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Rev 4 to Offsite Dose Calculation Manual.
	ML18093B053
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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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Introduction SALEM NU~LEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents 1*0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls . ; *

2 1.2 Liquid Effluent Monitor Setpoint Determination 3 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown and Service Water) 4 1.2.2 Conservative Default Values .* s 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 6 1.4 Liquid Effluent Dose Calculations - 10 CFR SO . . . 7 1.*4.1 Member of the Public Dose - Liquid Effluents 7 1.4.2 Simplified Liquid Effluent Dose Calculation 8 1.5 Secondary Side Radioactive Liquid Effluents -

Dose Calculations During Primary to Secondary Leakage 10 1.6 Liquid Effluent Dose Projection * * * **. 12 2.0 Gaseous Effluents 2.1 Radi.ation Monitoring Instrumentation and Controls 13 2.2 Gaseous Effluent Monitor Setpoint Determination 15 2.2.1 Containment and Plant Monitor 1s

2.3 2.4 2.2.2 2.3.1 2.3.2 Conservative Default Values Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 Site Boundary Dose Rate - Noble Gases Site Boundary Dose Rate - Radioiodine and Particulates Noble Gas Effluent Dose Calculations - 10 CFR SO 16 18 18 19 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 * * * * * * *

24 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations ********** 2S 2.7 Ga~eous Effluent Dose Projection 28 3.0 Special Dose Analyses 3.1 Doses 'Due To Activities Inside .the SITE BOUNDARY 29 3.2 Doses to MEMBERS OF THE PUBLIC . 40 CFR 190 30 3.2.1 Effluent Dose Calculations * *

30 3.2.2 Direct Exposure Determination 31 4.0 Radiological Environmental Monitoring Program 32 4.1 Sampling Program * * * * * * * * * * * *

32 4.2 lnterlaboratory Comparison Program

33

Salem ODCM Rev. 4 05/17/88

Table of Contents - Continued Tables 1- 1 Parameters for Liquid Alarm Setpoint Determination - Unit 37 1-2 Parameters for Liquid Alarm Setpoint Determination - Unit 2 38 1-3 Site Related Ingestion Dose Commitment Factors, Aio 39 1-4 Bioaccumulation Factors CBFi)

41 2-1 Dose Factors for Noble Gases 44 2-2 Parameters for Gaseous Alarm Setpoint Determinations - Unit 1 45 2-3 Parameters for Gaseous Alarm Setpoint Determinations - Unit 2 46 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

49 2- 5 P a t h wa y Do s e P a r a me t e,_r s - At mo s p h e r i c Re l e a s e s so A-1 Calculation of Effective MPC - Unit 1 A-4 A-2 Calculation of Effective MPC - Unit 2 .. A-5 B-1 Adult Dose Contributions Fish and Drinking Water Pathway~

Unit 1 B- 5 B-2 Adult Dose Contributions Fish and Drinking Water Pathways Unit 2 B-5 C-5 Effective Dose Factors c-s Appendices Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents

A- 1 Appendix B - Technical Basis for Effective Dose Factors -

Li~uid Radioactive Effluents

Appendix c - Technical Bases for Effective Dose Factors -

Gaseous Radioactive Effluents Appendix D - Radiological Environmental Monitoring Program -

Sample Type, Location and Analysis B- 1 c- 1 D- 1

.

Salem OOCM Rev. 4 05/17/88

SALEM NUCLEAR GENERATING STATION OFFSITE .DOSE CALCULATION MANUAL Introduction The Salem Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in: 1) the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and 2) the calculation of radioactive liquid and gaseous concentrations, dose rates and 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 f~r

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 ~s is deemed necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.

NOTE: As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Salem Technical Specifications *

1

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.

1-R19 A,B,C,and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines. 2-R19 A,B,C and D provide this function for Unit 2.

2) Alarm 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 *

2

Salem ODCM Rev. 4 05/17/88 1.2 Liquid Effluent Monitor Setpoint Determination

Per the requirements release of Technical concentration Limits Specification 3.3.3.8, of Specification 3.11.1.1 alarm setpoints be established for the Liquid effluent monitoring instrumentation to ensure that the are met (i.e.,

shall the concentration of radioactive material released in Liquid effluents to UNRESTRICTED AREAS shall be Limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides and 2.0E*04 uCi/ml for dissolved or entrained noble gases). The. following equation* must be satisfied to meet the liquid effluent restrictions:

C ( F+f) ( 1. 1) f where:

C = the effluent concentration limit of Technical Specification

c =

C3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA f = the flow rate at the radiation monitor location, in volume per unit time, but in the same units as F, below F = the dilution water flow rate as measured prior to the release point, in volume per unit time

[Note that if no dilution is provided, c~ C. Also, note that when CF) is large compared to Cf), then CF + f) = F.]

Adapted from NUREG-0133

3

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 at the equations:

Salem Nuclear Generating Station are liquid effluent monitors determined by the following MPCe

SEN

CW SP ~ --------------- + bkg ( 1. 2)

RR with:

L Ci MPCe = ------------ (1 3)

I ci MPCi where:

SP = afarm setpoint corresponding to the maximum allowable release rate (cp MPCe = an effective MPC value for the mixture of radionuclides in the effluent stream CuCi/ml) ci = 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.

MP Ci = the MPC value corresponding to radionuclide from 10 CFR 20, Appendix B, Table .II, Column 2 (uCi/ml)

SEN = 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 interconnections Water System between the discharge.

Service Water This 4

Systems routing (see i s Figures possible and vi a 2).

1

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 non-conservative for the R19 Steam Generator blo~down 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

Salem ODCM Rev. 4 05/17/88

~.3 Liquid Effluent Concentration Limits - 10 CFR 20 Technical Specification 3.11.1 .1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other t~an 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 perf~rmed using the following equation:

ci RR

( 1. 4)

"pc i cw + RR

where:

ci MPCi

=

a c tu a L con cent rat i on of r a d'i on u c L i de undiluted Liquid effluent (uC(/mL) the MPC value corresponding to radionuclide Appendix B, Table II, Column 2 (uCi/mL>

2E-04 uCi/mL for dissolved or entrained noble gas~s as measured i n th e from 10 CFR 20,

=

RR = the actual liquid effluent release rate (gal/min) cw = the actual circulating water flow rate (dilution water flow) at the time of the release (gal/min)

6

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 G~nerating 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:

O.o =

1.67E*02

VOL

cw

r: (Ci

Aio) c 1. 5)

Do = dose or dose commitment to organ o, including total body Cmrem)

Aio = site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i Cmrem/hr per uCi/ml) ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL CuCi/ml>

VOL = volume of liquid effluent released (gal)

CW = a v e r a g e c i r c u l a t i n g wa 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

Salem ODCM Rev. 4 05/17/88

where:

Aio =

Aio = 1.14E+OS CCUI

Bli) + (UF

BFi)] DFi composite dose parameter for the total body or critical organ o

( 1. 6) of an adult for radionuclide i, for the fish and invertebrate ingestion pathways Cmrem/hr per uCi/ml) 1.14E+OS = conversion factor CpCi/uCi

ml/kg : hr/yr)

UI = adult invertebrate consumption CS kg/yr)

BI i bioaccumulation factor for radionuclide in invertebrates from Table 1-4 CpCi/kg : pCi/l)

UF adult fish consumption C21 kg/yr)

BFi = bioaccumulation factor for radionuclide in fish from Table 1-4 CpCi/kg per pCi/1)

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 added to the dose analysis at radiochemical analysis (e.g.,

a frequency consistent with Sr-89 and Sr-90) the will required minimum be 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

L ( 1

7)

Dtb = ************** Ci cw 8

Salem ODCM Rev. 4 05/17/88

Maximum Organ 2.52E+04

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

. c IJ

L Ci ( 1. 8) where:

ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (UCi/ml)

VOL = volume of liquid effluent released (gal) c IJ = average circulating water discharge rate during release period (gal/min)

Dtb = conservatively evaluated total body dose Cmrem)

Dmax = 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 leaks),

periods of primary to secondary leakage *(i.e.,

radioactive material will be transmitted from the primary system to the steam generator tube secondary system. The potential e~ists for the release of radioactive material t o t he o f f

s i t e e n v i r o n me n t <De l a wa r e Ri 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 10 is released directly to

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 *

11

Salem ODCM Rev. 4 05/17/88 1.6 Liquid Effluent Dose Projections

Technical processing Specific~tion system be used 3.11.1.3 to requires reduce the that the radioactive liquid liquid waste prior to release when the quarterly projected doses exceed:

material radioactive levels in waste t,he 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:

Dtbp = Dtb (91 : d) ( 1

9)

Dmaxp =

Dmax (91 d) (1.10) where:

Dtbp = the total body dose projection for current calendar quarter (mrem)

Dtb = 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) 0 maxp = the maximum organ dose projection for current calendar quarter

<mrem) 0 max = the maximum organ dose to date for current calendar quarter as determined by equation (1.5) or (1.8) (mrem) d = the number of days to date for current calendar quarter 91 = the number of days in a calendar quarter

