ML20239A125
| ML20239A125 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1998 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18106A856 | List: |
| References | |
| PROC-980331, NUDOCS 9809080240 | |
| Download: ML20239A125 (92) | |
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SALEM NUCLEAR GENERATING STATION 1
OFFSITE DOSE CALCULATION MANUAL Revision 11 March 1998 I
l REVISION
SUMMARY
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Section 1.2.1 - Removed note referencing inclusion of most recent l
composite of non-gamma emitters in.setpoint calculation j
Section 1.2.2 - Added discussion of basis for alarm setpoints during batch releases Safety Factor used in liquid effluent alarm setpoint calculations specified at 0.75 Incorporated chenges in gaseous rad monitor designation from R41C to R41D as per DCPs 1EC-3244 and 2EC-3212 Table E-1 deleted reference to TLD location changes noted in ODCM l
Rev. 10; changed control air sampler location from Maplewood to l
Delaware location.
Prepared by:
/2 [ M f_
Date:
3 /d/ 98-7
/
3)/v99 Reviewed by:
Date:
Date:
b
[
3 Approved by:
_ Y F
Approval SORC Chairman:
Date: 3 I T
Mtg. # N~ONd
)
1 9809080240 980827 PDR ADOCK 05000272.
R PDR,
Salem ODCM Rev. 11 SALEM NUCLEAR GENERATING STATION 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 (Radwaste, Steam Generator Blowdown and Service Water).............
4 1.2.2 Conservative Default values.......................
5 1.3 Liquid Effluent Concentration Limits - 10 CFR 20....
6 1.4 Liquid Effluent Dose Calculations - 10 CPR 50......
8 1.4.1 Member of the Public Dose - Liquid Effluents...... 8 1.4.2 Simplified Liquid Effluent Dose Calculation...... 10
,1.5 Secondary Side Radioactive Liquid Effluents - Dose Calculations During Primary to Secondary Leakage... 11 1.6 Liquid Effluent Dose Projection................... 12 2.0 Gaseous Effluents 2.1 Radiation Monitoring Instrumentation and Controls 13 2.2 Gaseous Effluent Monitor Setpoint Determination... 14 2.2.1 Containment and Plant Monitor................... 14 2.2.2 Conservative Default Values......................
15 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 2 0................. 16 2.3.1 Site Boundary Dose Rate - Noble Gases............
16 2.3.2 Site Boundary Dose Rate -
Radioiodine and Particulate 18 2.4 Noble Gas Effluent Dose Calculations - 10 CFR 50...
19 2.4.1 UNRESTRICTED AREA Dose - Noble Gases...........
19 2.4.2 Simplified Dose Calculation for Noble Gases......
20 2.5 nJdioiodine and Particulate Dose Calculations -
' OFR Sc........................................
21 2.5.1' UNRESTRICTED AREA Dose -
Radioiodine and Particulate 21 2.5.2 Simplified Dose calculation for Radioiodines j
and Particulate 22 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations 23 2.7 Gaseous Effluent Dose Projection.................
25 3.0 Special Dose Analyses 3.1 Doses Due To Activities Inside the SITE BOUNDARY... 26 3.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190.......
26 3.2.1 Effluent Dose Calculations.....................
27 3.2.2 Direct Exposure Determination..................
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Salem ODCM Rev. 11 Table of Contents - Continued 4.0 Radiological Environmental Monitoring Program.......... 28 4.1 Sampling Program.................................. 28 4. ;2 Interlaboratory Comparison Program................ 2B Radwaste System Flowpaths and Description................... 29 Tables 1-1 Parameters for Liquid Alarm Setpoint Determination
- Unit 1......................................... 32 1-2 Parameters for Liquid Alarm Setpoint Determination
- Unit 2 33 1-3 Site Related Ingestion Dose Commitment Factors, Ag.
34-35 1-4 Bioaccumulation Factors (Bfi) 36 2-1 Dose Factors for Noble Gases 39 2-2 Parameters for Gaseous Alarm Setpoint Determinations
- Unit 1......................................... 40 2-3 Parameters for Gaseous Alarm Setpoint Determinations
- Unit 2 41 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations 41 2-5 Pathway Dose Parameters - Atmospheric Releases 43-54 A-1 Calculation of Effective MPC - Unit 1........... A-6 A-2 Calculation of Effective MPC - Unit 2........... A-7 B-1 Adult Dose Contributions Fish and Drinking Water Pathways Unit 1 B-5 B-2 Adult Dose Contributions Fish and Drinking Water B-5 Pathways Unit 2 C-1 Effective Dose Factors.......................... C-4 D-1 Infant Dose Contribution Fraction of Dose....... D-5 D-2 Fraction of Dose Contribution by Pathway........ D-5 I
E-1 Environmental Sampling Locations................ E-3 Appendices Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents A-1 Appendix B - Technical Basis for Effective Dose Factors -
Liquid Radioactive Effluents B-1 Appendix C - Technical Basis for Effective Dose Factors -
Gaseous Radioactive Effluents........... C-1 Appendix D - Technical Basis for Effective Dose -
Parameters - Gaseous Effluents D-1 Appendix E - Radiological Environmental Monitoring Program - Sample Type, Location and Analysis............................ E-1 l
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Salem ODCM Rev. 11 4
SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL 1
Introduction The Salem Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in:
- 1) the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints; and
- 2) the calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and yearly doses.
The methodology stated in this manual is acceptable for use in demonstrating compliance with 10 CFR 20.106, 10 CFR 50, Appendix I and 40 CFR 190. More conservative calculation metheds 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 Salem Technical Specifications.
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1 Salem ODCM Rev. 11 1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Salem Radiological Effluent Technical Specifications are summarized as follows:
1)
Alarm (and Automatic Termination) R18 (Unit 1) and 2-R18 (Unit 2) provide the alarm and automatic termination of
. liquid radioactive material releases as required by Technical Specification 3.3.3.8.
1-R19 A,B,C, and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines.
2-R19 A,B,C and D provide this function for Unit 2.
2)
Alarm (only) - The alarm functions for the Service Water System are provided by the radiation monitors on the Containment Fan Cooler discharges (1-R 13 A,B,C,D and E for Unit 1 and 2-R 13 A,B,and C for Unit 2).
Releases from the secondary system are routed through the Chemical Waste Basin where the effluent is monitored (with an alarm function) by R37 prior.to release to the environment.
Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 1-1 and 1-2 for Units 1 and 2, respectively.
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Salem ODCM Rev. 11 1.2-Liquid Effluent Monitor Setpoint Determination 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 )
(1.1) c$
f where:
C=
the effluent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uC1/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 concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA f=
the flow rate at the radiation monitor location, in volume per unit time, but in the same units as F, below F=
the dilution water flow rate as measured prior to the release point, in volume per unit time
[ Note that if no dilution is provided, c $ C.
Also, note l
that when (F) is large compared to (f), then (F + f)
=
F.]
Adapted from NUREG-0133 I
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Salem ODCM Rev. 11 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service Water.
The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations:
SF MPCe
- SEN
+ bkg (1.2)
RR with:
E Ci MPCe =
(1.3)
Ci E
MPCs where:
alarm setpoint corresponding to the maximum SP
=
allowable release rate (cpm)
MPCe =
an effective MPC value for the mixture of radionuclides in the effluent stream (uCi/ml) the concentration of radionuclides i in the undiluted Ci
=
liquid effluents (uci/ml)
- MPCs =
the MPC value corresponding to radionuclides i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml) the sensitivity value to which the monitor is SEN
=
calibrated (cpm per uCi/ml) the circulating water flow rate (dilution water CW
=
flow) at the time of release (gal / min) the liquid effluent release rate (gal / min)
=
the background of the monitor (cpm) bkg
=
Safety factor to account for non-gamma SF
=
emitting nuclides in default setpoint calculations.
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Salem ODCM Rev. 11 The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value.
Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.
However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-1 or Unit-2 Circulating Water System discharge.
This routing is possible via interconnections between the Service Water Systems (see Pages 29 and 30).
Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.
1.2.2 Conservative Default Values.
Conservative alarm setpoints may be determined through the use of default parameters.
Tables 1-1 and 1-2 summarize all current default values in use for Salem Unit-1 and Unit-2, respectively.
They are based upon the following:
a) substitution of the effective MPC value with a default value of 6.05E-06 uCi/ml (Unit 1) and 4.81E-06 uci/ml (Unit 2). (refer to Appendix A for justification);
b) for additional conservatism *, substitution of the I-131 MPC value of 3E-07 uCi/ml for the R19 Stean Generator Blowdown Monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water Monitors.
c) substitutions of the operational circulating water flow with the lowest flow, in gal / min; and, d) substitutions of the effluent release rate with the highest allowed rate, in gal / min.
e) substitution of a safety factor of 0.75 to account for non-gamma emitting nuclides.
For batch liquid releases a fixed alarm setpoint is established for the 1,2 R18 monitors and the release rate is controlled to ensure the inequality of equation 1.1 is maintained.
With this approach, values selected for the parameters in the setpoint calculation (e.g., Table 1-1 and Table 1-2) should be any set of 5
1 Salem ODCM Rev. 11 reasonable values that provide a setpoint value significantly above anticipated monitor response, plus background, so as not to yield spurious alarms.
The release rate is controlled to ensure compliance with the requirements of Technical Specification 3.3.3.8.
Calculations, as performed by Engineering, to establish the-actual fixed setpoints for use in the plant, incorporate uncertainties and instrument drift.
These factors will cause the actual installed instrument setpoint to be at a lower (conservative) value.
However, for batch releases, when the rate is controlled, these uncertainties and drift should not be included in the evaluation of acceptable release rate, since this could cause a non-conservative correction, i.e.,
a higher allowable release rate.
Therefore, for 1,2 R1B monitors, the setpoint value used for calculating the allowable release rate should be that value prior to correction for uncertainty and drift.
Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1, 2 R-19 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the R-13 Service Water Monitors.
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Salem ODCM Rev. 11 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 LTechnical Specification 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix-B, Table II, Column 2 for radionuclides other than noble gases.
Noble gases are limited to a diluted concentration of 2.0E-04.uci/ml.
Release rates are controlled and radiation monitor alarm 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 Specification 3.11.1.1 may be performed using the following equation:
RR C2 E_
$1 (1.4)
Ci
= actual concentration of radionuclides i as measured in the undiluted liquid effluent (uci/ml)
MPC = the MPC value corresponding to radionuclides 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)
=.the actual circulating water flow rate (dilution water flow) at the time of the release (gal / min) l 7
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Salem ODCM Rev. 11 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 each unit of the Salem Nuclear Generating Station to:
1
- during any calendar quarter; 5 1.5 mrem to total body per unit 1 5.0 mrem to any organ per unit
- during any calendar year;
$ 3.0 mrem to total body per unit 5 10.0 mrem to any organ per unit.
Per the surveillance requirements of Technical Specification 4.11.1.2, the following calculational methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem.
1.67E-02
- VOL D. =
- E (Ci
- A.)
(1.5) i CW where:
D.
= dose or dose commitment to organ o (mrem).
Total body dose can also be calculated using site-related total body dose commitment factor.
A.=
site-related ingestion dose commitment factor to the i
total body or any organ o for radionuclides 1 (mrem /hr per uCi/ml) average concentration of radionuclides i, in undiluted C3
=
liquid effluent representative of the volume VOL s s~
(uC1/ml)
VOL= volume of liquid ef fluent released (gal)
CW =
average circulating water discharge rate during release period (gal / min) 1.67E-02=
conversion factor (hr/ min) 8 l
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Salem ODCM Rev. 11 The site-related ingestion dose / dose commitment factors
( A.)
are 1
presented in Table 1-3 and have been derived in accordance with the requirements of NUREG-0133 by the equation:
1.14E+05 ( (UI
- BI ) + (UF
- Bri) ] DFi (1. 6)
As.
=
t where:
composite dose parameter for the total body or A1.
=
critical organ o of an adult for radionuclides i, for the fish and invertebrate ingestion pathways (mrem /hr per uCi/ml)
UI =
adult invertebrate consumption (5 kg/yr)
BI = bioaccumulation factor for radionuclides i in t
invertebrates from Table 1-4 (pCi/kg per pCi/1)
UF = adult fish consumption (21 kg/yr)
BF = bioaccumulation factor for radionuclides i in fish i
from Table 1-4 (pCi/kg per pCi/1)
D Fi=
dose conversion factor for nuclide i for adults in pre-selected organ, o,
from Table E-11 of Regulatory Guide 1.109 (mrem /pCi) 1.14E+05=
conversion factor (pCi/uCi + ml/kg per hr/yr)
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.
Radionuclides requiring radiochemical analysis (e.g., St-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.
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1 Salem ODCM Rev. 11 1.4.2 Simplified Liquid Effluent Dose Calculation.
1 In lieu of the individual radionuclides dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance w3.th the dose limits of Technical Specification 3.11.1.2.
(Refer to Appendix B for the derivation and justification for this simplified method.)
l Total Body 1.21E+03
- VOL E C1 (1.7)
Da
=
CW Maximum Organ 2.52E+04
- VOL EC1 (1.8)
D.,,
=
CW where:
Ci
= average concentration of radionuclides i, in undiluted liquid effluent representative of the volume VOL (uCi/ml)
VOL = volume of liquid effluent released (gal)
= average circulating water discharge rate during release period (gal / min)
Da = conservatively evaluated total body dose (mrem)
D..= conservatively evaluated maximum organ dose (mrem) 1.21E+03 = conversion factor (hr/ min) and the conservative total body dose conversion factor (Fe-59, total body -- 7.27E+04 mrem /hr per uCi/ml) 2.52E+04 = conversion factor (hr/ min) and the conservative maximum organ dose conversion factor (Nb-95, GI-LLI
-- 1.51E+06 mrem /hr per uCi/ml) 10
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i Salem ODCM Rev. 11 l-1.5 secondary Side Radioactive Liquid Effluents and Dose Calculations During Primary to Secondary Leakage During periods of primary to secondary leakage (i.e.,
steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system.
