Text

Rev 4 to Offsite Dose Calculation Manual.
	ML18093B053
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Site:	Salem
Issue date:	05/17/1988
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SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Revision 4 05/17/88

Approval *. SORC Chairman.

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1 PDR ADOCK 05000272 R PDC

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SALEM GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents Introduction 1

0 Liquid Effluents

1.1 Radiation

Monitoring Instrumentation and Controls . ; ** 1.2 Liquid Effluent Monitor Setpoint Determination

1.2.1 Liquid

Effluent Monitors (Radwaste, Steam Generator Blowdown and Service Water) 1.2.2 Conservative Default Values .* 1.3 Liquid Effluent Concentration Limits -10 CFR 20 1.4 Liquid Effluent Dose Calculations

-10 CFR SO ... 1.*4.1 Member of the Public Dose -Liquid Effluents

1.4.2 Simplified

Liquid Effluent Dose Calculation

1.5 Secondary

Side Radioactive Liquid Effluents

-Dose Calculations During Primary to Secondary Leakage 1.6 Liquid Effluent Dose Projection

* * **. 2 3 4 s 6 7 7 8 1 0 1 2 2.0 Gaseous Effluents 3.0 2.1 Radi.ation Monitoring Instrumentation and Controls 2.2 2.3 Gaseous Effluent Monitor Setpoint Determination

2.2.1 Containment

and Plant Monitor 2.2.2 Conservative Default Values Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20 2.3.1 Site Boundary Dose Rate -Noble Gases 1 3 1 5 1 s 16 18 1 8 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates 19 2.4 Noble Gas Effluent Dose Calculations

-10 CFR SO 21 2.4.1 UNRESTRICTED AREA Dose -Noble Gases * * * . 21 2.4.2 Simplified Dose Calculation for Noble Gases 21 2.S Radioiodine and Particulate Dose Calculations

10 CFR SO 23 2.5.1 UNRESTRICTED ARfA Dose -Radioiodine and Particulates 23 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates

- - - - 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations

2.7 Effluent

Dose Projection Special Dose Analyses 3.1 Doses 'Due To Activities Inside .the SITE BOUNDARY 3.2 Doses to MEMBERS OF THE PUBLIC . 40 CFR 190 3.2.1 Effluent Dose Calculations

- - 3.2.2 Direct Exposure Determination 24 2S 28 29 30 30 3 1 4.0 Radiological Environmental Monitoring Program 32 32 33 4.1 Sampling Program *************

4.2 lnterlaboratory

Comparison Program

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Salem ODCM Rev. 4 05/17/88 Table of Contents -Continued Tables 1 -1 Parameters for Liquid Alarm Setpoint Determination

-Unit 1-2 Parameters for Liquid Alarm Setpoint Determination

-Unit 2 1-3 Site Related Ingestion Dose Commitment Factors, Aio 1-4 Bioaccumulation Factors CBFi)

2-1 Dose Factors for Noble Gases 2-2 Parameters for Gaseous Alarm Setpoint Determinations

-Unit 2-3 Parameters for Gaseous Alarm Setpoint Determinations

-Unit 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

2 -5 P a t h w a y D o s e P a r a me t e,_r s -A t mo s p h e r i c R e l e a s e s A-1 Calculation of Effective MPC -Unit 1 A-2 Calculation of Effective MPC -Unit 2 B-1 Adult Dose Contributions Fish and Drinking Water Unit 1 B-2 Adult Dose Contributions Fish and Drinking Water Pathways Unit 2 C-5 Effective Dose Factors .. Appendices Appendix A -Evaluation of Conservative, Default MPC Value for Liquid Effluents

Appendix B -Technical Basis for Effective Dose Factors -

Radioactive Effluents

Appendix c -Technical Bases for Effective Dose Factors -Gaseous Radioactive Effluents Appendix D -Radiological Environmental Monitoring Program -Sample Type, Location and Analysis .. 37 38 39 41 44 1 45 2 46 49 so A-4 A-5 B -5 B-5 c-s A -1 B -1 c -1 D -1

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Salem OOCM Rev. 4 05/17/88 Introduction SALEM NUCLEAR GENERATING STATION OFFSITE .DOSE CALCULATION MANUAL 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 cu.mulative 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 and 40 CFR 190. More conservative calculation methods and/or conditions (e.g., location and/or* exposure pathways) expected to yield higher computed doses than appropriate 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 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 appearing all capitalized denote Salem Technical Specifications

this document, excluding acronyms, the application of definitions as used 1 words in the

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Salem OOCM Rev. 4 05/17/88 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 Cand 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. 2) 1-R19 A,B,C,and D provide the alarm Unit 1 steam generator blowdown lines. function for Unit 2. and isolation function for the 2-R19 A,B,C and D provide this Alarm Conly> 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. 4 05/17/88 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:

where: C ( F+f) ( 1. 1) f C = the effluent concentration limit of Technical Specification C3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml c = the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution f = 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 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. large compared to Cf), then CF + f) = F.] Also, note that when CF) is

Adapted from NUREG-0133 3

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Salem ODCM Rev. 4 05/17/88 1. 2. 1 Liquid Effluent Monitors CRadwaste, 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:

where: SP = MPCe = c i MP Ci = SEN = with: MPCe

SEN

CW SP ---------------

+ bkg RR L Ci MPCe = ------------

c i MPCi ( 1. 2) ( 1 I 3 ) afarm setpoint corresponding to an effective MPC value for the effluent stream CuCi/ml) the maximum allowable release mixture of radionuclides in rate the = the concentration of radionuclide in the liquid effluent CuCi/ml)*

NOTE The concentration mix must include the most recent composite of alpha emitters, Sr-89, Sr-90, Fe-55, and H-3 per Technical Specification 3.11.1.1.

the MPC value corresponding to radionuclide from 10 CFR 20, Appendix B, Table .II, Column 2 (uCi/ml) the sensitivity value to which the monitor is calibrated Ccpm per uCi/ml) CW = the circulating water flow rate (dilution water flow) at the time of release (gal/min)

RR = the liquid effluent release rate (gal/min) bkg = the background of the monitor (cpm) 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 i s possible vi a interconnections between the Service Water Systems (see Figures and 2). 4 (cp

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Salem ODCM Rev. 4 05/17/88 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 1E-05 uCi/ml for radwaste releases (refer to Appendix A for justification);

b) for additional conservatism, substitution of the 1-131 MPC value of ** 3E-07 uCi/ml for the R19 Steam Generator blowdown monitors, 1R13 Service Water monitor and R37 Chemical Waste Basin monitor; 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. With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and for differing Circulating Water System dilutions.

Use of the effective MPC value as derived in Appendix A may be conservative for the R19 Steam Generator monitors and R37 Chemical Waste Basin monitors where 1-131 transfer during primary to secondary Leakage may potentially be more controlling.

- The Unit 2 Service Water system utilizes the Unit 1 Circulating Water' system for dilution prior to release to the river. It is possible to have the Unit Circulating Water system out of service when Unit 1 is in an outage. So, for conservatism no dilution is used for determining a 2R13 default alarm setpoint.

Because no dilution is considered and the 2R13 monitor sensitivity is high, the MPCe of 1E-05 uCi/ml is used in calculating the alarm* setpoint (otherwise using 3E-07 uCi/ml would result in an alarm setpoint of 1 cpm). 5 1 ; '

Salem ODCM Rev. 4 05/17/88 Liquid Effluent Concentration Limits -10 CFR 20 Technical Specification 3.11.1 .1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other noble gases. Noble gases are limited to a diluted concentration of 2.0E*04 uCi/ml. Release rates are controlled and radiati 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 using the following equation:

where: c i = MPCi = = RR = cw = c i RR * ( 1. 4) "pc i cw + RR a c tu a L con cent rat i on of r a d'i on u c L i de as measured i n th e undiluted Liquid effluent (uC(/mL) the MPC value corresponding to radionuclide from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/mL> 2E-04 uCi/mL for dissolved or entrained noble 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) 6

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Salem ODCM Rev. 4 05/17/88 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 Station to: during any calendar quarter; 1.5 mrem to total body per unit 5.0 mrem to any organ per unit during any calendar year; 3.0 mrem to total body per unit 10.0 mrem to any organ per unit. Per the surveillance requirements of Technical Specification 4.11.1.2, the following calculation methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem. where: Do Aio c i 1.67E*02

VOL O.o = --------------

r: (Ci

Aio) c 1. 5) cw = dose or dose commitment to organ o, including total body Cmrem) = site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i Cmrem/hr per uCi/ml) = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL CuCi/ml> VOL = volume of liquid effluent released (gal) C W = a v e r a g e c i r c u l a t i n g w a t e r d i s c h a r g e .r a t e d u r i n g r e l e a s e p e r i o d (gal/min) 1.67E-02 = conversion factor (hr/min) The *site-related ingestion dose/dose commitment factors CAi 0> are presented in Table 1-3 and have been derived in accordance with of NUREG-0133 by the equation:

7

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Salem ODCM Rev. 4 05/17/88 Aio = 1.14E+OS CCUI

Bli) + (UF

BFi)] DFi ( 1. 6) where: Aio = 1.14E+OS UI = BI i composite dose parameter for the total of an adult for radionuclide i, for ingestion pathways Cmrem/hr per uCi/ml) body or the fish critical organ o and invertebrate

= conversion factor CpCi/uCi

ml/kg : hr/yr) adult invertebrate consumption CS kg/yr) bioaccumulation factor for radionuclide Table 1-4 CpCi/kg : pCi/l) in invertebrates from adult fish consumption C21 kg/yr) UF BFi = bioaccumulation factor for radionuclide CpCi/kg per pCi/1) in fish from Table 1-4 DFi = dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E-11 of Regulatory Guide 1 .109 (mrem/pCi)

The radionuclides included in the periodic dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11*1

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11-1. 1

4. 2 Simplified Liquid Effluent Dose Calculation.

In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of Technical Specification 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.) Total Body 1.21E+03

VOL Dtb = **************

L Ci ( 1

7) cw 8

*

Maximum Organ where: c i = VOL = c IJ = Dtb = Dmax = Salem ODCM Rev. 4 05/17/88 2.52E+04

VOL Dmax = --------------

L Ci . c IJ average concentration of radionuclide i, effluent representative of the volume VOL volume of liquid effluent released (gal) in undiluted (UCi/ml) ( 1. 8) liquid average circulating water discharge rate during release period (gal/min) conservatively evaluated total body dose Cmrem) conservatively evaluated maximum organ dose Cmrem) 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 CNb-95, GI-LLI --1.51E+06 mrem/hr per uCi/ml) 9 Salem OOCM Rev. 4 05/17/88 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 for the release of radioactive material t o t h e o f f

s i t e e n v i r o n me n t < D e l a w a r e R i v e r ) v i a s e

c. o n d a r y s y s t e m d i s c h a r g e s

Potentially significant radioactive material levels and potential releases are controlled/monitored by the Steam Generator blowdown monitors CR19) 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 pr*imary 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 tlie 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 normal Ly 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 10 Salem ODCM Rev. 4 05/17/88 the environment via the Chemical Waste Basin. This approach while not exact, is

conservative and ensures timely analysis for regulatory compliance.

Accounting for radioactive material retention of the condensate clean-up sys fem ion exchange resins may be needed to more accurately account for actual releases * *

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Salem ODCM Rev. 4 05/17/88 1.6 Liquid Effluent Dose Projections Technical 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in t,he liquid waste prior to release when the quarterly projected doses exceed: 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 Figure 1-3. Alternately, the waste evaporator as presented in the Salem FSAR has processing capabilities meeting the NRC ALARA design requirements and may be used in conjunction or in lieu of the ion exchange system for waste processing require-ments in accordance with Technical Specification 3.11.1.3.

These processing requirements are applicable to each unit individually.

Exceeding the projected dose requidng 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:

where: Dtbp = Dtb = 0 maxp = 0 max = d = 91 = Dtbp = Dtb (91 : d) ( 1

9) Dmaxp =

Dmax (91 d) (1.10) the total body dose projection for current calendar quarter (mrem) the tot a l body dose to date. for current ca l end a r quarter as determined by equatioh (1.5) or (1.7) (mrem) the maximum organ dose projection for current calendar quarter <mrem) the maximum organ dose to date for current calendar quarter as determined by equation (1.5) or (1.8) (mrem) the number of days to date for current calendar quarter the number of days in a calendar quarter 12

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Salem ODCM Rev. 4 05/17/88 2.0 Gaseous Effluents

2. 1 Radiation Monitoring 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 summarized as follows:

1) Waste Gas Holdup System -The vent header gases are collected by the waste gas system. Gases may be recycled to provide cover gas for the eves 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-R41C provides noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1; this function is provided by 2-R41C 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-R41C for Unit-1 and 2-R41C 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 R41C, 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 R41C monitors.

Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers with redundant back-up sampling capabilities provided by R41B and R41A, respectively.

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 rotometer).

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 with Technical Specification 3/4.3.3, Table 3.3-6, the R12A alarm/trip setpoint shall be established at twice background, providing early indication and containment isolation accompanying unexpected increases in containment airborne radioactive material levels indicative of a fuel degradation.

