ML18096B319

Rev 8 to Salem Nuclear Generating Station Odcm.

ML18096B319
Person / Time
Site:	Salem
Issue date:	07/17/1992
From:	Paluzzi V Public Service Enterprise Group
To:
Shared Package
ML18096B317	List: ML18096B316 ML18096B318 ML18096B319
References
PROC-920717, NUDOCS 9303090326
Download: ML18096B319 (95)

Text

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SALEM NUCLEAR GENERA'rING' *sT.A'.ttlION

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OFFSITE O()SE CALCULAT.!'ON M$'UAL ,  :

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Salem ODCM Rev~ 8 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents Introduction . . . . -. - . . * . . . . . * *

• _ * ........ 1 1.0 Liquid Effluents Lt 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 L1quid Effluent Concentration Limits - 10 CFR 20 7 1.4 Liquid Effluent Dose Calculations - 10 CFR 50 . * . a 1.4.1 Member of the Public Dose - Liquid Effluents 8 1.4.2 Simplified Liquid Effluent Dose Calculation 10 1.5 Secondary Side Radioactive Liquid Effluents - Dose calculations During Primary to Secondary Leakage. . 11 1.6 Liquid Effluent Dose Projection * * * * * * . * . 13 I ,

2.0 Gaseous Effluents 2.1 Radiation Monitoring Instrumentation and Controls .

2.2 Gaseous Effluent Monitor Setpoint Determination . .

2.2.1 Containment and Plant Monitor 2.2.2 Conservative Default Values * * * * * . . .

2.3 Gaseous Effluent Instantaneous 15 17 17 19 Dose Rate Calculations - 10 CFR 20. * * * * * . 20 2.3.1 Site Boundary Dose Rate - Noble Gases. . 20

2. 3. 2 Site Boundary Dose Rate - .,

Radioiodine and Particulates * * * * * :i . . 21 2.4 Noble Gas Effluent Dose Calculations - 10 c::FRt,50 . . 24 2.4.1 UNRESTRICTED AREA Dose - Noble Gases * * . . 24 2.4.2 Simplified Dose Calculation for Noble Gases. 25 2.5 Radioiodine and Particulate Dose Calculations -

10 CFR 50. * * * * * * * * * * * * * * * * * . . . 26 2.5.1 UNRESTRICTED AREA Dose -

Radioiodine and Particulates * * * * * * . . 26 2.s.2 Simplified Dose Calculation for ~adioiodines and Particulates * * * * * * * * * * . . 27

-2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations * * * * * * * * * * * * . . . 28 2.7 Gaseous Effluent Dose Projection * * * * * * * . . 32 3.0 Special Dose Analyses 3.1 Doses Due To Activities Inside the SITE BOUNDARY. . 33 3.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 *

• 34

3. 2 .1 Effluent Dose Calculations * * * * -* . . 35 3.2.2 Direct Exposure Determination * * * * .

• 35 i

• Table of Contents - continued 4.0 Salem ODCM Radiological Environmental Monitoring Program. .

4.1 Sampling Program . . * . * . . * * * * * * .

Rev. 8

• .36

• 36 4.2 Interlaboratory Comparison Program * * . * . * *

• 37 Tables 1-1 Parameters for Liquid Alarm Setpoint Determination

- Unit 1 . . . . . . . . . . . . . . . . . . . . . 41 1-2 Parameters for Liquid Alarm Setpoint Determination

- Unit 2 . . . . . . . . . . . . . . . . . . . . . 42 1-3 Site Related Ingestion Dose Commitment Factors, Am * * * * * * * * * * * * * * * ~ ... 43-44 1-4 Bioaccumulation Factors (BFi) * * * * * * * . . . . 45 2-1 Dose Factors for Noble Gases * * * * * * * * . . . 48 2-2 Parameters for Gaseous Alarm Setpoint Determinations 2-3

- Unit 1 * * * * * * * ... * * * * * * * . * . . 49 Parameters for Gaseous Alarm Setpoint Determinations

- Unit 2 . . . . . . . . . . ._ . . . . .. . . . . . 50 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations * * * * * * . . . 51 2-5 Pathway Dose Parameters - Atmospheric Releases 52-63

• A-1 A-2 B-1 B-2 Calculation of Effective MPC - Unit 1 * . . . . . A-5 Calculation of Effective MPC - Unit 2 * * * * *

• A-6 Adult Dose Contributions Fish Pathways Unit 1 * * *

• and Drinking water

. . .and Adult Dose Contributions Fish

. .Drinking Water B-5 Pathways Unit 2 *.* * * * * * * * .* * * * * :_'r..

• B-5 C-5 Effective Dose Factors * * * * * * * * * * * ,, * . C-6 Appendices Appendix A - Evaluation of Conservative, .Default MPC Value for Liquid Effluents * * * * . . A-1 Appendix B - Technical Basis for Effective Dose Factors -

Liquid Radioactive Effluents * * * . . B-1 Appendix c - Technical Bases for Effective Dose Factors -

Gaseous Radioactive Effluents . . c-1

• • Appendix D - Radiological Environmental Monitoring Proqram - Sample Type, Location and Analysis * * * * * * * * * * * * * . D-1 ii

-. Salem ODCM SALEK NUCLEAR GENERATING STATION Rev. a OFFSITB DOSB CALCULATIOH MAHOAL Introduction The Salem Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in: 1) the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and 2) the calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and yearly doses. The methodology stated in this manual is acceptable for use in demonstrating compliance with 10 CFR 20.106, 10 CFR so, Appendix I and 40 CFR 190.

• More conservative calculation methods and/or conditions (e.g.,

location and/or exposure pathways) expected to yield higher computed doses than appropriate for the maximally exposed person may be assumed in the dose evaluations.

The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations. Changes will be made to the ODCM calculation methodoloqies and parameters as is deemed necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR S0.36a and Appendix I for demonstrating radi~active 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 ODCM Rev. 8 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> - l-Rl8 (Unit 1) and 2-Ris (Unit 2) provide the alarm and automatic termination of liquid radioactive material releases as requir~d by *

• Technical Specification 3.3.3.8.

1-Rl9 A,B,C,and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines. 2-R~9 A,B,C and D provide this function for Unit 2.

2) Alarm Conly> - The alarm functions for the Service ~ter 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 l and 2, respectively .

• 2

Salem ODCM Rev. 8 1.2 Liqui4 lffluent Monitor sotpoint Determination Per the requirements of Technical Specification 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of Specification 3.11.1.1 are met (i.e., the concentration- of radioactive material released in liquid effluents to UNRESTRICTED AREAS.shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides and 2.oE-04* uCi/ml for dissolved or entrained noble gases). The f ollowinq equation* must be satisfied to meet the liquid effluent restrictions:

• where:

cs C (F+f) f (1.1) c = the effluent concentration limit of ~chnical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml .

c = the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in 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, cs c. Also, note that when (F) is large compared to (f), then (F + f) = F.]

• Adapted from NUREG-0133 3

Salem ODCM Rev. a Liquid Effluent Monitors CRadwaste, steam Generator Blowdown. Chemical Waste Basin and service water. The setpoints for the liquid effluent monitors at the Salem Nuclear Generating station are determined by the following equations:

MPCe

• SEN

• CW SP S, + bkq (1. 2)

RR with:

l: Ci MPCe = ------ (1. 3)

Ci

• where:

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

MPCe = an effective MPC value for the mixture of *;:,

radionuclides in the effluent stream (uCi/mlL)

Ci = the concentration of radionuclide i in the undiluted liquid* effluents (uCi/ml)*

9NOTE: The concentration mix must include the most recent composite of alpha emitters, sr-89, sr-90, Fe-55, and H-3 per Technical Specification J.11.1.1.

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

SEN = the sensitivity value to which the monitor is calibrated (cpm per uCi/ml)

• cw = the circulating water flow rate (dilution water flow) at the time of release (qal/min)

RR = the liquid effluent release rate (qal/min) bkg = the backqround of the monitor (cpm)

• 4

• Salem ODCM Rev. a The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.

However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-1 or Unit-2 Circulating Water System discharge. This routing is possible via interconnections between the Service Water Systems (see Figures 1 and 2). 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. Conserv~tive 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 th,~.:

• -11 following:

a) substitution of the effective MPC value with a default value of 4.71E-06 uci/ml (Unit 1) and 3.38E-06 uci/ml (Unit 2). (refer to Appendix A for justification);

b) *or additional conservatism*, substit~tion of the I~131 MPC value of JE-07 uci/ml for the Ri9 steam Generator Slowdown Monitors, the R-37 Chemical waste Baain monitor and the R-13 Service Water Monitors.

• Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1, 2 R-19 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the R-13 Service Water

• Monitors

• s

-~

• • c) d)

Salem ODCM Rev. 8 substitutions of the operational circulating water flow with the lowest flow, in gal/min; and, 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 MPGe and for differing Circulating Water System dilutions

• The Unit 2 Service Water system utilizes the Unit 1 Circulating Water-* systb for dilution prior to release to the river. It is possible to have the Unit 1 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 3.JSE-06 uCi/ml is used in calculating the alarm setpoint (otherwise using 3E-07 uCi/ml would result in an alarm setpoint of 1 cpm) *

• 6

• 1.3 Salem ODCM Liquit lffluent concentration Limits - 10 CPR 20 Rev. a 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 than noble gases. Noble gases are limited to a diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded. However, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance

• • with the concentration limit's of Technical Specification 3.11.1.1 may be performed using the following equation:

Ci RR ~-

~

\~

E

• -~ 1 (1.4)

~~ cw + RR where:

Ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (~Ci/ml)

~~ =- the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml)

=- 2E-04 uCi/ml for dissolved or entrained noble gases RR = the actual liquid effluent release rate (gal/min) cw = the actual circulating water flow rate (dilution water flow) at the time of the release (gal/min)

• 7

Salem ODCM Rev. a

~* 1.4 Liqui4 lffluent Dose Calculation - 10 Cl'R so 1.4.1 MEMBER OP THE PUBLIC Dose - Liquid Effluents.

Technical Specific~tion 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:

- during any calendar quarter;

~ 105 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 shall be used for

• determining the dose or dose commitment due to the liquid radioactive effluents from Salem.

l.67E-02

• VOL

( 1. 9'l cw where:

dose or dose commitment to organ o (mrem). Total body dose can also be calculated using site- related total body dose commitment factor.

site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per uCi/ml) -

• average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL *

(uCi/ml)

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

1. 67E-02 = conversion factor (hr/min)

• • 8

• Salem ODCM Rev. 8 The site-related ingestion dose/dose commitment factors (Aw) are presented in Table 1-3 and have been derived in accordance with of NUREG-0133 by the equation:

( 1. 6) where:

Aw = composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathways (mrem/hr per uci/ml)

UI = adult invertebrate consumption (5 kg/yr)

Bii = bioaccumulation factor for radionuclide*i in invertebrates from Table 1-4 (pCi/kg per pCi/l)

UF = adult fish consumption (21 kg/yr)

BFi = bioaccumulation factor for radionuclide i in fish from Table 1-4 (pCi/kg per pCi/l) dose conversion factor for nuclide i for adults in pre~

selected organ, o, from Table E-11 of Regulatory Guide 1.109 (mrem/pCi) -

1.14E+05= conversion factor (pCi/uCi

• ml/kg per hr/yr)

The radionuclides included in the periodic dose assessmen~ per the requirements of Technical Specification 3/4.11.1.2 are.tho~e 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.

Radionuclid- requiring radiochemical analysis (e.g., Sr-89 and sr-

90) will be added to the dose analysts at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11-1 .

• • 9

• Salem ODCM 1.4.2 Simplified Liquid Effluent Dose Calculation.

Rev. a 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 D111 = (1.7) cw

~ Maximum Organ 2.52E+04

• VOL Dmu = (1. 8) cw where:

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

VOL = volwaa of liquid effluent released (gal) cw -~

average circulating water dischar9e r~te during release period (gal/min)

• Dlb o_ ----- conservatively evaluated total body dose (mrem) conservatively evaluated maximum organ dose (mrem)

1. 21E+03 = conversion factor (hr/min) and the conservative total body dose conversion factor (Fe-59, total body -- 7.27E+04 mrem/hr per uCi/ml) 2.52E+04 = conversion factor (hr/min) and the conservative maximum organ dose conversion factor (Nb-95, GI-LLI

-- 1.51E+06 mrem/hr per uCi/ml)

• 10

• Salem ODCM 1.s secondary Sid* Radioactive Liquid Effluents and Dose Calculat~ODI Qurinq Primary to Secondary Leakage Rev. 8 During periods of primary to secondary leakage (i.e., steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system. The potential exists for the release of radioactive material to the off-site environment (Delaware' River) via secondary system dischargeso Potentially significant radioactive material levels and potential releases are controlled/monitored by the Stea~ Generator blowdown monitors (Rl9) and the Chemical Waste Basin monitor (R37). However to ensure compliance with the regulatory limits on radioactive material releases, it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage. Any potentially significant releases will be via the Chemical Waste Basin with the major source of*~activity

. '((.

being the Steam Generator blowdown.