The potential exists for the release of radioactive material to the off-site environment (Delaware River) via secondary system discharges.
Potentially significant radioactive material levels and potential releases are controlled / monitored by the Steam Generator blowdown monitors (R19) and the Chemical Waste Basin monitor (R37).
However to ensure compliance with the regulatory limits on radioactive material releases, it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage.
Any potentially significant releases will be via the Chemical Waste Basin with the major source of. activity being the Steam Generator blowdown.
With identified radioactive material levels in the secondary system, appropriate samples should be collected and analyzed for the principal gamma emitting radionuclides.
Based on the identified radioactive material levels and the volume of water discharged, the resulting environmental doses may be calculated based on equation (1. 5).
Because the release rate from the secondary system is indirect (e.g., SG blowdown is normally routed to condenser where the condensate clean-up system will remove much of the radioactive material), samples should be collected from the final release point (i.e., Chemical Waste Basin) for quantifying the radioactive material releases.
However, for conservatism and ease of controlling and quantifying all potential release paths, it is prudent to sample the SG blowdown and to assume all radioactive material is released directly to the environment via the Chemical Waste Basin.
This approach while not exact, is I
conservative and ensures timely analysis for regulatory compliance.
Accounting for radioactive material retention of the condensate clean-up system ion exchange resins may be needed to more accurately account for actual releases, 11
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l Salem ODCM Rev. 11 1.6 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 quarterly projected doses exceed:
1 0.375 mrem to the total body, or 1.25 mrem to any organ.
The applicable liquid waste processing system for maintaining radioactive material releases ALARA is the ion exchange system as delineated in Fjgure 1-3.
Alternately, the waste evaporator as presented in the Salem FSAR has processing capabilities meeting the NRC LLARA design requirements and may be used in conjunction or in lieu of the ion exchange system for waste processing requirements in accordance with Technical Specification 3.11.1.3.
These processing requirements are applicable to each unit individually.
Exceeding the projected dose requiring processing prior to release for one unit does not in itself dictate processing requirements for the other unit.
Dose projections are made at least once per 31 days by the following equations:
De (91 / d)
(1.9)
Deep
=
t D., (91 / d)
(1.10)
D.,p
=
where:
the total body dose projection for current calendar Deep
=
quarter (mrem)
Did the total body dose to date for current calendar
=
quarter as determined by Equation 1.5 or 1.7 (mrem)
D., p=
the maximum organ dose projection for current calendar quarter (mren) 4., = the maximum organ dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) the number of days to date for current calendar d
=
quarter the number of days in a calendar quarter 91
=
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Salem ODCM Rev. 11
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2.0 Gaseous Effluents l
2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are l
summarized as follows:
- 1) Waste Gas Holdup System - The vent header gases are collected by the I
waste gas holdup system. Gases may be' recycled to provide cover gas for the CVCS hold-up tank or held in the waste gas tanks for decay prior to release. Waste gas decay tanks are batch released after sampling and analysis. The tanks are discharged via the Plant Vent. 1-R41D provides l
noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1. This function is provided by 2-R41D for Unit-2.
2)
Containment Purge and Pressure / Vacuum Relief - containment purges and pressure / vacuum reliefs are released to the atmosphere via the respective unit Plant Vent.
Noble gas monitoring and auto isolation function are provided by 1-R41D for Unit-1 and 2-R41D for Unit-2.
Additionally, in accordance with Technical specification 3.3.3.9, Table 3.3-13, 1-R12A and 2-R12A may be used to provide the containment monitoring and automatic isolation function during purge and pressure / vacuum reliefs.*
3)
Plant Vent - The Plant Vent for each respective unit receives discharges from the waste gas hold-up system, condenser evacuation system, containment purge and pressure / vacuum reliefs, and the Auxiliary Building ventilation.
Effluents are monitored by R41D, a flow through gross activity monitor (for noble gas monitoring).
Additionally, in-line gross activity monitors (1-R16 and 2-R16) provide redundant back-up monitoring capabilities to the R41D monitors.
Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers.
Plant Vent flow rate is measured and as a back-up may be determined empirically as a function of fan operation (fan curves).
Sampler flow rates are determined by flow rate instrumentation (e.g., venturi rotameter).
The R12A monitors also provide the safety function of containment isolation in the event of a fuel handling accident during refueling.
During MODE 6 in accordance with Technical specification 3/4.3.3, Table 3.3-6, the R12A alarm / trip setpoint shall be established at twice background. This will provide containment isolation and indication of unexpected increases in containment airborne radioactive material levels which can be indicative of fuel degradation. The R41D monitor may also provide this function if the R12A monitor is inoperable during MODE 6.
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Salem ODCM Rev. 11 Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are i
presented as Figures 2-1 and 2-2 for Units 1 and 2, respectively.
2.2 Gaseous Effluent Monitor Setpoint Determination j
2.2.1 Containment and Plant Vent Monitor.
Per the requirements of Technical Specification 3.3.3.9, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem / year to the total body or 3000 mrem / year to the skin.
Based on a grab sample analysis of the applicable release (i.e.,
grab sample of the Containment atmosphere, waste gas decay tank, or Plant Vent), the radiation monitoring alarm setpoints may be established by the following calculation method.
The measured radionuclides I
concentrations and release rate are used to calculate the fraction of the allowable release rate,'as limited by Specification 3.11.2.1, by the equation:
FRAC = [4.72E+02
- X/Q
- E (Ci
- Ki) ) / 500 (2.1)
(Lt + 1.1 M ) ) ) / 3000 (2.2)
FRAC = [4.72E+02
- X/O
- Z (Cs i
l where:
FRAC = fraction of the allowable release rate based on the i
identified radionuclides concentrations and the release flow rate X/O = annual average meteorological dispersion to the 3
controlling site boundary location (sec/m )
= ventilation system flow rate for the applicable release point and monitor (f t*/ min)
Ci
= concentration of noble gas radionuclides i as determined 8
by radioanalysis of grab sample (uci/cm )
Ki
= total body dose conversion factor for noble gas 3
radionuclides 1 (mrem /yr per uCi/m from Table 2-1)
= beta skin dose conversion factor for noble gas Li 3
radionuclides 1 (mrem /yr per uCi/m from Table 2-1)
= gamma air dose conversion factor for noble gas Mi radionuclides 1 (mrem /yr per uCi/m' from Table 2-1) 1.1
= mrem skin dose per mrad gamma air dose (mrem / mrad) 500 = total body dose rate limit (mrem /yr) 3000 = skin dose rate limit (mrem /yr) 4.72 E+02 = conversion factor (cm /f t*
- min /sec) 8
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Salem ODCM Rev. 11 l
Based on the more limiting FRAC (i.e., higher value) as determined l
l above, the alarm setpoints for the applicable monitors (R16, R41D, and/or R12A) may be calculated by the equation:
SP = [AF
- E Ci
- SEN / FRAC) + bkg (2.3) where:
SP alarm setpoint corresponding to the maximum
=
allowable release rate (cpm)
SEN = monitor sensitivity (cpm per uCi/cm')
bkg =
background of the monitor (cpm)
AF administrative allocation factor for the specific
=
monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the release.
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, the combined AF value for Salem Units 1 and 2 is equal to 0.5 (0.25 per unit), with the remainder 0.5' allocated to Hope Creek.
Any increase in AF above 0.5 for the Salem Nuclear Generating Station will be coordinated with the Hope Creek Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.
2.2.2-Conservative Default Values.
A conservative alarm setpoint can be established, in lieu of the individual radionuclides evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclides distribution and variations in release flow rate.
The alarm setpoint may be conservatively determined by the default values presented in Table 2-2 and 2-3 for Units'1 and 2, respectively.
These values are based upon:
the maximum ventilation (or purge) flow rate; a radionuclides distribution
- comprised of 95% Xe-133, 2% Xe-135, 1% Xe-133m, 1% Kr-88 and 1% Kr-85; and an administrative allocation factor of 0.25 to conservatively ensure that any simultaneous releases from Salem Units 1 and 2 do not exceed the maximum allowable release rate. For this radionuclides distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate.
- Adopted from ANSI'N237-1976/ANS-18.1, Source Term Specifications, Table 6 l
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Salem ODCM Rev. 11.
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 $500 mrem /yr, total body and
$3000 mrem /yr, skin.
Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.
In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:
Da = X/Q
- E (Ki
- Qi)
(2.4) and D, = X / Q
- E((L1 + 1.1M )
- Qi)
(2. 5) 1 where:
Da = total body dose rate (mrem /yr) skin dose rate (mrem /yr)
D.
=
X/O = atmospheric dispersion to the controlling SITE 3
BOUNDARY location (sec/m )
average release rate of radionuclides i over the Qi
=
release period under evaluation (uci/sec) total body dose conversion factor for noble gas K
=
i radionuclides i (mrem /yr per UCi/m', from Table 2-1)
= beta skin dose conversion factor for noble gas Lt radionuclides 1 (mrem /yr per uCi/m', from Table 2-1)
= gamma air dose conversion factor for noble gas Mi radionuclides 1 (mrad /yr per uCi/m', 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 release exceeding the above prescribed alarm setpoints.
Monitor indications (readings) may be averaged over a time period not
-to exceed 15 minutes when determining noble gas release rate 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 s
16 j
j i
l I
_..___.________._J
Salem ODCM Rev. 11 electronic spiking monitor responses may be excluded from the analysis.
NOTE:
For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed.
- However, conditions exceeding these more limiting alarm setpoints do not i
necessarily indicate radioactive material release rates l-exceeding the limits of Technical Specification 3.11.2.la.
l 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 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.
l 17
Salem ODCM Rev. 11 2.3.2 Site Boundary Dose Rate - Radiciodine and Particulate.
Technical Specification 3.ll.2.1.b limits the dose rate to <l500 lives greater than 8 days. To demonstrate compliance with this limit, &n evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g.,
nominally once per 7 days).
The following equation shall be used for the dose rate evaluation:
l Z [R.
- Qi)
(2.6)
X/Q
- D.
=
t where:
l D.
= average organ dose rate over the sampling time period (mrem /yr)
X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m')
dose parameter for radionuclides i (mrem /yr per uCi/m')
Rt.
=
l and organ o for the child inhalation pathway from Table 2-5 Qi
= average release rate over the appropriate sampling period and analysis frequency for radionuclides i --
I-131, I-133, tritium or other radionuclides in particulate form with half-life greater than 8 days (uci/sec) l f
By substituting.1500 mrem /yr for D and solving for Q, an allowable release rate for I-131 can be determined.
Based on the annual average meteorological dispersion (see Taole 2-4) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid --
Rs. = 1. 62E+07 mrem /yr per uCi/m'), the allowable release rate for I-131 is 42 uCi/sec.
Reducing this release rate by a factor of 4 to account for potential dose contributions from othtr radioactive particulate material and other release points (e.g., Hope Creek), the corresponding release rate allocated to each of the Salem units is 10.5 uCi/sec.
For a 7 day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 6.3 Ci.
Therefore, as long as the I-131 releases in any 7 day period do not exceed 6.3 Ci, no additional analy",es are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.
l t
18
l Salem ODCM Rev. 11 l
2.4 Noble Gas Effluent Dose Calculations - 10 CFR 50 l
2.4.1 UNRESTRICTED AREA Dose - Noble Gases.
l Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of $5 mrad, gamma-air and $10 mrad, beta-air and the calendar year limits $10 mrad, gamma-air and $20 mrad, beta-air.
The limits are applicable separately to each unit and are not combined site l
limits..The following equations shall be used to calculate the gamma-air and beta-air doses:
3.17E-08
- X/Q
- E (Mi
- Qi)
(2.7)
D,
=
and l
3.17E-08
- X/0
- E (Ni
- Ot)
(2.8)
D.
=
where:
D,
= air dose due to gamma emissions for noble gas radionuclides (mrad)
L Do = air dose due to beta emissions for noble gas radionuclides (mrad)
X/O = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m')
Qi = cumulative release of noble gas radionuclides i over the period of interest (uci) where uCi = (uci/cc) (cc released) or (uCi/sec) (see released)
M4 = air dose factor due to gamma emissions from noble gas 3
radionuclides 1 (mrad /yr per uCi/m, from Table 2-1)
Ni = air dose factor due to beta emissions from noble gas 3
radionuclides 1 (mrad /yr per uCi/m, Table 2-1)
I' 3.17E-08 = conversion factor (yr/sec) l l
r i
I l
i l
l l
i I
19 L_
i,
Salcm ODCM Rev. 11 l
2.4.2 Simplified Dose Calculation for Noble Gases.
l In lieu of the individual noble gas radionuclides dose assessment as presented above, the following simplified dose calculation equations shall be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2.
(Refer to Appendix C for the derivation and justification for this simplified method.)
3. l'IE- 08
- X/O
- M.tr
- I Qi (2.9)
D.
=
0.50 and 3.17E-08
- X/Q
- N.tr
- E Qi (2.10)
D.
=
0.50 where:
M.rs=
5.3E+02, effective gamma-air dose factor (mrad /yr per 3
uCi/m )
N.rc=
1.1E+03, effective beta-air dose factor (mrad /yr per 3
uCi/m )
01
= cumulative release for all noble gas radionuclides (uci) where uCi = (uci/cc) (cc released) or (uC1/sec)
(see released) 0.50 = conservatism factor to account for potential variability in the radionuclides distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the gamma-air and beta-air doses.
i 1
20 W----_-_____-
Sclem ODCM Rsv. 11 2.5 Radiciodine and Particulate Dose Calculations - 10 CPR 50 l
2.5.1 UNRESTRICTED AREA Dose - Radiciodine and Particulate.
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 shall be used to evaluate the maximum organ dose due to releases of I-131, tritium and particulate with half-lives greater than 8 days:
3.17 E- 0 8
- W
- S r
- E ( R.,
- Ot )
(2.11)
D..,
=
p t
where:
D..,= dose or dose commitment via all pathways p and controlling age group a (as identified in Table 2-4) to organ o, including the total body (mrem)
W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-4 X/O =
atmospheric dispersion for inhalation pathway and H-3 dose contribution via other 3
pathways (sec/m )
atmospheric deposition for vegetation, milk D/0
=
and ground plane exposure pathways (m-2 )
3 dose factor for radionuclides 1 (mrem /yr per uC1/m ) or Rp
=
i (m' - mrem /yr per uCi/sec) and organ o from Table 2-5 for each age group and the applicable pathway p as identified in Table 2-4.