The R41C monitor may also provide this function if the R12A monitor is inoperable during MODE 6. 13 Salem ODCM Rev. 4 05/17/88 A gaseous radioactive waste flow diagrams with the applicable, associated

radiation monitoring instrumentation and controls are presented as Figures 2-1 and 2-2 for Units 1 and 2, respectively

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Salem ODCM Rev. 4 05/17/88 2.2 Gaseous Effluent Monitor Setpoint Determination

2. 2. 1 Containment and Plant Monitor. Per the requirements of Technical Specification 3.3.3.9, alarm setp.oints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases 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 *radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation:

FRAC = [4.72E+02

X/Q *VF* L (Ci *Ki)]+ 500 c 2. 1 ) FRAC = C4.72E+02

X/Q *VF* r. (Ci *(Li + 1.1 3000 c 2. 2) where: FRAC = X/Q = VF = c i = Ki = L i = Mi = 1 .. , = 4.72E+02 500 = 3000 = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate annual average dispersion to the controlling site boundary location Csec/m ) ventilation system (Low rate for the applicable release point and monitor Ctt 3/min) concentration of noble gas radionuclide as determined by radioanalysis of grab sample CuCi/cm 3> total body dose conversion factor for noble gas radionuclide (mrem/yr per uCitm 3 , from Table 2-1) beta skin dose conversion factor for noble gas radionuclide Cmrem/yr per uCitm 3 , from Table 2-1) gamma a i r dose con v e rs i on f a c t o r .f o r nob l e g a s rad i on u c l i de Cmrad/yr per ucitm 3 , from Table 2-1) mrem skin dose per mrad Jamma air dose Cmrem/mrad)

= conversion factor (cm /ft 3

min/sec) total body dose rate limit Cmrem/yr>

skin dose rate limit Cmrem/yr>

15

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Salem ODCM Rev. 4 05/17/88 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applica"ble monitors CR16, R41C, and/or R12A) may be calculated by the equation:

where: SP = SEN = bkg = AF = SP = [AF

L_ Ci

SEN -FRAC] + bkg alarm setpoint corresponding to the maximum rate (cpm) monitor sensitivity (cpm per uCi/cm 3> background'of the monitor (cpm) ( 2. 3) allowable release admin.istrative 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 imposed to ensure that combined releases from Salem Units and 2 and Hope Creek will not exceed the regulatory limits on release rate the site (i.e., the release rate limits of Technical Specification Normally, the combined AF value for Salem Units 1 and 2 is 0.5 (0.25 per unit), with the remainder

0.5 allocated

to Hope Creek. Any increase in AF above 0.5 for the 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 radionuclide evaluation based on the grab sample analysis, to eliminate the of periodically having to the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-1 and 2-2 for Units and 2, respectively.

16

*

i____. Salem ODCM Rev. 4 05/17/88 These values are based upon: the maximum ventilaiion (or purge) flow rate; a radionuclide distribution*

comprised of 95X Xe-133, 2X Xe-135, 1X Xe-133m, 1X Kr-88 and 1X 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 radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Tables 2-2 and 2-3 *

Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6 17 Salem ODCM Rev. 4 05/17/88 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20

2.3.1 Site Boundary Dose Rate -Noble Gases. Technical Specification 3.11.2.1a l i m i t s t h e d o s e r a t e a t t h e S I T E B OU N D A R Y d u e t o n o b l e g a s r e l e a s e s t o 0 O m r e m /

y r , t o t a l b o d y a n d 0 0 0 m r e m I y r , s k i n

Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.

In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release may be performed using the following equations:

Dtb = X/Q *I:, (Ki *Qi) ( 2. 4) and Os= X/Q * "£((Li + 1.1Mi) *Qi) ( 2. 5) where: Dtb = total body dose rate (mrem/yr)

Os = skin dose rate Cmrem/yr)

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sectm 3> * = average release rate of radionuclide over the release period under eval*uation (uCi/sec)

Qi = total body dose conversion factor for noble gas radionuclide (mrem/yr per uc i!m 3 , from Table 2-1> Ki Li = beta skin dose conversion factor for noble gas radionuclide (mrem/yr per uc i/m 3 , from Table 2 -1 ) = gamma air dose conversion factor for noble gas radionuclide (mrad/yr per uc i!m 3 , from Table 2 -1 ) Mi 1

1 = mrem skin dose per mrad gamma air dose (mrem/mrad)

As appropriate, simultaneous releases from Salem Units and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.1a, 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 co r re l at i on of the mo n i tor re a.d i n g and mo n i tor sens i t i vi t y

The 15 minute averaging is needed to allow for reasonable monitor response to potentially

changing radioactive material concentrations and to exclude potential electronic 18

*

Salem ODCM Rev. 4 05/17/88 spikes in monitor readings that may be unrelated to radioactive material releases.

As identified, any electronic spiking monitor responses may be excluded from the analysis.

NOTE: For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the limits of Technical Specification 3.11.2.1a.

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 3.11.2.1a.

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. 2. 3. 2 Site Boundary Dose Rate

Radioiodine and Particulates.

Technical Specification 3.11.2.1.b limits the dose rate to mrem/yr to any organ for I

1 3 1 , t r i t i u m a n d p a r t i_ c u l a t e s w i t h h a l f

l i v e s g r e a t e r t h a n 8 d a y s . T o demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The following equation may be used for the rate evaluation:

where: Do X/Q R i Qi = = = Do = X/Q

L. (Ri *Qi) ( 2. 6) average organ dose rate over the sampling time period Cmrem/yr) atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway Csec/m 3> dose parameter for radionuclide i, Cmrem/yr child inhalation pathway from Table 2-5 per for the average analysis release frequency other radionuclide 8 days (uCi/sec) rate over the appropriate sampling period and for radionuclide i 1*13l, 1*133, tritium or in particulate form with half-life greater than 19

* ** Salem ODCM Rev. 4 05/17/88 By substituting 1500 mrem/yr for Do* and solving for Q, an allowab_le release rate for 1-131 can be determined.

Based on the annual average meteorological dispersion (see Table 2-4) and the most limiting p.otential pathway, age group and organ <inhalation, child, thyroid --Ri = 1.62E+07 mrem/yr per uCi/m 3), the allowable release rate for 1-131 is 42 uCi/sec. Reducing this release rate by a factor of 4 to account for potential dose contributions from other radioactive p a r t i c u l a t e m a t e r i a l a n d o t h e r r e l e a s e .p o i n t s ( e

g * , H o p e C r e e k ) , t h e 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 1-131 releases in any 7 day period do not exceed 6.3 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate

20

*

Salem ODCM Rev. 4 05/17/88 2.4 Noble Gas Effluent Dose Calculations

-10 CFR SO 2. 4. 1 UNRESTRICTED AREA Dose -Noble Gases. Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance w i th the qua r. t er L y dose L i mi ts of m rad , gamma -a i r and 1 O m rad , bet a -a i r and the calendar year Limits mrad, gamma-air and mrad, beta-air.

The Limits are applicable separately to each unit and are not combined site limits. The following equations may be used to calculate the gamma-air and beta-air doses: Dg = 3.17E-08

X/Q *I: (Mi *Qi) ( 2. 7) and Db = 3.17E-08

X/Q

L (Ni *Qi) ( 2. 8) where: 2. 4. 2 Dg Db X/Q Qi = air dose due to gamma emissions for noble gas radionuclides (mrad) = air dose due to beta emissions for noble gas radionuclides Cmrad) = atmospheric dispersion to the controllfng SITE BOUNDARY location Csectm 3> = cumulative release of noble gas radionuclide i over the period of interest CuCi) Mi = air dose factor due to gamma emissions from noble gas radionuclide (mrad/yr per uCi/m 3 , from Table 2-1) Ni = air dose factor due to beta emissions from noble gas radionuclide Cmrad/yr per uCitm 3 , Table 2-1) 3.17E-08 = conversion factor (yr/sec) Simplified Dose Calculation for Noble Gases. In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2. (Refer to Appendix C for the derivation and justification for this simplified method.) 21

*

where: Me ff = Neff = Qi = 0.50 = Dg Db Salem ODCM Rev. 4 05/17/88 3.17E-08 --------* X/Q

Meff

L_ Qi 0.50 and 3.17E-08 = --------* X/Q

Neff

1::. Qi 0.50 ( 2. 9) (2.10) 5.3E+02, effective gamma-air dose factor (mrad/yr per uCitm 3) 1.1E+03, effective beta-air dose factor (mrad/yr per uCi/m 3> cumulative release for all noble gas radionuclides (uCi) conservatism factor to account for potential variability in the radionuclide distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the and beta-air doses . 22

*

Salem ODCM Rev. 4 05/17/88 2.5 Radioiodine and Particulate Dose Calculations

-10 CFR 50 2. 5

1 UNRESTRICTED AREA Dose -Radioiodine and Particulates.

In accordance with requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of mrem and calendar year limit mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of 1-131, tritium and particulates with half-lives greater than 8 days: where: Daop R i Qi Daop 3.17E-08

W

SFp

l:_ (Ri *Qi) (2.11) = dose or dose commitment via controlling pathway p and age group a (as identified in Table 2-4) to organ o, including the total body (mrem) = = = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-4 X/Q = atmospheric dispersion for inhalation and H-3 dose contribution via other pathways (sec/m ) D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2) dose factor for radionuclide i, (mrem/yr per uCiJm 3> or cm 2 mrem/yr per uCi/sec) from Table 2-5 for each age group a and the applicable pathway p as identified in Table 2-4. Values for Ri were derived in accordance with the methods described in NUREG-0133. cumulative release over the period of --1-131 or radioactive material in life greater than 8 days (uCi). interest for radionuclide particulate form with half-SFp = annual seasonal correction factor to account for the 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 season (May through October) = o.s 2) For inhalation and ground plane exposure pathways:

= 1. 0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway and the child age group is controlling for the 23

*

Salem ODCM Rev. 4 05/17/88 vegetation pathway. Only the age group and pathway as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3.

2. 5. 2 Simplified Dose Calculation for Radioiodines and Particulates.

In lieu of the individual radionuclide CI-131 and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (refer to Appendix D for the derivation and justification of this simplified method). where: Dmax = RI-131 = = II = Omax =

II* SFp

RI-131 * [_ Qi (2.12) maximum organ dose Cmrem) 1-131 dose parameter for the thyroid for the identified controlling pathway 1.0SE+12, infant thyroid dose parameter with the cow-milk pathway controlling cm 2 -mrem/yr per uCi/sec) D/Q for radioiodine, 2.1E-10 1/m Qi = cumulative release over the period of interest for radionuclide i I-131 or radioactive material in particulate form with half life greater than 8 days (uCi) 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

24

Salem OOCM Rev. 4 05/17/88 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 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 e vacua t i. on, R 4 1 C on pl ant vent , and the pl ant vent pa rt i cu l ate and ch a r co a l 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 radioiodines and particulates 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 calculate potential releases.

Based on the guidance in NRC NUREG-Q133, the releases of the radioiodines and particulates may be calculated by the equation:

where: Qi = c i = Rsgb = Fft = Qi = Ci

Rsgb

Fft * (1-SQftv)

(2.13) the release rate of radionuclide, *i, from the steam generator flash tank vent (uCi/sec) the concentration of radionuclide, i, in th'e secondary coolant water averaged over not more than one week (uCi/ml) the steam generator b(owdown rate to the flash tank the fraction of blowdown *flashed in the tank. determined from a heat balance taken around the flash tank at the applicable reactor power level SQftv = the measured steam quality in the flash tank. vent; or an assumed value of 0.85, based on NUREG-0017.

25

*

Salem ODCM Rev. 4 05/17/88 Tritium releases via the steam flashing may als'o be quantified using the above equation*

with the assumption of d steam quality CSQftv> 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 particula.tes.

Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam CFft) is approximately 0.48. following:

Qi = 0.072 Ci Rsgb For H-3, the simplified equation is: Qi = 0.48 Ci Rsgb The equation simplifies to the (2.14) (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 CPORV) 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 tlie 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 fo*r all other particulate radioactive material.

The resulting equation for quantifying releases via the atmospheric steam releases is: 26

*

Salem ODCM Rev. 4 05/17/88 where: Qi j SFj Qi = 0.13

r,ccij

Sfj)

PF = release rate of radianuclide i via pathway (uCi/sec)

=

flow for release pathway = 450,000 lb/hr per PORV = 800,000 lb/hr per safety relief valve = 50,000 lb/hr for feed pump exhaust PF = partitioning factor, ratio of concentration in steam to that in the water in the steam generator

= 0.01 for radioiodines

= 0.005 for all other particulates

= 1

0 for H'-3 (2.16) 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.

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 radionuclide concentration in the steam may be used for quantifying the noble gases, radioiodine and particulate releases.

Note: The expected mode of operation would be to isolate the effected steam genera to r , t.h ere by red u c i n g th e potent i a l re l eases du r i n g th e shutdown/cooldown process. Use of the above calculation methods should consider actual operating conditions and release mechanisms.

The calculated quantities of radioactive materials may be used as inputs to the equation (2.11) or (2.12) to calculate offsite doses for demonstrating compliance with the Radiological Effluent Technical Specifications

27

*

Salem ODCM Rev. 4 05/17/88 2.7 Gaseous Effluent Dose Proiection Technical 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 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 gp =

(2.17) D bp = Db

C91T d) (2.18) Dmaxp = Dmax

d) (2.19) where: D g'p Dg D bp Db Dmaxp Dmax d 91 = = = = = = = = gamma air dose projection for .current calendar quarter (mrad) gamma air dose to date for current calendar quarter as determined by equation (2.7) or (2.9) Cmrad) beta atr dose projection for current calendar quarter (mrad) beta air dose to date for current calendar quarter as determined by equation (2.8) or (2.10) (mrad) organ dose projection for current calendar quarter Cmrem) maximum organ dose to date for current calendar quarter as by equation (2.11) or (2.12) Cmrem) number of days to date in current calendar quarter number of days in a calendar quarter .28

*

Salem OOCM Rev. 4 05/17/88 3.0 Special Dose Analyses 3. 1 Doses Due To Activities lns{de the SITE BOUNDARY In accordance with Technical Specification 6.9.1.11, the Radioactive Effluent Release Report CRERR) submitted within 60 days after January of each year 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.