With identified radioactive material levels in the secondary system, appropriate samples should be collected and analyzed for the principal gamma emitting radionuclides~ Based on the identified radioactive material levels and the volume of water discharged, the resulting environmental doses may be calculated based on equation (1.5) .

• • 11

Salem ODCM Rev. a Because the release rate from the secondary system is indirect (e.g. , SG blowdown is normally routed to condenser where the condensate clean-up system will remove much of the radioactive material), samples should be collected from the final release point (i.e., Chemical Waste Basin) for quantifying the radioactive material releases. However, for conservatism and ease of controlling and quantifying all potential release paths, it is prudent to sample the SG blowdown and to assume all radioactive material is released directly to the environment via the Chemical waste Basin. This approach while not exact, is conservative and ensures timely analysis for regulatory compliance. Accounting for radioactive material retention of the condensate clean-up system

• ion exchange resins may be needed to more accurately account for actual releases *

• 12

Salem ODCM Rev. a 1.6 Liqui4 lffluent Dose Pro1ections Technical Specification 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the quarterly projected doses exceed:

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 requirements in accordance with Technical Specification 3.11.1.3. These processing requirements are applicable to each unit indiV'tidually.

• i.

Exceeding the projected dose requiring processing prior to release for one unit does not in itself dictate processing requirements for the other unit *

• • 13

-* Salem ODCM Dose projections are made at least once per 31 days following equations:

Rev. 8 by the Dtbp = Dlb (91 I d) (1. 9)

Dmaxp = Dmu (91 I d) ( 1. 10) where:

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

• Dtb = the total body dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) om.up = the maximum organ dose projection for current calendar quarter (mrem)

Dmu = the maximum organ dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) d = the number of days to date for current calendar quarter 91 = the number of days in a calendar quarter

• 14

• 2.0 2.1 Gas90u1 Bffluents Salem ODCM Radiation Monitoring Instrumentation and Controls Rev. a The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are summarized as follows:

1) Waste Gas Holdup System - The vent header gases are collected by the waste gas holdup 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.

l-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 l-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-Rl2A and 2-Rl2A may be used to provide the containment monitoring and automatic isolation function during purge. and pressu~e/vacuum reliefs.* *  :\:

?1

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

• The R12A monitors also provide the safety function of containment isolation in the event of a fuel handling accident during refueling. During MODE 6 in accordance with Technical Specification 3/4.3.3, Table 3.3-6, the R12A alarm/trip setpoint shall be established at twice background, 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 .

15

• 3)

Salem ODCM Rev. 8 Plant Vent Ccont'dl Rl6) 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 rotameter) .

Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 2-1 and 2-2 for Units 1 and 2, respectively .

• 16

• 2.2

2. 2. 1 Gaseoq1 Effluent Monitor setpoint Determination containment and Plant vent Monitor.

Salem ODCM Rev.

Per the requirements of a

Technical Specification 3.3.3.9, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin. Based on a grab sample analysis of the applicable release (i.e., grab sample of the Containment atmosphere, waste gas decay tank, or Plant Vent), the radiation monitoring alarm setpoints may be established by the following calculation method. The measured

. radionuclide concentrations and

• release rate are used to calculate the frac~ion of the allowable release rate, as limited by Specification J.11.2.1, by the equation:

FRAC = [ 4. 72E+02

• X/Q

• VF

• l: (Ci * ~) ] / 500 ( 2. 1)

FRAC = [4.72E+02

• X/Q *VF* I: {Ci*{~+ 1.1 ~))] / 3000 (2.2) where FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate .

X/Q = annual average meteorological dispersion 3to the controlling site boundary location {sec/m )

VF = ventilation system flow rate for the applicable release point and monitor (ft3 /min)

= concentration of noble gas radionuclide i as determine radioanalysis of grab sample {uCi/cm3)

= total body dose conversion factor 3 for noble gas radionuclide i (mrem/yr per uci/m from Table 2-1)

= beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 from Table 2-1)

• 17

• =

Salem ODCM gamma air dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 from Table 2-1) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad)

Rev. a 500 = total body dose rate limit (mrem/yr) 3000 = skin dose rate limit (mrem/yr) 4.72 E+02 = conversion factor (cm /ft3

• min/sec)

Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors (R16, R41C, and/or R12A) may be calculated by the equation:

SP = [AF

• I: Ci

• SEN / FRAC] + bkg ( 2. 3) where:

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

SEN = monitor sensitivity (cpm per uCi/cm3 )

bkg = background of the monitor (cpm)

AF = administrative allocation factor for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the release.

The allocation factor (AF) is an administrative control i~posed to

,...\;

ensure that combined releases from Salem Uni ts 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site {i.e., the release rate limits of Technical Specification 3.11.2.1). Normally, the combined AF value for Salem Units 1 and 2 is equal to o

• 5 ( o. 25 per unit) , with the

• remainder o. 5 allocated to Hope Creek. Any increase in AF above 0.5 for the Salem Nuclear Generating station will be coordinated with the Hope Creek Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0 *

• • 18

• 2.2.2 can be Cog1eryative Default Values.

established, in lieu of the Salem ODCM individual Rev. a A conservative alarm setpoint radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2 and 2-3 for Units 1 and 2, respectively. These values are based upon:

the maximum ventilation (or purge) flow rate; a radionuclide distribution* comprised of 95% Xe-133, 2%

Xe-135, 1% Xe-133m, 1% Kr-88 and 1% Kr-85; and

- an administrative allocation factor of 0.25 to.conservatively ensure that any simultaneous releases from Salem Units 1 and 2 do not exceed the maximum allowable release rate.

• For this radionuclide distribution, the alarm setpoint based oh 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 Specif_ications, Table 6

• 19

• 2.3 2.3.1 Boundary Dose Rate Salem ODCM GastOg* lffluent Instantaneous Dose Rate Calculations -

10 CD 20 sit* Noble Gases.

Rev. 8 Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to ~500 mrem/yr, total body and ~3000 mrem/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

( 2. 4) and D1 = X/Q

• l: ( (~ + 1.1~)

• Qi) (2. 5) where:

= total body dose rate (mrem/yr) .,

= skin dose rate (mrem/yr) _}

= atmospheric dispersion to3 the controlling SITE BOUNDARY location (sec/m )

= average release rate of radionuclide i over the release_ period under evaluation (uCi/sec)

= total body dose conversion factor for noble gas radionuclide i (mrem/yr per uci/m3 , from Table 2-1)

= beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 , :fro~ Table 2-1)

- q&J11Da air dose conversion factor for noble gas radionuclide i (mrad/yr per uci/m3 , from Table 2-1) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad)

As appropriate, simultaneous releases from sa_lem Units 1 and 2 and Hope creek will be considered in evaluating compliance with the releas*e rate limits of Specification 3 .11. 2. la, following any

• 20

• Salem ODCM release exceeding the above prescribed alarm setpoints.

Rev. a Monitor indications {readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. The 15 minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases. As identified, any 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.la. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of Specification 3.11.2.la.

.l:

Actual meteorological conditions concurrent with the relea~e period or the default, annual average dispersion parameters as presented in Table 2-4 may be used for evaluating the gaseous effluent dose rate.

Sit* Boundary Dose Rate - Radioiodine and Particulates.

Technical Specification 3.11.2.1.b limits the dose rate to ~1500 lives greater than 8 days. To demonstrate compliance with this

• 21

• Salem ODCM Rev. 8 limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g.,

nominally once per 7 days). The following equation shall be used for the dose rate evaluation:

(2. 6) where:

average organ dose rate over the sampling time period (mrem/yr)

X/Q = atmospheric dispersion to the controlling* SITE BOUNDARY location for the inhalation pathway (sec/m3 )

~o = dose parameter for radionuclide i (mrem/yr per uCi/m3 )

and organ o for the child inhalation pathway from Table 2-5 average release rate over the appropriate sampling period and analysis frequency for radionuclide i --

I-131, I-133, ttitium or other radionuclide in particulate form with half-life greater than 8 days (uCi/sec)

By substituting 1500 mrem/yr for D0 and solving for Qu an allowable release rate for I-131 can be determined. Based on th*. annual average meteorological dispersion (see Table 2-4) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid -- Rm= l.62E+07.mrem/yr per uCi/m3 ), the allowable release

• rate for I-131 is 42 uCi/sec. Reducing this:release rate by a factor of 4 to account for potential dose contributions from other radioactive particulate material and other release points (e.g.,

Hope Creek), the corresponding release rate allocated to each of

• 22

• the Sal.em units is 10.5 uCi/sec.

Salem ODCM Rev. s For a 7 day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 6.3 Ci. Therefore, as long as the I-131 releases in any 7 day period do not exceed 6. 3 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate *

• 23

• 2.4 trlfBISTRICTBD AREA Dose Salem ODCM Noble Gaa Effluent Dose Calculations - 10 CFR so Noble Gases.

Rev. 8 Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly* dose limits of ss mrad, gamma-air and SlO mrad, beta-air and the calendar year limits SlO mrad, gamma-air and s20 mrad, beta-air.

The limits are applicable separately to each unit and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses:

= 3.17E-08

• X/Q

• E {~ * ~) (2.7) and

• where:

=

= 3.17E-08

• X/Q

• E {~ * ~)

air dose due to gamma emissions for noble g*(\ls

( 2_. 8) radionuclides (mrad) ,,\:

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

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location {sec/m3) cumulative release of noble gas radionuclide i over the period of interest {uCi) where uci = {uci/cc} (cc released) or (uCi/sec) (sec released) air dose factor due to gamma emis~ions. from noble gas radionuclide i (mrad/yr per uCi/m3 , from Table 2-1) air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per uCi/m3 , Table 2-1) 3 .17E-08 = conversion factor (yr/sec)

• 24

• 2.4.2 Sipplifie4 Dose Calculation for Noble Gases.

Salem ODCM individual noble gas radionuclide dose assessment as presented Rev. 8 In lieu of the above, the following simplified dose calculation equations shall be used for verifying compliance with the dose limits of Technical Specification J.11.2.2. (Refer to Appendix c for the derivation and justification for this simplified method.)

J.17E-08 o, = (2. 9) 0.50 and J.17E-08

=

• X/Q

• Neff

• l: Qi (2 .10)

o. 50 v

where:

MetT = 5.JE+02, effective gamma-air dose factor (mrad/yr per uCi/m3 )

1. lE+OJ, effective beta-air dose factor ..(mrad/yr per uCi/m3 )  : 'l cumulative release for all noble gas radibnuclides (uCi) where uCi = * (uCi/cc) (cc released) or (uCi/sec) (sec released) 0.50 = conservatism factor to account for potential variability in the radionuclide distribution Actµal meteorological conditions concurrent witQ the, release period or the default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the gamma-air and beta-air doses *

• 25

Salem ODCM Rev. a

• .2.5 Radioiodin* and Particulate Dose Calculations - 10 CFR so 2.s.1 tJNBBSTBICTED AREA Dose - Radioiodine and Particulates.

In accordance with reqllirements of Technical Specification 3 .11. 2. 3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of ~7.5 mrem and calendar year limit ~15 mrem to any organ. The following equation shall be used to evaluate the maximum organ dose due to releases of I-131, tritium and particulates with half-lives greater than 8 days:

Daop = 3. l 7E-08

• W

• SFp * :t (Rq,

• Qi) (2.11) where:

Daop = dose or dose commitment via all pathways p and controlling age group a {as identified in Table 2-4) to organ *O, including the total body {mrem) w = atmospheric dispersion parameter to the controlling location{s) as ide~tified in Table 2-4

• X/Q D/Q

=

=

atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways {sec/m3)

• atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2 )

Ru,, = dose factor for radionuclide i {mrem/yr per ~i/m3 ) or

{m2 - mrem/yr per uCi/sec) and organ o from Table 2-s for each age group and the applicable pathway p as identified in Table 2-4. Values for Rm were derived in accordance with the methods described in NUREG-0133

= cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form with half-life g~eater than 8 days (uCi). - .

