ML20153F336

Rev 9 to Offsite Dose Calculation Manual

ML20153F336
Person / Time
Site:	Hope Creek
Issue date:	06/08/1988
From:	Public Service Enterprise Group
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ML20153F327	List: ML20153F325 ML20153F333 ML20153F336
References
PROC-880608, NUDOCS 8809070230
Download: ML20153F336 (93)

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{{#Wiki_filter:_ O OFFSITE DOSE CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION Revision 9 May 1988 Approvals //ftn_Date: / ! M Mtg.e M "# [ 8 SORC Chairman: M i / // 8809070230seh {DR ADOCK og,o g4

Hopo Creek OUCM S/17/88 LIST OF' EFFECTIVE PAGES l Revision 0 - April, 1985 Revision 1 - December, 1985 Revision 2 - January, 1986 Revision 3 - August, 1986 Revision 5 - November, 1986 Revision 6 - February, 1987 (Entire Manual) Revision 7 - March, 1987 Revision 8 - June, 1987 Revision 9 - May, 1988 Pace No. Rev. No. Pace No. Rev. No. Title 7 3 9 2 7 5 9 6 7 6 9 8 7 11 9 9 7 39 9 10 7 A-4 9 O 11 7 A-5 9 12 7 B-2 9 13 7 B-3 9 31 7 B-5 9 32 7 E-1 to E-10 9 39 7 52 7 53 7 54 7 55 7 A-3 7 A-4 7 A-5 7 B-3 7 B-4 7 B-5 7 5 8 13 8 38-59 8 All Appendices (A-E) 8 Rev. 9

HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL b \\' TABLE OF CONTENTS l l INTRODUCTION 1 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls. 2 1.2 Liquid Effluent Monitor 3 Setpoint Determination. l 4 l 1.2.1 Liquid Effluent Monitors 1.2.2 Conservative Def ault Values. 5 1.3 Liquid Effluent concentration Limits -10 CFR 20 7 1.4 Liquid Effluent Dose Calculations - 10 CFR 50 8 1.4.1 Member of the Public Dose - l Liquid Effluents 8 l (] 1.4.2 Simplified Liquid Effluent l Dose Calculation 10 1.5 Liquid Ef fluent Dose Projection 12 l 2.0 GASEOUS EFFLUENTS l 2.1 Radiation Monitoring Instrumentation and Controls. 13 2.2 Gaseous Effluent Monitor Setpoint Determination. 15 2.2.1 Plant Vent and FRVS Monitors 15 j 2.2.2 Conservative Default Values. 18 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20. 19 2.3.1 Site Boundary Dose Rate - Noble Gases. 19 2.3.2 Site Boundary Dose Rate - Radioiodine and Particulates 21 1 1 l l l

4 2.4 Noblo Gas Effluont Doce Calculations - 10 CFR 50 24 f/) 2.4.1 UNRESTRICTED AREA Dose - s. Noble Gses 24 L 2.4.2 Simplified Dose Calculation for Noble Gases. 25 2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50 27 2.5.1 UNRESTRICTED AREA Dose - Radioiodine and Particulates 27 2.5.2 Simplified Dose Calculation f or Radioiodines and Particulates. 29 2.6 Gaseous Ef fluent Dose Projection. 31 c 3.0 SPECIAL DOSE ANALYSIS l 3.1 Doses Due to Activities Inside l the SITE BOUNDARY 33 3.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 34 3.2.1 Effluent Dose Calculations 35 7 3.2.2 Direct Exposure Determination. 35 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 36 4.1 Sampling Program. 36 l 4.2 Interlaboratory Comparison Program. 37 TABLES l l-1 Parameters for Liquid Alarm Setpoint Determination. 39 1-2 Site Related Ingestion Dose Commitment Factors, Aio 40 1-3 Bioaccumulation Factors (BFi) 42 2-1 Dose Factors for Noble Gases. 45 2-2 Parameters for Gaseous Alarm Septoint Determination. 46 l 2-3 Controlling Locations, Pathways l and Atmospheric Dispersion for Dose Calculations 47 2-4 Pathway Dose Parameters - Atmospheric Releases. 48 i O

A-1 Calculation of Effoctive MPC A-4 B-1 Adult Dose Contributions Fish and i Drinking Water Pathways B-4 / C-1 Effective Dose Factors C-5 D-1 Infant Dose Contribution Fraction of Dose D-4 l D-2 Fraction of Dose Contributions by Pathway D-4 APPENDICIES Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents A-1 1 Appendix B - Technical Basis for Ef fective Dose l Factors - Liquid Radioactive Effluents B-1 ( Appendix C - Technical Basis for Ef fective Dose r Factors - Gaseous Radioactive Effluents C-1 Appendix D - Technical Basis for Ef fective Dose l Parameters - Gaseous Radioactive Effluents. D-1 j Appendix E - Radiological Environmental Monitoring [ Program - Sample Type, Location and Analysis. E-1 l l lC) i i i I l l i i i i i

t Hope Creek ODCM 7/29/d7 \\ l HOPE C.4EEK GENERATING STATION j OFFSITE DOSE CALCULATION MANUAL l INTRODUCTION The Hope Creek Of f site Dose Calculation Manual (ODCM) describes the methodology and parameters used in:

1) the calculation of I

radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints; and 2) the calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and yearly doses. The methodology stated in i this manual is acceptable for use in demonstrating compliance l with 10 CFR 20.106, 10 CFR 50, Appendix I and 40 CFR 190. More conservative calculation methods and/or conditions (e.g., I location and/or exposure pathways) expected to yield higher computed doses than appropriate for the maximally exposed person l may be assumed in the dose evaluations. l The ODCM will be maintained at the station for use as a reference l guide and training document of accepted methodologies and l calculations. Changes will be made to the ODCM calculation t methodologies and parameters as is deemed necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are AtARA. \\ l NOTE: As used throughout this document,- excluding acronyme, l words appearing all capitalized denote the application of j definitions as used in the Hope Creek Technical ( Specifications. 1 Rev. 8

Hope Creek ODCM 7/29/87 t 1.0 Liquid Effluents I 1.1 Radiation Monitoring Instrur.entation and Controls The liquid effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance l with the Hope Creek Radiological Effluent Technical l Specifications are summarized as follows: t

1) Alarm (and Automatic Termination) - Liquid Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861)

I radioactive material releases from the liquid waste management system as required by Technical t Specification 3.3.7.9. ( O

2) Alarm (Only) - The Cooling-Tower Blowdown Effluent Monitor (RE8817) provides an Alarm function only for releases into the enviroment as required by Technical Specification 3.3.7.9.

Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figure 1-1. 1 l 1 1 l i 2 Rev. 8 i

Hopo Cecek CDCM 5/17/88 (O ,/ 1.2 Liquid Ef fluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.3.8, alarm setpoints shall be established for the i liquid effluent monitoring insttumentation 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, j Appendix B, Table II, Column 2, for radionuclides and 2.0E-04 uCi/ml for dissolved or entrained noble gases). The f ollowing equation

• must be satisfied to meet the liquid effluent restrictions:

i C (F + f) (1.1) c1 f where: i C = the effluent concentration limit of Technical l l Specification (3.11.1.1) implementing the j ] 10 CFR 20 MPC for the site, in uCi/ml. l I c = the setpoint, in uCi/ml, of the radioactivity 1 monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a 4 value which, if exeseded, would result in concentrations exceeding the limits of 10 CFR 20 l l in the UNRESTRICTED AREA. i 1 i

• Adopted from NUREG-0133 3

Rev. 9 i

Hope Creek ODCM 7/29/d7 '() f = the flow rate at the radiaton monitor location, l in volume per unit time, but in the same unito as I F, below F = the dilution water flow rate as measured prior to the release point, in volume per unit time. I l l [ Note that if no dilution is provided, c 1 C. Also, note that l 1 F.] when (F) is large compared to (f), then (F + f) = e i i 1.2.1 L_i, quid Effluent Monitors [ t i The setpoints for the liquid effluent monitors { l at the Hope Creek Generating Station are determined by the following equationt l I l MPCe

• CTBD l

+ bkg (1.2) SP 1 RR l l c i with: 2 t l f I: [", Ci I (1.3) MPCe = e C (Ci / MPCi) l l i ) where d i SP = alarm setpoint corresponding to the maximum allowable release rate (uci/ml) 3 MPCe = an effective MPC value for the mixture 3 3 f ] of radionuclides in the effluent stream j (uCi/ml) !O i i j 4 Rev. 8 I,

Hope Crook ODCM 5/17/06 l Ci = the concentt'ation of radionuclide i in the liquid effluent (uCi/ml)*

• NOTE:

The concentration mix must l, include the most recent composite of alpha emmitters, Sr-89, Sr-90, Fe-55, and H-3 as per Technical Specification 3.11.1.1. l i MPCi = the MPC value corresponding to l radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml) CTBD = the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min) RR = the liquid effluent release rate r ] (gal / min) at the monitor location t (i.e., at the liquid radwaste monitor l 2 or at the CTBD monitor). bkg = the background of the monitor (cpm) l The radioactivity monitor setpoint equation (1.2) temains valid during outages when the f Cooling-Tower Blowdown discharge is potentially at its lowest value. Reduction of I the waste stream flow (RR) may be necessary [ during these periods to meet the discharge criteria. Procedural restrictions prevent simultaneous liquid releases. ) 4 e 5 Rev. 9

f l Hope Crook ODCM b/17/dd () 1.2.2 Conservative Default Values Conservative alarm setpoints may be determined through the use of default parameters. Table 1-1 summarizes all current default values in use for Hope Creek. l P They are based upon the followingt l a) substitution of the effective MPC value with a default value of 4.19E-05 uCi/ml for radwaste releases (Refer to Appendix A for justification); b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal / min; and, ) c) substitutions of the effluent release rate l l with the highest allowed rate, in gal / min. i j With pre-established alarm setpoints, it is a j possible to control the radwaste release rate j (RR) to ensure the inequality of equation ] (1.2) is maintained under changing values for ) MPCe and for differing Cooling-Tower Blowdown I discharge. l 1 1 I I i I i 4 ] I 1 i ) 6 Rev. 9 1 l 1

i Hops Creek ODCM 7/29/87 1 1.3 Liquid Effluent doncentration Limits - 10 CFR 20 Technical Specification 3.11.1.1 limits the l I concentration of radioactive material in liquid j effluonts (after dilution in the Cooling-Tower i Blowdown Discharge System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radicnuclides other than. noble gases. Noblo gases are limited to a diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these l concentration limits are not exceeded. However, in j the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of Technical O Specification 3.11.1.1 mal