There is one location on Artificial Island that is accessible to MEMBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities. "This location is the Second Sun (visitor's center) located near the contractors gate for the. Salem Nuclear Generating Station. The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-4 and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per visit per year. The default value for* the meteorological dispersion data as presented in. Table 2-3 may be used if current year meteorology in unavailable at the time of NRC reporting.

However, a follow-up evaluation shall be performed when the data becomes available . 29

*

Salem ODCM Rev. 4 05/17/88 3.2 Total dose to MEMBERS OF PUBLIC -40 CFR 190 The Radioactive Effluent Release Report CRERR) submitted within 60 days* after January 1 of each year shall also include an assessment of the radiation dose to the Lilcely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources dose contributions from effluents and direct radiation from on-site sources).

For the lilcely 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 Creelc 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 thfi! operation of Hope Creelc Nuclea-r Generating Station wi L l be estimated based on .the methods as presented in the Hope Creelc 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 environme'ntal monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.

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 for the Salem Nuclear Generating Station may be performed using the calculation methods contained within this ODCM; the conservative controlling pathways and of Table 2-4 or the actual pathways and Locations as identified by the land use census (Technical Specification 3/4.12.2) may be used. Average annual meteorological dispersion 30

*

Salem ODCM Rev. 4 05/17/88 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 d u r i n g a t y p i c a l c o n d i t i o n s w i l l t h e r e e x i s t a n y p o t e n t i a l f o r s i g n i f i c a n t o n

.s i t e 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 whereby the direct expos,ure 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

31

*

Salem ODCM Rev. 4 05/17/88 4.0 Radiological Environmental Monitoring Program 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program CREMP) is conducted in accordance with the requirements of Appendix A Technical Specification 3.12. The objectives of the program are: To determine whether any significant increases occur in the concentration of radionuclides in the critjcal pathways of exposure in the vicinity of Artificial Island; -To determine if the operation of the Salem Nuclear Generating 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 health and safety of the public or on the environment.

The sampling requirements (type of samples, collection frequency and analysis) and sample Locations are presented in Appendix E

32 Salem ODCM Rev. 4 05/17/88 4.2 Interleboratory Comparison Program

Technicaj Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison.

Participation in an approved Interlaboratory Comparison Program provides a check on the 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 . *

33 HJXED BED DEHINERIUZER ASTE f2 REACTOR COOLANT FIL TEA VOLUllE CONTROL TANK Rl9A0 0Rl90 I

IASTE MONITOR Hll.D-LlP T-11 VENT I I OA SC STH GEN I I llOOllt+N-+-* STH GEN I I I I llOOllPl-1-..-------+*

61l4,'-'----+lll88---oi I STH GEN I I I I )100111

E841-'--'----+<ll88---oi 12 REACTOR COO.ANT OAA IN TFN:

RADIATION MONITORING LIQUID RELEASES UNIT 2 FIGURE 1-2 REFUELING IATER STOMGE Tfvt( f21 Hll.D-LlP Tfvt( VENT f22 HDLD-LlP TANIC IFROll I VOL. CONTROL TANK VENT VENT TO GASEOUS AADIASTE f2l HOLD-LlP TIW:

GAS SIHIPPER FEED CDllPOllENT COO.ING SIJlSE Tfvt( R29o R2e 0 REFl£1.. IATER [l] D RlO FILTER

..-El-12 SPENT FUEL PIT PUlf' L-1 IPIT DEHINEAALIZEA IASTE HOLD-LlP Tfvt( f 11 STEAM GENERATOR BLDIOOIN TflNI: SKJllHER FILTER FILTER '---------J VENT IASTE HOLD-UP TANK 112 VENT TO AUX BLDG VENT SYS TO BORIC ACID 1 EVAPORATOR NO* 1 IASIE EVAPOAATOA NO* 1 GAS STRIPPER f2 ION [j] EXCHANGER I IASTE HONllOR TPH: 111 IASTE l'IOHllOA TANK 112 NO. 21 EVAPORATOR FEED JON EXCHANGE A ,-,All '--' NO* 22 EVAPORATOR FEED ION EXCHANGE A I FA011 HONJTOR 1 r TANK PlttPS NO-2l EVAPORATOR FEED ION EXCl'lll<<JEA

-**" = HOLD-LlP IANI: PlttPS NO* 24 EVAPORATOR FEED ION EXC!ilNGCA I *Cll4llL____...L---,...----'

TO +--------081 B C!HJENSM +----GBJB

+-----<lBIB LICUID IASTE DISPOSll.

CIAC IATER !FOR JNfOAl1ATION OllLYJ WM..iTOIHfllUNT Wl.1'7 1WMT -I FROMCVCS I NON oo; I I I I WI. 1111 I IDIFROM cmtER UNIT 'M.47 L-----Wl.51 w1.11M Wl.115 TONIO FROM OIHER UNIT

WMSTEEVAP FEEOl'UMP FROM W\1111 WI.In FROM BAEVAP WI. I I I t WHUT .... Wl11 2WHUT Wllrl!I Wl.11 WHUl!i Wl.11 Wl.12 FC FC Wl.13 4-... I VMSIEEVAP:

I I EOUIPDAS FLOOR ORS CVCS HUI RELIEFS -SUMPS -Wl2Z1 RWST CVCSHUT DR WI. 13 WI." Wl.18 Wll7 Wllt CONT-Wl.',. 1" 2"'1.114 2WI. -Wl.7 lllCPHfllll TllS RCLOC.OAS Rll FlAHGE l 0 AllCtMJlATOR OAS Ella:SS LET 1XMN RCOT ACPS 3SEAl.LO l'mDR _______ ,.. _______ ,.._

.. ........

,..,. ..........

Wl.183 I : + IWUllO --I T-----M--*

2MHJT .a. 2Wl911 *--..

J *-rf-----4*--f---OO-

I -...-..,--+---.-tt-+:

on fl . x-t-1 *WR21 6 6 !Mn* !Mn* L------1--.J I.WIS llW41

WUJll Wl.71 WUll3 FOR INFORMATION 0 FIGURE 1-3 LIQUID WASTE *

*

Parameter Actual Value ----------------MP Ce calculated MPCl-131 3E-07 Ci measured MPCi as determined SEN 1-R18 as determined 1-R19 (A,B,C,D) 1-R13 CA,B,C,D,E) cw as determined RR 1-R18 as determined 1-R19 1-R13 SP 1-R18 calculated 1-R19** calculated 1-R13** calculated Salem OOCM Rev. 4 05/17/88 Table 1-1 Parameters for Liquid Alarm Setpoint Determinations Unit 1 Default Units Value ------------------

1E-05

uCi/ml N/A uCi/ml N/A uCi/ml N/A uCi/ml 2.9E+07 cpm per uCi/ml 2.9E+07 1.2E+08 1.85E+OS gpm 120 gpm 120 2500 4.4E+OSC+bkg) cpm 1.3E+04C+bkg) 2.6E+03C+bkg)

Comments -------------------------------------------

calculate for each batch to be released 1-131 MPC conservatively used for SG blow-down and Service Water monitor setpoints taken from gamma spectral analysis of liquid effluent taken from 10 CFR 20, Appendix B, Table Col. 2. radwaste effluent (Cs-137) Steam Generator blowdown (Cs-137) Service Water -Containment fan cooling (Cs-137) Circulating Water System, single CW pump II, determined prior to release; release rate can be adjusted for Technical Specification compliance Steam Generator blowdown rate per generator Service Water flow rate for Containment fan coolers Default alarm setpoints; more conservative values may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA.

Refer to Appendix A for derivation

- The MPC values of 1-131 (3E-07 uCi/ml) has been used for derivation of the R19 Steam Generator blowdown and R13 Service Water monitor setpoints as discussed in Section 1.2.2. 37

*

Salem OOCM Rev. 4 05/17/88 Parameters for Liquid Alarm Setpoint Determinations Unit 2 Parameter Actual Default *uni ts Value Value ----------------------------------

MP Ce calculated 1E-05

uCi/ml MPCl-131 3E-07 N/A uCi/ml Ci measured N/A uCi/ml MP Ci as N/A uCi/ml determined SEN 2-R18 as 8.8E+07 cpm per uCi/ml determined 2-R19 8.8E+07 CA,B,C,D) 2-R13 8.8E+07 (A,B,C,D,E)

R37 8.8E+07 cw as 1.85E+OS gpm determined RR 2-R18 as 120 gpm determined 2-R19 120 2-R13 2500 R37 300 SP 2-R18 calculated 8.0E+05C+bkg) cpm 2-R19** calculated 3.9E+04C+bkg) 2-R13** calculated 8.8E+02(+bkg)

R37**** calculated 1.6E+04(+bkg)

** Refer to Appendix A for derivation Based on Cs-137 response Comments -------------------------------------------

calculate for each batch to be released 1-131 MPC conservatively used for SG blow-down, Service Water and Chemical Waste Basin monitor setpoints taken from gamma spectral analysis of liquid effluent taken from 10 CFR 20, Appendix B, Table Col. 2. radwaste effluent (Cs-137) Steam Generator blowdown (Cs-137) Service Water -Containment fan cooling (Cs-137) Chemical Waste Basin (Cs-137) 11, Circulating Water System, single CW pump (Note no CW pump in service for 2R13 monitor see section 1.2.2) determined prior to release; release rate can be adjusted for Technical Specification compliance Steam Generator blowdown rate per generator Service water flow rate for Containment fan coolers Chemical Waste Basin discharge Default alarm setpoints; more conservative values may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA. *** Actual calculated setpoint for 2-R18 (1.3E+06) is greater than the full scale monitor indicator, therefore, for conservatism the recommended setpoint has been reduced to 8.0E+OS cpm **** The MPC value of 1-131 (3E-07 uCi/ml) has been used for derivation of the R19 Steam generator blowdown and the R37 Chemical Waste Basin monitor setpoints as discussed in Section 1.2.2 38 Salem ODCM Rev. 4 05/17/88 I Table 1 -3

Site Related lngest"ion Dose Commitment Factors, Aio (mrem/hr per uCi/ml) Nuclide Bone Liver T.Body Thyroid Kidney Lung Gl*LLI --------------------------------------------------------H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 C-14 1 .45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 P-32 4.69E+6 2.91E+5 1.81E+5 5.27E+5 Cr -5 1 5.58E+O 3.34E+O 1. 23E+O 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1. 78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1. 90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1. 42E+2 2.36E+2 3.59E+3 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 -6 5 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 Br-82 4.07E+O 4.67E+O Br-83 7.25E-2 1.04E-1 Br-84 9. 39E--2 7.37E-7 Br-85 3.86E-3 Rb-86 6.24E+2 2.91E+2 1.23E+2 Rb-88 1. 79E+O 9.49E-1 2.47E-11 Rb-89 1.19E+O 8.34E-1 6.89E-14 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+O 4.37E+2 Sr-92 3.48E+1 1.51E+O 6.90E+2 Y-90 6.06E+O 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-91 8.88E+1 2.37E+O 4.89E+4 Y-92 L32E-1 1.56E-2 9.32E+3 Y-93 1. 69E+O 4.66E-2 5.35E+4 Zr-. 9 5 1.59E+1 5.11E+O 3.46E+O 8.02E+O 1.62E+4 Zr-97 8.81E-.1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 Nb-97 3.75E+O 9.49E-1 3.46E-1 1.11E+O 3.50E+3

Mo-99 -1. 28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 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 39 --------------

li . Salem ODCM Rev. 4 05/17/88 ,. Table 1 -3 (cont'd> Site Related Ingestion Dose Commitment Factors, Aio Cmrem/hr per uCi/ml> Nuclide Bone Liver T.Body Thyroid Kidney Lung Gl-LLI ----------------------------

...............

Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-105 8.89E+O 3.51E+O 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+O 1. 1 OE+2 6.71E-1 2.15E+2 7.86E+3 Sb-125 1.77E+2 1. 98E+O 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 8.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23E+3 1. 84E+3 Te-127 8. 90E+O* 3.20E+O 1.93E+O 6.60E+O 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+O 9.SSE-1 6.19E-1 1.9SE+O 1.07E+1 1.92E+O Te-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 6.80E+3 Te-131 1. 59E+O 6.66E-1 S.03E-1 1.31E+O 6.99E+O 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 S.35E+2 8.23E+1 I -132 1.06E+1 2.85E+1 9.96E+O 9.96E+2 4.54E+1 5.35E+O I -133 7.45E+1 1.30E+2 3.95E+1 1. 90E+4 2.26E+2 1.16E+2 I -134 5.56E+O 1.51E+1 S.40E+O 2.62E+2 2.40E+1 1.32E-2 I -13 5 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 cs-134 6.84E+3 1.63E+4 1.33E+4. 5.27E+3 1.75E+3 2.8SE+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 7.8SE+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+O 1.20E+1 S.94E+O 8.81E+O 8.70E-1 S.12E-5 Ba-139 7.85E+O 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+O 1. 08E+2 7.02E-1 1.18E+O 3.38E+3 Ba-141 3.81E+O 2.88E-3 1.29E-1 2.68E-3 1.63E-3 1.80E-9 8a-142 1.72E+O 1.77E-3 1.0SE-1 1.SOE-3 1.00E-3 2.43E-18 La-140 1.57E+O 7.94E-1 2.10E-1 5.83E+4 La-142 8.06E-2 3.67E-2 9.13E-3 2.68E+2 Ce-141 3.43E+O 2.32E+O 2.63E-1 1. 08E+O 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+O 4.43E+1 -6.04E+4 Pr-143 5.79E+O 2.32E+O 2.87E-1 1.34E+O 2.54E+4 Pr-144 1;90E-2 7.87E-3 9.64E-4 4.44E-3 2.73E-9

Nd-147 3.96E+O 4.58E+O 2.74E-1 2.68E+O 2.20E+4 W-187 9.16E+O 7.66E+O 2.68E+O 2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 40 -----

I I._ ll * ,, Element H c Na p Cr Mn -Fe Co Ni cu Zn Br Rb _s r y Zr Nb Mo Tc Ru Rh Ag Sb Te I Cs Ba La Ce Pr Nd w Np Table 1-4 Bioaccumulation Factors (Bfi) (pCi/kg per pCi/liter)*

Saltwater Fish 9.0E-01 1.8E+03 6.7E-02 3.0E+03 4.0E+02 5.5E+02 3.0E+03 1. OE+02 1.0E+02 6.7E+02 2.0E+03 1.SE-02 8.3E+OO 2.0E+OO 2.5E+01 2.0E+02 3.0E+04 1.0E+01 1.0E+01 3.0E+OO 1.0E+01 3.3E+03 4.0E+01 1.0E+01 1.0E+01 4.0E+01 1. OE+01 2.5E+01 1.0E+01 2.5E+01 2.SE+01 3.0E+01 1.0E+01 Salem ODCM Rev. 4 05/17/88 Saltwater Invertebrate 9.3E-01 1.4E+03 1.9E-01 3.0E+04 2.0E+03 4.0E+02 2.0E+04 1. OE+03 2.SE+02 1. 7E+03 5.0E+04 3.1E+OO 1.7E+01 2.0E+01 1. OE+03 8.0E+01 1. OE+02 1.0E+01 5. 0 E +_O 1 *1.0E+03 2.0E+03 3.3E+03 5.4E+OO 1. OE+02 5.0E+01 2.5E+01 1.0E+01 1.0E+03 6.0E+02 1. OE+03 1. OE+03 3.0E+01 1.0E+01

Values in this table are taken from Regulatory Guide 1.109 except for phosphurus (fish) which is adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev. 1, October 1972. 41

............... * ------.. .. * .. ---.... ..... ... ... .. 1111 -.. -..... ... MIC ..... ..... MtDtll MIOt .. MICllM --*IC .._._, -... _ .., ... _ ...... M .. lt -=.......---*

--* I -'"""'--, L I --;t:-i.:*

--'------' I.:,__ <XlN!.""l AOOll ----.. _J ,-----. -*-----, I I I ' FOR INFORMATION ONLY FIGURE 2-2 RADIATION GA MONITORING SEOUS 2UNIT Salem ODCM Rev. 4 05/17/88 Table 2-1 Dose Factors for Noble Gases ,. Total Body Gamma Air Beta Air I\ Dose Factor Skin Dose Factor Dose Factor Dose Factor Radionuclide Ki Li Mi Ni I Cmrem/yr per uCi/m3) Cmrem/yr per uCi/m3) Cmrad/yr per uCi/m3) Cmrad/yr per uCi/m3) ------------

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1. 72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2-37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1. 73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7. 11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1 .86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-i38 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

44

I / \ I *

Parameter Actual Value ----------------X/Q calculated VF as measured (Plant or Vent) fan curves VF as measured (Cont. or Purge) fan curves AF coordinated with HCGS Ci measured I( i nuclide specific Li nuclide specific Mi nuclide specific SEN 1-R41C* as determined 1-R16 1-R12A SP 1-R41C calculated 1-R16 calculated 1-R12A** calculated Salem ODCM Rev. 4 05/17/88 Table 2-2 Parameters for Gaseous Alarm Setpoint Determinations Unit-1 Default Units Value ------------------

2.2E-06 sectm 3 1.25E+05 ft 3 tmin 3.SE+04 0.25 unit less N/A uCi/cm 3 N/A mrem/yr per uCiJm 3 N/A mrem/yr per uCitm 3 N/A mrad/yr per uCitm 3 1 .6E+07 cpm per uCi/cm 3 3.6E+07 2.1E+06 3.3E+04(+bkg) cpm 7.4E+04C+bkg) 1.5E+04(+bkg)

Comments USNRC Salem Safety Evaluation, Sup. 3 Plant Vent -normal operation Containment purge Administrative allocation factor to ensure combined releases do not exceed release rate limit for site. Values from Table 2-1 Values from Table 2-1 Values from Table 2-1 Plant Vent Plant Vent (redundant)

Containment Default alarm setpoints; more conservative values may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA.

Based on mean for calibration with mixture of radionuclides

- Applicable during MODES 1 through 5. During.MODE 6 (refueling), monitor setpoint shall be. reduced to 2X background in accordance with Jech Spec Table 3.3-6

45.

*

Parameter Actual Value ----------------X/Q calculated VF as measured (Plant or Vent) fan curves VF as measured (Cont. or Purge) fan curves AF coordinated with HCGS Ci measured Ki nuclide specific Salem ODCM Rev. 4 05/17/88 Table 2-3 Parameters for Gaseous Alarm Setpoint Determinations Unit-2 Default Units Value ------------------

2.2E*06 sec/m 3 1.25E+05 ft 3/min 3.5E+04 0.25 unit less N/A uCi/cm 3 N/A mrem/yr per uCi/m 3 Comments licensing technical specification value Plant

-normal operation Containment purge Administrative allocation factor to ensure combined releases do not exceed release rate limit for site. Values from Table 2-1 Li nuclide specific*

N/A mrem/yr per uCi/m 3 Values from Table 2-1 Mi nuclide specific N/A mred/yr per uCi/m 3 Values from Table 2-1 SEN 2*R41C* es 1 .6E+07 cpm per uCi/cm 3 Plant Vent determined 2*R16 3.5E+07 Plant Vent (redundant) 2*R12A 3.3E+07 Containment SP 2-R41C calculated 3.3E+04(+blcg) cpm Default alarm setpoints; more conservative values may be used as deemed appropriate and 2-R16 calculated 7.2E+04C+blcg) desirable for ensuring regulatory compliance and for maintaining releases ALARA. 2-R12A** calculated 2.4E+05(+blcg)

Based on mean for calibration with mixture of redionuclides

- Applicable during MODES 1 through 5. During MODE 6 (refueling),

setpoints shall be reduced to 2X background in accordance with Tech Spec Table 3.3-6

46

*

Salem ODCM Rev. 4 DS/17/88 Table 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

Atmospheric Dispersion Technical Specification 3.11.2.1a 3.11.2.1b 3.11.2.2 3.11.2.3 6.9.1.10 Location site boundary (0.83 mi le, N> site boundary (0.83 mi le, N) site boundary (0.83 mi le, N) residence/dairy (4.8 miles, NNE) Second sun (0.21 mile/SE) Pathway(s) noble gases direct exposure inhalation gamma-air beta-air milk and ground plane direct exposure and inhalation Controlling Age Group N/A child N/A infant N/A X/Q ( sectm 3) 2.2E-06 2.2E-06 2.2E-06 S.4E-08 8.22E-06

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)

47 N/A N/A N/A 2.1E-10 N/A I Salem ODCM Rev. 4 05/17/88 Table 2-5 ** Pathway Dose f.actors -Atmospher;c Releases R(;o), lnhalat;on Pathway Dose Factors -ADULT Cmrem/yr per uC;/m3) Nucl;de Bone L;ver Thyroid Kidney Lung GI-LLI T. Body --------------------------------------------------------H-3 1 -26E+3 1. 26E+3 1. 26E+3 1. 26E+3 1. 26E+3 1. 26E+3 C-14 1. 82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1. 32E+6 7.71E+4 8.64E+4 5.01E+4 Cr -5 1 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 3.96E+4 9.84E+3 1. 40E+6 7 .*74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 1 .02E+6 1. 88E+5 1 .06E+4 Co-57 6.92E+2 3.70E+5 3.14E+4 6.71E+2 Co-58 1. 58E+3 9.28E+5 1.06E+5 2.07E+3 Co-60 1.15E+4 5.97E+6 2.85E+5 1. 48E+4 Ni-63 4.32E+5 3.14E+4 1. 78E+5 1.34E+4 1 .45E+4 Zn-65 3.24E+4 1.03E+5 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 1 .35E+5 1. 66E+4 5.90E+4 Sr-89 3.04E+5 1. 40E+6 3.50E+5 8.72E+3

Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6 Y-91 4.62E+5 1. 70E+6 3.85E+5 1.24E+4 Zr-95 1.07E+5 3.44E+4 5.42E+4 1. 77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1. 53E+3 5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-106 6.91E+4 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ag-110m 1. 08E+4 1. OOE+4 1. 97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 1.74E+6 1.01E+5 1. 26E+4 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. 5.8E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 I -131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 1. 04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 8.56E+4 1. 20E+4 1;17E+4 1.10E+5 cs-137 4.78E+5 6.21E+5 2.22E+5 7.52E+4 8.40E+3 4.28E+5 Ba-140 3.90E+4 4.90E+1 1.67E+1 1. 27E.+6 2.18E+5 2.57E+3 Ce-141 1 .99E+4 1.35E+4 6.26E+3 3.62E+5 1. 20E+5 1.53E+3 Ce-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.00E+5 4.64E+2

Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73E+5 3.65E+2 . pa 48 Salem ODCM Rev. 4 05/17/88

Table 2-5 (cont'd) RCio), Inhalation Pathway Dose Factors -TEENAGER Cmrem/Yr per uCi/m3> Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI T.Body ---------------------.. -.. --.. -..............

H-3 1.27E+3 1.27E+3 1.27E+3 1. 27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+5 9.28E+4 7.16E+4 Cr -51 7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Mn-54 5.11E+4 1.27E+4 1. 98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 1.53E+6 1. 78E+5 1.43E+4 Co-57 6.92E+2 5.86E+5 3.14E+4 9.20E+2 Co-58 2.07E+3 1.34E+6 9.52E+4 2.78E+3 Co-60 1.51E+4 8.72E+6 2.59E+5 1. 98E+4 Ni -63 5.80E+5 4.34E+4 3.07E+5 1. 42E+4 1. 98E+4 Zn-65 3.86E+4 1.34E+5 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 1. 90E+5 1.77E+4 8.40E+4 Sr-89 4.34E+5 2.42E+6 3.71E+5 1. 25E+4

Sr-90 1.08E+8 1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 2.94E+6 4.09E+5 1. 77E+4 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. OOE+4 7.51E+5 9.68E+4 5.66E+3 Ru-103 2.10E+3 7.43E+3 7.83E+5 1. 09E+5 8.96E+2 Ru-106 9.84E+4 1 .90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-110m 1.38E+4 1.31E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4. 7.94E+2 9.76E+1 3.85E+6 3.98E+5 1. 68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1. 72E+4 Te*125m 4.88E+3 2.24E+3 1. 40E+3 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1. 66E+6 1. 59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1. 98E+6 4.05E+5 2.25E+3 I -131 3.54E+4 4.91E+4 1. 46E+7 8.40E+4 6.49E+3 2.64E+4 Cs-134 5.02E+5 1.13E+6 3.75E+5 1. 46E+5 9.76E+3 5.49E+5 cs-136

1. 94E+5 1.10E+5 1. 78E+4 1. 09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 3.04E+5 1.21E+5 8.48E+3 3.11E+5 Ba-140 5.47E+4 6.70E+1 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 1.21E+6 1. 34E+7 8.64E+5 2.62E+5 Pr-143 1 .34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2

Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1. 82E+5 5.13E+2 49 I_

.-* Nuclide H-3 c-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co*58 Co*60 Ni* 63 Zn-65 Rb-86 Sr*89 Sr*90 Y-91 Zr-95 Nb*95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te*129m I -131 Cs-134 Cs*136 Cs-137 Ba-140 Ce*141 Ce-144 Pr-143 Nd-147 Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) RCio), Inhalation Pathway Dose Factors

CHILD Cmrem/yr per uCi/m3) Bone 3.59E+4 Liver 1.12E+3 6.73E+3 2.60E+6 1.14E+5 4.29E+4 4.74E+4 2.52E+4 2.07E+4 3.34E+4 9.03E+2 8.21E+5 4.26E+4 5.99E+5 1.01E+8 9.14E+5 1. 77E+3 1.31E+4 4.63E+4 1.13E+5 1. 98E+5 1.90E+5 4.18E+4 2.35E+4 9.18E+3 2.79E+3 1. 36E+5 1. 69E+4 5.74E+4 9.84E+4 6.73E+3 2.49E+4 1. 92E+4 4.81E+4 6.51E+5 6.51E+4 9.07E+5 7.40E+4 3.92E+4 6.77E+6 1.85E+4 1 .08E+4 1.14E+4 7.40E+2 7.59E+2 2.33E+3 8.55E+3 6.85E+3 4.81E+4 1.01E+6 1.71E+5 8.25E+5 6.48E+1 1 .95E+4 2.12E+6 5.55E+3 8.73E+3 Thyroid 1.12E+3 6.73E+3 Kidney 1.12E+3 6.73E+3 Lung 1.12E+3 6.73E+3 Gl*LLI 1.12E+3 6.73E+3 T.Body 1.12E+3 6.73E+3 4.22E+4 9.88E+4 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2

