ML18092B039

From kanterella
Jump to navigation Jump to search
Rev 1 to Offsite Dose Calculation Manual
ML18092B039
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/13/1985
From:
Public Service Enterprise Group
To:
Shared Package
ML18092B037 List:
References
PROC-850913-01, NUDOCS 8603100240
Download: ML18092B039 (89)
v • d • e


Text

{{#Wiki_filter:* SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION H!NU!L 8603100240 860228 PDR ADOCK 05000272 R PDR

  • Revision 1 9/13/85

Jalem ODCM Re"'. SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents 9 1 3' 8 5 Introduction

1. 0
2. 0
3. 0 Liquid Effluents
1. 1 Radiation Honitoring Instrumentation and Controls.
1. 2 Liquid Effluent Monitor Setpoint Oetermination
1. 2. 1 Liquid Effluent Monitors ( Rad;iaste, Steam Generator Blo11do11n and Ser~ice Hater)
1. 2. 2 Conservative Default Values
1. 3 Liquid Effluent Concentration Limits -

10 CFR 20

1. 4 Liquid 1. 4. 1
1. 4. 2 Effluent Dose Calculations -

10 CFR 50 Hember of the Public Dose - Liquid Effluents Simplified Liquid Effluent Dose Calculation

1. 5 Secondar:r* Side Radioactive Liquid Effluents -

Dose Calculations During Primary to Secondary Leakage

1. 6 Liquid Eff 1 uent Dose Projection..

Gaseous Effluents

2. 1 Radiation Monitoring Instrumentation and Controls
2. 2 Gaseous Effluent Monitor Setpoint Determination
2. 2. 1 Containment and Plant Monitor
2. 2. 2 Conservati*1e Default Values
2. 3 Gaseous Effluent Instantaneous 2

3 4 5 5 6 0 8 9 1 0 1 2 1 3 1 3 1 4 Dose Rate Calculations - 10 CFR 20 16

2. 3. 1 Site Boundary Dose Rate -

Noble Gases 16

2. 3. 2 Site Boundary Dose *Rate -

Radioiod1ne and Particulates 17

2. 4 Noble Gas Effluent Dose Calculations -

10 CFR 50 18 2.. J.. t UNRESTP.IGTED AP.EA Dose - Noble Gases. 18

2. 4. 2 Simplified Dose Calculation for Noble Gases 19
2. 5 Radioiodine and Particulate Dose Calculations -

1 O CFR 50 19

2. 5. 1 UNRESTRICTED AREA Dose -

P.ad1oiodine and Particulates 19

2. 5. 2 Simplified Dose Calculation for Radioiodines and Particulates.
2. 6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations
2. 7 Gaseous Effluent Dose Projection Special Dose Analyses
3. 1 Doses *Due To Acti*lities Inside the SITE BOUNDARY
3. 2 Doses to MEMBERS OF THE PUBLIC -

40 CFR 190

3. 2. 1 Effluent Dose Calculations.
3. 2. 2 Direct* Exposure Determination 20 21 2-l 26
28.

28 29

4. O Radiological En*;ironmental Monitoring Program 30

.. ~ _.. ..... :.:.!~. '.' ~.. -... Salem ODCM Re*1. 9 : 1 3 8 5 Table of Contents - Continued Tables 1 -1 1 -2 1 -3 1 -4 2-1 2-2 2-3 2-4 2-5 A-1 A-2 B-1 B-2 C-5 Parameters for ~iquid Alarm Setpoint Determ1nat1on - Unit 1 Parameters for Liquid Alarm Setpoint Determination - Unit 2 Site Related Ingestion Dose Commitment Factors, A10 Bioaccumulation Factors CBFil Dose Factors for Noble Gases Parameters for Gaseous Alarm Setpoint Determinations - Unit 1 Parameters for Gaseous Alarm Setpoint Determinations - Unit 2 Controlling Locations, PathKays and Atmospheric Dispersion for Dose Calculations. PathKay Dose Parameters - Atmospheric Releases Calculation of Effective MPC - Unit 1 Calculation of Effective MPC - Unit 2 ~dult Dose Contributions Fish and Drinking Hater PathKays Unit 1 Adult Dose Contributions Fish and Drinking Rater PathKays Unit 2 Effective Dose Factors Appendicies Appendix A Evaluation of Conservative, Default MPC Value for Liquid Effluents. Appendix B - Technical Basis for Effective Dose Factors - Liquid Radioactive Effluents. Appendix C - Technical Bases for Effective Dose Factors - Gaseous Radioactive Effluents Appendix D - Radiological Environmental Monitoring Program - Sample T;*pe, Location and Anal;:sis 33 3 4 35 37 41 42 43 H 47 A-4 A-5 B-5 B-5 C-5 A-1 B-1 C-1 D-1

Salem ODCM Rev. SALEH NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION HANUAL 9113185 The Salem Offsite Dose C~lculation Manual COOCH) describes the methodology and parameters used in: 1 ) the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/tr-ip setpoints; and 2) the calculation of r-adioactive liquid ~nd gaseous concentr-ations, dose rates and cumulative quarter-ly and yearly doses. The methodology stated in this manual is acceptable for-use in demons tr-a ting compliance 1ri th 1 0 CFR 20. 106, 10 CFR 50, Appendix I and 40 CFR 190. Hore conservative calculational methods and/o~ conditions Ce. g., location and/or exposure path1raysl expected to yield higher computed doses than appr-opriate for-the maximally exposed person may be assumed in the dose evaluations. The ODCH 1rill be maintained at the station for use as a refer-ence guide and tr-aining document of accepted methodologies and calculations. changes Ifill be made to the ODCM calculational methodologies and par-ameters as is deemed nece3sary to ansute r-easonable c~nservatism in keeping Rith the principles of 10 CFR 50. 36a and Appendix I for-demonstrating radioacti*1e effluents are il.LAF.A. NOTE: As used thr-oughout this

document, excluding acr-onyms,
ords appear-ing all capitalized denote the application of definitions as used in the Salem Technical Specifications.

-~ .)

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

Salem ODCH Rev. 911 3/85 The liquid effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance R"ith the Salem Radiological Effluent Technical Specifications are summarized as folloR"s:

1)
2) algrffi-lggg_AYtQffig~i~-I~rminstiQnL R18 CITnit 1l and 2-R18 <Unit 2l provide the alarm and automatic termination of liquid radioactive material releases as required by Te.chnical Specification 3. 3. 3. 8.

1-R19 A, B,C,and D provide the alarm and isolation function for the Unit 1 steam generator bloRdoRn lines. 2-R19 A,B,C and D provide this function for Unit 2. Algrffi_LQilllL - The alarm functions for the Service Hater System are provided bv the radiation monitors on the Containment Fan Cooler discharges ( 1 -R 1 J A, 8, C, D and E for Unit 1 and 2-R 13 A, B, and C for Unit 2l. Releases from the secondary system are routed through the Chemical ~aste Basin R"here the effluent is monitored (with an alarm function) by R3-prior to release to the environment. Liquid radioactive R"aste floR' diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 1-1 and 1-2 for Units 1 and 2, respectively. 2

  • j

'{~

  • .-~

' *... ;;,~:.. Sal em ODCM Re*1. 9/13/85 Per-the r-equir-ements of Technical Specification 3. 3. 3. 8, al.arm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of Specification 3. 11. 1. 1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for r-adionuclides and 2.0E-04 uCi/ml for dissolved or-entrained noble gases). The follo;;ing equation~ must be satisfied to meet the liquid effluent restrictions:

here

c = c = f F = c ( F+fl f the effluent concentration limit of Technical ( 3. 11. 1. 1 l implementing the 10 CFR 20 MPC for the site, ( 1. 1) Specification in uCi/ml the setpoint, in uCi/ml,. of the r-adioacti *;i t:l monitor measuring the radioacti~ity concentration in the effluent line ~rior to dilution and subsequent release; the

setpoint,
hich is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flo;; of the dilution stream plus the effluent stream, repr-esents a value ;ohich, if exceeded, ;;ould result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA the flo;; rate at the radiation monitor location, in volume per unit time, but in the same units as F, belo.-

the dilution ;;ater flo;; rate as measured prior to the release point, in volume per unit time CNote that if no dilution is provided, large compared to (fl, then ( F + f) ~ c $.. c. F. l Al so, note that ;,hen (Fl is Adapted from NUREG-0133 3

  • 1 l
  • --~

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

  • Salem ODCH Rev.

9/13,'85

1. 2. 1 The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the follo"ing equations:

where: SP HP Ce Ci HP Ci = SEN CH RR = bkg = HPCe 1r. SEN 1r. CH SP $. i" bkg ( 1. 2 j RR with: L Ci HPCe = ------------ ( 1. ] ) alarm setpoint corresponding to the maximum allo;rable release rate (cpmi an effective HPC value for the mixture of radionuclides in the effluent stream ( uCi/mll the concent~ation of radionuclide i in the liquid effluent (uCi/mll the HPC value corresponding to radionuclide i from 10 CFR 20, llppendix B, Table II, Column 2 ( uCi/mll the sensitivity value to "hich the monitor is calibrated ( cpm per-uCi/mll the cir-culating Rater floR rate (dilution ;rater-flo;r) at the time of release (gal/min) the liquid effluent releaser-ate (gal/min) the background of the monitor- (cpml The radioactivity monitor-setpoint equation ( 1. 2l remains valid during outages ~hen the circulating "ater dilution is potenti&lly at its lo;rest value. Reduction of the ~aste str-eam floR (RR) may be necessary during these periods to meet the discharge criteria. HoRever-, in order-to maximize the available plant discharge dilution and thereby minimize the potential offsite

doses,

~el eases from either Unit-1 or Unit-2 may be routed to either the Unit-1 or-Unit-2 Circulating Rater System discharge. This routing is possible via inter-connections bet~een the Service Hater Systems (see Figures and 2). Procedural res~rictions prevent conducting simultaneous releases from either a single unit or both units into a single Circulating Rater System discharge. 4

-~ '~-.-. - -. - :~_ t:.* -. -*- Salem ODCH Rev. 9/13/85

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-2, cespectively. They are based upon the folloRing: a) substitution of the default effective HPC value of 1E-05 uCi/ml for radRaste releases (~efer to Appendix A for justificationl; bl for additional conservatism*, substitution of the I-131 HPC value of 3E-07 uCi/ml for the R19 Steam Generator blowdown

monitors, R13 Service Hater monitor and R37 Chemical Haste Basin monitor; cl substitutions of the lowest operational circulating Rater floR, in gal/min; and, dl substitutions of the highest alloRed effluent release C"'ate, in gal/min.

aith pre-established alar'm setpoints, it is possible to control the C"'adRaste C"'elease C"'ate (RR) to ensure the inequality of equation ( 1. 2) is maintained under changing values for' HPCe and for' differing CiC"'culating Rater' System dilutions. Technical Specification

3. 11. 1. 1 limits the concentr'ation of C"'adioactive mateC"'ial in liquid effluents (after' dilution in the CiC"'culating Hater System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for C"'adionuclides other' than noble ga~es.

Noble gases are limited to a diluted concentration of 2. OE-04 uCi/ml. Release C"'ates are contt"'olled and Ose of the effective HPC value as deC"'ived in Appendix A may be non-conservative for' the R19 Steam GeneC"'atoC"' blowdown monitor's and*R37 Chemical Haste Basin monitors wheC"'e I-131 transfer' dut"'ing pC"'imary to secondary leakage _may potentially be more controlling. 5

~.*..

'.*.:,'.:r: * ;. *.. *,:;,:.~

Salem ODCH Rev. 9/13/BS radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded. Ho Kever, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance Rith the concentration limits of Technical Specification 3.11.1.1 may be performed using the folloMing equation: [2= (--=:~)

  • ( ---~~-~]

HPCi CR + RRf ( 1. 4) Mhere: Ci = actual concentration of radionucl.ide i as measured in the undiluted liquid effluent ( uCi/mll HP Ci the 11PC value corresponding to radionuclide i from 1 0 CFR 20, Appendix B, Table II, Column 2 (uCi/mll = 2E-04 uCi/ml for dissolved or entrained noble gases RR = the actual,liquid effluent release rate (gal/min) CR. = the actual circulating Mater floM rate (dilution Mater f loll') at the time of the release (gal/min) 1. 4. 1 Technical Specification

3. 11. 1. 2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:

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. 6

  • .. ;:* *-~*

Sal em ODCH Rev. 9113/85 Per the surveillance requirements of Technical Specification

4. 11. 1. 2, the folloKing calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem.

Ii here: Do Aio

1. 67E-02
  • VOL Do =
  • ,1; [c Ci "' Aiol

( 1. 5) CH = dose or dose commitment to organ o, including tot.al body.( mrem) = site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per uCi/mll Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uCi/ml) VOL = volume of liquid effluent released (gal) CH = average circulating Kater discharge rate during release period (gal/min)

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

The site-related ingestion dose/dose commitment factors CA are presented in io Table 1-3 and have been derived in accordance Kith guidance of NUREG-0133 by the equation: K he re: Aio Alo = 1.14E+05 C(UI

  • Biil + CUF

,1; BFi)J DFi ( 1. 6) = composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathKays (mrem/hr per uCi/mll

1. 1iE+05

=conversion factor (pCi/uCi *ml/kg~ hr/yr) DI adult invertebrate consumption (5 kg/yrl BI1 bioaccumulation factor for radionuclide i in invertegrates from Table 1-4 (pCi/kg ~ pCi/ll OF = adult fish consumption ( 21 kg/yr) 7

. ;,,~: __...... ~._,; ~ 1 ~1 -1 I.** I * ~ BFi DFi ., *... i* *.. -*- Salem ODCH Rev. 9113/85 bioaccumulation factor for radionuclide i in fish from Table 1-4 CpC1/kg per pCi/1) = dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E-11 of Regulatory Guide 1. 109 ( mremipCil The radionuclides included in the periodic dose assessment per the requirements of Technical Specificatio*n 3/4. 11. 1. 2 are those as identified by gamma spectral analysis of the liquid ;;aste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11-1. Radionuclides requiring radiochemical analysis Ce. g., Sr-89 and Sr-90) ;;ill be added to the dose analysis at a frequency consistent Kith the required minimum analysis frequency of Technical Specification Table 4. 11-1. In lieu of the individual radionuclide dose assessment as presented in Section

1. 4. 1, the folloi;ing simplified dose calculational equation may be used for demonstrating compliance
i th the dose limits of Technical Specification 3. 11. 1. 2.

(Refer to Appendix B for the derivation and justification for this simplified method. l

here

Ci !/OL c lf Dtb Dmax ( 1. 7) (,. 8) average concentration of radionuclide i, in undiluted liquid effluent representative of the volume YOL C uCi/mll volume of liquid effluent released (gall = average ~irculating Kater discharge rate during release period C gal /min) conservatively evaluated total body dose Cmreml = conservatively evaluated maximum organ dose Cmreml 8

~-- -. ~---- "o{..

.~:.,*..

Salem ODCH Rev. 9' 1 3. 8 5

1. 21Et03

= conversion factor (hr/mini and the conservative total body dose conversion factor ( Fe-59, total body -- 7. 27E-t04 mremihr per uCi/mll

2. 52E+04 conversion factor (hr/mini and the conservative maximum organ dose conversion factor C Nb-95, GI-LLI --
1. 51 E-t06 mrem/hr per uCi/mll
1. 5

~§gQnQsr~--~ig§ __ BsQiQs£ti~§_bigyig_~fflY§Ilt§_snQ_QQ§§_gslgYlstiQn§_Qyring f rimsrY __ tQ_§§£QnQsr~_b§s~s9§ 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 bloNdonn monitors (R19l and the Chemical Haste Basin monitor CRJ7l. HoNever 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 Haste Basin with the major source of activity being the Steam Generator blowdoRn. Mith identified radioactive material levels in the secondary system, appropriate samples should be collected and analyzed for the principal gamma emitting radionuclides. Based on the identified radioactive material levels and the volume of Nater discharged, the resulting environmental doses may be calculated based on equation ( 1. 5). Because the release rate from the secondary system is indirect Ce. g., SG blowdown is normally routed to condenser Nhere the condensate clean-up system Nill remove much of the radioactive material), samples should be collected from the final release point (i.e., Chemical Haste Basini for quantifying the 9

~ -.. - "-~ - -,;.* --~*., -.~- Salem ODCH Rev. 9/13/85 -~ l:'adioactive Roiiever-, material releases. for-consel:'vatism and ease of contl:'olling and quantifying all potential release paths, it is prudent to sample the SG bloiidolfn and to assume all radioactive material is released directly to -~ ' the envir'onment via the Chemical ijaste Basin. This approach ;ihile not exact, is conservative and ensures timely analysis for l:'egulatol:'Y compliance. Accounting I ,';j fol:' radioactive material retention of the condensate clean-up system ion

I "J
]

exchange l:'esins may be needed to more accurately account for actual releases. 1 Technical Specification

3. 11. 1. 3 requires that the liquid radioactive lfaste "j

-:1 processing system be used to reduce the radioactive material levels in the ~ liquid liaste prior to r'elease iihen the quarterly projected doses exceed: -- ~

0. 375 mrem to the total body, or j *
  • i
    • f
1. 25 mrem to any organ.

'.j The applicable liquid lfaste processing system for maintaining radioactive --~~ material releases ALARA is the ion exchange system as delineated in Figure 1-3. Alternately, the lfaste evaporator' as pr'esented in the Salem FSAR has pr'ocessing capabilities meeting the NRC ALARA design requirements and may be used in conjunction or in lieu of the ion exchange system for lfaste pl:'ocessing require- .-) -.~ ments in accordance lfith Technical Specification 3. 11. 1. 3. These processing l:'equirements are applicable to each unit individually. Exceeding the projected dose requiring processing prior to J:'elease for' one unit does not in itself dictate processing l:'equirements for' the other-unit. -. ~ 1 0

. i

  • I
j ;

'.1

-t

.*i

  • )

._j I J .. _.- ***"-- *~.. .. ~ -..

  • ~.. J:

_.\\.. *:- Salem ODCM Rev. 9/13/85 Dose projections are*made at least once per 31 days by the following equations: Dtbp Dtb ( 91 + dl ( 1. 9) Dmaxp Dmax ( 91 ~ dl ( 1. 1 Q) ~here: Dtbp the total body dose projection for current calendar quarter ( mrem) Dtb = the total bocty dose to date for current calendar quarter as Dmaxp = Dmax = d = 91 = determined by equation ( 1. 5l or ( 1. 7) ( mrem) the maximum organ dose projection for current calendar quarter ( mreml the maximum organ dose to date for current calendar quarter as determined by equation ( 1. 5) or < 1. 8) C mreml the number of days to date for current calendar quarter. the number of days in a calendar quarter 11

.. "~"'... Salem ODCH Rev. 9/13185 The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance Kith the Radiological Effl~ent Technical Specifications are summarized as follolfs:

1)

Hs§t~_gg§_HQlQYQ-~l§t~m - The vent header gases are collected by the Kaste gas holdup system. Gases may be recycled to provide cover gas for the CVCS hold-up tank or held in the Raste gas tanks for decay prior to release. Raste 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 Raste gas decay tank releases for Unit-1; this function is provided by 2-R41C for Unit-2. 2l ~Qnts~nm~nt_fyrg~_sn9_ft§§§Yt~lYs~YYm_B~l~§f - Containment purges and pressure/vacuum reliefs are released to the atmosphere via the respective unit Plant Vent. Hoble gas monitoring and auto isolation function are provided by 1-R41C for Unit-1 and 2-R41C for Unit-2. Additionally, in accordance Kith Technical Specification 3. 3. 3. 9, Table 3. 3-13, 1-R12A and 2-R12A may be used to provide the containment monitoring and automatic isolation function during purge and pressure/vacuum reliefs.* . 3) The Plant Vent for each respective unit receives discharges from the Kaste gas hold-up system, condenser evacuation system, containment purge and pressure/vacuum reliefs, and the Auxiliary Building ventilation. Effluents are monitored by R41C, a flow through gross activity monitor (for noble gas monitoring). Additionally, in-line gross activity monitors (1-R16 and 2-R16) provide ~edundant 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, respectively.