• be performed using the U

following equations f L [ Ci [ RR 1 (1.4) I MPCi / (CTBD + RR i wheres Ci = actual concentration of radionuclide i as j meareured in tne undiluted liquid effluent (uC1/ml) MPCi = the MPC value correspondirig to radionuclide i l from 10 CFR 20, Appendix B, Table II, Column 2 l (uCi/ml) = 2E-04 uCi/ml for dissolved or entrained noble l gases RR = the actual liquid offluent release rate l (gal / min) CTBD = the actual Cooling-Tower Blowdown discharge at the time of release (gal / min) 7 Rev. 8

Hopo Creek ODCM 7/29/87 ) 1.4 Liquid Effluent Dose Calculation - 10 CFR 50 i 1.4.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents

l t

i Technical Specification 3.11.1.2 limits the l dose or dose commitment to MEMBERS OF THE l PUBLIC from radioactive materials in liquid 4 1 effluents from Hope Creek Generating Station i to: I l - during any calendar quarters j i i 1.5 mrem to total body i 5.0 mrom to any organ L { ] - ouring any calendar year: [ I i 3.0 mrom to total body I i l 1 10.0 mrem to any organ 1 6 i Per the surveillance requirements of Technical I Specification 4.11.1.2, the following calculation methods may be used for l determining the dose or dose commitment due to i the liquid radioactive effluents from Hope l i Creek. 1 i 1 i 8.35E-04 VOL j Do = ----------------

• [,(Ci*Aio)

(1.3) j l CTBD l i 1 I where: dose or dose commitment to organ Do = i t o, including total body (r j I ($$) 8 Rev. 8 l j i 1

Hope Creek ODCM 7/29/87 1 1 site-related ingestion dose ) Aio = commitment factor to the total 1 body or any organ o for radionuclide 1 (mrem /hr per uCi/ml) average concentration of Ci = radionuclide i, in undiluted liquid effluent representative of the volume VOL (uCi/ml) volume of liquid effluent VOL = a released (gal) average Cooling-Tower Blowdown { CTBD = discharge rate during release period (gal / min) l conversion factor (1.67E-2 8.35E-04 = l hr/ min) and a near field dilution factor of 0.05 (refer to Appendix B, Page B-4 for definition). The site-related ingestion dose / dose j commitment factors (Aio) are presented in Table 1-2 and have been derived in accordance l i with a NUREG-0133 by the equations 1 i ) 1.14E+05 [(UI

• BIi) + (UF
• Bri)) DFi (1.6) l Aio

= where: composite dose parameter for the total body Aio = or critical organ o of an adult for 4 radionuclide i, for the fish and invertebrate ingestion pathways (mrem /hr l 2 per uCi/ml) t conversion factor (pCi/uCi

• ml/kg per l

1.14E5 = 1 hr/yr) adult invertebrate consumption (5 kg/yr) UI = i l i l 9 Rev. 8

Hope Creek ODCM 7/29/87 i() bioaccumulation factor for radionuclide i BIi = in invertebrates from Table 1-3 (pci/kg per pCi/1) adult fish consumption (21 kg/yr) UF = bioaccumulation factor for nuclide i in BFi = fish from Table 1-4 (pCi/kg per pCi/1) dose conversion factor for nuclide i for I Dri = adults in pre-selected organ, o, from Table E-ll of Regulator Guide 1.109 (mrom/pCi) The radionuclides included in the periodic 1 dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those 4 as identified by gamma spectral analysis of the liquid waste samples collected and I analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11.1.1.1-1. i i Radionuclides requiring radiochemical analysis ) (e.g., Sr-89 and Sr-90) will be added to the i j dose analysis at a frequency consistent with ] the required minimum analysis frequency of j j Technical Specification Table 4.11.1.1.1-1. I t t 1.4.2 Simplified Liquid Ef fluent Dose Calculation i I In lieu of the individual tr'ionuclide dose j assessment as presented in See: ion 1.4.1, the ( { following simplified dose calculation equation l l may be used for demonstrating compliance with j the dose limits of Technical Specification [ l 3.11.1.2. (Refer to Appendix B for the [ derivation and justification for this simplified method.) l 10 Rev. 8 j

Hopo Crcck ODCM 5/17/80 th ( l (/ Total Body 1.94E+02 VOL Ci (1.7) Dtb = CTBD Maximum Organ VOL 4.28E+02 C1 (1.8) Dmax = CTBD where: conserv3tively evaluated total body Dtb = dose (mrem) conservatively evaluated maximum Dmax = organ dose (mrom) average concentration of Ci = radionuclide i, in undiluted liquid 4 effluent representative of the volume VOL (uCi/ml) I VOL volume of liquid effluent released = (gal) average Cooling-Tower Blowdown CTBD = l discharge rate during release period (gal / min) conversion factor (1.67E-2 hr/ min) 1.94E+02 = the conversative total body dose conversion factor (2n-65, total body -- 2.32E5 mrem /hr per uti/ml), and the near field dilution factor nf 0.05 (See Appendix B). conversion factor (1.67E-2 hr/ min) 4.28E+02 = the convervative maximum organ dose conversion factor (2n-65, Liver -- 5.13E5 mrem /hr per uCi/ml), and the (s near field dilution factor of 0.05 ,) (See Appendix B). 11 Rev. 9

Hopo Crook ODCM 7/29/87 1.5 Liquid Effluent Dose Projections () Technical Specification 3.11.1.3 requires that the I liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid I waste prior to release when the 31-day projected doses exceed: / 0.06 mrom to the total body, or 3 0.2 mrom to any organ. I Tne applicable liquid waste processing system for maintaining radioactive material releases ALARA are l the drain filters and dominorilizers as delineated in j Figure 1-1. Dose projections are made at least once per 31-days ) by the following aquations: i () i 31d (1.9) (Dtb / d) j Dtbp = 31d (1.10) i Dmaxp (Dmax / d) = t I where: l the total body dose projection for current Dtbp = j 31-day period (mrom) I the total body dose to date for current I Dtb = 1 calendar quarter as determined by equation l (1.5) or (1.7) (mrem) ( = the maximum organ dose projection for Duaxp = j current 31-day period (arem) j the maximum organ dose to dace for current l Dmax = l calendar quarter as determined by equation l (1.5) or (1.8) (prem) the number of days in current calendar j i d = quarter at the end of the release { the numo.. of days of concern i 31d = i 12 Rev. 8 1 l

Hope Creek CDOt 7/29/d7 2.0 Gaseous Effluents i 2.1 Radiation Monitorino Instrumentation and Controls The gaseous effluent monitoring instrumentation and i coritrols at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with 4 the Radiological Effluent Technical Specifications are 4 summarized as follows: 1) Filtration, Recirculation, and Ventilation System - The FRVS is maintained !1 a standby condition. Upon reactor building icolation, the FRVE recirculation system recirculates the reactor 2 I building air through HEPA and charcoal filters. Releases are made to the atmosphere v'a a reactor j i building vent or the South Plant Vent depending on mode of operation. Noble gas monitoring is i l provided by RE-4811A. i { 2) South Plant Vent - The SPV receives discharge from the radwaste evaporator, reactor building purge, ( ) auxiliary building radwaste area, condensate l f demineralizer, pipe chase, feedwater heater, and untreated ventilation sources. Effluents are [ I monitored (for noble gas) by the RE-4875B monitor. j ) 3) North Plant Vent - The NPV receives discharges from } the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources. l Effluents are monitored (for noble gases) by the f RE-4573B monitor. l l L 13 Rev. 8 l

i Hope Creek ODCM 7/29.Jd7 l i i A gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figures 2-1 and 2-2. l r i j f c ) l l ) \\ i I. 1 i L 1 ) I l l i l J i i l 1 ] 14 Rev. 8 I

i......

dopo Crook ODCM 7/D/87 O 2,2 Gaseous Ef fluent Monitor Setpoint Determination 2.2.1 Plant Vent and FRVS Vent Monitors Per the requirements of Technical Specification l 3.3.3.10, alarm setpoints shall be established for the gaseous effluent monitoring ) instrumentation to ensure that the release rate j of noble gases does not exceed the limits of i specification 3.11.2.1, which corresponds to a j dose rate at the SITE BOUNDARY of 500 mrom/ year l to the total body or 3000 mrom/ year to the

l skin.