= 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)

= 0.5

2) For inhalation and ground plane exposure pathways:

= 1.0 26

• Salem ODCM For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway.

Rev. 8 Only the controlling age group as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3.

2.s.2 simplified Dose Calculation for Radioiodines and Particulates. In lieu of the individual radionuclide (I-131 and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of Technical Specification 3. 11. 2. 3 (refer to Appendix D for the derivation and justification of this simplified method).

Dmu = 3 . 17E-08

• W

• SFp

• Rr.131

• I: Qi ( 2. 12) where:

maximum organ dose (mrem)

I-131 dose parameter for the thyroid for the identified controlling pathway

= 1.05E+12, infant thyroid dose parameter with the cow-milk pathway controlling (m2 - mrem/y~ per uci/sec) ,Y D/Q for radioiodine, 2.lE-10 1/m2

• cumulative release over the period of interest for radionuclide I -- I-131 or radioactive material in particulate from with half life greater than a days (uCi)

The location of exposure pathways and the maximum organ dose

. :;i 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 .

• 27

• 2.6 secondary Calculations Side Radioactive Gaseous Salem ODCM Effluents Rev. 8 and Dose During periods of primary.to secondary leakage, minor levels of radioactive material may be released via the secondary system to the atmosphere. Non-condensables (e.g., noble gases) will be predominately released via the condenser evacuation system and will*

be monitored and quantified by the routine plant vent monitoring and sampling system and procedures (e.g., RlS on condenser evacuation, R41C on plant vent, and the plant vent particulate and charcoal samplers).

However, if the Steam Generator blowdown is routed directly to the

• Chemical Waste Basin (via the SG blowdown flash tank) instead of being recycled through the condenser, it may be desirable to account for the potential atmospheric releases of radioiodines and particulates from the flash tank vent (i.e., release~; due to t:

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-0133, tl}e releases of the radioiodinas and particulates shall be calculated by the equation:

(2.13) where:

Qi = the release rate of radionuclide, i, from the steam generator flash tank vent (uCi/sec)

• • 28

• Ci

~b =

=

Salem ODCM Rev. 8 the concentration of radionuclide, i, in the secondary coolant water averaged over not more than one week (uCi/ml) the steam generator blowdown rate to the flash tank (ml/sec)

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

• SQ!tv = the measured steam quality in the flash tank vent; or an assumed value of 0.85, based on NUREG-0017.

Tritium releases via the steam flashing may also be quantified using the above equation with the assumption of a steam quality (SQ1tv) equal to o. Since the H-3 will be associated with the water molecules, it is not necessary to account for the moisture carry-over which is the transport media for the radioiodines and particulates.

• Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam (Fft) is approximately o. 48. The equa~ion simplifies to the following:

(2 .14)

For H-3, the simplified equation is:

Also durinq reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs (PORV) and the safety

• 29

• Salem ODCM Rev. a reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust. The evaluation of the radioactive material concentration in the steam relative to that in the steam generator water is based on the guidance of NUREG-0017, Revision 1. The partitioning factors for the radioiodines is 0.01 and is 0.001 for all other particulate radioactive material. The resulting equation for quantifying releases via the atmospheric steam releases is:

(2 .16) where:

Qij = release rate of radionuclide i via pathway j {uCi/sec) cij = concentration of radionuclide i, in pathway j, (uCi/sec)

SFj = steam flow for.release pathway j

= 450,000 lb/hr per PORV .

= 800,000 lb/hr per safety relief valve

= 50,000 lb/hr for auxiliary feed pump exhaust PFi = partitioning factor, ratio of concentration in steam to that in the water in the steam generator

= 0.01 for radioiodines

= 0.005 for all other particulates

= 1. o for H-3 0.13= conversion factor - [(hr*ml) / (sec*lb)]

Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculation methods o~ the Salem Emergency Plan Implementation* Procedure .

• 30

-* Salem ODCM Rev. 8 Alternately, the quantification of the release rate and cumulative releases may be based on actual samples of main steam collected at the R4 6 sample locations. The measured radionuclide concentration in the steam may be used for quantifyinq the noble gases, radioiodine and particulate releases.

Note: The expected mode of operation would be to isolate the effected steam generator, thereby reducinq the potential releases durinq the 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 demonstratinq compliance with the Radioloqical Effluent Technical Specifications *

• 31

• 2.7 Gaseou* Bffluent Dose Proiection Salem ODCM Rev. 8 Technical Specification 3 .11. 2. 4 requires that the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the annual design objective rate in any calendar quarter, i.e., exceeding:

0.625 mrad/quarter, gamma air; 1.25 mrad/quarter, beta air; or 1.875 mrem/quarter, maximum organ.

The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation system (filtration systems # 1,2 and 3) and the Waste Gas Decay Tanks as delineated in Figures 2-3 and 2-4 *

• Dose projections are performed at least once per 31 days by. the following equations:

DIP = o, * (91 I d) (2.17)

Dtip = Db * (91 I d) (2 *:Ja>

Dmap = Dmu * (91 I d) (2 .19) where:

DIP = gamma air dose projection for current calendar quarter (mrad)

D, = gamma. air dose to date for current calendar quarter as determined by Equation 2.7 or ~.9 (mrem)

Dtip -- beta air dose projection for current calendar quarter

~ -

Dmup =

(mrad) beta air dose to date for current calendar quarter as determined by Equation 2.8 or 2.10 (mrem) maximum organ dose projection for current calendar quarter (mrem)

Dmu = maximum organ dose to date for current calendar quarter as determined by Equation 2.11 or 2.12 (mrem) d = number of days to date in current calendar quarter

• • 91 = number of days in a calendar quarter 32

• 3.0 3.1 Special Dose Analyses Salem ODCM Doses Due To Activities Inside the SITE BOUNDARY Rev. a In accordance with Technical Specification 6. 9 .1.11, the Radioactive Effluent Release Report (RERR) submitted within 60 days after January 1 of each year shall include an assessm,ent of radiation doses from radioactive liquid and qaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.

The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-4

• The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at .;the time

. l-of NRC reporting. However, a follow-up evaluation 'shall be performed when the data becomes available *

• • 33

• 3.2 Salem ODCM Total dose to MEMBERS OP THE PUBLIC - 40 CJ'R 190 Rev. a The Radioactive Effluent Release Report (RERR) submitted within 60 days after January 1 of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from. effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Nuclear Generating Station and the Hope creek Nuclear Generating Station: No other

• fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.

The dose contribution from the operation of Hope Creek,}Nuclear Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS ODCM).

As appropriate for demonstrating/evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure .

• 34

• 3. 2 .1 Bfflutnt Dost Calculations.

Salem ODCM Rev. a For purposes of implementing the surveillance requirements of Technical Specification 3/4.11.4 and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the Salem Nuclear Generating Station may be performed using the calculation methods contained within this .ODCM; the conservative controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.2) may be used. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.

l.2.2 Direct Exposure Dose Determination. Any potentially

• significant direct exposure contribution to. off-site individual doses may be evaluated based on the results of the environmental measurements (e.g., TLD, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation} method.

Only during atypical conditions will there exist any potential for significant on-site sources at Salem that wouid yield potentially significant off-site doses (i.e., in excess of 1 mrem per year to a MEMBER OP THE PUBLIC) , that would require detailed evaluation for demon*stratinC) compliance with 40 CFR 190. However, should a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculation techniques will be used for determination of dose for assessing 40 CFR 190 compliance .

• 35

• 4.0 Salem ODCM Radiological Environmental Monitoring Program Rev. 8 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of Appendix A Technical Specification 3.12. The objectives of the program are:

- To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; To determine if the operation of the 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 environmen~.

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

• uoTB: No public drinking water samples or irrigation water samples are taken as these pathways are not directly effected by liquid effluents discharged from Salem Generating Station *

• 36

• 4.2 InterlaJ2oratory comparison Program Salem ODCM Rev.

Technical Specification 3.12.3 requires analyses be performed on a

radioactive material supplied as part of an Interlaboratory Comparison. Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Proqram results.will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.10 *

• 37

RAOIATION MONITORING LIQUID RELEASES UNIT l FIGURE 1-1 u*-* c&£L

.I *~ *1 i::,

J. .. ..... Lr ..,.,.

• I

~ i * '*; ...

..~

~- ........ .-".:Jlfl& ,

dBftfu

-*----- '1 lo--

"IL"ll-w

-=wt '-- 111(111' J"" ..... r . . . . r &.1*r r-- ...... Ilk I* '* I*

. 1.,...

-m m-IDI

..." .. CllllUIMlll 111P1 1111111

_J *****---..

auau:aa

. ~,-:._...;

. *.~ *.

• RADIATION ~ONITORING *** LIQUID RELEASES UNIT 2 FIGURE 1-2 u,_ .. ~&.

I dl&Ma

• r..1, 1 ~

• .IL.'WI. ~

....* :JI._.. ...... J' Ha m -~ er .....

• r mlll'\.. .... -u&a'Tll*

w

.-m,_,..

~ .._

Bl"'

• tm

.... . r . . . . r ...., r-- -&..-

I* I* ** *I

• a I

.... -----

• P*

m-..

!Ml' lf**-**11

_J '

.. Cl&llJlllllll .... llllP

• llOTE: Evaporator p.cltage and/or 1'.aMste delltneraltierr s1ste11 1'0 *****

AC&:l..IULAl'Ull U11&1*a

• • r.:a.. U*IMl*M (lllC) 0 I

I I

I I --*... -

• • ac.* COO&.* ...

--- -*-- :I --

.... c ...................

ftg 1-l S.I*

a.....u.a """"'-*** W.ar i;,.,....,

IU FOi llFCNllATIOI aw a"'"" rt *11,

• Table 1-1 Salem ODCM Rev. 8 Parameters for Liquid Alarm Setpoint Determinations Unit 1 Parameter Actwl Defailt ~it* ec-nta Value Value MPC 0 calculated 4.71E-06

• uci/ml calculated for each batch to be released.

MPC I-131 3.0E-07 N/A uci/11l I-131 MPC conservatively used for SG blowdown and Service Water monitor set....,ints.

c, measured N/A uci/ml taken froia g1111111a spectral analysis of l fm.iid effluent.

14P(1 as det emi necl N/A uci/11l taken froia 10 CFR 20, Appendix B, Table II. Col 2.

Sen 1-R18 as determined 2.9E+07 Cplll per Radwaate Effluent (Cs-137) uci/*l 1-R19 2.9E+07 Ste.. Generator &lowdown ccs-137)

(A,B,C,D) 1-R13 (A) 1-R13 CB) 1-R13 (C,D,E) 5.62E+07 5.98E+07 1.01E+08 Service Water - Contai1111ent Fan Cooling ccs-137)

I cw BS deten1inecl 1.00E+OS 9PI circulating ...ter *sys.tern - single cw m..a .,

RR 1-R18 as detenained 120 aim detenained prior to n;l~ase:

release rate can be ad-justed for 1-R19 Technical Specification c~liance 1-R13 120 Ste.. Generator blowdown rate per Generator Service Water flow rate for 2500 Contai1111ent fan coolers Setpoint 1-R11 calculated 1.13E+05(+bkg) Cplll Default alana setpoints: more conser:vative*velues may be used as 1-R19 - 7.25E+03C+blcg) deenied appropriate and desiralbe for ensuring regulatory c~liance 1-R13 CA) .. 6.70E+02(+bkg) and for .. intaining releases ALARA.

1-R13 (B) ..., 7.10E+02(+blcg) 1-R13 (C,D,E)- 1.09E+03(+bkg)

• Refer to Appendix .A for derivation

• • The MPC*value of I-131 C3E-07 uci/ml) has been used for derivation of R19 Ste.. Generator blowdown and R13 Service Water monitor setpoints as discussed in Section 1.Z.Z 41

• Table 1-2 Parameters for Liquid Alarm setpoint Determinations Unit 2 Salem ODCM Rev. 8 Parameter Actual Default *units Conmen ts Value Value MPC0 calculated 3.38E-06

• uci/111l calculated for each batch to be released.

MPC 1*131 3.0E-07 N/A uci/ml 1*131 MPC conservatively used for SG blowdown, Service Water and Chemical Waste Basin monitor setnoints.

c. measured N/A uci/11l tak1n frCllll 98111111! spectral analysis of ll,.*id effluent.