Plant Vent floK rate is measured and as a back-up may be determined empirically as a function of fan operation (fan curves). Sampler floK rates are dete~mined by floK rate instrumentation le. g., venturi rotometerl. The R12A monitors also provide the safety function of containment isolation in the event of a fuel handling accident during refueling. During MODE 6 in accordance

ith Technical Specification 3/4. 3. 3, Table
3. 3-6, the R12!

alarm/trip setpoint shall be established at tKice background, providing early indication and containment isolation accompanying unexpected increases in containment airborne radioactive material levels indicative of a fuel degradation. 1 2

Salem ODC!1 Rev. 9113/85 A gaseous radioactive 11aste flow diagrams 11ith the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 2-1 and 2-2 for crnits 1 and 2, respectively.

2. 2. 1 Per the requirements of Technical Specification
3. 3. 3. 11, alarm setpoints shall be established for the gaseous effluent monitoring ins~rumentation 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 sampl~ analysis of the applicable release ( i. e., grab sample of the Containment atmosphere, waste gas decay tank, or Plant Vent), the radiation monitoring alarm setpoints may be established by the follo11ing 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: 11here: FRAC FRAC = [ 4. 72E+02

  • X/Q
  • VF
  • L (Ci
  • Kill :- 500

( 2. 1 ) FRAC = (4.72E+02

  • X/Q *VF"' [cci *(Li+ 1.1 Hi))] :-*3000

( 2. 21 = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flo~ rate X/Q = annual average meteorological dispersion to the controlling site boundary location Csec/m3l VF = ventilation system flo11 rate for the applicable release point and monitor ( ft3/minl Ci concentration Of noble gas radionuclide i as determined by radioanalysis of grab sample ( uCi/cm3) Ki total body dose conversion factor for noble gas radionuclide i ( mrem/yr per uCi/m3, from Table 2-1) Li = beta skin dose conversion factor for noble gas radionuclide i ( mrem/ yr pet" uCi/m3, ft"Om Table 2-1 ) Hi = gamma air dose conversion factor for noble gas radionuclide i ( mrad/ :,rr per uCi/m3, from Table 2-1) , 3

l r 1

1. 1

=

4. 72E+02 500 3000 Salem ODCH Rev.

1* 9/13/85 mrem skin dose per mrad gamma air dose {mrem/mradJ conversion factor Ccm3/ft3 *min/sec) total body dose rate limit (mrem/yrl skin dose rate limit Cmrem/yrl Based on the more limiting FRAC (i.e., higher value) as determined

above, the alarm setpoints for the applicable monitors (R16, R41 C, and/or R12Al may be calculated by the equation:

SP = [AF

  • 2= Ci "' SEN : FRACl

+ bkg ( 2. 3) 111here: SP = alarm setpoint corresponding to the maximum alloRable release rate ( cpm) SEN = monitor sensitivity Ccpm per uCi/cm3) bkg background of the monitor Ccpml AF = administrative allocation factor for the specific. monitor and type

release, Rhich corresponds to the fraction of the total allo111able release rate that is administratively allocated to the release.

The allocation factor (AFl is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek Rill not exceed the regulatory limit~ on release rate from the site Ci. e., the release rate limits of Technical Specification 3. 11. 2. 1). Normally, the combined AF value for Salem Units 1 and 2 is 0. 5 ( 0. 25 per unit), i;ith the remainder 0. 5 allocated to Hope Creek. Any increase in AF above 0. 5 for the Salem Nuclear Generating Station ~ill be coordinated Rith 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 analysis, t~ eliminate the potential of periodically having to adjust the

~etpoint to reflect minor changes in radionuclide distribution and variations in release floi; rate. The alarm setpoint may be conservati~ely determined by the default values presented in Table 2-1 and 2-2 for Units 1 and 2, re spec ti vel y. 1 4

... :.i ~-... : --~.:'..:' : *_.:.* Salem ODCH Rev. 9/13/85 These values ar-e based upon: the maximum ventilation (or-pur-gel flo;o r-ate; a r-adionuclide distr-ibution"' compr-ised of 95% Xe-133, 2% Xe-135, 1 % Xe-133m, 1% Kr-88 and 1% Kr--85; and an administrative allocation factor-of

0. 25 to conser-'latively ensure that any simultaneous releases fr-om Salem Units 1 and 2 do not exceed the maximum allo~able r-elease r-ate.

For this radionuclide distribution, the alar-m setpoint based on the total body dose r-ate is more r-estr-ictive than the car-responding setpoint based on the skin dose r-ate. The r-esulting conservative, default setpoints are presented in Tables 2-2 and 2-3. Adopted from ANSI N237-19i6/ ANS.:.18. 1, Source Ter-m Specifications, Table 6 1 5

.j

/:~:.

Salem ODC!1 Rev. 9/13/85 Technical Specification

3. 11. 2. 1 a limits the dose rate at the SITE BOUNDARY due to noble gas releases to

~500 mr-em/ yr, total body and ~3000 mrem/yr, skin. Radiation monitor alarm setpoints ar-e established to ensur-e that these release limits are not exceeded. In the event any gaseous releases from the station results in an alar-m setpoint being

exceeded, an evaluation of the SITE BOUNDARY dose r-ate r-esulting fr-om the r-elease may be per-for-med using the folloRing equations:

Kher-e: btb bs XJQ Qi Ki Li Mi

1. 1 Dtb = XI Q " L ( Ki "' Qi)

( 2. 4) and Os= X/Q * [((Li + 1.1HiJ

  • Qil

( 2. 5) = total body dose rate (mr-em/yr-l skin dose rate (mrem/yrl = atmospher-ic disper-sion to the controlling SITE BOUNDARY location ( sec/m3) average r-elease rate of r-adionuclide i over-the r-elease period under-evaluation (uCi/secl = total body dose conver-sion factor-for noble gas r-adionuclide i ( mr-em/yr per uCi/m3, fr-om Table 2-1 l = beta skin dose conversion factor for noble gas r-adionuclide i ( mr-em/yr per-uCi/m3, fr-om Table 2-1 l gamma air-dose conversion factor-for noble gas radionuclide i Cmr-ad/yr per uCi/m3, from Table 2~1) = mrem skin dose per mrad gamma air dose Cmrem/mradl As appropr-iate, simultaneous r-eleases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the r-elease r-ate limits of Specification

3. 11. 2. 1 a, folloRing any r-elease exceeding the above pr-escr-ibed alar-m setpoints.

Monitor indications (readings) may be averaged over-a time per-iod not to exceed 15 minutes when determining noble gas release r-ate based on corr-elation of the monitor reading and monitor sensitivity. The 15 minute averaging is needed to allow for re~sonable monitor-re,ponse to potentially changing radioactive material concentrations and to exclude potential electronic 1 6

. 1 .. : ;*. :'.*: - ~- _, '..... ...~ *. *. ~'.~--:. Salem ODCH Rev. 9/13/85 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.

HoKever, 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 Kith the limits of SpeciEication

3. 11. 2. 1 a.

Actual meteorological conditions concurrent Kith 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 Technical Specification 3. 11. 2. 1. b limits the dose rate to ~1500 mrem/yr to any organ for I-1 31 I tritium and particulates with half-lives greater than a days.

To demonstrate compliance Kith this

limit, an evaluation is performed at a

frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The folloKing equation may be used for the dose rate evaluation: Khere:. Do X/Q

  • Ri Qi Do

= XIQ "' L ( Ri

  • Qil

( 2. 6) = average organ dose rate over the sampling time period Cmrem/yr> = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathKay Csec/m3) = dose parameter for radionuclide ~. ( mrem/yr per uCi/m3) for the child inhalation pathRay from Table 2-5 average release rate over the appropriate sampling period and analysis frequency for radionuclide i -- I-131, I-133, tritium or other radionuclide in particulate form Kith half-life greater than a days C uCi I sec) 1 7

Salem ODCH Rev. 9/1 3/85 By substituting 1500 mrem/yr for Do and solving for Q, an allo11able release rate for I-131 can be determined. Based on the annual average meteorological dispersion (see Table 2-4) and the most limiting potential path11ay 1 age group and organ (inhalation, child, thyroid -- Ri = 1. 62E+07 mrem/yr per uCi/mJl, the allo11able 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 period, 11hich is the nominal sampling and analysis frequency tor I-131, the cumulative release is 6. 3 Ci. Therefore, as long as the I-1 31 releases in any 7 day period do not exceed 6. 3 Ci, no additional analyses are needed for verifying compliance 11ith the Technical Specification

3. 11. 2. 1. b limits on allo11able release rate.
2. 4. 1 Technical Specification 3. 11. 2. 2 requires a periodic assessment of releases of noble gases to evaluate compliance 11ith the quarterly dose limits of

~5 mrad, gamma-air and ~10 mrad, beta-air and the calendar year *limits ~10 mrad, gamma-air and ~20 mrad, beta-air. The limits are applicable separately to each unit and are not combined site limits. The follo11ing equations may be used to calculate the gamma-air and beta-air doses:

,here

D~ Op XIQ D.r =

3. 17E-08 " X/Q

,~ L (Mi

I; Qil

( 2. 7) and

3. 17E-08 " X/Q " I (Ni

-~ Qi) ( 2. 8) = air dose due to gamma emissions for noble gas radionuclides (mradl air dose due to beta emissions for noble gas radionuclides (mradl atmospheric dispersion to the controlling SITE BOUNDARY location ( sec/m3l 1 8

.-.1 . ~ Qi Hi Ni

  • - ** -- *.* ~*
  • .:.~ *._.: :.

'- "' * --~->.-\\.--::'.. *...: * *. - - Salem ODCH Rev. 9/13/85 cumulative release of noble gas radionuclide i over th~ period of interest ( uCil = air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per uCi/m3, from Table 2-1) = air dose factor due to beta emissions from noble gas radionuclide i ( mrad/yr per uCi/m3, Table 2-1 l 3.17E-08 conversion factor (yr/sec) In lieu of the individual noble gas radionuclide dose assessment as presented

above, the folloi.ing simplified dose calculational equations may be used for verifying compliance Ni th the dose limits of Technical Specification 3. 11. 2. 2.

(Refer to Appendix C for the derivation and justification for this simplified method. l where: Hef f Neff

0. 50 3.17E-08

=

  • X/Q
  • Heff *

( 2. 9) 0.50 and

3. 1 7E-08.

X/Q

  • Neff

.~ L Qi ( 2. 10)

0. 50
5. 3E+02, effective gamma-air dose factor ( mrad/yr per uCi/m3l
1. 1 E+03, effective beta-air dose factor ( mrad/yr per uCi/m3l

= conservatism *factor to account for potential variability in the radionuclide distribution Actual meteorological conditions concurrent with the release period or the

default, annual average dispersion parameters as presented in Table 2-4, may be used for the evaluation of the gamma-air and beta-air doses.
2. 5. 1 accordance with requirements of Technical Specification 3. 11. 2. 3, a

periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of ~7. 5 mrem and calendar year limit ~15 mrem to any organ. The folloi.ing equation may 1 9

. --~ ~.. :_.

    • -- ___..;.~ *-*........
  • .' u_,;_-; * ;;'._..;; * *'*

. ~

  • j I

Salem ODCH Rev. 1 9/13/85 be used to evaluate the maximum organ dose due to releases of I-131, tritium and particulates with half-lives greater than 8 days:

rhere

Daop Ri Qi SFp Daop =

3. 17E-08 "' H "' SFp "' L ( Ri "' Qil

( 2. 11 ) dose or dose commitment via controlling pathway p and age group a (as identified in Table 2-4) to organ o, including the total body C mreml = 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/m3l D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2) dose factor for radionuclide i, Cmrem/yr per uCi/m3) or (m2 mrem/yr per uCi/secl from Table 2-5 for each age group a and the applicable pathway p as identified in Table 2-4. Values for Ri were derived in accordance with the methods described in NUREG-0133. = cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form

rith half-life greater than 8 days (uCil.

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

1)

For milk and vegetation exposure path;rays: A six month fresh vegetation and grazing season through October)*

0. 5 2l For inhalation and ground plane exposure pathways:

= ,. a Of C Hay For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway and the child age group is controlling for the 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. 5. 2 In lieu of the individual radionuclide ( I-131 and particulates) dose assessment as presented
above, the following simplified dose calculational equation may be 20

Salem ODCM Rev. 9/13/85 used for verifying compliance with the dose limits of Technical Specification 3.11.2.3. Dmax = 3.17E-OB

  • H
  • SFp
  • RI-131 * ~ Qi

( 2. 1 2) where: maximum organ dose (mreml Dmax = ' RI-1 31 = I-131 dose ~arameter for the thyroid for the identified controlling pathway =

1. 05E+12, infant thyroid dose parameter with the cow-milk pathway controlling Cm2 - mrem/yr per uCi/secJ The ground plane exposure and inhalation pathways need not be considered when the above simplified calculational method is used because of the ovetall negligible contribution of these pathways to the total thyroid dose.

It is recognized that for some particulate radionuclides Ce.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway.

However, use of the I-131 thyroid dose parameter for all radionuclides will 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.

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. 2J.

Otherllise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-4. 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 ~eleased via the 21

I. I -,..: *.. J*; Salem ODCH Rev. 9/1 3/85 condenser evacuation system and Rill be monitored and quantified by the routine plant vent monitoring and sampling system and procedures Ce. g., R15 on condenser evacuation, R41C on plant vent, and the plant vent particulate and charcoal samplers). Ho Kever, if the Steam Generator bloRdown is routed directly to the Chemical Raste Basin (via the SG blowdown flash tankl 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 Ci. e., releases due to moisture carry over). Since this pathRay is not sampled or monitored, it is necessary to calculate potential releases. Based on the guidance in NRC NUREG-0133, the releases of the radioiodines and particulates may be calculated by the equation: Qi Ci* Rsgb

  • Fft * (1-SQftvl (2.13)

Khere:

  • Qi

= the release rate of radionuclide, tank vent CuCi/secl i I from the steam.generator flash Ci = the concentration of radionuclide, i I in the secondary coolant water averaged over not more than one Reek ( uCi/mll Rsgb = the steam generator bloKdown rate to the flash tank (ml/ sec) Fft = the fraction of bl0Rdo1rn flashed in the tank determined from a heat balance taken around the flash tank at the applicable reactor power level SQftv = the measured steam quality in the flash tank vent; or an assumed value of 0. 85, based on NUREG-0017. Tritium releases via the steam flashing may also be quantified using the above equation Kith the assumption of a steam quality ( SQftvl equal to 0. Since the H-3 Rill be associated Kith the water molecules, it is not necessary to account for the moisture carryover Khich is the transport media for the radioiodines and particulates. 22

.l ~ ~--... Salem ODCl1 Rev. 9; 1 3/85 Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam ( Fft) is approximately O. 48. The equation simplifies to the following: Qi = 0. 072 Ci Rsgb ( 2. 1 4) For H-3, the simplified equation is: Qi = 0. 48 Ci Rsgb ( 2. 1 5) Also during reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs CPORV) and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust. The evaluation of the radioactive material concentration in the steam relativs to that in the steam generator Kater is based on the guidance of NUREG-0017, Revision

1.

The partitioning factors for the radioiodines is 0. 01 and is 0. 001 for all other particulate radioactive material. The resulting equation for quantifying releases via the atmospheric steam releases is: Kher'e: Qij SFj PF Qij= 0.13 "'L(Cij "'SFj) "'PF j release rate of r'adionuclide i via pathway j CuCi/sec) = steam flow for release pathway j 450,000 lb/hr per PORV = 800,000 lb/hr per safety relief valve = 50,000 lb/hr for auxiliary feed pump exhaust = partitioning factor', ratio of concentration in steam to that in the Kater in the steam generator

0. 01 for radioiodines

= 0. 005 for all other particulates

1. 0 for-H-3 23

( 2. 1 5)

'. ~ 

'f
  • i I:

i' 

*~
  • .i..

'~*.

  • ~** :. _ _._*

Salem ODCH Rev. 9/13/85 Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculational methods of the Salem Emergency Plan EP IV-III. Al terna tel y, 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. Technical Specification 3. 11.2. 4 requires that the GASEOUS RADHASTE TREATMENT SYSTEH and VENTILATION EXHAUST TREATHENT SYSTEM be used to reduce radioactive material levels prior to disc~arge when projected doses exceed one-half the annual design objective rate in any calendar quarter, i.e., exceeding:

0. 625 mrad/quarter, gamma air;
1. 25 mrad/quarter, beta. air; or 1.875 mrem/quarter, maximum organ.

The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation system (filtration systems I 1,2 and 31 and the Haste Gas Decay Tanks as delineated in Figures 2-3 and 2-4. 24

-~ * .'i Sal em ODCl1 Rev. 9/13/85 Dose projections are performed at least once per 31 days by the following equations: D p = D

  • C 91~ dl

( 2. 1 7) D p = D "' ( 91 :- dl ( 2. 1 8) Dmaxp = Dmax: ;. ( 91~ dl ( 2. 1 9) M'here: D p D D p D Dmaxp Dma.x d 91 = = = = = = = gamma air dose projection for current calendar quarter Cmradl gamma air dose to date for cu~rent calendar quarter as determined by equation ( 2. 7) or ( 2. 9) ( mrad) beta air dose projection for current calendar quarter (mradl beta air dose to date for current calendar quarter as determined by equation ( 2. 8) or ( 2. 1 OJ ( mradl maximum organ dose projection for current calendar quarter Cmrem) maximum organ dose to date for current calendar quarter as determined by equation ( 2. 11 J or ( 2. 12) c mreml number of days to date in current calendar quarter number of days in a calendar quarter 25

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

  • Salem ODCH Rev.

9/13/85 In accordance ifith Technical Specification 6. 9. 1. 11, the Radioactive Effluent Release Report < RERRJ submitted Rithin 60 days after January 1 of each year shall include an assessmept of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. There is one location on Artificial Island that is accessible to 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 main gate for the Salem Nuclear Generating Station. Ball fields located near the intersection of the access roads for the Salem and Hope Creek sites are recreational *sites available only to PSE&G employees and site contractor employees: they are not available for use by others. Because of occupanc~ times, the ball fields repre~ent a more controlling recreationally accessible area than does the Second Sun and shall also be evaluated for determining the maximum potential dos~ to a HEHBER OF THE PUBLIC. 26

', ~

~

'*j .. ~" '~.11*:~*-*. ;*,'.'*.'*J'.*.~*-:..~.'.*- Salem ODCH Rev. 9/13/85 HoMeveI", *the Second Sun I"epI"esents the location for" Technical Specification evaluation. The following conseI"vative assumptions may be made conceI"ning locations, exposure times, and exposure pathMays: Distance1DiI"ection Exposul:'e Time: Exposure PathMays: HeteoI"ological Dispersion"':

0. 21 mile* I SE 4 hours/yr (2 hours per visit 2 visits per yeaI"l diI"ect exposuI"e (Noble gases) inhalation CH-3, I-131, particulates) annual aveI"age (as determined for" year being evaluated)
1. OE-05 sec/m3 (default val uel 0.71 mile IE 210 hr/yr (4 hour"s tnice per' Reek over' a 6 month ball season) diI"ect exposuI"e

( Noble gases) inhalation CH-3, I-131, par'ticulates) annual average (as determined for year being evaluated)

1. 2E-06 sec/m3 C default val uel The calculational methods as pI"esented in Sections 2. 4 and 2. 5 may be used for deteI"mining the maximum potential dose to a MEMBER OF THE PUBLIC based on the above assumptions.