Based on a grab sample analysis of the ) applicable release (i.e., of FRVS, pipe chase, gaseous radwaste treatment system air, etc.), i the radiation monitoring alarm setpoints guy be I established by the following calculauon method. The measured radionuclide concentrations and release r co are used to calculate the fraction of the allowable release i rate, as limited by Specification 3.11.2.1, by l the equationt l FRAC = [4.72E,02

• X/O
• VF *[(Ci
• Ki)) / 500 (2.1) l FRAC a [4. 72E+02
• X 'O
• VF *E(Ci * (Li + 1.1 Mi))) / 3000 (2.2) f 1'

where: fraction of the allowable release FRAC = rate based on the identified j j radionuclide concentrations and l the release flow rate annual average meterological X/O = dispersion to the controlling site boundary location (sec/m3) l 15 Rev. 8 i

Hopo Crook 00CM 7/29/87 0 1 ventilation system flow rate for '(,) VF = the applicable release point and monitor (ft3/ min) concentration of noble gas Ci = radionuclide i as determined by radioanalysis of grab sample (uCi/cm3) total body dose conversion factor Ki = for noble gas radionuclide 1 (mrem /yr per uCi/m3, from Table 2-1) beta skin dose conversion factor Li = for noble gas radionuclide i (mrem /yr per uCi/m3, f rom Table 2-1) gamma air dose conversion factor Mi = (~ for noble gas radionuclide i k-(mrad /yr per uCi/m3, from l Table 2-1) mrem skin dose per mrad gamma air 1.1 = dose (mrem / mrad) conversion factor (cm3/ft3

• 4.72E+02

= min /sec) total body dose rate limit 500 = (; rem /yr) skin dose rate limit (mrum/yr) 3000 = Based on the more limiting FRAC (i.e., higher value) as determined abeve, the alarm setpoints for the applicable monitors may be calculated by tae equation: SP = [AF

• [ Ci

/ FRAC) + bkg (2.3) O 16 Rev. 8 l

Hope Creos ODCM 7/29/,7 where: alarm setpoint corresponding to the SP = maximum allowable release rate (uci/cc) highest fraction of the allowable FRAC = release rate as determined in equation i (2.2) background of the monitor (cpm) j bkg a administrative allocation factor for [ AF = l the specific monitor (0.2 NPV, 0.2 SPV, 0.1 FRVS) The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not I exceed the regulatory limits on release rate I j from the site (i.e., the release rate limits of i Technical Specification 3.11.2.1).

Normally, j

) the combined AF value for Salem Units 1 and 2 is 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek. Any increase in AF I i above 0.5 for the Hope Creek Generating Station ( j will be coordinated with the Salem Generating l Station to ensure that the combined allocation factors for all units do not exceed 1.0. l I f i 4 l i 4 l 1 ) l lO 17 Rev. 8 i l l l [

Hope Creek 00CM 7/29/67 /~S (s,) 2.2.2 conservative Default Values l A conservative alarm setpoint can be estabitshed, in lieu of the individual f radionuclide evaluation based on the grab sample P analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide ] distribution and variations in release flow I rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2. I These values are based upon l 1 the maximum ventilation (or purge) flow rater a radionucide distribation adopted from ANSI O N237-1976/ANS 18.1 "Source Term l t Specifications", Table 5 and; I an administrative allocation factor of 0.5 to ) r conservatively ensure that any releases from Hope Creek do not exceed the maximum allowable release rate. 1 For the noble gas radionuclide distribution f rom j ANSI N237-1976/ANS 18.1 (Note Table C-1), the j alarm setpoint based on the total body dose rate j is more restrictive than the corresponding setpoint based on the skin dose rate. The j resulting conservative, default setpoints are + presented in Table 2-2. I Adopted from ANSI N237-1976/ANS-18.1, Source Term f () Specifications, Table 6 18 Rev. 8 .m..

Hopo Crook ODCM 7/J9/87 ) 2.3 Gaseous Effluent _ Instantaneous Dose Rate Calculations - 10 CFR 20 2.3.1 Site Boundary Dose Rate - Noble Gases Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to i 500 mrem /yr, total body and i 3000 mrem /yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release may be performed using the following equations: Os# Otb = X/Q * [ (Ki

• Qi)

(2.4) and Ds = X/O * [ ((Li + 1.lHi)

• Qi)

(2.5) where: total body dose rate (mrom/yr) Dtb = skin dose rate (mrem /yr) i Ds = atmospheric dispersion to the X/0 = controlling SITE BOUNDARY location (sec/m3) average release rate of radionuclide i Qi = over the release period under evaluation (uci/sec) i 19 Rev. 8 i

l l Hopo Crook ODCM 7/29/d7 l l () total body dose conversion factor for Ki = noble gas radionuclide 1 (mrom/yr per uCi/m3, from Table 2-1) beta skin dose conversion factor for Li = noble gas radionuclidu i (mrem /yr per uC1/m3, from Table 2-1) gamma air dose conversion factor for Mi = noble gas radionuclide 1 (mrad /yr per uCi/m3, from Table 2-1) mrom skin dose per urad gamma air dose 1.1 = (mrom/ mrad) As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.la, following any releases exceeding the above prescribed alarm O setpoints. Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. The 15-minute averaging is needed to allow for reasonable monitor response to potentially changiag radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelate6 to radioactive material releases. As identified, any electronic spiking monitor responses may be excluded f rom the analysis. O 20 Rev. 8

Hopo Crook ODCM 7/29/87 l ? () NOTE: For administrative purposes, more I conservative alarm setpoints than those l as prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the dose limits of Technical Specification 3.11.2.la. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of Specification 3.ll.2.la. Actual meteorological conditions concurrent with O the release period or the default, annual average dispersion parameters as presented in Table 2-4 may be used for evaluating the gaseous effluent dose rate. 2.3.2 Site Boundary Dose Rate - Radioiodine and Particulates Technical Specification 3.11.2.lb limits the dose rate to i 1500 mrem /yr to any organ for I-131, tritium and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at frequency no greater than that corresponding to O 21 Rev. 8

1 Hopo Cecok uDCM 7/29/67 a l the sampling and analysis time period (e.g, nominally once per 7 days). The following equation may be used for the dose rate ~ evaluation: Do = X/O

• I",(Ri
• Qi)

(2.6) where average organ dose rate over the l a Do = t sampling time period (mrem /yr) [ atmospheric dispersion to the X/0 = controlling SITE BOUNDARY location for the inhalation pathway (sec/m3) l dose parameter for radionuclide i, f Ri = (mrem /yr per uCi/m3) for the child 7 inhalation pathway from Table 2-4 j + average release rate over the 01 = { appropriate sampling period and l analysis frequency for radionuclide i -- I-131, I-133, tritium or other j radionuclide in particulate form with l half-livs greater than 8 days j (uci/sec) s' I { By substituting 1500 mrom/yr for Do and solving l for Q, an allowable release rate for I-131 can l be determined. Based on the annual average meteorological dispersion (See Table 2-3) and the most limiting potential pathway, age group l r and organ (inhalation, child, thyroid -- Ri = j 1.62E+07 mrem /yr per uCi/m3), the allowable [ release rate for I-131 is 34.7 uCi/sec. Reducing this release rate by a factor of 2 to J O I ' .l i 22 Rev. 8

Hopo Crook ODCM _7/29/o7 i r i account for potential dose contributions from ) other radioactive particulate material and other J release points (e.g., Salem), the corresponding i release rate allocated to Hope Creek is 17.4 uCi/sec. For a 7-day period, which is the nom..nal sampling and analysis frequency for I-131, the cumulative release is 10.5 C1. l Therefore, as long as the I-131 releans in any l i 7-day period do not exceed 10.5 Ci, no l additional analyses are needed for verifying a compliance with the Technical Specification l 3.11.2.1.b limits on allowable release rate. } i 9 () i i I 4 I l 1 l I i 1 f l f i l ( 23 Rev. 8

Hopo Crook ODCM 7/29s'87 1 2.4 Noble Gas Ef,, fluent Dose Calculations - 10 CFR 50 l 2.4.1 kNRESTRICTED AREA Dose - Noble Gases t I Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases j to evaluate compliance with the quartwely dose limits of 15 mead, gamma-air and i 10 mead, I beta-air and the calendar year limits i 10 mead, f gamma-air and i 20 mead, beta-air. The limits l are applicable separately to each generating l station and are not combir.ed site limits. The i following equations may be used to calculate the 1 gamma-air and beta-air doses: 1 3.17E-08

• X/O
• C(Mi
• Qi)

(2.7) l Dg = .i i and j .a i Db = 3.17E-08

• X/O * [(Ni
• Qi)

(2.8) i 1 where: ) air dose Guo to gamma emmissions J Dg = for noble gas radionuclides (mrad) air dose due to beta emissions for Db = ( noble gas radionuclides (mrad) atmospheric dispersion to the X/0 = J controlling SITE BOUNDARY location j i (sec/m3) cumulative release of noble gas Qi = 1 radionuclide i over the period of interest (uCi) j O 24 Rev. 8

Hopo Cecek CDCM 7/29/37 /y a'ir dose factor due to gamma (_) Mi = emissions,from noble gas radionuclide 1 (mrad /yr per uCi/m3, from Table 2-1) air dose f actor due to beta Ni = emissions from noble gas radionuclide i (mrad /yr por uCi/m3, Table 2-1) 3.17E-08 = conversion factor (yr/sec) 2.4.2 Simplified Dose Calculation for Noble Gases In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the ,r ~ x, dose limits of Technical Specification k/ 3.11.2.2. (Refer to Appendix C for the derivation and justification of this simplified method.) 3.17E-08

• X/Q
• Meff *{ Qi (2.9)

Dg = 0.50 and 3.17E-08

• X/Q
• Neff * ( Qi (1.10)

Db = 0.50 25 Rev. 8

l Hope Crook 00CM 7/29/47 wheres i 8.1E2, effective gamma-air dose Moff = factor (mrad /yr per uC1/m3) 8.5E3, ef f ective beta-air: dose Neff = factor (mrad /yr per uCi/m3) cumulative release for all noble j Qi = gas radionuclides (uci) l conservatism factor to account for 0.50 = potential variability in the radionuclide distribution i Actual meteorological conditions concurrent with the release period or the default, annual l average dispersion parameters as presented in ) Table 2-3, may be used for the evaluation of the j gamma-air and beta-air doses. i s i. t l r l O 26 Rev. 8 I i __________.________j

Hopo Crook CDCM 7/29/d7 0 2.5 Radiciodine and Particulate Dose Calculations - 10'CFR 50 2.5.1 UNRESTRICTED AREA Dose - Radioiodine and l Particulates l In accordance with requirements of Technical l Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with l the quarterly dose limit of 1 7.5 mrom and i calendar year limit i 15 mrom to any organ. The i following equation may be used to evaluate the i maximum organ dose due to release of I-131, l tritium and particulates with half-lives greater [ than 8 days: Daop = 3.17E-08

• W
• SFp * [ (Ri
• Qi)