12

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

2. 1 The Radiation Monitoring gaseous controlling effluent and monitoring Instru~entation monitoring normal and Controls instrumentation radioactive and material controls releases at in Salem for 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 h~ldup 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 a~cordance 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 and 2-2 for Units 1 and 2, respectively

are presented as Figures 2-1

14

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

2. 2. 1 Specification effluent Containment and Plant 3.3.3.9, monitoring alarm Ve~t instrumentation Monitor.

setp.oints to shall ensure Per be the requirements established that the for release of the rate Technical gaseous of noble gases do~s 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:

L

FRAC = [4.72E+02

X/Q *VF* (Ci *Ki)]+ 500 c2. 1 )

FRAC = C4.72E+02

X/Q *VF* r. (Ci *(Li + 1.1 Mi))]~ 3000 c2. 2) where:

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate X/Q = annual average meteorolo~ical dispersion to the controlling site boundary location Csec/m )

VF = ventilation system (Low rate for the applicable release point and monitor Ctt 3 /min) ci = concentration of noble gas radionuclide as determined by radioanalysis of grab sample CuCi/cm 3 >

Ki = total body dose conversion factor for noble gas radionuclide (mrem/yr per uCitm 3 , from Table 2-1)

Li = beta skin dose conversion factor for noble gas radionuclide Cmrem/yr per uCitm 3 , from Table 2-1)

Mi = 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) 1 .. , = mrem skin dose per mrad Jamma air dose Cmrem/mrad) 4.72E+02 = conversion factor (cm /ft 3

min/sec) 500 = total body dose rate limit Cmrem/yr>

3000 = skin dose rate limit Cmrem/yr>

15

Salem ODCM Rev. 4 05/17/88 Based on the more limiting FRAC (i.e., higher value) as determined above, the

alarm setpoints for calculated by the equation:

the applica"ble SP = [AF

monitors L_ Ci

SEN - FRAC]

CR16,

+

R41C, bkg and/or R12A) may be

( 2. 3) where:

SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)

SEN = monitor sensitivity (cpm per uCi/cm 3 >

bkg = background'of the monitor (cpm)

AF = 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 cont~ol imposed to ensure that combined releases from Salem Units and 2 and Hope Creek will not exceed the regulatory limits on release rate f~om the site (i.e., the release rate limits

of Technical Specification Units 1 and 2 is 0.5 Creek. Any increase 3~11.2.1).

(0.25 per unit),

in AF above 0.5 Normally, with the for the combined AF value for Salem remainder 0.5 the Salem Nuclear allocated Generating to Hope 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 pot~ntial of periodically having to adju~t 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

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 i____.

Salem ODCM Rev. 4 05/17/88 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20

2.3.1 l i mi t s Site Boundary Dose Rate - Noble Gases.

mr e m/ y r ,

t he d os e rat e t o t a l b od y a nd at

~3 t he S I TE BOU NDARY d u e 0 0 0 mr e mI y r , s k i n

Technical to Specification nob l e ga s r e l eas es Radiation monitor alarm setpoints 3.11.2.1a to ~5 0O 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 3

(sectm >

Qi = average release rate of radionuclide over the release period under eval*uation (uCi/sec)

Ki = total body dose conversion factor for noble gas radionuclide 3

(mrem/yr per uc i!m , from Table 2-1>

Li = beta skin dose conversion factor for noble gas radionuclide 3

(mrem/yr per uc i/m , from Table 2 - 1 )

Mi = gamma air dose conversion factor for noble gas radionuclide (mrad/yr per uc i!m 3 , from Table 2 - 1 )

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 ~1500 mrem/yr to any organ for I

13 1 , t r i t i um a nd p a r t i_ c u l a t e s wi t h ha l f

l i ves gr ea t e r t han 8 days . To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The following equation may be used for the ~ose rate evaluation:

Do = X/Q

L. (Ri *Qi) ( 2. 6) where:

Do = average organ dose rate over the sampling time period Cmrem/yr)

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway Csec/m 3 >

Ri dose parameter for radionuclide i, Cmrem/yr per for the child inhalation pathway from Table 2-5 Qi = average release rate over the appropriate sampling period and analysis frequency for radionuclide i 1*13l, 1*133, tritium or other radionuclide in particulate form with half-life greater than

8 days (uCi/sec) 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 dispersion (see Table 2-4) be and organ <inhalation, child, determined.

and Based the most on the limiting annual average p.otential meteorological pathway, thyroid -- Ri = 1.62E+07 mrem/yr per uCi/m 3 ),

age group 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 pa r t i c u l a t e ma t e r i a l a nd ot he r re l eas e .p o i n t s (e*g*, Ho p e Cr e e k ) , t he 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 requires a periodic assessment of releases of noble gases to evaluate compliance 3.11.2.2 wi th the qua r. t er Ly dose Li mi ts of ~5 mrad , gamma - a i r and ~1 O mrad , bet a - a i r and the calendar year Limits ~10 mrad, gamma-air and ~20 mrad, beta-air. The Limits are applicable separately to each unit and are not combined site 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:

Dg = air dose due to gamma emissions for noble gas radionuclides (mrad)

Db = air dose due to beta emissions for noble gas radionuclides Cmrad)

X/Q = atmospheric dispersion to the controllfng SITE BOUNDARY location Csectm 3 >

Qi = 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)

2. 4. 2 Simplified Dose Calculation for Noble Gases. In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2. (Refer to Appendix C for the derivation and justification for this simplified method.)

21

Salem ODCM Rev. 4 05/17/88 3.17E-08

X/Q

Meff

L_

Dg Qi ( 2. 9) 0.50 and 3.17E-08 Db = --------

X/Q

Neff

1::. Qi (2.10) 0.50 where:

Me ff = 5.3E+02, effective gamma-air dose factor (mrad/yr per uCitm 3 )

Neff = 1.1E+03, effective beta-air dose factor (mrad/yr per uCi/m 3 >

Qi = cumulative release for all noble gas radionuclides (uCi) 0.50 = conservatism factor to account for potential variability in the radionuclide distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the gamma-~ir 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 with UNRESTRICTED AREA Dose - Radioiodine and Particulates.

requirements of Technical Specification 3.11.2.3, a In periodic accordance assessment shall be performed to evaluate compliance with the quarterly dose limit of ~7.5 mrem and calendar year limit ~15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of 1-131, tritium and particulates with half-lives greater than 8 days:

Daop 3.17E-08

W

SFp

l:_ (Ri *Qi) (2.11) where:

Daop = 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 ~athway and H-3 dose

contribution via other pathways (sec/m )

D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (m- 2 )

2 Ri = dose factor for radionuclide i, (mrem/yr per uCiJm 3 > or cm 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.

Qi = cumulative release over the period of interest for radionuclide

-- 1-131 or radioactive material in particulate form with half-life greater than 8 days (uCi).

SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.

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.

Table 3.11.2.3.

2-4 need be Only the evaluated co~trolling for age group and pathway as identified in compliance with Technical Specification

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).

Omax = 3~17E-08 *II* SFp

RI-131 * [_ Qi (2.12) where:

Dmax = maximum organ dose Cmrem)

RI-131 = 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)

II = 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 material periods condensables may be of (e.g.,

primary released noble to via secondary the gases~

secondary will leakage, be system minor to predominately levels the of atmosphere.

released radioactive via Non-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, R4 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:

Qi = Ci

Rsgb

Fft * (1-SQftv) (2.13) where:

Qi = the release rate of radionuclide, *i, from the steam generator flash tank vent (uCi/sec) ci = the concentration of radionuclide, i, in th'e secondary coolant water averaged over not more than one week (uCi/ml)

Rsgb = the steam generator b(owdown rate to the flash tank (ml/s~c)

Fft = 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 for the moisture carry-over which is the transport media for is not necessary to account 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. The equation simplifies to the following:

Qi = 0.072 Ci Rsgb (2.14)

For H-3, the simplified equation is:

Qi = 0.48 Ci Rsgb (2.15)

Also during reactor secondary system, shutdown operations radioactive material with a may be released radioactively contaminated to the atmosphere via atmospheric reliefs CPORV) and the safety reliefs on the main steam lines and via the 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 Qi = 0.13

r,ccij

Sfj)

PF (2.16)

where:

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

SFj = stea~ flow for release pathway

= 450,000 lb/hr per PORV

= 800,000 lb/hr per safety relief valve

= 50,000 lb/hr for aux~liary 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 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 SYSTEM material and Specification 3.11.2.4 VENTILATION levels prior EXHAUST to requires TREATMENT discharge when that SYSTEM the projected be GASEOUS used doses to RADWASTE reduce exceed TREATMENT radioactive 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 D bp

=

Dg*(91~d)

Db

C91T d)

(2.17)

(2.18)

Dmaxp = Dmax * (91~ d) (2.19) where:

D g'p = gamma air dose projection for .current calendar quarter (mrad)

Dg = gamma air dose to date for current calendar quarter as determined by equation (2.7) or (2.9) Cmrad)