The conseI"vative default values have been deI"ived fI"om ~he meteoI"ological dispersion data as pI"esented in the HCGS rSAR, Section 2. 3. These values may be used if CUI"rent year' meteOI"Ology is unavailable at the time of NRC repoI"ting; hoMeveI" a folloM-up evaluation shall be peI"fOI"med Mhen the data becomes available. 27

\\..**.. .,....... '*' :_.*. -~.. --* -*-*** ____ *:..._.J'.:-.:.*. ~ ~ *- Salem ODCM Re*1. 9.'13/85 The Radioactive Effluent Release Report CRERRl submitted Kithin 60 days after January 1 of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Nuclear Generating Station and the Hope Creek Nuclear Generating Station: No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity. The dose contribution from the operation of Hope Creek Nuclear Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual CHCGS ODCM). As appropriate for demonstrating/evaluating compliance with the limits of Technical Specification 3. 11. 4 C 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. For purposes of implementing the surveillance requirements of Technical Specification 3/~. 11. 4 and the reporting requirements of

6. 9. 1. 11

( RERR), dose calculations for the Salem Nuclear Generating Station may be performed using the calculational methods contained within this ODCH; 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/-L 12. 2l may be used. Average annual meteorological dispersion* parameters 9r meteorological conditions concurrent with the release period under evaluation may be used. 28

  • ... :.... "'"-- ~*-*:.-

Sal em ODCH !l.ev. 9/13/85

3. 2. 2 Qir§£t

~~QQ~Yr§ QQ~§ Q§t§rmin~tiQD~ Any potentially significant direct exposure contribution to off-site indivi~ual doses may be evaluated based on the results of the environmental measurements (e.g.,

TLD, ion chamber-measur-ementsl and/or-by the use of a radiation transport and shielding calculational method.

Only during atypical conditions Rill there exist any potential for significant on-site sources at Salem that AOUld yield potentially significant off-site doses (i.e. I in excess of 1 mrem per year to a HEHBER OF THE PUBLIC), that

ould require detailed evaluation for demonstrating compliance
ith 40 CFR 190.
Ho1iever, should a situation exist ;;hereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques Rill be used for determination of dose for assessing 40 CFR 190 compliance.

29

,,**.1.-,.'*........

  • Salem ODC!1 Rev.

9/13/85 The operational phase of the Radiological Environmental Monitoring Program ( REHRl is conducted in accordance Rith the requirements of Appendix A Technical Specification 3. 12. The objectives of the program are: - To determine Rhether any significant increases occur in the concentration of radionuclides in the critical pathRays of exposure in the vicinity of Artificial Island; To determine if the operation of the Salem Nuclear Generating Stations has resulted in any increase in the inventory of long lived radionuclides in the environment; To detect any changes in the ambient gamma radiation levels; and To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment. The sampling requirements (type of samples, collection frequency and analysis) . and sample locations are presented in Appendix D. 30

lfTOOWN LEGEND (fJ FllJER 1BJ RADIATION MONITOR 6,. INSTRUMENT PANEL -fl-PNEUMATIC --- ELECTRICAL -+- LIQUID EFFLUENT --GAS EFFLUENT

  • u. Mfl.

SG SG ""... mi HI At.'.'1011 COOlANI SEA.l WAlt:U l\\JMPS ----i.t-""'"1[£) flllEH ) ::;~H Ull l!!J.... 1GO,. r*- llMSl:S*_ ~ ~R46A l:tMSl:tl ___ ~ r...., UMS1:11__ ~ r.. 68 Ll1o1S1.11 ~ CONOENSAJE POllStiJNG UN11 1~1.. 0

  • 12 ~RVL(

WAlfH **AL.ltR D .---t--III "" OI 04 fJr:C11ANGE FilTUi PS OOMJ' 10 NO ID HIJA -* tm2JA AAlllOo JllO:l** ~ RUO ...,.,0...,,.. A0011A RllA....,. "'°"'" RAl627 """'°" RlllO...... """'" IUU....,.,. - RMln - llJI ... JO, AOOOlA llMlOO....... RM310 - RAU18....... ll:U IWI028 11>1 RA4DP2 RA40JJ ... c...... llM01' FOR INFORMATION ONLY FIGURE 1-1 RADIATION MONITORING LIQUID 1UNIT . **-.... ;:.... : ~.. l:,

  • r*

~ ;.. i:

    • ~ :

.. ~ Parn1etH "Pee ~PCI-131 Ci MP Ci SEN 1-R18 !-R19 Actual Val ije cali:ijiated 3E-07 uasured as detm1ined as detmsined 1-R13 {A,B,C,D,EJ RR 1-R18 1-R19 1-R13 co 1-R13 -.ii 1-R19ii 1-R13it as d~t er*1i ned as deter*~in2d ca1cu1ated calcfjlated caki1ated . - *--*~:. ~:. ;, - *. '**. -- *~ - Table 1-1 Paraieters for Liquid Alars Setpaint Deter;inatians Urii t 1 Default Val ;1e iE-05 I Ni A N/A NIA 2.9E+07 2.9E+07 1.2E+05 1.35E+05 120 ao 2500 4.4E+05{+bkgi 2.0E+Q4{+bkg} 2.bE+OJ!+bkg) Uri its iJCi/WJl uCif;l

ii~ ! s 1 1J'.r4 i :11 uCi/11 calculate far each batch ta be released I-131 MPC conservatively used for S6 blow-dawn and Service Water ;onitar setpoints taken fro; ga;;a spectral analysis of liquid effluent taken fra; 10 CFR 20, Appendix B, Table II, Cal. 2.

cp; per uCi/;l radwaste effluent ICs-1371 CP:!I Steaa Generator b1a~down !Cs-137} Service Water - Cantain~ent fan coaling lCs-137) Circulating Water Syste~, single CW pu1p deter~ined prior to release; release rate can be adjusted for T~chnical Specification cosar 1 ian::e Stea1 Generator bla~dawn rate per generator Service Water flov rate for Ccntain~ent fan coolers Default alar~ setpoints; ~are conservative values 1ar be used as dee;ed appropriate and desirable for ensuring regulatory co~pliance and fur ;aintaining re1eas~s ALARA. has been used ar derivation of the R19 Stea; 6enerator

  • : ii

- _: -~~ .: :

  • I Table 1-2 Paraaeters far Liquid Alar; Setpoint Deter;inations Unit 2 Para12ter Actual Val ;12

~PC~ cah:uiated ~PCI-131 3E-07 Ci 1easur*ed ~PCi as dl!t e rr1 in ed Default Units Val 112 !E-05 t uCi/;l ~ :1

1/ l'1 uCi/11 NIA uCii1l Mi A uCi/11 calculat~ for each batch ta be r~leased I-131 ~PC conservatively used for S6 blow-dovn, Service Water and Cbe1ical ~aste Basin
onitar setpoints taken fro! gam~a spectra! analysis af liquid eff1ijent taken fro1 10 CFR 20, Appendix B, Table II, Cal. 2.

SEN11 2-R15 as 3a5E+07 cp1 per uCii11 radwaste effluent lCs-137} detmiined 2-R19 8.3E+07 Stea1 Generator blovdovn \\Cs-137) !A,B,C & Dl 2-R13 a.aE+07 5.8E+07 as 1.aSE+QS gp; det er-~i ned RR 2-R13 as 120 2-R19 2-R13 2500 R37 SP 2-R18 calculated 8.0E+05(+bkg}ifl cp; 2-R19i+if calculat2d 6.1E+04(+bkg) 2-R!3 caicuiated 1.9E+03\\+bkgJ RJ71111 calculated 1.6E+04(+bkg) 1 Refer to Appendix A for derivation Service Water - Contain1ent fan cooling \\Cs-137l Che1ica1 Waste Basin (Cs-i37l deter1ined prior ta release; rel~ase rate can be adjusted for Technical Specification Stea1 Generator b1awdo~n rate per generator Service Water fla~ rat~ for Cantain~ent fan 1:ooier*s Default alar! setpoints; ~are conservative values ~ay be used as dee~ appropriate and desirable for ensuring resu1atary co;pliance and for ~aintaining releases ALARA. 111 Actual calculated setpaint far 2-R18 !1.3E+06J is greater than the full scale ~onitar indicator, therefore, far canservatisi the reca;~ended setpoint has been reduced tij 8.0E+OS cp~. t -1..1..1. "P'? vpj" 1

    • T J1i 11,...-.1

,... r

  • \\ L j..

1 ~ ~ t"

  • l

~t. ""*:1.-i+ + TTT 1ne n ~ va,ue at l-1j L.it-{_~t u~II~L ii3.S ~-een iJSeL,1Jr* i.ier*1va.. 1on a, "11e rti1 J:..eai *3ener-at.Of" blowdown R1J Service Water and tbe RJ7 Che1ical Waste Basin ianitor setpoints as discussed in Sei:tion 1.2.2. ~ .. :.,.~:..-.... -* *'..... :-.'.':.oc;.. <<** *'*;;.,ccc,.,,._"'"""'

  • ' *\\

..,:.... ~-". lfllXlWN LEGEND If) FIUER EJ RADIATION MONITOR 6 INSTRUMENT PANEL -II-PNEUMATIC ELECTRICAL -+-UOUID EFFLUENT _._GAS EFFLUENT

  • 21 sa sa 00 114 5G 0....

r1"46C 21MS1Jt ~~~ ~ ~ 22MSIJI ~ ~MOO J4r'.lli T.IMSl:ll ___ ~ r-- WJN a*MSIJI ~ 24MS107 sttw

  • Monitoring for the #24 and #25 containment fan coil units is provided by the RI3A, B or C monitors through interconnects.

~ A<t 4 lll SCAl WAJfA R0fM:=TOA=COOlAN=='-J -.Lr-fil-?_,: NJ flU;As PUMPSEAl.FlOW 1.-[f}-L '15 (jj)., ** D C.HANNE.t __w_ All8 AIJC RU* HUI... AHIA llJ4A RJ41... PSEIGCO lliSllUQ. RA'.\\907 AA*:m RAU.1' llA*:r:li RAUl26 RAl62'7 RA16:nl R.111619 AMiii JlAUOJ RMJIO Al** RA.4316 A46C MOO.... Rl!.4012 AA..OJJ RA4014 RA.015 ........:...... :~":.' .---1--IIJ All I I ION EXc.ttANGE FL TEA cncwATEff N'.lN RACMIASTE H'fll'IJ-~1-.-.SEAVCf WArEA T JO UNIT I FOR INFORMATION ONLY FIGURE 1-2 RADIATION MONITORING LIQUID 2UNIT

  • 1,.

-- :. :..*.~:.. . *... ~-. -'-*-*.'. ::* _::.. Salem ODCH Rev. 1 '.l 1 3. 8 5 Table 1 -3 Site Related Ingestion Dose Commitment Factor's, A.10 ( mr'em/hr" per' uC1.'ml) Nuclide Bone Liver-T. Body Thyr-01d Kidney Lung GI-1..LI H-3

2. 82e-1
2. 82e-1
2. 82e-1
2. 82e-1
2. 82e-1
2. 82e-1 C-1 4
1. 45e 4
2. 90e 3
2. 90e 3
2. 90e 3
2. 90e 3
2. 90e 3
2. 90e 3 Na-24
4. S"e-1
4. 57e-1
4. 57e-1
4. 57e-1
  • L 57e-1
4. 57e-1
4. 57e-1 P-32
4. 69e 6
2. 91 e 5
1. 81 e 5
5. 27e 5 Cr--51
5. 58e 0
3. 34e 0
1. 23e 0
7. 40e 0
1. 40e 3 Hn'-54

.,. 06e 3

1. 35e 3
2. 1 Oe 3
2. 1 6e 4 Hn-56.
1. 78 e 2
3. 1 Se
2. 26e 2
5. 67e 3 Fe-55
5. 11 e 4
3. 5 3e 4
8. 23e 3
1. 97e 4
2. O 3e 4 Fe-59
8. 06e 4
1. 90 e 5
7. 27e 4
5. 30e 4
6. 32e 5 Co-58
6. 03e 2
1. 35e 3
1. 22e 4 Co-60
1. 7 3 e 3
3. 82e 3
3. 25e 4 Ni-63
4. 96e 4
3. Ue 3
1. 67e 3
7. 1 Se 2 Ni-65
2. 02e 2
2. 62e 1
1. 20e 1
6. 65e 2 Cu-64
2. 1 4e 2
1. 01 e 2
5. 40e 2
1. 8 3e 4 Zn-65
1. 61 e 5
5. 1 3e 5
2. 32e 5
3. 4 3e 5
3. 23e 5 Zn-69
3. 4 3e 2
6. 56e 2
4. 56e
4. 26e 2
9. 85e BC"-83
7. 2Se-2
1. 04e-1 Br--84
9. 39e-2
7. 37e-7 Br--85
3. 86e-3 Rb-8i)
6. 24e 2
2. 91 e 2
1. 2 3 e 2 Rb-88
1. 79e 0
9. 49e-1 2.47e-11 Rb-89
1. 1 9e 0
8. 34e-1
6. 89e-1 4 Sr-89

-1. 99e 3

1. 43e 2
8. ooe 2 Sr-90
1. 23e 5
3. o 1 e 4
3. 5 5 e 3

Sr-91

9. 1 8e
3. 71 e 0
4. 37 e 2 Sr--92
3. 48e 1
1. 51 e 0
6. 90e 2

'(-90

6. 06e r)
1. 62e-1
o. 42e 4 Y-91m
5. 72e-2
2. 22e-3
1. 68e-1 Y-91
8. 88 e 1
2. 37e 0
4. 89e 4

'(-92

s. J2e-1
1. 56e-2
9. 32e 3 y -9 J
1. 69e 0
4. 66e-2
5. JSe 4 Zc*-95
1. 59e 1
5. 11 e 0
3. 46e 0
8. 02e 0
1. 62e 4 Zr-':l7
8. 81 e-1
1. 78e-1
8. 1 2e-2
2. 68e-1
5. 51 e 4 tlb-95
4. 4 7e
2.

2.. 49e 2

1. 3 4 e 2
2. 46e 2
1. 51 e 6 Mo-99
1. 28e 2
2. 43e 1
2. 89e 2
2. 96e 2 Tc-99m 1.29e-2
3. 66e-2
4. 66e-1
s. 56e-1
1. 79e-2*
2. 1 7e 1 Tc-101
1. 33e-2
1. 92e-2
1. 88e-1
3. 46e-1
9. 81e-J
5. 77e-14 Ru-103
1. 07e 2
4. 60e 1
4. 07 e 2
1. 2 Se 4 Ru-105
8. 89e 0
3. 51 e 0
1. 1 Se 2
5. He 3 Ru-106
1. 59e 3
2. 01 e 2 3.06e 3
1. 0 3 e 5 35

Nucl i*je Ag-110m Te-125m Te-127m Te-127 Te-129m Te-129 Te-1 31 m Te-1 31 Te-132 I-130 I -1 31 I-1 32 I-133 I-1 34 I -1 3 S Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La -1 40 La-142 Ce-1 41 Ce-143 Ce-*144 Pr-1 43 Pr-144 Nd-147 H-187 tfp-2 3 9

      • *.- -~_.,:-:.:... *:: ** -_

.... J.. :. ..\\-./.-.* - Salem ODCH Rev. 1 9;13'85 Table 1 --3 (con' tl Site Related Ingestion Dose Commitment ~actors, Aio Cmrem/hr per uCi/mll Bone

1. 56 e J
2. 1 '."e 2
5. 48e 2
8. 90e 0
9. 31e 2
2. 54e 0
1. 40e 2
1. 59e 0
2. 04e 2
3. 96e
2. 18e 2
1. 06e
7. 4Se 1
5. S6e 0
2. 32e
6. 8 4 e 3
7. 1 6e 2
8. 77 e J
6. 07e 0
7. BS e 0
1. 61 e J J. 81 e 0
1. 72e O 1. 5 7 e 0
8. 06e-2 Liver 1. 4 5 e 3

". 86e 1 1.96e 2 J. 20e 0

3. 4 7e 2
9. SSe-1
6. 8Se 1
6. 66e-1
1. 32e 2
1. 17e 2 j_12e 2
2. 8 Se 1
1. 30e 2
1. 51 e
6. 08e
1. 63e 4
2. 8 3e 3
1. 20e 4
1. 20e
5. 59e-3
2. 06e 0
2. 88e-3
1. l"'e-3
7. 94e-1
3. o7e-2 3.43e 0 2.32e 0
6. 04e-1
  • L 46e 2 1.79e 2

-.47e 1

5. 79e 0
2. 32e 0
1. 90e-2
7. 87e-3
3. 96e 0
4. S8e 0
9. 16e O
7. 66e o
3. SJe-2
3. 47e-J T. Body Thyroid*
8. 60e 2
2. 91 e 1
6. 68e 1
1. 9Je O 1.47e 2
6. 19e-1
5. 71 e 1 S. 03e-1
1. 24e 2
4. 61 e
1. 79e 2
9. 96e o
3. 9Se 1
5. 40e 0
2. 24e
1. 3 3e 4
2. 04e 3
7. 8 Se 3
5. 94e O
2. 30e-1
1. 08e 2
1. 29e-1
1. 08e-1
2. 1 Oe-1 9.13e-3
2. 63e-1
4. 94e-2
9. S9e O
2. 87e-1
9. 64e-4
2. 74e-1
2. 68e 0
1. 91 e-3 36
6. 52e 1
1. 40e 2
6. 60e 0
3. 20e 2
1. 9Se O
1. 08e 2
1. 31e 0
1. 4 6 e 2
9. 91e 3
1. 02e S 9.96e 2
1. 90e 4
2. 62e 2 4.01e 3 Kidney
2. 8 Se 3
8. 82e 2
2. 2 3e 3
3. 6Je 1
3. 89e 3 1.07e 1
6. 94e 2
6. 99e 0
1. 27e 3
1. 82e 2
5. 35e 2
4. S4e 1
2. 26e 2
2. 40e
9. 7Se
5. 27e 3
1. S7e 3
4. 07e 3
8. 81e 0
5. 23e-J
-. 02e-1
2. 68e-3
1. SOe-3
1. 08e 0
1. 96e-1
4. 4 3 e 1
1. 34e 0
4. He-3
2. 68e 0
1. 08e-2 Lung
1. 7Se 3
2. 1 Se 2
1. 35e 3
8. 70e-1
3. 17e-3
1. 18e 0
1. _63e-3
1. OOe-3 GI-LLI
5. 91 e 5
8. 66e 2
1. 84e 3
7. OJe 2
4. 69e 3
1. 92e 0
6. 80e 3
2. 26e-1
6. 24e 3
1. 01e 2
8. 23e 1 S. 3Se o 1.16e 2
1. 32e-2
6. 87e
2. 8Se 2
3. 21 e 2
2. 32e 2 5.11e-5
1. 39e
3. 38e 3
1. 80e-9 2.43e-18
5. 83e 4
2. 68e2
8. 86e 3
1. 67e 4
6. 04e 4
2. 54e 4
2. 73e-9
2. 20e 4
2. 51 e 3 7.. 11 e 2