Values for Rt. were derived in accordance with the methods described in NUREG-0133 cumulative release over the period of interest for Os
=
radionuclides 1 -- I-131 or radioactive material in particulate form with half-life greater than 8 days (uci).
j annual seasonal correction factor to account for the S F,
=
fraction of the year that the applicable exposure pathway does not exist.
- 1) For milk and vegetation exposure pathways:
A six month fresh vegetation and grazing
=
0.5 season (May through October)
=
- 2) For inhalation and ground plane exposure
1.0 pathways
For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway.
Only the controlling age group as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3.
)
21
Salem ODCM Rev. 11 2.5.2 Simplified Dose Calculation for Radiciodines and Particulate.
l l
In lieu of the individual radionuclides (I-131 and particulate) 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).
3.17E-08
- W
- SF,
- Rs.in
- E Q1 (2.12)
D.,
=
where:
4..
= maximum organ dose (mrem)
Rs.in =
I-131 dose parameter for the thyroid for the identified controlling pathway
= 1.05E+12, infant thyroid dose parameter with the grass-cow-milk pathway controlling (m' - mrem /yr per uCi/sec)
D/O for radiciodine, 2.1E-10 1/m' W
=
Qt
= cumulative release over the period of interest for radionuclides I -- I-131 or radioactive material in particulate from with half life greater than 8 days (uCi)
The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Salem 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 2-4.
l l
J
- I f
22 A____--______.__._____
Salem ODCM Rev. 11 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations
~During periods of primary to secondary leakage, minor levels of radioactive material may be released via the secondary system to the atmosphere.
Non-condensables (e.g.,
noble gases) will be predominately released via the condenser evacuation system and will be monitored and quantified by the routine plant vent monitoring and sampling system and procedures (e.g., R15 on condenser evacuation, R41D on plant vent, and the plant vent particulate and charcoal samplers).
However, if the Steam Generator blowdown is routed directly to the Chemical Waste Basin (via the SG blowdown flash tank) instead of being recycled through the condenser, it may be desirable to account for the
. potential atmospheric releases of radiciodines and particulate from the flash tank vent (i.e., releases due to moisture carry over).
Since this pathway is not sampled or monitored, it is necessary to i
calculate potential releases.
l Based on the guidance in NRC NUREG-0133, the releases of the radioiodines and particulate shall be calculated by the equation:
Qi Ci
- R.,3
- Fa (1-SQn,)
(2.13)
=
where:
Oi
= the release rate of radionuclides, i, from the steam generator flash tank vent (uci/sec)
Ci
= the concentration of radionuclides, i, in the secondary coolant water averaged over not more than one week (uCi/ml)
R.gs = the steam generator blowdown rate to the flash tank (ml/sec)
En
= the fraction of blowdown flashed in the tank determined from a heat balance taken around the flash tank at the applicable reactor power level S0n = the measured steam quality in the flash tank vent; or an assumed value of 0.05, based on NUREG-0017.
Tritium releases via the steam flashing may also be quantified using the above equation with the assumption of a steam quality (SQn.) equal to 0. Since the H-3 will be associated with the water molecules, it is not necessary to account for the moisture carry-over which is the transport media for the radioiodines and particulate.
l l
l I
i 23
Salem ODCM Rev. 11 Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam (Fn) is approximately 0.48.
The. equation simplifies;to the following:
Qi = 0.072 Ci Rnd (2.14)
For H-0, the simplified equation is:
Qi = 0. 4 8 Ci Rye (2.15)
Also during reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs (PORV) and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust.
The evaluation of the radioactive material concentration in the steam relative to that in the steam generator water is based on the guidance of NUREG-0017, Revision 1.
The partitioning factors for the radioiodines is 0.01 and is 0.001 for all other particulate radioactive material.
The resulting equation for quantifying releases via the atmospheric steam releases is:
Qi3 = 0.13 * (Cy
- SF )
- PFi (2.16) 3 where:
013
= release rate of radionuclides i via pathway j, (uci/sec)
Ci3
= concentration of radionuclides i, in pathway j, (uCi/sec)
SF3 = steam flow for release pathway j.
~
= 450,000 lb/hr per PORV
= 800,000 lb/hr per safety relief valve
- 50,000 lb/hr for auxiliary feed pump exhaust PFi = partitioning factor, ratio of concentration in steam to that in the water in the steam generator
= 0.01 for radiciodines
= 0.005 for.all other particulate
= 1.0 for H-3 0.13= conversion f actor - [ (hr*ml) / (sec*1b))
Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculation methods of the Salem Emergency Plan Implementation Procedure, j
Alternately, the quantification of the release rate and cumulative releases may be based on actual samples of main steam collected at the R46 sample locations.
The measured radionuclides concentration in the steam may be used for quantifying the noble gases, radiciodine and particulate releases.
)
p 24
l i
Salem ODCM Rev. 11 1
Note:
The expected mode of operation would be to isolate the affected steam generator, thereby reducing the potential releases during the shutdown /cooldown process.
Use of the above calculation methods should consider actual operating conditions and release mechanisms.
I The calculated quantities of radioactive materials may be used as l
inputs to the equation (2.11) or (2.12) to calculate offsite doses for demonstrating compliance with the Radiological Effluent Technical Specifications.
2.7 Gaseous Effluent Dose Projection l
Technicel Specification 3.11.2.4 requires that the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected
)
doses exceed one-half the annual design objective rate in any calendar
- quarter, i.e.,
exceeding:
0.625 mrad / quarter, gamma air; 1.25 mrad / quarter, beta air; or 1.875 mrem / quarter, maximum organ.
The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation i
system (filtration systems # 1,2 and 3) and the Waste Gas Decay Tanks as delineated in Figures 2-3 and 2-4. Dose projections are performed at least once per 31 days by the following equations:
D, * (91 / d)
(2.17)
D,p
=
(91 / d)
(2.18)
De Dag
=
D.,
- (91 / d)
(2.19)
D..,
=
where:
D,,
= gamma air dose projection for current calendar quarter (mrad)
D,
= gamma air dose to date for current calendar quarter as determined by Equation 2.7 or 2.9 (mrem) 4,p
= beta air dose projection for current calendar quarter (mrad)
D.
= beta air dose to date for current calendar quarter as determined by Equation 2.8 or 2.10 (mrem)
D.x, = maximum organ dose projection for current calendar quarter (mrem)
D.. = maximum organ dose to date for current calendar quarter as determined by Equation 2.11 or 2.12 (mrem) d
= number of days to date in current calendar quarter 91 number of days in a calendar quarter 1
)
25 l
L-__-_____--______
Salem ODCM Rev. 11 3.0 Special Dose Analyses 3.1 Doses Due To Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.11, the Radioactive Effluent Release Report (RERR) must be submitted within 60 days after January 1st and July 1st of each year and shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.
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 2-4 The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting.
However, a follow-up evaluation shall be performed when the' data becomes available.
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 and July 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 irom 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 Nuclear Generating Station and the Hope Creek Nuclear Generating Station:
No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.
The dose contribution from the operation of Hope Creek Nuclear l
Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS 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.
I t
26 c__________-_-___
Salem ODCM Rev. 11 3.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of Technical Specification 3/4.11.4 and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the Salem Nuclear Generating Station may be performed using the calculation methods contained within this 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.
Avarage 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 environmental measurements (e.g.,
TLD, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method.
Only during a non-typical condition will there exist any potential for significant on-site sources at Salem that would yield potentially significant off-site doses (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 where the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculation techniques will be used for determination of dose for assessing 40 CFR 190 compliance.
i'
)
27
Salem ODCM Rev. 11 4.0 Radiological Environmental Monitoring Program 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of Appendix A Technical Specification 3.12.
The objectives of the l
program are:
I i
To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure l
in the vicinity of Artificial Island; To determine if the operation of the Salem Nuclear Generating 1
Stations 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 SNGS operations have no detrimental effects on the l
health and safety of the public or on the environment.
l The sampling requirements (type of samples *, collection frequency and analysis) and sample locations are presented in Appendix E.
- NOTE:
No public drinking water samples or irrigation water senples are taken as these pathways are not directly effected by liquid i
effluents discharged from Salem Generating Station.
l 4.2 Interlaboratory Comparison Program L
Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory l
Comparison.
Participation in an approved Interlaboratory Comparison l
Program provides a check on the preciseness of measurements of radioactive materials in environmental samples.
A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.10.
-)
28
Salem ODCM Rev. 11 Liquid Release,Flowpath Unit 1 e
4=r M
- g,=
~s~
w-
~s~
a.nu.
gg
.x,=9
-~
- se lau-_
r l
Hi 4 '
'#4 F
-c.c
%w' sue
- se ME' gg
.e mir.r I g w.
I I
I J
6, sw Jgy fh.
,2 - -
0-E
.g.
._1...
t I
e 5
l 1
29 i
Y Salem ODCM Rev. 11 Liquid Release Flowpath Unit 2 A*7"E.
ng
- _ ~
m.-
.. ~
ms yg
. ;p.,
-.. ~
l
-r.w-vt.
)
m -ar
- v. w av. w sur
=c.e g
g
___ g lmy I
I I
I Me
.d
.49858 N g
AN
..gg.
._l.
4 0
9 4
'I O
e j
i e
30
Salem ODCM Rev. 11 Radioactive Waste System j
l i
l
\\
l 1
e 1
.iotti r,.
reter p csees and/or i
nwie es=taarattner mta=
\\
l
_=r =.
o._
_.i_ _.'t_.~ ""lll.::* 1r
,o
=.. -a--L
.=-
-=
.=
T i
i i
I L
-=,
r
)
(ult) 2
~"
I j
---t*)
i qq 1
- w. r 8
- m..-
e xI
, u.
_ m i
i
- m-
= _ -
, 'I !
g 9
l
- =
n
=:= -
5 I
asse,a a
9.-
-4T~ %#
7
- ..=-
.6 n.......
T
_:3...._......
... n t
4, l
31 l
l l~____ _-______-____-____. _ _ _ _
Salem ODCM Rev. 11 j
Table 1-1 Parameters for Liquid Alarm Setpoint Determinations Unit 1 Desameter Asteal Defaalt Unita Ceemmata value va.ime
- MPC, calculated 6.05E-06
- uct/ml Calculated for each batch to be
- released, MPC 1-131 3.02-07 N/A uct/mi 1-131 MPC conservatively used for SG blowdown and Service Water i
l moaltor setpointa.
1 C.
measured N/A vol/m1 Taken from gamma spectral analysis of 11guld effluent.
4 i
MPCs as deteralped N/A ucl/ml Taken from 10 Cf1t 20, Appendia 3, Table !!, col 2.
Sensitivity as determined N/A cpm por Monitor sensitivities are 1-R18 uct/mi controlled under Public service 1-R19 (A,9,C, D)
Blueprint Document (PSSP) 315133 3-R13 ( A, s,C. D, t) j CW as determined 1.00E+0S gpn Circulating water system a single j
CW pump RA 1-R10 as determined 120 gpm Determined prior to release:
release rate can be adjusted for 1-R19 Techancal specification compliance 1 R13 120 Steam Generator blowdown rata per Genera tor Service Water flow rate for 2500 Containment fan coolers 1
Setpoint calculated N/A cpm Monitor setpoints are controlled 1-Rig under Public service Blueprint I
1-R19 "
Document (P8BP) 315133 l
1-R13 ( A, B,C, D, t) "
safety Tactor as determined 0.75 t'n t tless Default parameter to account for (Non-Gasona) non-ganeta emitting nue11 des.
(
Refer to Appendia A for derivation The MPC value of I 131 (3t-01 uci/ml) has been used for derivation of R19 Steam Generator bicudown and R13 service Water monitor setpoints as discussed in Section 1.2.2
's 32
!k -
_s
Salem ODCM Rev. 11 Table 1-2 Parameters for Liquid Alarm Setpoint Determinations Unit 2 Parameter Actual Default Units comuments Value Value MPC.
calculated 4.81E-06
- ucl/ml Calculated for each batch to be released.
MFC 1 131 3.0E-01 N/A uct/mi 1-111 MPC conservatively used for 80 blowdown, service Water and Chemical Waste Basin monitor setpoints.
Ca measured N/A uci/mi Takes from gasma spectral analysis of 11guld effluent.
MPCs as determined N/A uci/a1 Takee from 10 CFR 20, Appendia B, Table
!!, Col. 2 sensitivity as determined N/A cpe/uct/ml Monitor sensitivities are controlled 2-R10 under Public Service Blueprint Document 2-Ri t ( A. 8,C. C) 315734 2-R13 K37 CW as determined 1.0t+0S eps Circulating Water system, single CW pump (Notel no CW pump 13 serVICS for IR13 monitor - see section 1.2.2)
RR 2-R19 as determined 120 gpm Determined prior to releases release rate can be adjusted for Technical Specification Compliance 2-R19 120 steam Generator slowdown rate per Generator service Water flow rate for Containment 2-R13 2500 fan coolers R37 1200 Chemical Weste Basin discharge Setpoint calculated N/A cpm Monitor setpoints are controlled under 2 R13 Public Service B19eprint Document (PSBP) 2-Kit 1 A, B,C, D) 315134 2 - R13 *
- R31 **
Safety Factor as determined 0.75 Unitiess Default parameter to account for non-JNon-Gammal gamma 6mitting nuelldes.