D bp = beta atr dose projection for current calendar quarter (mrad)

Db = beta air dose to date for current calendar quarter as determined by equation (2.8) or (2.10) (mrad)

Dmaxp = maxi~um organ dose projection for current calendar quarter Cmrem)

Dmax = maximum organ dose to date for current calendar quarter as dete~mined by equation (2.11) or (2.12) Cmrem) d = number of days to date in current calendar quarter 91 = 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 Release Report with Technical CRERR)

Specification 6.9.1.11, submitted within 60 days after the Radioactive January of Effluent 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 meteorological dispersion data dose to a MEMBER OF 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 as presented THE in. Table PUBLIC 2-3 based on may be the The default value for*

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 T~E PUBLIC - 40 CFR 190 The Radioactive Effluent Release Report CRERR) submitted within January 1 of each year shall also include an assessment of the radiation dose to 60 days* after the Lilcely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources Cincludi~g 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 Ll 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 ~alculation~ for the Salem Nuclear Generating Station may be performed using the calculation methods contained within this ODCM; the conservative controlling pathways and loca~ions 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 30 annual meteorological dispersion

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 wi 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 gn 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 material supplied as part 3.12.3 of an requires analyses be performed Interlaboratory Comparison.

on radioactive Participation approved Interlaboratory Comparison Program provides a check on the preciseness of in an 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

RADIATION MONITORING LIQUID RELEASES UNIT 2

FIGURE 1-2 12 REACTOR COO.ANT OAA IN TFN:

IIFROll VOL. CONTROL TANK VENT TO GASEOUS VENT VENT AADIASTE REFUELING IATER STOMGE Tfvt( f22 HDLD-LlP f2l HOLD-LlP f21 Hll.D-LlP GAS SIHIPPER HJXED BED CDllPOllENT Tfvt( TANIC TIW:

DEHINERIUZER COO.ING SIJlSE Tfvt( REFl£1.. IATER [l] D RlO FEED PUllP~

'-----------'-----------'---------------'-~~---

FILTER R29o R2e 0 f2 REACTOR COOLANT 1

~1rm.:..,UER-RL-'-n-'----,

PUlf' L-1

..-El-

~IIPIT 12 SPENT FUEL PIT DEHINEAALIZEA FIL TEA SKJllHER FILTER FILTER ' - - - - - - - - - J NO. 21 NO* 22 NO- 2l NO* 24 EVAPORATOR EVAPORATOR EVAPORATOR EVAPORATOR NO* 1 GAS FEED ION FEED ION VOLUllE TO BORIC ACID STRIPPER FEED JON FEED ION CONTROL 1

EXCHANGE A EXCHANGE A EXCl'lll<<JEA EXC!ilNGCA EVAPORATOR TANK VENT TO f2 ION EXCHANGER

[j]I AUX BLDG ,-,All VENT SYS '--'

VENT VENT ASTE IASTE MONITOR Hll.D-LlP T-IASTE HOLD-LlP IASTE HOLD-UP IASTE HONllOR I FA011 HONJTOR r TANK PlttPS Tfvt( f 11 TANK 112 TPH: 111 11 1

~---.IL51-IAC IATER---+lllM~ffif

~"J =

Rl9A0 0Rl90 A1s~D I STH GEN II OA SC I I llOOllt+N-+-*------~*684,----toGBll-~

~ STH GEN I I I I llOOllPl-1-..-------+*61l4,'-'----+lll88---oi I STH GEN II II STEAM GENERATOR BLDIOOIN TflNI:

NO* 1 IASIE EVAPOAATOA IASTE l'IOHllOA TANK 112 -**"

HOLD-LlP IANI:

PlttPS

)100111

E841-'--'----+<ll88---oi

\~1GEN I *Cll4llL____...L---,...----'

TO

~..I

+--------081 B

~-AAD LICUID IASTE DISPOSll.

!FOR JNfOAl1ATION OllLYJ C!HJENSM +----GBJB

+-----<lBIB CIAC IATER

FROM WM..iTOIHfllUNT ~IOEMTIIS ~UNIT EOUIPDAS AllllllOG~TII lllCPHfllll TllS WHUl!i RCLOC.OAS FLOOR ORS WI.In CVCS HUI RELIEFS Rll FlAHGE l 0 W\1111 AllCtMJlATOR OAS

-SUMPS

-

Wl.1'7 Ella:SS LET 1XMN FROM BAEVAP WI.

I Wl2Z1 I RWST I t WHUT Wl.11 ACPS

.... CVCSHUT Wl.7 RCOT 3SEAl.LO DR WI. 1111 WI. 13 WI."

1WMT Wl11 Wl.18 I

IDIFROM cmtER UNIT 2WHUT Wl.12 FC FC Wll7 Wllt CONT-l'mDR Wl.13 4- ...

WMSTEEVAP I FEEOl'UMP Wllrl!I VMSIEEVAP:

Wl.11 I I

'M.47

_______ ,.. _______ ,.._1" Wl.',. ------.--~

2"'1.114 .. -~

2WI. - ........-tel~+I ,..,...........

I I

-

FROMCVCS NON oo; w1.11M Wl.183

~

+ IWUllO - -

T-----M--* 2MHJT

~

I

.a.I WUJll Wl.71

~ * - -..-,,...---*~.o*ct-~91!_-L.

I

-...- J I 2Wl911 I * - rf-----4*--f---OO- *I

[:;:::-

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

on fl .O~~~** *~~*

I L----- Wl.51

~

WUll3 Wl.115 TONIO FROM t--~~ OIHER UNIT x-

-r--T~ FOR INFORMATION 0 t-1 *WR21 6 6 FIGURE 1-3

!Mn* !Mn* LIQUID L------1--.J I.WIS WASTE llW41

Salem OOCM Rev. 4 05/17/88 Table 1-1

Parameters for Liquid Alarm Setpoint Determinations Unit 1 Parameter Actual Default Units Comments Value Value

-------- -------- ---------- -------------------------------------------

MP Ce calculated 1E-05

uCi/ml calculate for each batch to be released MPCl-131 3E-07 N/A uCi/ml 1-131 MPC conservatively used for SG blow-down and Service Water monitor setpoints Ci measured N/A uCi/ml taken from gamma spectral analysis of liquid effluent MPCi as N/A uCi/ml taken from 10 CFR 20, Appendix B, Table II, determined Col. 2.

SEN 1-R18 as 2.9E+07 cpm per uCi/ml radwaste effluent (Cs-137) determined 1-R19 2.9E+07 Steam Generator blowdown (Cs-137)

(A,B,C,D) 1-R13 1.2E+08 Service Water - Containment fan cooling CA,B,C,D,E) (Cs-137)

cw RR 1-R18 as determined as determined 1.85E+OS 120 gpm gpm Circulating Water System, single CW pump determined prior to release; release rate can be adjusted for Technical Specification compliance 1-R19 120 Steam Generator blowdown rate per generator 1-R13 2500 Service Water flow rate for Containment fan coolers SP 1-R18 calculated 4.4E+OSC+bkg) cpm Default alarm setpoints; more conservative values may be used as deemed appropriate and 1-R19** calculated 1.3E+04C+bkg) desirable for ensuring regulatory compliance and for maintaining releases ALARA.

1-R13** calculated 2.6E+03C+bkg)

*

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

MP Ce MPCl-131 Actual Value

calculated 3E-07 Default Value

1E-05

N/A

uni ts

uCi/ml uCi/ml 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 Ci measured N/A uCi/ml taken from gamma spectral analysis of liquid effluent MP Ci as N/A uCi/ml taken from 10 CFR 20, Appendix B, Table 11, determined Col. 2.

SEN 2-R18 as 8.8E+07 cpm per uCi/ml radwaste effluent (Cs-137) determined 2-R19 8.8E+07 Steam Generator blowdown (Cs-137)

CA,B,C,D) 2-R13 8.8E+07 Service Water - Containment fan cooling (A,B,C,D,E) (Cs-137)

R37 8.8E+07 Chemical Waste Basin (Cs-137) cw as 1.85E+OS gpm Circulating Water System, single CW pump

determined (Note no CW pump in service for 2R13 monitor see section 1.2.2)

RR 2-R18 as 120 gpm determined prior to release; release rate determined can be adjusted for Technical Specification compliance 2-R19 120 Steam Generator blowdown rate per generator 2-R13 2500 Service water flow rate for Containment fan coolers R37 300 Chemical Waste Basin discharge SP 2-R18 calculated 8.0E+05C+bkg) cpm Default alarm setpoints; more conservative values may be used as deemed appropriate and 2-R19** calculated 3.9E+04C+bkg) desirable for ensuring regulatory compliance and for maintaining releases ALARA.