.',. ~-. :_._.* H c Na p Cr Hn Fe Co N1 Cu Zn Br Rb

3 r y

z ["' N" b Ho Tc Ru Rh Ag 3b Te I Cs Ba La Ce Pr N" d N" p

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

ODCl1 Re*1. Table 1 -4 Bioaccumulation Factors CBFi) CpCi/kg per pCi/liter)*

9. OE-01
1. 8£+03
6. 7E-02
3. OE-t-03
4. OE+02
5. 5E+02
3. OE+03 1.0E+02
1. 0£+02
6. 7£-t-02
2. OEt-03
1. SE-02
8. 3E+OO
2. 0 E+OO
2. 5E+01 2.0E+02 3.0Et-04
1. OEt-01
1. OE+01
3. OE+OO
1. OEt-01 J. 3 Et-03
4. 0£+01
1. OEi-01 1. 0Ei-Q1
L OEi-O 1
1. 0 E i-01 2.5£+01 1.0E+01
2. 5E i-01
2. SEi-01
3. OE+01 1.0E+01

..:. ~~*.:~~~- :~._:.. *.**. 3/1 3/85

9. 3E-01 1.4E+03
1. 9E-01
3. OE+04
2. 0£+03
4. OE+02
2. OE+04 1.0E+03
2. 5E+02
1. 7E+03
5. OE+04
3. 1E+OO
1. 7E-t-01
2. OE+01 1, OE+03
8. OE+01
1. OE+02
1. 0£+01
5. 0£+01
1. OEi-03 2.0E+03
3. 3E+03
5. 4E+OO
1. OE+02
5. OE+01
2. 5 E -t-Q 1
1. OE+02
1. OE+03
6. OE+02 1.0E+03
1. 0£+03 3.0E+01
1. OE-t-01 ITalues in this *Table are taken from Regulatory Guide
1. 109 except for phosphorus I fishl

~hich is adapted from NUREG!CR-1336 and silver and antimony ~h1ch are.taken from UCRL 50564, P.ev. 1, October 1972. 37

WLl17 FROM LAUNDRY 4 CHEM TKS WL172 WL70 lWHUT 2UNIT WHUTS WL71 EQUIP.DRS j\\UX BLDG SUMP TK FLOOR ORS CVCS HUT RELIEFS RHRSUMPS WL222 RWPP RCPHEADTKS RCLOOPDRS RXFLANGELO 'ICCUMULATOR ORS EXCESS LET DOWN.. RWST CVCSHUT WL7 ACDT RCPS 3SEAL LO IWMT WL 86 2WMT I TO&FROM

  • OTHER UNIT Wl42 WL42 WL43 WL43 Wl.47 W"STEEV'IP FEED PUMP I

I I I I WL17 2WHUT WMHUT WLl78 wi.11 WL73 ~-... I W"STEEVj\\P: I I WLl5 WL17 WLl6 CONT SUMP DR WLl3 WLl2 I L_ WLl79 'f' 2WLl74 2Wll93

~-------~------~---w-~-*.;oo.;..;.,....""*'-4; t

~WL89. Wl49 IWMtiUT I ~ 14-~11----w.-.&...-....;~-'°'3--0(J---1.., PUMP {> IWL910 2WL909 I 1 WL*83 r-----w--> 2WMHUJ I I I I 2WL911 1' IWl.908*"""-:,.---..-'"fl.iiQ-'91!__+-.! 1 1wRoo r+-----i*--+---w-

Jon I

~-+---~-*-~ L _____ -----------1 Q-.. 0~=***~:;::, *=*" WL 115 TO ANO FROM I IWL2ee OTHER UNIT -~6'."" -T JWfl26 SW222 SW222 I

  • WA27
  • WR27 Exchange system OVEHBOj\\RD

. OftWMTS llLWl6 r-....---.-. 12 WJ\\STE EVJ\\P WLU13 SERVICE WATER 6 6

  • ~yL.._ 21 CIRC WATER DISCH I

!wn31 !wn31 L ______ 1 __ _.. N~inoe~~.~D 4,.&..W--(llit---o<t-t LW15 ILW*I WLl78 2W"5TE EVAP FEED PUMP WLl19 2WMHUT PUMP FOR INFORMATION ONLY FIGURE 1-3 LIQUID WASTE r::. \\'** - /_.:*

RJ l~J CCINIAINMfNT Rr ~~ lN CORE SEAL TABLE RIOA(@ PER?t~~-O~JCH Rlotl~ PfR~l~~~!°'fCH Rll [!l_!:J CONIAINMfNI

~* r.~ CClr.TAN.WI It RANC.f OtANNfl PSf & G CO COMPulER

l.Q._...lliS!8..!fQ_ _JIL__

RIA RA 4321 ROOOIA 1118 AA lll43 A0009A RJ AA 4322 B'..ll02A ltJ RA 432.J RlOO.lA R4 RA. 4324 R0004A RA.4325 ~ RIA fl.J. 4326 R0006A A611 HA.6.J.c.4 V24!11D ft1 RA.4321 ~IA RI HA 4328 ROOOat,, R9 HA 4311 FOl31A RIOA f1A. 4)12 >>ooJ3A RIOll HA. 8145 fnllOA RUA HA, 4303 ln>18A RUA AA 4JJO R0012A Rlll!I AA 431.J f0'.>39A RA 4332 RIO llA6346 '"'°""' ftA4l14 R>J RA.4315 fl48J.49 flJJA HA 8350 Y200'.lA ftA. IOl!il R411 llA 1015~ ..'. '.,....... ~.....,. fC fC r.=-----~ l~R4J