MPC. as determined N/A uci /Ill taken frOll 10 CFR 20, Appendix B, Table II - Col. 2 Sen 2*R18 as determined 1.14E+08 cpnt/uc i /111l Redweate Effluent ccs-137) 2*R19CA,C) 1.26E+08 Ste.. Generator Blowdown (Cs-137) 2*R19(B) 1. 14E+08 2*R19(D) 1. 13E+08 2*R13 9.05E+07 Service Water

• Containnent Fan Cooling (Ca-137>

.,_ R37 1.24E+08 C!'e11ical Waste Basin discharge cw as determined 1.0E+05 gpm Circulating Water System, single CW

~ (Note: no CW ~ in service for 2R13 monitor* see section 1.2.2)

RR 2*R18 aa deten1i necl 120 9fm deten1inecl prior to r~ease: release rate can be adjusted.:lr Technical Specification Ccq:il i *: e

• 2*R19 120 Ste.. Generator Slowdown rate per Generator Service Weter flow rate for 2*R13 2500 Contairaent fan coolers R37 1200 Chemical Waste Baain discharge Setpoint 2-R1a calculated 3.20E5 C+bkg) Cpnl Default alarm setpoints: more conservative values may be used as 2-R19 - 2. 10E4 deellld appropriate and desirable for

• CA,B,C,aJ ensuring regulatory ccq:iliance and for

..intaining releases ALARA.

2*R13 " 3.05E2 (+bkg)

R37" 3. 10E3 (+bkg)

• Refer to Appendix A for derivation

• • The MPC value of 1*131 (3.0E-7 ucilml) has been used for derivation of the R13 and R37 monitor setpoints as discussed in Section 1.2.2

• • • 2R19A setpoint calc - SC-RM-002-08, 2R19B setpoint calc - SC-RM-002*09, 2R19C setpoint calc - SC*RM-002-10, 2R19D setpoint calc

• SC*RM-002-11.

42

Salem ODCM Rev. 8 Table 1-3 (cont'd)

Site Related Ingestion Dose Commitment Factors, Aio (mrem/hr per uCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Ru-103 1. 07E+2 4.60E+l 4.07E+2

1. 25E+4 Ru-105 8.89E+O 3.SlE+O l.15E+2 5.44E+3 Ru-106 l.59E+3 *2.01E+2 3.06E+3 1.03E+5 Rh-103m Rh-106 Ag-llOm 1. 56E+3 l.45E+3 8.60E+2 2.85E+3 5.91E+5 Sb-124 2.77E+2 5.23E+O l.10E+2 6.71E-l 2.15E+2 7.86E+3 Sb-125 1.77E+2 l.98E+O 4.21E+l l.SOE-1 1. 36E+2 1. 95E+3 Te-125m 2.17E+2 7.86E+l 2.91E+l 6.52E+l 8.82E+2 8.66E+2 Te-127m 5.48E+2 l.96E+2 6.68E+l 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+l 7.03E+2 Te-129m 9.31E+2 3.47E+2 L47E+2 3.20E+2 3.89E+3 4.69E+3 Te-129 2.54E+O 9.55E-1 6.19E-l 1. 95E+O l.07E+l 1. 92E+O Te-131m 1.40E+2 6.85E+l 5.71E+l 1. 08E+2 6.94E+2 6.80E+3 Te-131 1. 59E+O 6.66E-1 5.03E-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+l l.17E+2 4.61E+l 9.91E+3 1.82E+2 1. 01E+2 I-131 2.18E+2 3.12E+2 1.79E+2 l.02E+5 5.35E+2 8.23E+l

• '1:-132 1. 06E+l 2.85E+l 9.96E+O 9.96E+2 4.54E+l 5.35E+O I-133 7.45E+l l.30E+2 3.95E+l l.90E+4 2.26E+2 1.16E+2 I-134 5.56E+O 1.51E+l 5.40E+O 2.62E+2 2.40E+l 1. 32E-2 I-135 2.32E+l 6.0SE+l 2.24E+l 4.01E+3 9.75E+l 6.87E+l Cs-134 6.84E+3 1.63E+4 1. 33E+4 5.27E+3 1. 75E+J'.' 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2 .16E+z};- 3.21E+2 Cs-137 .8. 77E+3 1.20E+4 7.85E+3 4.07E+3 l.35E+3 2.32E+2 Cs-138 6.07E+O 1.20E+l 5.94E+O 8.81E+O 8.70E-1 5.12E-5 Ba-139 7.SSE+O 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1. 39E+l Ba-140 1.64E+3 2.06E+O l.08E+2 7.02E-1 l.18E+O 3.38E+3 Ba-141 3.SlE+O 2.SSE-3 1.29E-1 2.68E-3 1.63E-3 1. SOE-9

• Ba-142 1.72E+O 1.77E-3 1.0SE-1 1.50E~3 l;.OOE-3 2.43E-18 La-140 1.57E+O 7.94E-1 2.lOE-1 5.83E+4 La-142 8.06E-2 3.67E-2 9.13E-3 2.68E+2 Ce-141 j.43E+o 2.32E+O 2.63E-l 1. OSE+O 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1. 67E+4 Ce-144 l.79E+2 7.47E+l 9.59E+O 4.43E+l 6.04E+4

. Pr-143 5.79E+O 2.32E+O 2.87E-l 1.34E+O 2.54E+4 Pr-144 l.90E-2 7.87E-3 9.64E-4 4.44E-3 2.73E-9 Nd-147 3.96E+O 4.58E+O 2.74E-l 2.68E+O 2.20E+4 W-187 9.16E+O 7.66E+O 2.68E+O 2.51E+3

. *~p-239 3.53E-2 3.47E-3 1. 91E-3 1.0SE-2 7.11E+2 44

Salem ODCM Rev. a Table 1-4 Bioaccumulation Factors (BFi)

(pCi/kg per pCi/liter)*

Element Saltwater Fish Saltwater Invertebrate H 9.0E-01 9.3E-Ol c 1. 8E+03 1. 4E+03 Na 6.7E-02 l.9E-Ol 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 2.5E+02 Cu 6.7E+02 1. 7E+03 Zn 2.0E+03 5.0E+04 Br 1.5E-02 3.lE+OO Rb 8.3E+OO 1. 7E+Ol Sr 2.0E+OO 2.0E+Ol y 2.5E+Ol 1. OE+03 Zr 2.0E+02 8.0E+Ol Nb 3.0E+04 1. OE+02 Mo 1. OE+Ol l.OE+Ol Tc l.OE+Ol 5.0E+Ol Ru 3.0E+OO 1.0E+03 Rh 1.0E+Ol 2.0E+03 Ag 3.3E+03 3.3E+03 Sb 4.0E+Ol 5.4E+OO Te l.OE+Ol l.OE+02 I l.OE+Ol 5.0E+Ol Cs 4.0E+Ol 2. 5E+Q;l Ba 1. OE+Ol 1.0E+ot2 La 2.5E+Ol 1. OE+b3 Ce l.OE+Ol 6.0E+02 Pr 2.5E+Ol 1. OE+03 Nd 2.5E+Ol l.OE+03 w 3.0E+Ol 3.0E+Ol Np 1.0E+Ol l.OE+Ol Values in thia*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~

• • 45

tt

"!!l'

I . LE l[I I I*

I ll~ill I I 11 i I

I I

11I! i*

Ii

'\'

'_.~.

II I l-1 JlfBU I j AllO IOU-*I IO.f l

r--

-:-*- -~ . I

__ J

~1-rn~

r- -~

L - __-*-:_1_,

Salem ODCM Rev. 8

• Table 2-1 Dose Factors for Noble Gases Total Body Ganma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Radionuclide Ki Li Mi Ni Cmremtyr per uCi/m3) Cmremty_r per uCi/m3) Cmrad/yr per uCi/1113) Cmrad/yr per uCi/m3)

Kr-8311 7.56E-02 1.93E+01 2.88£+02 1Cr*85m 1. 17E+03 1.46E+03 1.23E+03 1.97E+03 Kr*85 1.61E+01 1.34E+03 1.ne+o1 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03£+04 Kr-88 1.47E+04 2.37E+03 1.52£+04 2.93£+03 Kr-89 1.66E+04 1.01E+04 1.73£+04 1.06E+04 Kr*90 1.56E+04 7.29E+03 1.63£+04 7.83E+03

• xe-131* 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133111 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe*133 2.94E+02 3.06E+02 3.53£+02 1.05£+03 Xe*13511 3.12E+03 7.11E+02 3.36E+03 7.39£+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4. 75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

• 48

Salem ODCM Rev. a

• Table 2-2 Parameters for Gaseous Alarm Setpoint Determinations Unit 1 Par-ter Actual Defailt lklit* ~t*

Value Value X/Q calculated 2.2E-06 sec/1l USNRC Salem Safety Evaluation. SUQ 3 VF (Plant Vent) as measured or 1.30E+OS ft 3 /min Plant Vent - normal fan curves operation (Cont Purge) 3.50E+04 Contairment Purcie AF coordinated 0.25 N/A Adninistrative allocation factor with HCGS to ensure conmined releases do not exceed release rate limit for site.

c. measured N/A uci /cm.,, Taken frOll gamna spectral analvsis of gaseous effluent Kt nuclide speci'fic N/A mretl!,}r per Values from Table 2-1 uci/

L, *nuclide specific N/A mr9{/r per Values from Table 2-1 uci/

Mi nuclide specific N/A mremt,;r per Values frOll Table 2-1 uci/

Sen 1-R41C

• as determined 6.42E+07 Cpl per Plant Vent ***

uci/cc '

1-R16 3.6E+07 Plant Vent (Redundant) 1-R12A 2.1E+06 Contairmenti'

• .. 1r:*

Setpoint 1-R41C calculated 1.14E+04 cpm Default alenil setpoint; more conservative values may be 1-R16 7.2E+04 (+bltg) used as deemed appropriate and desireable for ensuring 1-R12A ** 1.5E+04 (+bltg) regulatory compliance and maintaining releases ALARA *

• Based on - calibr*tion wfth mixture of radionucl ides

• • App.licable ufng Modes 1 through 5. During Mode 6 (refueling), monitor setpoint shall be reduced to 2Jl mckgr~ in accordance with Technical Specification Table 3.3-6

• • • 1R41C setpoint c*lcul*tion SC-RM-001-04

• • 49

Salem ODCM Rev. 8

• Table 2-3 Parameters for Gaseous Alarm Setpoint Determinations Unit 2 Par-ter Actual Default Units Conmen ts Value Value X/Q calculated 2.2E-6 sec/rrf Licensing Technical S.....,,ification value VF Plant Vent as measured or 1.30E+OS ft3/min Plant Vent - normal operation fan curves Cont. Purge 3.SOE+04 Containnent Purge AF coordinated with 0.25 N/A Ac:!J!inistretive allocation factor HCGS to ensure correined releases do not exceed release rate for site.

c. measured N/A Ut;f/ar Taken fra11 ga11111111 spectral aMlvsis of gaseous effluent Ki nuclide specific N/A mremt,;r per Values from Table 2*1

. Ut;i/

L1 nuclide specific N/A mremt,;r Ut;i/

per V*lues from Table 2*1 nuclide specific N/A mremt,;r per Values frOlll Table 2-1

• "' Ut;i/

Sen 2*R41C

• as ctetermi ned 6.73E+07 Cf:llll per Plant Vent ***

Ut;i/CC 2*R16 3.SE+07 Pl81'1t Vent (Redl.rdant) 2-R12A 4.43E+07 Contafrrnent -**

Setpoint 2*R41C calculated 1.14E+04 CPI Default alan11 setpoints; more conservative v~s may be used 2*R16 7.2E+04 (+bkg) as deemed appr "ate and desirable for ensuring regulatory 2-R12A ** 8.60E+04 (+bkg) c~liance and for maintaining releases ALARA.

• Based on me81'1 for c*l ibration with mixture of radionuclidea

• • Applicable m.-tna MODEi 1 through 5. During MCX>E 6 (refueling), 1110nftor setpoints shall be reduced to 2x b8ckgrCMld fn KCOrcMnc* l!lith Technical Specification 3.3-6.