- Refer to Appendta A for derivation
- The MPC walue of I-111 (3.08-l uci/ml) has been used for derivation of the R13 and R37 monitor setpoints as discussed in Section 1.2.2 l
)
33 L__________
Salem ODCM Rev. 11
(
Table 1-3 Site Related Ingestion Dose Commitment Factors, Aio (mrem /hr per uCi/ml) l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-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 l
P-32 4.69E+6 2.91E+5 1.81E+5 5.27E+5 5.5BE+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 Cr-51
[
Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Hn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 l
5.30E+4 6.32E+5 Fe-59 8.06E+4 1.90E+5 7.27E+4 Co-57 1.4?E+2 2.36E+2 3.59E+3 l
Co-58 6.03E+2 1.35E+3 1.22E+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 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Zn-69 3.43E+2 6.56E+2 4.56E+1 4.26E+2 9.85E+1 4.67E+0 4.07E+0 Br-82 Br-83 7.25E-2 1.04E-1 Br-84 9.39E-2 7.37E-7 Br-85 3.06E-3 Rb-86 6.24E+2 2.91E+2 1.23E+2 1.79E+0 9.49E-1 2.47M-11 Rb-88 1.19E+0 0.34E-1 6.89E-14 Rb-89 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 4.37E+2 3.71E+0 Sr-91 9.18E+1 Sr-92 3.48E+1 1.51E+0 6.90E+2 6.42E+4 Y-90 6.06E+0 1.63E-1 1.68E-1 2.22E-3 Y-91m 5.73E-2 Y-91 8.88E+1 2.37E+0 4.89E+4 1.56E-2 9.32E+3 Y-92 5.32E-1 5.35E+4 Y-93 1.69E+0 4.66E-2 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4 2.68E-1 5.51E+4 Zr-97 8.81E-1 1.785-1 8.13E-2 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 1.11E+0 3.50E+3 Nb-97 3.75E+0 9.49E-1 3.46E-1 i
1.2BE+2 2.43E+1 2.89E+2 2.96E+2 l
Ho-99 I
Tc-99n 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 Tc-101 1.33E-2 1.92E-2 1.88E-1 3.46E-1 9.81E-3 5.77E-14 l
As-76 4.30E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 4.30E+4 i'
34 i
4 l
I l
Salem ODCM Rev. 11 Table 1-3 (cont'd)
Site Related Ingestion Dose Commitment Factors, Aio l
(mrem /hr per uCi/ml)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-105 8.89E+0 3.51E+0 1.15E+2 5.44E+3 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Rh-103m Rh-106 Ag-110m 1.56E+3 1.45E+3 8.60E+2 2.85E+3 5.91E+5 Sb-124 2.77E+2 5.23E+0 1.10E+2 6.71E-1 2.15E+2 7.66E+3 l
Sb-125 1.77E+2 1.98E+0 4.21E+1 1.80E-1 1.36E+2 1.95E+3 Te-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 B.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23E+3 1.84E+3 Te-127 8.90E+0 3.20E+0 1.93E+0 6.60E+0 3.63E+1 7.03E+2 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+1 1.92E+0 Te-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 6.80E+3 Te-131 1.59E+0 6.66E-1 5.03E-1 1.31E+0 6.99E+0 2.26E-1 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 I-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 1.01E+2 I-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 I-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 I-135 2.32E+1 6.00E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+0 B.81E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+0 3.38E+3 Ba-141 3.81E+0 2.8BE-3 1.29E-1 2.68E-3 1.63E-3 1.80E-9 Ba-142 1.72E+0 1.77E-3 1.08E-1 1.50E-3 1.00E-3 2.43E-18 La-140 1.57E+0 7.94E-1 2.10E-1 5.83E+4 La-142 8.06E-2 3.67E-2 9.13E-3 2.6BE+2 Ce-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Pr-143 5.79E+0 2.32E+0 2.87E-1 2.54E+4 1.34E+0 Pr-144 1.90E-2 7.87E-3 9.64E-4 4.44E-3 2.73E-9 Nd-147 3.96E+0 4.5BE+0 2.74E-1 2.6BE+0 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.0BE-2 7.11E+2 i
)'
35 t
1
Salem ODCM Rev. 11 Table 1-4 Bioaccumulation Factors (BFi)
(pCi/kg per pCi/ liter)
Element Saltwater Fish Saltwater Invertebrate 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 1.0F+02 1.0E+03 Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.0E+03 5.0E+04 Br 1.5E-02 3.1E+00 Rb 8.3E+00 1.7E+01 Sr 2.0E+00 2.0E+01 Y
2.5E+01 1.0E+03 Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.0E+01 5.0E+01 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 1.9E+01 1.0E+02 I
1.0E+01 5.0E+01 Cs 4.0E+01 2.5E+01 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 As 3.3E+02 3.3E+02 Values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is adapted from NUREG/CR-1336 l
and silver, arsenic and antimony which are taken from UCRL 50564, Rev.
1, I
October 1972.
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Salem ODCM Rev. 11 i-Table 2 1 Dose Factors for Noble Gases-Total Body Gamma Air seta Air Dese raetor
. Skin Dose ractor Dose ractor Dose Factor Asdionuclide K1 L1 M1 N1 toren/yr per uC1/m3)
(aren/yr per uC1/m3) tarad/yr per uC1/m3) tared /yr per uC1/m3)
~..
Kr.9 3m 1.562-02 1.93t+01 2.885+02 Krat $m 1.17t+03 1.465+03 1.23t+03 1.915+03 Er.0$
1.61E+01 1.34t+03 1.12t+01 1.95t+03-Kr-81 3.92E+03 9.13t+03 6.111+03 1.03t+04 Kr.08 1.41t+04 2.31E*03 1.52E+04 2.93te03 Kr.09 1.66t+04 1.01t+04 1.735404 1.06t+04
' Kr.90.
1.56t+04 7 29t+03 1.63E+04 1.03t+03 Ke.13 La 9.15t+01 4.16t+02 1.56t+02 1.11E+03 Xe.133m -
2.51t+02 9.94t+02 3.21E+02 1.488+03 Xe.131 2.94t+02 3.06t+02 3.53t+02 1.05t+03 Ke.135m 3.12t+03 1.11t+02
- 3. 3 6 r.+ 0 3 1.39t+02 Ke.135 1.011+03 1.06t+03 1.92t+03 2.46t+03 Ke 137 1.42t+03 1.22t+04
- 1. Sit +03 1.21E+04 Xe.138 8.53t+03 4.13t+03 9.21t+03 4.15E+03
' As.41 0.04t+03 2.69t+03 9.30t+03 3.28t+03 l
l f
![
39
Salem ODCM Rev. 11 Table 2-2 Parameters for Gaseous Alarm Setpoint Determinations Unit 1
- Parameter Astaal Defasit Omits comumeta vaise value M/0 calculated 2.2E-06 sec/m' USNRC Salem Safety Evaluation, Sup 3 VP (Diant Vant) as measured or 1.3CE+c5 f t'/ min Plant vent - normal fan curves operation (Cont Purge) 3.5CE4C4 Containment Purge AP coordinated 0.25 N/A Admir.istrative ellocation factor with MCG5 to ensare combined releases do not exceed release rate limit for site.
Cs measured N/A ucl/ cps Taken from ganea spectral i
analysis of Gaseous affluent Na nuclide specific N/A pres /yr per Values from Table 2-1 uct/m La nuclide specific N/A mrom/yrper Values f ree Table 2 3 uct/m M6 muclide specific N/A mram/yrper Values from Table 2 1 uct/m Sensitivities as determined N/A cpm per Monitor sensitivities are 1-R41D uct/m' controlled under Pubite 1*R16 Service Blueprint Document 1-R12A (PSBP) 215133 Setpolat calculated N/A cpm Hoalter setpolats are 1 R41D controlled under Public 1-R16 Gervice Bluepsint Document 1-RilA **
(PSBP 315713 I.
Applicable during Modes 1 through 5. During Mode 6 trafuellag), monitor setpoint shall be I
reduced to 2a background la accordance with Technical Specification Table 3 3-6 l
l i
4o i
Salem ODCM Rev. 11 Table 2-3 Parameters for Gaseous Alarm Setpoint Determinations Unit 2 Parameter Actual Default Units Conumenta value value X/Q calculated 2.2t.6 sec/m Licensing Technical 8
Specification value VP Plant Vent as measured or 1.3CE4C5 f t'/ min Plant Vent - normal operation fan curves Cont. Purge 3.5Ct+C4 Containment Purge Ar coordinated with D.25 N/A Administrative allocatica factor to HCGS ensure combined releases do not onceed release rate for site.
s Ce measured N/A uct/ca Taken from gamma spectral analysis of gaseous affluent K. '
auclide specific N/A mrea/y{per Values from Table 2 1 uct/m Li nuclide specific N/A mies/yrper Values from Table 2-1 uct/m Na muclice specific N/A mren/yrper Values from Table 2-1
/
uct/m sensitivities as determined N/A cpm per Monitor sensitivittaa are 2-R41D uct/m' contro11ed under Public $stwice 2-R16 Blueprint Document (PSBP) 315734 2-R124 Setpoint calculated N/A eps
- nitor setpoints are controlled 2-R41D
.*er Public service Blueprint 2 R16
' sument (P337) 315134 2-R12A "
Applicable during MODr.S 1 through 5. During H3DC 6 (refueling), monitor setpoints shall be reduced to 2s background in accordance with Technical Specification 3.3 6.
l l
41 l
Salem ODCM Rev. 11 Table 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations
- Atmospheric Dispersion Technical Specification Location Pathway (s)
Controlling X/Q D/Q Age Group (Sec/m3)
(1/m2) 3.11.2.la site boundary noble gases N/A 2.2E-06 N/A (0.83 mile, N) direct exposure 3.11.2.lb site boundary inhalation' child 2.2E-06 N/A (0.83 mile, N) 3.11.2.2 site boundary gamma-air N/A 2.2E-06 N/A (0.83 mile, N) beta-air 3.11.2.3 residence / dairy
- milk, ground infant 5.4E-08 2.1E-10 (4.9 miles, W) plane and inhalation
- Location and distance are determined from the performance of the annual land use census as required by Technical Specification 3.12.2.
The identified controlling locations, pathways and atmospheric dispersion are from the Safety Evaluation Report, Supplement No. 3 for the Salem Nuclear Generating Station, Unit 2 (NUREG-0517, December 1978).
42
!e-_______________
Salem ODCM Rev. 11 Table 2-5 Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT (mrem /yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1.32E+6 7.71E+4
- 8. 64 E+4 5.01E+4 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2
.cr-51 Mn-54 3.96E+4 9.84E+3 1.40E+6 7.74E+4 6.30E+3 7.21E+4 6.03E+3 3.94E+3 re-55 2.46E+4 1.70E+4 1.02E+6 1.88E+5 1.06E+4 re-59 1.18E+4 2.78E+4 3.70E+5 3.14E+4 6.71E+2 Co-57 6.92E+2 9.28E+5 1.06E+5 2.07E+3 Co-58 1.58E+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 2n-65 3.24E+4 1.03E+5.