!!C~ a

[ _____ J ~

~~~1i:J:

L_ _____ _, ~naoo - =11°NG--, L-_ ____ _, CHANNEL PSf&GOO COf..AJIEH __fil__ -..!!iSI!!.J:Q_ - _..lQ.__ R41C RA 10155 Mll RA.2111

'-::::RA 4051 M>C.--

M50 RA.~ AMA RA~ M4il RA2586 RA.4111 .. --~*.-::.............,.. *~*-~-*. ~.*...:J.<J..:.:~ **. :._ ;.'..,..".:.** ~*'.*.* *:-...... '""'""~ AU)l BL 1510 YARO I ___ _J l'"'f *11 ~ ffi PROCESS RADIATION MONITOR ffil AREA RADIATION MONITOR r *. J..... --.... ~ C:'J fMSi!I tu MSC RANGE ~.......... -+-GASEOUS EFFLUENT

ELECTRICAL

_,,...._ PNEUMATIC f'j'l R40A ,,,.,.llCOLAIE IR1 R411

  • KX>NE

~~ R40C

  • NOfllE GAS
  • ------.\\

Ir-- I ' C(~)l ~-J*** i L:_ ~ =-i-_J I !"'1"'" j,---- l ou1Sioe-- sciWiGEI jl ~"" I r ! COH1HOl!~~':fE~ _ _J I r- ~:i '"" HANDll..;; I I 1 ~RS ~Ri fUfl STORAGE I I i 1 ~RJJA CUANE MONJIOR lfUfL-1 _J fUEL HANDUNG 8UllOING - ---- - ----~ ~ -4'--~~-+-l CONDENSER AIR llt:UO'JAL SYS1'fM rse;:.~--i ~*~ *nl~I AUX BLOO flOOf ~;-AC~-~J ~ RELEASE ..,ru~I UNITS 1 I 2

J'"l Pl.ANT \\ifNlS r.;;;::;-------.

MOkllOflLNG fn,;U

____~---~

r ~I W~l.:.~;-;;,-.,-.-.. -----i v.<14 1 I iDtSCHA.RG~ rnoM c-"A:> OEc.Av *~-*-s* ___ _.I FOR INFORMATION ONLV FIGURE 2-1 RADIATION MONITORING GASEOUS 1UNIT ~- :

....www._ 111*... Ill..... Rr....... 1111& 1111& 111n 1111 1111 1111 RUA ft2 8 COHYAINMEN1 111 ~ 1NCORE SEAl TAa.E "'°"~PERSONNEL tWCH El 100* RIOI ~ f'ERSONNEL tWCH El 130'-0" OA.... MIA RA.IOIQ Mtl RA IDllM MIC AA.10116 MJA MIQOI INSll.lf -+it ~IJJl:BLDG ISi YARD I ---, I I I

  • ,,.I I

~LArE I LEGEND ILi PROCESS RADIATION rJ'I MONITOR ~ AREA RADIATION MONITOR __..,GASEOUS EFFLUENT ---~*-ELECTRICAL -- PNEUMA11C M1A.f'ARTICUL.AJE .J Ml8 -ICDHE MIC.ffOBl£ GAS FA FUEL ttANDl.IHG FUEL SfORAGE ~ODA _J CRANE MOHllOO lfUEU ~----*u_*_* ~~- CONDENSER AIR REMO\\t.\\t. SYSJfM _ _j ~-----....1 WASIE CiAs Ot!:iPOSAL SYSJEM I IDISCI WKif FROM GAS DECA'f fAHKSJ I I M.ilA A42P MIC 114.ilD ~- f~ ~-~---~I FOR iNFORMATION ONLY FIGURE 2-2 RADIATION MONITORING GASEOUS 2UNIT

.:.* ii
.:_::c )'.~.;._ *-.~*.. '-.... :.... : *,... ' -*':.....,__,:.

~ -1 ~. i. ,.i . ~

  • .J Radionuclide Kr-831 Kr-85; Kr*-85 Kr-87 Kr-38 Kr-89 Kr-90 Xe-1311 Xe-1331 Xe-133 Xe-1351 Ie-135 Xe-137 Xe-133 Ar-41 Total Body Oose Factor Table 2-1 Dose Factors far Noble Gases Skin Dose Factor

~: s*am1a Air* Om Factor Mi Beta Air* Dose Factor-Ni l1re;/7r per uCi/;31 l;re;/yr per uCi/;JJ l;rad/rr per uCi/;31 (;rad/yr per uCi/~31 7.56E-02 t.17E+03 1.61E+01 5.92E+03

1. 47E+04 1.66E+04 1.56E+04 9.15E+Ot 2.51E+02 2.94E+02 3,12£+03 1.81E+03 1.42E+03 8.33E+03 8.84E+03 1.46E+Q3 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03
4. 76E+02 9.94E+02 3.06E+02 7,11E+02 1.86E+03 t.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03
1. 72E+Ot 6.17E+03 1.52E+04 t.73E+04 1.63E+04 1.56E+02 3a27E+02 3.53E+02 3.36E+03
1. 92E+03 1.51E+03

'1.21E+03 ?.30E+03 2,88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03

1. 48£+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03
  • ~-

/.:**'.**.* Parai1eter X/G VF (Plant l/entl VF \\Cant. Purge) AF c i K I... ~ SEN 1-R41CI i-R16 1-R12A Ad1Jal Val iJe calculated as :aeasured or fan curves as measured or fan curves coordinated ~ith HC65 1easured nuclide speci fie riuc! ide specific rrncl ide S~ 1 eCltlC as deter1ined SP 1-R41C calculated l-R16 calculated l-R12At+ calctilated

  • ..:. ~-

Table 2-2 Parameters far 6aseo1Js Alar1 Setpoint Deterninations Unit-t Oefau 1t Value 2.2E-OO 1.25E+OS 3.5E+04 0.25 Ni A Ni A NIA Ni A 1.6£+07 3.6E+07 2.!E+06 3 m/1 3 ft /1in 3 ft fain unitlm 3 uCi/c1 3 USNRC Sale; Safety Evaluation, Sup. J Plant Vent - nor1al operation Contain1ent purge Ad1inistrative allocation factor to ensure co1bined releases do not exceed release rate limit for site. 1re1/yr per uCi/1 Values fro1 Table 2-1 3 1re1/yr per uCi/1 Values froa Table 2-1 3 ~rad/yr per uCi/a. Yalu~s fro1 Table 2-1 Plant Vent Plant Vent (redundant) J.3E+041+bkgl cp~

7. 4E+1)4 ( +bkgl Default alart s~tpoints; ~ore conservative valyes ~ay be used as deejed appropriate and desirable far ensijring r~gu1atory co~pliance and far laintaining releases ALARA.

+ -Based on 1ean for calibration with 1ixture of radionuclides reduced to 21 background in accordance ~ith Tech Spec Table 3.3-6.

~ * ~*"- ' - I -~ : Table 2-3 Para1eters far Gaseous Alar1 Setpoint Deterainations Unit-2 ?ara;eter-Act ua. l DefaiJlt Units Canent s Value Val Ye VF \\Plant cai cu lated as 1easured or Verit) fan mves VF AF " e: I! ii Purge) or-hn curves coor-dinated 'ilith HCGS nuclide *:pecific SEN 2-R41C1 as 2-R16 2-R12A SP 2-R41C ca1cu1ated 2-R16 calculated 2-R12Ati calculated 1.25E+t)5 3.5E+04 0.25 ~! ! 1 ilif1 3 3 3 ft fain unitless 3 ~* ' U~l/Cil

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

licensing technical specification va1ue Plant Vent - nor~al operation Contain1ent purge Administrative allocation factor ta ensure cosbined releases do not exceed release rate liait for site. NIA ir~1/yr per uCi/1 Values fra1 Table 2-1 3 NIA mre~/yr per ijCii~ Values fro~ Tab12 2-1 3 U:'l Rf i1 ~rad/yr per*uCi/1 Ya1ues froa Table 2-1 iabE+07 3a5E+07 3.3Ett)7 3a3E+04{+bkg) cp~ 7.2E+04(+bkgl 2a4E+05!+bkg) 3 Piant Vent Default alar~ setpcints; 10 e conservative values iay be used as dee1e appropriate and desirabl2 for ensuring regu atnry co;pliance and far ;aintaining releases ALARA. + Based on ;ean far calibration ~ith ~ixture af radionuclides +1 Applicab ~during "ODES l thraugb 5. During nDDE 6 lrefuelingl, ~anitar setpaints shall be reduced o 2X background in accordance with Tach Spec Table 3a3-6.

~ Table 2-4 Controlling Locations, Pathways and At1aspheric Oispersian far Oose Calculations I At1aspheri:: Disper*sian Technical Specification Location Path1i1ay(sl Contra l l ir1g X/G Ase Sra1Jp \\mfll3l 3e11.2.1a site boljndan noble gases NIA 2,2E-06 (0,83., 111 e, Nl direct HPOSIJre 3.!1.2.1b

  • ite boundary inhalation child 2.2E-06

!0.33 lli i e I Nl 3.11.2.2 site bo1Jndary guaa-air NIA 2.2E-tJ6 (0.83 '1 lld!i NJ beta-air r*esiiience/dairy llilk and infant 5.4E-08 !4.8 1iles, NNEl 91'Glliid plane 1 The identified controlling locations, path~ays and at1ospheric dispersion are fro1 tbe Safety Evaluation Report, Supple1ent No. 3 far the Sale1 Nuclear Generating Station, Unit 2 INURE6-0517, Oece1ber 19781

  • C1/~

{f /12} Ni A NIA NIA 2.1E-10 -*******-~-~-

"'""'7 SIOH.r.l>tl-'"" llSf'lNI Gf~RAI. -JI

  • 00~""

AfCIAC~ f\\JMP"'RIA J IJt&D (R221 RA-4315 (R81 RA-4328 TRUCK BAY SOl.D RAO WASTE ..... *.***"""""******.._,*>* *-* ***._ **'*~***,.. * ****->>**-

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

0-.*.*.-~T*---.. ~- **** ~SUPPLY ..._RETURN IEXHAUSTI ~ RElURN tEXHAUSTI EMERGENCY. CR41AI RAIOl53 CR4111) RAl0154 CR41CI RAIOl55 (R45AJ RA405J (R45B) RM05J (R45CJ RA405J (R45D) RA405I U1JJ o-(R32A) RA-41350 fL.154 (Rill RA-4311 EL.130 (~) RA-4325 EL.130 FUEL HANOLNG i.DG RA-413411 (RZDBJ co..NTNG RM fUl.....-H"f~UG uuo1uo1C"lnt 4flt" CReiA)

r. 1111 m RA-4326 CHEM LAB (R31 RA-432J

--f-f!- f'lt.11!!'.]!

WC..l*c.ut.Mt~u..(1 lAU:lMAl(W.l* oll.MfA

-----~

Cf A. t_.=2*14Nl11&12l.AUN~1 6t4U1~(AIAJM 11&11MONifORClllMICAI. 2**11tHl11,ttft.11CM. IUdCS&_f'll... OHAIN DAAIHta.fM ARI.A (.ti.--* ..--.-----'+.;- ::~~

~

FOR INFORMATION ONLY FIGURE 2-3 AUXILIARY BUILDING VENTILATION UNIT!

~

~ ".

10 (i(MfRAI... 0 .... ~ ---*. - *-*,., ** :.. '* - -*-._,..~.. - --. *-~ *..,._.1.;.-.'....... *..,.~.. ~,,,_.:.1 **.:*...... ~.<* :J...;,,'.. ~ ~~-*-'* *'*** *-..... *..*... ..... ~* ,,..... :r Sf~IAtM iUSf'lf:"I ~l'W-* ~:.o.-.-J (RC2AI RA*lllMlll ~SUPPLY ~RETURN !EXHAUSTJ ~ HETUAN !EXtlAUSTI EMERGENCY ~~----"'~m7;i£~*rco11 ~1.. f~~.,Ht I l"IWHAlm,lfNI (RC1AI RA 10153 IRC1BI RA 10154 IRC1CI RA10155 CRC5AI RAC057 CRC5DI RAC057 IRC5C) RAC057 CRC5D) RAC05tl t:i.111-0* 11111110 SEC...-.oAR-.~~ lAfJORAIOfh ARI A

r. 100*0*

f'W'INGl'fHfltlAl11ltl.utlA

----~

-+-----t--- h ~::i*o t-~---'+--- ::~~:;:::. Afll"A

~

CR32DI RA*8351 EL. 165 . (R32A) RA-11350 El.154 (R91 RA-4311 El.130 (RSI RA-4325 EL.130 . FUEL HANOI.NG llWG FOR INFORMATION ONLY FIGURE 2-4 AUXILIARY BUILDING VENTILATION UNIT2

,/

r.... * ~...

  • l

-'.) -:*I Nuclide H-3 C-14 P-32 Ct'-51' Hn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr--89 St'-90 Y-91 Zr--95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs -1 34 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 p [" -1 4 3 Nd-147 .'3alem ODCH Rev. Table 2-5 PathKay Dose Factor's - Atmosphet"ic Releases Rliol Inhalation PathHay Factor's - ADULT Bone

1. 82e 4
1. 32e 6
2. 46e 4
1. 1 8 e 4
4. 32e 5
3. 24e 4
3. 04e 5
9. 92e 7
4. 62e 5
1. 07e 5 1.41e 4
1. 5 3e 3
6. 91 e 4
1. 08e 4
3. 42e 3
1. 26e 4
9. 76e 3
2. 52e 4
3. 7 3e 5
3. 90e 4
4. 78e 5
3. 90e 4
1. 99e 4
3. 43e 6
9. 30 e J
5. 27e 3

( mt'em/yr per uCi/m3l Liver-T. Body Thyroid Kidney

1. 26e 3
3. 41 e 3
7. 71 e 4
3. 9tie 4
1. 70e 4
2. 78e 4
1. 58e 3
1. 1 Se 4
3. 1 4e 4
1. 03e 5
1. 35e 5
3. 87e 2
3. He 4
7. 82e 3
1. OOe 4
1. 58e 3
5. 77e 3
4. 67e 3
3. 58e 4
8. 48e 5
1. 46e 5
6. 21 e 5
4. 90e 1
1. 3 Se 4
1. 43e 6
3. '.'Se 3
6. 1 Oe 3
1. 26e 3
3. 41e 3
5. 01 e 4
1. OOe 2
6. 30e 3
3. 94e 3
1. 06e 4
2. 07e 3
1. 48e 4
1. 45e 4
4. 66e 4
5. 90e 4
1. 93e 2
8. 72e 3
6. 1 Oe 6
1. 24e 4
2. 33e 4
4. 21e 3
6. 58e 2
8. 72e 3 S. 94e 3
4. 67e 2
1. 57e 3
1. 58e 3
2. 05e 4
7. 28 e 5
1. 10e 5
4. 28e 5
2. 68e 3
1. 53e 3
1. 84e 5
4. 64e 2
3. 65e 2 47
1. 26e 3
1. 26e 3
3. 41 e 3
3. 41 e 3
5. 95e
2. 28e 1
9. 84e 3
1. 05e J
3. 29e J
3. 44e 3
1. 1 9 e :
6. 90e 4
5. 42e 4
7. 74e 3
5. 83e 3
1. 34e 5
1. 97e 4
1. 24e 4
4. 58e 4*
3. 66e 4
6. 1 3e 4
2. 87e 5
8. 56e 4
2. 22e 5
1. 67 e 1
6. 26e 3
8. ae s
2. 1 6e 3
3. 56 e 3 Lung
1. 26e 3
3. 41 e 3
1. He 4
1. 40e 6
7. 21 e 4
1. 02e 6
9. 28e 5 5.97e 6
1. 78e 5
8. 64e 5
1. 40e 6
9. 60e 6
1. 70e 6
1. 77e 6
5. 05e 5
5. 05e 5
9. 36e 6
4. 63e 6
3. 1 4e 5 9.60e 5
1. 1 6e 6
9. 76e 4
1. 20e 4
7. 52e 4
1. 27e 6
3. 62e 5
7. 7 8e 6
2. 81 e 5
2. 21 e 5 9/1]/85 GI-LLI
1. 26e 3
3. 41 e 3
a. 6 4e 4
3. 32e 3
7. 74e 4
6. o 3e 3
1. 88e 5
1. 06e 5
2. 85e 5
1. 34e 4
5. 34e 4
1. 66e 4
3. 34e-9
3. 50e 5
7. 22 e 5
3. 85e 5
1. 50e 5
1. 04e 5 1.10e 5
9. 1 2e 5
3. 02e 5
7. 06 e 4
1. SOe S
3. 8 3e s
6. 28e 3 1. 0 4 e 4 1.17e 4
8. 40e 3
2. 1 Se 5
1. 20e S
8. 16e 5
2. OOe S 1. 7 3 e S
  • -.i Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co **58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr-89 Sr--90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-1 36 Cs-137 Ba-1 40 Ce -1 41 Ce-144 Pr--143 Nd-147 Salem ODCM Rev.

1 9/13185 Table 2-5 C con' tl R(iol Inhalation PathRay F~ctors - TEENAGER (mrem/yr per uCi/m3l Bone Liver T. Body Thyroid

2. 60E 4 1. 8 9 E 6
1. 27 E 3

-1. 87E 3

1. 10E 5
5. 11 E 4
3. HE 4 *2. 38E 4
1. 59E 4
3. ~OE 4
2. 07 E 3
1. 51 E 4
1. 27E 3
4. 87E 3
7. 1 6 E 4 1. 3 5 E 2
8. 40E 3
5. 54E 3
1. 4 3 E 4
2. 78E 3
1. 98E 4
1. 98 E 4
6. 24E 4
8. 40 E 4
2. 72E 2
1. 25E 4
6. 68E 6
1. 77E 4 3.15E 4
5. 66E 3
8. 96E 2
1. 24E 4
7. 99E 3
6. 67E 2
2. 1 8 E 3
5. BOE 5
4. 34E 4 3.86E4 1.34E5
4. 34 E 5
1. 08E 8
6. 61 E 5 1.46E 5
1. 86E 4 2.10E 3
9. 84 E 4
1. 38E 4
4. 88E 3
1. 80 E 4 1.39E 4
3. 54E 4
5. 02E 5
5. 1 5 E 4 6...,OE 5
5. 47E 4
2. 848 4 4.89E 6
1. 3-1£ 4

~. 8 6E 3

1. 90E 5
5. 46E 2 4.58E 4
1. 03E 4
1. 31 E 4
2. 24E 3
8. 1 6 E 3 6.58E3 2.25E3
4. 91 E 4.
2. 64£ 4 1.13E 6 5.49E 5 1.94.ES 1.37E5 8.48£5 3.11E5
6. 70E 1
3. 52E 3 1.90E4 2.17£3
2. 02E 6
2. 62E 5 5.31£3 6.62E2 8.56E3 5.13E2 48
1. 27E 3
4. 87E 3
7. 50 E
1. 40E 3
4. 38E 3
4. 58E 3
1. 46 E 7 Kidney
1. 27E 3
4. 87 E 3
3. 07E 1
1. 27E 4
8. 64E 4
6. 74E 4
1. OOE 4
7. 43E 3
1. 90E 5
2. SOE 4
6. 54E 4
5. 19E 4
8. 40E 4
3. 75E 5
1. 10E 5
3. 04 E 5
2. 28 E 1
8. 8 8 E 3
1. 21 E 6
3. 09E 3
5. 02E 3 Lung 1. 2 7 E J
4. 87E 3
2. 1 OE 4
1. 98E 6
1. 24£ 5
1. 5 3 E 6
1. 34E 6
8. 72E 6
3. 07 E 5
1. 24E 6
2. 42E 6
1. 65E 7
2. 94£ 6 2.69E 6
7. 51 E 5
7. 83E 5
1. 61 E 7 GI-LLI 1. 2 7 E 3
4. 87E 3
9. 28E 4
3. 00 E 3
6. 68 E 4
6. 39E 3
1. 78E 5
9. 52E 4
2. 59E S
1. 42E 4
4. 66E 4
1. 77E 4
2. 92E-5 3.71E 5
7. 65E 5
4. 09 E 5 1.49E-5
9. 68E 4
1. 09E 5
9. 60E 5
6. 75E 6
2. 73E 5 5.36E5 7.50E4 1.66E 6 1.59E 5 1.98£6 4.05£5
6. 49 E 3 1.46E 5* 9.76E 3
1. ;g E 4 1. 21 E 5
2. OJE 6
6. 1 4E 5
1. J 4E

~

4. 83E 5
3. :c-2E 5
1. 09 E 4
8. 48E 3
2. 29E 5
1. 26 E 5
8. 64£ 5
2. HE 5
1. 82E 5

Nuclide .. -... ~ **:

  • ~- -~. _,

.. :, ; __ ;:_.~ *;;.'.'.,. *:*:,.-.~::.'....,'.".:>..:... ':...... .3alem ODCH Re-.-. 1 '..i.. 13.85 Table 2-5 (con' t) R(io) Inhalation PathKay Factors - CHILD lmrem/yr per uCi/m31 Bone Liver T. Body Thyroid Kidney GI-LLI H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-5S Co-60 Ni-63 Zn-65 Rb-S6 Rb-SS Sr-89 S!:"-90 'f-91 Zr-95 Nb-9S Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-1 H Pr-143 Nd 3. S9 E 4 2.60E

4. 74E 4
2. 07 E 4 S.21E S
4. 2 5 E 4 S.99E S 1. 01 E S 9.14E 5 1.90E S
2. 3 5 E 4
2. 79E 3
1. 36E 5 1.69E 4
6. 7 3 E 3
2. 49E 4
1. 92E 4
4. S1E 4
6. 51 E S
6. S 1 E 4
9. 06E 5
7. 40E 4
3. 92 E 4
6. 7"' E 6
1. 8 5 E 4 1.08E 4 1. 1 2 E 3
6. 7 3 E 3
1. 1 4E 5
4. 29E 4
2. S2E 4
3. 34E 4 1.77E 3 1.31E 4
4. 62E 4 1. 1 3 E 5
1. 9SE S
5. 62E 2
4. 1 BE 4
9. 1 SE 3 1. 1 4 E 4
2. 33E 3
8. 55E 3
6. 84E 3
4. 81 E 4
1. 01 E 6 1. 71 E 5
8. 25E S
6. 4 7E 1 1. 9 5 E 4
2. 1 2E 6
5. 5SE 3
8. 73E 3
1. 1 2E 3 6.73E 3 9 8SE 4
1. S4E 2 9.51E 3
7. 77 E 3
1. 67E 4
3. 1 6E 3
2. 26E 4
2. SOE 4
7. 03E 4
1. 1 4E s
3. 66E 2
1. 72E 4
6. 44E 6
2. 44E 4
3. 70E 4
6. SSE 3
1. 07E 3
1. 69E 4 9.-1 4E 3
9. 1 4E 2
3. 02E 3
3. 04E 3 2.73E 4
2. 2SE 5
1. 16E 5
1. 2BE S 4.33E 3
2. 90E 3
3. 61 E S
9. 1 4E 2
6. S1 E 2 49
1. 1 2 E 3
6. 73E 3 S. SSE
1. 92E 3 6.07E 3
6. 33E 3 1.62E 7
1. 1 2 E 3
6. 73E 3
2. 4 3 E 1
1. OOE 4
7. 1 4E 4