• • • 2R12A sepafnt calcul*tfon SC*RM-002-03, 2R41C setpoint calcul*tion SC-RM-002-07

• so

Salem ODCM Rev. 8

• Table 2*4 Controlling Locations, Pathways ancl Atmospheric Dispersion for Dose Calculations

• Atmospheric Dispersion Technical Specification Location Pathway(s) Controlling ----------------------

X/Q D/Q Age Group (sec/rn3) ( 1/m2) 3.11.2.1a site bcxnlary noble gases N/A 2.2E*06 N/A (0.83 mile, N) direct exposure 3.11.2.1b site bou"tdary inhalation child 2.2E*06 N/A C0.83 *i le, N) 3.11.2.2 site bou"tdary ganma*air N/A 2.2E*06 N/A (0.83 mi le, N) beta* air 3.11.2.3 residence/dairy milk, grcx.rd infant 5.4E*08 2.1E*10 (4.9 miles, W) plane encl inhalation

• The identified controllfnt locations, pathways encl atmospheric dispersion are frOll the Safety Evaluation Report, Suppl-.it llo. 3 for tti. .. l* Nuclear Generating Station, Unft 2 (NUREG*0517, Decetimer 1978) .

• 51

Salem ODCM Rev. 8 Table 2-5 Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT (mrem/yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1. 26E+3 1. 26E+3 1.26E+3 1. 26E+3 1. 26E+3 1.26E+3 C-14 1. 82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1. 32E+6 7.71E+4 8.64E+4 5.01E+4 cr-51 5.95E+l 2.28E+l 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 l.18E+4 2.78E+4 l.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 l.06E+5 2.07E+3 Co-60 l.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 l.66E+4 5.90E+4 sr-89 3.04E+5 1.40E+6 3.SOE+S 8.72E+3 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6 Y-91 4.62E+5 1.70E+6 3.85E+5 1.24E+4 Zr-95 l.07E+5 3.44E+4 5.42E+4 l.77E+6 l.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 l.lOE+S 6.58E+2 Ru-106 6.91E+4 1. 34E+5 9.36E+6 9.l~E+S 8.72E+3

.'~.

Ag-llOm 1.08E+4 1.00E+4 1.97E+4 4.63E+6 3. ()2E+5 5.94E+J Sb-124 3.12E+4 5.89E+2 7.55E+l 2.48E+6 4.06E+5 1. 24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+l l.74E+6 l.01E+5 1. 26E+4 Te-125m 3.42E+J l.58E+3 l.05E+J l.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m l.26E+4 5.77E+3 3.29E+J 4.58E+4 9.60E+5 1. 50E+5 l.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 l.16E+6 3.83E+5 1.58E+3 I-131 2.52E+4 3.58E+4 l.19E+7 6.13E+4 6.28E+3 2.0SE+4 Cs-134 3.73E+S 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. lOE+S 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+l 1. 67E+l 1.27E+6 2.18E+5 2.57E+3 Ce-141 1. 99E+4 *i. 35E+4 6.26E+3 3.62E+5 1.20E+S 1. 53E+3 ce-144 3.43E+6 1. 43E+6 8.48E+5 7.78E+6 8.16E+S 1.84E+5 Pr-143 9.36E+J 3.75E+3 2.16E+3 2.81E+5 2.00E+S 4.64E+2 Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1. 73E+5 3.65E+2

• 52

. Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Inhalation Pathway Dose Factors - TEENAGER (mrem/yr per uCi/m3)

Nuclide Bone Liver Thyroid *Kidney Lung GI-LLI T.Body

. H-3 1. 27E+3 1. 27E+3 1. 27E+3 1.27E+3 1. 27E+3 l.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+l 3.07E+l 2.10E+4 3.00E+3 l.35E+2 Mn-54 5.11E+4 1. 27E+4 l.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 l.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 l.98E+4 Zn-65 3.86E+4 1. 34E+5 8.64E+4 l.24E+6 4.66E+4 6.24E+4 Rb-86 1. 90E+5 1.77E+4 8.40E+4 Sr-89 4.34E+5 2.42E+6 3.71E+5 1. 25E+4 sr-90 1.0SE+S

• 1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 2.* 94E+6 4.09E+5- l.77E+4 Zr-95 1.46E+S 4.58E+4 6.74E+4 2.69E+6 1. 49E+5 3.15E+4 Nb-95 1.86E+4 1. 03E+4 1. OOE+4 7.51E+5 9.68E+4 5.66E+3 Ru-103 2.10E+3 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 1.90E+5 1.61E+7 9. 6C)E+5 1. 24E+4 f.,.

• ~; ;*

Ag-llOm 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+l 3.85E+6 3.98E+5 1. 68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+l 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 l.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.0SE+5 2.25E+3 I-131 Cs-134 J.54E+4 5.02E+5 4.91E+4 1.13E+6

1. 46E+7 8.40E+4 - - 6.49E+3 2.64E+4 5.49E+5 3.75E+5 1.46E+5 9.76E+3 cs-136 5.15E+4 1.94E+S 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+l 2o28E+l 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 8.88E+3 6.14E+S 1. 26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 l.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1. 34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 53

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Inhalation Pathway Dose Factors - CHILD (mrem/yr per uCi/m3)

Nuclide Bone Liver. Thyroid Kidney Lung GI-LLI T.Body H-3 l.12E+3 1.12E+3 1.12E+3 1.12E+3 l.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3*

P-32 2.60E+6 l.14E+5 4.22E+4 9.88E+4 Cr-51 8.55E+l 2.43E+l 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 1.13.E+5 7.14E+4 9.95E+5 1. 63E+4 7.03E+4 Rb-86 l.98E+5 7.99E+3 1.14E+5 Sr-89 5.99E+5 2.16E+6 1. 67E+5 1. 72E+4

• sr-90 Y-91 Zr-95 Nb-95 Ru-103

1. OlE+S 9.14E+5 1.90E+5 2.35E+4 2.79E+3 4.18E+4 9.18E+3 5.96E+4 8.62E+3 7.03E+3 l.48E+7 2.63E+6 2.23E+6 6.14E+5 6.62E+5 3.43E+5 l.84E+5 6.llE+4 3.70E+4 4.48E+4 6.44E+6 2.44E+4 3.70E+4 6.55E+3 1.07E+3 Ru-106 1. 36E+5 l.84E+5 1. 43E+7 4. 2;~~+5 1. 69E+4 Ag-llOm l.69E+4 1.14E+4 2.12E+4 5.48E+6 l.OOE+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.lOE+l 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 5.0JE+4 l.76E+6 l.82E+5 3.04E+3 I-131 Cs-134 4.81E+4 4.81E+4 6.51E+5 l.01E+6

1. 62E+7 7.88E+4 3.30E+5

- 2.84E+3 l.21E+5 3.85E+3 2.73E+4 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 l.04E+5 3.62E+3 1. 28E+5 Ba-140 7.40E+4 6.48E-H 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 l.08E+4 8.73E+3 4.81E+3 3.28E+5 8. 21E+4 6.81E+2 54

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R ( io) , Inhalation Pathway Dose Factors - INFANT (mrem/yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 P-32 2.03E+6 l.12E+5 1. 61E+4 7.74E+4 cr-51 5.75E+l 1. 32E+l 1.28E+4 3.57E+2 8.95E+l Mn-54 2.53E+4 4.98E+3 l.OOE+6 7.06E+3 4.98E+3 Fe-55 1. 97E+4 l.17E+4 8.69E+4 1. 09E+3 3.33E+3 Fe=59 1. 36E+4 2.35E+4 l.02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 Co-58 1. 22E+3 7.77E+5 l.11E+4 1. 82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 l.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 ZlT-65 1. 93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3.11E+4 Rb-86 1. 90E+5 3.04E+3 8.82E+4 Sr-89 3.98E+5 2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 1.12E+7 1. 31E+5 2.59E+6 Y-91 5.88E+5 2.45E+6 7.03E+4 1. 57E+4 Zr-95 1.15E+5 2.79E+4 3.11E+4 1. 75E+6 2.17E+4 2.03E+4 Nb-95 1. 57E+4 6.43E+3 4.72E+3 4.79E+S 1.27E+4 3.78E+3 Ru-103 2.02E+3 4.24E+3 5.52E+S 1. 61E+4 6.79E+2 Ru-106 8.68E+4 1.07E+S 1.16E+7 1. 6iE+5 1. 09E+4

• .. t -~.

-'.l Ag-llOm 9.98E+3 7.22E+3 1. 09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 2.65E+6 5.91E+4 1. 20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+l 1.64E+6 1. 47E+4 l.09E+4 Te-125m 4.76E+3 1.99E+3 1. 62E+3 4.47E+5 1. 29E+4 6.58E+2.

Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1. 31E+6 2.73E+4 2.07E+3 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 I-131 cs;-134 3.79E+4 l.96E+5 4.44E+4 7.03E+5 l.48E+7 5.18E+4 -

1.90E+5 7.97E+4 l.06E+3

1. 33E+3

1. 96E+4 7.45E+4 Cs-136 4.83E+4 1.35E+5 5.64E+4 1.18E+4 1. 43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 1. 72E+S 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+l 1. 34E+l 1.60E+6 3.84E+4 2.90E+3 ce-141 2.77E+4 1.67E+4 5.25E+3 5.17E+S 2.16E+4 1. 99E+3 Ce-14.4 3.19E+6 1. 21E+6 5.38E+S 9.84E+6 1. 48E+5 1. 76E+5 Pr-143 1. 40E+4 5.24E+3 l.97E+3 4.33E+S 3.72E+4 6.99E+2 3.22E+S 3.12E+4 5.00E+2 Nd-147 7.94E+3 8.13E+3 3.15E+3 55

~ ~;:;

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Grass-cow-Milk Pathway Dose Factors - ADULT (mrem/y~ per uCi/m3) for H-3 and C-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lunq GI-LLI T.Body H-3 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1. 71E+l0 1. 06E+9 1. 92E+9 6.60E+8 Cr-51 1. 71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 8.40E+6 2.50E+6 2.57E+7 l.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 l.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 2.59E+9 5.11E+8 1.21E+9 sr-89 1.45E+9 2.33E+8 4.16E+7

• sr-90 4.68E+10 1. 35E+9 l.15E+10 Y-91 8.60E+3 4.73E+6 2.30E+2 Zr-95 9.46E+2 3. 03.E+2 4.76E+2 9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 4.54E+4 2.79E+8 2.47E+4 Ru-103 1.02E+3 3.89E+3 1*.19E+5 4.39E+2 RU-106 2.04E+4 3.94E+4 1. 3'2E+6

{'

2.58E+3

,_'li:

Aq-llOm 5.83E+7 5.39E+7 l*06E+8 2.2t>E+l0 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.00E+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 l.17E+7 1.86E+8 1.54E+8 S.58E+6 Te-129m 6.04B+7 2.25E+7

• 2.08E+7 2.52E+8 3.04E+8 9.57E+6 I-131 2'.96B+8 4.24E+8 l.39E+ll 7.27E+8 1.12E+8 2.43E+S Cs-134 5.65B+9 1.34E+10 4.35E+9 1.44E+9 2.35E+8 1.lOE+lO Cs=136 2.61E+8 1.03E+9 5.74E+8 7.87E+7 l.17E+8 7.42E+8 Cs-137 7.38E+9 1.0lE+lO 3.43E+9 1.14E+9 1. 95E+8 6.61E+9 Ba-140

• 2. 69E+7 3.38E+4 1.15E+4 1.93E+4 5.54E+7 l.76E+6 Ce-141 4.84E+3 3.27E+3 l.52E+3 1.25E+7 3.71E+2 Ce-144 3.58E+5 l.50E+5 8.87E+4 1.21E+8 1. 92E+4 Pr-143 1.59E+2 6.37E+l 3.68E+l 6.96E+S 7.88E+O

• Nd-147 9.42E+l l.09E+2 6.37E+l 5.23E+5 6.52E+O 56

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Grass-cow-Milk Pathway Dose Factors - TEENAGER (mrem/yr per uCi/m3) for H-3 and C-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1. 34E+5 1. 34E+5 1. 34E+5 1. 34E+5 1. 34E+5 1. 34E+5 P-32 3.15E+10 l.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 l.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 6.61E+10 1.86E+9 1.63E+l0 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 ..

