-05 5.0E-05 Pr-143 5.0E-05 1.5E-04 Ce-144 1.0E-05 5.2E-03 Pr-144 3.0E-06 1.3C-05 All Others 3.0E-08 4.3E-05_
TOTAL 3.5E-01 SUM (Ci/MPCi) 2.6E+04 MPCe (uCi/ml) 1.4E-05
- From Hope Creek Final Safety Analysis Report, Table 11.2-11.
O I A-6
O l
l
\
l
\
\
APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS LIQUID RADIOACTIVE EFFLUENT O
i i
I O
B-1
-.---_,.,,-n--,
/N
\
)
APPENDIX B Technical Basis for Effective Dose Factors -
Liquid Effluent Releases The expected radioactive liquid effluents from Hope Creek FSAR (Table 11.2-12) were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the expected radionuclide distribution of effluents from Hope Creek FSAR (Table 11.2-12), the controlling organ is the GI-LLI. The calculated GI-LLI dose is predominately a function of the Nb-95, Mn-54, Mn-56 and Ce-144 releases. The radionuclides, Co-58 and Co-60 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.
\(~N) x, 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 Nb-95 dose conversion factor (1.51E6 mrem /hr per uCi/ml, GI-LLI). By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose factor of all the radionuclides evaluated. For the total body calculation, the Cs-134 dose factor (6.48E5 mrem /hr per uC1/ml, total body) is the highest amoung the identified dominant nuclides.
For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may be used:
Total Body 1.67E-02
- VOL Dtb = ---------
- Ai,TB * {Ci CTBD O
B-2
O LJ Where:
Dtb = dose to the total body (mrem)
Ai,TB = 6.48ES, total body ingestion dose conversion factor for Cs-134 where A is dose conversion factor, i is isotope which is Cs-134, and TB is total body. (mrem /hr per uCi/ml)
VOL = volume of liquid effluent released (gal)
C = total concentration of all radionuclides (uCi/ml)
CTBD = average cooling tower blowdown discharge rate during release period (gal / min) j 1.67E-02 = conversion factor (hr/ min) i Substituting the value for the Cs-134 total body dose conversion factor, the equation simplified to:
1.08E4 VOL Dtb = --------
- J,Ci CTBD n/
N. Maximum Organ 1.67E-02
- VOL
- Aio, GI-LLI Dmax = ---------------- *7_Ci CTBD
! Where:
Dmax = maximum organ dose (mrem)
Ai,0 = 1.51E+06, GI-LLI ingestion dose conversion factor for Nb-95 where A is dose conversion factor, i is isotope which is Nb-95 and O is maximum organ which is GI-LLI. (mrem /hr per uCi/ml)
Substituting the value for Aio the equation simplifies to:
i 2.52E+04 VOL Dmax = ---------
- Ci CTBD i
' 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.
B-3 l
. - . . - - - _ . - _ . . _ _ _ . _ . - _ _ - . - . - . - - _ . - . . - . . . . . _ . - - . - . - - - - - ~ -
O TABLE B-1 Adult Dose Contributions Fish and Invetebrate Pathways Hope Creek
- GI-LLI Radionuclide Release (Ci) TB Dose Frac. Dose Frac.
- 0.13 Mn-54 1.3E-3 Mn-56 5.4E-3 ** 0.17
- 0.07 Cu-64 2.4E-2
- 0.09 Cs-144 5.2E-3
- = Release data based on FSAR Table 11.2-12
- = Less than 0.01 O
B-4
a l
l 4
6 APPENDIX C TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADIOACTIVE EFFLUENT O
1 O
C-1 l
O
> 1 kJ 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 released to approximate the dose in the environment. Instead of having to perform individual radioluclide dose analysis only a single multiplication (i.e.,
Keff, Meff, or Neff times the total quantity of radioactive material released) would be needed. The approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculation technique.
Determination of Ef fective Dose Factors g
Effective dose transfer factors are calculated by the following
'- equations:
Keff =
{_ (Ki fi)
Where:
Keff = 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.
fi = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity.
ds (L + 1.1 M)eff = E ((Li + 1.1 Mi)
- fi)
Where:
(L + 1.1M)eff = the effective skin dose factor due to beta and gamma emissions from all noble gases released.