5. 96 E 4
8. 62E 3
7. 03 E 3
1. S4E S
2. 1 2 E
6. 36 E 4
5. 03E 4
7. SSE 4
3. 30 E 5
9. 55E 4
2. 82E 5
2. 11 E
8. 5SE 3 1.17E 6
3. 00 E 3
4. 81 E 3
1. 1 2E 3
6. 73E 3
1. ?OE 4
1. SSE 6
1. 11 E S
1. 27E 6 1.11E6 7.07E 6 2.7SE 5
9. 95E S
2. 1 6 E 6
1. 4SE 7
2. 63E 6
2. 23E 6
6. 1 4 E S
6. 62E S 1.43E 7 S. 48E 6
4. 77 E S
1. 4BE 6
1. 76E 6 1. 21 E 5
1. 4 SE 4
1. 0 4 E 5
1. 74E 6 5..tH 5
1. 20 E 7

.t. 3 3 E 5

3. 2 8 E 5
1. 1 2 E 3
6. 73E 3
4. 22E 4
1. OS E 3
2. 29 E 4
2. 87 E 3
7. 07E 4
3. 44E 4
9. 62E 4
6. 33E 3
1. 63E 4 7.99E 3
1. 72E 1 1.67E 5
3. 43E S
1. S4E s 6.10E 4
3. 70 E 4
4. 4 SE 4
4. 29E 5
1. OOE 5
3. 38E 4
7. 1 4 E 4
1. 82E 5
2. S 4 E 3
3. SSE 3
4. 1 8 E 3
3. 62E 3
1. 02E 5
5. 6 6 E 4
3. S8E 5
9. 7JE 4 S. 21 E 4
*.. :,,~--.--:'.... ~ '-*.. _,_, ___..

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe -5 5 Fe-59 Co-58 Co-60 Ni-6 3 Zn-65 Rb-86 Rb-88 SC"-89 Sr--90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-11 Om Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-1 37 Ba-140 Ce-1 41 Ce-1 H Pi;-1 43 Nd-1-P

  • . "'I"

.. ~--, ;~'{';*.,_r*,; :~:_.- :.. Table 2-5 (con' tl 3alem ODCM Re*1. 1 9113/85 RC iol Inhalation Pathtiay Factor's IHFANT Bone 2.65E 4

2. 0 3 E 6
1. 97 E 4 1. 3 6 E 4
3. 39 E 5 1.93E 4
3. 98E 5
4. 98E 7
5. 88 E 5 1.15E 5
1. 57E 4
2. 02E J
8. 6 8 E 4
9. 98E 3
4. 76 E J
1. 67E 4
1. 41 E 4
3. 79 E 4
3. 96E 5
4. 83E 4
5. 49 E 5
5. 60 E 4
2. 7-:- E 4
3. 1 9 E 6
1. 40 E 4
. 94E 3

( mrem/yi; per" uCi/m3l Liver-

6. 47E 2 5.31E 3 1. 1 2 E 5
2. 53E 4
1. 17E 4
2. 3 5 E 4
1. 22E 3
8. 02E 3
2. 04E 4
6. 26E 4
1. 90E 5
5. 57E 2
2. 79E 4
6. 43£ 3
7. 22E 3
1. 99E 3
6. 90 E 3
6. 09£ 3
4. 44E 4
7. 03E 5
1. J 5 E 5
6. 1 2E 5
5. 60E 1 1. 6 7 E 4
1. 21 E 6
5. 24E 3
8. 1 3E 3 T. Body Thyi;oid
6. 47E 2
5. 31 E 3
7. 74E 4
8. 95E 1
4. 98E 3
3. 33E 3
9. 48E 3
1. 82E 3
1. 1 BE 4
1. 1 6 E 4
3. 11 E 4
8. 82E 4
2. 87E 2
1. 14E 4
2. 59E 6 1.57E 4
2. 03E 4
3. 78E 3 6.79E 2.
1. 09E 4
5. OOE 3
6. 58E 2
2. 07 E 3
2. 23 E 3
1. 96E 4
7. 45E 4
5. 29E 4 4.55E 4
2. 90E 3
1. 99E 3
1. 76 E 5
6. 99E 2
5. OOE 2 50
6. 47E 2
5. 31 E 3
5. 75 E
1. 6 2 E 3
  • L 87 E 3
5. 47E 3 1. 4 8 E -

Kidney

6. 47E 2
5. J1 E 3
1. 32E 1
4. 98 E 3
3. 2 5 E 4
3. 1 1 E 4
4. 72E 3
4. 24 E 3
1. 07E 5
1. 09E 4
3. 75E 4
3. 1 BE 4
5. 1 SE 4
1. 90E 5
5. 64E 4
1. 72E 5
1. HE 1
5. 25E 3
5. 3 8 E 5
1. 97E 3
3. 1 5 E 3 Lung
6. 47 E 2
5. 31 E 3
1. 28 E 4
1. OOE 6
8. 69 E 4
1. 01E 6
7. 77E 5
4. 51E 6
2. 09E 5
6. 47E 5 2.03E 6
1. 12E 7
2. 45£ 6
1. 75£ 6
4. 79E 5
5. 52£ 5
1. 16E 7
3. 67E 6
4. 47E 5 1.31E 6
1. 68E 6
7. 97E 4
1. 18£ 4
7. 1 3 E 4
1. 60E 6
5. 1 7 E 5
9. 84E 6
4. 33E 5 J. 2 2 E 5 GI-LLI
6. 4 7 E 2
5. 31 E 3
1. 61 E 4 3.57E 2
7. 06£ 3 1.09£ 3
2. 48£ 4
1. 1 1 E 4
3. 1 9E 4
2. 42E 3
5. 1 4E 4
3. 04E 3
3. 39E 2 6.40£ 4
1. 31 E 5
7. 03E 4 2.17E 4 1.27E 4
1. 61 E 4
1. 64E 5
3. 30E 4
1. 29E 4
2. 73£ 4
6. 90E 4 1. 0 6 E 3
1. 3 3 E 3
1. 43E 3
1. 3 3 E 3 J. 84E 4
2. 1 6E 4
1. 48E 5 J. 72E 4 3.12£ 4

Nuclide H-3 C-14 P-32 Ct"-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 St"-89 St"-90 Y-91 Zt"-95 Nb-95 Ru-10.3 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-134 Cs-1 36 Cs-1 37 Ba-140 Ce-141 Ce-144 Pr--143 Nd-147 , '. "~*. ~. Salem ODCH Rev. 1 9./1 3/85 Table 2-5 (con' tl R(iol Gt"ass-CoK-Hilk Pathway Factor' - ADULT ( mt"em/yt" per-uCi/m.3l for" H-3 and C-14 ( m2 "' mt"em/yt" per' uCi/sec) for-other's Bone Liver-T. Body Thyr-oid

2. 63E.8 1. 71 E 1 0
2. 51 E
2. 98E 7
6. 73E 9
1. 37E 9
7. 63E 2 5.27E 7 1.06E 9
8. 40E 6
7. 53E 2
5. 27E 7
6. 60E 8
2. 86E 4
1. 60E 6
1. 73E
7. OOE
4. 72E 7
4. 04E 6
7. 2. 6BE 7 6
1. 06E 7
1. 6 4 E
4. 66E 8
4. 36E 9 2.59E 9
3. 62E 7
2. 26E 8
1. 97E 9
1. 21 E 9 1.25E7 6.61E6
1. 45E 9
  • L 16E 7
4. 68E1 0 B. 60 E J 9. 4 6 E 2*

J. 0 3 E 2 8.25E4 4.59E4

1.02E 3
2. 04E 4 5.8JE7 5.39E7
1. 6 3 E.
4. 58E :

6.04E 7

2. 96E B
5. 6SE 9
2. 61 E B 7.3BE 9
2. 69E 7
4. 848 3 J. 58 E 5 1.59E 2
9. 42E
5. 90E 6
1. 64E ;
2. 25E 7
4. 24 E 8 1.34£10
1. 0 3 E 9 1.01E10 J..38E 4
3. 27E 3
1. SOE S
6. 37E 1
1. 09E 2 1.1SE10
2. 30 E 2
2. OSE 2
2. 4 7E 4
4. 39E 2
2. 5BE 3
3. 20E 7
2. 1 8 E 6
5. 58E 6
9. 57E 6
2. 43E 8
1. 10E10 7.42E 8
6. 61 E 9
1. 76E 6
3. 71E 2
1. 92E 4
7. 8BE 0
6. 52E 0 51 7.63E2 S. 27E 7
1. 71 E 4
4. 90E 6
1. 17 E 7
a. QBE 7
1. 39 E11 Kidney
7. 6JE 2
5. 27E 7
6. 30 E 3
2. SOE 5*

Lung

7. 6JE 2
5. 27E 7
3. BOE 4 GI -LLI
7. 6JE 2 S. 27E,
1. 92E 9
7. 20E 6
2. 57E,
9. 67E 6
9. 9SE 6 1.9SE 7 2.33E 8
9. 57E 7
3. OBE B
9. 73E 7
2. 92E 9 2.7SE 9 5.11E B 1.72E-4
2. 33E 8
1. 35E 9
4. 73E 6
4. 76E 2
4. SH 4
3. B9E 3
3. 94E 4
1. 06E 8 6.63E 7
1. B6E 8
2. 52E B
7. 27E 8
4. 35E 9 5.74E B 3.43E 9
1. 1 5 E 4
1. 52E 3 8.87E 4
3. 68 E 1
6. 3 7E 1
1. HE 9
. 87E 7
1. 14E 9
1. 9 3 E 4
9. 62E 5 2.79E.8
1. 1 9 E 5
1. 32E 6 2.20E10
6. SOE 7
1. 54E B
3. OH 8
1. 1 2 E 8
2. 35E 8
1. 1 7 E 8
1. 95 E 8
5. 54E 7
1. 2SE 7 1.21E 8
6. 96 E 5
5. 23E 5

Nuclide H-3 C-14 P-32 Cr--51 Hn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr--89 Sr--90 Y-91 Zr--95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-1 34 Cs-136 Cs-137 8a*1.t0 Ce-1 41 Ce-1 44 l?r-143 Nd-147 ~. ' ~* : *-*. Salem ODCH Rev. 1 911 3/85

  • Table 2-5 (con' tl RC io) Grass-CoK-Hilk l?athKay Factor -

TEENAGER ( mrem/yr-per uCi/m3l for H-J and c-14 Bone

4. 86E 8 3.15E10
4. 45E 7
5. 20E 7
1. 18£10 2.11E 9
2. 67E 9
6. 61£10
1. 58E 4 1. 6 5 E 3
1. 41 E 5
1. 81 E 3
3. 75E 4 9.63E 7
3. OOE 7
8. HE 7 1.11£8
5. 38 E 8
9. 81 E 9 4.45E 8
1. 34£10
4. 8 5 E.,,
8. 87E 3
6. 58 E 5
2. 92E 2
1. 81 E 2

( m2

  • mr-em/yr-per uCi/secl for others Li *1er
9. 94E 2
9. 72E 7
1. 95E 9 1.-1.0E 7
3. 16E 7
1. 21 E 8
7. 95E 6
2. 78E 7
8. 35 E 8 7.31E 9
4. 73E 9
2. 26E 7
5. 22E 2
7. 8 0 E 4
9. 11 E 7 1.08E 7 2.99E 7
4. 1 0 E 7
7. 53E 8 2.31E10 1.75E 9 1.78E10
5. 95E 4
5. 92E 3
2. 72E 5
1. 1 7 E 2 1. 9 7 E 2 T. Body Thyroid
9. 9H 2
9. 72E 7
1. 22E 9
5. OOE 4
2. 78 E 6 7.36E 6
4. 68E 7
1. 83E 7
6. 26E 7 4.01E 8
3. 41£ 9
2. 22E 9
1. 21 E 7 7.66E 7
1. 63E1 0
4. 24E 2
3. 59E 2
4. 30E 4
7. 75E 2
4. 73E 3
5. 54E 7 4.02E 6
1. OOE 7 1.75E 7
4. 04E 8
1. 07E10
1. 1 SE 9
6. 20 E 9 3.13E 6 6.81E 2
3. 54E 4
1. 4 5 E
1. 1 8 E 52
9. 94E 2
9. 72E 7
2. 78E 4
8. 39E 6
2. 01 E 7
3. 5 7 E :
2. 18 E11 Kidney
9. 94E 2
9. 72E 7
1. 10E 4
4. 17E 6
4. 68E 9
7. 67E 2
7. 57E 4
6. 40E 3
7. 23E 4 1.. 74 E 8
3. 42E 3
4. 62E 8
1. JOE 9
7. 34 E 9
9. 53E 8
6. 06E 9
2. O 2E 4
2. 79 E 3
1. 6 3E 5
6. 77E 1
1. 16E 2 Lung
9. 94E 2
9. 72E 7
7. 1 3 E 4
2. OOE 7
3. 82E 7
2. SOE 9
1. 50 E 8
2. JSE 9
4. OOE 4 GI-LLI
9. 94E 2
9. 72E 7
2. 65E 9
8. 40E 6
2. 87E 7
1. 37E 7
2. 87E 8
1. 1 OE 8
3. 62E 8
1. 33E 8
3. 1 OE 9
7. OOE 8
1. 94E O 3.18E 8
1. 86E 9
6. 48 E 6
1. 20 E 6
3. 34E 8
1. 52E 5

.1.SOE 6

2. 56E1 0 8.86E 7
2. 1 OE 8
4. 1 SE 8
1. 49 E 8
2. 87 E 8
1. 41 E 8
2. 5 3 E 8 7.49E 7
1. 69 E 7
1. 66E 8
9. 61 E 5
7. 11 E 5

Nuclide H-3 C-14 P-32 Cr--51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr-89 Sr--90 Y-91 Zr--95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-1: 4 Cs-136 Cs-137 Ba-140 Ce -1 41 Ce-1 44 p r--14 3 Nd-147 ..~ *. ;:.* Salem ODCM Rev.1 9/13,85 Table 2-5 (con' tl RC iol Gr-ass-Coli-Hilk Pathliay Factor-CHILD ( mr-em/yr-per uCi/m3l for-H-3 and c-14 ( m2 "' mr-em/yr-per-uCi/secl for-others Bone Liver-T. Body Thyroid

1. 1 9 E 9 7.77E10
1. 1 2 E 8
1. 20E 8
1. 5 7 E J
2. J9 E 8
3. 64E 9
2. 09 E 7 5.93E 7
1. 95E 8
1. S 7E 3

'2. 39E 8

3. OOE 9
1. 02E 5 S. SSE 6
1. 84E 7
9. 71E 7 1.21E7 3.72E7
4. 32E 7
1. 27E 8
2. 96E10
1. S9E 9
4. 13E 9 1.10E10
6. 62E 9
1. 12E11 J. 91 E 4
3. 84E 3
3. 1 SE S
4. 29E 3
9. 24E 4
2. 09 E 8
7. J8E 7 2.08E 8
2. 72E 8 1.30E 9 2.26E10
1. 00 E 9 3.22E10 1. 1 '.' E 8
2. 1 9 E 4
1. 62E 6
. 23E 2 4.4SE 2 8.77E 9 4.17E 7 8 *. 4 SE 2
1. 24E S
1. 41 E 8
2. OOE 7
5. 60E
7. 61 E 7
1. 31 E 9
3. 71E1 0
2. 76 E 9
3. 09E1 0
1. 03E S
1. 09 E 4
5. 09E S
2. 1 7E 2
3. 60E 2
1. 01E 9
6. SSE 9 S. 39E 9
2. 89E 7
1. 89E 8
2. 83E10 1.04E 3
7. S2E* 2
8. 84E 4
1. 6SE 3 1.1SE 4 1. 1 3 E 8
9. 84E 6
2. 4 7 E 7
4. 23E 7
7. 46E 8
1. 83E 9
1. 79E 9
4. SSE 9
6. 84E 6
1. 62E 3 8.66E 4
3. S9E
2. 79 E 53 1.S7E 3
2. 39E 8 S. 66E 4 2.07E 7
4. 97E 7
8. 78E 7
4. 34E11 Kidney
1. S7E 3
2. 39E 8
1. SSE 4 S. 87E* 6
6. 94E 9 1. 21 E 3
1. 16E 5
1. 08E 4
1. 25E S
2. 63E 8 S. 93E 8
8. OOE 8
2. 1 SE 9 1.1SE10
1. 4 iE 9
1. OOE1 0 J. 34E 4
4. 78E 3
2. 82E S
1. 17E 2
1. 98E 2 Lung
1. S7E 3
2. 39 E 8 1. 0 3 E S
3. 3 5 E 7 S. 6SE 7
4. 1 J E 9
2. 1 9 E 8 J. 6 2E 9
6. 1 2 E 4 GI-LLI
1. S7E 3
2. 39E 8
2. 1 SE 9 S. 41 E 6
1. 76E 7
1. 1 0 E 7
2. 03E 8
7. 08E 7
2. 39E 8
1. 07E 8
1. 93E 9
5. 64 E 8
2. 04.E 6
2. 56E 8
1. SOE 9 S. 21E 6 8.81E S
2. 29E 8 1. 11 E S
1. 44E 6
1. 68E10
7. 1 2E 7
1. 68E 8
3. 32E 8 1.17E 8
2. OOE 8
9. 70 E.,
1. 93 E 8 S. 94E /
1. J6E 7
1. 3 J E 8
7. 80 E S S. 71 E 5

Nuclide H-3 C-14 P-32 Cc--51 11n-S4 Fe-5S Fe-S9 Co-S8 Co-60 Ni-63 Zn-6S Rb-86 Rb-88 Sr-89 Sr-90 Y-91 Zc--95 Nb-9S Ru-103_ Ru-106 Ag-110m Te-125m Te--1 27m Te-129m r-1 31 Cs-134 Cs-1 36 Cs-1 37 Ba-1 -10 Ce-1 41 Ce-1 44 Pr-1 -1.3 Nd-147 -~: _ Salem ODCH Rev. 1 9113/85 Table 2-5 (con' t) R( io) Grass-CoK-Hilk PathKay Factor-IN'FANT ( mr-em/yc-pee-uCi/m3l for-H-3 and c-14 (m2 *me-em/yr-per-uCi/secl foe-others Bone

2. 34E 9 1.60E11
1. 3SE 8
2. 2SE 8
3. 49E10 S. 55E 9 Liver
1. 57E 3
5. OOE 8
9. 42E 9
3. 90E 7
8. 72E 7
3. 93E 8
2. 43E 7
8. S1 E 7
2. 1 6E 9
1. 90E10
2. 22E1 0 T. Body Thyroid
1. S?E: 3 S. OOE S
6. 21E 9
1. 61 E S
8. 8 3E 6
2. 33E 7
1. SSE 8
6. 06E 7
2. 08E 8
1. 21 E 9 S. 7SE 9 1.10E10
1. S7E 3 S. OOE 8 1.0SE S
1. 09E 8 S. 99E 7 1.26E10 3.61E 8
1. 22E11 7, 33E 4
6. 83E 3 S. 93E S
8. 69E 3 1.90E S
3. S6E S
1. S 1 E S

-1.. 21 E 8

5. S9E 8
2. 72E 9
3. 6SE1 0
1. 96 E 9 5.1SE10
2. 41 E 8
4. 33E 4 2.33E 6
1. 49E 3 8.82E 2
1. 66E 3
2. 44E s
2. S2 E S
5. 04:E 7 1.40E S
1. 92E 8
3. 21 E 9
6. 80E1 0 S.77E 9
6. 02E1 0
2. 41 E S
2. 64 E 4
9. S2E S 5.S9E 2
9. 06E 2 3.09E10
1. 9SE 3 1.18E 3
1. 41 E S
2. 91 E 3
2. 38E 4
1. S6E S
2. 04E 7 S. 1 OE 7
8. 62E 7 1.41E 9
6. 87E 9
2. 1 SE 9
4. 27E 9
1. 24E 7
3. 11 E 3
1. 30E S
7. 41 E S. SSE 54 S. 07E 7
1. 22E 8
2. 1 SE S 1.05E12 Kidne:;;
1. 57E 3 S. OOE 8
2. 30E 4
8. 63E 6
9. 23E 9
1. 79E-3 1. 7 SE S 1. S 1 E 4
2. 2S E S
4. 03E 8
1. 04E 9 1.40E 9
3. 7SE 9
1. 7SE10
2. 30 E 9 1.62E10 S. 73E 4 8.1SE 3
3. SSE S
2. 08E 2
3. 49 E 2 Lung
1. 57E 3 S. OOE S
2. 05 E 5
4. 26E 7
1. 16E S
7. 1 SE 9
4. 70 E S
6. SSE 9
1. 48E 5 GI -LLI 1. 5 7 E 3 S. OOE S 2.17E 9
4. 71 E 6
1. 43E 7
1. 11 E 7
1. SSE S
6. OSE 7 2.10E S
1. 07E S 1.61E10
5. 69E S 1.06E 8
2. S9E S
1. 52E 9 S. 26E 6 S. 28 E 5
2. 06E S 1.06E S
1. 44E 6
1. 46E10
7. 1 SE 7 1.70E S
3. 34E S.
1. 1 SE 8
1. SSE 8
8. 76 E 7
1. SSE S S. 92E 7
1. 36 E -
1. 3 3 E S
7. 89E S
s. -4E s

'.'.{ j . ~ '/ - Nuclide Bone ~ " .*:-~,.... *.~: :*

  • .:.~-:*_:* :o/
.:. :.:Ji... ~~~-.:'.:-~~~.~*~:~~ ~... _\\i:~*~'~::~!_z:,,.. :::.:.:s"" :*. ~-':

Sal em ODCH Rev. 9/13/BS Table 2-S (con' t) RC iol Vegetation Pathioay FactoI" - ADULT ( mrem/yI" peI" uCi/m3) fOI" H-3 and C-1 4 (m2 ~ mremiyI" per uCi/secl foI" others Liver-T. Body Thyroid Kidney Lung GI-LLI H-3 C-14 P-.32 Cr--51 Hn-54 Fe-55 Fe-S9 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr-89 St"-90 Y-91 Zr-9S Nb-95 Ru-103 Ru-106 Ag-110m Te-12Sm Te-127m Te-129m I -1 31 Cs-134 Cs-136 Cs-137 Ba-140 Ce-1 41 Ce-1 H Pr-143 Nd-1-17

2. 28E 8
1. 40E 9
2. 09E 8
1. 27E 8
1. 04E10 3.17E 8
9. 96E 9
6. 04E11 S. 1 3E 6
1. 19E 6
1. 42E S
4. SOE 6
1. 9 3E 8
1. 06E 7
9. 66E 7
3. 49E 8 2.SSE 8 8.09E 7
4. 66 E 9
  • L 20E /
6. 36E 9
1. 29 E 8
1. 96E S
3. 29 E
6. HE 4
3. 34E 4
2. 26E J
4. SSE 7
8. 73E 7 3.11E 8
1. 4SE 8
2. 99E 8
3. 09E 7 1.67E 8 7.21E 8
1. 01 E 9 2.19E 8
3. 29 E 6
3. 81 E 5
7. 91 E 4
9. 7 6E 6
3. SOE 7
1. 2S E 8
9. SOE /
1. 16E 8
1. 1 1 E1 0
1. 66 E 8
8. 70E 9
1. 62E S
1. 33E S
1. 3 7 E 7
2. SH 4
3. 86E 4
2. 26E 3
4. SSE 7 S. 42E 7 4.66E 4
5. 94E 7
3. 37E 7 1.14E 8
6. 92E 7
3. 69E 8
3. 49E 8
4. S6E 8
1. 02E 8
1. 74E 6
2. 86E 8 1.48E11
1. 37E S
2. 58E S
4. 2 SE 4
2. 07E 6
2. 44E 7 S. BOE 6 1.29E 7
4. 26E 7
4. 0 3 E 7 6.63E 7
9. 07E 9
1. 19E 8 S. 70E 9
8. 43E 6
1. S1 E 4
1. 77E 6
3. 14E 3
2. 31 E 3 S5
2. 26E 3
2. 26E 3 4.SSE7 4.SSE7 2.79E 4 1.03E 4
2. 90E 7
8. 92E 7
8. ?SE 7
3. 79E10

-9. 27E 7

6. 75E 8 S. 97E S
7. 81E 4
1. 83E 7
3. 72E 8
1. 92E 7
3. 93E 8
1. 42E 9
1. 06 E 9
1. 98 E 8
3. S9E 9
9. 24E 7 2.9SE 9 S. 49 E 4
6. 17 E 4
8. 1 6 E 6
1. 47 E 4
2. 2SE 4
2. 26 E 3
4. SSE 7
6. 19E 4
8. 06 E 7
8. 3SE 7
1. 1 9E 9
1. 27E 7
9. 81 E 8
9. 2 SE 4
2. 26E 3
4. SSE 7
1. SSE 8
1. 1 7 E 7
9. 54E 8
8. 29E 7
9. 96E 8
6. 26E 8
3. 1 4E 9
1. SOE 8
6. 36E 8
4. 32E 7
4. S4E-S
1. 60E 9 1.7SE10
2. 82E 9
1. 21 E 9
4. 80 E 8 S. 61 E 8
1. 2SE10
3. 98E 9
3. 86E 8 1.17E 9
1. 28E 9
3. OSE -
1. 94E 8
1. 89 E 7
1. 68E 8
2. 65E 8 S. 08 E 8 1.11E10 2.78E 8
1. 8SE 8

. :~

~*..

-i -.. ~ _.-. _.-.. :_' ~:: Nuclide H-3 C-14 P-32 Cr-51

  • Hn-54 Fe-55 Fe-59 Co-58 Co-60 N'i-63 Zn-65 Rb-86 Rb-88 Sr-89 Sr-90 y -91 Zt"-95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 J 1 Cs-1 34 Cs-136 Cs-1 37 Ba-1 40 Ce-1 41 Ce-144 p t"-143 Nd-147 Salem ODCM Re'I, 1

9:13/85 Table 2-5 C con' tl R(iol Vegetation Path~ay Factor - TEENAGER ( mr-em/yt" pet" uCi/m3l for-H-3 and C-14 Bone

3. 69E 8
1. 61 E 9 J.25E 8 1.81E 8
1. 61 E1 0
4. 24E 8 1.51E10 7.51E11
7. 87E 6
1. 748 6
1. 92E 5 6.87E 5
3. 09 E 8 1.52E 7
1. 48E 8
5. 51 E 8 J. 67E 8 7...,OE 7.09E 9
4. 29 E 1.01E10 1.38E S
2. 8 2 E 5
5. 27E -
7. 1 2E 4
3. 53E 4

( m2 1< mt"emlyC" per' uCi/secl for" other"s Li *1eC"

2. 28 E 3
7. 38E 7
9. 96E: 7
4. 52E 8
2. 31 E 8
4. 22E 8 T. Body ThyC"oid
2. 28 E 3 7.38E 7 6.23E 7
6. 20E 4
8. 97E 7
5. 38E 7 1.63E 8
2. 28 E 3
7. 38E 7 3.44E 4
4. JBE 7
1. 01E: 8
2. 49E 8
1. 13E 9 1.47E 9
2. 73E 8
5. 1 3 E 6 5.49E 5 1. 0 6 E 5
1. HE 7
5. HE 7