1. 26E+2 9.10E+1 1. 92E+3 6.07E+3 6.33E+3 1. 62E+7 1.00E+4 1.58E+6 2.29E+4 9.51E+3 1.11E+5 2.87E+3 7.77E+3 1.27E+6 7.07E+4 1.67E+4 5. 07E+5 1. 32E+4 1. 07E+3 7.14E+4 5.96E+4 8.62E+3 1.11E+6 3.44E+4 3.16E+3 7.07E+6 2.75E+5 9.95E+5 9.62E+4 6.33E+3 1.63E+4 2.26E+4 2.80E+4 7.03E+4 7.99E+3 1.14E+5 2.16E+6 1.67E+5 1.72E+4 1.48E+7 3.43E+5 6.44E+6 2.63E+6 1.84E+5 2.44E+4 2.23E+6 6.11E+4 3.70E+4 6.14E+5 3.70E+4 6.55E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 1.84E+5 1.43E+7 4.29E+5 1.69E+4 2.12E+4 6.36E+4 5.03E+4 7.88E+4 3.30E+5 9.55E+4 2.82E+5 2.11E+1 8.55E+3 1.17E+6 3.00E+3 4.81E+3 50 5.48E+6 3.24E+6 2.32E+6 4.77E+5 1. 48E+6 1. 76E+6 1.21E+5 1. 45E+4 1. 04E+5 1. 74E+6 5.44E+5 1. 20E+7 4.33E+5 3.28E+5 1.00E+5 1. 64E+5 4.03E+4 3.38E+4 7.14E+4 1.82E+5 2.84E+3 3.85E+3 4.18E+3 3.62E+3 1. 02E+5 5.66E+4 3.89E+5 9.73E+4 8.21E+4 9.14E+3 2. OOE+.4 2.07E+4 9.14E+2 3.02E+3 3.04E+3 2.73E+4 2.25E+5 1.16E+5 1. 28E+5 4.33E+3 2.90E+3 3.61E+5 9.14E+2 6.81E+2 Salem ODCM Rev. 4 05/17/88 51

*

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni -63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95* Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem ODCM Rev. 4 05/17/88 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 uCi/sec) for others 3.63E+5 Liver 7.63E+2 7.26E+4 Thyroid 7.63E+2 7.26E+4 Kidney 7.63E+2 7.26E+4 Lung 7.63E+2 7.26E+4 Gl-LLI 7.63E+2 7.26E+4 T.Body 7.63E+2 7.26E+4 1.71E+10 1.06E+9 1.92E+9 6.60E+8 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 2.51E+7 2.98E+7 8.40E+6 1. 73E+7 7.00E+7 1. 28E+6 4.72E+6 1.64E+7 6.73E+9 4.66E+8 1.37E+9 4.36E+9 1. 45E+9 4.68E+10 8.60E+3 1.35E+S 1. 07E+S 3. 44E+4 1.41E+4 7.82E+3 1. 02E+3 2.04E+4 5.83E+7 2.57E+7 2.04E+7 1. 63E+7 5.39E+7 4.86E+5 2.28E+5 5.90E+6 6.24E+4 2.08E+4 4.90E+6 4.58E+7 6.04E+7 2.96E+8 1.64E+7 1.17E+7 2.25E+7 2.08E+7 4.24E+8 1.39E+11 5.6SE+9 1.34E+10 2.61E+8 1.03E+9 7.38E+9 1.01E+10 2.69E+7 . 4.84E+3 3.27E+3 3.58E+S 1.SOE+5 1.59E+2 6.37E+1 9.42E+1 2.SOE+6 2.92E+9 9.67E+6 1.95E+7 2.57E+7 9.95E+6 2.33E+8

3.25E+7 1. 60E.+6 4.04E+6 2.68E+7 2.13E+6 9.57E+7 1.06E+7 3.08E+8 3.62E+7 9.73E+7 2.26E+8 2.75E+9 1.97E+9 1 .66E+4 5 .90E+4 2.33E+8 ,.16E+7 1.35E+9 1.15E+10 4.73E+6 2.30E+2 5.24E+4 1.77E+6 1.SOE+S 2.33E+4 7.74E+3 5.0SE+S 1.04E+5 4.21E+3 3.89E+3 3.94E+4 1.06E+8 6.63E+7 1.86E+8 2.52E+8 7.27E+8 1.19E+S 4.39E+2 1.32E+6 2.58E+3 2.20E+10 2.00E+7 7.31E+8 1.58E+7 2.25E+8 6.SOE+7 1. 54E+8 3.04E+8 1.12E+8 3.20E+7 1. 02E+7 4.86E+6 2.18E+6 9.57E+6 2.43E+8 4.35E+9 1.44E+9 2.35E+8 f.10E+10 5.74E+8 7.87E+7 1.17E+8 7.42E+8 3.43E+9 1.14E+9 1.9SE+8 6.61E+9 1 .1 SE+4 1. 93E+4 5. 54E+7 1. 76E+6 1.52E+3 1.25E+7 3.71E+2 8.87E+4 3.68E+1 6.37E+1 52 1.21E+8 1.92E+4 6.96E+S 7.88E+O S.23E+S 6.52E+O

*

Salem ODCM Rev. 4 05/17/88 Table 2*5 (cont'd) RCio), Grass*Cow*Mitt Pathway Dose Factors

TEENAGER Cmrem/yr per uCi/m3) for H-3 and C*14 Cm2

mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung Gl*LLI T.Body __ .;. ___ _ H-3 C*14 6.70E+5 9.94E+2 1. 34E+5 1.95E+9 9.94E+2 1. 34E+5 9.94E+2 1. 34E+.5 9.94E+2 1.34E+5 9.94E+2 1.34E+5 2.65E+9 9.94E+2 1.34E+5 1.22E+9 P*32 3.15E+10 Cr*51 Mn*54 Fe-55 Fe*59 Co-57 Co-58 Co-60 Ni* 63 Zn*65 Rb*86 Sr-89 Sr-90 Y-91 zr-95 Nb*95 Ru-103 Ru-106 Ag*110m Sb-124 Sb-125 Te*125m Te*127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 1. 40E+7 4.45E+7 3.16E+7 5.20E+7 1.21E+8 2.25E+6 7.95E+6 2.78E+7 1.18E+10 8.35E+8 2.11E+9 7.31E+9 4.17E+6 4.68E+9 2.87E+7 2.00E+7 1.37E+7 3.82E+7 2.87E+8 4.19E+7 2.78E+6 7.36E+6 4.68E+7 3.76E+6 1.10E+8 1.83E+7 3.62E+8 6.26E+7 1.33E+8 4.01E+8 3.10E+9 3.41E+9 4.73E+9 7.00E+8 2.22E+9 2.67E+9 3.18E+8 7.66E+7 9.92E+7 9.60E+6 7.22E+5 6.10E+6 1.58E+4 6.48E+6 4.24E+2 1. 65E+3 5. 22E+2 1.41E+5 7.80E+4 1.81E+3 3.75E+4 7.67E+2 7.57E+4 6.40E+3 7.23E+4 1.20E+6 3.59E+2 3.34E+8 4.30E+4 1.52E+5 7.75E+2 1.80E+6 4.73E+3 9.63E+7 9.11E+7 1.74E+8 2.56E+10 5.54E+7 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25Et8 1.79E+7 3.65E+7 3.99E+5 3.49E+4 3.00E+7 1.08E+7 8.39E+6 8.44E+7 2.99E+7 2.01E+7 1.11E+8 4.10E+7 3.57E+7 5.38E+8 7.53E+8 2.20E+11 9.81E+9 2.31E+10 4.45E+8 1.75E+9 1.34E+10 1.78E+10 4.85E+7 5.95E+4 1. 99E+4 1. 35E+4 6.58E+5 2.72E+5 2.92E+2 1.17E+2 1.81E+2 1.97E+2 3.42E+8 4.62E+8 1.30E+9 7.34E+9 3.21E+7 2.84E+8 8.54E+6 8.86E+7 4.02E+6 2.80E+9 2.10E+8 1.00E+7 4.15E+8* 1.75E+7 1. 49E+8 4. 04E+8 2.87E+8 1.07E+10 9. 53E+8 1. 50E+8 6.06E+9 2.35E+9 1.41E+8 1.18E+9 2.53E+8 6.20E+9 2.02E+4 4.00E+4 7.49E+7 3.13E+6 6.26E+3 3.62E+5 1.20E+5 1.53E+3 1.63E+5 6.77E+1 1.16E+2 53 1.66E+8 3.54E+4 9.61E+5 1.45E+1 7.11E+5 1.18E+1

*

Nuclide H-3 C-14 P-32 Cr -5 1 Mn-54 Fe-55 Fe-59 Co-57 co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m I -131 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) RCio), Grass-Cow-Milk Pathway Dose Factors -CHILD Cmrem/yr per uCi/m3) for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Bone Liver Thyroid Kidney Lung Gl-LLI T.Body 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1 .65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+S 3.29E+5 7.77E+10 3.64E+9 2.15E+9 3.00E+9 5. 66E+4 1. 55E+4 1. 03E+5 5. 41 E+6 1. 02E+S 2.09E+7 1.12E+8 S.93E+7 1.20E+8 1.95E+8 3.84E+6 1.21E+7 4.32E+7 2.96E+10 1.59E+9 4.13E+9 1.10E+10 6.62E+9 1.12E+11 9.14E+S 8.77E+9 3.84E+3 8.45E+2 3.18E+5 1.24E+5 4.29E+3 9.24E+4 2.09E+8 1.41E+8 1.09E+8 1.41E+8 8.70E+7 1.41E+6 7.38E+7 2.00E+7 2.40E+5 8.06E+4 2.07E+7 2.08E+8 5.60E+7 4.97E+7 2.72E+8 7.61E+7 8.78E+7 1.30E+9 1.31E+9 4.34E+11 2.26E+10 3.71E+10 1. OOE+9 2. 76E+9 3.22E+10 3.09E+10 1.17E+8 1.03E+5 2.19E+4 1.09E+4 1.62E+6 5.09E+5 7.23E+2 2.17E+2 4.45E+2 3.60E+2 5.87E+6 6.94E+9 1.21E+3 1.16E+5 1. 08E+4 1.25E+5 2.63E+8 5.93E+8 8.00E+8 2.15E+9 1.76E+7 3.35E+7 1.10E+7 5.65E+7 2.03E+8 3.14E+7 5.58E+6 1. 84E+7 9.71E+7 7.77E+6 7.08E+7 3.72E+7 2.39E+8 1.07E+8 1.93E+9 1.27E+8 1.01E+9 6.85E+9 S.64E+8 5.39E+9 2.56E+8 1.89E+8 1.51E+9 2.83E+10 2.63E+6 1.84E+5 2.44E+4 8.81E+5 7.52E+2 2.29E+8 8.84E+4 1.11E+5 1.65E+3 1.44E+6 1 .15E+4 1.68E+10 6.03E+7 6.79E+8 4.85E+7 2.08E+8 7.12E+7 1. 68E+8 3.32E+8 1.17E+8 1.13E+8 3.81E+7 1.82E+7 9.84E+6 2.47E+7 4.23E+7 7.46E+8 1 .15E+10 4.13E+9 2.00E+8 7.83E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 1 .01E+10 3.62E+9 1.93E+8 4.55E+9 3.34E+4 6.12E+4 5.94E+7 6.84E+6 4.78E+3 2.82E+5 1.17E+2 1. 98E+2 54 1.36E+7 1.62E+3 1.33E+8 8.66E+4 7.80E+5 3.59E+1 S.71E+5 2.79E+1

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Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) R ( i o ) , G r a s s -

C o w -M_ i l le P a t h w a y D o s e F a c t o r s -I N F A N T Cmrem/yr per uCi/m3) for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI T.Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 6.89E+5 2.38E+3 2.38E+3 6.89E+5 6.89E+5 2.17E+9 6.21E+9 4.71E+6 1.61E+5 C-14 3.23E+6 6.89E+S 6.89E+5 6.89E+5 P-32 1.60E+11 9.42E+9 Cr-51 1.05E+5 2.30E+4 2.05E+5 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni -63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m I -131 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 3.89E+7 1.35E+8 8.72E+7 2.25E+8 3.93E+8 8.95E+6 2.43E+7 8.81E+7 3.49E+10 2.16E+9 5.55E+9 1.90E+10 1.26E+10 1.22E+11 7.33E+4 2.22E+10 6.83E+3 1.66E+3 5.93E+5 2.44E+5 8.69E+3 1. 90E+5 8.63E+6 9.23E+9 1. 79E+3 1.75E+5 1.81E+4 2.25E+5 4.27E+7 1. 43E+7 1.11E+7 8.83E+6 2.33E+7 1 .16E+8 1.88E+8 1.55E+8 3.05E+7 1.46E+7 6.05E+7 6.06E+7 2.10E+8 2.08E+8 1.07E+8 1.21E+9 1.61E+10 8.78E+9 5.69E+8 1.10E+10 2.59E+8 3.61E+8 1.52E+9 3.10E+10 5.26E+6 1.95E+3 8.28E+5 1.18E+3 2.06E+8 1.41E+5 1.06E+5 1.44E+6 2.91E+3 2.38E+4 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 3.08E+6 5.56E+5 1.31E+8 6.46E+8 6.49E+7 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 1.51E+8 5.04E+7 5.07E+7 4.21E+8 1.40E+8 1.22E+8 5.59E+8 1.92E+8 2.15E+8 2.72E+9 3.21E+9 1.0SE+12 3.65E+10 6.80E+10 1.96E+9 5.77E+9 5.15E+10 6.02E+10 2.41E+8 2.41E+S 4.33E+4 2.64E+4 2.33E+6 9.52E+S 1. 49E+3 5. 59E+2 8.82E+2 9.06E+2 1.04E+9 1. 40E+9 3.75E+9 1.75E+10 2.30E+9 1.62E+10 7.18E+9 4.70E+8 6.55E+9 7.18E+7 2.04E+7 1. 70E+8 3.34E+8 1.15E+8 5.10E+7 8.62E+7 1.41E+9 1.85E+8 6.87E+9 8.76E+7 2.1SE+9 1 .88E+8 4.27E+9 S.73E+4 1.48E+S S.92E+7 1.24E+7 8.15E+3 1.37E+7 3.11E+3 3.85E+5 2.08E+2 3.49E+2 55 1. 33E+8 1. 30E+S 7.89E+S 7.41E+1 S.74E+S 5.SSE+1