(2.11) J where t dose or dose commitment via Daop = 1 controlling pathway p and age group a i (as identified in Table 2-3) to organ l 1 o, including the total body (arem). l atmosphoric dispersion parameter to l W = ( j the controlling location (s) as j identified in Table 2-3. [ i X/O = atmospheric dispersion for I inhalation pathway and H-3 dose contribution via other I pathways (sec/m3). D/0 = atmospheric deposition for f J vegetation, milk and ground [ l plane exposure pathways (1/m2). l lO i 27 Rev. 8 4

~. I Hope Crvek ODCM 7/29/o7 dose factor for radionuclide i, Ri = (mrem /yr per uCi/m3) or (m2 - mrom/yr ( per uCi/sec) from Table 2-4 for each age group a and the applicable pathway f' p as identified in Table 2-3. Values for Ri were derived in accordance with the methode described in NUREG-0133. [ cumulative release over the period of l 01 = interest for radionuclide 1 -- I-131 l or radioactive material in particulate l 1 form with half-life greater than 8 j [ I days (uci). annual seasonal correction factor to f l Srp = { account for the fraction of the year that the applicable exposure pathway ( does not exist. j l O 1) For milk and vegetation exposure pathways: J = A six month fresh vegetation and j grazing season-(May through i l October). [ = 0.5 2) For inhalation and ground plane exposure pathways j = 1.0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk ( pathway and the child age group is controlling [ for the vegetation pathway. Only the l l controlling age group and pathway as identified in Table 2-3 need be evaluated for compliance j with Technical Specification 3.11.2.3. f 28 Rev. 8 l t

Hope Creek 00CM 7/23/s7 't ] 2.5.2 Simplitied Dose Calculation for Radioiodines and j Particulates i In lieu of the individual radionuclide (I-131 i and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (Refer to Appendix D for the derivation and justification of this 1 simplified method). (2.12) l Dmax = 3.17E-08

• W
• SFp
• RI-131 * { Qi l

j where i maximum organ dose (mrem) Dmax = t RI-131 = I-131 dose parameter for the thyroid for the identified controlling pathway I i r 1.67E12, infant thyroid dose parameter l = 4 i with the cow-milk pathway controlling ) (m2 - arem/yr per uCi/sec) J D/0 for radioiodine, 2.87E-10 1/m2 W = s j Qi cumulative release over the period of = I interest for radionuclide i -- I-131 l } J or radioactive material in particulate form with half-life greater than 8 l days (uCi) 1 l 29 Rev. 8

Hopo Crook ODCM 7/29/87 j l i , () The location of exposure pathways and the maximum organ dose calculation may be based on l the available pathways in the surrounding l l environment of Hope Creek as' identified by the i annual land-use census (Technical Specification l 3.12.2). Otherwise, the dose will be evaluated t based on the predetermined controlling pathways as identified in =ble 2-3. ) i !) s I k i l l i 4 t 4 l 1 i i i l i l t t I l t i r N l i I l l } 30 Rev. W l 1 l i i i

I I Hope Creek ODCM 7/29/87 2.6 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses in 31-days exceed: 0.2 mrad to air from gamma radiation, or 0.4 mrad to air from beta radiation, or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC The applicable gaseous processing systems for maintaining rs ~ioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in rigures 2-1 and 2-2. (~T Dose projection are performed at least once per 31-days 5/ by the following equations: ~

• 31d (2.17)

(Dg / d) Dgp =

• 31d (2.18) i (Db / d)

Dbp = (Dmax / d)

• 31d (2.19)

Dmaxp = where: gamma air dose projection for current 31-day 4 Dgp = period (mrad) i gamma air dose to date for current calendar Dg = l quarter as determined by equation (2.7) or (2.9) (mrad) beta air dose projection for current 31-day Dbp = period (mrad) beta air dose to date for current calendar Db = quarter as determined by equation (2.8) or () (2.10) (mrad) 31 Rev. 8

. ~.... . - ~ -. Hope Creek ODCM 7/29/87 4 l 4 maximum organ dose-projection for current ~ Dmaxp = 31-day-period (mrem) i maximum organ dose to date for current Dmax = calendar quarter as determined by equation j l (2.11) or (2.12) (mrem) number of days in current calendar quarter at i d a 4 the end of the release the number of days of concern ) 31d = ) i i d i i I 4 1, t I I l 1 1 4 l f E ( l ( l l i 1 I l 4 i I t i l' : 32 Rev. 8 i'

i Hope Creek ODCM 7/29/37 ( ) 3.0 Special Dose Analysis 3.1 Doses Due to Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.7, the Radioactive Effluent Release Report (RERR) submitted within 60-days after January 1st of each year shall include an assessment of radiation doses from radioactive liquid and ( ,,e effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. There is one location on Artificial Island that is i accessible to MEMBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities. This location is the Second Sun (visitor's center) i located near the contractors gate in the Salem O Generating Station. The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-3 and 2-hours per visit per year. The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes avail 6ble. 33 Rev. 8

7 u Hope Creek ODCM 7/29/37 1 Q(,f 3.2 Total Dose to MEMBERS OF THE PUBLIC - 40 CFR 190 The Radioactive, Effluent Release Report (RERR) i submitted within 60-days after January 1st 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 Generating Station and the Hope Creek 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

• O Generating Station will be estimated based on the methods as presented in the Salem Offsite Dose Calculation Manual (SGS ODCM).

As appropriate for demonstrating / evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure. 34 Rev. 8

Hopo Creek ODCM 7/29/87 3.2.1 Effluent Dose Calculations () For purposes of. implementing the surveillance requirements of Technical' Specification 3/4.11.4 and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the Hope Creek Generating Station may be performed using the calculation methods contained within the ODCM; the conservative controlling pathways and locations of Table 2-4 or the actual pathways and locations as. identified by tr.a land use census (Technical Specification 3/4.12.2) may be used. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used. i 3.2.2 Direct Exposure Dose Determination Any pocentially significant direct exposure i O contribution to off-site individual doses may be evaluated based on the results of the j environmental measurements (e.g., TLD, ion 'hamber measurements) and/or by the use of a l radiation transport and shielding calculation method. Only during a typical conditions will l l there exist any potential for significant on-site sources at Hope Creek that would yield l potentially significant off-site doses (i.e., in l excess of 1 mrem per year to a MEMBER OF THE l PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190. However, should a situation exist whereby the I I direct exposure contribution is potentially [ i significant, on-site measurements, off-site j measurements and/or calculational techniques [ will be used for determination of dose for [) j assessing 40 CFR 190 compliance. I t 4 35 Rev. 8 _.,y, ._,. _ _ _ _ ~. - _ _ _ _. _ _ _ _. -., _ _.. -.., __

Hope Creek ODCM 7/29/d7 (G_,/ 4.0 Radiological Environmental Monitorina Program 4.1 Samplina Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of Appeadix A Technical ~ Specification 3.12 The ob.dectives of the program are: To determine whether'ary significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; To determine if the operation of the Hope Creek i Generating Station has resulted in any increase in the inventory of long lived radionuclides in the environments To detect any changes in the ambient gamma radiation levels; and To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment. The sampling requirements (type of samples, collection j frequancy and analysis) and sample locations are presented in Appendix E. i ( i 1 ($) 36 Rev. 8 l

Hope Creek ODCM 7/29/87 O 4.2 Interlaboratory Comparison Procram Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison. Participation in an approved Interlanoratory Comparison i Program provides a check on the precisness of measuremets of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison f Program results will be provided in the Annual Radiological Environmental Operating Report pursant to Technical Specification 6.9.1.7. L i e 4 i i J i l l i i ($) i 37 Rev. 8 i [

Hope Creek ODCM 7/29/87 I FIGURE l-1 ( LIQUID RADWASTE TREATMENT SYSTEM Cooling JL /k Tower Basin Collector y-> Tanks (2) Equipment Equipment Equipment p> Drain Drain e D'tain Samplo y y Surge JE Filter Ab Demine ralize r Tanks (2) Tank y Condensate Storage Tank Ak m 47 Ak Floor Floor Floor Floor Drain Drain Up Drain Drain Collector JL Filter Demineralizer Sample Tanks (2) Tanks (2) > Vapor to Chemical Decontamination South Vent Waste Solution Tank JL Evaporator > Bottoms to Solid Waste Detergent Detergent 9 Drain Drain Tanks (2) Filter RE 4861 .oggsd RE = Effluent Radiation Monitor RE 8817 1 To Delaware River p (offsite) 38 Rev. 8

Hopa Creek uDCM 5/17/06 kl TABLE l-1 PARAMETERS t'OR I.IQUID ALARM SETPOINT DETERMINATION Actual Default Pr:rr me ter Value Value Units Comments MPCo Calculated 4.19E-5 uCi/ml Calculated for each batch to be released MPC I-131 3.0E-08 N/A uCi/ml I-131 MPC conservatively used for HC CTBD and liquid radwaste monitor setpoints Ci Measured N/A uCi/mi Taken from gamma spectral analysis of liquid effluent MPCi As N/A sci /mi Taken frca 10 CFR 20, Determined Appendix B, Table II, Column 2 As 1.20E4 gpm Cooling tower blowdown Determined discharge RR As 176 gpm or Determined prior to Determined 1300 gpm (CST) release; release rate can be adjusted for Technical Specification compliance SP A) RE4861 Calculated 2.86E-03 uCi/ml* De.!ault alarm setpoints; more conservative values RE8817 Calculated 4.19E-05 uCi/ml ma)- be used as deemed appropriate and desirable for ensuring regulatoty compliance and for maintaining releases ALARA B) RE4861 Calculated 3.87E-04 uCi/ml These setpoints are for condensate storage tank RE8dl7 Calculated 4.19E-05 uCi/ml releases a These setpoints are more conservative for Detergent Drain Tank releases. For higher conservative default setpoints multiply setpoint by 7.04 for DT releases. 39 Rev. 9