1. 96 E 8 1.36E 8 1.0BE 8 1.67£10
1. 69 E 8
1. 35E10
1. 69 E 5
1. BBE 5
2. 1 8 E ;
2. 84E 4
3. 94E 4
5. 50E 8
5. 45E 8
6. 86E 8
1. 28E 8
2. 74E 6
4. 33E 8 1.85E11
2. 11 E 5 J. 78E 5
5. 86E 4
2. 94E 6 3.90E 7
8. 74E 6 1.98E 7
6. 56E 7
5. 81 E 7
5. 79E 7
7. 74E 9 1.13E 8 4.69E 9
8. 91 E 6 2.16E 4 2.83E 6
3. 5 5 E 3
2. 36E 3 56 4.14E 7
1. 31 E 8
1. 1 8 E 8 3.14E10 Kidney
2. 2 8 E J
7. 38E 7
1. 36E 4
1. 35E 8 9.41E 8
8. 07E 5
1. 03 E 5
2. 42E.,
5. 97E 3
2. HE -
2. 24E 9
1. 54E 9
1. 8 SE 8
5. 3 OE 9
9. 1 9E 7

. 4. 59E 9 5..., 5 E 4

8. 86E 4
1. 30E
1. 6 5 E 4
2. 32E 4 Lung
2. 28 E 3
7. J 8 E 7
8. 8 5 E 4 1. 4 6 E 8 1. 3 3 E 8
2. 0 2 E 9
1. 45 E 7
1. 7 8 E 9
1. 1 4E 5 GI-LL!
2. 28 E 3
7. 38E 7
1. 35E 8
1. 04E 7
9. 28E 8 9.98E 7
9. 98E 8
6. 04E 8
3. 24E 9 1.81E 8 6.23E 8
4. 05E 7
4. 40E-1
1. BOE 9 2.11E10
3. 23 E 9
1. 27 E 9
4. 55E 8
5. 74E 8 1.48E10
4. 04E 9
4. 37E 8
1. 37E 9 1.38E 9
2. 1 3 E,
2. 08 E 8
1. 3 5 E 7 1.92E 8
2. 1 3 E 8
5. 38E 8
1. 3JE10
2. 34E 8
1. 42E 8

.i l Salem ODCH Rev. 1 9r1Ji85 Table 2-5 (con' tl RCiol Vegetation Path~ay Factor - CHILD ( mrem/yr per uCiimJ) for H-3 and C-14 ( m2 "' mrem; yr per uCi/secl for others Nuclide Bone Liver T. Body Thyro1d Kidney Lung GI-LLI H-3 C-14 P-32 c r-51 Hn-54 Fe-55 Fe-59 Co-SS Co-60 Ni-63 Zn-65 Rb-86 Rb-88 Sr-S9 St"-90 '(-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-110m Te-125m Te-127m Te-129m I -1 31 Cs-1 34 Cs-136 Cs-137 Ba-1 0 Ca -1 41 Ce-1 H Pr-143 Nd-14 7

4. 3 7E 3 S.S9E S 1.7SE 8 3.37E 9 1.5SE 8
6. 61 E 8 S. OOE 8
4. 24E 8
4. 01 E S
6. 49E 8 6.47E 7
3. 78E 8 3.95E10 2.11E 9
8. 12E S
2. 16E 9 4.52E 8
9. 1 9E 6
3. 59E10
1. 24E12 1.87E 7
3. 90E 6
4. 1 OE 5
1. 55E 7
7. 45E 8
3. 22E 7
3. 51 E 8
1. 32 E 9 8.54E 8
1. 43 E 8 1.60E10
8. 06 E 7 2.39E10
2. :':'E

'.:3

6. SJE 5 1.2'.'E 8
1. rnE 5
7. 1 6 E 4
8. SSE 5
1. 59E 5 2.18E 7
9. 50E 7
3. 56E 8
2. 39E 8
1. HE 8
2. 63E10
2. 22E 8
2. 29E10
2. -DE 5 J. 26E 5
3. 98E 7
4. HE 4
5. SOE 4
4. 37E 3
1. 78E 8
1. JOE S
1. 18E 5
1. 76E 8
1. 31 E S
3. 23E S
1. 98E 8
1. 1 2E 9
1. 34E 9
1. 35E 9
2. 7SE 8
6. 39 E 6
1. 03E 9 3.15E11
5. 01 E 5
7. 64E 5
1. 1 4 E 5
5. 94E 6
9. 30E 7
1. 74E 7 4.67E 7
1. 57E S
1. 33E 8 S. 1 SE 7 5.54E 9 1.43E S
3. 38E 9
1. 62E 7
4. 84E 4
6. 78E 6
7. 3 7E 3
4. 49E 3 57
4. 37E J
1. 78 E 8
6. 54 E 4
9. 84E 7
3. 1 6 E 8
2. 75E 8
4. 76 E1 0
4. 37E 3
1. 78E 8
1. 79 E 4 1.85E 8
1. 36E 9 1.23E 6
1. 50 E 5
3. S9 E 7 1.01E 9 4.05E...,
3. 77E 9 2.51E 9
2. 36E S
8. 14E 9
1. 1 8 E 8
7. 46E 9

...,. 90 E 4

1. 43E 5 2.21E 7 2..J.1 E 4
3. 1 SE 4
4. J!E 3
1. 78E 8
1. 1 9 E 5
2. 40E S
1. S8 E S
2. nE 9
1. 7 6 E
2. 68 E 9
1. 4 5 E 5
4. J7E 3
1. 78E S
9. 30E 7
6. 25E 6
5. 55E 8 7.S6E 7
6. 76E 8
3. 77E S 2.10E 9
1. 42E 8
3. 80 E S
2. 91 E 7 4.51E 5
1. 39E 9
1. 67E10
2. 49E 9 S.95E 8
2. 95E S
3. 99E 8 1.16E10
2. SSE 9
3. 38E S
1. 07E 9
1. 04E 9
1. 28 E 7
1. 42 E S
7. 79E 6
1. 4 3 E S
1. 40 E 8

-l.. 07 E 8 1.04E10

1. 60 E 8
9. 1 8 E 7

. *.. ~*',.... Salem ODCH Rev. 1 9i1 J;a5 Table 2-5 (con' tl R( iol Ground Plane Path,.ay Factor (m2

  • mrem/yr per uCi/secl Nuclide any Or-gan H-3 C-14 P-32 Cr-51
4. 68 E 6 Mn-54
1. HE 9 Fe-55
j.

Fe-59

2. 75E 8 Co-58
3. B2E 8 Co-60 2.15E10 Ni-6 3 Zn-65
7. 45E 8 Rb-86
8. 98E 6 Rb-88
3. 32 E 8 St'-89
2. 1 6 E 4 Sr-90 Y-91
1. 09E 6 Zr--95
2. 48 E 8 Nb-95
1. 36E 8 Ru-103
1. 09 E 8 Ru-106
  • L 21 E 8 Ag-110m 3..PE 9 Te-125m*
1. 55E 6 Te-127m
9. 1 7 E 4 Te*-1 29m
2. OOE -:

I -1 31

1. 7 2E 7 Cs -1 34
6. 75E 9 Cs-136
1. 49 E 8 Cs-1 37 1.03E10 Ba -1 4 0
2. 05E..,

Ce -1 41

1. 36 E 7 Ce-1 H
6. 95E 7 p r--143 Nrj-147
8. 40E 6 58

Salem ODCH Re*1. J. 1 3 i 8 5 APPENDIX A Evaluation of Default HPC Value fo~ Liquid Effluents A-1

'* *.1.. (.* Salem ODCH Rev. '.L13/85 Appendix A Evaluation of Default HPC Value for-Liquid Effluents In accordance 11ith the requirements of Technical Specification ( 3. 3. 3. 10) the radioactive liquid effluent monitor-s shall be operable ~ith alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the HPC value of 10 CFR 20, Appendix 8, Table II, Column

2.

The determination of allo11able radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and cor-r-esponding MPC values. In or-der-to limit the need for-r-outinely having to r-eestablish the alar-m setpoints as a function of changing r-adionuclide distr-ibutions, a default alarm setpoint can be established. .This default setpoint can be based on an evaluation of the r-adionuclide distr-ibution of the liquid effluents from Salem and the effective MPG value for this distr-ibution. The effective MPC value for-a radionuclide distr-ibution is calculated by the equation: liher-e: MP Ce Ci MP Ci L Ci MPCe = \\A. l) an effective MPC value for-a mixture of radionuclide C uCi/ml) = concentr-ation of r-adionuclide i in the mixture the 10 CFR 20, Appendix B, 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 year-s from Salem, an effective MPC value can be determined. F!.esults are presented in Tables A-1 and A-2 for-Unit 1 and Unit 2, respectively. A-2

i ,*1 ~*._ Salem ODCH Rev.* 1 9/13/85 Consider-ing the aver-age effecti*:e HPC values for-the year-s 1981 thr-ough 1984, it is r-easonable to select an HPC value of 1E-05 uCi!ml as typical of liquid e r-adwaste dischar-ges. Using this value to calculate the default R18 alar-m setpoint value, r-esul ts in a setpoint that:

1) 2l Hill not r-equir-e fr-equent re-adjustment due to minor-var-iations in the nuclide distr-ibution which ar-e typical of r-outine plant oper-ations, and Hill pr-ovide for-a each batch r-eleasel Tables 1 -1 and 1 -2).

liquid radwaste discharge rate (as evaluated for that is compatible with plant oper-ations ( r-efer to A-3

l

-~ -'

  • ~..

Na-24 Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zr-95 Nb-95 Nb-97 Tc-99fll Sf-89 Sr-90 ~o-99 Aq-110~ c;1-H1 iJI

  • *v Sb-124 Sb-125 I-131

!-~11 J. l.W-:.i I-135 Cs-134 1.--411

,,.~

.i.:Jf Ba-140 La-140 Total Ci ~Pee !uCi/11 j JE-05 2E-03 1E-04 5E-05 9E-05 3E-OS 6E-05 1E-04 9E-04 3E-03 3E-06 3E-07 4E-tJ5 1t'-!1l;

  • .ii.. 'J.i 3E-05 2E-05 1E-04 3£-(17 tE-06 4E-~)b 9E-06 2E-05 2E-05 2E-05

-~*~ >::*~**,-;;* _.*.. '* ~ I iable A-1 Calculation of Effective ~PC 2.4E-02 5,9E-02 7.4E-02 3.8E-03 4.SE-01 3.2E-1)1 1.0E-02 1.8£-02 Ni DH N!u N/fi NiD 2.SE-04 N/D 3.9E-04 6.2E-04 "! :'\\;C'_lH -.JI VL. ~.z.i. t.1E-01 8.3E-02 NIU 7.6E-02 N!O Y!l'\\

11 11 1,59 4.86E+05 3.3E-06 Sa!er. Ur.it 1 Activity Released ICil

!982 1.9E-03 1.4E-01 2.1E-01 3.6E-!)3

1. 7 9.1E-01 1.1E-02 4.3E-1)2 9.SE-03 N/O N/O u /f\\

iHU LOE-03 4 7~-;)1 Ill. ".t'W 2.2£-04 8.0E-03 6.3E-03 6.SE-02 5.5E.-tJ3 3.SE-04 4.0E-02 5.9E-iJ2 N/D 7.SE-03 3.24 2.83E+05

1. i4E-05 1983 5.JE-03 6.2E-02 1.6E-01 4.2E-02 1.3 7.tE-01 3.0E-03 2.2E-02 3.bE-04 N/O 1.2E-03 N/D L6E-03 N/O 3.BE-04 1.4E-02 4.4E-02 2.4E-02 3.JE-02 t.6£-03 i.3£-{)2 3.0E-02 1.3E-02 1.JE-02 1.66E+05 f * ~PC vaiue for mestrided ai*ea frn1 10 CFR 20, AppendU B, Tabie II, Colian 2.

ff N/D - not detected .... ' *... : *. -: * '*. -.: * ~=. *-*~-.. *.. 1984 5.6E-!)3 5.JE-02 L9E-Ot 5.SE-03 1.6 1.2 1.8E-03

1. 7E-02 2.0E-02 L6E-03 4.2E-04 2.2E-OS
1. 9E-!)3 NiD 9.4E-04 1.7E-02 4.9E-03 4.SE-02 2.SE-02 1.2£-!)J 5.tE-02 s.aE-02

~ C'-l':"?

.,.i.I.. *.*
.J 1".6E-~)2 3.32 2.46E+05

--~ * .:.1 "j -I * .... ~ ~* ...,. ). Nuclide MPCJ !uC'i/11} Na-24 3E-05 Cr-51 2E-03 ~n-54 !E-04 Fe-59 SE-05 Ca-58 9E-05 Co-60 3E-05 Zr-95 6E-05 Nb-95 !E-04 Nb-97 9E-04 ic-991 3E-03 Sr-89 JE-06 Sr-90 3E-07 Mo-99 4E-05 Ag-1101 3E-05 Sn-113 8£-05 Sb-124 2E-05 Sb-125 tE-04 T-CH* 3E-07 "'""~ Y-l11 J. .i.:.iw tE-06 I-135 4E-tJ6 Cs-134 9E-06 Cs-137 2E-05 Ba-140 2E-05 La-140 2E-05 Total.. ~l I.. l l __ ;a_. __ ~or; iii V.i. ~?Ce (uCi!;lJ Tab 1 e-A-2 Calculation of Effective ~PC Sale1 Unit 2 '=

:y; Activity Released (Ci) 1981 1952 1983 2.0E-01 t.2E-!J3 9.2E-03 9.5E-02 1.1E-01 4.6E-02 4.4E-02 2.0E-01 L4E-01 5.aE-03 5.6E-03 3.1E-02
8. tE-01
1. 7 t,7 2.6E-Ot 3.6E-Of 5.7E-01

!.OE-02 9.7E-03 5.2E-i)3 t.SE-02 2.3E-02 1.6E-02 Ni OH 1.1E-02 1.1E-02 N/D N/O N/D N/D N/O 3.2E-04 N/O N/O N/O 7.4E-05 L 7E-04 3.0E-03 u,,, 3.9E-03 N/O ill!.! 2.6E-{)4 1.6E-04 5.9E-04 9.1E-04 1 i~C-fr1 11\\!I. ;.:i. 2.0E-02 8a4E-03 1.0E-02 9.bE-02 2.6E-02 1.3E-01 ~;:-fi*j ..J1\\.i._.,,. 6.0E-04 ' 'E '*3 o.ll -u. 5.4E-02 N/O N/D 1.bE-03 t.8£-02 5.. iE-02 2.0E-02 2.9E-02 7.6E-02 3.6E-02 N/D N/O 9.3E-03 N'"* iU 6.7E-03

3. iE-02 1.52 3.21 2.39 i.16E+05 5.00E+OS 2.26E+05 1.31E-05 6.42E-06 1.28E-05

+ ~PC value far unrestricted area fro! 10 CFR 20, Appendix B, Table II, Colu~n 2. . 11 N/D - not detected 1984

4. 4E-03 3.6E-i)2 i.bE-01 7.6E-i)3 L3 9.SE-01
1. 2E-03
1. 4E-02 2.tE-02
1. 4E-03 3.2E-04 4.1E-05 1.4E-03 N/D 1.2E-03 3,0E-02 3.6E-03 4.2E-02 2.6E-02 4.4E-04 2.6E-02 4.SE-02 6,6E-03 3.0E-02 2.74 2.24E+05 1.22E-05

.Salem ODCH Rev. 9' 1 3, 8 5 APPENDIX B Technical Basis for Effective Dose ractors Liquid Radioactive Effluent B-1

']

  • .;~
1 d

~.. *..... *... : :. *.

...~*: );:.-

Salem ODCH Rev. APPENDIX B Technical Basis for Effective Dose Factors - Liquid Effluent Releases 9113/85 The radioactive liquid effluents for the years

1984, 1983 and 1982 Rere evaluated to determine the dose contribution of the radionuclide distribution.

This analysis Ras performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance

ii th the dose limits of Technical Specification 3. 11. 1. 2.

For the radionuclide distribution of effluents from Salem, the controlling organ is the GI-LLI. The calculated GI-LLI dose is predominately a function of the Fe-59, C0-58, C0-60 and Nb-95 releases. The radionuclides, Co-58 and C0-60 contribute the large majority of the calculated total body dose. The results of this evaluation are presented in Table B-1 and Table 8-2. For purposes of simplifying the details of the dose calculational_ process, it is conservative to identify a controlling, dose significant radion~clide and limit the calculat1onal process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative acti*1ity for all radionuclidesl by this dose conversion factor provi~es for a dose calculational method that is simplified Rhile also being conservative. For the evaluation of the maximum organ dose, it is conservative to use the Nb-95 dose conversion factor (1. 51 E~06 mrem/hr per

uCiiml, GI-LLil.

By this

approach, the maxi~um organ dose Rill be overestimated since this nuclide has the highest organ dose factor of all the radionuclides evaluated.

For the total body calculation, the Fe-59 dose factor (7. 27 E~04 mrem/hr per uCL' ml, total body) is the highest among the identified dominant nuclides. 8-2

    • .j *
j

~.. * .~.: Salem OOCM Rev. 1 9113/85 For evaluating compliance 11ith the dose limits of Technical Specification

3. 11. 1. 2, the folloRing simplified equations may be used:

11here:

1. 67E-02 "' VOL Dtb = --------------

A Fe-59,TB"' CH ~Ci Dtb = dose to the total body (mrem) A Fe-59,TB VOL = 2= c = i =

7. 27E+04, total body ingestion dose conversion factor Fe-59 (mrem/hr pe~ uCi/mll volume of liquid effluent released Cgal) total concentratibn of all radionuclides ( uCi/ml)

( B. 1 l for-CH = average circulating Rater 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. 21 E+03 * 'IOL

"' L Ci CB. 2l Dtb = CH

1. 67E-02"' VOL A A Nb-95,GI-LLI 2:: Ci CB. 3l Dmax

= CH 11here: Dmax = maximum organ dose Cmreml A Nb-95,GI-LLI = 1. 51E+06,Gi-LLI ingestion dose conversion factor for Hn-54 Cmrem/hr per uCi/mll Substituting the value for A the equation simplifies to: Nb-95,GI-LLI 2'. 52E+04 * 'IOL Dmax ( B. 4l CH B-3 .:_____~--* _-- __. ___ _

. ~

  • -~

--.. ~ - '.-.. *'~:.. -:t. Salem ODCM Rev. 9/13/85 Tritium is not included in the limited analysis dose assessment for liquid rel eases, 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 pathKays.

This amounts to 0. 08% of the design objective dose of 3 mrem/yr. Furthermor*e, the release of tritium is a function. of operating time and poKer level and is essentially unrelated to radRaste system operation. B-4

i., ~ *.,_*.:~*-*:=.:.. ;.*~- ;._.'; 1984 Radio-nuc i ide Release TB 61-LLI Liver Dose Dose Dose Fr*ac. Frac. Frac. Fe-59 Co-sa Co-60 Ag-1101 ~n-54 Nb-95 Cs-137 Cs-134

A,.__.;4 VI

.ii. 5.83E-03 0.05 1.58. 0.25 1.20 0.54

1. 74E-02 t

5.84E-02 0,05 5.00E-02 0.08 5.30E-02 t Totai 3.33E+OO t less than 0.01 N/D = not detected !'I l'<aa10-Release nui:l ide 1984 TB Dose 0.04 0.21 I\\ M i.11't.t: 0.05 0.28 t t t 0.18 0,02 0.34 0.22 f 0.11 0.13 t Frac. Frac. F~aca Fe-59 7.56E-03 o.oa Ca-58 1.30 Os25 Ca-60 9.79E-01 0.53 Ag-110~ N/O 1 Mn-54 .Nb-95 Cs-137 Cs-134 1'*--~l WI J4 Total t.61E-01 0.03 1.36E-02 + 4a81E-02 0.05 2.6JE-02 0.05 3.64E-02 f 2,75E+OO t less than 0.01 N/O = net detected 0.06 !),41 0.24 0.13 t),28 f 0.15 0.10

\\ :'\\'T

=.j,i.ji Table B-1 Adult Dose Contributions Fish and Invertebrate Pathways Unit 1 Re1me ff';\\ i.V.i./ 1983 TB Om Liver* Dase Frac. Frac.

Frac, 4.21E-02 0.34 1.82 0.27 7.06E-!)1 0.30 N/D t

1,63E-~)1 0.02 2.17E-02 1 3, 04E-02 O. i14 1.83E-tl2 i).03 6.iSE-02 i 3.03E+OO Tab12 S-2 0.30 {),03 0.26 f 0.04 !).37 t f f Adtilt Das~ Cantributi~ns Fish and *1nverte~rat2 Pathways Unit 2 1983 0166 0.09 O.iO f 0.09 0.03 0.02 Release TB 61-LLI Livei" IR'\\ II, 1 \\ w.1.1 Dose . Dose 3.12E-02 J l: 1.1:10 N!D 1.36E-01 1.59E-02 3.SBE-02

1. 98E-tJ2 4.SBE-02 2e85E+OO Frac.

Frac.

Frac, 0.31 0.30 0.29 t

0.04 0.04

  • ..::.:.1

.24 .~., ri.£.. .03 ~28 0.61 0.10 0110 0.10 .03 ~ 1 -.: *.;;::. ~ 2 ; t : Release (Ci) 1932 TB Dose 61-Lll Dose Liver* Dose

Frac, Frac.

Frac. 3.57E-!)J 0.08

1. 70 0.30 9,.f)9E-01 0.45 4.70E-03 t

2.0bE-01 0.04 2.53E-02 + 5.89E-02 0.06 3.95E-02 0.07 1.38E-1)1 t 3.2iE+OO 1982 {Cil {),05 0.20 0.28 0.03 0.04 0.40 t f t 5I-LLI Dose 0.23 0.15