2-R13** calculated 8.8E+02(+bkg)

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

Refer to Appendix A for derivation

- Based on Cs-137 response

- - 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 Table 1 - 3 I

Nuclide

Site Related lngest"ion Dose Commitment Factors, Aio Bone Liver (mrem/hr per uCi/ml)

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

Salem ODCM Rev. 4 05/17/88 I

I._ Table 1-4 Bioaccumulation Factors (Bfi)

(pCi/kg per pCi/liter)*

Element Saltwater Fish Saltwater Invertebrate H 9.0E-01 9.3E-01 c 1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 p 3.0E+03 3.0E+04 Cr 4.0E+02 2.0E+03 Mn 5.5E+02 4.0E+02

- Fe 3.0E+03 2.0E+04 Co 1. OE+02 1. OE+03 Ni 1.0E+02 2.SE+02 cu 6.7E+02 1. 7E+03 Zn 2.0E+03 5.0E+04 l Br 1.SE-02 3.1E+OO Rb 8.3E+OO 1.7E+01

_s r 2.0E+OO 2.0E+01 y 2.5E+01 1. OE+03 Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1. OE+02 Mo 1.0E+01 1.0E+01

Tc Ru Rh Ag Sb Te 1.0E+01 3.0E+OO 1.0E+01 3.3E+03 4.0E+01 1.0E+01

5. 0 E +_O 1

1.0E+03 2.0E+03 3.3E+03 5.4E+OO

1. OE+02 I 1.0E+01 5.0E+01 Cs 4.0E+01 2.5E+01

,, Ba La

1. OE+01 2.5E+01 1.0E+01 1.0E+03 Ce 1.0E+01 6.0E+02 Pr 2.5E+01 1. OE+03 Nd 2.SE+01 1. OE+03 w 3.0E+01 3.0E+01 Np 1.0E+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

............... * -----~

'

I -

L'"""'-

--;t:-i.:*

--'--

~... -,

'

I I.:,__ -- ~~~.._J

<XlN!.""l AOOll - -

.,----- ~-~- -*--

~

.-*.. -- --_

~~*IC

.., ...

.._._,

- --,

FOR INFORMATION ONLY

-

-............

.....

=----

...... M .. l t

--

=.......---*

I I

I FIGURE 2-2

-.-.... --.....--

1111 RADIATION MONITORING

..... MtDtll GASEOUS 2UNIT

.....

MIOt ..

MIC MICllM

Salem ODCM Rev. 4 05/17/88

,. Total Body Table 2-1 Dose Factors for Noble Gases Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor I\ 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

Salem ODCM Rev. 4 05/17/88 Table 2-2

Parameters for Gaseous Alarm Setpoint Determinations Unit-1 Parameter Actual Default Units Comments Value Value

/

I -------- -------- -------- ----------

X/Q calculated 2.2E-06 sectm3 USNRC Salem Safety Evaluation, Sup. 3 VF as measured 1.25E+05 ft 3tmin Plant Vent - normal operation

\ (Plant or I Vent) fan curves VF as measured 3.SE+04 Containment purge (Cont. or Purge) fan curves AF coordinated 0.25 unit less Administrative allocation factor to with HCGS ensure combined releases do not exceed release rate limit for site.

Ci measured N/A uCi/cm3 I( i nuclide specific N/A mrem/yr per uCiJm3 Values from Table 2-1

Li Mi SEN 1-R41C*

nuclide specific nuclide specific as N/A N/A 1 .6E+07 mrem/yr per uCitm3 mrad/yr per uCitm3 cpm per uCi/cm3 Values from Table 2-1 Values from Table 2-1 Plant Vent determined 1-R16 3.6E+07 Plant Vent (redundant) 1-R12A 2.1E+06 Containment SP 1-R41C calculated 3.3E+04(+bkg) cpm Default alarm setpoints; more conservative values may be used as deemed appropriate and 1-R16 calculated 7.4E+04C+bkg) desirable for ensuring regulatory compliance and for maintaining releases ALARA.

1-R12A** calculated 1.5E+04(+bkg)

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.

Salem ODCM Rev. 4 05/17/88 Table 2-3

Parameters for Gaseous Alarm Setpoint Determinations Unit-2 Parameter Actual Default Units Comments Value Value

-------- -------- ----------

X/Q calculated 2.2E*06 sec/m3 licensing technical specification value VF as measured 1.25E+05 ft 3 /min Plant Ve~t - normal operation (Plant or Vent) fan curves VF as measured 3.5E+04 Containment purge (Cont. or Purge) fan curves AF coordinated 0.25 unit less Administrative allocation factor to with HCGS ensure combined releases do not exceed release rate limit for site.

Ci measured N/A uCi/cm 3 Ki nuclide specific N/A mrem/yr per uCi/m3 Values from Table 2-1

Li Mi SEN 2*R41C*

nuclide specific*

nuclide specific es N/A N/A 1 .6E+07 mrem/yr per uCi/m3 mred/yr per uCi/m3 cpm per uCi/cm3 Values from Table 2-1 Values from Table 2-1 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), monito~ setpoints shall be

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

46

~I Salem ODCM Rev. 4 DS/17/88

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

Atmospheric Dispersion Technical Specification Location Pathway(s) Controlling X/Q Age Group ( sectm3 )

3.11.2.1a site boundary noble gases N/A 2.2E-06 N/A (0.83 mi le, N> direct exposure 3.11.2.1b site boundary inhalation child 2.2E-06 N/A (0.83 mi le, N) 3.11.2.2 site boundary gamma-air N/A 2.2E-06 N/A (0.83 mi le, N) beta-air 3.11.2.3 residence/dairy milk and infant S.4E-08 2.1E-10 (4.8 miles, NNE) ground plane 6.9.1.10 Second sun direct exposure N/A 8.22E-06 N/A (0.21 mile/SE) and inhalation

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

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 3.04E+5 1. 40E+6 3.50E+5 8.72E+3

Sr-89 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 2.81E+5 2.00E+5 4.64E+2

Pr-143 9.36E+3 3.75E+3 2.16E+3 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

RCio),

Table 2-5 (cont'd)

Inhalation Pathway Dose Factors Cmrem/Yr per uCi/m3>

- TEENAGER 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 Y-91 Zr-95 Nb-95 Ru-103 1.08E+8 6.61E+5

1. 46E+5

1. 86E+4 2.10E+3 4.58E+4 1.03E+4 6.74E+4

1. OOE+4 7.43E+3 1.65E+7 2.94E+6 2.69E+6 7.51E+5 7.83E+5 7.65E+5 4.09E+5

1. 49E+5 9.68E+4

1. 09E+5 6.68E+6

1. 77E+4 3.15E+4 5.66E+3 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 ~.15E+4 1. 94E+5 1.10E+5 1. 78E+4 1. 09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 3.04E+5 1.21E+5 8.48E+3 3.11E+5 Ba-140 5.47E+4 6.70E+1 2.28E+1 2.03E+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 49 3.72E+5 1. 82E+5 5.13E+2 I_

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

Nuclide H-3 RCio),

Bone Inhalation Pathway Dose Factors

Liver 1.12E+3 Cmrem/yr per uCi/m3)

Thyroid 1.12E+3 Kidney 1.12E+3 Lung 1.12E+3 CHILD Gl*LLI 1.12E+3 T.Body 1.12E+3 c-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 4.22E+4 9.88E+4 Cr-51 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 4.29E+4 1.00E+4 1.58E+6 2.29E+4 9.51E+3 Fe-55 4.74E+4 2.52E+4 1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 Co-57 9.03E+2 5. 07E+5 1. 32E+4 1. 07E+3 Co*58 1. 77E+3 1.11E+6 3.44E+4 3.16E+3 Co*60 1.31E+4 7.07E+6 9.62E+4 2.26E+4 Ni* 63 8.21E+5 4.63E+4 2.75E+5 6.33E+3 2.80E+4 Zn-65 4.26E+4 1.13E+5 7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 1. 98E+5 7.99E+3 1.14E+5 Sr*89 5.99E+5 2.16E+6 1.67E+5 1.72E+4 Sr*90 1.01E+8 1.48E+7 3.43E+5 6.44E+6

.-

Y-91 9.14E+5 2.63E+6 1.84E+5 2.44E+4 Zr-95 1.90E+5 4.18E+4 5.96E+4 2.23E+6 6.11E+4 3.70E+4 Nb*95 2.35E+4 9.18E+3 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1. 36E+5 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1. 69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1. 26E+2 3.24E+6 1. 64E+5 2. OOE+.4 Sb-125 9.84E+4 7.59E+2 9.10E+1 2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1. 92E+3 4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1. 48E+6 7.14E+4 3.02E+3 Te*129m 1. 92E+4 6.85E+3 6.33E+3 5.03E+4 1. 76E+6 1.82E+5 3.04E+3 I - 131 4.81E+4 4.81E+4 1. 62E+7 7.88E+4 2.84E+3 2.73E+4 Cs-134 6.51E+5 1.01E+6 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs*136 6.51E+4 1.71E+5 9.55E+4 1. 45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 2.82E+5 1. 04E+5 3.62E+3 1. 28E+5 Ba-140 7.40E+4 6.48E+1 2.11E+1 1. 74E+6 1. 02E+5 4.33E+3 Ce*141 3.92E+4 1 .95E+4 8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 1.17E+6 1. 20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1 .08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2