C-2
/ \
i }
V (Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released.
Meff =
[_ (Mi fi)
Where:
Meff = the effective air dose factor 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.
ds Neff =[_(Ni fi)
Where:
Neff = 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 for the determination of the effective dose factors. However, the noble gas releases from Hope Creek have a short history. So, to provide a reasonable basis for the derivation of the effective noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, " Source Term Specifications",
Table 5 has been used as representing a typical distribution.
The effective dose factors as derived are presented in Table B-1.
Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservatism provides 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.
For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:
. 3.17E-08
- Dx = ----- X/O Meff * [_ O i 0.50
\. and C-3
l'h 3.17E-08 Db
= -----
- X/O
- Neff * [. O i 0.50 Where:
D = 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/O = atmospheric dispersion J
to the controlling site boundary (sec/m )
Meff = 8.lE3, effective gamma-air dose factor (mrad /yr per uCi/m3)
Neff = 8.5E3, effective beta-air dose factor (mrad /yr per uCi/m 3)
Qi = cumulative release for all noble gas radionuclides (uci)
-s 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:
D = 5.14E-4
- X/O
- E Qi Db
= 5.39E-4
- X/O
- EQi 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, i
4 O
C-4 i
t
1 (O
G TABLE C-1 Effective Dose Factors Noble Gases - Total Body and Skin Total Body Effective Skin Effective Keff (L + 1.1 M) eff (mrem /y per uCi/m3) (mrem /y per uCi/m3)
Radionuelide_ fi*
Kr83m 0.01 1.0El 2.8E1 Kr85m 0.01 2.4E2 6.6E2 Kr87 0.04 7.6E2 Kr88 0.04 5.9E2 4.5E3 7.9E3 Kr89 0.27 1.4El Xel33 0.02 5.9E0 9.0El 2.0E2 Xel35 0.05 1.9E2 2.6E2 Xe135m 0.06 4.3E3 Xel37 0.31 4.4E2 1.7E3 2.7E3 Xe138 0.19 7.8E3 1.7E4 TOTAL Noble Gases - Air Gamma Air Effective Betta Air Effective Meff Neff (mrad /y per uCi/m3)_ (mrad /y per uCi/m3)
Radionuclide fi*
3.0E0 Kr83m 0.01 -----
2.0El Kr85m 0.01 1.2El 2.5E2 4.lE2 Kr87 0.04 2.0E2 Kr88 0.04 6.lE2 4.7E3 2.9E3 Kr89 0.27 7.0E0 2.lEl Xel33 0.02 9.6El 1.2E2 Xe135m 0.05 4.4El Xe135 0.06 2.0E2 4.7E2 3.9E3 Xel37 0.31 9.0E2 Xel38 0.19 1.8E3 8.1E3 8.5E3 TOTAL
- Based on noble gas distribution from ANSI N237-1976/ANS-18.1,
" Source Term Specification".
O) u C-5
AA - - _. m O
APPENDIX D TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETER GASEOUS RADIOACTIVE EFFLUENT p
. O D-1
1 l
1 (D
t I
\_/ APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ 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 - milk - cow (g/m/c) pathway.
An infant receives a greater radiation dose from the g/m/c pathway than any other pathway. Of this g/m/c 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 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 dose commitment via a controlling pathway and age group, it is conservative to use the 2 infant, g/m/c, thyroid, I-131 pathway dose factor (1.67E12m mrem /yr per uCi/sec). By 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:
Dmax = 3.17E-8
- W
- RI-131
- Qi Where:
Dmax = maximum organ dose (mrem)
W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.
X/O = Atmospheric dispersion for inhalation pathway and3 H-3 dose contribution via other pathways (sec/m )
D-2
~
t n/'- D/O = atmospheric disposition for vegetation, milk and -
ground plane exposure pathways (m-2)
Oi = cumulative release over the period of interest for radiciodines and particulates (uci) .
