Text

Rev 2 to Offsite Dose Calculation Manual.
	ML18092B445
Person / Time
Site:	Salem
Issue date:	02/26/1987
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18092B443	List: ML18092B442; ML18092B444; ML18092B445;
References
	PROC-870226, NUDOCS 8703030705
	Download: ML18092B445 (128)
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SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Revision 2 02/26/87 8703030705 870227 PDR ADOCI-<. 05000272 p PDR

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SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents Introduction ........... ........ 1 1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls*. * * * * *

2 1.2 Liquid Effluent Monitor Setpoint Determination * * * * * * *

3 1.2.1 Liquid Effluent Monitors <Radwaste. Steam Generator Slowdown and Service ~ater) * * * * * * * * * * *

4 1.2.2 Conservative Default Values * * * * * * * * * * * * * *

5 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 5 1.4 Liquid Effluent Dose Calculations - 10 CFR 50 * *

7 1.4.1 Member of the Public Dose - Liquid Effluents 7 1.4.2 Simplified Liquid Effluent Dose Calculation 8 1.5 Secondary Side Radioactive Liquid Effluents -

Dose Calculations During Primary to'Secondary Leakage *

10 1.6 Liquid Effluent Dose Projection * * * * * * * * * * *

12 2.0 Gaseous Effluents 2.1 Radiation Monitoring Instrumentation and Controls * *

13 2.2 Gaseous Effluent Monitor Setpoint Determination

15 15 2.2.1 Containment and Plant Monitor 2.2.2 Conservative Default Values *

c. * * * .... 16 2.3 Gaseous Effluent Instantaneous Dose Rate calculations - 10 CFR 20 **** *

18 2.3.1 Site Boundary Dose Rate - Noble Ga~es

18 2.3.2 Site Boundary Dose Rate - Radioiodine and Particulates

19 2.4 Noble Gas Effluent Dose Calculations - 10 CFR 50 ****

21 2.4.1 UNRESTRICTED AREA Dose - Noble Gases * * * * * * *

21 2.4.2 Simplified Dose Calculation for Noble Gases

21 2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50

23 2.5.1 UNRESTRICTED AREA Dose - Radioiodine and Particulates

23 2.5.2 Simpl Hied Dose Calculation for Radioiodines and Particulates * * * * * * * * * * * * * * * * * *

24 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations * * * * * * * * * * * * *** 25 2.7 Gaseous Effluent Dose Projection * * * * * * * * * * * *

28 3.0 Special Dose Analyses 3.1 Doses Due To Activities Inside the SITE BOUNDARY *

29 3.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 ** 30 3.2.1 Effluent Dose Calculations * * * * * *

30 3.2.2 Direct Exposure Determination

31 Radiological Environmental Monitoring Program* * * *

32 4.0 4.1 Sampling Program * * * * * ~ * * * * * * *

32 4.2 Interlaboratory Comparison Program * * * * * ....

33

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Salem ODCH Rev. 2 02/26/87

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Table of Contents - Continued Tables 1-1 1-2 Parameters for Liquid Alarm Setpoint Determination - Unit 1 Parameters for Liquid Alarm Setpoint Determination - Unit 2 **

~7 38 1-3 Site Related Ingestion Dose Commitment Factors1 Aio * * * * *

39 1-4 Bioaccumulation Factors <BFi) * * * * * * * * * * * * * * * *

41 2-1 Dose Factors for Noble Gases * * * * * * * * * * * * * * * *

44 2-2 Parameters for Gaseous Alarm Setpoint Determinations - Unit 1

45 2-3 Parameters for Gaseous Alarm Setpoint Determinations - Unit 2

46 2-4 Controlling Locations. Pathways and Atmospheric Dispersion for Dose Calculations * * * * * * * * * * * * * * ***** 49 2-5 Pathway Dose Parameters - Atmospheric Releases ****** 50 A-1 Calculation of Effective HPC - Unit 1 * * * * * *

A-4 A-2 Calculation of Effective HPC - Unit 2 * * * * * * * **** A-5 B-1 Adult Dose Contributions Fish and Drinking Water Pathways Unit 1 " * * * * * * * * * * * . * * . * * * * * . * * .

B-5 B-2 Adult Dose Contributions Fish and Drinking Water Pathways Unit 2 * . * * * * * * * * * * * . * * * . . B-5 c-s Effective Dose Factors ~ * * * * * * * * * * *

C-5 Appendicies Appendix A - Evaluation of Conservative1 Default HPC Value for Liquid Ef,luents * * * * * * * * * * * *

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 0 - Radiological Environmehtal Monitoring Program - ,

Sample Types Location and Analysis *** D-1*

(

Salem ODCH Rev. 2 02/26/87 SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL The Salem Offsite Dose Calculation Manual COOCH> 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 SQ, Appendix I and 40 CFR 190.

Hore c*onservative calculation methods and/or conditions Ce.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 ODCH 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 ODCH calculation methodologieg; and parameters as is deemed necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.

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

1

Salem ODCH Rev. 2 02/Zbl~t 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> . alsai:m_1aosLf11li2Hii~-I~t:miosaii20.1 R18 CUn it 1> and 2-RlS <Unit 2>

provide the alarm and automatic termination of liquid radioactive material releases as required by Technical Specification 3.3.3.8.

1-R19 A,B,C1and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines. 2-R19 A1B1C and D provide this function for Unit 2.

2> alat:m-120.l~l - The~larm functions for th~ Service Water System are provided by the radiation monitors on the Containment Fan Cooler discharges <1-R 13 A.e,c,o and E for Unit 1 and 2-R 13 A1B1and 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 applicables associated radiation monitoring instrumentation and controls are presented as Figures 1-1 and 1-2 tor Units 1 and 2, respectively.

2

Salem ODCH Rev. 2 02/26/87 Per the requirements of' Technical Specification 3.3.3.81 alarm setpoints shall be established f'or the liquid ef'f'luent monitoring instrumentation to ensure that the release concentration limits of' Specification 3.11.1.1 are met Ci.e.1 the radioactive material released in liquid ef'f'luents to concentration of' UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 201 Appendix 81 Table Iii Column 21 for radionuclides and 2.0E-04 uCi/ml f'or dissolved or entrained noble gases>. The following equation* must be satisfied to meet the liquid effluent restrictions:

( 1.1>

C <F+f >

c { -------

f where:

c = the effluent concentration limit of' Technical Specification (3.11.1.1> implementing the 10 CFR 20 HPC for the site. in uCi/ml c = the setpoint1 in uCi/ml1 of' the radioactivity monitor measuring the radioactivity - concentration in the ef'f'luent 1 ine prior to - di lu.tion and subsequent release: the setpoint1 represents a value which.

if' exceeded. would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA f' = the f'low rate at the radiation monitor location* in volume per unit time1 but in the same units as F1 below F = the dilution water flow rat~ as measured prior to the release point.

in volume per unit time

[Note that if' no dilution is provided. c~ C. Also. note that when <F> is large compared to (f), then <F ~ f) = F.J Adapted f'rom NUREG-0133 3

* - * * * *** * * : . ** *~ ** #

Salem ODCH Rev. 2 02/26/87 1.2.1 The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations!

HPCe

SEN

CIJ SP ~ --------------- + bkg ( 1.2)

RR with:

L Ci HPCe = ------------ (1.3) where:

2: (-~;~~--0 SP = al*rm setpoint corresponding to the maximum allowable release rate <cp HPCe = an effective HPC value for the mixture of radionuclides in the effluent stream (uCi/ml)

Ci = the concentration of radionuclide i in the liqui~ effluent <uCi/mlJ*

The concentration mix must include the most recent quarterly composite of alpha emmitters.

Sr-89, Sr-90. Fe-551 Fe-59, and H-3.

£;;~0,

,.liA* HPC i :;;: the HPC v~l~e t~~~~s~~hdi~~ t~*~adi~ri~tll~e i fr~m 10 CFR *20~

Appendix B1 Table. II1 Column 2 (uCi/ml)

SEN = the sensitivity value to which the monitor is calibrated (cpm per uCi/mlJ CIJ = the circulating water flow rate (dilution water flow) at the time of release (gal/min)

RR = the liquid effluent release rate (gal/min) bkg = the background of the monitor (cpm)

The radioactivity monitor setpoint equation C1.2) 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 lalater System discharge. This routing is possible via interconnections between the Service Water Systems <see Figures 1 and 2J.

4

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Salem ODCH Rev. 2 02/26/87 Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.

1.2.2 Conservative alarm setpoints may be determined through the use of default parameters. Tables 1-1 and 1-2 summarize all current default values in use for Salem Unit-1 and Unit-21 respectively.

They are based upon the following:

a> substitution of the effective HPC value with a default value of lE-05 uCi/ml for radwaste releases

<refer to Appendix A for justification):

b> for additional conservatism** substitution of the I-131 HPC value of 3E-07 uCi/ml for the R19 Steam Generator blowdown monitors. R13 Service Water monitor and R37 Chemical Waste Basin monitor:

c> substitutions of the operational circulating water flow with the lowest flow. in gal/min: and.

d> substitutions of the effluent release rate with the highest allowed rates in gal/min.

With pre-established alarm setpoints1 it is possible to control the radwaste rele~se rate <RR> to ensure the ineQuality of eQuation (1.2> is maintained under changing values for HPCe and for differing Circulating Water System ditutions.

Technical Specification 3.11.1.1 limits. the concentration of radioactive material in liQuid effluents <after dilution in the Circulating Water System> to les~ than the concentrations as specified in 10 CFR 20, Appe~dix B1 Table !!1 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

Use of the effective HPC value as derived in Appendix A may be non-conservative for the R19 Steam ~enerator blowdown monitors and R37 Chemical Wast~ Basin monitors where 1-131 transfer during primary to secondary leakage may potentially be more controlling.

5

S.a l em OOCH Rev. 2 02/26/87 radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded. However. in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of Technical Specification 3.11.1.1 may be performed usin9 the following equation:

( 1. 4) where:

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

HPCi = the HPC value corresponding to radionuclide trom 10 CFR 201 Appendix 81 Table II1 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 wat~r flow rate (dilution water flow) at the.time or the release (gal/min)

' 6

Salem ODCH Rev. 2 02/26/87

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1.4.1 Technical Specificafion 3.11.1.2 limits the dose or dose commitment to HEHBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:

during any calendar quarter:

{ 1.5 mrem to total body per unit

~ 5.0 mrem to any organ per unit during any calendar year:

{ 3.0 mrem to total body per unit

~ 10.0 mrem to any organ per unit.

Per the surveillance requirements of Technical Specification 4.11.1.2, the following calculation methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem.

i.67E-02

VOL Do = --------------

L CCi

Aio) ( 1.5)

CLI whe.re:

Do = dose or dose commitment to organ 01 including total body Cmrem)*

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

Ci = average concentration of radionuclide i1 in undiluted liq~id effluent representative of the volume VOL <uCi/ml>

VOL = volume of liquid effluent released (gal>

Cid = average circulating water discharge rate during release period

<gal/min) 1.67E-02 = conversion factor (hr/min)

The site-related ingestion dose/dose commitment factors (A ) are presented in io Table 1-3 and have been derived in accordance with of NUREG-0133 by the equation:

7

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Salem OOCH Rev. 2 02/26/87 Aio = 1.14E+OS t<UI

Bli) + <UF

BFi>J OFi ( 1.6) where:

Aio = composite dose parameter for the total body or critical organ o of an adult for radionuclide i* for the fish and invertebrate ingestion pathways (mrem/hr per uCi/ml) 1.14E+05 = conversion factor (pCi/uCi

ml/kg + hr/yr)

UI = adult invertebrate consumption CS kg/yr)

Bli = bioaccumulation factor for radionuclide i in invertegrates from Table 1-4 CpCi/kg + pCi/1)

UF = adult fish consumption <21 kg/yr)

BFi = bioaccumulation factor for radionuclide CpCi/kg per pCi/1) in fish from Table 1-4 OFi :::: dose conversion factor for nuclide i for adults in pre-selected organ. 01 from Table E-11 of Regulatory Guide 1.109 Cmrem/pCi)

The radionuclides included in the periodic dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.11 Table 4.11-1.

R~dionuclfdes requiring radiochemical *analysis <e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent ~ith the re~uired minimum analysis freque.ncy of Technical Specification Tab1e 4.11-L In lieu o; the individual radionuclide dose assessment as presented in Section 1.4.11 the following simplified dose calculational equation may be used for demonstrating compliance with the dose limits of Technical Specification 3.11.1.2. CRefer to Appendix e for the derivation and justification for this simplified method.)

1.21E+03

VOL Otb = --------------

Cl:.I

(1.7)

' 8

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Salem ODCH Rev. 2 02/26/87

(.

2.52E+04

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

L. c i CLS>

Cl.I where:

average concentration ot radionuclide i* in undiluted liquid Ci = etTluent representative ot the volume VOL CuCi/ml)

VOL = volume ot liquid ettluent released (gal>

average circulating water discharge rate during release period CIJ = (gal/min) conservatively evaluated total body dose Cmrem)

Dtb = conservatively evaluated maximum organ dose Cmrem)

D =

max conversion ¥actor Chr/min) and the conservative total body 1.21E+03 = dose conversion ¥actor CFe-591 total body -- 7.27E+04 mrem/hr per uC i/ml) conversion ¥actor (hr/min) and the conservative maximum organ 2.S2E+04 = dose conversion ¥actor CNb-951 GI-LL! -- 1.51E+06 mrem/hr per uCi/ml) 9

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

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Salem ODCH Rev. 2 02/26/87

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(.:, ecim~c~ __ i2_S~~2ndac~-L~akaa~ .

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During periods of primary to secondary leakage (i.e ** steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system. The potential exists for the release of radioactive material to the off-site environment <Delaware River) via secondary system discharges.

Potentially significant radioactive material levels and potential releases are controlled/monitored by the Steam Generator blowdown monitors <R19) and the Chemical Waste Basin monitor <R37). However to ensure compliance with the regulatory limits on radioactive material releases. it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage. Any potentially significant releases will be via the Chemical Waste Basin with the major source of activity being the Steam Generator blo~down.

With *identified radioa.ctive 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 l~vels and the volume of water discharged. the resulting environmental doses may be cal~ulated based on equation <1.5>.

Because the release rate from the secondary system is indirect Ce.g., SG blowdown is normally routed to condenser where the condensate clean-up system

~ill remove much of the radioactive material), samples should be collected from the final release point (i.e., Chemical Waste Basin) ~or quantifying the radioactive material releases. However, for conservatism and ease of controlling and quantifying all potential release paths. it is prudent to sample the SG blowdown and to assume all radioactive material is released directly to 10

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Salem ODCH Rev. 2 02/26/87

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the environment via the Chemical Waste Basin.

radioactive material retention of the This approach while not exact. is conservative and ensures timely analysis for regulatory compliance.

for condensate clean-up Accounting system ion exchange resins may be needed to more accurately account for actual releases.

Salem OOCH Rev. 2 02126/87 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 ~aste 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 m~y be used in conjunction or in lieu of the ion exchange system for waste processing require-ments in accordance with Technical Specification 3.11.1.3. These processing requirements are applicable to each unit individually. Exceeding the projected dose requiring p~ocessing prior ;o release for one unit does not in itself dictate processing requirements for the other unit.

Dose projections are made at least once per 31 days by the following equations:

0 Otbp = Dtb C91 + d> ( 1. 9)

Dmexp = Omax (91 + d> ( 1.10) t::here:

Otbp = the total body dose projection for current calender quarter Cmrem)

Dtb = the total body dose to date for current calendar quarter as determined by equation Cl.5> or C!.7) Cmrem) the maximum organ dose projection for current calendar quarter Dma>tp = (mrem) maximum organ dose to date for curre~t calendar quarter as Dmax = the determined by equation (1.5> or Cl.8) Cmrem>

d = the number of days to date for current calendar quarter 91 = the number of days in a calendar quarter 12

Salem ODCH Rev. 2 02/26/87 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) W~ii~-~§i_H2l~YQ_S~~i~m - 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. 1-R41C provides noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1: this function is provided by 2-R41C for Unit-2.

2> ~2Diaiom~oi_eycg~_90~_ec~iiYC~L~a~yym_B~li~£ - Containment purges and pressure/vacuum reliefs are released to the atmosphere via the respective unit Plant Vent. Noble gas monitoring and auto isolation function are provided by 1-R41C for Unit-1 and 2-R41C for Unit-2. Additionally, in accordance with Technical Specification 3.3.3.91 Table 3.3-131 1-R12A and 2-R12A may be used to provide the containment monitoring and automatic isolation function during purge and pressure/vacuum reliefs.*

3> elaoi_Y~oi - 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 R41C1 a flow through gross activity monitor (for noble gas monitoring). Additionally, in-line gross activity monitors <1-R16 and 2-R16> provide redundant back-up monitoring capabilities to the R41C monitors. Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers

~ith redundant back-up sampling capabilities provided by R41B and R41A,

~espectively. Plant Vent flow rate is measured and as a back-up may be determined empirically as a function of fan operation <fan curves>.

Sampler flow rates *are determined by flow rate instrumentation (e.g.,

venturi rotometer).

The R12A monitors also provide the safety function of containment isolation in the event of a fuel handling accident during refueling. During HOOE 6 in accordance with Technical Specification 3/4.3.3, Table 3.3-61 the R12A alarm/trip setpoint shall be established at twice backgrounds providing early indication and containment isolation accompanying unexpected increases in containment airborne radioactive materiaJ levels indicative of a fuel degradation.

' 13

Salem OOCH Rev. 2 02/26/87 A gaseous radioactive waste flow diagrams with the applicable. associated i'

\,-.

..... J.,.-.

r-adiation monitoring instrumentation and controls are presented as Figures and 2-2 for Units 1 and 2, respectively.

2-1 14

Salem ODCH Rev. 2 02/26/87 2.2.1 Per the requirements of Technical Specification 3.3.3.91 alarm setpoints shall be established for the gaseous I 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 eetpoints may be established by the following calculational method. The measured radionuclide* concentrations and release rate are used to calculate the fraction of the allowable release rate. as limited by Specification 3.11.2.1, by the equation:

FRAC = [4. 72E+02

X/Q

VF * £ <Ci

Ki ) l + 500 <2.1>

FRAC = [4.72E+02

X/Q *VF* r,cci *(Li+ 1.1 Hi))]+ 3000 <2.2>

where:

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate 0

.X/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m3>

VF = ventilatio~ system flow rate for the applicable release point and.

monitor (ft3/min)

Ci = concentration of noble gas radionuclide as determined by radioanalysis of grab sample CuCi/cm3>

Ki = total body dose conversion factor for noble gas radionuclide (mrem/yr per uCi/m3. from Table 2~1>

Li = beta skin dose conversion factor for noble gas radionuclide (mrem/yr per uCi/m31 from Table 2-1)

Hi = gamma air dose conversion factor for noble gas, radionuclide (m~ad/yr per uCi/m31 from Table 2-1) 1.1 == mrem skin dose per mrad gamma air dose (mrem/mrad>

conversion factor (cm3/ft3

min/sec>

4.72E+02 500 = skin dose total body dose rate limit (mrem/yr) 3000 = rate limit (mrem/yr) 15

Salem ODCH Rev. 2 02/26/87 Based on the more limiting FRAC (i.e ** higher value> as determined above. the alarm setpoints for the applicable monitors <Rl61 R4lC1 and/or R12A> may be calculated by the equation:

SP = CAF *'[.Ci

SEN + FRACJ + 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 rel ease.

The allocation factor CAF> is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e ** the release rate limits of Technical Specification 3.11.2.1>. Normally. the combined AF value lor Salem Units 1 an~ 2 is 0.5 C0.25 per unit>. with the remainder 0.5 allocated to Hope Creek. Any increase in AF above 0.5 for the Salem Nuclear Generating Station will be coordinated with the Hope Creek Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.

2.2.2 A conservative alarm setpoint can be established. in lieu of the individual radionuclide evaluation based on the grab sample analysiB* 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 2-1 and 2-2 for Units 1 and 21 respectively.

16

Salem OD'H Rev. 2 02/26/87 These values are based upon:

the maximum ventilation (or purge) flow rate:

a radionuclide distribution* comprised of 95X Xe-1331 2X Xe-1351 lX Xe-133m1 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 maximu.m allowable release rate.

For this radionuclide distribution* the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Tables 2-2 and 2-3.

Adopted from ANSI N237-1976/ANS-18.11 Source Term Specifications* Table 6 17

Salem ODCH Rev. 2 02/26/87 limits the dose rate at the SITE BOUNDARY due to noble gas releases to {500 mrem/yr. total body and {3000 mrem/yr1 skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint being exceeded. an evaluation of the SITE BOUNDARY dose rate resulting from the release may be performed using the following equations:

Dtb = X/Q * '[ <Ki

Qi) <2.4) and Os= X/Q

t, <
*Qi) <2.S>

where:

Dtb = total body dose rate (mrem/yr)

os = skin dose rate (mrem/yr)

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location

Qi - average release rate of radionuclide i over the release period under evaluation iuCi/sec> ~

Ki = total

body_ dose conversiQn ~actor f'or nob 1 e gas radionuclide (mrem/yr per uCi/m31 from Table 2-1>

Li = beta skin dose conversion factor for noble gas radionuclide (mrem/yr per uCi/m31 from Table ~-1)

Mi = gamma air dose conversion factor for noble gas radionuclide (mrad/yr per uCi/m31 from Table 2-1>

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

As appropriate. simultaneous releases rrom Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.lai following any release exceeding the above prescribed alarm setpoints. Monitor indications (readings> may be averaged over a time period not to exceed 15 minutes when determining noble gas release rste 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 18

Salem OD~M Kev. ~ uL1Lo101 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.