50

Salem ODCM Rev. 4 05/17/88 51

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

Nuclide 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 Liver Thyroid Kidney Lung Gl-LLI T.Body H-3 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 1.92E+9 6.60E+8 Cr-51 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 8.40E+6 2.SOE+6 2.57E+7 1. 60E.+6 Fe-55 2.51E+7 1. 73E+7 9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 1.95E+7 2.33E+8 2.68E+7 Co-57 1. 28E+6

3.25E+7 2.13E+6 Co-58 4.72E+6 9.57E+7 1.06E+7 Co-60 1.64E+7 3.08E+8 3.62E+7 Ni -63 6.73E+9 4.66E+8 9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 2.92E+9 2.75E+9 1.97E+9 Rb-86 1.35E+S 1 .66E+4 5 .90E+4 Sr-89 1. 45E+9 2.33E+8 ,.16E+7 Sr-90 4.68E+10 1.35E+9 1.15E+10 Y-91 8.60E+3 4.73E+6 2.30E+2

Zr-95 Nb-95*

Ru-103 Ru-106

1. 07E+S 1.41E+4

1. 02E+3 2.04E+4

3. 44E+4 7.82E+3 5.24E+4 7.74E+3 3.89E+3 3.94E+4 1.77E+6 5.0SE+S 1.SOE+S 1.04E+5 1.19E+S 1.32E+6 2.33E+4 4.21E+3 4.39E+2 2.58E+3 Ag-110m 5.83E+7 5.39E+7 1.06E+8 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.00E+7 7.31E+8 1. 02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1. 63E+7 5.90E+6 4.90E+6 6.63E+7 6.SOE+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 1. 54E+8 5~58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 3.04E+8 9.57E+6 I - 1 31 2.96E+8 4.24E+8 1.39E+11 7.27E+8 1.12E+8 2.43E+8 Cs-134 5.6SE+9 1.34E+10 4.35E+9 1.44E+9 2.35E+8 f.10E+10 Cs-136 2.61E+8 1.03E+9 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 3.43E+9 1.14E+9 1.9SE+8 6.61E+9 Ba-140 2.69E+7 3.l8~+4 1 .1 SE+4 1. 93E+4 5. 54E+7 1. 76E+6 Ce-141 . 4.84E+3 3.27E+3 1.52E+3 1.25E+7 3.71E+2 Ce-144 3.58E+S 1.SOE+5 8.87E+4 1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 3.68E+1 6.96E+S 7.88E+O Nd-147 9.42E+1 1.09E~2 6.37E+1 S.23E+S 6.52E+O

52

Salem ODCM Rev. 4 05/17/88 Table 2*5 (cont'd)

Nuclide RCio), Grass*Cow*Mitt Pathway Dose Factors

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

mrem/yr per uCi/sec) for others Liver Thyroid Kidney Lung Gl*LLI

__ .;. ___ _

T.Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C*14 6.70E+5 1. 34E+5 1. 34E+5 1. 34E+.5 1.34E+5 1.34E+5 1.34E+5 P*32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr*51 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn*54 1. 40E+7 4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe*59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 1.10E+8 1.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni* 63 1.18E+10 8.35E+8 1.33E+8 4.01E+8 Zn*65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Rb*86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6

Y-91 1.58E+4 6.48E+6 4.24E+2 zr-95 1. 65E+3 5. 22E+2 7.67E+2 1.20E+6 3.59E+2 Nb*95 1.41E+5 7.80E+4 7.57E+4 3.34E+8 4.30E+4 Ru-103 1.81E+3 6.40E+3 1.52E+5 7.75E+2 Ru-106 3.75E+4 7.23E+4 1.80E+6 4.73E+3 Ag*110m 9.63E+7 9.11E+7 1.74E+8 2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25Et8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te*125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te*127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+8 1.00E+7 Te-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 4.15E+8* 1.75E+7 I - 1 31 5.38E+8 7.53E+8 2.20E+11 1.30E+9 1. 49E+8 4. 04E+8 Cs-134 9.81E+9 2.31E+10 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 9. 53E+8 1. 50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 1. 99E+4 1. 35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-144 6.58E+5 2.72E+5 1.63E+5 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 6.77E+1 9.61E+5 1.45E+1 Nd-147 1.81E+2 1.97E+2 1.16E+2 7.11E+5 1.18E+1

53

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

Nuclide RCio),

Bone 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 Liver Thyroid Kidney Lung Gl-LLI T.Body H-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1 .65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+S 3.29E+5 P-32 7.77E+10 3.64E+9 2.15E+9 3.00E+9 Cr - 5 1 5. 66E+4 1. 55E+4 1. 03E+5 5. 41 E+6 1. 02E+S Mn-54 2.09E+7 5.87E+6 1.76E+7 5.58E+6 Fe-55 1.12E+8 S.93E+7 3.35E+7 1.10E+7 1. 84E+7 Fe-59 1.20E+8 1.95E+8 5.65E+7 2.03E+8 9.71E+7 Co-57 3.84E+6 3.14E+7 7.77E+6 co-58 1.21E+7 7.08E+7 3.72E+7 Co-60 4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9 Zn-65 4.13E+9 1.10E+10 6.94E+9 1.93E+9 6.85E+9 Rb-86 8.77E+9 S.64E+8 5.39E+9 Sr-89 6.62E+9 2.56E+8 1.89E+8 Sr-90 1.12E+11 1.51E+9 2.83E+10

Y-91 9.14E+S 2.63E+6 1.84E+5 2.44E+4 Zr-95 3.84E+3 8.45E+2 1.21E+3 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+5 2.29E+8 8.84E+4 Ru-103 4.29E+3 1. 08E+4 1.11E+5 1.65E+3 Ru-106 9.24E+4 1.25E+5 1.44E+6 1 .15E+4 Ag-110m 2.09E+8 1.41E+8 2.63E+8 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 1. 68E+8 2.47E+7 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+8 3.32E+8 4.23E+7 I - 131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.17E+8 7.46E+8 Cs-134 2.26E+10 3.71E+10 1 .15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-136 1. OOE+9 2. 76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1 .01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+6 5.09E+5 2.82E+5 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 1. 98E+2 S.71E+5 2.79E+1

54

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

Nuclide R( i o ) ,

Bone Gr a s s - Co w - M_ i l le P a t h w a y Do s e F a c t o r s -

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

mrem/yr per uCi/sec) for others Liver Thyroid Kidney Lung I NF ANT Gl-LLI T.Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+S 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 9.42E+9 2.17E+9 6.21E+9 Cr-51 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 3.89E+7 8.63E+6 1. 43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 1 .16E+8 1.88E+8 1.55E+8 Co-57 8.95E+6 3.05E+7 1.46E+7 Co-58 2.43E+7 6.05E+7 6.06E+7 Co-60 8.81E+7 2.10E+8 2.08E+8 Ni - 63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 8.78E+9 Rb-86 2.22E+10 5.69E+8 1.10E+10 Sr-89 1.26E+10 2.59E+8 3.61E+8 Sr-90 1.22E+11 1.52E+9 3.10E+10

Y-91 Zr-95 Nb-95 Ru-103 Ru-106 7.33E+4 6.83E+3 5.93E+5 8.69E+3

1. 90E+5 1.66E+3 2.44E+5

1. 79E+3 1.75E+5 1.81E+4 2.25E+5 5.26E+6 8.28E+5 2.06E+8 1.06E+5 1.44E+6 1.95E+3 1.18E+3 1.41E+5 2.91E+3 2.38E+4 Ag-110m 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 Sb-124 2.0~E+8 3.08E+6 5.56E+5 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1. 70E+8 5.10E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1. 40E+9 3.34E+8 8.62E+7 I - 131 2.72E+9 3.21E+9 1.0SE+12 3.75E+9 1.15E+8 1.41E+9 Cs-134 3.65E+10 6.80E+10 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.1SE+9 Cs-137 5.15E+10 6.02E+10 1.62E+10 6.55E+9 1 .88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+S S.73E+4 1.48E+S S.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 8.15E+3 1.37E+7 3.11E+3 Ce-144 2.33E+6 9.52E+S 3.85E+5 1. 33E+8 1. 30E+S Pr-143 1. 49E+3 5. 59E+2 2.08E+2 7.89E+S 7.41E+1 3.49E+2 S.74E+S 5.SSE+1

Nd-147 8.82E+2 9.06E+2 55

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

Nuclide R(io), Vegetati~n Pathway Dose Factors - ADULT Bone Cmrem/yr per uCi/m3) for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others 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 1.40E+9 8.73E+7 1. 58E+8 5. 42E+7 Cr-51 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 3.11E+8 9.27E+7 9.54E+8 5.94E+7 Fe-55 2. 09E+8 1. 45E+8 8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 8.35E+7 9.96E+8 1.14E+8 Co-57 1.17E+7 2.97E+8 1.95E+7 Co-58 3.09E+7 6.26E+8 6.92E+7 Co-60 1.67E+8 3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 1.SOE+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 6.75E+8 6.36E+8 4.56E+8 Rb-86 2.19E+8 4.32E+7 1.02E+8 Sr-89 9.96E+9 1.60E+9 2.86E+8 Sr-90 6.05E+11 1.75E+10 1.48E+11 Y-91 5.13E+6 2.82E+9 1.37E+S