Hope Creek ODCM 7/29/87 l TABIE l-2 SI'IE REIMED INGESTICH DOSE CCp0GTMENT FACICR, Ait

g}

(FISH AND INVERITBRATE CCMR3GTIGI) v (MRDVhr per uCi/ml) Page 1 of 2 NUCLIDE Bore Liver Total Body Thyroid Kidney _ Lung, GI-LLI 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 H-3 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+5 NA-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 5.27E+5 P-32 4.69E+6 2.91E+5 1.81E+5 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 CR-51 2.16E+4 i 2.10E+3 7.06E+3 1.35E+3 MN-54 5.67E+3 1.78E+2 3.15E+1 2.26E+2 MN-56 1.97E+4 2.03E+4 FE-55 5.11E+4 3.53E+4 8.23E+3 5.30E+4 6.32E+5 FE-59 8.06E+4 1.90E+5 7.27E+4 1.22E+4 6.03E+2 1.35E+3 Co-58 3.59E+4 1.42E+2 2.36E+2 CO-57 3.25E+4 1.73E+3 3.82E+3 CD-60 7.18E+2 NI463 4.96E+4 3.44E+3 1.67E+3 6.65E+2 NI-65 2.02E+2 2.62E+1 1.20E+1 5.40E+2 1.83E+4 2.14E+2 1.01E+2 CU-64 i2N-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 2N-69 3.43E+2 6.56E+2 4.56E+1 4.26E+2 9.85E+1 BR-82 4.07E+0 4.67E+0 1.04E-1 BR-83 7.25E-2 9.39E-2 7.37E-7 BR-84 3.86E-3 BR-85 RB-86 6.25E+2 2.91E+2 1.23E+2 1.79E+0 9.49E-1 2.47E-11 RB-88 RB-89 1.19E+0 8.34E-1 6.89E-14 SR-89 4.99E+3 1.43E+2 8.00E+2 SR-90 1.23E+5 3.01E+4 3.55E+3 i SR-91 9.18E+1 3.71E+0 4.37E+2 ~~ SR-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6.06E+0 1.62E-1 6.42E+4 Y-91m 5.72E+2 2.22E-3 1.68E-1 Y-91 8.88E+1 2.37E+0 4.89E+4 Y-92 5.32E-1 1.56E-2 9.32E+3 Y-93 1.69E+0 4.66E-2 5.35E+4 2R-95 1.59E+1 5.IlE+0 3.46E+0 8.02E+0 1.62E+4 ~~ 2R-97 8.81E-1 1.78E-1 E.12E-2 2.68E-1 5.51E+4 NB-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 NB-97 3.75E+0 9.49E-1 3.46E-1 1.llE+0 3.50E+3 1.28E+2 2.43E+1 M>-99 2.89E+2 2.96E+2 TC-99m 1.29E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 l 3.46E-1 9.81E-3 5.77E-14 TC-101 1.33E-2 1.92E-2 1.88E-1 40 Rev. 8l>

Hope Creek ODCM 7/29/67 TABLE l-2 SIM REIAED INGESTIQ4 DOSE CQetI'ITENT FACIOR, Alt -3 ) (FISH AND INVERITBRAM CDEWGTIQ4) (V (MRDVhr per uC1/al) Page 2 of 2 NUCLIDE Bone Liver Total Body _ Thyroid Kidney.

Lu_ng, GI-LLI 1.25E+4 4.07E+2 4.60E+1 RU-103 1.07E+2 1.15E+2 5.44E+3 3.51E+0 R0-105 8.89E+0 1.03E+5 3.06E+3 2.01E+2 RU-106 1.59E+3 RH-103m 41-106 5.91E+5 AG-110m 1.56E+3 1.45E+3 8.60E+2 2.85E+3 2.15E+2 7.86E+3 SB-124 2.77E+2 5.23E+0 1.10E+2 6.71E-1 SB-125 1.77E+2 1.98E+0 4.21E+1 1.80E-1 1.36E+2 1.95E+3 8.66E+2 E-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 1.84E+3 TE-127m 5.48E+2 1.96E+2 6.CE+1 1.40E+2 2.23E+3 7.03E+2 TE-127 8.90E+0 3.20E+0 1.93E+0 6.60E+0 3.63E+1 4.69E+3 E-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 TE-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+1 1.92E+0 6.80E+3 TE-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 2.26E-1 TE-131 1.59E+0 6.66E-1 5.03E-1 1.31E+0 6.99E+0 hTE-132 6.24E+3 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 1.01E+2 I-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 8.23E+1 I-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1.16E+2 I-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 6.87E+1 I-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 5.27E+3 1.75E+3 2.85E+2 CS-134 6.84E+3 1.63E+4 1.33E+4 1.57E+3 2.16E+2 3.21E+2 G-136 7.16E+2 2.83E+3 2.04E+3 4.07E+3 1.35E+3 2.32E+2 CS-137 8.77E+3 1.20E+4 7.85E+3 8.81E+0 8.70E-1 5.llE-5 CS-138 6.07E+0 1.20E+1 5.94E+0 5.23E-3 3.17E-3 1.39E+1 BA-139 7.85E+0 5.59E-3 2.30E-1 7.02E-1 1.18E+0 3.38E+3 BA-140 1.61E+3 2.06E+0 1.08E+2 2.68E-3 1.63E-3 1.80E-9 BA-141 3.81E+0 2.88E-3 1.29E-1 1.50E-3 1.00E-3 2.43E-18 BA-142 1.72E+0 1.77E-3 1.08E-1 IA-140 1.57E+0 7.94E-1 2.'10E-1 5.83E+4

= 2.68E+2 LA-142 8.06E-2 3.67E-2 9.13E-3 8.86E+3 1.08E+0 CE-141 3.43E+0 2.32E+0 2.63E-1 1.67E+4 1.96E-1 CE-143 6.04E-1 4.46E+2 4.94E-2 6.04E+4 4.43E+1 CE-144 1.79E+2 7.47E+1 9.59E+0 1.34E+0 2.54E+4 PR-143 5.79E+0 2.32E+0 2.87E-1 2.73E-9 4.44E-3 PR-144 1.90E-2 7.87E-3 9.64E-4 2.20E+4 2.68E+0 " ND-147 3.96E+0 4.58E+0 2.74E-1 2.51E+3 W-187 9.16E+0 7.66E+0 2.68E+0 1.08C-2 7.11E+2 l NP-239 3.53E-2 3.47E-3 1.91E-3 41 Rev. 8

Hope Creek ODCM 7/29/87 TABLE l-3 O' (pci/kg per pCi/ liter)* BIOACCUMULATION FACTORS ELEMENT SALTWATER FISH SALTWATER INVERTEBRATES H 9.0E-01 9.3E-01 C 1.8E+03 1.4E+03 NA 6.7E-02 1.9E-01 P 3.0E+03 3.0E+04 CR 4.0E+02 2.0E+03 MN 5.5E+02 4.0E+02 FE 3.0E+03 2.0E+04 CO 1.0E+02 1.0E+03 NI 1.0E+02 2.5E+02 i CU 6.7E+02 1.7E+03 2N 2.0E+03 5.0E+04 i BR 1.5E-02 3.lE+00 RB 8.3E+00 1.7E+01 Sn 2.0E+00 2.0E+01 Y 2.5E+01 1.0E+03 ZR 2.0E+02 8.0E+01 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.0E+01 5.0E+01 RU 3.0E+00 1.0E+03 O RH 1.0E+01 2.0E+03 AG 3.3E+03 3.3E+03 Sb 4.0E+01 5.4E+00 ~ TE 1.0E+01 1.0E+02 I 1.0E+01 5.0E+01 CS 4.0E+01 2.5E+02 BA 1.0E+01 1.0E+C2 J LA 2.5E+01 1.0E+03 CE 1.0E+01 6.0E+02 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 3.0E+01 3.0E+01 1 NP 1.0E+01 1.0E+01 Values in Table 2.2-2 are taken from Regulatory Guide 1.109 j except for phosphurus (fish) which is adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev. 1, October 1972. !)O 2 { s 42 Rev. 8

Hope Creek ODCM 7/29/87 FIGURE 2-1 GASEOUS RADWASTE TREATMENT SYSTEM I Main or Auxiliary Steam SJAE I l Offgas Recombiner f II I Preheater Recombiner Condenser l u t Condenser l Offgas Typical of 2 Recombiner Packages 4 I I _] 4 I Holdup Pipes 4 i 4 l -] l O t Cooler Reheater Guard Condenser Bed s L l U To North 4 HEPA Filter Absorber Plant Vent Train (Figure 4.1-2) l Ambient Charcoal System a e 1 l l 43 Rev. 8

Hope Creek ODCM 7/29/87 l FIGURE 2-2 /D VENTILATION EXHAUST TREATMENT SYSTEM V Gcseous Radwaste RE Treatment System 4573B (from Figure 4.1-3) North p: Plant Vent Untreated Ventilation 0: Air Sources Radwaste Decon. Evaporator Rocctor Building R H p. Purge Air (Typ. of 3) RE r Auxiliary Building 4875B Radwaste Area R H gr South Vontilation Air -Plant (Typ. of 3) Vent ndensate + Demineralizer Room Air Pipe Chase Air R E C H + Foodwater Heater Room Air Untreated Ventilation Air Sources t (Recirculation) RE 4811A A FRVS Reactor H C H 3: C H >: System Vent ,l Building Air (Typ. of 6) (Typ. of 2) Roughing Filter Legendt R = Charcoal Filter C = HEPA Filter H = O RE = Effluent Radiation Monitor This Foot-Treatment Monitor is not an effluent monitor i as designated by the RETS. 44 Rev. 8

Hope Creek ODCM 7/29/87 l. i TABLE 2-1 DOSE FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air l Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni (mrem /yr per (mrem /yr per (mrad per (mrad /yr Radionuclide uCi/m3) uCi/m3) uCi/m3) uCi/m3) 1.93E+01 2.88E+02 Kr-83m 7.56E-02 1 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-95 1.61E+01 1.34E+03 1.72E+01 1.95E+03 I Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 [ Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.'66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 ( / Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.llE+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 i Xe-133 2.94E+02 3.06E+02 3.35E+02 1.05E+03 I Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 { b f 45 Rev. 8 i