, / >
3.17E-8= conversion' factor (yr/sec)
RI-131 = I-131; dose parameter for the thyroid for tha identified controlling pathway ,
= 1.675E12, infant thyroid dose parameter with the cow - milk - grass pathway controlling'{m 2nrem/yr per uCi/sec) s The ground plane exposure and inhalatir/n pathways,need not be ;
considered when the above simplified calculaticual method is used -
because of the overall negligible contribution o'f th,ese pathways' to the total thyroid dose. It is recognized that for some 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 O
pathway than I-131 for the thyroid via the milk pathway.
The location of exposure pathways and the maximum organ dose -g ,
calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual '
land-use census (Technical Spec'ification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling '
pathways as identified 1.n Table 2-3.
/
s 9
/
D-3 4
s r- - -a-, . - ---- - . . - - , . - , , , _ , - -,-n ,n,_n,- . , . . - - - - - - - - - - , , . , ,..m__,,s, , - - ~ - - - - - . ~ , . -
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- l. s TABLE D-1 I
.' Infant Dose Contributions
[
Fraction of Total Organ and Body Dose '
I fi. r PATHWAYS lf ,
Target Organs Grass - Cow - Milk Ground Plane j.. Total Body 0.02 0.15
- 1 Bone 0.23 0.14 Liver 0.09 0.15 1
1 Thyroid 0.59 0.15 b
Kidney 0.02 0.15 l
Lung 0.01 0.14 4
GI-LLI 0.02 0.15 j-i i
TABLE D-2 i
i Fraction of Dose Contribution by Pathway Pathway 1 i ,
Grass-Cow-Milk 0.92 l
Ground Plane 0.08 l *
! Inhalation l
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s D-4
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APPENDIX E
)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -
SAMPLE TYPE, LOCATION AND ANALYSIS l
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b 's V ,1 TABLE E-1 Page 1 of 7 ODCM - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION METHOD ANALYSES PATHWAY STATION CODE LOCATION I. DIRECT 5.8 miles N of origin 2 TLD's will be collected Gamma dose IFl from each location quarterly quarterly 1G3 # 18.5 miles N of origin 2S2 0.4 miles NNE of origin 2El 4.4 miles NNE of origin 2F2 8.7 miles NNE of origin
' 2F5 7.4 miles NNE of origin 2F6 7.3 miles NNE of origin 3El 4.1 miles NE of origin 3F2 5.1 miles NE of origin 3F3 8.6 miles NE of origin 3G1 4 16.6 miles NE of origin 3H1 # 32 miles NE of origin 3I13 # 110 miles NE of origin 4D2 3.7 miles ENE of origin SS1 1.0 mile E of origin SD1 3.5 miles E of origin
- 5F1 8.0 miles E of origin 6S2 0.2 miles ESE of origin 6F1 6.4 miles ESE of origin 7S1 0.12 miles SE of origin 7F2 9.1 miles SE of origin 9El 4.2 miles S of origin 10S1 0.14 miles SSW of origin 10D1 3.9 miles SSW of origin 5.8 miles SSW of origin Collected quarterly Gamma-dose 10F2 quarterly 10G1 # 11.6 miles SSW of origin
- Control Station 1 M P85 183/15 4-dh
O O O P;ga 2 of 7 TABLE E-1 ODCM - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES i[. DIRECT (Con't) 10F2 5.8 miles SSW of origin Collected quarterly Gamma dose quarterly 10G1 # 11.6 miles SSW of origin 11S1 0.07 miles SW of origin 11E2 5.0 miles GW of origin 11F1 5.2 miles SW of origin 12El 4.4 miles WSW of origin 12F1 9.4 miles WSW or origin 13E1 4.2 miles NE of origin 13F4 9.8 miles W of origin 13F2 6.5 miles W of origin 13F3 9.3 miles W of origin 14D1 3.4 miles WNW of origin 14F2 6.6 miles WNW of origin 15F3 5.4 miles NW of origin 16El 4.1 miles NNW of origin 16F2 8.1 miles NNW of origin 16G1 # 14.8 miles NNW of origin i
- Control Station (in addition to controls listed, two additional program controls are used for internal studies and are referred to as SITE-CAL and SITE-ZERO).