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

2.3.2 Te.chn ica 1 Specification 3.11.2.1.b limits the dose rate to {1500 mrem/yr to any organ for I-1311* tritium and particulates with half-lives greater than 8 days. To dem~nstrale compliance with this limii1 an evaluat4on is performed at a frequency no greater than that corresponding to the sampling and analysis time period <e.g., nominally once per 7 days). The following equation may be used for the dose rate evaluation:

Do = X/Q u [ (Ri

Qi) <2.6>

where:

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

X/Q = atmospheric dispersion ~o the controlling SITE BOUNDARY location for the inhalation pathway Csec/m3>

Ri = dose parameter for radionuclide i1 Cmrem/yr per uCi/m3) for the child inhalation pathway from Table 2-5 Qi = average release rate over the appropriate sampling period and analysis frequency for rsdionuclide i -- I-1311 l-1331 tritium or other radionuclide in particulate form with half-life greater than 8 days (uCi/sec>

19

Salem ODCM Rev. 2 02/26/87 l.*

By substituting 1500 mrem/yr for D and solving for Q, an allowable release rate for I-131 dispersion can be and organ (inhalation*

determined.

0 Based on the child, thyroid -- Ri annual

= 1.62E+07 average (see Table 2-4> and the most limiting potential pathway. *age

~eteorological 3

gfoup mrem/yr per uCi/m ), the allowable release rate for I-131 is 42 uCi/sec. Reducing this release rate by a factor of 4 to account for potential dose contributions from other radioactive particulate material and other release points <e.g., Hope Creek), the corresponding release rate allocated to each of the Salem units is 10.5 uCi/sec.

For a 7 day period1 which is the nominal sampling and analysis frequency for !-

1311 the cumulative release is 6.3 Ci. Therefore1 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.t~b limits on allowable release rate.

20

Salem OOCH Rev. 2 02/26/87

(:'..

2.4 2.4.1 Technical Specification 3.11~2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of ~5 mrad1 gamma-air and ~10 mrads beta-air and the calendar year limits ~10 mrad1 gamma-air and ~20 mrads beta-air. The limits are applicable separately to each unit and are not combined site limits. The following equations may be used to calculate the gamma-air and beta-air doses:

Og = 3.17E-08

X/Q * '[_ <Hi *Qi) <2.7) and

= 3.17E-08

X/Q

L (Ni

Qi)

<2.8>

Db where:

Og = air dose due to gamma emissions for noble gas radionuclides Cmrad>

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

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3>

- ~ Qi = cumulative release of noble gas radio~uclide i over the period of interest <uCi)

Hi = air dose factor due to gamma emissions from n9ble gas radionuclide i (mrad/yr per uCi/m31 from Table 2-1)

Ni = air dose factor due to beta emissions from noble gas radionuclide fmrad/yr per uCi/m31 Table 2-1) 3.17E-08 = conversion factor (yr/sec>

In lieu of the individual noble gas radio'nuclide dose, assessment as presented above. the following simplified dose calculational equations may be used ~or verifying compliance with the dose limits of Technical Specification 3.11.2.2. <Refer to Appendix C for the derivatlon and justification for this simplified method.)

21

Salem ODCH Rev. 2 02/26/87 3.17E-08 Og = --------

X/Q

HeH * [_ Qi <2.9) 0.50 and 3.17E-08 Db = --------

X/Q

NeH * [ Qi (2.10) a.so where:

HeH = 5.3E+02, effective gamma-air dose factor <mrad/yr per uCi/m3>

NeH = t.1E+03, effective beta-air dose factor (mrad/yr per uCi/m3>

Qi = cumulativ~ release for all noble gas radionuclides (uCi>

the a.so = conservatism factor to account for potential variability in radionuclide distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the gamma-air and beta-air doses.

22

Salem OOCH Rev. 2 02/26/87

/.:.

~ *:

2.s.1 In accor dllnce with requirements of Technical Specification 3.11.2.31 a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of ~7.5 mrem and calendar year limit {15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of I-1311 tritium and particulates ~ith half-lives greater than 8 days:

Daop = 3. 17E-08

Id If SFp * [ <Ri

Qi > (2.11) where:

Daop = dose or dose commitment via controlling pathway p and age group a

<as identified in Table 2-4> to o~gan 01 including the total body (mrem>

w = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-4 X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways Csec/m3)

O/Q = atmospheric deposition for vegetation. milk and ground

,,f.*

plane exposure pathways Cm-2>

Ri = dose factor for radionuclide i '* (mrem/yr per uC i/m3) or (m2 mrem/yr per uCi/sec> from Table 2-5 for each age group a and the applicable pathway pas identified in T~ble 2-4. Values for Ri were derived in accordance with the methods described in NUREG-0133.

Qi = cumulative release over the period of interest for radionuclide i

-- I-131 *or radioactive material in particulate form with half-

. life greater than 8 days CuCi).

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

1) For milk and vegetation exposure pathways:

= A six month fresh vegetation and grazing season <Hay through October)

= o.s 2> For inhalation and ground plane exposure pathways:

= 1.0 For evaluating the maximum exposed individual. the infant age group is controlli~~ for the milk pathway and the child age group is controlling for the 23

.... '!>~**

- - - - -;, ... ... . .-*~ .. .. ,,. . '. ..: . :

:-.. * * * * * ~ .. '< *.:. ... ~ ** * : . : , ; .

Salem OOCH Rev. 2 02/26/87 vegetation pathway. Only the controlling age group and pathway as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3.

In lieu 2.s.2 of the individual radionuclide <I-131 and particulates> dose assessment as presented above. the following simplified dose calculational equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (refer to Appendix 0 for the derivation and justification of this simplified method>.

Omax = 3.17E-0.8

IJ

SFp

RI-131 * [. Qi (2.12>

where:

Om ax = maximum organ dose (mrem)

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

= 1.0SE+121 infant thyroid dose parameter wiih the cow-milk pathway controlling <m2 - mrem/yr per uCi/sec>

w.

Qi

=

O/Q for radioiodine1 2.lE-10 1/m cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form ~ith half life greater than 8 days (uCi)

The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Salem as identified by the annual land-use census <Technical Specification 3.12.2>.

Otherwise* the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-4.

24

*~ ~

Salem ODCH Rev. 2 02/26/87 During periods of primary to secondary leakage, minor levels of radioactive material may be released via the secondary system to the atmosphere. Non-condensables Ce.g., noble gases) will be predominately released via the condenser evacuation system and will be monitored and quantified by the routine plant vent monitoring and sampling system and procedures (e.g., R15 on condenser evacuations R41C on plant vent. and the plant vent particulate and charcoal samp 1 era).

However. if the Steam Generator blowdown is routed directly to the Chemical Waste Basin Cvia the SG blowdown flash tank) instead of being recycled through the condenser. it may be desirable to account for the potential atmospheric releases of radioiodines and particulates from the flash tank vent (i.e **

releases due to moisture carry over>. Since this pathway is not sampled or monitored *.. it is necessary to calculate potential releases.

Based on the guidance rn NRC NUREG-0133, the releases of the radioiodines and particulates may be calculated by the equation:

Qi = Ci

Rsgb

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

Qi = lhe release rate of radionuclide, i* from the steam generator rlash tank vent <uCi/sec)

Ci = the concentration of radionuclide, i t in the secondary coolant water averaged over not more than one week (uCi/ml)

Rsgb = the steam generator blowdown rate to the flash tank <ml/sec>

FH = the fraction of blowdown flashed in the tank determined from a heat balance taken around the flash tank at the applicable reactor power 1 evel SQftv = the measured steam quality in the flash tank vent: or an assumed value of 0.851 based on NUREG-0017.

25

Salem ODCH Rev. 2 02/26/87 Tritium releases via the steam flashing may also be quantified using the above eQuation with the assumption of a steam quality <SQ ) equal to 0. Since the H-ftv 3 will be associated with the water molecules, it is not necessary to account for the moisture carryover 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 0.48. The equation simplifies to the following:

Qi = 0.072 Ci Rsgb (2.14)

For H-3, the simplified equation is!

Qi = 0.48 Ci Rsgb (2.15)

Also during reactor shutdown operations with a radioactively contaminated secondary systems radioactive material may be released to the atmosphere via the atmospheric reliefs CPORV> and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust. The evaluation of the

. 0 radioactive material concentration in the steam relative to that in the steam

generator water is based on the guidance of NUREG-00171 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 i~:

26

~ ' ..... *: ~*.' .. . ..... ;* - 0 *' .:, *.J.-*M , , ' , , , < " * * * ... ,.\ **.* , ** :. :.: l " *.. ::,: ....:.: .._., ... .... :.;. *..** . .. . ...... ;.. ~* . .. . .. ~ ~.. . '.. -*** ~ ... : .*... , .. : .. .

Salem OOCH Rev. 2 02/26/87

(.

where:

Qi j SFj Qi = *o .13 *L j

<Ci j *

=release rate of radionuclide i via pathway j (uCi/sec>

= steam flow for release pathway j SF j >

PF <2.16)

= 4501000 lb/hr per PORV

= 800.000 lb/hr per safety relief valve

= 501000 lb/hr for auxiliary feed pump exhaust PF = partitioning factor, ratio of concentration in steam to that in the water in the steam generator

= 0.01 for radioiodines

= 0.005 for all other particulates

= 1.0 for H-3 Any aignificaryt releases of noble gases via the atmospheric steam releases can be Quantified in accordance with th~ calculational methods of the Salem Emergency Plan EP IV-III.

Alternately, the Quantification of the release rate and cumulative releases may be based on actual samples of main steam collected at the R46 sample locations.

The measured radionuclide concentration in the steam may be used for Quantifying

'\'

the noble gases, radioiodine and particulate releases.

Note: The expected mode of operation would be to isolate the effected steam generator. thereby reducing the potential releases during the shutdown/cooldown process. Use of the above calculational methods should consider actual operating conditions and release mechanisms.

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

27

.. *' *- ~ .... *... :- ..:.:.. :. ........ : ..... :. .. : *. ~ .. '.~.- .*-.~_:-:

.. _.-:-_:.cc*.: __.-:._._~

... -.*.. :_-:__-_:~ ...-.. _ ..-*.:. -.~-~-------

. ~~*,;:.. :*_ . -. -****~* ......: .*.. :.. *:.'..'.-.*~***

Salem ODCH Rev. 2 02/26/87 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.1 exceeding:

0.625 mrad/quarter1 gamma air:

1.25 mrad/quarter1 beta air: or 1.875 mrem/quarter1 maximum organ.

The applicable gaseous processing systems 'for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation system (filtration systems ~ 112 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 equat"i ons: *,;;-

D gp = Dg * <91+ d> (2.17)

D bp = Db * <91+ d> <2.10>

Dmaxp = Dmax * (91+ dl <2.19) where:

D gp = gamma air dose projection for current calendar quarter Cmrad>

Dg = bygamma air dose to date for current equation <2.7> or <2.9> Cmrad>

calendar quarter as determined D bp = beta air dose projection for current calendar quarter (mrad) beta air dose to date for current calendar quarter as determined Ob = by equation <2.8) or <2.10) (mrad) maximum organ dose projection for current calendar quarter (mrem)

Omaxp = maximum organ dose to date for current calendar quarter as Om ax = determined by equation (2.11) or <2.12) (mrem) d = number of days to date in ~urrent calendar quarter 91 = number of days in a calendar quarter 28

-* .*.: * .** -~ .1 * . *.: .- - -** -- ...... . *- : ._..... :~ .... ~ ._

Salem ODCH Rev. 2 02/26/87 In accordance with Technical $pecification 6.9.1.111 the Radioactive Effluent Release Report <RERR> submitted within 60 days after January 1 of each year shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to HEHBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.

There is one location on Artificial Island that is accessible to HEHBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities.

This location is the Second Sun (visitor's center) located near the contractors gate for the Salem Nuclear Generating Station.

The calculational methods as presented in Sections 2.4 and 2.5 may be used ~or determining the maximum potential dose to a HEHBER OF THE PUBLIC based on the parameters from Table 2-4 and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per visit per year. The default value ~or the mereorological dispersion data as presented in Table 2-3 may be used if current year meteorology in unavailable at the time of NRC reportin. However. a follow-up evaluation shall be performed when the ~ate becomes available

29

Salem OOCH Rev. 2 02/26/87 3.2 The Radioactive Effluent Release Report CRERR> submitted within 60 days after January 1 of each year shall also include an assessment of the radiation dose to the likely most exposed HEHBER 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 MEHBER 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 HEHBER 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 es presented in the Hope Creek Offsite Dose Calculation .Hanual <HCGS OOCH>.

As appropriate for demonstrating/evaluating compliance ~ith 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.

3.2.1 Effl~~ni 02a~ ~il,~liii2na. For purposes of implementing the survei11ance requirements of Technical Specification 3/4.11.4 and the reporting re~uirements of 6.9.1.11 <RERR>, dose calculations for the Salem Nuclear Generating Station

BY be performed using the calculational methods contained within this OOCH: 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 30

- . .:. " **-'- *~ ~ -_. .:...~ :..- _:_, _* :.:_~- ...... ..:

.:..: ~-- - *; :.:. -~- -~ *...__ .:_

Salem ODCH Rev. 2 02/26/87

/**

.1.*-'

parameters or meteorological conditions concurrent with the release period under evaluation may be used.

3.2.2 Oic~~i E~~2~~c~ D2~~ D~i~cmioaii2n~ Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of the environmental measurements (e.g., TLD1 ion chamber measurements>

and/or by the use of a radiation transport and shielding calculational method.

Only during atypical conditions will there exist any potential for significant on-site sources at Salem that would yield potentially significant off-site doses (i.e., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190.

However* should a situation exist whereby the direct exposure contribution is potentially significant. on-site measurements, off~site measurements and/or calculational techni~ues will be used for determination of dose for assessing 40 CFR 190 compliance.

31

Salem OOCH Rev. 2 02/26/87 The operational phase of the Radiological Environmental Monitoring Program

<REHP> 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 viciniti of Artificial Island:

- To determine if the operation of the Salem Nuclear Generating Stations has resulted in any increase in the inventory of long lived radionuclides in the environment:

To detect any changes in the ambient gamma radiation levels: and

- To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment.

The sampling requirements Ctyp~ of samples. collection frequ~ncy and analysis) and sample locations are presented in Appendix E.

32

.*.. * ... ;_. -* ....... -* . - '* -*. ... *.. *--~ ~*:*.* -:,. ** , *... -~.* :..*.*-~-...-*.< ..

Salem ODCH Rev. 2 02/26/87

\ .\_- __ *.- Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison.

Participation in an approved Interlaboratory Comparison Program provides a check on the precieness of measurements of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiologi~al Environmental Operating Report pursuant to Technical Specification 6.9.1.10.

33

~* .... ..........._

P5il&GCD

.... ft Oil IUllJI Uloc.N

-...- ----*.. AMiii

--- --** -IQ

1&ra u I I

HIXINI ClllCWlllmtlt

......--*--.I dWkWI'

~I- -

FOR INFORMATION ONLY Ill fl.JSS ..

21 ICUCtM ,_.., FIGURE 1-2 '* .

~.*

Ii RADIA'OOH IWHl'OR A IN811UIENI' MHEL

+-PNEUMATIC

... ,,..,JI mlXINI RADIATION MONITORING LIQUID

-ELECINCAL to ~ri:r.rz- -=-1*>1 2UNIT

-+-UDUI> EfFl.UENI'

..... GAS EfFWENI' ~ * .'.*

Monitoring for the 124 and 625 containment fan coil untti is provided by the RlJA, 8 or C monitors through tnterconnects.

t,.**

FROM

-HUJ Oll!ER UH!f lMJl<<JllVICHEMlllS 2UNll fllUIPDRS ACPHEAOIKS 1--1)6-+-~ \VHUIS AUX lllllG SUMP Ill AC LOOP DAS flOOflDRS AX fl.ANGELO WLH2* CllCS HUI RELIEFS ~ORDAS MIU RHRSUMl'S IEJICESS l£1 llDIMt WllO I

I AWSI I IWHUT <'illl

...I CllCSHUI ACP5 lSEAllO e Wl.11 2WMT I I

I I 2WHUT IOIFROM I OTHER COHISUMP UNIT E

.I WLT:r I

I 4-..,,

WASrEEVAP I &

FEED..- I WLHI I WASTE EVAP :

I G WI.Ill i' I

2WLH4 WUI L- -------~-------~------~---w-+- '

l

~

Wl.411 WASTE EVAP

~ IWLlllO --- f WUl3 T-----*--> _, ,a, WLU I I 2WLllll 1' IWL-;,,__,,--._-'Wl.W-111~-+ .t r-4-----w- --+--H- *Ion

.0 .

1Wftll() Wlllll

~-~--.-N-+;

lWR23 :a:~ I -

E11change L-w-1) 2C11CSurs System 1""290 WI.II& IOANOFAOlll 1--~4-* OTHER UHlf Q ..-r--T:rx-IC\ICSMJS

°'Ji~

2lllll111-

..__Wl.fldll-lltllo-_,;2WMHU-I l'UMP FOR INFORMATION ONLV t-* *M11l ll SERlllCE WAIER

6 !~*

,..m. b r~~~-1.L.lldo--Mil----l>f..~

FIGURE 1-3 LIQUID llllll& WASTE L------1--.J lllllltl

. . :.*.**.*.-... :_. ..:_,*'_:.. ~~'.J*:.:. . :.,_:_. *~:\**'...'.t-.~*.:: .\.;.::: * ..... :: --~::.. ~* .. :... *. .". : . .:-* ~*

Sale1 ODC" Rev. 2 02/2b/87

. *~ ....'"'

Paraaehr Actual Default Units Table 1-t Paraaeters fir Liquid Alar* Setpaiat Deter1i1atia1s Unit 1 Caneots Ya he Ya ht "PC calculated lE-05 I uCi/11 calculate far each batch ta be released e

"PCl-131 JE-07 N/A uCi/11 1-131 "PC conservatively used for 56 blau-dava aad Service !later 1anitar setp1ints Ci 1easur!d N/A uCi/11 taken fro1 ga11a spectral analysis ef liquid effluent "PCi as N/A 1Ci/1l taken fro1 10 CFR 20, Appendix B, Table 11,

eteraiaed Cal. 2.

SEii 1-R18 as 2.9E+07 CPI per uCi/11 radvaste effluent lCs-137)

eter1iried 1-R19 2.9E+07 Steaa Generator blovdovn lCs-137) lA,B,C,DJ 1-RlJ 1.2E+08 Service Yater - Cantain1ent fan coaling lA,B,C,D,EJ lCs-1371

.. al as . 1.85E+05 gp1 Circulating Wah! Sysh1, single CU pu1p 4eter1ined RR t-R18 as 120 gp1 . dehr1ined prior ta release; release rah dehr1ined can be adjusted for Technical Specification ca1pliaoce 1-Ri9 80 Steaa 6eneratar blavdovn rate per generator 1-Rll 2500 Service Yater flow rate far Contain1ent fan caolns SP 1-R18 calculated 4.4E+05l+bkg) CPl'l Default alar1 setpaints; ~ore canservative values aar be used as dee1ed appropriate and i-R19H calculated 2.0E+04(+bkgl desirable for ensuring regulatory caaplianu *--

and far 1aintaining releases ALARA~

1-R13H calculated 2.6E+03l+bkgl t Refer ta Appendix Afir derivation

.iii Th~ "PC values af l-13t (JE-07 uCi/11) has been used for derivation af tbe R19 Stea1 6eneratar hlavdavn and R13 Service Yater 1aaitar setpaints as discussed in Sectian 1.2.2.