Zr-95 Nb-95 Ru-103 Ru-106 1.19E+6 1.42E+5 4.80E+6 1.93E+8 3.81E+5 7.91E+4 5.97E+5 7.81E+4 1.83E+7 3.72E+8 1.21E+9 2.58E+5 4.80E+8 -4.25E+4 5.61E+8 1 .25E+10 2.07E+6 2.44E+7 Ag-110m 1.06E+7 9.76E+6 1.92E+7 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 2.95E+9 4.11E+7 Sb-125 1. 36E+8 1. 52E+6 1. 39E+5 1. 05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 3. 86E+8. 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 1. 28E+9 4.03E+7 I - 1 31 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.0SE+7 6.63E+7 Cs-134 4.66E+9 1.11E+10 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4~20E+7 1.66E+8 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Ba-140 1. 29E+8 1. 62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 1. 96E+5 1. 33E+5 6.17E+4 5.08E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 8.16E+6 1.11E+.10 1.77E+6 Pr-143 6.34E+4 2.54E+4 1.47E+4 2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 2.25E+4 1.85E+8 2.31E+3

56

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

Nuclide RCio),

Bone Vegetation Pathway Dose Factors - TEENAGER Cmrem/yr per uCi/m3) for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Liver 2.59E+3 Thyroid 2.59E+3 Kidney 2.59E+3 Lung 2.59E+3 Gl-LLI 2.59E+3 T. Body 2.59E+3 H-3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 1.35E+8 6.23E+7 cr - 5 1 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 4.52E+8 1.35E+8 9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 1.33E+8 9.98E+8 1.63E+8 Co-57 1. 79E+7 3.34E+8 3.00E+7 Co-58 4.38E+7 6.04E+8 1.01E+8 Co-60 2.49E+8 3.24E+9 5.60E+8 Ni - 63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Rb-86 2.73E+8 4.05E+7 1.28E+8 Sr-89 1.51E+10 1.80E+9 4.33E+8 Sr-90 7.51E+11 2.11E+10 1.85E+11 Y-91 7.87E+6 3~23E+9 2.11E+5

Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m

1. 74E+6 1.92E+5 6.87E+6 3.09E+8 1.52E+7

5. 49E+5 1.06E+5 1.44E+7 8.07E+5 1.03E+5 2.42E+7 5.97E+8 2.74E+7 1.27E+9 4.55E+8 5.74E+8 1.48E+10 4.04E+9 3.78E+5 5.86E+4 2.94E+6 3.90E+7 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 1. 88E+8 1. 66E+9 5.00E+7 Te-125m 1. 48E+8 5.34E+7 4.14E+7 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 1 .38E+9 5.81E+7 I - 131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 2.13E+7 5.79E+7 Cs-134 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4. 29E+7 1. 69E+8 9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1 .69E+5 5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ce-141 2. 82E+5 1. 88E+5 8.86E+4 5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3

57

Salem OOCM Rev. 4 05/17/88 Table 2-5 (cont'd)

Nuclide R(io), Vegetatiqn Pathway Dose Factors - CHILD Bone (mr~m/yr per uCi/m3)

Liver Thyroid for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others Kidney Lung GI-Lll T.Body H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1. 58E+8 9.30E+7 1. 30E+8 Cr-51 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 6.61E+8 1.85E+8 5.SSE+B 1.76E+8 Fe-55 8.00E+8 4.24E+8 2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 1.88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 co-58. 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 2.10E+9 1.12E+9 Ni - 63 3.95E+10 2.11E+9 1. 42E+8 1. 34E+9 Zn-65 8.12E+8 2.16E+9 1. 36E+9 3.80E+8 1.35E+9 Rb-86 4.52E+8 2.91E+7 2.78E+8 Sr-89 3.59E+10 1.39E+9 1.03E+9 Sr-90 1.24E+12 1.67E+10 3.15E+11 Y-91 1.87E+7 2.49E+9 5.01E+5

Zr-95 Nb-95 Ru-103 Ru-106 3.90E+6 4.10E+5 1.55E+7 7.45E+8 8.58E+5 1.59E+5

1. 23E+6

1. 50E+5 3.89E+7 1.01E+9 8.95E+8 2.95E+8 3.99E+8 1.16E+10 7.64E+5 1.14E+5 5.94E+6 9.30E+7 Ag-110m 3.22E+7 2.17E+7 4.05E+7 2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1. 23E+8 Sb-125 4.99E+8 3.85E+6 4. 62E+5 2.78E+8 1.19E+9 1.0SE+B Te-125m 3.51E+8 9.SOE+7 9.84E+7 3.38E+8 4.67E+7 Te-127m 1. 32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1. 57E+8 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 1 .04E+9 1.33E+8 1 - 1 31 1.43E+8 1.44E+8 4.76E+10 2.36E+8 1. 28E+7 8.18E+7 Cs-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43E+8 cs-137 2.39E+10 2.29E+10 7.46E+9 2.68E+9 1.43E+8. 3.38E+9 Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 1.23E+5 6.14E+4 2.69E+4 7.66E+7 9.12E+3 Ce-144 1. 27E+8 3. 98E+7 2.21E+7 1.04E+10 6.78E+6 Pr-143 1. 48E+5 4. 46E+4 2.41E+4 1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 3.18E+4 9.18E+7 4.49E+3

58

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 Any Organ H-3 C-14 P-32 Cr - 5 1 4.68E+6 Mn-54 1.34E+9 Fe-55 Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Zn-65 7.45E+8 Rb-86 8.98E+6 Sr-89 2.16E+4 Sr-90 Y-91 1.08E+6 Zr-95 2.48E+8

Nb-95 1. 36E+8 Ru-103 1. 09E+8 Ru-106 4.21E+8 Ag-110m 3.47E+9 Te-125m 1.55E+6 Te-127m 9 .17E+4 Te-129m 2.00E+7 I - 1 31 1.72E+7 Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10 Ba-140 2.05E+7 Ce-141 1. 36E+7 Ce-144 6.95E+7 Pr-143

59

Salem ODCM Rev. 4 05/17/88

APPENDIX A Evaluation of Default KPC Value for Liquid Effluents

A-1

Salem ODCM Rev. 4 05/17/88 Appendix A Evaluation of Default MPC Value

In accordance with the for Liquid Effluents requirements of Technical Specification (3.3.3.10) the r a d. i o a c t i v e l i qu i d e f f l ue nt mo n i t o r s s ha l l be ope r a b l e wi t h a l a r m s e t po i nt 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:

[ Ci MPCe = ------------ CA. l )

where:

L<>

MP Ce = an effective MPC value for a mixture of radionuclide CuCi/ml>

ci = concentration of radionuclide i in the mixture MPCi = 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.

A-2 Results are

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 is reasonable radwaste to select discharges.

an Using MPCe this value value of to the years 1981 1E-05 uCi/ml calculate as the through typical default of R18 1987, it liquid 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 liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (refer to Tables 1-1 and 1-2) .

A-3

Salem ODCM Rev. 4 05/17/88

Table A-1 Calculation of Effective MPC Salem Unit 1 Activity Released (Ci)

*---------------------

Nuclide MPC* 1982 1983 1984 1985 1986 1987 (UC i /ml)

*- -------- --------- --------- ................... .. ................

---------

Na-24 3E-05 1 .9E-03 5.3E-03 S.6E-03 6.2E*03 9.2E-04 6.9E-04 Cr-51 2E-03 1.4E-01 6.2E-02 S.3E-02 3.6E-02 6.0E-02 N/D Mn-54 1E-04 2.1E-01 1.6E-01 1.9E-01 8.7E-02 1.9E-01 1.0E-01 Fe-59 SE-OS 8.6E-03 4.2E-02 S.SE-03 1.4E-03 2.4E-03 N/D Co-58 9E*OS 1. 7 1.8 1.6 6.6E-01 2.22 1. 54 Co-60 3E-05 9.1E-01 7.1E-01 1.2 6.SE-01 3.1E*01 4.2E-01 Zr-95 6E*OS 1.1E-02 8.0E-03 1.8E-03 3.2E-03 4.3E-03 8.6E-04 Nb-95 1E-04 4.SE-02 2.2E-02 1.7E-02 1.3E-03 1.SE-02 2.4E-03 Nb-97 9E-04 9.SE-03 3.6E-04 2.0E-02 7.2E-03 1.SE-03 9.SE-03 Tc-99m 3E-03 N/D N/D 1.6E*03 N/D N/D 1. 1E-04 Sr-89 3E*06 N/D 1.2E-03 4.2E-04 1. 7E-03 3.SE-07 1.6E-02 Sr-90 3E-07 N/D N/D 2.2E*OS 1 . 7E