6.90E+4 8.64E+5 5.34E+4 4.66E+4 1.66E+4 5.90E+4 1.35E+5 Rb-86 1.40E+6 3.50E+5 8.72E+3 Sr-89 3.04E+5 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6
- 1. 7 0 E+ 6 3.85E+5 1.24E+4 Y-91 4.62E+5 5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-95 1.07E+5 3.44E+4 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4.21E+3 5.83E+3 5.05E+5 1.10E+5 6.58E+2 l
Ru-103 1.53E+3 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ru-106 6.91E+4 Ag-110m 1.00E+4 1.00E+4 1.97E+4 4.63E+6 3.02E+5 5.94E+3 2.48E+6 4.06E+5 1.24E+4 Sb-124 3.12E+4 5.89E+2 7.55E+1
- 1. 7 4 E+ 6 1.01E+5 1.26E+4 l
Sb-125 5.34E+4 5.95E+2 5.40E+1 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.5BE+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 l
4.06E+2 1.16E+3 I-132 1.16E+3 3.26E+3 1.14E+5 5.10E+3 i
8.88E+3 4.52E+3 2-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 1.01E+0 6.15E+2 I-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 I-135 2.6BE+3 6.98E+3 4.48E+5 1.11E+4 5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 1.04E+4 7.2BE+5 l
Cs-136 3.90E+4 1.46E+5 B.56E+4 1.20E+4 1.17E+4 1.10E+5 I
2.22E+5 7.52E+4 8.40E+3 4.2BE+5 Cs-137 4.78E+5 6.21E+5 1.67E+1 1.27E+6 2.18E+5 2.57E+3 1
Ba-140 3.90E+4 4.90E+1 Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 I
8.48E+5 7.78E+6 8.16E+5 1.04E+5 Ce-144 3.43E+6 1.43E+6 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.00E+5 4.64E+2 Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73E+5 3.65E+2
)
43
Salem ODCM Rev. 11
-Table 2-5 (cont'd)
R(io), Inhalation Pathway Dose Factors - TEENAGER (mrem /yr per uC1/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 1.27E+3 1 27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.07E+3 4.87E+3 9.28E+4 7.16E+4 P-32 1.89E+6 1.10E+5 7.50E+1 3.07E+1. 2.10E+4 3.00E+3 1.35E+2 Cr-51 5.11E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Mn-54 1.24E+5 6.39E+3 5.54E+3 Fe-55 3.34E+4 2.3BE+4 Fe-59 1.59E+4 3.70E+4 1.53E+6 1.78E+5 1.43E+4 5.86E+5 3.14E+4 9.20E+2 Co-57 6.92E+2 1.34E+6 9.52E+4 2.78E+3 2.07E+3 Co-58 1.51E+4 8.72E+6 2.59E+5 1.98E+4 Co-60 3.07E+5 1.42E+4 1.98E+4 Ni-63 5.80E+5 4.34E+4 Zn-65 3.86E+4 1.34E+5 8.64E+4 1.24E+6 4.66E+4 6.24E+4 1.77E+4 8.40E+4 1.90E+5 Rb-86 2.42E+6 3.71E+5 1.25E+4 Sr-89 4.34E+5 1.65E+7 7.65E+5 6.68E+6 Sr-90 1.08E+8 2.94E+6 4.09E+5 1.77E+4 Y-91 6.61E+5 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 7.43E+3 7.83E+5 1.09Et5 8.96E+2 Ru-103 2.10E+3 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ru-106 9.84E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Ag-110m 1.38E+4 1.31E+4 3.85E+6 3.98E+5 1.68E+4 Sb-124 4.30E+4 7.94E+2 9.76E+1 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92Ev4 1.72E+4 5.36E+5 7.50E+4 6.67E+2 Te-125m 4.88E+3 2.24E+3 1.40E+3 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.9BE+6 4.05E+5 2.25E+3 6.49E+3 2.64E+4 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 I-132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 1.27E+3 1.58E+3 I-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 1.03E+4 6.22E+3 I-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+1 8.40E+2 I-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 6.95E+3 3.49E+3 Cs-134 5.02E+5 1.13E+6 3.75E+5 1.46E+5 9.76E+3 5.49E+5 1.10E+5 1.785+4 1.09E+4 1.37E+5 Co-136 5.15E+4 1.94E+5 Cs-137 6.70E+5 8.48E+5 3.04E+5 1.21E+5 8.48E+3 3.11E+5 2.2BE+1 2.03E+6 2.29E45 3.52E+3 Ba-140 5.47E+4 6.70E+1 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-141 2.84E+4 1.90E+4 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Ce-144 4.89E+6 2.02E+6 Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 5.02E+3 3.72E+5 1.82E+5 5.13E+2 Nd-147 7.86E+3 8.56E+3 I
44 e-_:--_______-_--______-____-__-_-________
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Inhalation Pathway Dese Factors - CHILD (mrem /yr per uC1/m3)
Huclide Bone Liver Thyroid Kidney Lung GI-LLI T. 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 w
4.22E+4 9.88E+4 Cr-51 0.55E+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 Fe-55 4.74E+4 2.52E+4 1.11E+5 2.87E+3 7.77E+3 i
Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 1
-Co-57 9.03E+2 5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 1.11E+6 3.44E+4 3.16E+3 Co-60 1.31E+4 7.07E+6 9.62E+4 2. 2 0'.+ 4 Ni-63 8.21E+5 4.63E+4 2.75E+5 6.33E+3 2.80E+4 i
7.14E+4 9.95E+5 1.63E+4 7.03E+4 l
Zn-65 4.26E+4 1.13E+5 Rb-86 1.98E+5 7.99E+3 1.14E+5 Sr-89 5.99E+5 2.16E+6 1.6?E+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+0 6.11E+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 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.n7E+3 Ru-106 1.36E+5 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 Sb-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 4.03Eid 2.07E+4 Te-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 6.07E+3 6.36E+4 1.40E+6 7.14E+4 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.BBE+4 2.84E+3 2.73E+4 I-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.88E+3 I-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+3 I-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+2 I-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 3.30E+5 1.21E+5 3.85E+3
- 2. 2 5';+ 5 Cs-136 6.51E+4 1.71E+5 9.55E+4 1.45E+4 4.18E+3 1.1 LE+ 5 Cs-137 9.07E+5 8.25E+5 2.82E+5 1.04E+5 3.62E+3 1.2BE65 Ba-140 7.40E+4 6.4BE+1 2.11E+1 1.74E+6 1.02E+5 4.33E+2 Ce-141 3.92E+4 1.95E+4 8.55E+3 5.44E+5 5.66E+4 2.90E+3 l
Ce-144 6.77E+6 2.12E+6 1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1.08E+4 8.73E+3 4.01E+3 3.28E+5 8.21E+4 6.81E+2 i
45 l
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Inhalation Pathway Dose Factors - INFANT (mrem /yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 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 Hn-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 9.4RE+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 Co-58 1.22E+3 7.77E+5 1.11E+4 1.82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3.11E+4 Rb-86 1.90E+5 3.04E+3 8.82E+4 Sr-89 3.98E+5 2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 1.12E+7 1.31E+5 2.59E+6 Y-91 5.88F+5 2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 3.11E+4 1.75E+6 2.17E+4 2.03E+4 Hb-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+1 Ag-110m 9.98E+3 7.22E+3 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 2.65E+6 5.91E+4 1.20E+4 sb-125 5.17E+4 4.77E+2 6.23E+1 1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62Et3 4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.6BE+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 I-132 1.69E+3 3.54E+3 1.69E+5 3.95E+3 1.90E+3 1.26E+3 1
I-133 1.32E+4 1.92E+4 3.56E+6 2.24E44 2.16E+3 5.60E+3 1
I I-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 1.29E+3 6.65E+2 I-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 1.90E+5 7.97E,f 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 5.64E+4 1.18E+4 1.41E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 1.72E+5 7.13E+4 1.336+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.4BE+5 1.76E+5 i
Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 l
Nd-147 7.94E+3 8.13E+3 3.15E+3 3.22E+5 3.12E+4 5.00E+2 l
l 46 i
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uti/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-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 Fe-59 2.98E+7 7.00E+7 1.95E+7 2.33E+8 2.68E+7 Co-57 1.20E+6 3.25E+7 2.13E+6 Co-58 4.72E+6 9.57E+7 1.06E+7 1.64E+7 3.08E+8 3.62E+7 Co-60 Ni-63 6.73E+9 4.66E+8 9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 2.92E+9 2.75E+9 1.97E+9 Rb-86 2.59E+9 5.11E+8 1.21E+9 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 9.46E+2 3.03E+2 4.76E+2 9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 4.54E+4 2.79E+8 2.47E+4 3.89E+3 1.19E+5 4.39E+2 Ru-103 1.02E+3 3.94E+4 1.32E+6 2.58E+3 Ru-106 2.04E+4 Ag-110m 5.83E+7 5.39E+7 1.06E+8 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5
- 6. 2 4 E+4 2.00E+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.0BE+4 1.58E+7 2.25E+8 4.86E+6 6.50E+7 2.18E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 1.54E+8 5.58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 3.04E+8 9.57E+6 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 1.12E+8 2.43E+8 I-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 8.22E-2 1.53E-1 I-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 6.20E+6 2.10E+6 I-134 I-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 4.10E+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 4.35E+9 1.44E+9 2.35E+8 1.10E+10 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-136 2.61E+8 1.03E+9 Cs-137 7.38E+9 1.01E+10 3.43E+9 1.14E+9 1.95E+8 6.61E+9 1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-140 2.69E+7 3.38E+4 Ce-141 4.84E+3 3.27E+3 1.52E+3 1.25E+7 3.71E+2 8.87E+4 1.21E+8 1.92E+4 Ce-144 3.58E+5 1.50E+5 6.96E+5 7.88E+0 Pr-143 1.59E+2 6.37E+1 3.68E+1 Nd-147 9.42E+1 1.09E+2 6.37E+1 5.23E+5 6.52E+0 47 l
l I
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(lo), Grass-Cow-Milk Pathway Dose Factors - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (N2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 1.40E+7 4.17E+6 2.87E+7 2.78E+6 Fe-55 4 45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6
.Co-58 7.95E+6 1.10E+8 1.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 1.33E+8 4.01E+8 2n-65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Rb-86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 6.61E+10 1.86E+9 1.63E+10 Y-91 1.58E+4 6.48E+6 4.24E+2 Zr-95 1.65E+3 5.22E+2 7.67E+2 1.20E+6 3.59E+2
-N5-95 1.41E+5 7.80E+4 7.57E+4 3.34E+8 4.30E+4 Ru-103 1.81E+3 6.40E+3 1.52E+5 7.75E+2 Ru-106 3.75E+4 7.23E+4 1.80E+6 4.73E+3 Ag-110m 9.63E+7 9.11E+7 1.74E+8 2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E46 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+8 1.00E+7 Te-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 4.15E+8 1.75E+7 I-131 5.3BE+8 7.53E+8 2.20E+11 1.30E+9 1.49E+8 4.04E+8 I-132 2.90E-1 7.59E-1 2.56E+1 1.20E+0 3.31E-1 2.72E-1 I-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 9.30E+6 3.75E+6 I-134 I-135 2.47E+4 6.35E+4 4.08E+6 1.00E+5 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 5.92E+3 2.79E+3 1.69E+7 6.81E+2 Ce-144 6.58E+5 2.72E+5 1.63E+5
- 1. 66E+ 8 3.54E+4 Pr-143 2.92E+2 1.17E+2 6.77E+1 9.61E+5 1.45E+1 Nd-147 1.81E+2 1.97E+2 1.16E+2 7.11E+5 1.18E+1
)
48 L
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 (rdt
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 1.57E+3,1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+10 3.64E+9 2.15E+9 3.00E+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 Fe-59 1.20E+8 1.95E+8
' 5. 65 E+7.
2.03E+8 9.71E+7 Co-57 3.84E+6 3.14E+7 7.77E+6 Co-58 1.21E+7 7.08E+7 3.72E+7 Co-60 4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9 En-65' 4.13E+9 1.10E+10 6.94E+9 1.93E+9 6.85E+9 Rb-86 8.77E+9 5.64E+8 5.39E+9 Sr-89 6.62E+9 2.56E+8 1.89E+8 3r-90
.1.12E+11 1.51E+9 2.83E+10 Y-91 3.91E+4 5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 1.21E+3 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+5 2.29E+8 8.84E+4 Ru-103 4.29E+3 1.08E+4 1.11E+5 1.65E+3 Ru-106 9.24E+4 1.25E+5 1.44E+6 1.15E+4 Ag-110m
'2.09E+8 1.41E+8 2.63E+8
.1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 6.03E+7 6.79E+8 3.81E+7 sb-125
~8.70E+7 1.41E+6 8.06E+4 4.85E+7 2.00E+8-1.82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 7.12E+7
- 9. 84E4 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 I-131
'1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.17E+8' 7.46E+8-I-132 6.86E 1.26E+0 5.85E+1 1.93E+0 1.4BE+0 5.80E-1 I-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 8.77E+6 8.23E+6 I-134 I-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 8.00E+4 4.97E+4 Cs-134 2.26E+10 3.71E+10-1.15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-136
'1.00E+9 2.76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+6. 5.09E+5 2.82E+5 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+1 Nd-147 4.45E+2 '3.60E+2 1.9BE+2 5.71E+5 2.79E+1 l '.
l 1
49 i
E
_-a
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io); Grass-Cow-Milk Pathway Dose Factors - INEANT (mrem /yr per uti/m3) for H-3 and C-14 (rd
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3.
2.38E+3-2.38E+3 2.38E+3 2.38E+3 2.3BE+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 L
Mn-54 3.89E+7 8.63E+6 1.43E+7 8.83E+6 re-55 1.35E+8 8.72E+7 4.27E+7 1.11E+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 8.81E+7 2.10E+8 2.08E+8 Co-60 Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 8.78E+9 Rb-86 2.22E+10 5.69E+8 1.10E+10
.]
Sr-89 1.26E+10 2.59E+8 3.61E+8 I
1.52E+9 3.10E+10 Sr-90 1.22E+11 Y-91 7.33E+4 5.26E+6 1.95E+3 Zr-95 6.83E+3 1.66E+3 1.79E+3 B.28E+5 1.18E+3 2.06E+8 1.41E+5 Nb-95 5.93E+5 2.44E+5 1.75E+5 1.81E+4 1.06E45 2.91E+3 Ru-103 8.69E+3 Ru-106 1.90E+5 2.25E+5 1.44E+6 2.38E+4
'Ag-110m 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 7.18E+7 2.04E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 3.34E+8 8.62E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.15E+8 1.41E+9 I-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 2.34E+0 1.03E+0 I-133 3.72E+7. 5.41E+7 9.84E+9 6.36E+7 9.16E+6 1.5BE+7
'I-134 1.01E-9 8.74E+4 8.80E+4 I-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 Cs-134 3.65E+10 6.80E+10 1.75E+10 7.18E+9 1.85E+8 6.87E+9 l
Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.15E+9 l
Cs-137 5.15E+10.6.02E+10 1.62E+10 6.55E+9 1.88E+8 4.27E49 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ba-140 2.41E+8 2.41E+5 1.37E+7 3.11E+3 i
8.15E+3 Ce-141-4.33E+4 2.64E+4 1.33E+8 1.30E+5 Ce-144 2.33E+6 9.52E+5 3.85E+5 2.08E+2 7.89E+5 7.41E+1 Pr-143 1.49E+3 5.59E+2 5.74E+5 5.55E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 50
__.._____-..._.____._______-_m______
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Vegetation Pathway Dose Factors - ADULT (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 T. Body 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 H-3 C-14 8.97E+5 1.79E+5' 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.58E+8 5.42E+7 P-32 1.40E+9 8.73E+7 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Cr-51 9.27E+7 9.54E+8 5.94E+7 Mn-54 3.11E+8 Fe-55 2.09E+8 1.45E+8-8.06E+7 8.29E+7 3.37E+7 8.35E+7 9.96E+8 1.14E+8 Fe-59 1.27E+8 2.99E+8 2.97E+8 1.95E+7 Co-57 1.17E+7 6.26E+8 6.92E+7 3.09E+7 Co-58 3.14E+9 3.69E+8 Co-60 1.67E+8 Ni-63 1.04E+10 7.21E+8 1.50E+8 3.49E+8 6.36E+8 4.56E+8 Zn-65
-3.17E+8 1.01E+9 6.75E+8 2.19E+8 4.32E+7 1.02E+8 Rb-86 1.60E+9 2.86E+8 Sr-89 9.96E+9 Sr-90 6.05E+11 1.75E+10 1.4BE+11 2.82E+9 1.37E+5 Y-91 5.13E+6 Zr-95 1.19E+6 3.81E+5 5.97E+5 1.21E+9 2.58E+5 I
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 3.72E+8 1.25E+10 2.44E+7 Ru-106 1.93E+8 1.92E+7 3.98E+9 5.80E+6 Ag-110m 1.06E+7 9.76E+6 Sb-124-1.04E+8 1.96E+6 2.52E+5 8.00E+7 2.95E+9 4.11E+7 1.05E+8 1.50E+9 3.25E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.17E+9 4.26E+7.
Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 1.28E+9 4.03E+7 3.05E+7 6.63E+7 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 2.89E+1 5.38E+1 I-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 I-12 2.12E+6 3.69E+6 5.42E+8 6.44E+6 3.31E+6 1.12E+6 I-134 1.06E-4 2.88E-4 5.00E-3 4.59E-4 2.51E-7 1.03E-4 I-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 1.21E+5 3.94E+4 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-134 4.66E+9 1.11E+10 9.24E+1 1.27E+7 1.89E+7 1.19E+8 Cs-136 4.20E+7 1.66E+8 2.95E+9 9.81E+8 1.68E+8 5.70E+9 l
Cs-137 6.36E+9 8.70E+9 Ba-140 1.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 1
Ce-141 1.96E+5 1.33E+5 6.17E+4 5.00E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 8.16E+6 1.11E+10 1.77E+6 2.78E+8 3.14E+3 1.47E+4 Pr-143 6.34E+4 2.54E+4 Nd-147 3.34E+4 3.86E+4 2.25E+4 1.85E+8 2.31E+3 I
s I
51 l
l t____
~ - - - - - -, -
Salem ODCM Rev. 11 Table 2-5 (cont'd)
R(io), Vegetation Pathway Dose Factors - TEENAGER (mrom/yr per uC1/m3) for H-3 and C-14 I
(m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-I.1.I T. Body H-3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 l
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.f4E+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 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Rb-86 2.73E+8 4.05E+7 1.28E+8 3r-89 1.51E+10 1.80E+9 4.33E+8 i
Sr-90 7.51E+11 2.11E+10 1.85E+11 Y-91 7.87E+6 3.23E+9 2.'1E+5 Zr-95 1.74E+6 5.49E+5 8.07E+5 1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 1.03E+5 4.55E+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 3.11E+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 I-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 5.91E+1 4.87E+1 I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 2.53E+6 1.02E+6 I-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 3.35E-6 9.13E-5 I-115 3.68E+4 9.48E+4 6.10E+6 1.50E+5 1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ce-141 2.82E+5 1.88E+5 8.86E+4 5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3 52
l 1
Salem ODCM Rev. 11 I
table 2-5 (cont'd)
R(io), Vegetation Pathway Dose Factors - 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 T. Body
== _______ _______ _ _ _ _ __ _
H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 9.30E+7 1.30E+8 Cr-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 Fa-55 8.00E+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. 7 6E+ 8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 2.10E+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 1.42E+8 1.34E+9 En-65 8.12E+8 2.16E+9 1.36E+9 3.80E+8 1.35E+9 Rb-86 4.52E+8 2.91E+7 2.78E+8 SI-89 3.59E&l0 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 I-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 1.99E+2 7.77E+1 I-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 1.79E+6 1.68E+6 I-134 1.70E-4 3.16E-4 7.20E-3 4.84E-4 2.10E-4 1.46E-4 I-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 7.46E+9 2.68E+9 1.43E+8 3.30E+9 Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 6.53E+5 3.26E+5 1.43E+5 4.07E+8 4.84E+4 Ce-144 1.27E+8 3.98E+7 2.21E+7 1.04E+10 6.78E+6 Pr-143 1.48E+5 '4.46E+4 2.41E+4 1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 3.18E+4 9.18E+7 4.49E+3 53 I
l 1
Salem ODCM Rev. 11
. Table 2-5 (cont'd)
R(io), Ground Plane Pathway Dose Factors (m2
- mrem /yr per uC1/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 2.16E+10 N1-63 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 i
Nb-95 1.36E+8 Ru-103 1.09E+8 Ru-106 4.21E+8
}
Ag-110m 3.47E+9 i
J Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.00E+7 I-131 1.72E+7 I-132 1.24E+6 I-133 2.47E+6 1
I-134 4.49E+5 I-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+8 l
Cs-137 1.04E+10 Ba-140 2.05E+7
)
1 Ce-141 1.36E+7 I
Ce-144 6.95E+7
)
Pr-143 Nd-147 8.40E+6 l.
54 E
__1_
l l
Salem ODCM Rev. 11 l
l l
l I
I l
APPENDIX A Evaluation of Default Parameters for Liquid Effluents I
i l
l
\\
f 1
C_______.____.__._
Salem ODCM Rev. 11 Appendix A Evaluation of Default Parameters for Liquid Effluents A. ::ffective Maximum Permissible Concentration (MPC.)
In accordance with the requirements of Technical Specification
- (3. 3. 3. 8) the radioactive liquid effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2.
The determination of allowable radionuclides concentration and corresponding alarm setpoint is a function of the individual radionuclides distribution and corresponding MPC values.
In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclides distributions, a default alarm setpoint can be established.
This default setpoint can be based on an evaluation of the radionuclides distribution of the liquid effluents from Salem and the effective MPC value for this distribution.
"The effective MPC value for a radionuclides distribution is calculated by the equation:
ECi MPC. =
(A.1)
Ci I
MPCi where:
MPC.
an effective MPC value for a mixture of radionuclides
=
(uCi/ml)
Ci concentration of radionuclides i in the mixture
=
the 10 CFR 20, Appendix B, Table II, Column 2 MPC MPCt
=
value for radionuclides 1 (uCi/ml)
The equation for determining the liquid effluent setpoints ( Section 1.2.1, equation 1.2 ) is based on a multiplication of the effective MPC timesithe monitor sensitivity. Considering the average effective l
MPC value for the years 1992 through 1994, it is reasonable to select an MPCe value of 6.05E-06 uCi/ml for Unit 1 and 4.81E-06 uci/ml for Unit 2 as typical of liquid radwaste discharges.
J A-1
Salem ODCM Rev. 11 B.
Safety Factor The type of radiation detector used to monitor radioactive releases is not capable of cetecting non gamma emitting radionulcides such as H-3, Fe-55, and Sr-89,90, as required by Technical Specification 3.11.1.1. A conservative default safety factor can be determined to account for non-gamma emitting radionuclides. Non gamma emitting radionulcides are analyzed at Salem station on a monthly or quarterly basis from a composite sample of liquid releases.
Nuclide MPC (uci/ml)
Activity Activity / MPC (uci/ml)
H-3 3E-3 5.2E-1 173.3 Fe-55 OE-4 2.5E-3 3.1 Sr-89 3E-6 2.0E-5 6.7 Br-90 3E-7 7.2E-7 2.4 Total 185.5 The values in the table above represent the maximum reactor coolant values for non-gamma emitting nuclides in 1994 for Unit 1 and 2.
Reactor coolant values were chosen to represent the maximum concentration of non-gamma emitting nuclides that could be released from Salem Station. The activity values in the table will be diluted by a minimum factor of 800 prior to release. The minimum dilution factor is obtained by using the minimum circulating water flowrate of 100,000 gpm and the maximum release rate of 120 gpm.
A conservative non-gamma factor for non-gamma emitting nuclides can be obtained using the highest Activity /MPC fraction and the minimum dilution factor as follows:
Non-Gamma Factor =
185.5 / 800 =
0.23 (Rounded up to 0.25)
Safety Factor = 1 - 0.25 = 0.75 C. Default setpoint determination:
Using the information and parameters described above a default setpoint can be calculated for Unit 1 and 2 liquid radwaste disposal process radiation monitors (R18).
Using these values to calculate the default R18 alarm setpoint value, results in a setpoint that:
- 1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and I
I
- 2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (refer to Tables 1-1 and 1-2).
A-2
-_ __-__ _ _s
)
Salem ODCM Rev. 11 Table A-1 Calculation of Effective MPC l
Salem Unit 1 Activity Released (Ci)
Nuclide MPC' 1992 1993 1994 (uCi/ml)
CURIES CURIES CURIES Be-7 2E-03 8.74E-05 8.88E-04 N/D Na-24 3E-05 3.99E-04 6.68E-04 1.62E-04 Cr-51 2E-03 4.30E-03 5.38E-03 2.02E-03 Mn-54 1E-04 7.24E-02 3.52E-02 1.37E-02 re-59 5E-05 1.20E-04 4.76E-04 4.84E-03 Co-57 4E-04 1.26E-02 1.03E-02 3.10E-03 Co-58 9E-05 2.33E+00 1.71E+00 6.47E-01 Co-60 3E-05 2.52E-01 3.04E-01 1.10E-01 Zr-95 GE-05 2.90E-03 3.29E-03 7.13E-04 Nb-95 1E-04 6.37E-03 5.78E-03 1.28E-03 Nb-97 9E-04 3.99E-04 1.27E-03 1.07E-03 Tc-99m 3E-03 8.23E-05 2.66E-04 N/D Sr-92 6E-05 N/D N/D 7.32E-06 Mo-99 4E-05 N/D 1.76E-04 1.76E-04 Ag-110m 3E-05 8.38E-03 1.19E-02 1.10E-02 Sn-113 8E-05 3.91E-04 7.88E-05 4.91E-05 Sb-122 3E-05 8.54E-05 1.21E-03 5.35E-04 Sb-124 2E-05 1.37E-02 2.08E-02 1.75E-02 Sb-125 1E-04 7.27E-02 9.04E-02 8.23E-02 Sb-126 3E-06 N/D N/D 6.18E-05 I-131 3E-07 3.06E-02 1.27E-01 1.82E-02 I-133 1E-06 1.75E-03 2.16E-03 1.88E-04 I-134 2E-05 N/D N/D 3.63E-04 Ce-141 9E-05 3.69E-05 N/D 4.24E-05 Ce-143 4E-05 N/D 5.42E-05 N/D Cs-134 9E-06 1.64E-01 3.54E-01 6.46E-01 Cs-136 6E-05 1.20E-03 3.61E-03 1.59E-03 Cs-137 2E-05 1.86E-01 4.53E-01 8.54E-01 Cs-138 3E-06 N/D 4.15E-06 1.35E-04 Ba-140 2E-05 N/D N/D 8.62E-05 La-140 2E-05 6.26E-05 2.12E-04
'1.86E-04
{
Ru-105 1E-04 4.58E-04 2.21E-04 1.35E-04 l
Ru-106 1E-05 N/D N/D 1.03E-03 Zn-65 1E-04 8.75E-04 6.72E-04 N/D Total Ct Gamma 3.16E+00 3.14E+00 2.42E+00 MPC. (uCi/ml) 1.88E-05 6.05E-06 1.28E-05 MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.
N/D - not detected 1
l A-3
l i
Salem ODCM Rev. 11 Table A-2 Calculation of Effective MFC Salem Unit 2 Activity Released (Ci)
Nuclide MPC' 1992 1993 1994 (uci/ml)
CURIES CURIES CURIES i
Be-7 2E-03 2.20E-04 1.59E-03 2.88E-04 Na-24 3E-05 7.33E-04 1.05E-03 5.77E-05 Cr-51 2E-03 4.13E-03 4.39E-03 1.55E-03 Mn-54 1E-04 9.15E-02 3.73E-02 1.37E-02 Fe-59 SE-05 1.61E-04 4.83E-04 3.25E-03 Co-57 4E-04 1.42E-02 1.17E-02 3.24E-03 Co-58 9E-05 2.57E+00 1.75E+00 6.60E-01 Co-60 3E-05 2.61E-01 3.47E-01 1.03E-01 Zr-95 6E-05 2.06E-03 2.34E-03 3.22E-04 Nb-95 1E-04 5.35E-03 3.97E-03 1.11E-03 Nb-97 9E-04 9.37E-04 1.46E-03 1.10E-03 Tc-99m 3E-03 2.75E-04 3.77E-04 N/D Mo-99 4E-05 2.28E-04 N/D N/D Ag-110m 3E-05 6.07E-03 1.03E-02 1.34E-02 5n-113 8E-05 8.51E-05 7.45E-05 N/D Sb-122 3E-05 1.12E-04 1.20E-03 N/D Sb-124 2E-05 1.20E-02 3.77E-02 9.82E-03 Sb-125 1E-04 8.29E-02 1.35E-01 6.03E-02 Sb-126 3E-06 1.83E-05 3.51E-04 N/D I-131 3E-07 4.35E-02 1.87E-01 7.90C-03 I-132 SE-06 N/D 8.72E-05 N/D I-133 1E-06 2.16E-03 2.39E-03 1.85E-04 Ce-141 9E-05 N/D N/D 2.87E-05 Co-143 4E-05 2.44E-04 N/D N/D Cs-134 9E-06 2.32E-01 4.57E-01 6.44E-01 Cs-136 6E-05 1.82E-03 4.82E-03 1.51E-03 Cs-137 2E-05 2.34E-01 5.70E-01 8.54E-01 Cs-138 3E-06 4.73E-05 N/D N/D Ru-106 1E-05 N/D N/D 4.3BE-04 Ru-105 1E-04 2.78E-04 4.07E-05 N/D La-140 2E-05 6.51E-05 2.03E-03 1.11E-04 W-187 6E-05 N/D N/D 7.98E-05 En-65 1E-04 1.38E-03 1.59E-04 N/D Sr-92 6E-05 N/D N/D 1.43E-05 Total-ci Ganna 3.57E+00 3.57E+00 2.38E+00 MPC, (uci/ml) 1.59E-05 4.81E-06 1.55E-05 MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.
- ' N/D - not detected I
i A-4 I
l u_____-_____-
Salem ODCM Rev. 11 APPENDIX B Technical Basis for Effective Dose Factors Liquid Radioactive Effluent
\\
f
t i
l 1
Salem ODCM Rev. 11 1
APPENDIX B Technical Basis for Effective Dose Factors -
Liquid Effluent Releases a
The radioactive liquid effluents for the years 1992 through 1994 were evaluated-to determine the dose contribution of the radionuclides distribution.