37

-~.:;~::~~'"<:*.~.~.:*~~~-; . -- ~.~~~ ::~~--r*.~-::*.}.~"T.~*- -;-, *~--,-~-.',*.*:*;~-r~;-.~-:..~.7~-*~:~_.*-*-. -r* i: .,.,. ,,. - *1-:. ,- ~ .. -.~-':'"" -~ **-** ** ,*,*~*-* *- *** ~-.* * ** - * -----..., *

-~-'------""~ * .... **' * **-*** .. ~~~*:_.'-***~-:~_:"--'--.*-~-*---~***,~.----'-':_.:~:'--"'-*..___.__:_*-'_._:_*.:""-.c:.;*"---'-*~-...:..**:~'-"".~._:_:~**>:.:.::::~-'.~:~,___:_:-~*~.-:,__:,~*.:'-'-'

..~::_:.~~~~~;:.'.;;.:_:~L;*:~---:~~~;.~2~.):_;_;_:~_'~**+/-*-~;)li..~;-,;..:-~*::.::..;.:~*:~J-~~2::.-*:~;.;;6:*~:2(::..2--;_j

Sale1 ODC" Rev. 2 02/26i8i Table 1-2 Paraaeters far Liquid Alar* Setpaiat Deter1inations Unit 2 Para1eter Actual Default Units Ca11e11ts Value Value _________________________._________________

"Pee calculated lE-05 I. uCi/11 calculate for each batch ta be released "Ptl-131 JE-07 N/A uCi/11 1-131 "PC conservatively used for S6 blov-davn, Service Yater and Che1ical Waste Basin 1aoitar setpaiots Ci 1easured N/A uCi/11 taken fra1 ga11a spectral analysis af liquid effluent "PCi as N/A uCi/11 taken fra1 10 CFR 20, Appendix B, Table II, dehr1in!d Cal. 2.

SEHH 2-Rt8 as B.8E+07 cp1 per uCi/11 radvaste effluent <Cs-137>

dehr1ined 2-R19 8.8E+07 Stea* 6eaeratar blovdavn lCs-137)

<A,B,C &0) 2-RtJ 8.8E+07 Service Water - Contain1ent fan cooling fA,B,& Cl lCs-137>

RJ7 &.8E+07 Cbe1ical Vaste Basin lCs-137) cw as t.85E+05 gp1

Circulating Yater Syste1, single CV pu1p dehrained RR 2-R18 as 120 gpa deterained prior ta release; release rate deter1ined can be adjusted far Technical Specification co1pliance 2-R19 80 Stea1 Generator blovdovn rate.per generator 0

2-R1J 2500 Service Water flov rate for Contain1ent fan caalers RJ7 JOO Cbe1ical Waste Basin discharge SP. 2-Rta calculated 8.0E+05(+bkg)iff CPI Default alara setpoints; 1ore conservative values 1ay be used as dee* appropriate and 2-R19ffff calculated 6. iE+04l+bkg) desirable far ensuring regulatory caapliance

and far maintaining releases ALARA.

2-RtJ calculated 1.9E+OJ(+bkgl 137ffff calculated i.6E+04l+bkg) t Ref er ta Appendix Afnr derivatiea 11 Based 11 Cs-137 respanse fff Actual calculated setpoiat far 2-R18 lt.JE+o6) is greater than the full scale aanitor indicator, therefore, far canservatis1 tbe reco11ended setpoint has been reduced to a.OE+05 cp1.

ffff The "PC value af I-131 <3E-07 uCi/11) has been used for derivation af the R19 Stea1 generator

~lavdovn R1J Service Yater and the RJ7 Cheaical Waste Basin !anitor setpoints as discussed in Secti1111 1.2.2 38

_- . --.. - .... ~.' . -* ... . . . - :. ~.:.,. *----~ ; *. *.

Salem ODCH Rev. 2 02/26/87 i.

".":;;~: .

Table 1-3 Site Related Ingestion Dose Commitment Factors. Aio

<*re*/hr per uCi/*l>

Nuclide Bone Liver T.Body Thyroid Kidney Lun9 GI-LLI H-3 2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.82e-1 C-14 1.45e 4 2.9De 3 2.90e 3 2.90e 3 2.90e 3 2.9De 3 2.90e 3 Na-24 . 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 P-32 4.69e 6 2.91e 5 1.s1e 5 5.27e 5 Cr-51 5.58e 0 3.34e 0 1.23e a 7.40e 0 1.40e 3 Hn-54 7.06e 3 1.35e 3 2.1oe 3 2.16e 4 Hn-56 1.78e 2 3.15e 1 2.26e 2 5.67e 3 Fe-55 5.Ue 4 3.53e 4 8.23e 3 i.97e 4 2.03e 4 Fe-59 8.06e 4 1.90e 5 7.27e 4 5.30e 4 6.32e 5 Co-58 6.03e 2 1.35e 3 1.22e 4 Co-57 1.42e 2 2.36e 2 3.59e 4 Co-60 1.73e 3 3.82e 3 3.25e 4 Ni-63 4.96e 4 3.44e 3 1.67e 3 7.18e 2 Ni-65 2.02e 2 2.62e 1 1.20e 1 6.65e 2 Cu-64 2.14e 2 1.01e 2 5.40e 2 1.83e 4*

Zn-65 1.61e 5 5.13e 5 2.32e 5 3.43e 5 3.23e 5 Zn-69. 3.43e2 6.56e 2 4.56e 1 4.26e 2 9.85e 1 Br-8~ 4.07e 0 4.67e 0 Br-83 7.25e-2 1.04e-1 Br-84 9.39e-2 7.37e-7 Br-85 3.86e-3 Rb-86 6.24e 2 2.91e 2 1.23e 2 Rb-88 1.79e 0 9.49e-1 2.47e-11 Rb-89 1.19e a 8.34~-1 6.89e-14 Sr-89 4.99e 3 1.43e 2 8.00e 2 Sr-90 1.23e 5 3.01e 4 3.55e 3 Sr-91 9.18e 1 3.71e D 4.37e 2 Sr-92 3.48e 1 1.s1e o 6.90e 2 Y-90 6.06e 0 1.62e-1 6.42e 4 if-91* 5.72e-2 2.22e-3 i.68e-1 Y-91 8.88e 1 2.37e 0 4.89e 4 Y-92 5.32e-1 1 *.56e-2 9.32e 3 y.-93 1.69e 0 4.66e-2 5.35e 4 Zr-95 1.59e 1 5.11e O 3.46e 0 8.02e a i.62e 4 Zr-97 8.81e-1 1.78e-1 8;12e-2 2.68e-1 5.51e 4.

Nb-95 :' 4.47e 2 2.49e 2 1.34e 2 2.46e 2 1.s1e 6 Nb-97 3.75e 0 9.49e-1 3.46e-1 1.28e 2 2.43e 1

1. ue a 2.89e 2 3.SDe 3 2.96e 2

I

Ho-99 Tc-99* 1.29e-2 3.66e-2 4.66e-1 5.S6e-1 1.79e-2 2.17e 1 Tc-101 1.33e-2 1.92e-2 1.88e-1 3.46e-1 9.81e-3 5. 77e-14 39

- ..... - - . - ... ---*-. -- -* - . *- - ; .- . -*-* ... .: ***-. *~- .* : \ .: --~*. ~- : ,_ ::_.: ' -

Salem ODCH Rev. 2 02/26/87 Table 1-3 Ccon't>

-* Site Related Ingestion Dose Commit*ent Factors, Aio

<*re*/hr per uCi/*1>

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Ru-103 1 *.07e 2 4.60e 1 4.07e 2 1.25e 4 Ru-105 8.89e 0 3.51e 0 1.15e 2 5.44e 3 Ru-106 t.59e 3 2.01e 2 3.06e 3 1.03e 5 Rh-103*

Rh-106 I Ag-110111 1.56e 3 1.45e 3 9.60e 2 2.85e 3 5.91e 5 Sb-124 2.77e 2 S.23e 0 L10e 2 6.71e-1 2.15e 2 7.86e 3 Sb-125 1.77e 2 1.98e 0 4.21e 1 1.80e-1 1.36e 2 1.95e 3 Te-125* 2.17e 2 7.86e 1 2.91e 1 6.52e 1 8.82e 2 8.66e 2 Te-127* 5.48e 2 1.96e 2 6.68e 1 1.40e 2 2.23e 3 1.84e 3 Te-127 8.90e 0 3.20e O 1.93e 0 6.60e 0 3.63e 1 7.03e 2 Te-129m 9.31e 2 3.47e 2 1.47e 2 3.20e 2 3.89e 3 4.69e 3 Te-129 2.54e O 9.55e-1 6.19e-1 1.95e 0 1.07e 1 1.92e 0 Te-131* 1.40e 2 6.85e 1 5.71e 1 1.08e 2 6.94e 2 6.80e 3 Te-131 1.59e 0 6.66e-1 S.03e-1 1.31e 0 6.99e O 2.26e-1 Te-132 2.04e 2 1.32e 2 L24e 2 1.46e 2 1.27e 3 6.24e 3 I-130 3.96e 1 i.17e 2 4.61e 1 9.91e 3 1.82e 2 1.0le 2 19;~~~~~ ~. I-131 2.18e 2 3.12e 2 1. 79e 2 1.02e 5 5.35e 2 8.23e 1 I-132 1.06e 1 2.85e 1 9.96e o 9.96e 2 4.54e 1 5.35e i:f I-133 7.45e 1 1.30e 2 3.95e 1 1.90e 4 2.26e 2 L16e 2 I-134 5.56e 0 1.51e 1 5.40e a 2.62e 2 2.40e 1 1.32e-2 I-135 2.32e 1 6.08e 1 2.24e 1 4.0le 3 9.75e 1 6.87e 1 Ca-134 6.84e 3 1.63e 4 1.33e a 5.27e 3 1.75e 3 2.85e 2 Cs-136 7 .16e 2 2.83e 3 2.04e 3 1.57e 3 2.16e 2 3.21e 2 Cs-137 8.77e 3 1.20e 4 7.85e 3 4.07e 3 1.35e 3 2.32e 2 Cs-138 6.07e a 1.20e 1 S.94e 0 s.s1e a S.70e-1 5.11e-5 Ba-139 7.85e O 5.59e-3 2.30e-1 5.23e-3 3.17e-3 L39e 1 Ba-140 1.61e 3 2.06e 0 1.ose 2 7.02e-1 :!..1Se 0 :S.38e 3 Ba-141 3.81e 0 2.88e-3 1.29e-1 2.68e-3 :l..63e~3 1.80e-9 Ba-142 1.72e 0 1.77e-3 1.08e-1 1.50e-3 LOOe-:5 2.43e-18 La-140 1.57e 0 7.94e-1 2.1oe-1 5.83e 4 La-142 8.06e-2 3.67e-2. 9.13e-3 2.68e2 Ce-141 3.43e 0 2.32e a 2.63e-1 L08e 0 8.86e 3 Ce-143 6.04e-1 4.46e 2 4.94e-2 1.96e-1 - 1.67e 4 Ce-144 1.79e 2 7.47e 1 9.59e O 4.43e 1 6.04e 4 Pr-143 5.79e 0 2.32e 0 2.87e-1 1.34e 0 2.54e 4 Pr-144 1.90e-2 7.87e-3 9.64e-4 4.44e-3 2.73e-9

(.

Nd-147 3.96e 0 4.58e 0 2.74e-1 2.68e 0 2.20e 4 Ll-187 9.16e a 7.66e 0 2.68e 0 2.51e 3 Np-239 3.53e-2 3.47e-3 1. 91e-3 1.08e-2 7. Ue 2 40

--~... .... -* __ -~~-_,:**-.:

-( - .

.* : .. :.: ...:..~:........*:.. .:.-~* ~--.: .. --*~ ~-;'. .:.:.

. -~ *.;. . -* .:. . :.\*.* :.~:....:.*-*-

Salem ODCM Rev. 2 02/26/87

"*j" El1m1ni Sdil!Uthc._E.iiib Bioaccu*ulation Factors <BFi >

Table 1-4 (pCi/k9 per pCi/1 iter>*

Sali~ai1c._la~1c.i1~c.ai~

H 9.0E-01 9.3E-01 c 1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 p 3.0E+D3 3.0E+04 Cr 4.0E+02 2.0E+03 "n 5.SE+02 4.0E+02 Fe 3.0E+03 2.0E+04 Co 1.0E+02 1.0E+03 Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.0E+03 5.0E+04 Br 1.se-02 3.1E+OO Rb 8.3E+OO 1.7E+01 Sr 2.0E+OO 2.0E+01 y 2.SE+01 i.OE+03 Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1.0E+02 "o 1.0E+Ol 1.0E+01 Tc 1.0E+01 5.0E+01 Ru 3.0E+OO 1.0E+03 Rh *:: 1.0E+01 2.0E+03 A9 3.3E+03 3.3E+03 Sb 4.0E+01 5.4E+>O Te 1.0E+01 1.0E+02 I 1.0E+01 5.0E+01 Cs 4.0E+01 2.SE+01 Ba 1.0E+01 1.0E+02 0 La 2.SE+01 1.0E+03 Ce 1.0E+01 6.0E+02 Pr

2.5E+01 1.0E+03 Nd 2.SE+Ol 1.0e+03 w 3.0E+01 3.0E+O:!.

Np 1.0E+01 1.0E+01

Values in this table are taken from Regulatory Guide 1.109 except ~or phosphurus (fish> ~hich is adaptd from NUREG/CR-1336 and silver and anti~ony Mhich are taken fro* UCRL 505641 Rev. 11 October 1972.

41

. .~

j

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r ' PROCESS RADIATION MONITOR Hr.I AREA RADIATION

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au&

aw .. Jl~!

MONITOR

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HA ll<tl RA U.lZ fUJCJi" Ra11A FOR INFORMATION ONLY Ill RA 411) m7.IOlA M RAdlt Rr.lt:MA

Mna A00'.16A MA a*

M ltA.*lll fCA OJ(4 AA <UI HA 412tl fF.lllftA Y1*~10 ROCOIA ROCOIA

..... I *~fROMGAS . .CM'~-"---- .. FIGURE 2-1

- HA Ut I fQ.dlA a1GA P.ti OU f<<llllA RllA AAIJ.H RAOJOS IUJIO.ti.

~

RADIATION ltll& 1U 4ll> ..OllA MONITORING ltlle AA *l1 J rv.naA RA UJ> P.'..CU6A GASEOUS RAf.>IA

~&Jlt AA 4111 Aoo<IA 1 UNIT

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FOR INFORMATION ONLY t~ li:'~--r"ms At.4111 !iflOIS,A&.$YSHM W1GI fHCJll~

..... OKA't r.v.51

= ~~--.,._, FIGURE 2-2 t:m r.. ..,.. ~- ~ WJC

....... RADIATION r.<lll

~IC r.<tA

==

MIOllJ MIDIM MIOlll

~E~ING 2UNIT S

.. *-::* .. .- ___ ._. *-*~ .. _,_ .. **-- ._ .. .: . ::.._*:.... ,;,,.'.* -**--* - - .... . .. *. '*-* :;_,_:_,_ :... ~. -~- *.. ~. .. . . .... -*--* .*--*- .. .* ......_._....; .~*-:.. :.~;:._,. ~.: .

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--.... ~ge~

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._,;~*-..*:_*,.~. -*-.* -.-...... --*.-.-*--* .

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

Sales ODC" Rev. 2 02/26/87 Table 2-1 Dose Factors for Noble Gases Total Body Ga.Ha Air Beta Air*

Dose Factor Skin Dose Factor Dose Factor Om Factor Radionuclide Ki Li Mi Ni (1re1/yr per uCi/13l (1re1/yr per uCi/13l (arad/yr per uCi/m3l !arad/yr per uCii1Jl Kr-831 7.56E-02 t.93E+01 2.88E+02 Kr-851 1.17E+03 1.46E+03 1.23E+03 1.97E+03 1.61E+01 t.34E+03 1.72E+01 1. 95E+03 Kr-85 1.03E+04 Kr-87

5.92E+03 9.73E+03 6.17E+03 Kr-88 1.47E+04 2.37E+03 t.52E+04 2.93E+03 Kr-89 1.66E+04 t.OtE+04 t.73E+04 1.06E+04 Kr-90 t.56E+04 7.29E+03 t.63E+04 7.83E+03 Xe-1311 9.1SE+01 4.76E+02 1.56E+02 1.11E+03 Xe-1331 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.0SE+03 Xe-135n 3.12E+03 7.11E+02 3.36E+03 7.39E+02 h-135 t.81E+03 1.36E+03 L92E+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

- - -- ---- *-*AT'-... 4t*-*- 8.84E+03 2.69E+03 9.JOE+l)J 3.28E+03

,~;:!:*?>~. -*.":

44

,_:_* * :. _: .... :;*.~ _, ...

Sale1 ODC" Rev. 2 02/26/87 Table 2-2 Parameters for Gaseous Alar1 Setpoint Deter1inations

. . . . .. . Uni t-1 Paraaeter Ai:t1Jal Default Units Cori1ents Val1Je Value J

X/Q calculated 2.2E-Ob sec/1 USNRC Sain Safety _Evaluatior1, Sup. J 3

VF as aeasured 1.25E+05 ft /1in Plant Vent - normal operation

!Plant or Ventl far1 curves j

VF as aeasured 3.5E+04 ft /1in Containment purge

!Cont. or Purge) fan curves AF coordinated 0.25 unitless Administrative allocation factor to with HCGS ensure co~bined releases do not exceed release rate li1it for site.

3 c 1easured N/A uCi/cm i 3 K nuc tide speci fie N/A 1re1/yr per uCi/a Values froa Table 2-1 J

l

... nuclide specific NIA 1re1/yr per uCi/1 Values fro1. Table 2-1 i 3 nuclide specific NIA arad/rr* per uCi/11 ValueS: fr.01 Table 2-1

" 3 SEN 1-R41Ct as 1.6E+07 cp; per uCii C!il Plant Vent determined 1-R16 J.bE+07 Plant Vent (redundantl 1-R12A 2.1E+06 Containaent SP 1-R41C calculated J.JE+04(+bkgl . CPI Default alarm setpointsi ~ore conservative values 1ay be used as dee1ed appropriate and t-R16 calculated 7.4E+04!+bkgl desirable for ensuring regulatory compliance and for aaintaining releases ALARA.

i-R12A11 caicuiated 1.5E+04i+bkgi

' Based on 1ean for calibration ~ith aixture of radionuclides H Applicable during KODES 1 through 5. During KODE 6 !refueling), aanitor setpoint shall be reduced to 2X background in accordance with Tech Spec Table J.3-b.

45

- -- -'~*- *-* .:._ -* ... - - .... ,,.. ___ ; __,_ * .. _,_ - .._.,_*......

,: ....--.~-.:.... _:_ ;.._. -_ - .:_:. .. ---*.,. . - *. . .....

Sale1 ODCtt Rev. 2 02/2b/87

-.:~*.>. :* '

Table 2-3 Para1eters for Gaseous Aiar1 Setpoint Deter1inations Unit-2 Paraaeter Actual Default Units Co1mnts Value Vaiue J

X/Q calculated 2.2E-Ob m/1 licensing technical specification value J

VF as aeasured 1.25E+Q5 ft /1in Plant Vent - noraal operation

!Plant or Veno fan curves J

VF as 1easuted J.5E+04 ft /1in Contain1ent purge tCor1t. or Purge) fan curves AF *:oordinated 0.25 unitless Ad1inistrative allocation factor to*

with HCGS ensure co1bined releases do not exceed release rate 1iait for site.

J c aeasured N/A UCif *:I i 3 K nuc1 ide specific NIA 1re1/yr per uCi/1 Values froa Table 2-1 i J L nuclide specific NIA area/yr per uCi/1. Value~ fro1 Table 2-1 i 3

nuclide- specific N/A firad/yr *per uCi/1 Values fro1 Table 2-1

" J SEN 2-R41Ct as 1.bE+07 cpa per uCi/cn Plant Vent deter1ined 2-R1b 3.5E+07 Plant Vent (redundant!

2-R12A 3.3E+07 Containaent SP 2-mc calculated 3.3E+Q4(+bkgl CPf!I Default alar1 setpointsi 1ore conservative values 1ay be used as deeRed appropriate and 2-R16 calcuiated 7.2E+04t+bkgi desirable *for ensuring regulatory co~pliance and for 1aintaining releases ALARA.

2-R12A~f calculated 2.4E+OS!+bkgl 1 Based on 1ean for calibration with 1ixture of radionuclides 11 Applicable during MODES 1 through 5. During KOOE b (refueling), 1onitor setpoints shall be reduced to 2X background in accordance with Tech Spec Table 3.3-6.

4b

......i. *** :.~. ---**** --- - ~ - *-*-:.* **

Sale1 ODC~ Rev. 2 02/26/87 Table 2-4

-,~ ... ::

Controlling Locations, Path~ays and Atmospheric Dispersion for Dose Calculations 1 Atmospheric Dispersion iechr1ical ----------------------

Location Pathway(sl Controlling X/Q O/Q Specification (1/12}

Age Group (sec/13l 3.11.2.1a site boundary noble gases N/A 2.2E-06 N/A

\0.83 1ile1 Ni direct exposure 3.11.2.tb site boundar*y inhalation child 2.2E-06 N/A (0.83 1ile1 Nl 3.11.2.2 site bo1rndary gaHa-air N/A 2.2E-06 N/A (Q;B3 1ile1 Nl beta-air 3.11.2.3 residence/dairy 1ilk and inf ant 5.4E-08 2.1E-10 14.8 1iles, NNEl gr*ound pi ane b.9.1.10 Second sun direct exposur*e N/A 8.22E-Ob NiA

!0.21 ;ile/SEl and inha 1ati on

_______________ A _______ _

1 Th@ identified controlling locations, pathways and atDospheric dispersion are fr-011 the Safety Evaluation Repor*t, Supplmnt No. 3 for* the Salem Nuclear Gerier*ating Station, Unit 2 !NUREG-0517, Dm~ber 1978l.