Hope Creek ODCM 7/29/87 TABLE 2-2 /(O PARAMETERS FOR GASEOUS ALARM ) SETPOINT DETERMINATION HOPE CREEK Actual Def ault i Parameter Value Value Units Comments X/0 Calculated 2.67E-6 sec/m3 From FSAR Table 2.3-31 l 0.5 mile, N 3 ft / min Maximum Operation VF (NPV) Measured 41900 3 ft / min Maximum Operation VF (SPV) Measured 440,180 3 ft / min Maximum operation VF (FRVS) Measured 9000 AF (NPV) Coordinated 0.2 Unitiess Administrative with SGS allocation factor to unaure releases i AF (SPV) 0.2 Unitiess do not exceed release rate limit AF (FRVS) 0.1 Unitiess k fleasured N/A uCi/m3 Ki Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m3) Li Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m3) 4 Mi Nuclide N/A (mrem /yr Table 3.1-1 Specific per uCi/m3} ( d Sv: NPV Calculated 2.43E-4 uCi/cc Default alarm SPV Calculated 2.31E-5 uCi/cc Setpoints; more FRVS Calculated 5.56E-4 uCi/cc conservative values l i may be used as deemed appropriate for ensuring ALARA and regulatory complianes d i l Sv(0) NPV Calculated 4.8E3 uCi/sec Determined by SPV Calculated 4.8E3 uCi/sec multiplying setpoint J FRVS Calculated 2.4E3 uCi/sec (uCi/cc) times vent flow rates (cc/sec) l \\ n j 46 Rev. 8 i d I

Hope Creek ODCM 7/29/87 i TABLE 2-3 CONTROLLING LOCATIONS, PATHWAYS AND ATOMSPHERIC DISPERSION FOR DOSE CALCULATIONS

• Controlling X/0 D/0 Toch. Spec.

Location Pathway (s) Age Group (sec/m3) (1/m2) 3.11.2.la Site Boundary Noble Gases N/A 2.67E-06 N/A (0.5 Mile, N) direct 1 exposure l 3.ll.2.lb Site Boundary Inhalation Child 2.67E-06 N/A 1 (0.5 Mile, N) i 3.11.2.2 Site Boundary Gamma-Air N/A 2.67E-06 N/A (0.5 Mile, N) Beta-Air i l 3.11.2.3 Residence / Dairy milk and Infant 7.2E-08 2.87E-10 (4.9 Miles, W) ground plane 6.9.1.7 Second Sun direct exposure N/A 8.22E-06 N/A (0.21 Miles, SE) and inhaltion r a The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR. i 1 I i J i l ('T (/ 4 1 I 47 Rev: 8 ) l i I m.

Hope Creek ODCM 7/29/87 TABLE 2-4 \\ PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES (d R(lo) INEALATION PATHWAY FACTORS - ADULT (aren/yr per uCi/m3) Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 H-3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 8.64E+4 5.01E+4 P-32 1.32E+6 7.71E+4 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Cr-51 9.84E+3 1.40E+6 7.74E+4 d.30E+3 3.96E+4 Mn-54 7.21E+4 6.03E+3 3.94E+3 Fe-55 2.46E+4 1.70E+4 1.02E+6 1.88E+5 1.06E+4 Fs-59 1.18E+4 2.78E+4 3.70E+5 3.14E+4 6.71E+2 6.92E+2 Co-57 9.28E+5 1.06E+5 2.07E+3 1.58E+3 Co-58 5.97E+6 2.85E+5 1.48E+4 1.15E+4 Co-60 1.78E+5 1.34E+4 1.45E+4 Ni-63 4.32E+5 3.14E+4 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Zn-65 3.24E+4 1.03E+5 1.66E+4 5.90E+4 1.35E+5 Rb-86 b",'5 0 1.40E+6 3.50E+5 8.72E+3 ') 9 3.04E+5 1 9.60E+6 7.22E+5 6.10E+6 9.92E+7 1.70E+6 3.85E+5 1.24E+4 Y-91 4.62E+5 5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-95 1.07E+5 3.44E+4 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4.21E+3 5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-103 1.53S+3

1. 34E F5 9.36E+6 9.12E+5 8.72E+3 Ru-106 6.91E+4 Ag-110m 1.08E+4 1.00E+4 1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 1.74E+6 1.01E+5 1.26E+4 To-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+S 7.06E+4 4.67E+2 To-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Tc-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 1.04E+4 7.28E+5 1

Cs-136 3.90E+4 1.46E+5 8.56E+4 1.20E+4 1.17E+4 1.10E+5 2.22E+5 7.52E+4 8.40E+3 4.26E+5 Cs-137 4.78E+5 6.21E+5 1.67E+1 1.27E+6 2.18E+5 2.57E+3 Bm-140 3.90E+4 4.90E+1 Co-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Co-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 2.16E+3 2.81E+5 2.00E+5 4.64E+2 ^^4 4 3 9.36E+3 3.75E+3 s_,147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73E+5 3.65E+2 48 Rev. 8

Hope Crook ODCM 7/29/87 TABLE 2-4 (Con't) ['] PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES \\_/ R(io) INHALATION PATHWAY FACTORS - TEENAGER (mrem /yr per uCi/m3) Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 H-3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 9.28E+4 7.16E+4 P-32 1.89E+6 1.10E+5 7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Cr-51 1.27E+4 1.98E+6 6.68E+4 8.40E+3 5.11E+4 Mn-54 1.24E+5 6.39E+3 5.54E+3 Fe-55 3.34E+4 2.38E+4 1.53E+6 1.78E+5 1.43E+4 Fe-59 1.59E+4 3.70E+4 5.86E+5 3.14E+4 9.20E+2 6.92E+2 Co-57 1.34E+6 9.52E+4 2.78E+3 2.07E+3 Co-58 8.72E+6 2.59E+5 1.98E+4 1.51E+4 Co-60 3.07E+5 1.42E+4 1.98E+4 Ni-63 5.80E+5 4.34E+4 8.64E+4 1.24E+6 4.66E+4 6.24E+4 2n-65 3.86E+4 1.34E+5 1.77E+4 8.40E+4 1.90E+5 Rb-86 2.42E+6 3,71E+5 1.25E+4 9 4.34E+5 1.65E+7 7.65E+5 6.68E+6 0 1.08E+8 2.94E+6 4.09E+5 1.77E+4 Y 1 6.61E+5 6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-95 1.46E+5 4.58E+4 Nb-95 1.86E+4 1.03E+4 1.00E+4 7.51E+5 9.68E+4 5.66E+3 7.43E+3 7.83E+5 1.09E+5 8.96E+2 'Ru-103 2.10E+3 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ru-106 9.84E+4 Ag-110m 1.38E+4 1.31E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 3.85E+6 3.98E+5 1.68E+4 Sb-124 4.30E+4 7.94E+2 9.76E+1 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1.72E+4 5.36E+3 7.50E+4 6.67E+2 To-125m 4.88E+3 2.24E+3 1.40E+3 To-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 Co-134 5.02E+5 1.13E+6 3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 1.10E+5 1.78E+4 1.09E+4 1.37E+5 3.04E+5 1.21E+5 8.48E+3 3.llE+5 Cs-137 6.70E+5 8.48E+5 2.28E+1 2.03E+6 2.29E+5 3.52E+3 BC-140 5.47E+4 6.70E+1 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Co-141 2.84E+4 1.90E+4 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Cc-144 4.89E+6 2.02E+6 3.09E+3 4.83E+5 2.14E+5 6.62E+2 1 P m143 1.34E+4 5.31E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 [ 147 7.86E+3 8.56E+3 x_/ 4 49 Rev. 8 \\

Hope Creek ODCM 7/29/87 TABLE 2-4 (Con't) () PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - CHILD (area /yr per uCi/m3) Nuclide Bone Liver Thyroid Kidney Luno GI-LLI Total Body 1.12E+3 1.12E+3 1.12E+3 1.12Ev3 1.12E+3 1.12E+3 H-3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 4.22E+4 9.88E+4 P-32 2.60E+6 1.14E+5 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Cr-51 1.00E+4 1.58E+6 2.29E+4 9.51E+3 4.29E+4 Mn-54 1.llE+5 2.87E+3 7.77E+3 Fe-55 4.74E+4 2.52E+4 1.27E+6 7.07E+4 1.67E+4 Fe-59 2.07E+4 3.34E+4 5.07E+5 1.32E+4 1.07E+3 9.03E+2 Co-57 1.llE+6 3.44E+4 3.16E+3 1.77E+3 Co-58 7.07E+6 9.62E+4 2.26E+4 1.31E+4 Co-60 2.75E+5 6.33E+3 2.80E+4 Ni-63 8.21E+5 4.63E+4 7.14E+4 9.95E+5 1.63E+4 7.03E+4 Zn-65 4.26E+4 1.13E+5 7.99E+3 1.14E+5 1.98E+5 Rb-86 2.16E+6 1.67E+5 1.72E+4 I 9 5.99E+5 L_,];0 1.48E+7 3.43E+5 6.44E+6 1.01E+8 2.63E+6 1.84E+5 2.44E+4 Y-91 9.14E+5 5.96E+4 2.23E+6 6.llE+4 3.70E+4 Zr-95 1.90E+5 4.18E+4 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-95 2.35E+4 9.18E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-103 2.79E+3 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ru-106 1.36E+5 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Ag-110m 1.69E+4 1.14E+4 3.24E+6 1.64E+5 2,00E+4 Sb-124 5.74E+4 7.40E+2 1.26E+2 2.32E+6 4.03E+4 2.07E+4 f Sb-125 9.84E+4 7.59E+2 9.10E+1 4.77E+5 3.38E+4 9.14E+2 To-125m 6.73E+3 2.33E+3 1.92E+3 Ts-127m 2.49E+4 8.55E+3 7.14E+4 6.07E+3 6.36E+4 1.48E+6 3.02C+3 To-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 2.84E+3 2.73E+4 I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Co-134 6.51E+5 1.01E+6 9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-136 6.51E+4 1.71E+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-137 9.07E+5 8.25E+5 2.llE+1 1.74E+6 1.02E+5 4.33E+3 Bc-140 7.40E+4 6.48E+1 8.55E+3 5.44E+5 5.66E+4 2.90E+3 Co-141 3.92E+4 1.95E+4 \\ 1.17E+6 1.20E+7 3.89E+5 3.61E+5 Co-144 6.77E+6 2.12E+6 i 3.00E+3 4.33E+5 9.73E+4 9.14E+2 143 1.85E+4 5.55E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2 147 1.08E+4 8.73E+3 50 Rev. 8