This analysis was performed to evaluate the use of a limited dose analysis for determining environmental l
doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2.
For the radionuclides. distribution of effluents from Salem, the controlling organ is the GI-LLI.
For the last three years the calculated GI-LLI dose is predominately a function of the Fe-55, Co-58, Co-60, Fe-59 and Ag-110m releases. The radionuclides, Cs-134 and Cs-137 contribute the large majority of the calculated total body' dose.
The results of the evaluation for-1992, 1993, and 1994 are presented in Table B-1 and Table B-2.
For purposes of simplifying the details of the dose calculational process, it is conservative.to identify a controlling, dose significant radionuclides and limit the calculation process to the use of the dose conversion factor for this nuclide.
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 (1.51 Et06 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 Fe-59 dose factor (2.32 E+05 mrem /hr per uCi/ml, total body) is the highest among the identified dominant nuclides.
For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may be used:
l' I
l B-1
Salem ODCM Rev. 11 Total Body 1.67E-02
- VoL Du = ----------
- A Fe-59,TB
- EC1 (B.1)
CW where:
Dn dose to the total body (mrem)
=
t A Fe-59,TB 7.27E+04, total body ingestion dose conversion
=
factor for Fe-59 (mrem /hr per uCi/ml) volume of liquid effluent released (gal) voL
=
total concentration of all radionuclides (uci/ml)
Ci
=
average circulating water discharge rate during CW
=
release period (gal / min) conversion factor (hr/ min) 1.67E-02 Substituting the value for the Fe-59 total body dose conversion
- factor, the equation simplifies to:
1.21E+03
- VOL
- ECt (B.2)
Du,
= ---------
CW Maximum Organ 1.67E-02
- VOL
- A Nb-95,GI-LLI EC4 (B.3)
D.
= -------------------
- CW where:
Dmax
= maximum organ dose (mrem)
A Nb-95,GI-LLI
= 1.51E+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem /hr per uci/ml)
Substituting the value for A Nb-95,GI-LLI the equation simplifies to:
2.52E+04
- VOL EC1 (B.4)
Dmax = ---------
CW 1
Tritium is not included in the limited analysis dose assessment for j
liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.
The average annual tritium release from each Salem Unit is approximately 350 curies. The calculated total body dose from such a release is 2.4E-03 mrem /yr via che fish and invertebrate ingestion pathways.
This amounts to 0.08% of the design I
objective dose of 3 mrem /yr. Furthermore, the release of tritium is a l
function of operating time and power level and is essentially unrelated to radwaste system operation.
B-2 t
Salem ODCM Rev. 11 Table B-1 Adult Dose Contributions Fish and Invertebrate Pathways Unit 1 Nuclide Release (C1)
- 7. Body Dose Traction GI-LLI Dose traction Liver Dose fraction 1994 1993 1992 1994 1993 1992 1994 1993 1992 1994 1993 1992 Hn-54 1.325-2 3.515-2 1.23E-2 0.01 0.01 0.03 0.01 0.02 0.c4 re-55 1.491-1 6.40E-2 1.10E-1 0.07 0.06 0.11 0.11 0.03 0.03 0.20 0.19 0.35 re-59 4.84E-3 4.17E-4 N/0 0.02 0.12 0.01 0.04 0.01 Co-se 6.47E-1 1.71E+0 2.33E*0 0.05 0.19 0.34 0.21 0.42 0.50 0.01 0.01 0.12 Co-do 1.10E-1 3.041-1 2.51E-1 0.02 0.09 0.11 0.12 0.19 0.15 0.01 0.03 0.04 2n-65 0.00E+0 6.12E-4 0.15E-4 0.01 0.02 0.01 0.02 0.04 Nb-95 1.29E-3 S.19E-3 6.31E-3 0.07 0.17 0.11 Ag-110m 1.10E-2 1.191-2 0.35E-3 0.26 0.15 0.09 Cs-134 6.46E-1 3.54E-1 1.64E-1 0.47 0.35 0.24 0.31 0.34 0.22 Cs-137 8.54E-1 4.535-1 1.86E-1 0.36 0.27 0.16 0.36 0.32 0.10 Total 2.44E+0 2.94E+0 3.13E40 Table B-2 Adult Dose Contributions Fish and Invertebrate Pathways Unit 2 Nuclide Release IC1)
T. Body Dose traction ci-LLI Dose reaction Liver Dose traction 1994 1993 1992 1994 1993 1992 1994 1993 1992 1994 1993 1992 Mn-54 1.31E-2 3.13E-2 9.92E-2 0.01 0.01 0.01 0.03 0.01 0.05 re-53 1 38E-1 6.61E-2 6.14E-2 0.06 0.04 0.05 0.10 0.02 0.02 0.18 0 14 0.10 0.08 0.01 a
0.02 0.01 re-59 3.25E-3 4.82E-4 W/0 0.01 Co-58 6.60E-1 1.15t*0 2.47t+0 0.05 0.16-0.35 0.29 0.42 0.57 0.01 0.06 0.13 Co-60 1.03E-1 3.41E-1 2.58E-1 0.02 0.09 0.10 0.12 0.22 0.15 0.01 0.03 0.04 0.01 0.01 0.01 0.04 an-65 0.00E+0 1.59E-4 1.385-3 Nb-95 1.115-3 3.97E-3 5.35E.3 0.06 0.13 0.14 Aq-110m 1.341-2 1.03E-2 6.12E-3 0.31 0.15 0.06 Co 134 6.44E-1 4.58E-1 2.31E-1 0.47 0.40 0.28 0.01 0.39 0.38 0.30 l
Ca-131 8.54E-1 4.53E 1 1.04E-1 0.36 0.21 0.16 0.36 0.32 0.18 I
i Total 2 44E+0 2.94E60 3.13E+0 j
- Less than 0.01 N/D = not detected B-3 l
i L________________
Salem oDCM Rev. 11 I
1 APPENDIX C Technical Bases-for Effective Dose Factors Gaseous Radioactive Effluent
.i l
L-_:__-_-___--__,
Salem ODCM Rev. 11-APPENDIX C
. Technical Bases 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 radionuclides specific.
These effective factors, which can be based on typical radionuclides distributions of releases, can be applied to the total radioactivity released to~ approximate the dose.in the environment (i.e.,
instead of having to perform individual radionuclides dose analyses only a single multiplication (K u,14rr or Nen) times the total quantity of radioactive material: released ~ would be needed).
This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.
Determination of Effective Dose Factors Effective' dose transfer factors are calculated by the following equations:
E (KL f)
(C.1)
Kerr
=
t where:
the effective total body dose factor-due to gamma K. n
=
emissions from all noble gases released the total body dose factor due to gamma emissions Ki
=
from each noble gas radionuclides i released the fractional abundance of noble gas radionuclides ft
=
i relative to the total' noble gas activity E((L + 1.1 Mi) f)
(C.2)
(L + 1.1 M).er
=
t i
where:
(L +.1.1 M).n
= the effective skin dose factor due to beta and gamma. emissions from all noble gases released
-(Li + 1.1 Mi)'
= the skin dose factor due to beta ~and gamma emissions from each noble gas radionuclides i released C-1
SalGm ODCM Rev. 11 E (Mt M.sr f)
(C.3)
=
t where:
M.ee =
the effective air dose factor due to gamma emissions from all noble gases released M
= the air dose factor due to gamma emissions from 1
each noble gas radionuclides i released E (Ni N.rs f)
(C.4) 4 where:
the effective air dose factor due to beta emissions N tr
=
from all noble gases released the air dose factor due to beta emissions from Ng
=
each noble gas radionuclides 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 Salem have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations difficult.
For the past years, the total noble gas releases have been limited to 950 Ci for 1992, 1000 Ci for 1993, and 950 Ci for 1994.
Therefore, in order to provide a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, " Source Term Specifications," has been used as representing a typical distribution.
The effective dose factors as derived are presented in Table C-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.
C-2
Salem ODCM Rev. 11 For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:
3.17E-08 E Qi (C.6)
X/Q M.cr D,
=
0.50 and 3.17E-08 X/Q N.rr Z Qi (C. 6)
Da
=
0.50 where:
D,
= air dose due to gamma emissions for the cumulative release of all noble gases (mrad)
D.
= air dose due to beta emissions for the cumulative release of all noble gases (mrad)
X/O
= atmospheric dispersion to the. controlling site boundary (sec/m3)
M.cr
= 5.3E+02, effective gamma-air dose factor (mrad /yr per uCi/m3)
N.sg
= 1.1E+03, effective beta-air dose factor (mrad /yr per uCi/m3)
Qi
.= cumulative release for all noble gas radionuclides (uCi) 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:
E Qi (C.7) 3.5E-05 X/Q D,
=
and i
7.0E-05 X/Q E Qi (C.8)
D3
=
The effective dose factors are used on a very 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 C-3 t
l Salem ODCM Rev. 11 Table C-1 Effective Dose Factors Noble Gases - Total Body and Skin Total Body Effective Skin Effective Radionuclides fg*
Dose Factor Dose Factor K.gr (L+ 1.1 M).tr s
(mrem /yr per uCi/m )
(mrem /yr per uCi/m')
Kr-85 0.01 1.4E+01 Kr-88 0.01 1.5E+02 1.9E+02 Xe-133m 0.01 2.5E+00 1.4E+01 Xe-133 0.95 2.8E+02 6.6E+02 Xe-135' O.02 3.6E+01 7.9E+01 Total 4.7E+02 9.6E+02 Noble Gases - Air Gamma Air Effective Beta Air Effective Radionuclides fg*
Dose Factor Dose Factor M.rg N.gr 3
(mrad /yr per uC1/m )
(mrad /yr per uCi/m')
Kr-85 0.01 2.0E+01 Kr-88 0.01 1.5E+02 2.9E+01 Xe-133m 0.01 3.3E+00 1.5E+01 Xe-133 0.95 3.4E+02 1.0E+03 Xe-135 0.02 3.8E+01 4.9E+01 Total 5.3E+02 1.1E+03 Based on Noble gas distribution from ANSI N237-1976/ ANSI-18.1, " Source Term Specifications."
l l
C-4
Salem ODCM Rav. 11 APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent i
~ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ __._.
Salem ODCM Rev. 11 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 radionuclides.
This analysis was performed to provide a simplified method for determining compliance with Technical Specification
-3.11.2.3 For the infant age group, the controlling pathway is the grass-cow-milk (g/c/m) pathway. An infant receives a greater radiation dose from the g/c/m pathway than any other pathway. Of this g/c/m pathway,.the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclides I-131.
The results for 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 radionuclides and limit the calculation process to the use of the dose conversion factor for the organ and radionuclides. 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 infant, g/c/m, thyroid, I-131 pathway dose factor (1.05E12 m 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:
3.17E-8
- W
- RI-131
- Z Qt D.m
=
where:
maximum organ dose (mrem)
Q,
=
atmospheric dispersion parameters to the W
=
controlling location (s) as identified in Table 3.2-4.
X/Q atmospheric dispersion for inhalation pathway and
=
H-3 dose contribution via other pathways (sec/m')
D/O atmospheric deposition for vegetation, milk and
=
ground plane exposure pathways (m-8) cumulative release over the period of interest for 01
=
radiciodines and particulate conversion factor (yr/sec) 3.17E-8
=
f D-1 L______ - ________ _
I 1
Salem ODCM Rev. 11 l
I-131 dose parameter for the thyroid for the RI-131
=
identified controlling pathway 2
1.05E12 (m mrem /yr per uci/sec), infant thyroid i
=
dose parameter with the grass-cow-milk pathway controlling i
The ground plane exposure and inhalation pathways need not be considered when the above simplified calculation method is used i
because for the overall negligible contribution of these pathways to the total thyroid dose.
It is recognized that for some particulate radionuclides (e.g.,
l Co-60 and Cs-137), the ground exposure pathway may represent.a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclides has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the milk pathway (see Table D-1).
The location of exposure pathways and the maximum organ calculation may be based on the available pathways in the
(
surrounding environment of Salem as identified by the annual land-j use census (Technical Specification 3.12.2).
Otherwise, the dose l
will be evaluated based on the predetermined controlling pathways as identified in Table 2-4.
I I
l l
l D-2
Salem ODCM Rev. 11 Table D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass-Cow-Milk Ground Plane Total Body 0.02 0.15 Liver 0.23 0.14 Thyroid 0.59 0.15 Kidney 0.02 0.15 Lung 0.01 0.02 GI-LLI 0.02 0.15 Fraction of Dose Contribution by Pathway Pathway f
Grass-Cow-Milk O.92 Ground Plane 0.08 Inhalation
+
)
i D-3 i
i 1
- -~
~
Salem ODCM Rev. 11 l
APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis s
Salem ODCM Rev. 11 APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code.
The first two letters are the power station identification code, in this case "SA".
The next three letters are for the media sampled.
AIO = Air Iodine IDM = Immersion Dose (TLD)
APT = Air Particulate MLK = Milk ECH =
Hard Shell Blue Crab PWR = Potable Water (Raw)
ESF =
Edible Fish PWT = Potable Water (Treated)
ESS =
Sediment SWA = Surface Water WWA =
Well Water The last four symbols are a location code based on direction and distance from the site.
Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site.
Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e.,
2=NNE, 3=NE, 4=ENG, etc.
The next digit is a letter which represents the radial distance from the plant:
S = On-site location E = 4-5 miles off-site A = 0-1 miles off-site d
F = 5-10 m.les off-site B = 1-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = > 20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g.,
1,2,3,...
For exarple; the designation SA-WWA-5D1 would indicate a sample in the SGS program (SA),
consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radical distance of 3 to 4 miles off-site, (therefore, radial distance D).
The number 1 indicated that this is sampling station #1 in that particular sector.
i t
E-1 l
l L__ _
__--_-_-_--_-----J
Salem ODCM Rev. 11 SAMPLIstC 1,0 CATIONS All sampling locations and specific information about the individual locations are given in Table E-1.