47

~_:,;~.r*:_---:~~--~~~~:*r:.-- *--...:-:*:::::-:~~~-_::_*:.:**:. ~-~: .-;. -.*- *-*-- .:---*- -. --.-- ..... -*--- . - -

~

w:* *-~- .,....,~. -,---~ *- - ~

"1**

- .. *-.. .1 * ...........

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

....7* - -*.;-*

Salem ODCM Rev. 2 02/26/8

... -:-'::: ..:*,.*:~:. -.~* *.'.. ... ;~ :" ::'.':~ ,. ; ..::_. :. **... '

-- '. . . . . . *... *: .. : . ~ .-*: **.*****.*:*::*'"':'-.*..::--:;,*

_..*.':::, .. :_* ;.~:**

r.

Salem ODCH Rev. 2 02/26/8"

~,

Table 2-5 <cont'd)

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

Nuclide Bone Liver Thyroid Kidney Lung GI-LL! T.Body H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+S 9.28E+4 7.16E+4 Cr-51 7.SOE+l 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Hn-54 S.11E+4 1.27E+4 L98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 L24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 1.53E+6 1.78E+5 1.43E+4 Co-57 6.92E+2 S.86E+S 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+S 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 - 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 1.90E+5 1. 77E+4 8.40E+4 Sr-89 4.34E+S 2.42E+6 3.71E+S 1.25E+4 Sr-90 1.08E+8 1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 2.94E+6 4.09E+5 1. 77E+4 Zr-95 1.46E+.5 4.58E+4 6.74E+4 2.69E+6 1.49E+5* 3.15E+4-Nb,..95 1.86E+4 1.03E+4 1.00E+4 7.51E+5 9.68E+4 5.66E+3

' Ru-103 2.10E+3 7.43E+3 7.83E+5 1.09E+5 S.96E+2 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-110m 1.38E+4 1.31E+4 2.50E+4 6.75E+6 2.73E+S 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1. 72E+4 I.

Te-125m 4.88E+3 2.24E+3 1.40E+3 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+S 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+S 2.25E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 Cs-134 5.02E+5 1.13E+6 3.75E+5 1.46E+5 9.76E+3 5.49E+S Cs-136 S.15E+4 1.94E+5 1.10E+5 1. 78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+S 3.04E+5 i.21E+5 8.48E+3 3 .11E+S Ba-140 5.47E+4 6.70E+1 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 8.8SE+3 6.14E+S 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 1.21E+6 L34E+7 8.64E+S 2.62E+S Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+S 6.62E+2 Nd-147 7.86E+3 8.56E+3 S.02E+3 3.72E+S 1.82E+5 5.13E+2

~?-~~-~ ~:---:-.~;; **:* *::.~~*:_:_i ~~**.F

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

49

~ *,I

Salem ODCH Rev. 2 02/26/8

/ Table 2-5 <cont'd)

RCio), Inhalation Pathway Dose Factors - CHILO (mrem/yr per uCi/m3)

Nuclide Bone Liver Thyro.i d Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6. 73E+3*

P-32 2.60E+6 1.14E+5 4.22E+4 9.88E+4 Cr-51 8.SSE+l 2.43E+1 1.70E+4 1.08E+3 1.S4E+2 Hn-54 4.29E+4 1.00E+4 L58E+6 2.29E+4 9.51E+3 Fe-SS 4.74E+4 2.S2E+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+S 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+S 6.33E+3 2.80E+4 Zn-6S 4.26E+4 1.13E+5 7 .14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 1. 98E+S 7.99E+3 1.14E+5 Sr-89 5.99E+5 2.16E+6 1.67E+5 1. 72E+4 Sr-90 1.01E+8 1.48E+7 3.43E+5 6.44E+6 Y-91 9 .14E+5 2.63E+6 1.84E+S 2.44E+4

~~-~:~1;:)

~ /.c .

Zr-9S 1.90E+S 4.18E+4 5.96E+4 2.23E+6 6 .11E+4 3.70E+4 "Nb-95 2.35E+4 9.18E+3 S.62E+3 6.1AE+5 3.70E+4 6.55E-i-3 Ru-103 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+S L84E+S 1.43E-i-7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 2.32E+6 4.03E+4 2.07E+4 Te-12Sm 6.73E+3 2.33E+3 1. 92E+3 4.77E+5 3.38E+4 9 .14E+2 Te-127m 2.49E+4 8.S5E+3 3.02E+3 6.07E+3 6.36E+4 i.48E+6 7.14E+4 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1. 76E+6 L82E+5 3.04E+3 I-131 4.81E+4 4.81E+4 L62E+7 7.S8E+4 2.84E+3 2.73E+4 Cs-134 6.S1E+S 1.01E+6 :S.30E+S L21E+S 3.85E+3 Z.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 Z.S2E+S 1.04E+5 3.62E+3 1.2SE+S Ba-140 7.40E+4 6.48E+1 2.11E+1 1. 74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 1.95E+4 8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 1.17E+6 1.ZOE+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 S.55E+3 3.00E+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1. 08E+4 8.73E+3 4.81E+3 3.28E+5 S.21E+4 6.81E+2

' :: **.-:*. -~----.~~~~--~:*~**. -...*:**-. ~: *;:;:*::~ ~:-:*:-:::~'~?~~-.~-,~:~-~:* ~:*;;*::~-:~ ~

so

- - r

-~ .*_.

- .:;*_:-::;: .:'.~~~ **:*~~:*- ...-_._:

Salem OOCH Rev. 2 02/26/S~

Table 2-5 <cont'd>

-~.

RC io>, Inhalation Pathway Dose Factors - INFANT Cmrem/yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LL! T.Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 C-14 2.03E+6 1.12E+5 1.61E+4 7.74E+4 P-32 5.75E+1 1.32E+1 L28E+4 3.57E+2 8.95E+1 Cr-51 Hn-54 2.53E+4 4.98E+3 1.00E+6 7.06E+3 4.98E+3 1.97E+4 1.17E+4 8.69E+4 L09E+3 3.33E+3 Fe-55 Fe-59 1.36E+4 2.35E+4 L02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 Co-58 1.22E+3 7.77E+5 1.11E+4 L82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3 .11E+4 Rb-86 1.90E+5 3.04E+3 8.82E+4 Sr-89 3.98E+5 2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 1.12E+7 1.31E+5 2.59E+6 Y-91. 5.88E+S 2.45E+6 7.03E+4 L57E+4 rf~t)

Zr-95 1.15E+5 2.79E-:1-4 3 .11E+4 1.. 75E+6 2.17E+4 2.03E+4 Nb-95 !.57E+L! 6.43E+3 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 4.24E+3 S.52E+5 1.61E+4 6.79E+2 8.68E+4 1.07E+5 L16E+7 1.64E+5 1. 09E+4 Ru-106 Ag-110m 9.98E+3 7.22E+3 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 L01E+2 2.65E+6 5.91E+4 L20E+4 5.17E+4 4.77E+2 6.23E+1 1.64E+6 1.47E+4 1.09E+4 Sb-125 Te-125m 4.76E+3 1.99E+3 L62E+3. 4.47E+5' 1.29E+4 6.58E+2 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 L68E+6 6.90E+4 2.23E+3 Te-129111 3.79E+4 *4.44E+4 L48E+7 5.18E+4 L06E+3 !.96E+4 I-131 3.96E+S 7.03E+S 1.90E+S 7.97E+4 1.33E+3 7.45E+4 Cs-134 4.83E+L! 1.35E+S S.64E+4 1.18E+4 1.43E+3 S.29E+4 Cs-136 5.49E+5 6.12E+5 1. 72E+5 7.13E+4 L33E+3 4.55E+4 Cs-137 Ba-140 5.60E+4 5.60E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 L67E+4 5.25E+3 S.17E+5 2.16E+4 1.99E+3 Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.4SE+S 1.76E+S Pr-143 1.40E+4 S.24E+3 1.97E+3 4.33E+S 3.72E+4 6.99E+2 Nd-147 7.94E+3 S.13E+3 3.1SE+3 3.22E+S 3.12E+4 S.OOE+2

~- 51

.::..-:~:***r.:::..--~:r*~.~~~~:; ~"{~*y~ .. ~...

Salem OOCH Rev. 2 02/26/8~

Salem ODCH Rev. 2 02/26/8~

~

F:* Table 2-5 <cont'd>

R<io), Grass-Cow-Hilk 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 1.95E+9 2.65E+9 1.22E+9 Cr-51 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Hn-54 1.40E+7 4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 1.10E+8 1.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.3SE+8 1.33E+8 4.01E+8 Zn-65 2 .11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Rb-86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6

'Y-91 1.58E+4 ~

.. 6.48E+6 4.24E+2 Zr-95 1.65E+3 S.22E+2 ~

7.67E+2 1.20E+6 ' 3.59E+2 Nb-95 1.41E+S .7.80E+4 7.57E+4 3.34E+8 4.30E+4 Ru-103 1.81E+3 6.40E+3 1.52E+5 7.7SE+2 Ru-106 3.75E+4 7.23E+4 1.80E+6 4.73E+3 Ag-110m 9.63E+7 9.11E+7 1. 74E+8 2.56E+10 5.54E+7 Sb-124 1.53E+9 2.82E+7 3.47E+6 1.34E+9 3.08E+10 5.97E+8 Sb-125 1.22E+9 1.33E+7 1.16E+6 1.07E+9 9.48E+9 2.85E+8 Te-125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+B LOOE+7 Te-129m 1.11E+8 4.!0E+7 3.57E+7 4.62E+8 4.15E+8 L 75E+7 l-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 1.49E+8 4.04E+8 Cs-134 9.81E+9 2.31E+10 7.34E+9 2.80E+9 2.87E+B 1.07E+10 Cs-136 4.4SE+8 1. 7SE+9 9.53E+8 1.50E+8 1.41E+8 L18E+9 Cs-137 1.34E+10 !.78E+10 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.8SE+7 S.9SE+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+S 1.ZOE+S 1.53E+3 Ce-144 6.58E+5 2.72E+5 1.63E+5 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 6.77E+1 9.61E+S 1.4SE+1 Nd-147 1.81E+2 1.97E+2 1.16E+2 7.11E+S 1.18E+1

(~~~~;

53

Salem OOCM Rev. 2 02/26/8.

Table 2-5 Ccont'd)

RC io), Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem/yr per uCi/m3> for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Nuc 1 i de 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 t.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+10 3.64E+9 2.15E+9 3.00E+9 Cr-51 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 2.09E+7 5.87E+6 1.76E+7 5.58E+6 Fe-55 1.12E+8. S.93E+7 3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 5.65E+7 2.03E+8 9.71E+7 Co-57 3.84E+6 3.14E+7 7.77E+6 Co-58 1.21E+7 7.08E+7 3.72E+7 Co-60 4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 1.07E+8 1. 01E+9 Zn-65 4.13E+9 1.10E+10 6.94E+9 1.93E+9 6.85E+9 Rb-86 8.77E+9 S.64E+8 5.39E+9 Sr-89 6.62E+9 2.56E+8 1.89E+8 Sr-90 L12E+11 1.51E+9 2.83E+10 Y-91 9.14E+5 -- -

~-*- .

2. !63E+6. .1!841:+5 2.44E+4 Zr-95 3.84E+3 B.45E+2 1.21E+3 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+S 2.29E+8 8.84E+4 Ru-103 4.29E+3 1.08E+4 1.11-E+S 1.65E+3 Ru-106 9.24E+4 1.25E+5 1.44E+6 1.15E+4 Ag-110m 2.09E+8 . t .41E+8 2.63E+S 1.68E+10 1.13E+8 Sb-124 3.62E+9 4.70E+7 7.99E+6 2.01E+9 2.26E+10 1.27E+9 Sb-125 2.90E+9 2.24E+7 2.69E+6 1.62E+9 6.93E+9 6.08E+8 Te-125m 7.38E+7 2.00E+7 2.07E+7 7.12E+7 9.84E+6 Te-127m 2.08E+S 5.60E+7 4.97E+7 5.93E+8 1.68E+8 2.47E+7 Te-129111 2.72E+8 7.61E+7 8.78E+7 8.00E+S 3.32E+8 4.23E-t-7

!-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.17E+8 7.46E+8 Cs-134 2.26E+10 3.71E+10 1.15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-136 1.00E+9 2.76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+6 5.09E+5 2.82E+5 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.SOE+S 3.59E+1 Nd-147 4.45E+2 3.60E+2 1.98E+2 5.71E+5 2.79E+1 (t@})

54

Salem ODCH Rev. 2 02/26/8 Table 2-5 (cont'd)

R., Grass-Cow-Hilk Pathway Dose Factors - INFANT

<mrem/yr per uCi/m3> for H-3 and C-14 (m2

mrem/yr per uCi/sec> for others Nuc 1 i de 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 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 9.42E+9 2.17E+9 6.21E+9 Cr-51 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Hn-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 2.0SE+S Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 S.78E+9 Rb-86 2.22E+10 5.69E+8 1.10E+10 Sr-89 1.26E+10 2.59E+8 3.61E+8 Sr-90 1.22E+11 1.52E+9 3.10E+10 Y-91 7.33E+4 **.i.

5.26E+6 L95E+3 Zr-95 6.83E+3 1.66E+3 1.79E+3 8.28E+S 1*.18E+3 Nb-95 5.93E+5 2.44E+5 1. 75E+5 2.06E+S 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 2.3SE+4 Ag-110m 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+S Sb-124 6.98E+9 1.03E+8 1.85E+7 4.37E+9 2.15E+10 2.16E+9 Sb-125 4.98E+9 4.82E+7 6.24E+6 3.13E+9 6.64E+9 1.02E+9 Te-125m 1.51E+8 5.04E+7 5.07E+7 7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 Te-129m 5.59E+8 1.92E+S 2.15E+8 1.40E+9 3.34E+S S.62E+7 I-131 2.72E+9 3.21E+9 L05E+12 3.75E+9 1.15E+8 1.41E+9 Cs-134 3.65E+10 6.80E+10 1.75E+10 7 .18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+5 S.73E+4 1.48E+5 S.92E+7 L24E+7 Ce-l41 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 1.32':1E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 2.08E+2 7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 S.74E+5 S.SSE+l

~r~:~:j 55

Salem OOCH Rev. 2 02/26/8

'-** Table 2-5 (cont'd>

R<io), Vegetation Pathway Dose Factors - ADULT (mrem/yr per uCi/m3) f'or H-3 and C-14

<m2

mrem/yr per uC i/sec > f'or others Nuclide Bone Liver Thyroid Kidney Lung GI-LL! T.Body H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+~ 2.26E+3 2.26E+3 C-14 8.97E+5 1. 79E+5 1. 79E+5 1.79E+5 1. 79E+5 1.79E+5 1. 79E+5 P-32 1.40E+9 8.73E+7 1.58E+8 5.42E+7 Cr-51 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Hn-54 3.11E+8 9.27E+7 9.54E+8 5.94E+7 Fe-55 2.09E+8 1.45E+8 8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 8.35E+7 9.96E+8 1.14E+8 Co-57 1.17E+7 2.97E+8 1.95E+7 Co-58 3.09E+7 6.26E+8 6.92E+7 Co-60 1.67E+8 3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 1.SOE+S 3.49E+8 Zn-65 3.17E+8 1.01E+9 6.75E+8 6.36E+8 4.56E+8 Rb-86 2.19E+8 4.32E+7 1.02E+8 Sr-89 9.96E+9 1.60E+9 2.86E+8 Sr-90 6. 05E+11 1.75E+10 1.48E+11 J-91 5.13E+6 2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 . 5.97E+5 -* L21E+9 2.SSE+S 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-110m 1.06E+7 9.76E+6 1.92E+7 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.0SE+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.SOE+7 2.90E+7 3.93E+8 3.86E+8 1. 29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.17E+9 4.26E+7 Te-129m 2.55E+8 9.SOE+7 8.75E+7 L06E+9 L28E+9 4.03E+7 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.05E+7 6.63E+7 Cs-134 4.66E+9 1.11E+10 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 2.95E+9 9.81E+8 1.68E+8 -5.70E+9 Ba-140 1.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 1.96E+S 1.33E+5 6.17E+4 5.08E+8 L51E+4 Ce-144 3.29E+7 1.38E+7 8.16E+6 1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 1. 47E+4 2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 2.2SE+4 1.85E+8 2.31E+3

\~:,i}':J~i1 56

Salem ODCH R.ev. 2 02/26/8";'

/.

,o

=.-..

R<io>* Vegetation Pathway Dose Factors - TEENAGER Table 2-5 <cont'd)

(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-LL! T.Body

------- 2.59E+3 ------- ------- ------- ------- ------- -------

H-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+S 2.91E+5 2.91E+5 2.91E+S P-32 1.61E+9 9.96E+7 1.35E+8 6.23E+7 Cr-51 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Hn-54 4.52E+8 1.35E+8 9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 1.33E+8 9.98E+8 1.63E+8 Co-57 1. 79E+7 3.34E+8 3.00E+7 Co-58 4.38E+7 6.04E+8 1.01E+8 Co-60 2.49E+8 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Rb-86 2.73E+8 4.05E+7 1.28E+8 Sr-89 t.51E+10 1.80E+9 4.33E+8 Sr-90 7 .51E+11 2.11E+10 L85E+11 Y-91 7.87E+6 3.23E+9 2.11E+5

_@J~?} ...

1.74E+6 S.49E+5 . 8.07E+5 1.27E+9.. 3.78E+5 Zr-95 Nb-95 1.92E+5 1.06E+5 L03E+S 4.SSE+S 5.86E+4 Ru-103 6.87E+6 2.42E+7 5.74E+8 2.94E+6 Ru-106 3.09E+8 S.97E+8 1.48E+10 3.90E+7 Ag-110m 1.52E+7 1.44E+7 2.74E+7 4.04E+9 8.74E+6 Sb-124 1.SSE+S 2.8SE+6 3.51E+s* 1.3SE+8 3 .11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+S 1.88E+8 1.66E+9 5.00E+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 4.37E+8 1.98E+7 5.51E+8 1.96E+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 Te-127m Te-129m 3.67E+8 1.36E+8 1.18E+8 L54E+9 1.38E+9 5.81E+7 7.70E+7 LOSE+S 3.14E+10 1.85E+8 2.13E+7 S.79E+7 I-131 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.0SE+S 7.74E+9 Cs-134 4.29E+7 1.69E+8 9.19E+7 1.45E+7 1.36E+7 1..13E+8 Cs-136 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 1.38E+8 1.69E+5 5.7SE+4 1.14E+5 2.13E+8 8.91E+6 Ba-140 Ce-141 2.82E+S 1.88E+5 8.86E+4 S.38E+8 2.16E+4 Ce-144 S.27E+7 2.18E+7 L30E+7 1.33E+10 2.83E+6 Pr-143 7 .12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3 57

-~~(.,::~-~:~:~-~~~~ *~;~ .;, ~-- 4. *.-:* -:*:~-?~. *:: ~~<* :.*._:.~:~:;:-.' .-7' -~*.:~-;?_-,:):.~.~.:*:-_:::.:-_.~~7~!-;;:~}~-:\~~-~ !*~~ ,:::~,:*=*:*~ :*:' ~-~-.-. ~-~~.* -~ . . ~ .

'.. *.*!*,,:,,: .. -... _:_.:._=___ . _::,*.*;~:..':;. ,*,.:* .-.,

Salem ODCH Rev. 2 02/26/8"

':'. Tab 1 e 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-LL! 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+S 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 6.2SE+6 1.18E+S Hn-54 6.61E+8 1.85E+8 5.55E+8 1. 76E+8 Fe-55 8.00E+S 4.24E+8 2.40E+8 7.86E+7 1. 31E+8 Fe-59 4.01E+8 6.49E+8 1. 88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 - 2.10E+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 1. 42E+8 1. 34E+9 Zn-65 8 .12E+8 2.16E+9 1.36E+9 3.80E+8 1.35E+9 Rb-86 4.52E+8 2.91E+7 2.78E+8 Sr-89 3.59E+10 1.39E+9 1.03E+9 Sr-90 1.24E+12 1.67E+10 3.15E+11

(:~i~~.\ Y-91 1.87E+7 2.49E+9 5.01E+S Zr-95 3.90E+6 8.58E+5 1.23E+6 8.95E+8 7.64E+5 Nb-95 4.10E+5 1.59E+5 1.50E+5 2.95E+8 1.14E+5 Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 4.05E+7 2.58E+9 1. 74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1.57E+8 Te-129m 8.54E+B 2.39E+8 2.75E+8 2.51E+9 1.04E+9 1.33E+8 I-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 1.28E+7 8.18E+7 Cs-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 7 .46.E+9 2.68E+9 1. 43E+8 3.38E+9 Ba-140 2.77E+8 2.43E+S 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 1.23E+5 6.14E+4 2.69E+4 7.66E+7 9.12E+3 Ce-144 1.27E+8 3.9SE+7 2.21E+7 1.04E+10 6.78E+6 Pr-143 1. 48E+5 4.46E+4 2.41E+4 1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 3.18E+4 9.18E+7 4.49E+3

~:..::.: *:_;

58

.*.:""."."'": '. --** .. . . . : -~ .. ........ _._ *.