Hope Crcek ODCM 7/29/87 TABLE 2-4 (Con't) PATHWAY DOSE PACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY PACTORS - INFANT (mrem /yr per uCi/m3) Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 H-3 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 1.61E+4 7.74E+4 i P-32 2.03E+6 1.12E+5 5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Cr-51 4.98E+3 1.00E+6 7.06E+3 4.98E+3 2.53E+4 Mn-54 8.69E+4 1.09E+3 3.33E+3 l Fc-55 1.97E+4 1.17E+4 1.02E+6 2.48E+4 9.48E+3 Fo-59 1.36E+4 2.35E+4 3.79E+5 4.86E+3 6.41E+2 6.51E+2 Co-57 ( Co-58 7.77E+5 1.llE+4 1.82E+3 1.22E+3 4.51E+6 3.19E+4 1.18E+4 I Co-60 8.02E+3 l Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 3.25E+4 6.47E+5 5.14E+4 3.llE+4 Zn-65 1.93E+4 6.26E+4 3.04E+3 8.82E+4 p '16 1.90E+5 2.03E+6 6.40E+4 1.14E+4 L_,39 3.98E+5 1.12E+7 1.31E+5 2.59E+6 Sr-90 4.09E+7 2.45E+6 7.03E+4 1.57E+4 Y-91 5.88E+5 3.llE+4 1.75E+6 2.17E+4 2.03E+4 Zr-95 1.15E+5 2.79E+4 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-95 1.57E+4 6.43E+3 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-103 2.02E+3 1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ru-106 8.68E+4 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Ag-110m 9.98E+3 7.22E+3 2.65E+6 5.91E+4 1.20E+4 Sb-124 3.79E+4 5.56E+2 1.01E+2 1.64E+6 1.47E+4 1.09E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 4.47E+5 1.29E+4 6.58E+2 To-125m 4.76E+3 1.99E+3 1.62E+3 To-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 To-129m 1.41E+4 6.09E+3 5.47E+3 3tl8E+4 1.68E+6 6.90E+4 2.23E+3 1.06E+3 1.96E+4 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-134 3.96E+5 7.03E+5 5.64E+4 1.18E+4 1.43E+3 5.29E+4 i Cs-136 4.83E+4 1.35E+5 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-137 5.49E+5 6.12E+5 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ba-140 5.60E+4 5.60E+1 5.25E+3 5.17E+5 2.16E+4 1.99E+3 Co-141 2.7?E+4 1.67E+4 5.3BE+5 9.84E+6 1.48E+5 1.76E+5 3.19E+6 1.21E+6 9144 1.97E+3 4.33E+5 3.72E+4 6.99E+2 143 1.40E+4 5.24E+3 3.15E+3 3.22E+5 3.12E+4 5.00E+2 Nd-147 7.94E+3 8.13E+3 51 Rev. 8l

Hope Creek ODCM 7/29/87 TABLE 2-4 (Con't) O PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES (\\_ / R(io) GRASS-COW-MILK PATHWAY FACTOR - ADULT (area /yr per uCi/m3) for H-3 and C-14 (e1

• mrea/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luno GI-LLI Total Body 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 H-3 C-14 3.63E+5 7.26E+4 7.26E&4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 1.92E+9 6.60E+8 P-32 1.71E+10 1.06E+9 1.71Ei4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Cr-51 2.57E+7 1.60E+6 2.50E+6 8.40E+6 Mn-54 9.67E+6 9.95E+6 4.04E+6 Fc-55 2.51E+7 1.73E+7 1.95E+7 2.33E+8 2.68E+7 Fc-59 2.98E+7 7.00E+7 3.25E+7 2.13E+6 1.28E+6 Co-57 9.57E+7 1.06E+7 4.72E+6 Co-58 3.08E+8 3.62E+7 1.64E+7 Co-60 9.73E+7 2.26E+8 Ni-63 6.73E+9 4.66E+R 2.75E+9 1.97E+9 2.92E+9 2n-65 1.37E+9 4.36E+9 1.66E+4 5.90E+4 1.35E+5 r~'86 (j)0 2.33E+8 4.16E+7 9

1.45E+9 1.35E+9 1.15E+10 Sr-9 4.68E+10 4.73E+6 2.30E+2 Y-91 8.60E+3 5.24E+4 1.77E+6 1.50E+5 2.33E+4 2r-95 1.07E+5 3.44E+4 7.74E+3 5.05E+5 1.04E+5 4.21E+3 Nb-95 1.41E+4 7.82E+3 1.19E+5 4.39E+2 3.89E+3 Ru-103 1.02E+3 3.94E+4 1.32E+6 2.58E+3 Ru-106 2.04E+4 2.20E+10 3.20E+7 1.06E+8 Ag-110m 5.83E+7 5.39E+7 2,00E+7 7.31E+08 4.86E+6 Sb-124 2.57E+7 4.36E+5 6.24E+4 1.58E+7 2.25E+8 2.18E+6 Sb-125 2.04E+7 2.28E+5 2.08E+4 6.50E+7 2.18E+6 l To-125m 1.63E+7 5.90E+6 4. 9 0 ?.+ 6 6.63E+7 1.54E+8 5.58E+6 To-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 3.04E+8 9.57E+6 To-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 1.12E+8 2.43E+8 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-134 5.65E+9 1.34E+10 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-136 2.61E+8 1.03E+9 3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-137 7.38E+9 1.01E+10 1.15E+4 1.93E+4 5.54E+7 1.76E+6 ) 1 B:-140 2.69E+7 3.38E+4 1.25E+7 3.71E+2 1.52E+3 Cc-141 4.84E+3 3.27E+3 1.21E+8 1.92E+4 8.87E+4 144 3.58E+5 1.50E+5 6.96E+5 7.88E+0 3.68E41 143 1.59E+2 6.37E+1 5.23E+5 6.52E+0 6.37E+1 147 9.42E+1 1.09E+2 l j 52 Rev. 8

Hopo Crcek ODCM 7/29/87 TABLE 2-4 (Con't) [mi PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES %) R(io) GRMS-COW-MILK PATHWAY FACTOR - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2

• mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyrcid Kidney Lung GI-LLI Total Body 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 H-3 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 2.65E+9 1.22E+9 P-32 3.15E+10 1.95E+9 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Cr-51 2.87E+7 2.78E+6 4.17E+6 1.40E+7 Mn-54 2.00E+7 1.37E+7 7.36E+6 Fc-55 4.45E+7 3.16E+7 3.82E+7 2.87E+8 4.68E+7 Fe-59 5.20E+7 1.21E+8 4.19E+7 3.76E+6 2.25E+6 Co-57 1.10E+8 1.83EF7 7.95E+6 Co-58 3.62E+8 6.26E+7 2.78E+7 Co-60 1.33E+8 4.01E*8 Ni-63 1.18E+10 8.35E+8 3.10E+9 3.41E+9 4.68E+9 2n-65 2.llE+9 7.31E+9 f~'16 7.00E+8 2.22E+9 4.73E+9 3.18E+8 7.66E+7 L_,39 2.67E+9 9.60E+6 7.22E+5 6.10E+6 Sr-90 9.92E+7 6.48E+6 4.24E+2 Y-91 1.58E+4 1.20E+6 3.59E+2 7.67E+2 Zr-95 1.66E+3 5.22E+2 3.34E+8 4.30E+4 7.57E+4 Nb-95 1.41E+5 7.80E+4 1.52E+5 7.75E+2 6.40E+3 Ru-103 1.81E+3 1.80E+6 4.73E+3 7.23E+4 Ru-106 3.75E+4 2.56E+10 5.54E+7 1.74E+8 Ag-110m 9.63E+7 9.llE+7 4.01E+7 9.25E+8 1.79E+2 Sb-124 4.59E+7 8.46E+5 1.04E+5 3.21E+7 2.84E+8 8.54E+6 Sb-125 3.65E+7 3.99E+5 3.49E+4 8.86E+7 4.02E+6 To-125m 3.00E+7 1.08E+7 8.39E+6 i

2.10E+8 1.00E+7 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 4.15E+8 1.75E+7 To-129m 1.llE+8 4.10E+7 3.57E+7 4.62E+8 1.49E+8 4.04E+8 I-131 5.38E+8 7.03S+8 2.20E+11 1.30E+9 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-134 9.81E+9 2.31E+10 9.53E+8 1.50E+8 1.41E+8 1.18E+9 Co-136 4.45E+8 1.75E+9 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Cs-137 1.34E+10 1.78E+10 2.02E+4 4.00E+4 7.49E+7 3.13E+6 B2-140 4.85E+7 5.95E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Cc-141 1.99E+4 1.35E+4 1.66E+8 3.54E+4 1.63E+5 144 6.58E+5 2.72E+5 9.61E+5 1.45E+1 6.77E+1 43 2.92E+2 1.17E+2 7.llE+5 1.18E+1 1.16E+2 Nd-147 1.81E+2 1.97E+2 53 Rev. 8

Hope Creek ODCM 7/29/87 TABLE 2-4 (Con't) PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(lo) GRASS-COW-MILK PATHWAY PACTOR - CHILD (mrom/yr per uCi/m3) for H-3 and C-14 (m2