04 3.1E-08 7.7E-04 Mo-99 4E-05 1.0E-03 1.6E-03 1.9E-03 1.0E-04 N/D 1.0E-04

Ag*110m 3E*OS 4.7E-03 N/D N/D N/D N/D 2.SE-03 Sn-113 SE-OS 2.2E-04 3.SE-04 9.4E-04 N/D 3.SE-04 N/D Sb-124 2E*OS 8.0E-03 1.4E-02 1.7E-02 S.7E-03 8.4E-02 2.4E-02 Sb-125 1E-04 6.8E*03 4.4E-02 4.9E-03 N/D 3.6E-02 3.3E-02 1-131 3E-07 6.SE-02 2.4E-02 4.SE-02 7.9E-02 1.2E*01 1.SE-01 1-133 1E-06 3.3E-02 2.SE-02 1.9E-02 1.4E-03 1.9E-02 I-135 4E-06 3.SE-04 1.6E-03 1.2E-03 N/D N/D 2.0E-03 Cs-134 9E-06 4.0E-02 1.SE-02 5. 1E-02 1.6E-01 3.4E-01 3.1E-03 Cs-137 2E-05 5.9E-02 3.0E-02 S.SE-02 2.1E-01 3.6E-01 3.0E-01 Ba-140 2E-05 N/D 1.3E-02 2.1E-03 N/D N/D N/D La-140 2E-05 7.SE-03 1.3E-02 1.6E-02 1.1E-04 3.SE-04 N/D Total Ci 3.24 3.00 3.32 1.93 3.75 3.26

_£.i_ 2.83E+OS 1.66E+OS 2.46E+05 3.42E+05 4.99E+OS 7.31E+05 MPCi MP Ce (uCi/ml) 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

Salem ODCM Rev. 4 05/17/88

Table A-2 Calculation of Effective MPC Salem Unit 2 Activity Released (Ci)

Nuclide MPC* 1982 1983 1984 1985 1986 1987 CuCi/ml>

-------- --------- --------- --------- --------- --------- .........................

Na-24 3E-05 1.2E-03 9.2E-03 4.4E-03 3.5E-03 3.6E-03 7.3E-05 Cr-51 2E-03 1.1E-01 4.6E-02 3.6E-02 3.5E-02 9.5E-02 3.0E-03 Mn-54 1E-04 2.0E-01 1.4E-01 1.6E-01 1.1E-01 2.2E-01 1.2E-01 Fe-59 5E-05 5.6E-03 3.1E-02 7.6E-03 1. 1E-03 4.0E-03 N/D Co-58 9E-05 1. 7 1. 7 1.3 8.4E-01 3.32 1. i Co-60 3E-05 8.6E-01 5.7E-01 9.8E-01 6.3E-01 3.8E-01 4.2E-01 Zr-95 6E-05 9.7E-03 5.2E-03 1.2E-03 4.6E-03 1.1E-02 8.4E-04 Nb-95 1E-04 2.3E-02 1.6E-02 1.4E-02 1.4E-02 2.5E-02 6.6E-03 Nb-97 9E-04 1.1E-02 1.1E-02 2.1E-02 5.7E-03 2.?E-03 N/D Tc-99m 3E-03 N/D N/D 1.4E-03 N/D N/D 5.?E-04 Sr-89 3E-06 N/D 3.2E-04 3.2E-04 1.5E-03 4.1E-07 3.0E-03 Sr-90 3E-07 N/D N/D 4.1E-05 1.0E-04 3.2E-08 2.9E-04

Mo-99 4E-05 1. 7E-04 3.0E-03 1.4E-03 N/D N/D 4.4E-04 Ag-110m 3E-05 3.9E-03 N/D N/D N/D N/D N/D Sn-113 8E-05 1.6E-04 5.9E-04 1.2E-03 N/D 1.1E-03 N/D Sb-124 2E-05 1.0E-02 2.0E-02 3.0E-02 1.2E-03 1.2E-01 4.6E-02 Sb-125 1E~04 1.0E-02 9.6E-02 3.6E-03 N/D 5.4E-02 5.9E-02 1-131 3E-07 1.3E-01 3.6E-02 4.2E-02 8.4E-02 1.2E-01 2.2E-01 1-133 1E-06 6.0E-03 5.4E-02 2.6E-02 1.2E-02 2.6E-03 1.SE-02 1-135 4E-06 N/D 1.6E-03 4.4E-04 N/D N/D N/D Cs-134 9E-06 5.1E-02 2.0E-02 2.6E-02 1. 8E-01 3.6E-01 3.5E-01 Cs-137 '2E-05 7.6E-02 3.6E-02 4.8E-02 2.3E-01 3.7E-01 3.3E-01 Ba-140 2E-05 N/D 9.8E-03 6.6E-03 N/D N/D N/D La-140 2E-05 6.7E-03 8.1E-02 3.0E-02 N/D 6.9E-04 N/D Total Ci 3.21 2.89 2.74 2.15 5.09 3.85 Ji_ 5.00E+OS 2.26E+05 2.24E+05 3.56E+05 5.20E+05 8.59E+05 MPCi MPCe (uCi/ml) 6.42E-06 1.28E-05 1.22E-05 6.04E-06 9.79E-06 4.49E-06

MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.

- N/D - not detected

A-5

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 Nb~95 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 Total Body 1.67E-02 *VOL b~ used:

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 = volume of liquid effluent released (gal)

Ci = total concentration of all radionuclides (uCi/ml) cw average circulating water discharge rate during release period (gal/min) 1.67E-02 = conversion factor (hr/min)

Substituting the value for the Fe-59 total body dose conversion factor, the equation simplified to:

Dtb =

1.21E+03 *VOL cw

L Ci (B.2)

Maximum Organ 1.67E-02 *VOL* A Nb-95,GI-LLI Dmax = ---------------------------

l:_ Ci . (8.3).

cw where:

Dmax = maximum organ dose (mrem)

A Nb-95,GI-LLI = 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 (B.4) cw B-3

Salem ODCM Rev. 4 05/17/88 Tritium is not included in the limited analysis dose asses~ment for liquid

releases, because the potential dose resulting from normal relatively negligible.

approximately 350 curies.

reactor releases is The average annual tritium release from each Salem Unit is 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

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 1se; Radio- Release TB GI-LLI Liver Release TB GI-UI Liver Release TB GI-LLI Liller ru:lide (Ci) Dose Dose Dose (Ci) Dose Dose Dose (Ci) Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac.

Fe-59 N/D * *

2.4a:-Cl3 0.01 0.02 O.Cl3 1.4a:-Cl3 0.01 0.04 0.04 Co-58 1.54E+OO 0.20 0.47 O.IE 2.22 0.25 0.42 0.10 6.6CE-a1 0.12 0.36 0.05 Co-60 4.22E-01 0.16 a.34 a.06 3.1CE-a1 0.10 0.07 0.04 6.SCE-a1 0.34 0.42 0. 15 As-mm 2.81E-Cl3

a.04

N/D * *

N/D * *

ltl-54 1.(1jE-Q1 a.a1 a.06 0.07 1.~-01 0.02 a.06 o.1a 8.71E-C2 a.C2 a.IE a.ca lb-9'.i 2.43E-Cl3

a.09

1.!D:-02

0.42

1.3CE-Cl3

a.09

Cs-137 3.01E-01 0.23

a.32 3.6CE-01 0.14 0.01 0.32 2.1CE-01 0.22

0.33 Cs-134 3.11E-01 0.40

0.46 3.4a:-a1 0.38

0.41 1.6CE-01 0.29

0.35 Cr-51 N/D * *

6.CXE-02 * *

3.6CE-C2 * *

Total 2.69800 3.SCE+OO 1.!D:+OO

less thlrl a.a1 N/D =rot detected

Table B-2 Ad.Jl t Dose c:art:rituti a"S Fish ird IrMrtebrate Patlwlys I.hit 2 1S87 1986 1<;85 Radio- Release TB GI-UI Liver Release TB GI-UI Liver Release TB GI-LL! Liver ru:l ide (Ci) Dose Dose Dose (Ci) Dose Dose Dose (Ci) Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac.