--~--~~~~~--->; *-,.:***:.: . -* *. -**.' ;-. **,:.

Salem ODCH Rev. 2 02/26/81 Table 2-5 (cont'd)

R<ioh Ground Plane Pathway Dose Factors (m2

mrem/yr per uCi/sec)

Nuclide Any Organ H-3 C-14

., P-32 Cr-51 4.68E+6 Hn-54 1.34E+9 Fe-55 Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Zn-65 7.45E+8 Rb-86 8.98E+6 Sr-89 2.16E+4 Sr-90 Y-91 1.08E+6 Zr-95 2.48E+8

{t~:ff!f<. Nb-95 1.36E+8 Ru-103" 1.09E+8 Ru-106 4.21E+8 Ag-110m 3.47E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.00E+7 I-131 1. 72E+7 Cs-134 6.75E+9 Cs-136 L49E+8 Cs-137 1.04E+!O Ba-140 2.0SE+7 Ce-141 1.36E+7 Ce-144 6.9SE+7 Pr-143 Nd-147 8.40E+6 59

Salem ODCH Rev. 2 02/26/87 APPENDIX A Evaluation of Default MPC Value for LiQuid Effluents

~. *-: ..' : . ::"

A-1

Salem ODCM Rev. 2 02/26/87

(*.

Appendix A Evaluation of Default MPC Value for Liquid Effluents In accordance with the requirements of Technical Specification (3.3.3.10> 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 81 Table II1 Column 2. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding MPC values.

In order to limit the need for routinely having to reestablish the alarm setpoints as a *function of changing radionuclide distributions. a default alarm setpoint can be established. This default setpoint can be based on an evaluation of the radionuclide distribution of the liquid effluents from Salem and the effective MPC value for this distrib~tion.

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

[_ Ci HPCe = CA. 1 >

where:

HP Ce = ?1-n effective* MPC value for a mixture of radionuclide (uCi/ml >

Ci = concentration of radionuclide i in the mixture HPCi = the 10 CFR 201 Appendix 81 Table II, Column 2 HPC value for radionuclide i (uCi/ml)

Based on the above equation and the radionuclide distribution in the effluents for past years from Salem. an effective HPC value can be determine. Results are A-2

Salem ODCH Rev. 2 02/26/87 presented in Table A-1 and A-2 for Unit 1 and Unit 2, respectively.

Considering the average effective HPC value for the years 1981 through 19841' it is reasonable to select an HPCe value of lE-05 uCi/ml as typical of liquid radwaste discharges. Using this value to calculate the default R18 alarm setpoint value. results in a setpoint that:

1> Will not require frequent re-adjustment due to. minor variations in the nuclide distribution which are typi6al 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>

r _.., ,.* _:)

A-3

~ -** .' :**- .. ,... *~-

Sale1 ODCn Rev. 2 0212bi8i c* Tabh A-1 Calculatian af Effective nPC Sah1 Unit 1 Activity Released (Ci!

~-----~---------------------------------

luclide ftPCI 1981 1982 1983 1984 laCi/111 Na-24 JE-05 2.4E-02 1.9E-03 5.3E-03 5.6E-OJ Cr-51 2E-03 5.9E-02 t.4E-01 6.2E-02 5.JE-02 lln-54

lE-04 7.4£-02 2. tE-01 1.6E-01 1.9E-01 Fe-59 5E-05 3.8E-03 8.6E-03 4.2E-02 5.8E-OJ

Ca-58 Ca-60 9E-05 3E-05 4.5E-01 J.2E-01 1.7 9.tE-01 1.8 7.lE-01 1.6 1.2 Zr-95 6E-05 1.0E-02 1.1E-02 8.0E-03 1.8E-OJ Kb-95 1E-04 1.8E-02 4.8E-02 2.2E-02 1.7E-02 Nb-97 9E-04 N/DH 9.5E-OJ 3.6E-04 2.0E-02 Tc-991 JE-03 N/D N/D N/D 1.6E-OJ Sr-89. JE-06 N/D N/D 1.2E-OJ 4.2E-04 Sr-90 JE-07 N/D N/D N/D 2.2E-05 lla-99 4E-05 2.5E-04 i.OE-03 t.6E-03 1.9E-OJ Ag-1101 3E-05 N/D 4.7E-03 N/D N/D Sn-UJ 8E-05 8.9E-04 2.2E-04 J.8E-04 9.4E-04

~?(~~. Sb-124 2E-05 6.2E-04 8.0E-OJ 1.4E-02 1.7E-02 Sb-125 lE-04 J.OE-01 6.8E-OJ 4.4E-02 4.9E-03 1-131 JE-07 1.1E-01 6.SE-02 2.4E-02 4.5E-02 I-133 1E-06 8.8E-02 5.SE-03 . J.JE-02 2.5E-02 1-135 4E-06 N/D J.SE-04 1.6E-OJ 1.2E-03 Cs-134 9E-06 6.0E-02 4.0E-02 1.8E-02 5.lE-02 Cs-137 2£-05 7.6E-02 5.9E-02 J.OE-02 5.8E-02 Ba-140 2E-05 N/D N/D 1.3E*02 2.1E-03 la-140 2£-05 N/D 7.5E-OJ t.JE-02 1.6E-02 Tetal Ci 1.59 3.24 3.00 3.32 L .JLllPCi 4.86E+05 2.8JE+05 i.66E+05 2.46E+05 llPCe (uCi/e1l J.JE-06 i.14E-05 1.80E-05 1.J5E-05

1 ftPC value for unrestricted area fra1 10 CFR 20, Appendix B, Table II, Calu1n 2.

11 l/D - not detected

(' ~-4

-~ .

Sa Iea ODC" Rev. -2 02/26/87 Table A-2 Ca1cu1atien of Effective "PC

'* Saha Unit 2 Activity Released (Ci) lucl ide "PCI 1981 1982 1983 1984 (uCi/11)

Na-24 3E-05 2.0E-01 1.2E-OJ 9.2E-03 4.4E-OJ Cr-51 2£-03 9.5E-02 1.1E-01 4.6E-02 J.6E-02 lla-54 1E-04 4.4E-02 2.0E-01 1.4E-01 1.6E-01 Fe-59 5E-05 5.8E-03 5.6E-OJ 3.1E-02 7.6E-OJ Ce-58 9E-05 8.tE-01 1.7 1.7 t.J Ca-60 3E-05 2.6E-01 8.6E-01 5.7E-01 9.8E-01 Zr-95 6E-05 1.0E-02 9.7E-OJ 5.2E-OJ 1.2E-03 lb-95 lE-04. 1.5E-02 2.JE-02 l.6E-02 1.4E-02 Nb-97 9E-04 I/OH 1.lE-02 t.lE-02 2.1E-02 Tc-991 JE-OJ 110 l/D l/D 1.4E-OJ Sr-89 JE-06 l/D N/D 3.2E-04 3.2£-04 Sr-90 3E-07 N/D N/D N/D 4.tE-05

"*-99 4E-05 7.4E-05 1.7E-04 3.0E-03 1.4E-OJ Ag-1101 JE-05 N/D 3.9E-03 N/D 11/D Sn-113 8E-05 2.6E-04 1.6E-04 5.9E-04 1.2E-03 Sb-124 2£-05 9.tE-04 1.0E-02 2.0E-02 3.0E-02 Sb-125 1E-04 8.4E-03 1.0E-02 9.6E-02 3.6E-03 1-131 JE-07 2.6E-02 t.3E-01 3.6E-02 4.2E-02 1-133 iE-06 6.0E-04 6.0E-03 5.4E-02 2.6E-02 tsff2~, I-135 4E-06 N/D N/D 1.6E-03 4.4E-04 Cs-134 9E-06 t.8E-02 5.lE-02. 2.0E-02 2.6E-02 Cs-137. 2£-05 2.9E-02 7.6E-02 J.6E-02 4.BE-02 lla-140 2E-05 MID N/D 9.8E-03 6.6E-03 la-140 2E-05 N/D 6.7E-03 8.1E-02 3.0E-02

Tetal Ci 1.52 3.21 2.89 2.74 L Ji_

"PCi

. 1.16E+05 5.00E+05 2.26E+05 2.24E+05 "Pee luCifal) 1.31E-05 6.42E-06 t.28E-05 1.22£-05

~ "PC value far unrestricted area fro1 10 CFR 20, Appendix B, Table II, Calu1n 2.

f-t N/D - nut d~tected A-5

Salem ODCH Rev. 2 02/26/87

(. v *-~*

APPENDIX B Technical Basis for Effective Dose Factors LiQuid Radioactive Effluent

\.*-

B-1

...... ~ *-** ,:*.: -*-~~--,.. - ""*~:::* --.-*;__-:-:*:-.: .. --~ .

Salem ODCM Rev. 2 02/26/87 APPENDIX B Technical Basis for Effective Dose Factors -

LiQuid Effluent Releases The radioactive liQuid effluents for the years 1984, 1983 and 1982 were evaluated to determine the dose contribution of the radionuclide distribution.

This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses. providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the radionuclide distribution ~f effluents from Salem* the controlling organ is the GI-LLI~

The calculated GI-LLI dose is predominately a function of the Fe-59.

CO-SS, C0-60 and Nb-95 releases. The radionuclides* Co-58 and C0-60 contribute the large majority of the calculated total body dose. The results of this evaluation 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 contr0Yling1 dose significaht radionuclide and limit the ca 1cu1 at i ona 1 process to the use of the dose conversion factor for this nuclide. Multiplication of the total release Ci.e.1 cumulative activity.for all radionuclides> by this dose conversion factor provides for a dose calculational method that is simplified while also being conservative.

For the evaluation of the maximum organ doses it is conservative to use the Nb-95 dose conversion factor Cl.51 E+06 mrem/hr per uCi/ml1 GI-LLI>. By this approach, the maxi mum organ dose wi 11 be overestimated s i nee this- nuc 1 i de has the highest ~rgan dose factor of all the radionuclides evaluated. For the total_

body calculations the Fe-59 dose factor (7.27 E+04 mrem/hr per uCi/ml1 total body) is the highest among the identified dominant nuclides.

' *- .' ~~. *_:-_.* '. ',

. ~.

B-2

Salem OOCH Rev. 2 02/26/87 For evaluating compiiance with the dose limits of Technical Specification 3.11.1.21 the following simplified equations may be used:

1.67E-02

VOL (8 .1)

Otb = --------------

A Fe-591TB * 't_ Ci Cir.I where:

Otb = = dose to the total body (mrem) 7.27E+041 total body ingestion dose conversion factor for A Fe-59,TB Fe-59 (mrem/hr per uCi/ml)

VOL = volume of liquid effluent released (gal>

c = total concentration of all radionuclides <uCi/ml>

CW = average circulating water discharge rate during release period (gal/min) 1.67E-02 = conversion factor (hr/min)

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

1.21E+03

VOL Otb = --------------

L Ci (8.2) 1.67E-02

VOL

A Nb-951GI-LLI (8.3)

Omax = ---------------------------

Cir.I

'[_Ci where:

Dmax = maximum organ dose (mrem>

A Nb-951GI-LLI = 1.51E+061Gi-LLI ingestion dose conversion factor for Hn-54 (mrem/hr per uCi/ml)

Substituting the value for A the equation simplifies to:

Nb-951GI-LLI 2.52E+04

VOL (8.4)

Omax = -------------- * !: Ci CLI B-3

Salem ODCH Rev. 2 02/26/87 Tritium is not included in the limited analysis dose assessment for liquid releases. because the potential dose resulting from normal reactor releases is relatively negligible. 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. Th is amounts to O.OSX 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.

(; .

. '.*i B-4

Sale1 ODC" Rev. 2 02i26/87

(. Tible B-1 Adult Dose Cantributions Fish and lavertebrate Patbvars Unit 1 1984 1983 1982 RadiD- Release TB Lll- -

Liver

~------

Release TB 61-LLI liver

~---------------*

Re lease TB 61-lll Live auclide lCil Dose Dose Dose lCil Dose Dose Dose !Cil Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac. Frac Fe-59 5.aJE-03 0.05 0.04 0.18 4.21E-02 0.34 0.30 0.66 8.57E-03 0.08 0.05 0.23 Ci-58 1.58 0.25 0.21 0.02 1.82 0.27 0.03 0.09 1.70 0.30 0.20 0.15 Ca-60 1.20 0.54 0.42 0.34 7.06E-01 0.30 0.26 0.10 9.09E-01 0.45 0.28 0.22 Ag-110. N/D I I I N/D I I I 4.70E-03 I 0.03 I "n-54 1.93E-01 0.03 0.05 0.22 1.6JE-Ot 0.02 0.04 0.09 2.06E-01 0.04 0.04 0.21 Nb-95 1.74E;-02 I 0.28 I 2.HE-02 I 0.37 I 2.BJE-02 I 0.40 I Cs-137 5.HE-02 0.05 I 0.11 3.04E-02 0.04 I 0.03 5.89E-02 0.06 I O.H Cs-134 5.06E-02 0.08 I 0.13 t.8JE-02 0.03 I 0.02 3.95E-02 0.07 I G.O~

Cr-51 5.JOE-02 , I I I 6.15E-02 I I I t.38E-01 ~ I ,ii TDtal 3.33E+OO 3.03E+OO 3.21E+OO I less Uan 0.01 l/D =not detected

.. 67f{J1 Table B-2 Adult DDse Contributions Fish and Invertebrate Pathways Unit 2 1984 1983 1982

TB RadiD- Release 61-Lll Liver Release TB 61-Lll Liver Release TB 61-Lll Liv IUClide lCil Dose Dose Dose !Cil Dase Dase Dase lCil Dose Dose Das Frac. FriC. Frac. Frac. Frac. Frac. Frac. Frac. Fra Fe-59 7.56E-03 o.oa 0.06 0.24 J.t2E-02 0.31 0.23 0.61 5.61E-03 0.05 0.04 O.i Co-58 i.30 0.25 0.21 0.13 t.66 0.30 *0.24 0.10 t.70 O.JO 0.22 o. i Co-60 9.79E-01 0.53 0.41 0.28 5.72E-01 0.29 0.22 0.10 8.61E-Ot 0.44 O.JO .0 'i

~

Ag-1101 N/D I I I N/D I I I J.92E-OJ I 0.02 ' v "n-54 1.61E-01 0.03 0.05 0.18 t.36E-01 0.02 O.OJ 0.10 2.02E-01 0.04 0.05 0.2 Nb-95 1.J6E-02 I 0.27 I 1.59£-02 I 0.28 I 2.28E-02 I 0.37 ~

Cs-137 4.81E-02 0.05 I 0.10 3.58E-02 0.04 I 0.04 7.64E-02 0.08 I O.i Cs-134 2.6JE-02 0.05 I 0.07 1.98E-02 0.04 I 0.03 5.06£-02 0.09 I Q.. i Cr-51 J.64E-02 I I I 4.58E-02 i f I i.07E-01 I lf u TD ta I 2.75E+OO 2.85E+OO l.22E+OO I less than 0.01 l/D =aot *etected B-5

Salem ODCH Rev. 2 1/9/87

/

APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent 0

/ ..:.~*:.~.:*~

C-1

Salem ODCH Rev. 2 1/9/87 APPENDIX C Technical Bases for Effective Dose Factors -

(.-. .; ~* Gaseous Radioactive Effluents The evaluation of doses due to releases of radioactiv~ 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 CK t1 or N times the total eff eff eff quantity of radioactive material released would be rteeded). This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Effective dose transfer factors are calculated by the following equations:

Keff = 1[. CKi ~ fi) cc. u where:

Keff = the effective total body dose factor due to gamma emissions from all noble gases released Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released fi = the fracti~nal abundance of noble gas radionuclide relative to the total noble gas activity CL+ 1.1 H>eff = L <

fi) CC.2>

where: <L + 1.1 HleH = the effective skin dose factor due to beta and gamma emissions from all noble gases released

= the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released C-2 Salem ODCH Rev. 2 1/9/87 He H = L_ <Hi

f i> CC.3>

where: HeH = the effective air dose factor due to gamma emissions from all noble gases released Hi = the air dose factor due to gamma emi~sions from each noble gas radionuclide i released Neff = '[<Ni

fi) CC.4>

where: Neff = the effective air dose factor due to beta emissions from all noble gases released Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released Normally1 it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However1 the noble gas releases from Salem have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful ev~luations difficult. For the past three years* the total noble gas releases have been limited to 1400 Ci for 19821 900 Ci for 1983~ and 21000 Ci for 1984. Th~refore1 in order to provide a reasonable basis for the derivation of the effective noble gas dose factors* the primary coolant source term from ANSI N237-1976/ANS-18.11 "Source Term Specifications," has been used as representing a typical distribution. The effective dose factors as derived are presented in Table C-1. To provide an additional degree of conservatism* a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservatism provides additional assurance that the eval~ation 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 -~ .* .~ C-3

-::~ .-* :..-~ ..... ~ *~* _r-*~:-* -~~i.~~::~--~:::_--~-=~~ _*

. . ' . 't <~. - ': ._.*:.: ..... * - ' ** " Salem ODCH Rev. 2 1/9/87 ':. 3,11.2.:z. the following simplitied eciuations may be used: 3.17E-08 D = -------- a.so

X/Q

Heft * [ Qi CC.S>

and 3.17E-08 D = -------- a.so

X/Q

Neff * '[ Qi <C.6>

where: D = air dose due to gamma emissions tor the cumulative release Ot all noble gases Cmradl D = air dose due to beta emissions tor the cumulative release Ot all noble gases Cmradl dispersion to the controlling site boundary X/Q = atmospheric <sec/m3) Heft = 5.3E+O:Z1 etfective gamma-air dose factor (mrad/yr per uCi/m3) Neft = 1.1E+031 ettective beta-air dose tactor (mrad/yr per uCi/m3) Qi = cumulative release for all noble gas radionuclides CuCiJ 3.17E-08 = conversion factor (yr/sec> conservatism factor to account for the variabil!ty in the 0.50 = eHl uent data Combining the constants. the dose calculational eciuations simplify to: D = 3.SE-05

X/Q

L Qi CC.7>

and D = 7 .OE-05

X/Q

t. Qi. <C.8)

The effective dose factors are used on a very limited basis for the purpose of fac i 1 it a ting the timely assessment of radioactive eHl uent releases. particularly during periods of computer malfunction where a detailed dose assessment may be unavailable. C-4 -,-. . ..:-:-* ~-:--:?:".~-* ---;;:::---;*-:*: '. "\* : . ' ... :. ~ .'* . '*,: .. Salem ODCM Rev. 2 1/9/87 ~;_._ .. ~. Noble Gases - Total Body and Skin Table C-1 Effective Dose Factors Skin EHective Total Body Effective ti* Dose Factor Dose Factor Radionuclide KeH CL+ 1.1 H>eH (mrem/yr per uCi/m3> (mrem/yr per uCi/m3> L4E+01 Kr-85 0.01 0.01 1.SE+02 1.9E+02 Kr-88 0.01 2.5E+OO 1.4E+01 Xe-133m 0.95 3.0E+02 6.6E+02 Xe-133 0.02 3.6E+01 7.9E+01 Xe-135 ' 4.8E+02 9.6E+02 Total Noble Gases - Air Gamma Air Effective Beta Air Effective Dose Factor Dose Factor Radionuclide MeH Neff , (mrad/yr per uCi/m3) (mrad/yr per uCi/m3j> 2.0E+Ol Kr-85 0.01 0.01 1.5E+02 2.9E+01 Kr-88 1.SE+Ol .Xe-133m 0.01 3.3E+OO

0. 9.5 3.4E+02 i.OE+03*

Xe-133 4.9E+01 Xe-135 0.02 3.8E+0'1 5.3E+02 1.1E+03 Total

Based on Noble gas distribution from ANSI N237-1976/ANSI-18.11 "Source Term Spec i ti cat ions."

_,;~;:*_::* .. 1t c-s

.. ;::*;-;.***;**-~~~:*.-~:*-~.,*T'~.

~ .* _**~*: . :*-~*~_L:.. /. \. ~-~*-.. - - APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent D-1 Salem OOCH Rev. 2 02/26/87 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 thyro1d1 and the highest dose contributor is radionuclide I-131. The results for this evaluation are presented in Table D-1. For purposea of simplifying the details of the dose calculation process. it is

- .t::

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. Hultiplication of the total release (i.e. cumulative activity tor all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative. For the evaluation of the dose commitment via a controlling pathway and age groups it is conservative to use the infants g/m/c, thyroid, I-131 pathway dcse f.actor (1.675E12 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 0-2 Salem ODCH Rev. 2 02/26/87 3.11.2.31 the following simplified equation may be used: Dmax = 3.17E-8

W

RI-131

L Qi where:

Dmax = maximum organ dose (mrem) w = atmospheric dispersion parameters to the controlling location(s) as identified in Table 3.2-4. X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways Csec/m3> D/Q = atmoeperic deposition for vegetation. milk nad ground plane exposure pathways Cm-2) = 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 = 1.675El2 Cm2 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 fo the overall negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radioiodines <e.g., Co-60 and Cs-137>1 the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However. use of the I-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation. especially considering that no other 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-2>. The location of exposure pathways and the maximum organ soe 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-3 Salem ODCH Rev. 2 02/26/87 Table D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose 0.02 0.15 Total Body 0.23 0.14 Liver 0.59 0.15 Thyroid 0.02 0.15 Kidney Lung 0.01 0.02 0.02 0.15 GI-LLI Fraction of Dose Contribution by Pathway Grass-Cow-Hilk 0.92 Ground Plane 0.08 Inhalation

D-4

Salem ODCM Rev. 2 1/9/87

i.