..;,t,i,.

i) *)i

  • .: 8...

t 0.10 l),!)9 I 1 ; ~:.... ~. ~J.ti:l o~se Frac. Frac. Frac. 5.6iE-03 '5.61E-Ot 3s92E-03 2.02£-01 2.28E-02 7.64£-02 5.06E-02 1.07E-Ot 3c22E+OO

'\\

i°\\C

} I :j_j 0.30 0.04 ti !1 J

"*JI \\,l-'t 1\\

  • "'\\*"";
.;,Li..

0.30 0.02 0.05 0.37 t f f

":
  • L

~i I i iJ

o. 15 0.22
'\\..,j 1*} ski

-~1...

. ~-' ~.*. -. -.. --. .::. ~.\\:.. '.* Salem OOCM Rev. 9/13/85 APPENDIX C .j j Technical Bases fo~ Effective Dose Facto~s Gaseous Radioactive Effluent C-1

' -. ~-". -. Salem ODCM Re*1. APPENDIX C Technical Bases for Effective Dose Factors - Gaseous Radioactive Effluents <J. 1 3 / 8 5 The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective

factors, which can be based on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in the environment Ci. e., instead of having to perform individual radionuclide dose analyses only a

single multiplication (Keff, Heff or Neff) times the total quantity of radioactive material released would be needed). This approach provide~ a reasonable estimate of the actual dose Khile eliminating the need for a detailed calculational technique. Effective dose transfer factors are calculated by the following equations: wher:"e: Keff Ki fi

her
"e

Keff = LC Ki fil ( c. 1 :. the effective total body dose factor" d~e to gamma emissions fr"om all noble gases released = the total body dose factor due to gamma emissions fr"om each noble gas radionuclide i r"eleased = the fractional abundance of noble gas r:"adionuclide i r"elative to the total noble gas activity O:L + 1.1 Mleff = LCCLi + 1.1 Mil A fi) ( c. 2) (L + 1.1 Mleff the effective skin dose factor due to beta and gamma emissions from all noble gases released C Li +-

1. 1 Mil the skin dose factor due to beta and gamma emissions t'rom each noble gas radionuclide i released C-2
  • i
~
    • l
j

.;J J J -. - *-..-.. : ~-*.. i;her-e: Hef f Hi Rher-e: Neff Ni .-._ '***** **. *._:,*.:.:~.:_... *.. ;'.r~*: ~"~~.:-;:(:;.-.. 1~~.~;._*.. *.****~,.. *.. : Salem ODCH P.e*;. 9 '1 3/85 Heff = LCHi

k.

fi) ( C. 3) the effective air-dose factor-due to gamma emissions fr-om all noble gases r-eleased = the air-dose factor-due to gamma emissions fr-om each noble gas radionuclide i r-eleased Neff= L(Ni -~ fil (C.4) the effective air-dose factor due to beta emissions from all noble gases r-eleased the air-dose factor-due to beta emissions fr-om each noble gas r-adionuclide i released No~mally, it Rould be expected that past radioactive effluent data r1ould be used for the determination of the effective dose factor-s. Ho Rev er-, the noble gas r-eleases from Salem have been maintained to such negligible quantities that the inher-ent variability in the data makes any meaningful evaluations difficult. For the past three ;ear-s, the total noble gas r-eleases have been limited to 1400 Ci fOt" 1 982, 900 Ci for-1983, and 2,000 Ci for 198~. Therefor-e, in order-to provide a reasonable basis for-the der-ivation of the effective noble gas dose factor-s, the primar-y coolant sour-ce term from ANSI N237-1976/ A.NS-18. 1, "Sour-ce Term Specifications," has been used as representing a typical distr-ibution. The effective dose factors as derived ar-e pr-esented in table C-1. To provide an additional degree of conservatism, a factor of 0. 50 is introduced into the dose calculational pr-ocess Rhen the effective dose tr-ansfer factor is used. This conservatism provides additional assur-ance that the evaluation of doses by the use of a single effective factor-Rill not significantly under-estimate any actual doses in the environment. For evaluating compliance Rith the dose limits of Technical Specification C-3

,~..: -

Salem ODCH Rev. 9/13/85

3. 11. 2. 2, the folloKing simplified equations may be used:

and 11here: D,r = D,6 X/Q = He ff Neff = 2: Qi 3.17E-08

0. 50
3. 1 7E-08 Do

= -------- XIQ Meff

  • 2: Qi

( c. 5)

0. 50 3.17E-08 D,8

= -------- XIQ Neff }< L Qi ( c. 6)

0. 50 air dose due to gamma emissions for the cumulative release of all noble gases ( mrad) air dose due to beta emissions for the cumulative release of all noble gases Cmradl atmospheric dispersion to the controlling site boundary (sec/ m3)
5. 3E+02, effective gamma-air dose factor ( mrad/yr per uCi/m3l
1. 1 E+03, effective beta-air dose factor ( mrad/yr per uCi/m3) cumulative release for all noble gas radionuclides ( uCi) conversion factor (yr/sec) conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to:

D d' =

3. 5E-05 XIQ

"' L Qi ( c. 7) and Df =

7. OE-05
UQ

}< L: Qi ( c. 8) The effective dose factors are used on a very limited basis for the purpose of facilitating the timely assessment of radioacti *1e effluent releas.es, particularly during periods of computer malfunction Khere a detailed dose assessment may be unavailable. C-4

1 ~1., J -~ Salem ODCH Re*1. 9:13/85 Noble Gases - Total Body and Skin Radionuclide Kr-85 Kr-88 Xe-133m Xe-1 33 Xe-135 Total Noble Gases - Air Radionuclide Kr-85 Kr-88 Xe-133m Xe:-1 33 Xe-135 Total fi"'

0. 01
0. 01
0. 01
0. 95
0. *02 fi*
0. 01
0. 01
0. 01
0. 95
0. 02 Table C-1 Effective Dose Factors Total Body Effective Dose Factor Ke ff Cmrem/yr per uCi/m3l 1.SE+02
2. SE+OO
3. OE+02
3. 6Et01
4. 8Et02 Gamma Air Effective Dose Factor He ff Cmrad/yr per uCi/m3l 1.5Et02
3. 3E+OO
3. 4E+02
3. BE+01
5. 3 Et02 Based on Noble gas distribution from ANSI N237-1976/ ANSI-18. 1, Specifications."

C-5 Skin Et'fecti*1e Dose Factor (Lt 1. 1 Hl eff lmrem;yr per uCi/m3l

1. 4E+01 1.9E+02
1. 4E+01
6. 6E+02
7. 9E+01
9. 6E+02 Beta Air Effective Dose Factor Neff Cmrad/yr per uCi/m3)
2. OE+01
2. 9Et01
1. SE+01
1. OE+OJ 4.. 9E+01
1. 1 Et03 "Source Ter-m

. _._:. ~-. -*

  • r ***.*.. *

.:.'.~".. *". Salem ODCH Re~. _1 9 '1 . 8 5 Appendix D Radiological Environmental Monitoring P~o~ram Sample Type, Location and Analysis

EJIJOS&R PAT*AY I. Al~ la) p A R T I c u L A T E s I Control Stotlon STATION CODE 1001 252 . lfl 2f2 RADIOlOGICAl ENVIAOtMHTAL MOHIHIUt<24 hr. after.-pll119 ta ailcw for RA a~d Tii.oron daughter clecey 6-- laotoplc analyal* oa ~... rterly ~*t*

  • ..._.. 1pectr01Mtry ah*l I be perfonwd It gr-on botta exc*ad* t.,. tl-li th* y*orly *... n of control atatlon value *

. rr ~ H 0 l"4 8 H n ~ tlJ ~ H 'tJ

iilt-3 Ill 0 Pl IQ ZO' 3
....

tlJ " z 8 0 ~Q toJ I

  • .1.*:.*

ID 3: I-' 0 z H >-3 0

Ill H z Cl

'tJ 8 ~

I

  • Al ROruUtE Cb*

0 D i N E I Cofttrol 5totlon STAT ION COOE lUCAllON 100 i

1. 9 *I SSW of v.nt 16£1 4.1 *I Httf of vent 2f2
8. J *I NNE of vent 0.4 *I NHE"ot vont I IO *I Hl ot vonl COLLECTION HETH(I)

A TtoA I mpregn~t41d marcoai flo..-through cartridge Rs C10nnected to air portlculate air ~-pier on4 It. col l*cted Meokll'

r TWP£ Ml) fRfQIEICY Of A*LYSES lodlM UI aHIV** are pertorMll..-iv "O

Ill IQ

  • tJ 0

'IJ '° i*. i' e H 0 § H ~ tlJ ~ H :u t-) 0&11 z D' 3:...... tlJ CD z t-) ~ 0 I ~...... 0 z H t-) 0 :a H z Q "O 8 ~

~..

.,.'I

j, I PATHWAY STATION toot II. SOIL 1001 161: 1 Xii ' lttl I If I 2f2 !I> I 2f I 2fl 2S2 lOCATIOH

1. 9 al SSW of v*nt 4o1 al Htlil of vent 16.6 *llH NE of vent 110 al NE of *tat Ion 5.1 al N of vent
8. J al NNf of ve11t
1. ~ al E or v.-nt

~ al NHf of vent 4.4 *I NNf of li~t 0.4 al NNt: of vont COUECTIOH NEltlOO 10 soll plug* to a depth of 611 over on arN of 25 1t2 Al"e coapo*l1ed and.. eled In

  • pl**tlc INig at.. ch location**

A seaple *II I be collected froa.. di locat Ion once ev.-y 1.,_rs AIMLYSH 6-spectroaetry perforaed oa oollectiOA Sr-90 anal¥Ae* °" -

  • ...,1e fr*

Mdli locatlOA a. ool lectlon HSoll HllPIH ar* takon In gundral *Ith proc... ur*s outl lned Iii ttASL-100 (Rev. 5/D)e It a aultable aaaple mnAOt be obtel~ at a loc:etlon. a *eaple shell bo obhln41d fr<91 an-locatlon. The ta: *11*11 be notified I* wltl119 of the uw Mllfl* loc:atlon. I C-trol Station "O.. &Q

  • w 0

tlJ '° ~ H 0 I:"' 8 H 0 ~* llJ ~ H :a o-3 0111 ZO' ~:; ~ t'3 ~~ I 3:...... 0 z H t'3 0

0

.... z a 'tJ 8 ~- ~:.

        • .. **.*I

PAJHWAY STAI ION COC!E LOCAi ION COLLECTION METHOD AIMt.YSES 111. DIRECT E 2S2 0.4 ** NNE of vent H 0 t'" ~* 1.0 ** E of v&nt 8 bS2 0.2 *I ESE of v&nt H 1** 0 JSI 0.12 ** SE ol vdnt ~ r*. 1051

o. 14 *I SSW of vent HSI 0.09 al s.. of vent Pl

!iO I 1., al E of vent ~ 1001 1.9 ** S5'11 of vent 2 TLD *5 wlll a. coll*cted 6--..._ quarterly H 'U ~ '"3 l4DI 1.4 **._.., of vent lr01B -ch location quarterly 0111 2E I 4.4 *I NNE of vent IQ z lJ' 3:..... 1E I 4.1 ** NE of vent MID z UEI

4. 2 ** NE of v&ut

'"3 16E I 4.1 ** NhW ot vunt 0 ~o f1J If I ~.8 ** H ol VOllt I 2f2 &.1 ** NNE of vent '° 3:..... 0 5f I a.o *I £ of vunt z H t.f I ,_ "-" ES~ or.,.,.t '"3 0 Iii

t. I.... SE &t Vulll
a llF I

!1.2.1 SW of vent H z Bfl

9. 8 ** W of vent 1GI I

16.6 *I Nf of vent Q 'U 2111 ' )4 *I NNE of vunt 8 )Ill ' 12 *I Nl Of vunt JIU I 110 *I NE Of vent ~ I Control StetlOll

PATHIMY STATION Coot LOCATl<>>t 111. DIRECT (Cont 1d). 402 '* 1 *II *s ENE ol vent 9£1 4.2 alles S ol venr llE2

5. 0 al SW of vent 12E I 4.4 *11..s WSW ol vent 2.:&

1.4 alle1 NNE of vent 1f2

5. I *I I es NE ot vell Jfl 8.6..... NE of vent IOF2
5. 8 *ll*s SSW of vent 12fl 9.4 *Iles WSW of vent Uf2
6. 5 *llos W of vont un 9.) *II-:- W ot vont l41J
6. 6 *Iles' Wlfl/ or wuni BO 5.4 *lies NW of vent 16f2 8.1 *lies NNW uf vont 16GI I 14.8 *llos NHW of vent 16' I
18. 5 *I los N of vent IOGI I 11.6 *I los SSW of vent I Control Station COUECT ION METHOD AIMLYSH Collected querterly

"---doM qu.rterly 'd Ill IQ " I.II 0 t1j '° ~ H 0 rt 8 H 0 ~ t>J ~ H

o~

0111

z: D'
i:......

t>J " z t-:)0 ~ I

J:......

0 z H t-:) 0 :;o H z a 'd

o 8

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

~ *.. ~-- *-,...,; ~*****,;,....,.,.....,,_, ~. - ....,..... *-..... : *.~'... *.. ::~':_...'.: ::,:.,.'~ * :.:. i...'~~-'.~<' -~r) *..;...,!.,,*..'.~ ;;,,.,.. : * ~.~...:.,,;.:,.*,;*~,:,; ;~~ **..:J:. l~**.. *L **. : *.

  • IV.

PAT._Y MATER (111) s u A f A c E Cb) G A 0 II H 0 le) O A I H K I H G STATION CODE 11AI 12CI I l6F I JE I 251 ~I I 2f) Craw) I Co.trot St*tlon LOCATION Approwliaately 6!i0 tt SN of vent

2. 5 *I 1115'1 ot vent 6.9 *I NNil of vent C&D canal 1 *I W of Mad Hone Creek~ 4. ~ al SE of vent 00....
4. I 1111 NE,,, 11onl 541** Water Co.;

8 al NNE of vent COLLECTION METHOD Two gal Ion 5-pl* to be ml lected aonthly providing winter lcl119 condition& *llow auipl* mllectlon Two gallon gr*b u.pl* la collected aonthly. 50 *I *I lquot la tuen ca.11 r

  • nd c.. poalted to
  • 19811t*lr aoapl* of tw~ ~llqna MMlYSD

~ laotoplc enelyala oa ..........., camf091t* tt-J... ly*I* ere ~ .. t*lr. 0.... laotoplc... 1,1a a.a querterir Cllmfl09lt* tt-) OA... rt... ly cimpoalte 'd Ill IQ * °' 0 tlJ '° ~ ~**.:. *' I.*

    • I E

H 0 8 H 0 ~ ~ H ~ o-} 0111 z D'

i::....

MID ~ ~o I ~.... z H o-} 0,, H z a 'd 8 ~- I,,:

)..:: *** =: ***** *_~;..~:*~***.. ~~A PATHllAY AQUATIC B f H J H 0 s ltaSTIOH Ca) M I l K Cb) f s H I Control Station STATION ~ 7E I 12C I I

  • ~a 2f4 l4f I
sGi I llAI 12Cl I LOCATION I *I M of Had Hor~* Croak;
4. !J *I SE of vent
2. !J *I MSM of vent Outfal8.,.., 650 1 SW ot vent

'*2 ~I NW of vent 6.J *I HNE ot v*nt 1.0 *I E of vent 'i. ~ ai Ill~ ot vont lo.6 *ll*11> NE of v*nt Outfall area; 650 1 SW of 11ent

2. ~ *I NSlll of v*nt COLLECT ION MEntoo A b*nthos HllPI* cooahtlng ol benthlc org.nlSIU and associated Hdl*nt ia t.aien
  • -i*nnuallV four gel Ion grab sa.ple of treslb *Ilk Is col lect9d h*om ead'I far* ual-tblyo ho ~~ s.. plea of tllh ere 5ealed In plaatlc bag or jar and froun

... aannuallW' or !jfaan In s.. son AIMl.VSES Ga.. laotoplc... 1yala

  • -****¥911W'i

"-- i110toplc -lr*I* 1-UI I'-- lllOtoplc analyala of edlbl* portlonoa mllectlOA ~ H a § H 0 ~ . r.

VI. INGESTION (C) C R A 0 11AI 12CI., (d) fRUITS !GI I m VEGETA-2£ I TIO. 2f I I Coatrol Statloa LOCATION Outfall are.t; 650 1 SW oi vut Med., &.nk opposite Al"tlf lclal Island 2.' *I 5'15 ot VMt 10.2 *lies Not v*nt 40 4 *I NNE of vent COt.LECTIOH Mfll()() Two kuys *-Pl* of crab or* s*oled in

  • plastlc bog or Jor ond froien
      • lannu.l ly or lilflen In SHSOft Sa.pl** or* ool l*cted during the not"-1 harvut aeason. a.al.al Rn plaa~lc 0 ond frozen If perlahabl*.

Sutflc!ent Nllfle la col-lectud to ylald '°6 gr.- 0~ *c1 -ag11t r r AIN.VSH 6-- l10tottlc.. aliala of.. l~I* port IOA

  • ooilec:t Io.

Radlolodl..e det.,..lnatlon of ..... IMfy vegetables on collect I* 0.- laotOfJIC*ualyala

  • col lec:tlCMI Ill IQ
  • m 0

rsJ '° ,I

**~.

E H 0 t"' 8 H (} ~ twJ ~ H ~8 0 Ill z D' ~~ ~? I 3:.... 0 z H 8 0 ~ H z a 'tJ ~ 8 ~-

,J PATHlllAY INGEST BON (e) G A N E Si AT ION COOf xxx xxx, xxx XXX

  • locatlon glvun ilt t In...

of col 1 ect Ion LOCATION Station vicinity *a~t aid* of *tuary "9at aide of.stuary. >-S *I frca vent aitlthln 10.. of Stat Ion ... *Thia *-.Pl* Ii 5ubject to avallablllty of slaughtered cow I Co.trol Station COLLECTION NEDm Muskrats *r* skinned and fro1M... 1.nnaual Ir. Beet portion of COii la*** H11Pled and troien... tauuellr r r AIMLYSH S.- laotQlllC Mal~ala m...... partlOA oalr oa collectloa 'O.. eQ * '° 0 I'll '° ~ H 0 t1 8 H n ~ ['IJ ~ H :u ti 01>> za ~~ ~ ~D I 3:.... 0 z H ti 0 :u H z a tU 8 i-1:.. . ~.

w iCAU oi iU CU

  • ~,_.. -_.

Fi9ure D -l ':*\\.. t'... ONSITE SAMPLING LOCATIONS ARTIFICIAL ISLAND v i

.\\.'. ~.. ', Figure D -2 OFFSITE SAMPLING LOCATIONS

  • ARTIFICIAL ISLAND J

0 Ps~G The Energy People 1985 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT RERR-19 SALEM GENERATING STATION SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 MARCH 1986}}

Retrieved from "https://kanterella.com/w/index.php?title=ML18092B039&oldid=5008681"