1.80:E+6

• l*

4.73E+3

~g-llOm 9.63E+7 9.11E+7 1. 74E+8 2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.lOE+S 1.00E+7 Te-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 4.15E+8 1. 75E+7 I-131 5.38E+8 7.53E+8 2.20E+ll 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+l0 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+l0 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 1. 35E+4 2.79E+3 1.69E+7 6.81E+2 Ce-144 6.58E+5 2.72E+5 1. 63E+5 1. 66E+8 3.54E+4 Pr-143 1.17E+2 6.77E+l 9.61E+5 1.45E+l 2.92E+2 Nd-147 1. 81E+2 1.97E+2 l.16E+2 7.llE+S 1.18E+l 57

~

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Grass-cow-Milk Pathway Dose Factors - CHILD (mrem/yr per uCi/m3) for H-3 and c-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.57E+3 1. 57E+3 1.57E+3 1.57E+3 1. 57E+3 1. 57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+S 3.29E+S P-32 7.77E+10 3.64E+9 2.15E+9 3.00E+9 cr-51 5.66E+4 1. 55E+4 1.c53E+5 5.41E+6 1. 02E+5 Mn-54 2.09E+7 5.87E+6 1. 76E+7 5.58E+6 Fe-55 1.12E+8 5.93E+7 3.35E+7 1.10E+7 1. 84E+7 Fe-59 1. 20E+8 1. 95E+8 5.65E+7 2.0JE+S 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. lOE+lO 6.94E+9 1. 93E+9 6.85E+9 Rb-86 8.77E+9 5.64E+8 5.39E+9 sr-89 6.62E+9 2.56E+8 l.89E+8 Sr-90 1.12E+ll 1.51E+9 2.83E+10 Y-91 3.91E+4 5.21E+6 l.04E+3 Zr-95 3.84E+3 8.45E+2 1.21E+3 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+5 2.29E+8 8.84E+4 Ru-103 4.29E+3 1.08E+4 1.11E+5 -1. 65E+3 Ru-106 9.24E+4 1.25E+5 1.44E+6 l.15E+4 Aq-llOm 2.09E+8 1.41E+8 2.63E+8 1.68E+10 l.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 2.0SE+8 1. 82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 7. l;,~E+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 l.31E+9 4.34E+ll 2.15E+9 1.17E+8 7.46E+8 Cs-134 2.26E+10 3.71E+10 1.lSE+lO 4.13E+9 2.00E+8 7. 83E+9 .

cs-136 1.00E+9 2.76E+9 l.47E+9 2.19E+8 9.70E+7 1. 79E+9 Cs-137 3.22E+l0 3.09E+10 1.0lE+lO 3.62E+9 1. 93E+8 4.SSE+9 Ba-140 l.17E+8 l.03E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 l.09E+4 4.78E+3 l.36E+7 l.62E+3 Ce-144 1.62E+6 5.09E+5 2.82E+S 1. 33E+8 S.66E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+l Nd-147 4.45E+2 3.60E+2 l.98E+2 5.71E+S 2.79E+l

• 58

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem/yr per uCi/m3) for H-3 and C-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 ~.89E+5 6.89E+5 6.89E+5 P-32 1.60E+ll 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 l.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 J.49E+10 2.16E+9 1.07E+8 1. 21E+9 Zn-65 5.SSE+9 1.90E+10 9.23E+9 1.61E+10 8.78E+9 Rb-86 2.22E+10 5.69E+8 1.lOE+lO sr-89 1. 26E+10 2.59E+8 3.61E+8 Sr-90 1.22E+ll 1.52E+9 3.lOE+lO Y-91 7.33E+4 5.26E+6 1. 95E+3 Zr-95 6.83E+3 1.66E+3 1.79E+3 8.28E+5 l.18E+3 Nb-95 5.93E+5 2.44E+5 1.75E+5 2.06E+8 1.41E+5 Ru-103 8.69E+3 1.81E+4 1.06E+5 2.91E+3 Ru-106 1.90E+5 2.25E+5 1.44E+6 2.38E+4 Aq-llOm Sb-124 3.86E+8 2.82E+8 2.09E+8 3.08E+6 5.56E+5

- 4.03E+8

1. 31E+8 1.46E+10 1. 86E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1. 9*~E+8 3.07E+7 Te-125m 1. 51E+8 5. 04E+7 . 5. 07E+7 7. i:a\E+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 1.05E+12 3.75E+9 1.15E+8 1. 41E+9 Cs-134 3.65E+10 6.SOE+lO 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136. 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.lSE+lO 6.02E+10 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+5 5.73E+4 l.48E+5 5.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 8.15E+3 " - 1.37E+7 3.11E+3 Ce-144 2".33E+6 .9.52E+5 3.85E+5 1.33E+8 1. 30E+5 Pr-143 1.49E+3 '*5. 59E+2 2.08E+2 7.89E+5 7.41E+l Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+l

• • 59

Salem ODCM Rev. a Table 2-5 (cont'd)

R(io), Vegetation Pathway Dose Factors - ADULT (mrem/yr per uCi/m3) for H-3 and C-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body 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+S 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 1.50E+8 3.49E+8 Zn-65 3.17E+8 1. 01E+9 6.75E+8 6.36E+8 4.56E+8 Rb-86 2.19E+8 4.32E+7 1.02E+8 sr-s9 9.96E+9 1. 60E+9 2.86E+8 sr-90 6.05E+ll 1.75E+10 1.48E+ll Y-91 5.13E+6 2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 5.97E+5 1.21E+9 2.58E+5 Nb-95 1.42E+5 7.91E+4 7.81E+4 4.80E+8 4.25E+4 Ru-103 4.80E+6 1.83E+7 5.61E+8 2.07E+6 Ru-106 1.93E+8 3.72E+8 1.25E+10 2.44E+7 Ag-llOm 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 l.05E+8 1.SOE+9. 3.25E+7 Te-125m 9.66E+7 3.SOE+7 2.90E+7 3.93E+8 3. 8.iE+S 1. 29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.11£+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 1. 2'8E+9 4.03E+7

!~131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.0SE+7 6.63E+7 Cs-134 4.66E+9 1.llE+lO 3.59E+9 1.19E+9 1.94E+8 9.07E+9 cs-136 4.20E+7 1.66E+8 9.24E+7 l..27E+7 l.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+S 1.33E+5 6.17E+4 5.08E+8 1. 51E+4 Ce-144 3.29E+7 1. 38E+7 8.16E+6 1. llE+lO 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

• 60

Salem ODCM Rev. a Table 2-5 (cont'd)

R(io), Vegetation Pathway Dose Factors - TEENAGER (mrem/yr per uci/m3) for H-3 and C-14 (m2

• mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1. 45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 l.61E+9 9.96E+7 l.35E+8 6.23E+7 Cr-51 3.44E+4 1. 36E+4 8.85E+4 1. 04E+7 6.20E+4 Mn-54 4.52E+8 1. J5E+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 l.81E+8 4*. 22E+8 l.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 l.OlE+S 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 l.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+l0 1. 80E+9 4.33E+8 Sr-90 7.51E+ll 2.llE+lO l.85E+ll Y:-91 7.87E+6 3.23E+9 2.11E+5 Zr-95 1. 74E+6 5.49E+5 w 8.07E+5 1.27E+9 3.78E+5

• Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125in

1. 92E+5 l.06E+5 6.87E+6 3.09E+8 1.52E+7 1.44E+7

1. 55E+8 2.85E+6 3.51E+5 2.14E+8 2.34E+6 2.04E+5

1. 03E+5 2.42E+7 5.97E+8 2.74E+7 1.35E+8 1.88E+8 4.55E+8 5.86E+4 5.74E+8 2.94E+6 1.48E+l0 3.90E+7 4.04E+9 8.74E+6 3.11E+9 6.03E+7 l".66E+9 5.00E+7 1.48E+8 5.34E+7 4.14E+7 4. 3*~E+8 1. 98E+7 Te-127m 5.51E+8 1.96E+8 l.31E+8 2.24E+9 1. :l'i'E+9 6.56E+7 Te-129m 3.67E+8 l.36E+8 1.18E+8 L54E+9 1. 3'sE+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 2.0SE+S 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. OlE+lO 1. 35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 l.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 Pr-143 S.27E+7 2.18E+7 7.12E+4 2.84E+4

1. 30E+7 1.65E+4

- - 1. 33E+l0 2.83E+6 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3

• 61

Salem ODCM Rev. 8 Table 2-5 (cont'd)

R(io), Vegetation Pathway Dose Factors - CHILD (mrem/yr per uCi/m3) for H-3 and C-14 (m2

• mrem/yr per uci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 4.01E+3 4.01E+'3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7*01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 9.30E+7 1. 30E+8 cr-51 6.54E+4 1.79E+4 1 .* 19E+5 6.25E+6 l.18E+5 Mn-54 6.61E+8 l.85E+8 5.55E+8 1. 76E+8 Fe-55 8.00E+8 4.24E+8 2.40E+8 7.86E+7 1. 31E+8 Fe-59 4.0lE+S 6.49E+8 1.88E+8 6. 7.6E+8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1. 98E+8 Co-60 3.78E+8 2.10E+9 l.12E+9 Ni-63 3.95E+l0 2.11E+9 l.42E+8 1. 34E+9 Zn-65 8.12E+8 2.16E+9 1. 36E+9 3.80E+8 1. 35E+9 Rb-86 sr-89 3.59E+10 4.52E+8 - 2.91E+7 2.78E+8

1. 39E+9 1. 03E+9 Sr-90 1.24E+12 1.67E+10 3.15E+ll Y-91 1. 87E+7 2.49E+9 5.01E+5 zr-95 3.90E+6 8.58E+5 1.23E+6 8.95E+8 7.64E+5 Nb-95 4.10E+5 1.59E+5 1.50E+S 2.95E+8 l.14E+5 Ru-103 l.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Ag-llOm 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 l.96E+8 2.20E+9 1. 23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 2.78E+8 1.19E+9 1. 05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 3. 3*~E+8 4.67E+7 Te-127m 1. 32E+9 3.56E+8 3.16E+8 3.77E+9 1. 0, 'E+9 1. 57E+8

~.!

Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 1.04E+9 1. 33E+8 I-131 1.43E+8 l.44E+8 4.76E+10 2.36E+8 1. 28E+7 8.18E+7 Cs-134 1.60E+l0 2.63E+10 8.14E+9 2.92E+9 1. 42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 l.18E+8 l.76E+7 7.79E+6 l.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 l.62E+7 Ce-141 6.53E+5 3.26E+5 1.43E+S 4.07E+8 4.84E+4 ce-144 1.27E+8 3.98E+7 2.21E+7 - 1. 04E+l0 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

• 62

Salem ODCM Rev. 8 Table 2-s (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-Sl 4.68E+6 Mn-S4 1. 34E+9 Fe-SS Fe-S9 2.7SE+8 Co-S8 3.82E+8 Co-60 2.16E+10 Ni-63 Zn-6S 7.4SE+8 Rb-86 8.98E+6 sr-89 2.16E+4 Sr-90 Y-91 1.08E+6 Zr-9S 2.48E+8

• Nb-9S

• 1. 36E+8 Ru-103 1.09E+8 Ru-106 4.21E+8 Ag-llOm 3.47E+9 Te-12Sm 1.SSE+6 Te-127m Te-i29m 9.17E+4 2.00E+7

. ~ ! ~.

I-131 1. 72E+7 Cs-134 6.75E+9 cs-136 1.49E+8 cs-137 1.04E+10 Ba-140 2.0SE+7 ce-141 1. 36E+7 Ce-144 6.95E+7 Pr-143 Nd-147 8.40E+6

• 63

APPENDIX A Evaluation of Default MPC Value for Liquid Effluents

• Salem ODCM Rev. 8

. Appendix A Evaluation of Default MPC Value for Liquid Effluents In accordance with the requirements of Technical Specification {3.3.3.8) the radioactive liquid effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive

• material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2. The determination of allowable radionuclide concentration and correspondinq alarm setpoint is a function of the individual radionuclide distribution and corresponding

• MPC values.

In order to limit the need for routinely havinq t~ reestablish the alarm setpoints as a function of changinq radionuclide di~,hibutions, 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:

• A-2

• Salem ODCM Rev. 8 E C1 (qamma emitters only)

MPCe = -----------------------------

Ci (qamma) Ci (non-qamma).