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Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) R(io),

Pathway Dose Factors -ADULT Cmrem/yr per uCi/m3) for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI T.Body H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 1.40E+9 8.73E+7 1. 58E+8 5. 42E+7 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 3.11E+8 2. 09E+8 1. 45E+8 1.27E+8 2.99E+8 1.17E+7 3.09E+7 1.67E+8 1.04E+10 7.21E+8 3.17E+8 1.01E+9 9.96E+9 6.05E+11 5.13E+6 2.19E+8 1.19E+6 3.81E+5 1.42E+5 7.91E+4 4.80E+6 1.93E+8 1.06E+7 1.04E+8 1. 36E+8 9.66E+7 9.76E+6 1.96E+6 1. 52E+6 3.50E+7 3.49E+8 1.25E+8 2.55E+8 9.50E+7 2.52E+5 1. 39E+5 2.90E+7 8.92E+7 8.75E+7 8.09E+7 1.16E+8 3.79E+10 4.66E+9 1.11E+10 1.66E+8 6.36E+9 8.70E+9 1. 29E+8 1. 62E+5 1. 96E+5 1. 33E+5 3.29E+7 1.38E+7 6.34E+4 2.54E+4 3.34E+4 3.86E+4 9.27E+7 9.54E+8 5.94E+7 6.75E+8 5.97E+5 7.81E+4 1.83E+7 3.72E+8 1.92E+7 3.93E+8 1.42E+9 1.06E+9 1.98E+8 3.59E+9 8.06E+7 8.29E+7 3.37E+7 8.35E+7 9.96E+8 1.14E+8 2.97E+8 1.95E+7 8.08E+7 1. 05E+8 1.19E+9 6.26E+8 6.92E+7 3.14E+9 3.69E+8 1.SOE+8 3.49E+8 6.36E+8 4.56E+8 4.32E+7 1.02E+8 1.60E+9 2.86E+8 1.75E+10 1.48E+11 2.82E+9 1.37E+S 1.21E+9 2.58E+5 4.80E+8 -4.25E+4 5.61E+8 2.07E+6 1 .25E+10 2.44E+7 3.98E+9 2.95E+9 1.50E+9 3. 86E+8. 1.17E+9 1. 28E+9 3.0SE+7 1.94E+8 5.80E+6 4.11E+7 3.25E+7 1.29E+7 4.26E+7 4.03E+7 6.63E+7 9.07E+9 9.24E+7 1.27E+7 1.89E+7 1.19E+8 2.95E+9 9.81E+8 1.68E+8 5.70E+9 5.49E+4 9.25E+4 2.65E+8 8.43E+6 6.17E+4 8.16E+6 1.47E+4 2.25E+4 56 5.08E+8 1.51E+4 1.11E+.10 1.77E+6 2.78E+8 3.14E+3 1.85E+8 2.31E+3

*

Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) RCio), Vegetation Pathway Dose Factors -TEENAGER Cmrem/yr per uCi/m3) for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI T. Body H-3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 c r -5 1 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni -63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m I -131 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 1.61E+9 9.96E+7 4.52E+8 3.25E+8 2.31E+8 1.81E+8 4.22E+8 1. 79E+7 1.61E+10 4.24E+8 1.51E+10 7.51E+11 7.87E+6 4.38E+7 2.49E+8 1.13E+9 1.47E+9 2.73E+8 1. 74E+6 5. 49E+5 1.92E+5 1.06E+5 6.87E+6 3.09E+8 1.52E+7 1.55E+8 2.14E+8 1. 48E+8 1.44E+7 2.85E+6 2.34E+6 5.34E+7 1.35E+8 6.23E+7 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 3.51E+5 2.04E+5 4.14E+7 1.35E+8 9.27E+8 8.97E+7 9.41E+8 8.07E+5 1.03E+5 2.42E+7 5.97E+8 2.74E+7 1.46E+8 9.98E+7 5.38E+7 1.33E+8 9.98E+8 1.63E+8 3.34E+8 3.00E+7 1.35E+8 1. 88E+8 6.04E+8 1.01E+8 3.24E+9 1.81E+8 6.23E+8 5.60E+8 5.45E+8 6.86E+8 4.05E+7 1.28E+8 1.80E+9 4.33E+8 2.11E+10 1.85E+11 2.11E+5 1.27E+9 3.78E+5 4.55E+8 5.86E+4 5.74E+8 2.94E+6 1.48E+10 3.90E+7 4.04E+9 3.11E+9 1. 66E+9 4.37E+8 8.74E+6 6.03E+7 5.00E+7 1.98E+7 5.51E+8 3.67E+8 7.70E+7 1.96E+8 1.31E+8 2.24E+9 1.36E+8 1.18E+8 1.54E+9 1.08E+8 3.14E+10 1.85E+8 1.37E+9 1 .38E+9 2.13E+7 6.56E+7 5.81E+7 5.79E+7 7.09E+9 1.67E+10 4. 29E+7 1. 69E+8 1.01E+10 1.35E+10 1.38E+8 1 .69E+5 2. 82E+5 1. 88E+5 5.27E+7 2.18E+7 7.12E+4 2.84E+4 3.63E+4 3.94E+4 5.30E+9 2.02E+9 2.08E+8 7.74E+9 9.19E+7 1.45E+7 1.36E+7 1.13E+8 4.59E+9 1.78E+9 1.92E+8 4.69E+9 5.75E+4 1.14E+5 2.13E+8 8.91E+6 8.86E+4 5.38E+8 2.16E+4 1.30E+7 1.65E+4 2.32E+4 57 1.33E+10 2.83E+6 2.34E+8 3.55E+3 1.42E+8 2.36E+3

*

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 co-58. Co-60 Ni -63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-129m 1 -1 31 Cs-134 Cs-136 cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem OOCM Rev. 4 05/17/88 Table 2-5 (cont'd) R(io), Vegetatiqn Pathway Dose Factors -CHILD per uCi/m3) for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others Bone 3.50E+6 3.37E+9 Liver 4.01E+3 7.01E+5 1. 58E+8 6.61E+8 8.00E+8 4.24E+8 4.01E+8 6.49E+8 2.99E+7 6.47E+7 3.78E+8 3.95E+10 2.11E+9 8.12E+8 2.16E+9 3.59E+10 1.24E+12 1.87E+7 4.52E+8 3.90E+6 8.58E+5 4.10E+5 1.59E+5 1.55E+7 7.45E+8 3.22E+7 3.52E+8 4.99E+8 3.51E+8 2.17E+7 4.57E+6 3.85E+6 9.SOE+7 Thyroid Kidney 4.01E+3 4.01E+3 7.01E+5 7.01E+5 6.54E+4 1.79E+4 7.78E+5 4. 62E+5 9.84E+7 1.85E+8 1. 36E+9 1. 23E+6 1. 50E+5 3.89E+7 1.01E+9 4.05E+7 1. 32E+9 8.54E+8 1.43E+8 3.56E+8 3.16E+8 2.39E+8 2.75E+8 1.44E+8 4.76E+10 3.77E+9 2.51E+9 2.36E+8 8.14E+9 1.60E+10 2.63E+10 Lung 4.01E+3 7.01E+5 1.19E+5 GI-Lll 4.01E+3 7.01E+5 9.30E+7 6.25E+6 T.Body 4.01E+3 7.01E+5 1. 30E+8 1.18E+5 5.SSE+B 1.76E+8 2.40E+8 7.86E+7 1.31E+8 1.88E+8 6.76E+8 3.23E+8 2.45E+8 6.04E+7 3.77E+8 1.98E+8 2.10E+9 1.12E+9 1. 42E+8 1. 34E+9 3.80E+8 1.35E+9 2.91E+7 2.78E+8 1.39E+9 1.03E+9 1.67E+10 3.15E+11 2.49E+9 5.01E+5 8.95E+8 7.64E+5 2.95E+8 1.14E+5 3.99E+8 5.94E+6 1.16E+10 9.30E+7 2.58E+9 1.96E+8 2.20E+9 2.78E+8 1.19E+9 3.38E+8 1.74E+7 1. 23E+8 1.0SE+B 4.67E+7 2.92E+9 1.07E+9 1 .04E+9 1. 28E+7 1.42E+8 1. 57E+8 1.33E+8 8.18E+7 5.54E+9 8.06E+7 2.22E+8 2.39E+10 2.29E+10 2.77E+8 2.43E+5 1.23E+5 6.14E+4 1.18E+8 1.76E+7 7.79E+6 1.43E+8 7.46E+9 2.68E+9 1.43E+8. 3.38E+9 7.90E+4 1.45E+5 1.40E+8 1.62E+7 1. 27E+8 3. 98E+7 1. 48E+5 4. 46E+4 7.16E+4 5.80E+4 2.69E+4 2.21E+7 2.41E+4 3.18E+4 58 7.66E+7 9.12E+3 1.04E+10 6.78E+6 1.60E+8 7.37E+3 9.18E+7 4.49E+3

*

Salem ODCM Rev. 4 05/17/88 Table 2-5 (cont'd) R(io), Ground Plane Pathway Dose Factors (m2 ***mrem/yr per uCi/sec) Nuclide H-3 C-14 P-32 Cr -5 1 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Any Organ 4.68E+6 1.34E+9 2.75E+8 3.82E+8 2.16E+10 7.45E+8 8.98E+6 2.16E+4 1.08E+6 2.48E+8 1. 36E+8 1. 09E+8 4.21E+8 3.47E+9 1.55E+6 9 .17E+4 2.00E+7 1.72E+7 6.75E+9 1.49E+8 1.04E+10 2.05E+7 1. 36E+7 6.95E+7 59

*

Salem ODCM Rev. 4 05/17/88 APPENDIX A Evaluation of Default KPC Value for Liquid Effluents A-1

*

Appendix A Evaluation of Default MPC Value for Liquid Effluents Salem ODCM Rev. 4 05/17/88 In accordance with the requirements of Technical Specification (3.3.3.10) the r a d. i o a c t i v e l i q u i d e f f l u e n t mo n i t o r s s h a l l b e o p e r a b l e w i t h a l a r m s e t p o i n t s established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table. II,* Column 2. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding MPC values. In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established.

This default setpoint can be based on an evaluation of the radionuclide distribution of the liquid effluents from Salem and the effective MPC value for this distribution.*

The effective MPC value for a radionuclide distribution is calculated by the equation:

where: MP Ce c i MPCi [ Ci MPCe = ------------

CA. l ) L<> = an effective MPC value for a mixture of radionuclide CuCi/ml> = concentration of radionuclide i in the mixture = the 1 O c FR 2 O , -Append i x B , Tab l e I I , Co l um n 2 MP C v a l u e f o r radionuclide i (uCi/ml) Based on the above equation and the radionuclide distribution in the effluents for past years from Salem, an effective MPC value can be determine.

Results are A-2

*

Salem ODCM Rev. 4 05/17/88 presented in Table A-1 and A-2 for Unit 1 and Unit 2, respectively . Considering the average effective*

MPC value for the years 1981 through 1987, it is reasonable to select an MPCe value of 1E-05 uCi/ml as typical of liquid radwaste discharges.

Using this value 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 2) Will provide for a each batch release) Tables 1-1 and 1-2) . liquid radwaste discharge rate (as evaluated for that is compatible with plant operations (refer to A-3

*

Nuclide MPC* (UC i /ml) -----*---------Na-24 3E-05 Cr-51 2E-03 Mn-54 1E-04 Fe-59 SE-OS Co-58 9E*OS Co-60 3E-05 Zr-95 6E*OS Nb-95 1E-04 Nb-97 9E-04 Tc-99m 3E-03 Sr-89 3E*06 Sr-90 3E-07 Mo-99 4E-05 Ag*110m 3E*OS Sn-113 SE-OS Sb-124 2E*OS Sb-125 1E-04 1-131 3E-07 1-133 1E-06 I-135 4E-06 Cs-134 9E-06 Cs-137 2E-05 Ba-140 2E-05 La-140 2E-05 Total Ci _£.i_ MPCi MP Ce (uCi/ml) Table A-1 Calculation of Effective MPC Salem Unit 1 Salem ODCM Rev. 4 05/17/88 Activity Released (Ci) ------------------------------------------------------------*---------------------

1982 1983 1984 1985 1986 1987 ----------

...................

.. ................