1 M P85 183/15 4-dh
O O O Pags 3 cf 7 TABLE E-1 ODCM - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TYPE AND FREQUENCY EXPOSURE COLLECTION METHOD OF ANALYSES PATHWAY STATION CODE LOCATION
- I. AIRBORNE 0.4 miles NNE of origin Continous low volume air Gross beta analysis (a) P 2S2 on each weekly sampler. Sample collected A sample. Gamma every week along with filter R
change. spectrometry shall T be performed if 2F2 8.7 miles NNE of origin I gross beta exceeds C ten times the L yearly mean of A control station T value.
E S Gross beta analysis 3H3 # 110 miles NE of origin done > 24hr. after sampling to allow for Radon and Thoron daughter decay 10D1 3.9 miles SSW of origin 4.1 miles NNW of origin Gamma isotopic 16El analysis on quarterly composite
- Control Station M P85 183/15 4-dh
] TABLE E-1 Prga 4 of 7 i
ODCN - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL NONITORING PROGRAM TYPE AND FREQUENCY EXPOSURE COLLECTION METHOD OF ANALYSES PATHWAY STATION CODE LOCATION
- I. AIRBORNE (Con't)
A TEDA impregnated charcoal Iodine 131 analyses 2S2 0.4 miles NNE of origin (b) I flow-through cartridge is are perfotmed on O connected to air particulate each weekly sample.
D air sampler and is collected I
weekly at filter change.
N E 2F2 8.7 miles NNE of origin 3H3 # 110 miles NE of origin 16El 4.1 miles NNW of origin 10D1 3.9 miles SSW of origin i
i
- Control Station M P85 183/15 4-dh i
I
O O TABLE E-1 O
Prg3 6 of 7 ODCM - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES l1 INGESTION ,
(a) M 2F4 6.3 miles NNE of origin Sample of fresh milk is Gamma isotopic and I collected for each farm I-131 analyses on L semimonthly when cows each sample on i
K are on pasture, monthly collection at other times.
3G1 # 16.6 miles NE of origin 5F2 7.0 miles E of origin 13E3 4.9 miles W of origin 14F1 5.5 miles WNW of origin (b) F llAl Outfall area; approx. Two batch samples of fish Gamma isotopic I 650 feet SW of origin are sealed in plastic bag analysis of edible S or jar and frozen portion on H semiannually or when in collection in season 12Cl I West bank opposite Artificial Island; J 2.5 miles WSW of origin i
i 1
- Control Station M P85 183/15 4-dh J
O O O TABLE E-1 Page 5 of 7 ODCM - HOPE CREEK GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES I. WATER i (a) S 7El 1 mile W of Mad Horse Sample to be collected Gamma isotopic
, U Creek; 4.5 miles SE of monthly providing winter analysis monthly R origin icing conditions allow F sample collection H-3 on quarterly A composite C 12C1 # West bank opposite E Artificial Island; 2.5 miles WSW of origin 16F1 C&D canal; 6.9 miles NNW of origin ,
(b) G 2S3 Fresh water holding tank; R 700 feet NNW of origin O 5D1 Local farm; 3.5 miles E Collected monthly Gamma isotopic U of origin monthly N 3E1 Local farm; 4.1 miles Tritium analysis i D NE of origin monthly (c) S 7El 1 miles W of Mad Horse A sediment sample is Gamma isotopic E Creek 4.5 miles SE of taken semi-annually anaylsis - semi-
, D origin annually I 12Cl # West bank opposite
- M Artificial Island; 2.5 E miles WSW of origin
, N 16F1 C&D Canal; 6.9 miles NNW T of origin i Control Station M P85 183/15 4-dh
__ ~
uun E-1 ODCM - HOP s
RADIOLOGICAL EN EK E. 4WAY GENERATING IV. STATION CODE MENTAL MONITORINGSTATION Pigs 7 of 7 INGESTION PROGRAM (Cont'd) LOCATION (c) I COLLECTION N llAl METHOD V
E Outfall 650 feetarea; app rox. ANALYSES R SW of origin T
E Two batch samples are 13C1 # of crab B bag or jarsealedainplastic semian and R ArtificialWest banke oppositseason.nually or frozen Gamma Isotopic analysis A Island; when in of T
2 5 miles WSW of o i r gin edible on portion E
S collection 4 Control M P85 183/154-dhStation 9 -
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