(A. l)

E ----------- + ~ ---------------

where:

MPCe = an effective MPC value for a mixture of radionuclide (uCi/ml)

Ci = concentration of radionuclide i in the mixture MPCi = the 10 CFR 20, Appendix. B, Table II, Column 2 MPC value for radionuclide i (uCi/ml)

The equation for determining the liquid effluent setpoints ( Section 1.2.1, equation 1.2 ) is ba~d on a multiplication of the effective MPC

• times the monitor sensitivity. However, the *radiation monitors on the effluent lines will not detect non-gamma emitting radionuclides, such as H-3, Fe-SS, and sr-90. The derivation of the effective_MPC ( section 1.2.1, equation 1.3 ) is valid for any distribution but mu~t be modified to account for the fact that the effluent monitor will not detect the non-gammas. The above modified equation for the effective MPC provides for a default setpoint determination that accounts for the non-gamma emitting radionuclides *

• A-3

• Salem ODCM Rev. 8 Considering the average effective MPC value for the years 1988 through 1990, it is reasonable to select an MPCe value of 4.71E-06 uCi/ml for Unit 1 and 3.38E-06 uci/ml for Unit 2 as tYi:>ical of liquid radwaste discharges. Using these values to calculate the default Rl8 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-4

• Table A-1 Calculation of Effective MPC Salem Unit 1 Salem ODCM Rev. 8 Activity Released (Ci)

Nuclide MPC' 1988 -1989 1990 TOTAL CuCi/ml) CURIES CURIES CURIES CURIES Na-24 3E-05 1.38E-02 4.69E-04 1.69E-03 1.60E-02 Cr-51 2E-03 2.38E-02 5.25E-03 1.16£-02 4.06£-02 Mn-54 1E-04 1.01E-01 1.12E-01 1.52E-01 3.65E-01 Fe-59 5E-05 2.66E-04 1.32E-03 1.15E-03 2.73E-03 Co-57 4E-04 4.01E-03 6.11E-03 7.54E-03 1.77E-02 Co-58 9E-05 1.27E+OO 1.82E+OO 1.98E+OO 5.07E+OO Co-60 3E-05 2.77E-01 1. 78E-01 2.39E-01 6.94E-01 Zr-95 6£-05 1.23E-02 1.53E-03 4.52E-03 1.84E-02 Nb-95 1E-04 1.53E-02 3.85E-03 9. 76E-03 2.89£-02 Nb-97 9E-04 2.44E-02 7.94E-05 6.30E-03 3.0SE-02 Tc-99m 3E-03 4.74E-03 4.62E-04 8.53E-04 6.05E-03 Sr-89 3E-06 1.25E-02 1.54E-03 2.38E-03 1.64E-02 Sr-90 3E-07 2.40E-03 6.68E-04 4.66£-04 3.53E-03 Mo-99 4E-05 1.57E-03 N/0 N/D 1.57E-03 Ag-110ni 3E-05 4.96E-03 2.70E-03 8.40E-04 8.50E-03 Sn-113 BE-05 N/D N/D N/D N/D Sb-124 2E-05 6.32E-02 1.36E-02 1.94E-02 9.62E-02 Sb-125 1E-04 9.35E-02 6.53E-02 6.09£-02 2.20E-01 1-131 3E-07 5.54E-02 3.04E-02 3.53E-02 1.21E-01 1-133 1E-06 2.SOE-02 6.88E-03 8.36E-03 4.32E-02 1-134 2E-5 1.10E-02 N/D N/D 1.10E-02 1-135 4E-06 1.68E-02 1.94E-04 1.42E-04 1. 71E-02 Ce-144 1E-05 1.89E-02 1. 19E-04 1.69E-04 1.92E-02.

Cs-134 9E-06 1.31E-01 1.16E-01 1.91E-01 4.38E-01 Cs-136 6£-05 9.31E-05 9.79E-04 1.21E-03 2.28E-03 Cs-137 2E-05 1.34E-01 1.28E-01 2.02E-01 4.64E-01 Ba-140 2E-05 2.79£-04 N/D 1.10E-04 3.89E-04 La-140 2E-05 3.89£-04 2.66E-04 5.35E-04 1.19E-03 H-3 3E-03 6.34E+02 6.08E+02 3.53E+02 1.59E+03 Fe-55 SE-04 5.40E-01 1. 75E-01 1.61E-01 8.76E-01 ~

W-187 6£-05 1.25E-02 N/D N/D 1.25E-02 . 'ii.

Zn-65 1E-04 5.49E-04 3.62E-04 7.75E-03 8.66E-03 ~:

Zr-97 2E-05 1.37E-02 N/D N/D 1.37E-02 Total C. G1111111a 2.33E+OO 2.49E+OO 2.94E+OO 7.77E+OO Total C. Non-ganma 6.35E+02 6.08E+02 3.53E+02 1.60E+03 MPC, CUCi/111l) 4.71E-06 6.88E-06 9.45E-06 MPC value for 111r..tricted are* from 10 CFR 20, Appendix B, Table II, CotU111 2. *

• • N/D - not detected

• A-5

d Salem ODCM Rev. 8 Table A-2 Calculation of Effective MPC Salem Unit 2 Activity Released (Ci)

MPC 1988 1989 1990 TOTAL Nuclide CuCi/ml) CURIES CURIES CURIES CURIES Na-24 3E-05

1. 04E-02 8.0SE-04 2.28E-03 1.3SE-02 Cr-51 2E-03 3. 1'7E-03 1.57E-02 1.48E-02 3.37E-02 Mn-54 1E-04 1. 74E-01 1.19E-01 1.52E-01 4.4SE-01 Fe-59 5E-05 2.93E-05 3.00E-03 1.09E-03 4. 12E-03 Co-57 4E-04 4.55E-03 6.70E-03 7.92E-03 1.92E-02 Co-58 9E-05 1.32E+OO 2.02E+OO 2.01E+OO S.35E+OO Co-60 3E-05 2.97E-01 2.08E-01 2.36E-01 7.41E-01

. Zr-95 6E-05 3.1SE-03 3.39E-03 5.22E-03 1.18E-02 Nb-95 1E-04 6.55E-03 7.41E-03 1.03E-02 2.42E-02 Nb-97 9E*04 6.92E-03 2.54E-04 5.32E-04 7.71E*03 Tc-99m 3E-03 3.28E-03 6.64E-04 8.66E-04 4.81E*03 Sr-89 3E-06 1.69E*02 1.52E*03 2.28E-03 2.07E-02 Sr-90 3E-07 4.11E-03 6.45E-04 4.73E*04 5.23E-03 Mo-99 4E*OS 1.19E*04 N/D N/D 1.19E-04 Ag*110m 3E*05 1.04E*02 6.41E*03 2.56E-03 1.94E*02 Sn-113 8E*OS N/D N/D N/D N/D Sb-124 2E*OS 5.47E-02 1.89E*02 2.22E*02 9.58E-02 Sb-125 1E*04 9.22E*02 8.0SE-02 7.40E*02 2.47E-01 1*131 3E*07 1.3SE*01 3. 79E-02 3.83E*02 2.11E*01 1-133 1E*06 8.83E*02 8.64E*03 1.07E-02 1.0SE-01 I *134 2E*05 3.49E*02 N/D N/D 3.49£-02 I-135 4E*06 1.90E*02 5.17E-04 7.09E-04 2.02E*02 Ce-144 1E*OS 2.24E*03 6.05E*04 7.67E-05 2.92E*03 Cs-134 9E-06 9.53E*02 1.43E*01 1.86E-01 4.24E*01 Cs-136 6E*OS 2.20E*03 1.39E*03 1.31E*03 4.90E-03 Cs-137 2E*OS 1.09E*01 1.55E*01 1.95E*01 4.59E-01 Ba-140 2E*OS 1.57E*03 N/D N/D 1.57E-03 La-140 2E*OS 1.03E*03 5.19E*04 6.23E*04 2.17E-03 H*3 3E-03 3.68E+02 5.02E+02 3.03E+02 1.17E+03 Fe-55 SE-04 4.69E-01 1.84E*01 2.09E-01 8.62E*01 W*187 6E-05 6.37E-04 N/D N/D 6.37E-04 ....;

Zn-65 1E-04 11/D 1.41E*04 1.06E*02 1.07E-02 . t:.

Total Ci G&1111111 2.48E+OO 2.84E+OO 2.98E+OO 8.30E+OO Total Ci Non-gamna 3.68E+02 5.02E+02 3.03E+02 1.17E+03 MPC0 (uCi /ml) 3.38E-06 7.85E*06 9.71E-06 MPC value for ...,restricted ere* from 10 CFR 20, Appendix B, Table II, Colllll'I 2.

• • N/D - not detected

• • A-6

• Salem ODCM Rev. 8 APPENDIX B Technical Basis for Effective Dose Factors Liquid Radioactive Effluent

• B-1

• APPENDIX B Salem ODCM Technical Basis for Effective Dose Factors -

Liquid Effluent Releases Rev. 8 The radioactive liquid effluents for the years 1982 through 1989 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. For the last three years the calculated GI-LLI dose is predominately a function of the Fe-55, co-58, Co-60 and

• Nb-95 releases. The radionuclides, Co-58 and cs-134 contribute the large majority of the calculated total body dose. The results of the evaluation for 1989, 1988, and 1987 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 radi'onuclides) 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

• B-2

• Salem ODCM Rev. 8 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 ddse 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. For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may be used:

Total Body 1.67E-02 '* VOL Dtb = cw

• A Fe-59,TB * (B .1)

• where:

Dlb A Fe-59,TB

=

=

dose to the total body {mrem) 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 simplifies to:

.1.21B+03

• VOL cw * (B.2)

• B-3

• Maximum organ Salem ODCM Rev. 8 l.67E-02

• VOL *A Nb-95,GI-LLI Dmu = --------------------------- * (B.3) where:

Dmax = maximum organ dose (mrem)

A Nb-95,GI-LLI = 1.51E+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem/hr per uCi/ml)

Substituting the value for A Nb-95,GI-LLI the equation simplifies to:

2.52E+04

• VOL Dmax - * (B. 4) cw Tritium is not included in the limited analysis dose assessment for liquid releases, be~ause the potential dose resulting fro~ normal

.. \;.

reactor releases is relatively negligible. The average annual tritium release from each Salem Unit is approximately 350 curies.

The calculated total body dose from such a release is 2.4E-03 mrem/yr via the fish and invertebrate ingestion pathways. This amounts to 0.08% of the design objective dose of 3 mrem/yr.

Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation .

• B-4

Salem ODCM Rev. 8 Table B-1 Adult Dose Contributions Fi sh. and Invertebrate Pathways Unit 1 1989 1988 1987 Radio* RELEASE TBOOY GI-LLI LIVER RELEASE TBODY GI-LLI LIVER RELEASE TBOOY Gl-LLI LIVER nuclide (Ci) Dose Dose Dose (Ci) Dose Dose Dose (Ci) Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac MN-54 1.12E-01 0.06.

0.03 0.11 1.01E-01 0.01 0.03 0.03 1.05E-01 a.a1 a.a5 a.a4 FE-55 3.98E-a2 a.as a.a2 a.19 5.44E-01 a.43 a.11 0.76 2.35E-01 a. 16 a.11 a.43 FE-59 1.32E-a3 a.a2 a.a2 a.a3 2.66E-04 * *

• N/D * *

• C0-58 1.82E+OO a.39 a.56 a.16 1.27E+aO a. 11 a.24 a.a3 1.54E+OO a.17 a.42 a.as C0-60 1. 78E-01 a.11 0.15 a.a4 2..77E-01 a. 10 0.14 0.02 4.21E-01 0. 13 a.31 a.a4 ZN-65 3.62E-a4 a.a1

• a.a2 5.49E-a4 a.a1

• a.01 N/D * *

• NB-95 3.8SE-03

• a. 15

• 1.53E-02

• a.36

• 2.44E-a3

• a.a8

• AG-110M 2.7aE-a3

• a.04

• 4.96E-03

• o.os

• 2.36E-03

• a.o3

• CS* 134 1.16E-01 0.24

• a.25 1.31E-01 0.17

• 0.08 3.11E-01 0.34

• a.26 CS-137 1.28E-a1 a.16

• a.21 1.34E-a1 a.10

• a.a6 3.a1E-01 a.19

• a.19 Total 2.4aE+aO 2.48E+OO 2.92E+OO Table i-2 Adult Dose Contributions Fish and Invertebrate Pathways Unit 2 1989 1988 1987 ISOTOPE RELEASE TBOOY GI-LLI LIVER RELEASE TBOOY Gl*LLI LIVER RELEASE TBOOY GI -LLI LIVER (Ci) Dose Dose Dose (Ci) Dose Dose Dose (Ci) Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac.