Acoer.dtx E Rad:olog1ca1 Environmental Hon1tor1nq Program Samol~ Tvo~. Location and Analvs1s E-1

.* ~- ~:* ~* -:--:*~.: ~- ~-*-~;.:-~;**: ~.:::-~-.- ?:-:-*;*~*-*:-:~~._. . /~ ~ . ~* : E-1 Page ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES I* DIRECT .. lFl 5.8 miles N of origin 2 TLD's will be collected Gamma dose 1G3 # 18.5 miles N of origin from each location quarterly quarterly 2S2 0.4 miles NNE of origin 2El 4.4 miles NNE of origin 2F2 8.7 miles NNE of origin 2F5 7.4 miles NNE of origin 2F6 7.3 miles NNE -0f origin 3El 4.1 miles NE of origin 3F2* 5.1 miles NE of origin 3F3 8.6 miles NE of origin 3Gl i 16.6 miles NE of origin 3Hl ff: 32 miles NE of *origin 3H3 # 110 miles NE of origin 402 3.7 miles ENE of origin 5Sl 1.0 mile E of origin 501 3.5 miles E of origin 5Fl 8.0 miles E of origin 6S2 0.2 miles ESE of origin 6Fl 6.4 miles ESE -Of origin 7Sl 0.12 miles SE of origin 7F2 9.1 miles SE of origin 9El 4.2 miles S of origin lOSl 0.14 miles SSW of origin 1001 3.9 miles SSW of origin 10F2 5.8 miles SSW of origin Collected quarterly Gamma-dose quarterly lOGl # ,. 11.6 miles ~SW of ocigin

Control Station M P85 183/15 4-dh

..'.*:::};h., ~:, *.:~.-; .:&5~: TABLE E-1 ODCM SALEM GENERATING STATION . r" RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES I. DIRECT (Con't) 10F2 5.8 miles SSW of origin Collected quarterly Gamma dose quarterly lOGl I 11.6 miles SSW of origin llSl 0.07 miles SW of origin 11E2 5e0 miles SW of origin llFl 5.2 miles SW of origin 12El 4.4 miles WSW of origin 12Fl 9.4 miles WSW or origin 13El 4.2 miles NE of origin 13F4 9.8 miles W *of origin 13F2 6.5 miles W of origin . 13F3 9. 3 miles W of origin , 1401 3.4 miles WNW of origi~ 14F2 6.6 miles WNW of origin 15F3 5.4 miles NW of origin 16El 4.1 miles NNW of origin 16F2 8.1 miles NNW of origin 16Gl I 14.8 miles NNW.of origin i Control Station (in addition to controls listed, two additional program controls are used for internal studies and are referred to as SITE-CAL and SITE-ZERO). M P85 183/15 4-dh

'.;\~! TABLE E-l Page 3 of 1

~11

~: **~**:r:1' ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

"

*~/l EXPOSURE TYPE AND FREQUENCY

.~**.") PATHWAY STATION CODE LOCATION COLLECTION METHOD OF ANALYSES II. AIRBORNE (a) P 2S2 0.4 miles NNE of origin Continous low volume air Gross beta analysis A sampler. Sample collected on each weekly R every week along with filter sample. Gamma T change. spectrometry shall I 2F2 8.7 miles NNE of origin be performed if

.:;):;) c gross beta exceeds

,*1 L ten times the A yearly mean of T control station E value.

s JHJ I 110 miles NE of origin Gross beta a~alysis done > 24hr. after sampling to allow for Radon and Thoron daughter decay lODl 3~9 miles SSW of origin 16El 4ol miles NNW of origin Gamma isotopic analysis on quarterly composite I Control Station \ \ M P85 183/15 4-dh ""~P:,,, ..* "*"-~ *~~.9 TABLE E-1 Page 4 of 7 ODCM - SALEM GENERATING STATION .~ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE TYPE AND FREQUENCY PATHWAY STATION CODE LOCATION COLLECTION METHOD OF ANALYSES II. AIRBORNE (Can't) ( b) I 2S2 0.4 miles NNE of origin A TEDA impregnated charcoal Iodine 131 arialyse: 0 flow-through cartridge is are performed on D connected to air particulate each weekly sample I air sampler and is collected N weekly at filter change. E 2F2 8.7 miles NNE of origin 3H3 # 110 miles NE of origin

- .,,.. ; 16El 4.1 miles NNW of origin

' 1001 3.9 miles SSW of origin

Control Station M P85 183/15 4-dh

TABLE E-1 Page ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES III. WATER (a) S 7El 1 mile W of Mad Horse Sample to be collected Gamma isotopic u Creek7 4.5 miles SE of monthly providing winter analysis monthly R origin icing conditions allow F sample collection H-3 on quarterly A composite* c 12Cl I West bank opposite E Artificial Island; 2.5 miles WSW of origin. 16Fl C&D canal; 6.9 miles NNW of origin (b) G 2S3 Fresh water holding tqnk; R 700 feet NNW of origin _ **_:i 0 501 Local farm; 3.5 miles E Collected monthly Gamma isotopic , :.' u of origin monthly N 3El Local farm1 4.1 miles

Tritium analysis D NE of origin monthly (c) s 7El 1 miles W of Mad Horse A sediment sample is Gamma isotopic E Creek 4.5 miles .SE of taken semi-annually anaylsis - semi-D origin annually I 12Cl i West bank opposite M Artificial Island; 2.5 E miles WSW of origin N 16Fl C&D Canal; 6.9 miles NNW T of origin I Control Station M P85 183/15 4-dh

TABLE E-1 ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION METHOD ANALYSES PATHWAY STATION CODE LOCATION IV. INGESTION Sample of fresh milk is Gamma isotopic and (a) M 2F4 6.3 miles NNE of origjn I-131 analyses on collected for each farm I semimonthly when cows each sample on L are on pasture, monthly collection K at other times. 3Gl i 16.6 miles NE of origin 5F2 7.0 miles E of origin 13E3 4.9 miles W of origin 14Fl 5e5 miles WNW of origi-n Two batch samples of fish Gamma isotopic (b) F llAl Outfall area1 approx. analysis of ediblE 650 feet SW of origin are sealed in plastic bag I or jar and frozen portion on s semiannually or when in collection H in season 12Cl I West bank opposite Artificial Island; 2o5 miles WSW of origin

Control Station M PB5 183/15 4-dh

}/~

- ~~ *-:1 E-1 Page 7 , 7 ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES

~~! IV. INGESTION (Cont'd) (c) I llAl Outfall area; approx. Two batch samples of crab Gamma Isotopic N 650 feet SW of origin are sealed in a plastic analysis of v bag or jar and frozen edible portion E semiannually or when in on collection R season. T lJCl # West bank opposite E: Artificial Island; B 2~5 miles WSW of origin R g:cj A T E

SJ

. ,'*) s . *.:~":_,! . *:1 .--.?~*:~

}-:;-.:i f~

t,;;,1 i Control Station M PBS 183/15 4-dh )§j ~*~-1

-***- **-***- *-- ***-*-- ** --**---** . . *.*.*-*- ** ** ___ *----** ... _;_..._** * .:..::..-.J.*.-*. ~ * .-.. .:....:.: ** -.*; .: ...... * ..... : ........ ' *:...: .. * .**. *.::.:.'.-.. : ... : *...: __ :..;* . ..: ..

FIGURE E-2 ONSITE SAMPLING LOCATIONS ARTIFICIAL ISLAND

-~~-~:-:::~.;=-~~~:~~~ .-,~~---~-~.-* ~ -..- ~ ***1

SALEM GENERATING STATION ODCM AFFECTED P,l\GES

Salem ODCH Rev. 2 02/26/87 SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION HANUAL The Salem Offsite Dose Calculation Hanual COOCH> describes the *ethodology and parameters used in: 1> the calculation of radioactive liquid and gaseous effluent monitorin~ 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 20.1061 10 CFR so, Appendix I and 40 CFR 190. Hore 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. I .. The OOCH will 'be maintained at the station for use as a reference guide and trainin~ document of accepted methodologies and calculations. Changes will be made to the ODCH calculation methodologies and parameters as is deemed ne.cessary to ensure reason ab 1 e conservatism in keeping with the pr inc i p 1 es of 10 CFR S0.36a and Appendix I for demonstrating radioactive effluents are ALARA. NOTE: As used throughout this document. excluding acronyms* words appearing all capitalized denote the application of definitions as used in the Salem Technical Specifications. 1 Salem OOCH Rev. 2 02/26/87

I*

' Per the requirements o; Technical Speci;ication 3.3.3.81 alarm setpoints shall be established ;or the liquid e;;1uent monitoring instrumentation to ensure that the release concentration limits o; Speci;ication 3.11.1.1 are met (i.e ** the concentration o; radioactive material released in liquid e;;1uents to UNRESTRICTED AREAS shall be limited to the concentrations speci;ied in 10 CFR 201 Appendix e, Table II, Column 21 ;or radionuclides and 2.0E-04 uCi/ml ;or dissolved or entrained noble gases>. The following equation~ must be satis;ied to meet the liquid e;;1uent restrictions: C CF+;) Cl.1> c { ------- t where: c = the e;;1uent concentration limit o; Technical Speci;ication (3.11.1.1> implementing the 10 CFR 20 HPC ;or the site. in uCi/ml c = the setpoint. in uCi/ml1 o; the radioactivity monitor measuring the . _radioactivity c_oncentration in the eHJu_ent 1 ine prior to diluti~n and subsequent release: ~h~ eetpoint1 represe~ts a value which.' if exceeded, woutd result in concentrations exceed in; the 1 imit.s . o; 10 CFR 20 in the UNRESTRICTED AREA f = the ;low rate al the radiation monitor location. in volume per unit time. but in the same units as F, below F = the dilution Mater ;1ow rate as measured prior to the release point. in volume per unit time [Note that i; no dilution is provided* c~ C. Also1 note that when <F> is large compared to (;), then CF+ ;) = F.J

Adapted from NUREG-0133 3

Salem ODCH Rev. 2 02/26/87 t. 1.2.1 at the Salem Nuclear The setpoints for the liquid effluent monitors Generatin9 Station are determined by the following equations: HPCe

SEN

CLI SP ~ --------------- + bk9 ( 1.2>

RR with: L Ci HPCe - ------------ ( 1.::>> where: L (-;;~;--) SP = alarm setpoint corresponding to the maximum allowable release rate* Ci = the concentration of radionuclide i in the liquid effluent CuCi/ml)~

NOTE The concentration mix must include the most recent quarterly composite of alpha emmitters.

Sr-89, Sr-90, Fe-ss, Fe-59. and H-3. HPCi = *the HPC *"value c*orresp.onc:iing to radionuclide i -~rom *10 CFR 20~ ------ Appendix e, 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 (gal/min> RR 0: the liquid effluent release rate (Qal/min) bkQ = .the back9round of the monitor (Cpm) The radioactivity monitor setpoint equation <1.2> remains valid during outages ~hen the circulating water dilution is potentially at its 1o~est 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 disehar9e dilution and thereby *inimize the potential offsite doses. releases from either Unit-1 or Unit-2 *BY be routed to either the Unit-1 or Unit-2 Circulatin9 Llater System This routing is !)Ossible \Ii e. interconnections between the Service Llater Systems <see Fi9ures 1 and 2>. 4 Salem OOCH Rev. 2 02/26/87 Procedural restrictions prevent eimultaneoue releaees from either a single unit or both unite into a single Circulating Water System discharge. Conservative alarm setpoints may be determined through the use of default parameters. Tables 1-1 and 1-2 summarize all current default values in use for Salem Unit-1 and Unit-21 respectively. They are based upon the following: a> substitution ~f the effective HPC value with s default value of lE-05 uCi/ml for radwaste releases (refer to Appendix A for Justification): b> for additional conservatism** substitution of the I-131 HPC value of 3E-07 uCi/ml for the R19 Steam Generator blowdown monitors. R13 Service Water monitor and R37 Chemical Waste Basin* monitor; c> substitutions of the operational circulating water flow wit~ the lowest flow1 in gal/min: and. d> substitutions of the effluent release rate ~ith the highest allowed rate. in gal/min. ~ith pre-established alarm setpoints1 it is possible to control the rad~aste release rate <RR> to ensure the inequality of equation (1.2> is maintained under **.'7 changing values for HPCe and for differing Circulating Water System* dilutions. Technical .Specifi.cation 3.11.1.1 limits i.he concentration of radioactive material in liquid effluents <after dilution in the Circulating Water System) to lese t.han the concentrations as specified in 10 CFR 201 Appendix 81 Table !!1 Column 2 for radionuclides other than noble gases. Noble gases are limited toe diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled snd

Use of the effective HPC value as derived in Appendix A may be non~

conaervative for the R19 Steam Generator blowdown monitors end R37 Chemical Waste Basin monitors where I-131 transfer during primary to secondary leakage may potentially be more controlling. 5 Salem ODCH Rev. 2 02/26/87 2.2.1 Per the requirements of Technical Specification 3.3.3.91 alarm setpoint* shall be established for the gaseous I effluent monitoring instrumentation to ensure that the release rate of noble

ases does not exceed the limits of Specification 3.11.2.11 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 ;as decay tank.

or Plant Vent>. the radiation monitoring alarm setpoints may be established by the following calculational method. The measured radionuclide concentrations and release. rate are used to calculate the fraction of the allowable release rate. as limited by Specification 3.11.2.1, by the equation: FRAC = [4. 72E+02

X/Q ~ VF

i: CCi ~ Ki> l 500 <2. i)

FRAC = C4.72E+02

X/Q *VF* "t, <Ci *_
>l + 3000 111here:

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flo111 rate X/Q = annual average meteorological dispersion to the controlling site boundary location <sec/m3) VF = ventilation system flow rate for the applicable release point and monitor (ft3/min) Ci = concentration of noble gas radionuclide as determined by radioanalysis of grab sample <uCi/cm3>. Ki = total body dose conversion factor for noble gas radionuclide (mrem/yr per uCi/m3s from Table 2-1> Li = beta skin dose conversion factor for noble gas radionuclide (mrem/yr per uCi/m31 from Table 2-1> 11i = ;amma air dose conversion factor for noble gas radionuclide Cmrad/yr per uCi/m31 from Table 2-1> 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad> 4.72E+02 = conversion factor Ccm3/rt3

min/sec>

500 = total body dose ra-le ,limit (mrem/yr) 3000 = skin dose rate limit (mrem/yr) 15 Salem OOCM Rev. 2 02/26/87 vegetation pathway. Only the controlling age group and pathway as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3. 2.s.2 In 1 ieu* of the individual radionuclide <I-131 and particulates> dose assessment as presented above1 the following simplified dose calculational equation may be used for verifying compliance with the 4ose limits of Technical Specification 3.11.2.3 (refer to Appendix D for the derivation and justification of this simplified method). Dmax = 3.17E-08

W

SFp

RI-131 * [ Qi <2.12>

where: Dmax = ma.ximum organ dose (mrem> !-131 dose parameter for the thyroid for the identified RI-131 = controlling pathway = 1.0SE+121 infant thyroid dose parameter ~ith the cow-~ilk pathway controlling <m2 - Mrem/yr per*uCi/sec> bl *= D/Q. for radioiodine1 2.1E-10 1/m Qi = cumulative release over the period of interest vor radionuclide i -- I-131 or radioactive material in particulate form with half life greater than 8 days CuCi) 0 The location of expos~re pathways and the maximum organ dose calculation may be

based on the available pathways in the ~urrounding environment of Salem as identified by the annual *lend-use census CTeehni.cel

SpecHi.ca.t.!oM 3.12.2>.

Otherwise. the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-4. 24 Salem OOCH Rev. 2 02/26/87 In accordance with Technical Specification 6.9.1.i11 the Radioactive Effluent Release Report <RERR> submitted within 60 days after January 1 of each year ehall include an assessment of radiation doses from radioactive liquid and gaseous effluents to HEHBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. There is one location on Artificial Island that is accessible to HEHBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities. This location is the Second Sun (visitor's center> located near the contractors 9ate for the Salem Nuclear Generatin9 Station. The calculational methods as presented in Sections 2.4 and 2.5 may be used for determinin9 the- maximum potential dose to a H"EHBER OF THE PUBLIC based on the . .~ . "'!". parameters from Table 2-4 and 2 hou~s per visit ~er year. The default v~lue for the mereorolo9ical dispersion data as presented in Table 2-3 may be used if current year meteorology in unavailable at the time of NRC ~eportin. However. a follow-up evaluation shall be perf~rmed when the data becomes available. ' 29 Salem ODCH Rev. 2 02/26/87 Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part Of an Interlaboratory Comparison. Participation in an approved Interlaboratory Comparison Program provides a check on the precisness of measurements Of radioactive materials in environmental eamples. A summary of the InterJaboratory Comparison Program reaults will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.10. >'!~C{Z?*~*~;-:~~r~~~!.7~'.!~:-~:~~:::.~:\}~~,~~~*:* j~~~~.-=~~~ ~*.~~~~:*:.:~~~-; :~- w~** ~::~~:_:; -~~ ~... - * ~~-~ - *~.;- ..=---~ 33 _.-.: .. ~G---~j~ . **.-- -..... --. -:

.\ '.** *.*.;*

.. *. .. *~~ - ~... .. . .. . .- Salem ODCH Rev. 2 02/26/87 \,:;... _,., Nuclide Bone Liver Table 1-3 Site Related In9e*tion Doee Co**it*ent Factor** i\io <*re*/hr per uCi/*1> T.Body Thyroid Kidney Lunt GI-LLI H-3 2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.82e-1 2.a2e-1 C-14 1.45e 4 2.90e 3 2.90e 3 2.90e 3 2.90e 3 2.90e 3 2.90e 3 Na-24 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 4.57e-1 P-32 4.69e 6 2.91e 5 1.81e 5 S.27e 5 Cr-51 s.sae o 3.34e 0 1.23e O 7.40e 0 1.40e 3 Hn-54 7.06e 3 1.35e 3 2.1oe 3 2.16e 4 "n-56 1.78e 2 3.tse 1 2.26e 2 S.67e 3 Fe-55 5.11e 4 3.53e 4 8.23e 3 1*97e 4 2.03e 4 Fe-59 8.06e 4 1.90e S 7.27e 4 S.30e 4 6.32e S Co-58 6.03e 2 1.35e 3 1.22e 4 Co-57 1.42e 2 2.36e 2 3.59e 4 Co-60 1.73e 3 3.82e 3 3.2Se 4 Ni-63 4.96e 4 3.44e 3 1.67e 3 7.18e 2 Ni-65 2.02e 2 2.62e 1 1.2oe 1 6.6Se 2 Cu-64 2.14e 2 1.01e 2 5.40e 2 1.83e 4 Zn-65 1.61e S 5.13e 5 2.32e 5 3.43e 5 3.23e 5 Zn-69 :$.43e 2 6.56e 2 4.56e 1 ~.26e 2 9.8Se 1 Br-82 4.07e o 4.67e O .Br-83 Br-84 1*.25e-2 9.39e..::2 - 1.04e-1 7.37e-7 Br-85 3.86e-3 Rb-86 6.24e 2 2.91e 2 1.23e 2 Rb-88 1.79e 0 9.49e-1 2.47e-11 Rb-89 1.19e O 8.34e-1 6.89e-14 Sr-89 4.99e 3 1.43e 2 8.00e 2 Sr-90 !.23e 5 3.0te 4 3.55e 3 Sr-91 9.18e 1 3. 71e O 4.37e 2 Sr~92. 3.48e 1 1.s1e o 6.90e 2 Y-90 6.06e O 1.62e-1 6.42e 4 V-91e S.72e-2 2.22e-3 1.68e-1 Y-91 S.88e 1 2.37e 0 4.89e 4 Y-92 S.32e-1 1.56e-2 9.32e 3 V-93 1.69e 0 4.66e-2 5.3Se 4 Zr-95 !.59e 1 5.Ue D 3.46e 0 8.02e D 1~62e 4 Zr-97 8.81e-1 1.7Se-1 8.12e-2 2.68e-1 S.51e 4 Nb-95 4.47e 2 2.49e 2 1.34e 2 2.46e 2 *1.s1e 6 Nb-97 3. 75.e 0 9.49e-1 3.46e-1 1. ue o 3.SOe 3 "o-99 i.28e 2 2.43e 1 2.89e 2 2.96e 2 Tc-99* 1.29e-2 3.66e-2 4.66e-1

S.56e-1 1.79e-2 2.17e 1 Tc-101 1.33e-2 t.92e-2 1.aae-1 3.46e-1 9.81e-3 s. 77e-14 39