Maps E-1 and E-2 show the locations of sampling stations with respect to the site.
TABLE 3-1 A.
Direct Radiation Monitoring Locations (IDM)
STATION CODE STATION LOCATION 1S1-0.55 mi. N of vent 2S2 0.4 mi. NNE of vent 2S4 0.59 mi. NNE of vent 351 0.58 mi. NE of vent 451 0.60 mi ENE of vent SS1 1.0 mi. E of vent; site access road 6S2 0.21 mi. ESE of vent; observation building 731 0.12 mi. SE of vent; station personnel gate
- 10S1 0.14 mi. SSW of vent; circ water b1dg.
- 11S1 0.09 mi. SW of vent;' service water b1dg.
15S1 0.57 mi. NW of vent 16S1 0.54 mi. NNW of vent 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road SD1 3.5 nd. E of vent; local farm 1001 3.9 mi. SSW of vent; Taylor's Bridge Spur 14D1 3.4 mi WNW of vent; Bay View, Delaware 15D1 3.8 mi. NW of vent; Rt 9, Augustine Beach, DE.
2E1 4.4 mi. NNE of vent; local farm 3E1 4.1 mi. NE of vent; local farm 9El-4.2 mi. S of vent 11E2 5.0 mi. SW of vent 12E1 4.4 mi. WSW of vent; Thomas Landing 13E1 4.2 mi. W of vent; Diehl House Lab 16El 4.1 mi. NNW of vent; Port Penn 1F1 5.8 mi. N of vent; Fort Elfsborg 2F2 8,7 mi. NNE of vent; Salem Substation 2F5 7.4 mi. NNE of vent; Salem High School 2F6 7.3 mi. NNE of vent; PSEGG Training Center 3F2 5.1 mi. NE of vent; Hancocks Bridge Munc. Bldg 3F3 8.6 mi. NE of vent; Quinton Township School 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville SF1 6.5 mi. E of vent; Canton 6F1 6.4 mi. ESE of vent; Stow Neck Road 7 F2 9.1 mi. SE of vent; Bayside, NJ 10F2 5.8 mi. SSW of vent; Rt. 9
{
11F1 6.2 mi. SW of vent; Taylors Bridge, DE.
12F1 9.4 mi. WSW of vent; Townsend Elementary School 13F2 6.5 mi. W of vent; Odessa, DE.
I 13F3 9.3 mi. W of vent; Redding Middle School 13F4 9.8 mi. P of vent; Middletown, DE.
14F2 6.6 mi. WNW of vent; Boyds Corner 15F3 5.4 mi. NW of vent 16F2 8.1 mi. NNW of vent; Delaware City Public School l
E-2 L
a
Salem ODCM Rev. 11 TABLE E-1 (Cont'd)
A. Direct Radiation Monitoring Locations (IDM) (Cont'd)
STATION CODE STATION LOCATION 1G3 19 mi. N of vent; N. Church St. Wilmington, DE 3G1 17 mi. NE of vent; local farm 10G1 12 mi. SSW of vent; Smyrna, Delaware 16G1 15 mi. NNW of vent; Wilmington Airport 3H1 32 mi. NE of vent; National Park, NJ 3H3 110 mi. NE of vent; Maplewood R&TL i
STATION CODE STATION LOCATION SS1 1.0 mi. E of vent; site access road SD1 3.5 mi. E of vent; local farm 16El 4.1 mi. NNW of vent; Port Penn 101 5.8 mi. N of vent; Fort Elfsborg 2r6 7.3 mi. NNE of vent; PSE&G Training Center 14G1 11.8 mi. WNW of vent; Rte. 286, Bethel Church Road, Delaware C. Surface Water Locations (SWA) - Delaware River STATION CODE STATION LOCATION 11A1 0.2 mi. SW of vent; Salem Outfall Area 12C1 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi. SE of vent; Delaware River 16F1 6.9 mi. NNW of vent; CED Canal D. Ground Water Locations (WWA)
STATION CODE STATION LOCATION No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid effluents discharged from Salem Generating Station.
E. Drinking Water Locations (PWR,PWT)
STATION CCOE STATION LOCATION No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid effluents discharged from Salem Generating Station.
E-3 l
I
i Salem ODCM Rev. 11 Table E-1 (Cont'd)
F. Water Sediment Locations (ESS)
STATION CODE STATION LOCATION l
11A1 0.2 mi. SW of vent; Salem outfall area 15Al 0.3 mi. NW of vent; Hope Creek outfall area 16Al 0,7 mi. NNW of vent; South Storm Drain outfall 12C1 2.5 mi. WSW of vent; West bank of Delaware river 7El 4.5 mi. SE of vent; 1 mi West of Mad Horse River 16F1 5.9 mi. NNW of vent; C&D Canal G. Milk Sampling Locations (MLK) l STATION CODE STATION LOCATION 2F7 5.7 mi. NNE of vent; local farm 11F3 5.3 mi. SW of vent; Townsend DE.
14F4 7.6 mi. WNW of vent; local farm 3G1 17 mi. NE of vent; local farm H. Fish and Invertebrate Locations (ESF,ECH)
STATION CODE STATION LOCATION 11A1 0.2 mi. SW of vent; Salem outfall area 12C1 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi. SE of vent; 1 mi West of Mad Horse Creek I. Food Product Locations STATION CODE STATION LOCATION The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.
l 1
E-4 i-
Salem ODCM Rev. 11 SAMPLES COLLECTION AND ANALYSIS Sample Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler.
Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change.
be performed if gross beta exceeds 10 times the yearly mean of the control station value. Samples shall be analyzed 24 hrs or more after collection to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly composites.
Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on connected to air each weekly sample.
particulate air sampler and is collected weekly at filter change.
Crab andl Fish Two batch samples are Gamma isotopic sealed in a plastic-analysis of edible bag or jar and frozen portion on collection.
semi-annually or when in season.
Sediment A sediment sample is Gamma isotopic i
taken' semi-annually, analysis semi-annually.
Direct 2 TLD's will be Gamma dose quarterly.
collected from each location quarterly.
E-5 l
l I
Li____ ____ _ u_
Salem ODCM Rev. 11 SAMPLE COLLECTION AND ANALYSIS (Cont'd)
Sample Collection Method Analysis Milk Sample of fresh milk Gamma isotopic is collected for each analysis and I-131 farm semi-monthly when analysis on each cows are in pasture, sample on collection.
monthly at other times.
Water Sample to be collected Gamma isotopic
- Potable, monthly providing winter monthly H-3 on Surface) icing conditions allow.
quarterly surface sample, monthly on ground water sample.
l E-6 I
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Salem ODCM Rey, 11 l
Figure E-1 i
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APPENDIX C MAXIMUM PERMISSIBLE CONCENTRATIONS LIQUID EFFLUENTS 1
l The following radionuclides concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991.
Maximum Permissible Concentrations Element Isotope Soluble Conc Insoluble Conc.
(uci/ml)
(uci/ml)
Actinium (89)
Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95)
Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 1E-4 1E-4 Am-243 1E-6 3E-5 Am-244 SE-3 SE-3 Antimony (51)
Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 1E-4 Arsenic (33)
As-73 SE-4 SE-4 As-74 SE-5 SE-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85)
Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97)
Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4)
Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35)
Cd-109 2E-4 2E-4 Cd-115m 3E-5 3E-5 Cd-115 3E-5 4E-5 Calcium (20)
Ca-45 9E-6 2E-4 Ca-47 SE-5 3E-5 Californium Cf-249 4E-6 2E-5 (98)
Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 1E-7 1E-7 Carbon (6)
Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5
Element Isotope Soluble Conc.
Insoluble (uci/ml)
Conc.
(uci/ml)
)
Cs-131 2E-3 9E-4 Cs-134m SE-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17)
Cl-36 8E-5 6E-5 Cl-38 4E-4 4E-4 Chromium (24)
Co-57 SE-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 SE-5 3E-5 Copper (29)
Cm-242 2E-5 2E-5 Cm-243 SE-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium Dy-165 4E-4 4E-4 (66) l Dy-166 4E-5 4E-5 Iridium (77)
Ir-190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26)
Fe-55 8E-4 2E-3 Fe-59 6E-5 SE-5 Lanthanum (57)
La-140 2E-5 2E-5 j
Einsteinium Es-253 2E-5 2E-5 i
(99)
Es-254m 2E-5 2E-5 Es-254 1E-5 lE-5 i
Er-169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63)
Eu-152 (9.2 6E-5 6E-5 hrs)
Eu-152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5
(
Eu-155 2E-4 2E-4 l
Element Isotope Soluble Conc.
Insoluble (uci/ml)
Conc.
(uci/ml)
Fermium (100)
Fm-254 1E-4 1E-4
)
Em-255 3E-5 3E-5
{
Fm-256 9E-7 9E-7 1
Fluorine (9)
F-18 8E-4 SE-4 Gadolinium (64)
Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31)
Ga-72 4E-5 4E-5 Germanium (32)
Au-196 2E-4 1E-4 1
~
Au-198 SE-5 5E-5 Au-199 2E-4 2E-4 Hafnium (72)
In-113m 1E-3 1E-3 In-114m 2E-5 2E-5 In-115m 4E-4 4E-4 In-115 9E-5 9E-5 Iodine (53)
I-125 2E-7 2E-4 I-126 3E-7 9E-5 I-129 6E-8 2E-4 I-131 3E-7 6E-5 I-132 8E-6 2E-4 I-133 1E-6 4E-5 I-134 2E-5 6E-4 I-135 4E-6 7E-5 Lead (82)
Pb-203 4E-4 4E-4 Pb-210 1E-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71)
Lu-177 1E-4 1E-4 Manganese (25)
Mn-62 3E-5 3E-5 Mn-54 1E-4 1E-4 Mn-56 1E-4 1E-4 Mercury (80)
Hg-197m 2E-4 2E-4 Hg-197 3E-4 SE-4 i
Hg-203 2E-5 1E-4 l
Molybdenum (42)
Mo-99 2E-4 4E-5 Neodymium (60)
Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93)
Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28)
Ni-59 2E-4 2E-3 1
l Element Isotope Soluble Conc.
Insoluble (uci/ml)
Conc.
(uci/ml)
Ni-65 1E-4 1E-4 i
Niobium (41)
Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76)03-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 US-5 SE-5 i
Palladium (46)
Pd-103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15)
Pt-191 1E-4 1E-4 Pt-193m 1E-3 1E-3 Pt-193 9E-4 2E-3 Pt-197m lE-3 9E-4 Pt-197 1E-4 1E-4 Plutonium (94)
Pu-238 SE-6 3E-5 Pu-239 SE-6 3E-5 Pu-240 SE-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 5E-6 3E-5 l
Pu-243 3E-4 3E-4 l
Polonium (84)
Po-210 7E-7 3E-5 Potassium (19)
K-42 3E-4 2E-5 Praseodymium (59)
Pr-142 3E-5 3E-5 j
Pr-143 SE-5 SE-5 Promethium (61)
Em-147 2E-4 2E-4
{
Pm-149 4E-5 4E-5 Protactinium (91)
Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 1E-4 1E-4 Radium (88)
Ra-223 7E-7 4E-6 Ra-224 2E-6 SE-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75)
Re-183 6E-4 3E-4 Re-186 9E-5 SE-5 Re-187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45)
Rh-103m 1E-2 1E-2 Rh-105 lE-4 lE-4 Rubidium (37)
Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44)
Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 C
,Ru-105 1E-4 1E-4
)Ru-106 lE-5 1E-5
i Element Isotope Soluble Conc.
Insoluble (uci/ml)
Conc.
i (uci/ml) l Samarium (62)
Sm-147 6E-5 7E-5 Sm-151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21)
Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5
)
Selenium (34)
Se-75 3E-4 3E-4 j
Silicon (14)
Ag-105 1E-4 1E-4 Ag-110m 3E-5 3E-5
)
Na-22 4E-5 3E-5 i
Na-24 2E-4 3E-5 Strontium (38)
Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E-4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 I
Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16)
S-35 6E-5 3E-4 l
Tantalum (73)
Ta-182 4E-5 4E-5 Technetium (43)
Tc-96m 1E-2 1E-2 Tc-96 1E-4 SE-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52)
Te-125m 2E-4 1E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65)
Tb-160 4E-5 4E-5 Thallium (81)
T1-200 4E-4 2E-4 T1-201 3E-4 2E-4 T1-202 1E-4 7E-5 T1-204 1E-4 6E-5 Thorium (90)
Th-227 2E-5 2E-5 Th-228 7E-6 1E-5
(
Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69)
Element Isotope Soluble Conc.
Insoluble (uci/ml)
Conc.
(uci/ml) l Tm-171 SE-4 SE-4 Tin (50)
Sn-113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74)
W-181 4E-4 3E-4 W-185 1E-4 lE-4 W-187 7E-5 6E-5 I
Uranium (92)
U-230 SE-6 SE-6 O'232 3E-5 3E-5
~
U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 Vanadium (23)
Y-90 2E-5 2E-5 Y 91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y
?
6E-5 6E-5 Y ';3 3E-5 3E-5 Zinc (30)
Zn-65 lE-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 l
Zirconium (40)
Zr-93 8E-4 8E-4 l
Zr-95 6E-5 6E-5 I
Zr-9/
2E-5 2E-5 Any single 3E-6 3E-6 radionuclides not listed above with decay mode other than alpha emission or spontaneous fission and with the radioactive half-life greater than two hours.
l l
t
Element Isotope Soluble Conc.
Insoluble (uci/ml) conc. (uci/ml)
Any single 3E-8 3E-8 radionuclides not listed i
above, which decays by alpha emission or spontaneous fission.
Notes:
- 1. If the identity of any radionuclides is not known, the limiting values for the purposes of this table shall be: 3E-8 uci/ml.
- 2. If the identity and concentration of each radionuclides are known, the limiting values should be derived as follows: Determine, for each radionuclides in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclued not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. " unity").
l