MN-54 1.19E-01 0.02 0.05 o.a9 1.74E-01 0.03 0.07 0.06 1.20E-01 o.a1 a.04 a.a2 FE-55 4.61E-02 0.05 0.02 0.18 4.69E-01 0.42 0.16 0.75 8.74E*01 0.39 0.26 a.72 FE-59 3.00E-03 0.03 0.04 0.06 2.93E-05 * *

• N/D * * **

C0-58 2.02E+OO 0.37 0.47 a.14 1.32E+OO 0.19 0.29 0.04 1. 71E+OO -0.12 0.31 a.a2 C0-60 2.08E-01 . 0.11 0.13 0.04 2.97E-01 a.12 0.18 0.02 4.23E-01 .. 'i}.a9 0.21 o.a2 ZN-6S 1.41E-04 *

• a.01 N/D * *

• N/D .~ . * *

• NB-95 7.41E-03

• a.22

• 6.55E-03

• 0.18

• 7.92E-03

• o. 18 AG-110M 6.41E-03

• 0.07

• 1.a4E-02

• 0.11

• N/D * * **

CS-134 1.43E-01 0.25

• 0.26 9.53E-02 0. 14

• 0.07 3.49E-01 0.25

• 0.13 CS-137 1.55E-01 0.16

• 0.21 1.09E-01. 0.09

• 0.06 3.33E-01 o. 14

• o.a9 Total 2.71E+OO 2.48E+OO 3.82E+OO

• less than 0.01 N/D = not detected

• B-5

Salem OOCM Rev. 8 APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent

~.'*

• c-1

Salem OOCM Rev. 8

• overview APPENDIX C Technical Bases for Effective Dose Factors -

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

- * (C.1) where:

= the effective total body dose factor due to gamma emissions from all noble gases released

= the total body dose factor due to gamma emissions from each noble gas radionuclide i released

= the fractional abundance of noble gas radionuclide i relative to the total noble gas activity

• • c-2

Salem OOCM Rev. 8

• (C. 2) where:

(L + 1.1 M)eff =*the effective skin dose factor due to beta and gamma emissions from all noble gases released

(~ + 1.1 ~) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released (C. 3) where:

MctJ = 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 (C. 4) where:

= the effective air dose factor due to beta emissions from all noble gases released

= the air dose factor due to beta emissi~ns f~pm 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* 2,000 Ci for 1984, C-3

Salem ODCM Rev. 8

• 2,800 Ci for 1985, 2,700 Ci for 1986, 1700 Ci for 1988, and 1500 Ci for 1989. Therefore, in order to provids a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, "Source Term Specifications," has been used as representing a typical distribution. The effective dose factors as derived are presented in Table C-1.

Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservat~sm provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment. For evaluating compliance with:the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:

3.17B-08 Di: = --------

o.so

• X/Q

• M.:tr * :E Qi (C. 5) and 3.17E-08

~ = --------

o.so

• X/Q

• Neff

• :E Qi (C. 6)

• C-4

Salem ODCM Rev. 8

• where:

Dg = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)

Db air dose due to beta emissions for the cumulative releas.e of all noble gases (mrad)

X/Q = atmospheric dispersion to the controlling site boundary (sec/m3)

Melf = 5.3E+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}

0.50 = conservatism factor to account for the variability in the effluent data Combining the constant~, the dose calculational equations simplify to:

DI = 3.SE-05 and

• X/Q

• E Qi (C. 7)

= 7.0E-05

• X/Q

• E Qi *~JC. 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 malfunction where a detailed dose assessment may be unavailable .

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• Table C-1 Effective Dose Factors Noble Gases - Total Body and Skin Total Body Effective SkinEffective Radionuclide Dose Factor Dose Factor K.tr ( L+ 1. 1 M) etr (mrem/yr per uCi/m3 ) (mrem/yr per uCi/m3 )

Kr-85 0.01 l.4E+Ol Kr-88 0.01 l.5E+02 l.9E+02 Xe-133m 0.01 2.5E+OO l.4E+Ol Xe-133 0.95 3.0E+02 6.6E+02 Xe-135 0.02 3.6E+Ol 7.9E+Ol Total 4.8E+02 9.6E+02 Noble Gases - Air Gamma Air Effective Beta Air Effective Radionuclide Dose Factor Dose Factor M.tr Neff (mrad/yr per uCi/~) (mrad/yr per -uci/m3 )

Kr-85 0.01 2.0E+Ol Kr-88 0.01 l.5E+02 2.9E+Ol Xe-133m 0.01 3.3E+OO 1. SE+Ol Xe-133 0.95 3 . .4E+02 1. OE+03 Xe-135 0.02 3.8E+Ol 4 :;9E+Ol Total 5.3E+02 1. 1E+03

• Based on Noble gas distribution from ANSI N237-1976/ANSI-18.l, "Source Term Specifications."

C-6

Salem ODCM Rev. 8 APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent D-1

Salem ODCM Rev. 8

• APPENDIX D Technical Basis for* Effective Dose Parameter Gaseous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide. This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3 For the infant age group, the controlling pathway is the grass-milk-cow (g/m/c) pathway. An infant receives a greater radiation dose from the g/m/c pathway than any other pathway. Of this g/m/c pathway, the maximum exposed organ including the total

• body, is the thyroid, and the highest dose contributor is radionuclide I-131.

in Table D-1.

The results for this evaluation are presented For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. Multiplication of the total release (i.e. cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative .

• D-2

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• 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 (1.05E12 m2 mrem/yr per uCi/sec). By this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used:

• where:

Dmax w

Dmu:

=

=

= 3.17E-8

• W

• RI-131 maximum organ.dose (mrem)

• E Qi atmospheric dispersion parameters to the

• controlling location(s) as identified~~n Table 3.2-4. ,

X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3 )

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

Qi = cumulative release over the period of interest for radioiodines and particulates 3.17E-8 = conversion factor (yr/sec)

RI-131 = I-131 dose parameter for the thyroid for the identified controlling pathway

= 1.05E12 (m2 mrem/yr per uCi/sec), infant thyroid dose parameter with the cow-milk=grass pathway controlling The ground plane exposure and inhalation pathways need not be

., considered when the above simplified calculation method is used because for the overall negligible contribution of these pathways to D-3

Salem ODCM Rev. 3

• the total thyroid dose. It is recognized that for some particulate radioiodines (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will ma~imize 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)

• The location of exposur~ pathways and the maximum organ so 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 *

• D-4

Salem OOCM Rev. 8

• Table D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass-Cow-Milk Ground Plane Total Body 0.02 0.15 Liver 0.23 0.14 Thyroid 0.59 0.15 Kidney 0.02 0.15 Lung 0.01 0.02 GI-LLI 0.02 0.15 Fraction of Dose Contribution .Q:l Pathway Pathway Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation *

• D-5

Salem ODCM Rev. 8 APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis

\:

• E-1

Salem ODCM Rev. 3

• APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.

AIO = Air Iodine IDM = Immersion Dose (TLD)

APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)

ESF = Edible Fish PWT = Potable Water (Treated)

ESS = Sediment RWA = Rain Water (Precipitation)

FPB = Beef SWA = 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 radical distance from the plant:

s =

A =

on.:..site location 0-1 miles off-site E

F

=

=

4-5 miles off-site 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-si~e c = 2-3 miles off-site H = > 20 miles off-sit.

D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, ... For example; the designation SA-WWA-501 would indicate a sample in the SGS program (SA),

consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the.reactor site at a radical distance of 3 to 4 miles off-site; (therefore, radial distance D). The number 1 indicated that this is sampling station #1 in that particular sector .

• E-2

Salem ODCM Rev. 3

• SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E. Maps E-1 and E-2 show the locations of sampling stations with respect to the site.

TABLE E-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent IDM 3S3 700 ft. NNE of vent; fresh water WWA holding tank 5Sl 1.0 mi. E of vent; site access road AIO, APT, IDM 6S2 0.2 mi. ESE of vent; observation IDM building 7SI 0.12 mi. SE of vent; station personnel IDM gate

• lOSl llSl llAl 0.14 mi. SSW of vent; site shoreline.

0.09 mi. SW of vent; site shoreline 0.2 mi. W of vent; outfall area IDM IDM ECH, ESF, ESS, SWA **

'te.

15Al 0.3 mi. NW of vent; cooling tower ESS blowdown discharge line 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12Cl. 2.5 mi. WSW of vent; west bank of ECH, ESF, ESS Delaware River SWA 4D2 3.7 mi. ENE of vent; Alloway Creek IDM Neck Road 5Dl 3.5 mi. E of vent; local farm AIO, APT, IDM, WWA lODl 3.9 mi. SSW of vent; Taylor's Bridge IDM Spur

• E-3

Salem ODCM ~ev. 3

• TABLE E-1 (Cont'd)

STATION CODE STATION LOCATION SAMPLE TYPES llDl 3.5 mi. SW of vent GAM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM 3El 4.1 mi. NE of vent; local FPB, FPV, GAM, IDM, VGT, WWA 3F2 5.7 mi. NE of vent; local farm FPV 7El 4.5 mi. SE of vent; 1 mi. W of Mad. ESF, ESS, SWA Horse Creek 9El 5.0 mi. SW of vent IDM 11E2 5.0 mi. SW of vent IDM 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 VGT '*

1*

16El 4.1 mi. NNW of vent; Port Penn AIO, APT, IDM lFl 5.8 mi. N of vent; Fort Elf sborg AIO, APT, IDM 1F2 7.1 mi. N of vent; midpoint of SWA Delaware 1F3 5. 9' mi. N of vent; local farm FPL, FPV 2F2 8.7:mi. NNE of vent; Salem Substation AIO, APT, IDM, RWA 2F3 8.0 mi. NNE of vent; local farm FPV 2F4 6.3 mi. NNE of vent; local FPV 2F5 7.5 mi. NNE of vent; Salem High School IDM

• • E-4

Salem ODCM Rev. 8 TABLE E-1 (Cont'd)

• STATION CODE 2F6 STATION LOCATION 7.3 mi. NNE of vent; Southern Training center SAMPLE TYPES IDM 2F7 5.7 mi. NNE of vent; local farm MLK, VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge IDM Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township IDM School 5Fl 6.5 mi. E of vent FPV,IDM 5F2 7.0 mi. E of vent; local farm VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F~ 9.1 mi. SE of vent; Bayside, NJ IDM 10F2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge IDM Delaware 11F3 5.3 mi. SW of vent; Townsend, DE MLK, VGT 12Fl 9.4 mi. WSW of vent; Townsend Elem. IDM' School 13F2 6.5 mi. W of vent; Odessa, DE 13F3 9.3 mi. W of vent; Redding Middle IDM School, Middletown, DE 13F4 9.8 mi. W of vent; Middletown, DE IDM 14Fl 5.5 mi. WNW of vent; local farm VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 14F4 7.6 mi. WNW of vent; local farm MLK 15F3 5.4 mi. NW of vent IDM

• E-5 *I I

I i

.Salem ODCM Rev. 8

'-* STATION CODE TABLB B-1 (Cont'd)

STATION LOCATION SAMPLE TYPES 16Fl 6.9 mi. NNW of vent; C&D Canal ESS, SWA 16F2 8.1 mi. NNW of vent; Delaware City IDM Public School lGl 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, DE IDM 2Gl 12 mi. NNE of vent; Mannington FPV Township, NJ 3Gl 17 mi. NE of vent; local farm IDM, MLK, VGT lOGl 12 mi. SSW of vent; Smyrna, DE IDM 16Gl 15 mi. NNW of vent; Greater Wilminqton IDM Airport

• 3Hl 3H3 3H5 32 mi. NE of vent; National Park, NJ 110 mi. NE of vent; Research and Testing 25 mi. NE of vent; local farm IDM AIO, APT, IDM FPL,. FPV

Salem_ OOCM Rev. 8

• Sample SAMPLES COLLECTION AND ANALYSIS Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change. be performed if gross beta exceeds 10 times the yearly mean of the control station value. As well one sample is analyzed > 24 hrs after sampling to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly composites.

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

particulated air sampler and is collected weekly

• at filter change.

Crab and Fish Two batch samples are Gamma *isotopj_..Ct:

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.

-* E-7

Salem ODCM Rev. 8

• Sample SAMPLE COLLECTION AND ANALYSIS (Cont'd)

Collection Method Analysis Milk Sample of fresh milk Gamma isotopic is collected for each analysis and I-131 farm semi-monthly when analysis on each cows are in pasture,

• sample on collection.

monthly at other times.

Water (Rain, Sample to be collected Gamma isotopic Potable, monthly providinq winter monthly H-3 onsurf ace) icinq conditions allow. quarterly surface sample, monthly on qround water sample .

....~.

• • E-8