Fe-59 N/D * *

4.CXE-Cl3 a.02 a.Cl3 a.cs 1.1CE-Cl3 a.01 a.C2 a.C2 Co-58 1.71 0.32 0.44 a.13 3.32 a.32 0.44 a.13 8.4a:-01 0.14 a.23 0.06 Co-60 4.19E-01 0.10 a.06 a.04 3.!D:-a1 o.1a 0.06 0.04 6.3CE-01 a.30 a.21 a. 13 As-11Cm NJD * *

N/D * *

N/D * *

ltl-54 1.20E-01 0.02 a.cs a.10 2.20E-a1 0.02 a.cs 0.10 1.1CE-01 a.C2 0.05 0.09 6.63E-03 a.41 2.SCE-02

0.41

1.4a:-C2

0.48

lb-9'.i *

0.29 3.71'.E-01 0.20

0.29 2.3CE-01 a.23

a.33 Cs-137 3.31E-01 0.20

Cs-134 3.49E-a1 0.41

0."6 N/D * *

N/D * *

Cr-51 3.03E-Cl3 * *

9.SCE-02 * *

3.SCE-C2 * *

Total 2.94E+OO 4.77E+OO 2.04E+<Xl

less then 0.01 N/D = rot detected B-5

Salem ODCM Rev. 4 05/17/88

APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent

C-1

Salem ODCM Rev. 4 05/17/88 APPENDIX C Technical Bases for Eff~ctive Dose ractors

Gaseous Radioactive Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which 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:

Keff = (Ki

fi) (c. 1) wh e.r e:

Keff = the effective total body dose factor due to gamma emissions from all noble gases released Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released f i = the fractional abundance of noble gas radionuclide relative to the total noble gas activity CL+ 1.1 M)eff = ((Li + 1.1 Mi)

f i ) ( c. 2) where:

CL+ 1.1 M)eff = the effecti*ve skin dose factor due to beta and gamma e~issions from all noble gases released (Li. + 1. 1 Mi) = the skin dose factor due to beta a~d gamma emissions

from each noble gas radionuclide i released C-2

Salem ODCM Rev. 4 05/17/88 Meff = L (Mi

f i ) ( c. 3)

where:

Meff Mi

=

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) where:

Neff = the effective air dose factor due to beta emissions from *all noble gases released Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from 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 ~NSI N237*

1. 9 7 6 / ANS ~ 1 8

1 , 11 So u r c e Te r m S p e c i f i c a t i o n s , 11 has be e n us ed as r e pr e s e nt i ng 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:

D 3.17E*08

= --------

X/Q

Me ff

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

Neff * ~Qi ( 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 mo 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 (sec/m3)

Me ff = S.3E+02, effective gamma-air dose factor (mrad/yr per uCi/m3)

Neff = 1.1E+03, effective beta-air dose factor (mrad/yr per uCi/m3)

Qi - cumulative release for all noble gas radionuclides (uCi) 3.17E-08 = conversion factor (yr/sec) a.so = 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

Salem ODCM Rev. 4 05/17/88 Table C-1 Effective Dose Factors

Noble Gases - Total Body and Skin Total Body Effective Skin Effective Radionuclide* f.1

Dose Factor Dose Factor I( CL+ 1.1 M)eff 3 eff Cmrem/yr per uCi/m 3 ) Cmrem/yr per uCi/m )

IC r - 85 0. 0 1 1.4E+01 Kr - 88 0. 01 1.5E+02 1 .9E+02 Xe-133m 0. 01 2.5E+OO 1.4E+01 Xe-133 0.95 3.0E+02 6.6E+02 Xe-135 0.02 3.6E+01 7.9E+01 Total 4".8E+02 9.6E+02 Noble Gases - Air Gamma Air Effective Beta Air Effective Radionuclide f.1

Dose Factor Dose Factor "eff Neff 3 3 Cmrad/yr per uCi/m )

Cmrad/yr per uCi/m )

------

Kr-85 0. 01 2.0E+01 Kr - 88 0. 01 1.5E+02* 2.9E+01 Xe-133m 0. 01 3.3E+OO 1.5E+01 Xe-133 0.95 3.4E+02 1. OE+03 Xe-135 0.02 3.8E+01 4.9E+01 Total 5.3E+02 1.1E+03

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

C-5

Salem ODCM Rev. 4 05/17/88

APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent

D-1

Salem ODCM Rev. 4 05/17/88

APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide. This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3 For the infant age group, the controlling pathway is the grass-milk-cow (g/m/c) pathway. An infant receives a greater radiation dose from the g/m/c pathway than any other pathway. Of this g/m/c pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide 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 ac t i vi t y f or all r *a d i 6 n u c l i d e s ) by t hi s dos e c onve r s i on f ac t or pr ov i de s f or 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 hi s a pp r *o a c h , t he ma x i mum dos 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:

Dmax = 3.17E-8

W

Rl-131

Qi where:

Dmax = maximum organ dose (mrem)

w. = 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)

Qi = cumulative release over the period of interest for r~dioiodines and particulates 3.17E-8 = conversion factor (yr/sec>

Rl-131 = I - 131 dose parameter for the thyro~d for the identified controlling pathway

= 1.675E12 (m2 mrem/yr per uCi/sec), infant thyroid dose parameter with the cow-milk-grass pa~hway controlling The ground plane exposure and inhalation pathways need not be considered when the a b ov e s i mp l i f i e d c a l c u l a t i o n me t h o d is us e d be c a us e fo t he ove r a l l ne 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).

Th e l oc a t i on o f e x p o s u r e pa t h wa y s a n d t h e ma x i mu m o r g a n s o e c a l c u l a t i o n ma 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

Salem ODCM Rev. 4 05/17/88 Table D-1

InfaM~ Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass-Cow-Milk Ground Plane Total Body 0.02 0. 1 5 Liver 0.23 0. 1 4 Thyroid 0.59 0. 1 5 Kidney 0.02 0. 1 5 Lung 0. 0 1 0.02 Gl-LLI 0.02 0. 1 5

Fraction of Dose Contribution by Pathway Pathway f_

Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation *

D-4

Salem ODCM Rev. 4 05/17/88

Appendix E Radiological Environmental Monitoring Program Sample Type, Location and Analysis

E-5

Salem ODCM Rev. 4 5/17/!::!8

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -

SAMPLE TYPE, LOCATION AND ANALYSIS

E-1

Salem ODCM ~ev. 4 :>/17 /88.

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)

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 indica~es that this is sampling station il in that particular sector *

E-2

Salem ODCM Rev. 4 5/17/88

SAM~LING 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

Salem ODCM ~ev. 4 5/17/Sti

STATION CODE TABLE E-1. (Cont'd)

STATION .LOCATION 4.1 mi. NE of vent; local farm SAMPLE TYPES 3El fPB,fflV,GAM, IDM,VGT,WWA 3E~ 5.7 mi. NE of vent; local farm r'PV 7El 4.5 mi. SE of vent; l mi. W of Man Horse ESF,ESS,SWA Creek 9El 4.2 mi. S of vent IDM 11E2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. W of vent; local farm VGT 16El 4.1 mi. NNW of vent; Port Penn AIO,APT,IDM

lFl 1F2 1F3 5.8 mi. N of vent; Fort Elfsborg 7.1 mi. N of vent; midpoint of Delaware 5.9 mi. N of vent; local farm

~iver AIO,APT,IDM SWA FPL,FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO,APT,IDM, R.WA 2F3 8.0 mi. NNE of vent; Salem Water Company PWR, PWT 2F4 6.3 mi. NNE of vent; local farm FPV 2r'S 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training IDM Center 2F7 5.7 mi. NNE of vent; local farm M~K,VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge IDM Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM

5Fl 6.5 mi. E of vent FPV, IDM E-4

Salem ODCM Rev. 4 5/ l "7 /88

STATION CUDE 5F2 TABLE E-1 (Cont'd)

STATION LOCATION 7.0 mi. E of vent; local farm SAMPLE TYPES VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 11F3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT 12Fl 9.4 mi. WSW of vent; Townsend Elementary IDM School 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13r'3 9.3 mi. w of vent; Redding Middle School, IDM Middletown, Delaware

13F4 14Fl 14F2

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 IDM MLK,VGT IDM l4F3 5.4 mi. WNW of vent; local farm FPV 15F3 5.4 mi. NW of vent IlJM l6Fl 6.9 mi. NNW of vent; C&D Canal ES~,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public IDM School lGl 10.3 mi. of N of vent; local farm r'PV lG3 19 mi. N of vent; Wilmington, Delaware IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV 3Gl 17 mi. NE of vent; local farm IDM,MLK,VGT lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM

E-5

Salem ODCM Kev. 4 5/17/88

STATION CODE TABLE E-1 (Cont'd)

STATION LOCATION 15 mi. NNW of vent; Greater Wilmington SAMPLE TYPES IDM 16Gl Airport 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

Salem ODCM Rev. 4 5/17/88

Sample Air Particulate SAMPLE COLLECTION AND ANALYSIS Collection Method Continuous low volume Analysis Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change. 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.

Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on connected to air each weekly sample.

particulated air sampler and is collected weekly at filter change.

Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and frozen portion on collection semi-annually or when in season.

Sediment A sediment sample is Gamma isotopic taken semi-annually. analysis semi-annually.

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

Milk Sample of fresh milk Gamma isotopic is collected for each analysis and 1-131 farm semi-monthly when analysis on each cows are in. pasture, sample on collection.

monthly at other times

E-7

Salem ODCM Rev. 4 5/17/88

8ample SAMPLE COLLECTION AND ANALYSIS (Cont'd)

Collection Method Analysis Water (Rain,. Sample to be collected Gamma isotopic Potable, Surface) monthly providing winter monthly H-~ on icing conditions allow. quarterly surface sample, monthly on ground water sample *

E..:.8.

LOCATIONS

'

~

11F3

' Rev. 9 5/17/88

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