Salem ODCH Rev. 2 02/26/87 ~ ;'. : - : Nuclide Site Related In9eation Doee Co**it*ent Factor** Aio Bone Liver Table 1-3 <con't> (area/hr per uCi/al> T.Body Thyroid Kidney Lun9 GI-LLI Ru-103 1.07e 2 4.60e 1 4.07e 2 1.2Se 4 Ru-105 8.89e 0 3.Sle 0 1.1Se 2 S.44e 3 Ru-106 1.59e 3 2.01e 2 3.06e 3 1.03e 5 Rh-103a Rh-106 ~9-110., 1.56e 3 1.45e 3 8.60e 2 2o85e 3 5.91e 5 Sb-124 2.77e 2 S.23e 0 1.10e 2 6.71e-1 2.15e 2 7.86e 3 Sb-125 1.77e 2 1.98e 0 4.21e 1 1.eoe-1 1.36e 2 1.95e 3 Te-125a 2.17e 2 7.86e 1 2.91e 1 6.52e 1 8.82e 2 S.66e 2 Te-127* S.48e 2 1.96e 2 6.68e 1 1o40e 2 2.23e 3 1.84e 3 Te-127 8.90e 0 3.20e 0 1.93e 0 6.60e 0 3.63e 1 7.03e 2 Te-129a *9~31e 2 3.47e 2 1.47e 2 3.20e 2 3.89e 3 4.69e 3 Te-129 2.54e 0 9.SSe-1 6.19e-1 1.95e 0 1.07e 1 1.92e 0 Te-131* 1.40e 2 6.8Se 1 5. 71e 1 1.08e 2 6.94e 2 6.80e 3 Te-131 i.59e 0 6.66e-1 5.03e-1 1.31e 0 6.99e 0 2.26e-1 Te-132 2.04e 2 1.32e 2 1.24e 2 1.46e 2 1.27e 3 6.24e 3 I-130 3.96e 1 i.17e 2 4.61e 1 9.91e 3 1.82e 2 1.01e 2 (f~~,~~.~. I-131 2.18e 2 3.12e 2 1. 79e 2 1.02e 5 5.35e 2 8.23e 1 l-132 ' 1.06e 1 2.sse 1 9.96e O 9 *. 96e* 4;s4e-1 - ***-**-. s.. 3se o I-133 7.45e ! L30e 2 3.95e 1 L9De ~ 2.26e 2 1.16e 2 I-134 5.56e 0 1.Sle 1 5.40e 0 2.62e 2 2.40e 1 1.32e-2 I-135 2.32e 1 6.08e 1 2.24e 1 4.0le 3 .9.75e 1 6.87e 1 C.-134 6.84e 3 1.63e 4 1.33e 4 5.27e 3 1. 75e 3 2.sse 2 Ce-136 7.16e 2 2.83e 3 2.04e 3 1.57e 3 2.16e 2 3.21e 2 C.-137 8.77e 3 1.20e 4 7.85e 3 4.07e 3 1.35e 3 2.32e 2 Ce-138 6.07e 0 1.2oe 1 5.94e 0 8.81e O S.70e-1 5. Ue-5 Ba-139 7.8Se 0 S.59e-3 2.30e-1 5.23e-3 3.17e-3 1.39e 1 Ba-140 1.61e 3 2.06e 0 1.08e 2 7.02e-! 1.18e 0 3.38e 3 Bs-141 3.81e 0 2.88e-3 i.29e-1 2.68e-3 !.63e-3 1.soe-9 Be-142 1.72e 0 !.77e-3 !.Ose-1 1.soe-3 1.00e-3 2.43e-18 !..a-140 1.57e O 7.94e-1 2.1oe-1 S.83e 4 La-142 8.06e-2 3.67e-2 9.13e-3 2.68e2 Ce-141 3.43e 0 2.32e 0 2.63e-! 1.oae o 8.86e 3 Ce-143 6.04e-1 4.46e 2 4.94e-2 1.96e-1 1.67e 4 Ce-144 !.79e 2 7.47e 1 9.59e 0 4.43e 1 6.04e 4 Pr-143 5.79e 0 2.32e 0 2.87e-1 1.34e 0 2.54e 4 Pr-144 1.90e-2 1.S7e-3 9.64e-4 4.44e-3 2.73e-9 Nd-147 3.96e 0 4.58e 0 z.74e-1 2.68e 0 2.20e 4 W-187 9.16e 0 7.66e 0 2.68e 0 2.51e 3 Np-239 3.53e-2 3.47e-3 1.91e-3 1.08e-2 7 .11e 2 ([D~> 40 r.-: ~~**;*~-~-~~:~fb~;~~~~~~~~:~:~:._~;-~:~-~ r_r:~?~J::~::~-:4?~r~*;~?~~:::~~~~-~:r~::;.:-t:~r~-~7~;*:.~~-'.~~,*~?~: ~\~-~T-*::,;;_;*~*::;~~*~-:-.--.-~z:*~*.'.~:*,.:~---- :**;:; -....... _::-r:~- ,--~: - .-.~ *.:.~-'.~- ::*.-_ ~ ~-- . *~ ~. *-- :*~: ~~ ~-*-' .<.\"*~*~\::"_: ....... ~. -** *- . - . __ ;:;_ .. *~ .... , -**- *-* ,,.. *.:~---** :.. . : :..*.. . _. ..:.*.*~~ ;--* ""':::.-*; ::.-~: -*--** ... __ :_ . ... *:* -~ _. .*. **-** "........ *-.: .. -~ __ -_ - .. . . .:.. *-' - .. -- .

-~- :-* .- .:. .. ( ..

Sale1 ODC" Rev. 2 02/26/87 Tab le 2-4 Controlling Locations, Pathways and At1ospheric Dispersion for Dose Calculations 1 At1osrheric Dispersion Technical ----------------------

Specification Location Pathway Isl Contro II ing X/Q DiQ Age 6roup lsec/131 l1i12l 3.tl.2.1a si h boundary noble gases N/A 2.2£-06 NIA (0.83 Ii le I Nl direct exposure 3.11.2. lb site bo1mdary inhalation child 2.2£-06 NIA 10.83 1ile, NI 3.11.2.2 site bo11ndary garia-air N/A 2.2E-06 N/A 10.83 1ile, NI beta-air 3.11.2.3 residence/dairy 1ilk and inf ant 5.4E-08 2.1E-10 14.8 1iles, NNEl ground piane .I 6.9.1.10 Second sun

direct exposure N/A 8.22E-06 NIA 10.21 1ile/SEI and inhalation

- - -. -** ---*..*t*

1--The-tde~tiii!d-controlling locations, pathuays and.at1ospheric dispersion are fra1 the Safety Evaluation Report, Supple1ent No. 3 for the Sale1 Nuclear Generating Station, Unit 2 INUREG-0517, Dece1ber 19781. 47 ~ *.:. *, . . --- ' . . .*.. :. -- ..... -'*: ~ .:.: , :. Salem ODCH Rev. 2 02/26/8-Table 2-5 ., Pa.thway 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 1.26E+3 1.26E+3 L26E+3 H-3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1.32E+6 7.71E+4 8.64E+4 5.01E+4 Cr-51 5.95E+1 2.28E+1 1.44E+4 3.32E+3 LOOE+2 Hn-54 3.96E+4 9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 *2. 78E+4 1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2 3.70E+5 3.14E+4 6.71E+2 Co-58 1.58E+3 9.28E+5 1.06E+5 2.07E+3 Co-60 1.15E+4 5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 1. 78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+S 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 1.35E+S 1.66E+4 S.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 I~'toe+-6*- *3:9se+s 1.24E+4 Zr-95 1.07E+S 3.44E+4 5.42E+4 1. 77E+6 1.SOE+S 2.33E+4 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.0SE+S 1.04E+S 4.21E+3 Ru-103 1.53E+3 5.83E+3 S.05E+S 1.10E+5 6.58E+2 Ru-106 6.91E+4 1.34E+S 9.36E+6 9.12E+S 8.72E+3 Ag-110m 1.08E+4 1.00E+4 1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 S.89E+2 7.SSE+l 2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 1.74E+6 1.0lE+S 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.0SE+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+S LSOE+S L57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 *1.16E+6 3.83E+S 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 Cs-134 3.73E+5 8.48E+S 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 !.lOE+S Cs-137 4.78E+S 6.21E+S 2.22E+S 7.52E+4 8.40E+3 4.28E+5 Ba-140 3.90E+4 4.90E+1 i.67E+~ L27E+6 2.18E+S 2.57E+3 Ce-141 L99E+4 !.35E+4 6.26E+3 3.62E+S 1.20E+5 L53E+3 Ce-144 3.43E+6 1.43E+6 8.48E+S 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+S 2.00E+S 4.64E+2 Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+S 1. 73E+5 3.65E+2 ...~:;*. 48 Salem ODCH Rev. 2 02/26/8: 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 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+5 9.28E+4 7 .16E+4 Cr-51 7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 l'ln-54 5.11E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 1.24E+5 6.39E+3 S.54E+3 Fe-59 1.59E+4 3. 70E+4 1.53E+6 1. 78E+5 1.43E+4 Co-57 6.92E+2 S.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+S 1.98E+4 Ni-63 S.80E+5 4.34E+4 3-.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 8.64E+4 1. 24E+6 4.66E+4 6.24E+4 Rb-86 1.90E+S 1. 77E+4 8.40E+4 Sr-89 4.34E+5 2.42E+6 3.71E+5 1.2SE+4 Sr-90 1.08E+8 1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 2.94E+6 4.09E+5 1. 77E+4 Zr-95 1.46E+5 4.58E+4 6.74E+4 2.69E+6 !.49E+5 3.15E+4 ... -**** .. - '"tll):.:-95*:-- ... 1.86E+4 1.03E+4 .

1.00E+4 . 7.51E~5 *9:68E+4 5~66E+3 Ru-103 2.10E+3 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag*-11om 1.38E+4 1.31E+4 2._50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 5.36E+5 7.SOE+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+S 2.18E+3 Te-.129m 1.39E+4 6.58E+3 4.58E+3 S.19E+4 1.98E+6 4.0SE+S 2.2SE+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 Cs-134 5.02E+5 1.13E+6 :S.75E+5 :L46E+5 9.76E+3 *s.49E+S Cs-136 5.15E+4 1.94E+S L 10E+5 1.78E+4 1.09E+4 L37E+5 Cs-137

6.70E+5 8.48E+5 3.04E+5 1.21E+5 8.48E+3 3 .11E+5 Ffa-140 5.47E+4 6.70E+1 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 8.88E+3 6.14E+S !.26E+5 2.17E-1-3 Ce-144 4.89E+6 2.02E+6 1.21E+6 1.34E+7 8.64E+S 2.62E-1-S Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+S 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 S.02E+3 3.72E+5 1.82E+5 5.13E+2

~ ~~!!H~~ 49 Salem ODCH Rev. 2 02/26/87 i. l~* Table 2-5 <cont'd> R<ioh Inhalation Pathway Dose Factors - CHILO {mrem/yr per uCi/m3l Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E-+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6 *. 73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 4.22E+4 9.88E+4 Cr-51 8.55E+1 2.43E+1 1. 70E+4 1.08E+3 1.54E+2 Hn-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 L07E+3 Co-58 1.77E+3 1.11E+6 3~44E+4 3.16E+3 Co-60 1.31E+4 7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 2.75E+5 6.33E+3 2.80E+4 Zn-65 4.26E+4 1.13E+5 7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 1.98E+5 7.99E+3 1.14E+5 Sr-89 5.99E+5 2.16E+6 1.67E+5 !".72E+4 Sr-90 1.01E+8 1.48E+7 3.43E+S 6.44E+6 Y-91 9.14E+5 2.63E+6 i.84E+5 2.44E+4 £ffi).

*z:r-95 1.90E+5 4.18E+4 S.96E+4 * -2.23E+6 6.HE+4--3

70E+4 Nb-95 2.35E+4 9.18E+3* .8.62E+3 6.14E-+5 :S.70E+4 6.5SE+3 Ru-103 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+S 1.84E+5 1.43E+7 4.29E+5 i.69E+4.

Ag-110m 1.69E+4 1.14E+4 2.12E+4 S.48E+6 LOOE+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 2.32E~6 4.03E+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 3.02E+3 6.07E+3 6.36E+4 1.48E~6 7. !4E+4 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1. 76E+6 1.82E+5 3.04E+3 I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 2.84E+3 2.73E+4 Cs-134 6.51E+S i.01E+6 3.:SOE+S 1.21E+S 3.85E,*3 2.25E+5 Cs-136 6.51E+4 1.71E+5 9.55E+4 1.45£+4 4.18E+3 L16E+5 Cs-137 9.07E+5 8.25E+5 2.82E+5 i.04E+5 3.62E+3 1.2SE+5 Ba-140 7.40E+4 6.48E+1 2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 i.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 L20E+7 3.89E+5 3.61E+S Pr-14~ 1.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73E+4 9. UE+2 Nd-147 1.08E+4 8.73E+3 4.81E+3 3.28~5 S.21E+4 6.81E-l-2 so

_~t?~~rg;.?'?i)E2*~--~~?If.;~J~:(1'.',1*:i.:>;*;:::;~:jt!.~tf0*'?~,r~r~))~G?~:::'f.f;~~~::~~*2:?w~~?t:"FT'7 :?::G:~~'::*:-~i, *~::~r;:;*;*_::::*t"::~~~~:~::*;

Salem OOCH Rev. 2 02/26/87 ~.<. Table 2-5 <cont'd) ~.:~~... "'**..:.... , R<iol1 Inhalation Pathway Dose Factors - INFANT (mrem/yr per uCi/m3) Nuclide Bone Liver Thyroid Kidney Lun~ 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 2.6SE+4 5.31E+3 S.31E+3 5.31E+3 S.31E+3 5.31E+3 5.31E+3 P-32 2.03E+6 1.12E+S 1.61E+4 7.74E+4 Cr-51 5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.9SE+1 Hn-54 2.53E+4 4.98E+3 LOOE+6 7.06E+3 4.98E+3 Fe-55 L97E+4 i.17E+4 8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 1.02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 Co-58 1.22E+3 7.77E+5 L11E+4 1.82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 l.16E+4 Zn-65 1.93E+4 6.26E+4 3.25E+4 6.47E+5 S.14E+4 3.11E+4 Rb-86 1.90E+5 3.04E+3 S.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+S 2.59E+6 Y-91 5.88E+5 2.45E+6 7.03E+4 1.57E+4 .. . --*--**-**-- *---* ------*-z-.-*9s-----*--1-.1.1i£+5 ---2. 79E+4 * ---- ---------3 **HE +4 i.75E+6---2-.*-17E+4-:-* 2.03E-+4 . -*---- -* Nb-95 L57E+4 6.43E+3 4.72E+3 .4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 4.24E+'3 5.52E+S i.61E+4 6.79E+2 Ru-106 8~68E+4 1.07E+S 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 S.56E+2 1.01E+2 2.65E+6 S.91E+4 1.20E+4 Sb-125 S, 17E+4 4.77E+2 6.23E+1 1.64E+6 !.47E+4 1.09E+4 Te-12Sm 4.76E+3 1.99E+3 1.62E+3 4.47E+S 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 S.47E+3 :S.1SE+4 1.68E+6 6.90E+4 2.23E+3 I-131 3.79E+4 4.44E+4 L48E+7 5.1SE+4 L06E+3 i.96E+4 . Cs-134 3.96E+S 7.03E+S t.90E+5 7.97E+4 l.33E+3 7.4SE+4 Cs-136 4.83E+4 1.35E+5 5.64E+4 . L 1SE+4 :t.43E+3 5.29E+4 Cs-137 S.49E+S 6.12E+5 L 72E+5 7.13E+4 L33E+3. 4.55E+4 Ba-140 5.60E+4 S.60E+1 L34E+1 L60E+6 :S.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 S.2SE+3 5.17E+5 2.16E+4 L99E+3 Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 - 3.1SE+3 3.22E+5 3.12E+4 S.OOE+2 ~!I~~l~ 51 Salem ODCH Rev. 2 02/26/S j \.,

-:.::.~~/'

Table 2-5 <cont'd) R<io>. Grass-Cow-Hilk Pathway Dose Factors - ADULT (mrem/yr per uCi/m3) for H-3 and C-14 <m2

mrem/yr per uCi/aec> for other a Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body

------- ------- 7.63E+2 H-3 ------- - 7.63E+2 ------- ------- 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+S 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1. 71E+10 1.06E+9 1.92E+9 6.60E+8 Cr-51 1. 71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Hn-54 8.40E+6 2.50E+6 2.57E+7 1.60E+6 Fe-SS 2.S1E+7 1.73E+7 9.67E+6 9.9SE+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 1.95E+7 2.33E+8 2.68E+7 Co-57 1.28E+6 3.25E+7 2.13E+6 Co-58 4.72E+6 9.57E+7 1.06E+7 Co-60 1.64E+7 3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 2.92E+9 2.7SE+9 1.97E+9 Rb-86 1.35E+5 L66E+4 5.90E+4 Sr-89 1.45E+9 2.33E+S 4.16E+7 Sr-90 4.68E+10 i.35E+9 L 15E+10 - __ -'l-:~l-. ____ .;8.60E+3 - _______ :: ___________4_~-1~E_+JL..2~-~y-_z_______________ Zr-95 1.07E+5 3.44E+4 5.24E+4 !.77E+6 L50E+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 L02E+3 3.89E+3 L19E+5 4.39E+2 Ru-106 2.04E+4 3.94E+4 1.32E+6 2.58E+3 Ag-110m 5.83E+7 S.39E+7 1.06E+8 2.20E+10 3.20E+7

Sb-124 8.58E+8 1.62E+7 2.08E+6 6.6BE+8 2.44E+10 3.40E+8 Sb-125 6.81E+8 7.61E+6 6.93E+S 5.25E+8 7.SOE+9 1.62E+8 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 6.SOE+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 L1-7E+7 1.86E+8 1.54E+8 5.58E+6

-Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+S ::>.04E+S 9.57E+6 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 L 12E+8 2.43E+8 Cs-134 S.65E+9 1.34E+10 ~.35E+9 LUE+9 2.35E+8 1.10E+10 Cs-136 2.61E+S 1.03E+9 5.74E+6 7.87E+7 L17E+8 7.i!2E+S Cs-137 7.38E+9 1.0lE+lO 3.43E+9 ! .14E+9 1.95E+S 6.61E+9 Ba-140 2.69E+7 3.38E+4 LlSE.;.4 i.93E+4 5.54E+7 1.76E+6 Ce-141 4.84E+3 3.27E+3 t.S2E+3 L2SE+7 3.71Ey2 Ce-144 3.58E+5 1.SOE+S 9.87E+4 1.21E+8 1.92E+t Pr-143 1.59E+2 6.37E+l 3.68E+1 6.96E+S 7.88E+O Nd-147 9.42E+l 1.09E+2 6.37E+1 S.23E+S 6.52E+O @J'f.!~ 52 Salem OOCH Rev. 2 02/26/87 Table 2-5 <cont'd> R< io), Grass-Cow-Hilk Pathway Dose Factors - TEENAGER ' (mrem/yr per uCi/m3) for H-3 and C-14 <m2

mrem/yr per uCi/sec) for other&

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -~----- ------- ------- ------- ------- ------- ------- 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 2.78E+4 1.10E+4 7 .13E+4 8.40E+6 S.OOE+4 Hn-54 1.40E+7 4.17E+6 2.87E+7 2.78E+6 ,_ Fe-55 4.45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 1.10E+8 1.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Rb-86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6 i f~~~}\ Y-91 1.58E+4 6.48E+6 4.24E+2 i j j Zr-95 1.65E+3 5..22E+2 7.67E+2 1.20E+6 3~59E+2 Nb-95 1.41E+5 7.80E+4 7.57E+4 3.34E+8 4.30E+4 .Ru-103 1.81E+3 6.40E+3 1.52E+5 7.75E+2 Ru-106 3.75E+4 7.23E+4 1.80E+6 4.73E+3 A9-110m 9.63E+7 9.11E+7 1.74E+8 2.56E+l0 5.54E+7 Sb-124 1.53E+9 2.82E+7 3.47E+6 1.34E+9 3.08E+10 5.97E+8 Sb-125 1.22E+9 1.33E+7 1.16E+6 1.07E+9 9.48E+9 2.8SE+8 Te-125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+8 LOOE+7 Te-129m L 11E+8 4.10E+7 3.57E+7 4.62E+S 4.1SE+8 !.75E+7 I-131 5.38E+8 7.S3E+8 2.20E+11 1.30E+9 1. 49E+8 4.04E+8 Cs-134 9.81E+9 2.31E+10 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1. 75E+9 9.53E+8 1.SOE+8 1.41E+8 l.18E+9 Cs-137 1.34E+10 1.78E+10 6.06E+9 2.35E+9 2.53E+8 6-.20E+9 Ba-140 4.8SE+7 5.9SE+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+S 1.20E+5 1.53E+3 Ce-144, 6.58E+5 2.72E+5 L63E+5 l.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 6.77E+1 9.61E+S L4SE.(-1 Nd-147 1.81E+2 L97E+2 1.16E+2 7 .11E+5 1.18E+1 6D:fa 53 Salem ODCH Rev. 2 02/26/87 Table 2-5 <cont'd> R< i 0) I Grass-Cow-Hilk Pathway Dose Factors - CHILD (mrem/yr per uCi/m3) for H-3 and C-14 <m2

mrem/yr per uCi/sec> for othera Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI T.Body H-3 1.57E+3 1. S7E+3 1.S7E+3 1. 57E+3 1.S7E+3 1.S7E+3 C-14 1.65E+6 3.29E+S 3.29E+S 3.29E+S 3.29E+S 3.29E+5 3.29E+S P-32 7.77E+10 3.64E+9 2.1SE+9 3.00E+9 Cr-51 S.66E+4 1.SSE+4 1.03E+S S.41E+6 L02E+5 Hn-54 2.09E+7 S.87E+6 1. 76E+7 S.58E+6 Fe-SS 1.12E+8 S.93E+7 3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.9SE+8 S.65E+7 2.03E+8 9.71E+7 Co-S7 3.84E+6 3.14E+7 7.77E+6 Co-S8 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-6S 4.13E+9 1.10E+10 6.94E+9 1.93E+9 6.85E+9 Rb..;.86 8.77E+9 S.64E+8 5.39E+9 Sr-89 6.62E+9 2.56E+8 1.89E+8 Sr-90 1.12E+11 1.S1E+9 2.83E+10 Y-91 9.14E+S 2.63E+6 L84E+5 2.44E+4 Zr-9S 3.84E+3 *a.45E+-2 1.2.1E+3 8.81E+S 7.S2E+2 Nb-95 3.18E+S 1.24E;-5 1.16E+S 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+S