1 .9E-03 5.3E-03 S.6E-03 6.2E*03 9.2E-04 6.9E-04 1.4E-01 6.2E-02 S.3E-02 3.6E-02 6.0E-02 N/D 2.1E-01 1.6E-01 1.9E-01 8.7E-02 1.9E-01 1.0E-01 8.6E-03 4.2E-02 S.SE-03 1.4E-03 2.4E-03 N/D 1. 7 1.8 1.6 6.6E-01 2.22 1. 54 9.1E-01 7.1E-01 1.2 6.SE-01 3.1E*01 4.2E-01 1.1E-02 8.0E-03 1.8E-03 3.2E-03 4.3E-03 8.6E-04 4.SE-02 2.2E-02 1.7E-02 1.3E-03 1.SE-02 2.4E-03 9.SE-03 3.6E-04 2.0E-02 7.2E-03 1.SE-03 9.SE-03 N/D N/D 1.6E*03 N/D N/D 1. 1 E-04 N/D 1.2E-03 4.2E-04 1. 7E-03 3.SE-07 1.6E-02 N/D N/D 2.2E*OS 1 . 7E

04 3.1E-08 7.7E-04 1.0E-03 1.6E-03 1.9E-03 1.0E-04 N/D 1.0E-04 4.7E-03 N/D N/D N/D N/D 2.SE-03 2.2E-04 3.SE-04 9.4E-04 N/D 3.SE-04 N/D 8.0E-03 1.4E-02 1.7E-02 S.7E-03 8.4E-02 2.4E-02 6.8E*03 4.4E-02 4.9E-03 N/D 3.6E-02 3.3E-02 6.SE-02 2.4E-02 4.SE-02 7.9E-02 1.2E*01 1.SE-01 3.3E-02 2.SE-02 1.9E-02 1.4E-03 1.9E-02 3.SE-04 1.6E-03 1.2E-03 N/D N/D 2.0E-03 4.0E-02 1.SE-02 5. 1 E-02 1.6E-01 3.4E-01 3.1E-03 5.9E-02 3.0E-02 S.SE-02 2.1E-01 3.6E-01 3.0E-01 N/D 1.3E-02 2.1E-03 N/D N/D N/D 7.SE-03 1.3E-02 1.6E-02 1.1E-04 3.SE-04 N/D 3.24 3.00 3.32 1.93 3.75 3.26 2.83E+OS 1.66E+OS 2.46E+05 3.42E+05 4.99E+OS 7.31E+05 1.14E-05 1.SOE-05 1.3SE-05 S.63E-06 7.51E-06 4.46E-06

MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2. ** N/D -not detected A-4

*

Table A-2 Calculation of Effective MPC Salem Unit 2 Salem ODCM Rev. 4 05/17/88 Activity Released (Ci) -----------------------------------------------------------------------------------

Nuclide MPC* 1982 1983 1984 1985 1986 CuCi/ml> ------------------------------------------------------------Na-24 3E-05 1.2E-03 9.2E-03 4.4E-03 3.5E-03 Cr-51 2E-03 1.1E-01 4.6E-02 3.6E-02 3.5E-02 Mn-54 1E-04 2.0E-01 1.4E-01 1.6E-01 1.1E-01 Fe-59 5E-05 5.6E-03 3.1E-02 7.6E-03 1. 1 E-03 Co-58 9E-05 1. 7 1. 7 1.3 8.4E-01 Co-60 3E-05 8.6E-01 5.7E-01 9.8E-01 6.3E-01 Zr-95 6E-05 9.7E-03 5.2E-03 1.2E-03 4.6E-03 Nb-95 1E-04 2.3E-02 1.6E-02 1.4E-02 1.4E-02 Nb-97 9E-04 1.1E-02 1.1E-02 2.1E-02 5.7E-03 Tc-99m 3E-03 N/D N/D 1.4E-03 N/D Sr-89 3E-06 N/D 3.2E-04 3.2E-04 1.5E-03 Sr-90 3E-07 N/D N/D 4.1E-05 1.0E-04 Mo-99 4E-05 1. 7E-04 3.0E-03 1.4E-03 N/D Ag-110m 3E-05 3.9E-03 N/D N/D N/D Sn-113 8E-05 1.6E-04 5.9E-04 1.2E-03 N/D Sb-124 2E-05 1.0E-02 2.0E-02 3.0E-02 1.2E-03 Sb-125 1.0E-02 9.6E-02 3.6E-03 N/D 1-131 3E-07 1.3E-01 3.6E-02 4.2E-02 8.4E-02 1-133 1E-06 6.0E-03 5.4E-02 2.6E-02 1.2E-02 1-135 4E-06 N/D 1.6E-03 4.4E-04 N/D Cs-134 9E-06 5.1E-02 2.0E-02 2.6E-02 1. 8E-01 Cs-137 '2E-05 7.6E-02 3.6E-02 4.8E-02 2.3E-01 Ba-140 2E-05 N/D 9.8E-03 6.6E-03 N/D La-140 2E-05 6.7E-03 8.1E-02 3.0E-02 N/D Total Ci 3.21 2.89 2.74 2.15 Ji_ 5.00E+OS 2.26E+05 2.24E+05 3.56E+05 MPCi MPCe (uCi/ml) 6.42E-06 1.28E-05 1.22E-05 6.04E-06

MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2. ** N/D -not detected A-5 3.6E-03 9.5E-02 2.2E-01 4.0E-03 3.32 3.8E-01 1.1E-02 2.5E-02 2.?E-03 N/D 4.1E-07 3.2E-08 N/D N/D 1.1E-03 1.2E-01 5.4E-02 1.2E-01 2.6E-03 N/D 3.6E-01 3.7E-01 N/D 6.9E-04 5.09 5.20E+05 9.79E-06 1987 .........................

7.3E-05 3.0E-03 1.2E-01 N/D 1. i 4.2E-01 8.4E-04 6.6E-03 N/D 5.?E-04 3.0E-03 2.9E-04 4.4E-04 N/D N/D 4.6E-02 5.9E-02 2.2E-01 1.SE-02 N/D 3.5E-01 3.3E-01 N/D N/D 3.85 8.59E+05 4.49E-06

*

Salem ODCM Rev. 4 05/17/88 APPENDIX B Technical Basis for Effective Dose Factors Liquid Radioactive Effluent B-1

*

Salem ODCM Rev. 4 05/17/88 APPENDIX B Technical Basis for Effective Dose Factors -Liquid Effluent Releases The radioactive liquid effluents for the years 1987, 1986, 1985, 1984, 1983, and 1982 were evaluated to determine the dose contribution of the radionuclide distribution.

This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2.

For the radionuclide distribution of effluents from Salem, the controlling organ is the GI-LLI. The calculated GI-LLI dose is predominately a function of the Fe-59, C0-58, C0-60 and releases.

The radionuclides, Co-58 and C0-60 contribute the large majority of the calculated total body dose. The results of the evaluation for 1987, 1986, and 1985 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 radionuclide 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 E+06 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 (7.27 E+04 mrem/hr per uCi/ml, total body) is the highest among the identified dominant nuclides.

B-2

*

Salem ODCM Rev. 4 05/17/88 For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may used: Total Body 1.67E-02 *VOL Dtb

A Fe-59, TB

L Ci ( B. 1) cw where: . Dtb = dose to the total body (mrem) A Fe-59, TB = 7.27E+04, total body ingestion dose conversion factor for Fe-59 (mrem/hr per uCi/ml) VOL Ci cw 1.67E-02 = volume of liquid effluent released (gal) = total concentration of all radionuclides (uCi/ml) average circulating water discharge rate during release period (gal/min)

conversion factor (hr/min) Substituting the value for the Fe-59 total body dose conversion factor, the equation simplified to: Maximum Organ where: Dmax A Nb-95,GI-LLI 1.21E+03 *VOL Dtb

L Ci cw 1.67E-02 *VOL* A Nb-95,GI-LLI Dmax = ---------------------------

l:_ Ci . cw = maximum organ dose (mrem) (B.2) (8.3). = 1.51E+06, Gi-LLI ingestion dose conversion factor for Nb-95 Cmrem/hr per uCi/ml) Substituting the value for A Nb-95,GI-LLI the equation simplifies to: 2.52E+04

VOL Dmax = --------------* [ Ci cw B-3 (B.4)

*

Salem ODCM Rev. 4 05/17/88 Tritium is not included in the limited analysis dose for 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 the fish and invertebrate ingestion pathways.

This amounts to 0.08% of the design objective dose of 3 mrem/yr. Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation

B-4

*

Radio-Release ru:lide (Ci) Fe-59 Co-58 Co-60 As-mm ltl-54 lb-9'.i Cs-137 Cs-134 Cr-51 Total N/D 1.54E+OO 4.22E-01 2.81E-Cl3 1.(1jE-Q1 2.43E-Cl3 3.01E-01 3.11E-01 N/D 2.69800

less thlrl a.a1 N/D = rot detected ru:l ide Fe-59 Co-58 Co-60 As-11Cm ltl-54 lb-9'.i Cs-137 Cs-134 Cr-51 Total Release (Ci) N/D 1.71 4.19E-01 NJD 1.20E-01 6.63E-03 3.31E-01 3.49E-a1 3.03E-Cl3 2.94E+OO

less then 0.01 N/D = rot detected TB GI-LLI Liver Dose Dose Dose Frac. Frac. Frac.

0.20 0.16

a.a1

0.23 0.40

1S87 TB Dose Frac.

0.32 0.10

0.02

0.20 0.41 *

0.47 a.34 a.04 a.06 a.09 * *

GI-UI Dose

O.IE a.06

0.07

a.32 0.46

Liver Dose Frac. Frac.

0.44 a.06

a.cs a.41 * * *

a.13 a.04

a.10

0.29 0."6

Salem ODCM Rev. 4 05/17/88 Table B-1 Ad.Jl t Dose c:art:ri b.Jti ens Fish in::t IrMrtebrate Patlwlys Uiit 1 Release (Ci) TB GI-UI Liver Dose Dose Dose Frac. Frac. Frac. 2.4a:-Cl3 2.22 3.1CE-a1 N/D 1.!D:-02 3.6CE-01 3.4a:-a1 6.CXE-02 3.SCE+OO 0.01 0.25 0.10

0.02

0.14 0.38

Table B-2 0.02 0.42 0.07

a.06 0.42 0.01 *

Ad.Jl t Dose c:art:rituti a"S Fish ird IrMrtebrate Patlwlys I.hit 2 Release (Ci) 1986 TB GI-UI Dose Dose O.Cl3 0.10 0.04

o.1a

0.32 0.41

Liver Dose Frac. Frac.

Frac. 4.CXE-Cl3 3.32 3.!D:-a1 N/D 2.20E-a1 2.SCE-02 3.71'.E-01 N/D 9.SCE-02 4.77E+OO a.02 a.32 o.1a

0.02

0.20 *

B-5 a.Cl3 0.44 0.06

a.cs 0.41 * *

a.cs a.13 0.04

0.10

0.29 *

Release (Ci) 1.4a:-Cl3 6.6CE-a1 6.SCE-a1 N/D 8.71E-C2 1.3CE-Cl3 2.1CE-01 1.6CE-01 3.6CE-C2 1.!D:+OO Release (Ci) 1.1CE-Cl3 8.4a:-01 6.3CE-01 N/D 1.1CE-01 1.4a:-C2 2.3CE-01 N/D 3.SCE-C2 2.04E+<Xl 1se; TB GI-LLI Liller Dose Dose Dose Frac. Frac. Frac. 0.01 0.12 0.34

a.C2

0.22 0.29

1<;85 TB Dose 0.04 0.36 0.42

a.IE a.09 * *

GI-LL! Dose 0.04 0.05 0. 15

a.ca

0.33 0.35

Liver Dose Frac. Frac. Frac. a.01 0.14 a.30

a.C2

a.23 *

a.C2 a.23 a.21

0.05 0.48 * *

a.C2 0.06 a. 13

0.09

a.33 * *

*

Salem ODCM Rev. 4 05/17/88 APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent C-1

*

Overview Salem ODCM Rev. 4 05/17/88 APPENDIX C Technical Bases for Dose ractors Gaseous Radioactive Effluents The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific.

These effective factors, which can be based on typical radionuclide distributions of releases, can b*e applied to the total radioactivity released to approximate the dose in the environment (i.e., instead of having to perform individual radionuclide dose analyses only a single multiplication (Keff' Meff or Neff) 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:

wh e.r e: Keff Ki f i where: = = Keff = the effective total from all noble gases the total body dose (Ki

fi) body dose factor due to gamma released factor due to gamma emissions noble gas radionuclide i released = the fractional abundance of noble gas radionuclide to the total noble gas activity CL+ 1.1 M)eff = ((Li + 1.1 Mi)

f i ) ( c . 1 ) emissions from each relative ( c. 2) CL+ 1.1 M)eff = the effecti*ve skin dose factor due to beta and gamma from all noble gases released (Li. + 1. 1 Mi) = the skin dose factor due to beta gamma emissions from each noble gas radionuclide i released C-2

*

where: Meff = Mi = where: Neff = Ni = Salem ODCM Rev. 4 05/17/88 Meff = L (Mi

f i ) ( c. 3) the effective air dose factor due to gamma emissions from all noble gases released the air dose factor due to gamma emissions from each noble gas radionuclide i released Neff = l:_ (Ni

fi) ( c. 4) the effective air dose factor due to beta emissions from *all noble gases released the air dose factor due to beta emissions from each noble gas radionuclide i released Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from 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 1400 Ci for 1982, 900 Ci for 1983, 2,000 Ci for 1984, 2,800 Ci for 1985, and 2,700 Ci for 1986. Therefore, in order to provide a reasonable basis. for the derivation of the effective noble gas dose factors, the primary coolant source term from N237* 1. 9 7 6 / A N S 1 8

1 , 11 S o u r c e T e r m S p e c i f i c a t i o n s , 11 h a s b e e n u s e d a s r e p r e s e n t i n g a typical distribution.