1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 2.63E+8 1.68E+10 L13E+8 Sb-124 3.62E+9 4.70E+7 7.99E+6 2.01E+9 2.Z6E+10 1.27E+9 Sb-12S 2.90E+9 2.24E+7 2.69E+6 1.62E+9 6.93E+9 6.0SE+S Te-125m 7.38E+7 2.00E+7 2.07E+7 7 .12E+7 9.84E+6 Te-127m 2.0SE+S S.60E+7 4.97E+7 S.93E+8 1.68E+8 2.47E+7 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+S 3.32E+8 4.23E+7 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 !.17E+8 7.46E+8 Cs-134 2.26E+10 3.71E+10 1.15E+10 4.13E+9 2.00E+S 7.83E+9 Cs-136 1.00E+9 2.76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9. L93E+8 4.S5E+9 Ba-140 1.17E+8 1.03E+S 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+.4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+6 5.09E+5 2.82E+S 1.33E+8 8.66E+4 Pr-143 7.23E+2 2. i7E+2 1.17E+2 7.80E+S 3.59E+1 Nd-147 4.45E+2 3.60E+2 1.98E+2 S. 71E+S 2.79E+1

't'~j'}i S4 Salem ODCM Rev. 2 02/26/8 Table 2-5 <cont'd) R<io>* Graaa-Cow-Hilk 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 Lunca GI-LLI T.Body

------- ------- 2.38E+3 H-3 ------- 2.38E+3 ------- 2.38E+3 ------- 2.38E+3 ------- ------- ------- 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 9.42E+9 2.17E+9 6.21E+9 Cr-51 1.05E+5 2.30E+4 2.0SE+5 4.71E+6 1.61E+5 Hn-54 3.89E+7 8.63E+6 1.43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 1.16E+8 1.88E+8 1.55E+8 Co-57 8.95E+6 3.05E+7 1.46E+7 Co-58 2.43E+7 6.0SE+7 6.06E+7 Co-60 8.81E+7 2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 9.23,E+9 1.61E+10 S.78E+9 Rb-86 2.22E+10 5.69E+8 1.10E+10 Sr-89 1.26E+10 2.59E+8 3.61E+8 Sr-90 1.22E+11 1.52E+9 3.10E+10 ~;p 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 L18E+3 Nb-95 5.93E+5 2.44E+5 L75E+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 Aca-110m 3.86E+8 2.82E+8 4.03E+8 L46E+10 1.86E+S Sb-124 6.98E+9 1.03E+8 1.85E+7 4.37E+9 2.15E+10 2.16E+9 Sb-125 Te-125m

4.98E+9 1.51E+8 4.82E+7 5.04E+7 6.24E+6 S.07E+7 3.13E+9 6.64E+9 7.1SE+7 1.02E+9 2.04E+7 l

Te-127m 4.21E+S 1.40E+S 1.22E+8 L04E+9 1.70E+8 5.10E+7 Te-129m 5.59E+S L92E+8 2.15E+8 L40E+9 3.34E+S S.62E+7 I-131 2.72E+9 3.21E+9 1.0SE+12 3.75E+9 L15E+S 1.41E+9 Cs-134 3.65E+10 6.80E+10 1.75E+10 7.18E+9 LS5E{-S 6.87E+9 Cs-136 t.96E+9 5.77E+9 2.30E+9 4.70E+8 S.76E+7 2.1SE+9 Cs-137 5.15E+10 6.02E+10 1.62E+10 6.SSE+9 i.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+S S.73E+4 1.48E+5 5.92E+7 L24E+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 L30E+5 Pr-143 1.49E+3 S.59E+2 2.08E+2 7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+1 55 Salem ODCH Rev. 2 02/26/87 Salem ODCH Rev. 2 02/26/87 Table 2-5 <cont'd> r.C R< io) 1 Ve9etation Pathway Oo&e Factors - TEENAGER Cmrem/yr per uCi/m3> for H-3 and C-14 Cm2

mrem/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lun9 GI-LLI T.Body

------- ------- 2.59E+3 H-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+S 2.91E+S 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 1.35E+8 6.23E+7 Cr-51 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Hn-54 4.52E+8 1.35E+8 9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 1.33E+8 9.98E+8 1.63E+8 Co-57 1.79E+7 3.34E.+8 3.00E+7 Co-58 4.38E+7 6.04E+8 f.01E+8 Co-60 2.49E+8 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Rb-86 2.73E+8 4.05E+7 1.28E+8 Sr-89 1.51E+10 1.80E+9 4.33E+8 Sr-90 7 .51E+11 2.11E+10 1.85E+11 Y-91 7.87E+6 3.23E+9 2 .11E+5 6'¢; I"'*." Zr-95 1.74E+6 5.49E+5 8.07E+5 1.27E+9 3.78E+5 Nb-95 L92E+5 !.06E+5 1.03E+5 4.55E+8 S.86E+4 Ru-103 6.87E+6 2.42E+7 5. 7.4E+B 2.94E+6 Ru-106 3.09E+8 5.97E+8 1. 48E+1_0 3.90E+7 Ag-110m L52E+7 1.44E+7 2.74E+7 4.04E+9 8.74E+6 Sb-124 1.SSE+S 2.85E+6 3.51E+5 1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+S 1.88E+S 1.66E+9 5.00E+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 !.37E+9 6.56E+7 Te-129m :S.67E+8 L36E+8 1,.18Ev8 1.54E+9 L38E+9 5.81E+7 I-131 7.70E+7 t.08E+8 3.i4E+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 L45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 5.75E+4 i .14E+5 2.13E+S 8.91E+6 Ce-141 2.82E+5 L88E+5 S.86E+4 5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 L30E+7 L33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3~94E+4 2.32E+4 L42E+8 2.36E+3 57 -_.:..*-~~**_<._:~::::*-"-~:~*'.-"--- Salem ODCH Rev. 2 02/26/Si Table 2-5 <cont'd) R<io)1 Vegetation Pathway Dose Factors - CHILD (mrem/yr per uCi/m3) for H-3 and C-14 <m2

mrem/yr per uCi/sec> for othera Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body

------- ------- 4.01E+3 ------- 4.01E+3------- 4.01E+3 ------- ------- ------- 4.01E+3 ------- 4.01E+3 4.01E+3 H-3 C-14 3.SOE+6 7.01E+5 7.01E+5 7.01E+S 7.01E+S 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 9.30E+7 1.30E+8

Cr-51 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 t1n-54 6.61E-1-8 1.85E+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 4.01E+8 6.49E+8 1.88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 2.45E"+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 2.10E+9 1.12E+9 Ni-63 3.95E+10 2 .11E+9 1.42E+8 1.34E+9 Zn-65 8.12E+8 2.16E+9 1.36E+9 3.80E+8 1.35E+9 Rb-86 4.52E+S 2.91E+7 2.78E+8 Sr-89 3.59E+10 1.39E+9
t.03E+9 Sr-90 i.24E+12 1.67E+10 3.15E+11

~n~\ Y-91 1.87E+7 2.49E+9 5.01E+S .. *Zr-95 *3.90E+6 8~58E+S ~.23E+6. 8.95E+8 7.64E+5 Nb-95 L!.10E+5 1.59E+S 1.SOE+S 2.95E+8 1.14E+5 Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-106 7.4SE+8 1.01E+9 - 1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 4.05E+7 2.58E+9 1. 74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 3.38E+8 4.67E+7 " Te-127m L32E+9 3.56E+8 3.16E+8 3.77E+9 L07E+9 1.57E+8 Te-129m S.54E+8 2.39E+8 2.75E+8 2.51E+9 1.04E+9 L33E+8 I-131 L43E+8 1.44E+8 4.76E+10 2.36E+8 1.28E+7 8 .18E+7 Ca-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1.42E+8 S.54E+9 Cs-136 a*:o6E+7 2.22E+8 !.18E+8 1. 76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 7.46E+9 2.68E+9 1.43E+8 3.38E+9 Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+S L40E+8 1.62E+7 Ce-141 1.23E+S 6.14E+4 2.69E+4 7.66E+7 9.12E+3 Ce-144 1.27E+8 3.98E+7 2.21E+7 1.04E+10 6.78E+6 _f:J 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 .-r,:-*.*.* r r.\*.:~~ 58 APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent 0 0-1 . . ': ~ .* . . . Salem ODCH Rev. 2 02/26/87 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 ana1ysis was performed to provide a *implified method for determining compliance with Technical Specification 3.11.2.3 For the infant age group, the controlling pathway is ~he grass-milk-cow Cg/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 inclu~ing the total body, is the thyroid* and the highest dose contributor is radionuclide I-131. The results for this evaluation are presented in Table D-1. For purposes of simplifying the details of the dose calculatio~ process* it is conservative to identify a controlling. dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. Multiplication of the total release (i.e. cumulative .activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative. For the evaluation of the dose commitment via a controlling pathway and age groupa it is conservative to use the infant* g/m/ca thyroid* I-131 pathway dose factor C1.675E12 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. Fo~ evaluating compliance with the dose limits of Technical Specification D-2 . '. -~.: .r:*.~_*:7 ::: *~***~::~ii':**'..'.~:---:.:---**::; ~::-:--:*:~ *: .~:*' ; '.*.. : **_*: ' . : * ,*;::: *.** I* ** * *, ,* Salem ODCH Rev. 2 02/26187 3.11.2.31 the followin9 simplified eQuation may be used: Dmax = 3.17E-8

W
Rl-131 * [Qi where:

Dmax = maximum organ dose (mrem) W = atmospheric dispersion parameters to the controlling location as identified in Table 3.2-4. X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3) D/Q = atmosperic deposition for vegetation* milk nad 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) Rl-131 = 1-131 dose parameter for the thyroid for the identified controlling pathway = 1.675E12 <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 fo the overall negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radioio"dines <e.g **...-Co-60 and Cs-137>. the ground exposure-pathway may represent a higher dose contribution than either the vegetation or milk oathway. However. use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation. especially considering that no* other radionuclide has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the milk pathway <see Table D-2>. The location of exposure pathways. and the maximum orian soe 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. 0-3 . : *~*,. .... : - -.- ... *' .- . - .... -- ..... ..-.~-- Salem ODCH Rev. 2 02/26/87 ~-* ~* . Table 0-1 Infant Dose Contributions Fraction of Total Organ and Body Dose 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 o.o:z 0.15 Fraction of D.ose Contribution by Pathway Grass-Cow-Hille 0.92 Ground Plane a.as 0 Inhalation
D-4
*.\ .. !" *--* - '.-' . cc---~.-~-~~-*0--,-~~-~~~~~-~-~~- . -* : . ;_ .'\.....-*. . _: .....'.~- .. Salem ODCM Rev. 2 1/9187 E-1 ..*.,. *-* ,.: .* ~ :: .*:~\~-;.;:_:. ~... ;:, -~~.::.'. ~::*:::_';_* ~-~-*_.:_.:~.;.-~._-.:~--~~-*_.:_'._:_,_:=~*.-' .. *. *, - ~*: . : ~ ....:-:* . . ~ .: ~*' .. **.;* . . .,;--~-- :****:: . .. ~ ~-'-'*~*~-'-'-~~ ....... ~- . *:-*,*;** *- '~: ':'*'.*.-: .,_,.'.~"::* .* ".*.- .:'~*::-:**>> \*~ Page 1 ODCM - SALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATioN*coDE LOCATION COLLECTION METHOD ANALYSES . I. DIRECT lFl 5.8 miles N of origin 2 TLD's will be collected Gamma dose 1G3 I 18.5 miles N of origin. from each location quarterly quarterly 2S2 0.4 miles NNE of origin 2El 4.4 miles NNE of origin 2F2 807 miles NNE of origin 2F5 7.4 miles NNE of origin 2F6 7.3 miles NNE of origin 3El 4.1 miles NE of origin 3F2 5.1 miles NE of origin. 3F3 8.6 miles NE of origin: 3Gl t 1606 miles NE of origin 3Hl I 32 miles NE of origin 3H3 I 110 miles NE of origin 402 3.7 miles ENE of origin 5Sl 1.0 mile E of origin 5Dl 3.5 miles E of origin 5Fl 8c0 miles E of origin 6S2 Oo2 miles ESE of origin 6Fl 6.4 miles ESE of origin 7Sl 0.12 miles SE of origin 7F2 9.1 miles SE of origiru 9El 4. 2 miles S of origin ' lOSl Ool4 miles SSW of origin lODl 3.9 miles SSW of origin 10F2 5.B miles SSW of origin Collected quarterly Gamma-dose quarterly lOGl ih 11.6 miles SSW of o~igin ~ Control Station '1 M P85 183/15 4-dh /.\:0 ; : ~*. .;. E E-1 Page 2* OOCM - SALEM.GENERATING STATION ~DIOLOGICAL ENVIRONM~NTAL MONITORING PROGRAM .~ ..* i
.**j

.-'\ =
VH PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES I. DIRECT (Can't) . ' 10F2 5.8 miles SSW of origin Collected quarterly Gamma dose quarterly lOGl I 11.6 miles SSW of origin llSl o.~7 miles SW of oridin 11E2 5.0 miles SW of origin j.. llFl 5.2 miles SW of origin. ...; . 12El 4.4 miles WSW of origin *:! 12Fl 9.4 miles WSW or origin j .i-,
.l 13El 4o2 miles NE of origin. J

13F4 9.8 miles W of origin 13F2 605 miles W of origin

......; 13F3 9.3 miles W of origin.
1401 3.4 miles WNW of origin 14F2 6~6 miles WNW of origin i J 15F3 5.4 miles NW of origin 16Sl 4pl miles NNW of origin 16P2 8.1 miles NNW of origin 16Gl I 14.8 miles NNW of origin '. I -~ I Control Station (in addition to controls listed, two additional program controls are used for internal studies and are referred to as SITE-CAL and SITE-ZERO)
M P85 183/15 4-dh
(0:~:~ ",(,'.'/ '/ TABLE ~-1 Page 3 of 7 ODCM SALEM GENERATING STATION RADIOLOGICAL ENVIRONMEKTAL MONITORING PROGRAM EXPOSURE TYPE AND FREQUENCY PATHWAY STATION CODE LOCATION COLLECTION METHOD OF ANALYSES ~j CI. AIRBORNE (a) P 2S2 Oo4 miles NNE of origin Continous low volume air Gross beta analysis A sampler. Sample collected on each weekly R every week along with filter sample. Gamma T change. spectrometry shall I 2F2 8.7 miles NNE of origin be performed if c gross beta exceeds L ten times the A yearly mean of T control station E value. s 3H3 I 110 miles NE of origin Gross beta analysis done > 24hr. after .... ** J sampling to allow
' for Radon and Thoron daughter decay lODl 3o9 miles SSW of origin'.
16El 4cl miles NNW of origin) Gamma isotopic i analysis on .... i quarterly composite ; -~* ! i Control Station ' ' M PSS 183/15 4-dh '~~~ LE E-1 Page 7 ODCM .- ~ALEM GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE TYPE AND FREQUENCY PATHWAY STATION CODE LOCATION COLLECTION METHOD OF ANALYSES II. AIRBORNE (Con' t) ( b) I 2S2 0.4 miles ~NE of ori~irt . A TEDA impregnated charcoal Iodine 131 analyset 0 flow-through cartridge is are performed on D
connected to air particulate each weekly sample I air sampler and is collected N weekly at filter change.
E 2F2 Bo7 miles NNE of orig ill 3H3 I 110 miles NE of origin r {\;j 4.1 miles NNW of origin *.. , 16iH .\*:--1 . **._-.: 3e9 miles SSW of origin .. lODl .. }* ; ~ Control Station M PSS 163/15 4-dh Page ODCM - SALEM GENERATING STATION RADIOLOGICA~ ENVIRONMENTAL MONITORING PROGRAM LOCATION COLLECTION METHOD ANALYSES PATHWAY STATION CODE XII. WATER l mile W of Mad Horse Sample to be collected Gamma isotopic (a) s 7El monthly providing winter analysis monthly u Creek1 4.5 miles SE of or"igin icing conditions allow R H-3 on quarterly F sample collection composite A c 12Cl ~ West bank opposite E Artificial Island; 2~5 miles WSW of origin 16Fl C&D canal1 6.9 miles NNW of origin * (b) G 2S3 Fresh water holding tankf R 700 feet NNW of origin Gamma isotopic 0 501 Local farm1 3. 5 miles E* Collected monthly of origin monthly u Tritium analysis N 3El Local farm; 4ol miles NE: of origin monthly D I. ' A sediment sample is Gamma isotopic (c) s 7El 1 .miles W of Mad Horse Creek 4.5 miles SE of taken semi-annually anaylsis - semi-E annually D origin I 12Cl fi west bank opposite M Artificial Island~ 2.5,, . <1 miles WSW of origin
.*.: ~<:~ ~ E C&D canah 6. 9 miles NN;w
~' .;.; ' .. l N 16Fl *H T of origin
:.: ~*
I Control Station M PBS 183/15 4-dh '\E) . ~ ~-1 Page ,9 ODCM - SALEN GENERATING STATION ru\DIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION METHOD ANALYSES PATHWAY STATION CODE LOCATION i IV. INGESTION I Gamma isotopic and {a) M 2F4 6~3 miles NNE of origi~! Sample of fresh milk is I-131 analyses on collected for each farm I semimonthly when cows each sample on L are on pasture, monthly collection K at other times * . ::_*;. -~
'*.. 'i
., 3Gl ti 16.6 miles NE qf origin 5F2 lJEJ 4.9 miles W of origin 14Pl 5o5 miles WNW of OLigi~ Two batch samples of fish Gamma isotopic * (b) F llAl Outfall area; approxo analysis of ediblE 650 feet SW of origin ' are sealed in plastic bag I or jar and frozen portion on s semiannually or when in collection H in season 12Cl I west bank opposite Artificial Island1 .' .i 2.5 miles WSW of origin .*.:* ~ Control Station M PBS 183/15 4-dh ,-1 ~! 1 '. l .i Page 7
j
.! . ODCM SALEM GENERATING STATION 'i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PATHWAY STATION CODE LOCATION COLLECTION METHOD ANALYSES
-i IV. INGESTION (Cont'd)
. ( c) I llAl Outfall area: approx. Two batch samples of crab Gamma Isotopic N 650 feet.SW of origin are sealed in a plastic analysis of v bag or jar and frozen edible portion E semiannually or when in on collection R season. T 13Cl I West bank opposite -,' E Artificial Island: B 2.5 miles WSW of origin. R "\ A
T E
s . i ~\ *) I Control Station 0 M P85 183/15 4-dh .; ] ,~ FIGURE E-1 OFFSIT! SA~PLING LOCATIONS ARTIPICIAL IStAND ,_. . --~,.......,,,.. .--.---,-*-*--,_'._.,. : ... -. *.- -:~:--**r**".'*"'-:'-~:**;:** **:=-*7;\**-;*~ ~---- *:-* **--=-7~. :-:~*:~-~*-~~-~::*~;:;~;<~.*~~T- -:~~~.-~~ .,-~*-:--*.::-*-. ---*'.*~*.-:-:-~-*':T:-.---:~-~,.., ...,.. ~--:-z:~'.*-,-.~~...::-,.1"'*:**.~:~~~ ..._-.*~*** ',"*** __ *. ... .. *.*.* .* **;*'. '**'.:*.~:_. ... - * .... \ .....}}

ML18092B445

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