The effective dose factors as de.rived 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-3

*

Salem ODCM Rev. 4 05/17/88 For evaluating compliance with the dose Limits of Technical Specification 3.11.2.2, the following simplified equations may be used: 3.17E*08 D = --------* X/Q

Me ff

t. Qi ( c. s) a.so and 3.17E*08 D = --------* .X/Q

Neff * ( c. 6) a.so where: D = air dose due to gamma emissions for the cumulative release of a l l noble gases (mrad) D = air dose due to beta emissions for the cumulative release of a l l noble gases (mrad) X / Q = a t m o s p h e r i c d i s p e r s i o n t o t h e

c o n t r o l l i n g s i t e b o u n d

a r y Me ff Neff Qi 3.17E-08 a.so = = -= = (sec/m3) S.3E+02, effective gamma-air dose factor (mrad/yr per uCi/m3) 1.1E+03, effective beta-air dose factor (mrad/yr per uCi/m3) cumulative release for all noble gas radionuclides (uCi) conversion factor (yr/sec) conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to: D = 3.SE*OS

X/Q

L Qi ( c. 7) and D = 7.0E*OS

X/Q

L Qi ( c. 8) 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 ma.lfunction where a detailed dose assessment may be unavailable

C-4

*

Radionuclide*

IC r -85 Kr -88 Xe-133m Xe-133 Xe-135 Total Noble Gases -Air Radionuclide

Kr-85 Kr -88 Xe-133m Xe-133 Xe-135 Total f.

1 0. 0 1 0. 01 0. 01 0.95 0.02 f.

1 Table C-1 Effective Dose Factors Noble Gases -Total Body and Skin Total Body Effective Dose Factor I( eff 3 Cmrem/yr per uCi/m ) 1.5E+02 2.5E+OO 3.0E+02 3.6E+01 4".8E+02 Gamma Air Effective Dose Factor "eff Cmrad/yr per uCi/m 3) ------0. 01 0. 01 0. 01 0.95 0.02 1.5E+02* 3.3E+OO 3.4E+02 3.8E+01 5.3E+02 Salem ODCM Rev. 4 05/17/88 Skin Effective Dose Factor CL+ 1.1 M)eff 3 Cmrem/yr per uCi/m ) 1.4E+01 1 .9E+02 1.4E+01 6.6E+02 7.9E+01 9.6E+02 Beta Air Effective Dose Factor Neff Cmrad/yr per uCi/m 3) 2.0E+01 2.9E+01 1.5E+01 1. OE+03 4.9E+01 1.1E+03

Based on Noble gas distribution from ANSI N237-1976/ANSI-18.1, "Source Term Specifications." C-5

*

Salem ODCM Rev. 4 05/17/88 APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent D-1

*

APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent Releases Salem ODCM Rev. 4 05/17/88 The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide.

This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3 For the infant age group, the controlling pathway is the grass-milk-cow (g/m/c) pathway. An infant receives a greater radiation dose from the g/m/c pathway than any other pathway. Of this g/m/c pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide 1-131. 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 radionuclide and limit the calculation process to the use of the dose conve_rsion factor for _the organ and radionuclide.

Multiplication of the total release (i.e. cumulative a c t i v i t y f o r a l l r

a d i 6 n u c l i d e s )

by t h i s d o s e c o n v e r s i o n f a c t o r p r o v i d e s f o r a dose calculation method that is simplified while also being conservative.

For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/m/c, thyroid, I-131 pathway dose factor (1.675E12 m2 mrem/yr per uCi/sec).

By t h i s a pp r *o a c h , t h e ma x i mum d o s e commitment will be overestimated since 1-131 has the highest pathway dose factor of all radionuclides evaluated

D-2

*

Salem ODCM Rev. 4 05/17/88 For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used: where: Dmax w . Qi Dmax = 3.17E-8

W

Rl-131

Qi = maximum organ dose (mrem) = atmospheric dispersion parameters to the 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/m3) DI Q. = at mos per i c de po s i t i on for veg et at i on , mi l k n ad g round p l an e exposure pathways (m-2) = cumulative release over the period of interest for and particulates 3.17E-8 = conversion factor (yr/sec> Rl-131 = = I -131 dose parameter for the for the identified controlling pathway 1.675E12 (m2 mrem/yr per uCi/sec), infant thyroid dose parameter with the cow-milk-grass controlling The ground plane exposure and inhalation pathways need not be considered when the a b o v e s i m p l i f i e d c a l c u l a t i o n m e t h o d i s u s e d b e c a u s e f o t h e o v e r a l l n e g l i g i b l e t.:* contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radioiodines (e.g., Co-60 and Cs-137>, the ground exposure pat_hway 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 radionuclide 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). T h e l o c a t i o n o f e x p o s u r e pa t h w a y s a n d t h e m a x i m u m o r g a n s o e c a l c u l a t i o n m a y .b e 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

D-3

Target Organs Total Body Liver Thyroid Kidney Lung Gl-LLI *

Salem ODCM Rev. 4 05/17/88 Table D-1 Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Grass-Cow-Milk 0.02 0.23 0.59 0.02 0. 0 1 0.02 Fraction of Dose Contribution by Pathway Pathway f_ Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation

D-4 Ground Plane 0. 1 5 0. 1 4 0. 1 5 0. 1 5 0.02 0. 1 5

*

Salem ODCM Rev. 4 05/17/88 Appendix E Radiological Environmental Monitoring Program Sample Type, Location and Analysis E-5

*

Salem ODCM Rev. 4 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -SAMPLE TYPE, LOCATION AND ANALYSIS E-1 5/17/!::!8

*

Salem ODCM 4 APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled. AIO = Air Iodine IDM = Immersion Dose (TLD) APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR Potable Water ( f<.aw) ESf:o' = Edible Fish PWT = Potable Water (Treated)

>/17 /88. ESS = Sediment RWA = Rain Water (Precipitation) f:o'PB = Beef SWA = Surf ace Water FPL = Green Leafy Vegetables VGT = Fodder Crops (Various)

FPV = Vegetable (Various)

WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the 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 F = 5-10 miles off-site B = 1-2 miles off-site G = 10.-20 mile*s off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles oft-site The last number is the station numerical designation within eah sector and zone; e.g., 1,2,3, *** For example, the designation SA-WWA-5Dl 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 radial distance of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 that this is sampling station il in that particular sector

E-2

*

Salem ODCM Rev. 4 5/17/88 LOCATIONS All sampling locations and specific information about the individual locations are given in Table E. Maps E-1 and E-2 show the locations of sampling stations with respect to the site. TABLE E-1 STATION CODE STATION LOCATION SAMPLl:; TYPEt:i 282 0.4 mi. NNE of vent IDM 383 700 ft. NNE of vent; fresh water holding WWA tank 5Sl 1. 0 mi. E of vent; site access road AIO ,APT, IDM 6S2 0.2 mi. ESE of vent; observation building IDM 781 0.12 mi. SE of vent; station personnel gate IUM lUSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. W of vent; outfall area ECH,ESf ,ESS, SWA 15A1 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12Cl 2.5 mi. WSW of vent; west bank of Delaware ECH,ESf ,ESS, River SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 5Dl 3.5 mi. E of vent; local farm AIO,APT,IDM, WWA lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur IDM llDl 3.5 mi. SW of vent GAM 1401 3.4 mi. WNW of vent; Bay View, Delaware IDM 2E1 4.4 mi. NNE of vent; local farm IDM E-3

*

STATION CODE 3El 7El 9El 11E2 12El 13El 13E3 16El lFl Salem ODCM 4 5/17/Sti TABLE E-1. (Cont'd) STATION .LOCATION 4.1 mi. NE of vent; local farm 5.7 mi. NE of vent; local farm 4.5 mi. SE of vent; l mi. W of Man Horse Creek 4.2 mi. S of vent 5.0 mi. SW of vent 4.4 mi. WSW of vent; Thomas Landing 4.2 mi. W of vent; Diehl House Lab 4.9 mi. W of vent; local farm 4.1 mi. NNW of vent; Port Penn 5.8 mi. N of vent; Fort Elfsborg SAMPLE TYPES fPB,fflV,GAM, IDM,VGT,WWA r'PV ESF,ESS,SWA IDM IDM IDM IDM VGT AIO,APT,IDM AIO,APT,IDM 1F2 7.1 mi. N of vent; midpoint of Delaware SWA 1F3 2F2 2F3 2F4 2r'S 2F6 2F7 3F2 3F3 5Fl 5.9 mi. N of vent; local farm 8.7 mi. NNE of vent; Salem Substation 8.0 mi. NNE of vent; Salem Water Company 6.3 mi. NNE of vent; local farm 7.4 mi. NNE of vent; Salem High School 7.3 mi. NNE of vent; Southern Training Center 5.7 mi. NNE of vent; local farm 5.1 mi. NE of vent; Hancocks Bridge Municipal Building 8.6 mi. NE of vent; Quinton Township School 6.5 mi. E of vent E-4 FPL,FPV AIO,APT,IDM, R.WA PWR, PWT FPV IDM IDM IDM IDM FPV, IDM

*

STATION CUDE 5F2 6Fl 7F2 10F2 llFl 11F3 12Fl 13F2 13r'3 13F4 14Fl 14F2 l4F3 15F3 l6Fl 16F2 lGl lG3 2Gl 3Gl lOGl Salem ODCM Rev. 4 5/ l "7 /88 TABLE E-1 (Cont'd) STATION LOCATION SAMPLE TYPES 7.0 mi. E of vent; local farm VGT 6.4 mi. ESE of vent; Stow Neck Road IDM 9.1 mi. SE of vent; Bayside, New Jersey IDM 5.8 mi. SSW of vent IDM 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT 9.4 mi. WSW of vent; Townsend Elementary IDM School 6.5 mi. W of vent; Odessa, Delaware 9.3 mi. w of vent; Redding Middle School, Middletown, Delaware 9. 8 mi. W of vent; Middletown, Del*aware 5.5 mi. WNW of vent; local farm 6.6 mi. WNW of vent; Boyds Corner 5.4 mi. WNW of vent; local farm 5.4 mi. NW of vent 6.9 mi. NNW of vent; C&D Canal 8.1 mi. NNW of vent; Delaware City Public School 10.3 mi. of N of vent; local farm 19 mi. N of vent; Wilmington, Delaware 12 mi. NNE of vent; Mannington Township, NJ 17 mi. NE of vent; local farm 12 mi. SSW of vent; Smyrna, Delaware E-5 IDM IDM IDM MLK,VGT IDM FPV IlJM IDM r'PV IDM FPV IDM,MLK,VGT IDM

*

STATION CODE 16Gl Salem ODCM Kev. 4 5/17/88 TABLE E-1 (Cont'd) STATION LOCATION 15 mi. NNW of vent; Greater Wilmington Airport SAMPLE TYPES IDM 3Hl 32 mi. NE of vent; National Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM Laboratory 3H5 25 mi. NE of vent; local farm FPL,FPV E-6

Sample Air Particulate Air Iodine

Crab and Fish Sediment Direct Milk

Salem ODCM Rev. 4 5/17/88 SAMPLE COLLECTION AND ANALYSIS Collection Method Continuous low volume air sampler. Sample collected every week along with the filter change. A TEDA impregnated charcoal cartridge is connected to air particulated air sampler and is collected weekly at filter change. Two batch samples are sealed in a plastic bag or jar and frozen semi-annually or when in season. A sediment sample is taken semi-annually.

2 TLD's will be collected from each location quarterly.

Sample of fresh milk is collected for each farm semi-monthly when cows are in. pasture, monthly at other times

E-7 Analysis Gross Beta analysis on each weekly sample. Gamma spectrometry shall be performed it gross beta exceeds 10 times the yearly. mean of the control station value. As well one sample is ana*lyzed

>24 hrs after sampling to allow for radon and thoron daughter decay. Gamma

isotopic analysis on quarterly composites.

Iodine 131 analysis are performed on each weekly sample. Gamma isotopic analysis of edible portion on collection Gamma isotopic analysis semi-annually.

Gamma dose quarterly Gamma isotopic analysis and 1-131 analysis on each sample on collection.

*

Salem ODCM Rev. 4 5/17/88 SAMPLE COLLECTION AND ANALYSIS (Cont'd) 8ample Water (Rain,. Potable, Surface) Collection Method Sample to be collected monthly providing winter icing conditions allow. E..:.8. Analysis Gamma isotopic monthly on quarterly surface sample, monthly on ground water sample *

11F3 ' LOCATIONS

' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' Rev. 9 5/17/88

i ./ 10 PROl'ERTY OP ITATE Of NEW .ERSl'I g o I I e 0 O N .. .._ ......... FEET

0 z en H t-3 t:r:I en 'Tl H 'tl G'l t:-< c:: H :u z l:t1 G'l t:r:I t:-< I 0 I\.) () :r:-t-3 H 0 z en

ML18093B053

Text

1.1 Radiation

1.2.1 Liquid

1.4.2 Simplified

1.5 Secondary

2.2.1 Containment

2.7 Effluent

4.2 lnterlaboratory

1.1 Radiation

0.5 allocated

3.2.1 Effluent

conversion factor (hr/min) Substituting the value for the Fe-59 total body dose conversion factor, the equation simplified to: Maximum Organ where: Dmax A Nb-95,GI-LLI 1.21E+03 *VOL Dtb

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