• mrom/yr por uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 H-3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 2.15E+9 3.00E+9 P-32 7.77E+10 3.64E+9 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Cr-51 1.76E+7 5.58E+6 5.87E+6 2.09E+7 Mn-54 3.35E+7 1.10E+7 1.84E+7 FG-55 1.12E+8 5.93E+7 5.65E+7 2.03E+8 9.71E+7 Fe-59 1.20E+8 1.95E+8 3.14E+7 7.77E+6 3.84E+6 Co-57 7.08E+7 3.72E+7 1.21E+7 Co-58 2.39E+8 1.27E+8 4.32E+7 Co-60 1.07E+8 1.01E+9 Ni-63 2.96E+10 1.59E+9 1.93E+9 6.85E+9 6.94E+9 2n-65 4.13E+9 1.10E+10 5.64E+8 5.39E+9 g "5 8.77E+9 2.56E+8 1.89E+8 Sh_f9 6.62E+9 1.51E+9 2.83E+10 Sr-90 1.12E+11 2.63E+6 1.84E+5 2.44E+4 Y-91 9.14E+5 8.81E+5 7.52E+2 1.21E+3 2r-95 3.84E+3 8.45E+2 2.29E+8 8.84E+4 1.16E+5 Nb-95 3.18E+5 1.24E+5 1.llE+5 1.65E+3 1.08E+4 Ru-103 4.29E+3 1.44E+6 1.15E+4 1.25E+5 Ru-106 9.24E+4 1.68E+10 1.13E+8 2.63E+8 Ag-110m 2.09E+8 1.41E+8 6.03E+8 6.79E+8 1.82E+7 Sb-124 1.09E+8 1.41E+8 2.40E+5 4.85E+7 2.08E+8 9.84E+6 Sb-125 8.70E+7 1.41E+6 8.06Ev4 7.12E+7 9.84E+6 To-125m 7.38E+7 2.00E+7 2.07E+7 1.68E+8 2.47E+7 Tc-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 3.32E+8 4.23E+7 Tc-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+8 1.17E+8 7.46E+8 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-134 2.26E+10 3.71E+10 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-136 1.00E+9 2.76E+9 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-137 3.22E+10 3.09E+10 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Be-140 1.17E+8 1.03E+5 1.36E+7 1.62E+3 4.78E+3 Cc-141 2.19E+4 1.09E+4 1.33E+8 8.66E+4 2.82E+5 c'~l 4 4 1.62E+6 5.09E+5 7.80E+5 3.59E+1 1.17E+2 L

143 7.23E+2 2.17E+2 5.71E+5 2.79E+1 1.98E+2 Nd-147 4.45E+2 3.60E+2 54 Rev. 8

4 i Hope Creek ODCM 7/29/87 TABLE 2-4 (Con't) PATHWAY DOSE FACTORS - ATMOSPHERIC R3 LEASES V R(io) GRASS-COW-MILK PATHWAY FACTOR - INFANT (aren/yr per uCi/m3) for H-3 and C-14 (m2

• mres/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luna GI-LLI Total Body 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 H-3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 2.17E+9 6.21E+9 P-32 1.60E+11 9.42E+9 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Cr-51 1.43E+7 8.83E+6 8.63E+6 3.89E+7 Mn-54 4.27E+7 1.11E+7 2.33E+7 Fo-55 1.35E+8 8.72E+7 1.16E+8 1.88E+8 1.55E+8 Fe-59 2.25E+8 3.93E+8 3.05E+7 1.46E+7 8.95E+6 Co-57 6.05E+7 6.06E+7 2.43E+7 Co-58 2.10E+8 2.08E+8 8.81E+7 Co-60 1.07E+8 1.21E+9 Ni-63 3.49E+10 2.16E+9 1.61E+10 8.78E+9 9.23E+9 2n-65 5.55E+9 1.90E+10

.O 5.69E+8 1.10E+10 2.22E+10 ) R( d9 2.59E+8 3.61E+8 Sr-1.26E+10 1.52E+9 3.10E+10 Sr-90 1.22E+11 5.26E+6 1.95E+3 Y-91 7.33E+4 8.28E+5 1.18E+3 1.79E+3 Zr-95 6.83E+3 1.66E+3 2.06E+G 1.41E+5 1.75E+5 Nb-95 5.93E+5 2.44E+5 1.06E+5 2.91E+3 1.81E+4 Ru-103 8.69E+3 1.44E+6 2.38E+4 2.25E+5 Ru-106 1.90E+5 1.46E+10 1.86E+8 4.03E+8 Ag-110m 3.86E+8 2.82E+8 1.31E+8 6.46E+8 6.49E+7 Sb-124 2.09E+8 3.08E+6 5.56E+5 9.38E+7 1.99E+8 3.07E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 7.lRE+7 2.04E+7 Tc-125m 1.51E+8 5.04E+7 5.07E+7 1.70E+8 5.10E+7 Tc-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 3.34E+8 8.62E+7 To-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 1.15E+8 1.41E+9 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cc-134 3.65E+10 6.80E+10 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cc-136 1.96E+9 5.77E+9 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Cc-137 5.15E+10 6.02E+10 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Bs-140 2.41E+8 2.41E+5 1.37E+7 3.11E+3 8.15E+3 Co-141 4.33E+4 2.64E+4 1.33E+8 1.30E+5 3.85E+5 ( )44 2.33E+6 9.52E+5 7.89E+5 7.41E+1 2.08E+2 &c-143 1.49E+3 5.59E+2 5.74E+5 5.55E+1 3.49E+2 Nd-147 8.82E+2 9.06E+2 Rev. 8 l 55 )

Hope Creek ODCM 7/29/87 ( TABLE 2-4 (Con't) /3 PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES Nl R(io) VEGETATION PATHWAY FACTOR - ADULT (aren/yr per uCi/m3) for H-3 and C-14 (m2

• mren/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luno GI-LLI Total Body 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 H-3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.58E+8 5.42E+7 P-32 1.40E+9 8.73E+7 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 i

Cr-51 9.54E+8 5.94E+7 9.27E47 3.11E+8 Mn-54 8.06E+7 8.29E+7 3.37E+7 Fo-55 2.09E+8 1.45E+8 8.35E+7 9.96E+8 1.14E+8 Fe-59 1.27E+8 2.99E+8 2.97E+8 1.95E+7 1.17E+7 Co-57 6.26E+8 6.92E+7 3.09E+7 Co-58 3.14E+9 3.69E+8 1.67E+8 Co-60 1.50E+8 3.49E+8 Ni-63 1.04E+10 7.21E+8 6.36E+8 4.56E+8 6.75E+8 Zn-65 3.17E+8 1.01E+9 4.32E+7 1.02E+8 2.19E+8 6 1.60E+9 2.86E+8 l 9 9.96E+9 1.75E+10 1.48E+11 S 90 6.05E+11 2.82E+9 1.37E+5 Y-91 5.13E+6 1.21E+9 2.58E+5 5.97E+5 Zr-95 1.19E+6 3.81E+5 4.80E+8 4.25E+4 7.81E+4 Nb-95 1.42E+5 7.91E+4 5.61E+8 2.07E+6 1.83E+7 Ru-103 4.80E+6 1.25E+10 2.44E+7 3.72E+8 Ru-106 1.93E+8 3.98E+9 5.80E+6 1.92E+7 Ag-110m 1.06E+7 9.76E+6 8.08E+7 2.95E+9 4.11E+7 Sb-124 1.04E+8 1.96E+6 2.52E+5 1.05E+8 1.50E+9 3.25E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 3.86E+8 1.29E+7 To-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 l 1.17E+9 4.26E+7 To-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.28E+9 4.03E+7 To-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 3.05E+7 6.63E+7 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-134 4.66E+9 1.11E+10 l 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-136 4.20E+7 1.66E+8 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cs-137 6.36E+9 8.70E+9 5.49E+4 9.25E+4 2.65E+8 8.43E+6 B0-140 1.29E+8 1.62E+5 . Cc-141 1.96E+5 1.33E+5 5.08E+8 1.51E+4 i 6.17E+4 I 1.11E+10 1.77E+6 i 8.16E+6

Ce,144 3.29E+7 1.38E+7 2.78E+8 3.14E+3

[ ( 143 6.34E+4 2.54E+4 1.47E+4 1.85E+8 2.31E+3 + 2.25E+4 hus147 3.34E+4 3.86E+4 i 1 56 Rev.8l'

Hope Creek ODCM 7/29/87 l TABLE 2-4 (Con't) 7 PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES (v) R(io) VEGETATION PATHWAY FACTOR - TEENAGER (arem/yr per uCi/m3) for H-3 and C-14 (m2

• mren/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luno GI-LLI Total Body 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 H-3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 1.35E+8 6.23E+7 P-32 1.61E+9 9.96E+7 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Cr-51 9.27E+8 8.97E+7 1.35E+8 4.52E+8 Mn-54 1.46E+8 9.98E+7 5.38E+7 Fo-55 3.25E+8 2.31E+8 1.33E+8 9.98E+8 1.63E+8 Fo-59 1.81E+8 4.22E+8 3.34E+8 3.00E+7 1.79E+7 Co-57 6.04E+8 1.01E+8 4.38E+7 Co-58 3.24E+9 5.60E+8 2.49E+8 Co-60 1.81E+8 5.45E+8 Ni-63 1.61E+10 1.13E+9 6.23E+8 6.86E+8 9.41E+8 2n-65 4.24E+8 1.47E+9

(~'76 4.05E+7 1.28E+8 2.73E+8 L_,J 9 1.51E+10 1.80E+9 4.33E+8 2.11E+10 1.85E+11 Sr-90 7.51E+11 3.23E+9 2.llE+5 Y-91 7.87E+6 1.27E+9 3.788+5 Zr-95 1.74E+6 5.49E+5 8.07E+5 Nb-95 1.92E+5 1.06E+5 1.03E+5 4.55E+8 5.86E+4 1 2.42E+7 5.74E+8 2.94E+6 Ru-103 6.87E+6 5.97E+8 1.48E+10 3.90E+7 Ru-106 3.09E+8 4.04E+9 8.74E+6 Ag-110m 1.52E+7 1.44E+7 2.74E+7 1.35E+8 3.llE+9 6.03E+7 Sb-124 1.55E+8 2.85E+6 3.51E+5 1.88E+8 1.66E+9 5.00E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 l Tc-125m 1.48E+8 5.34E+7 4.14E+7 4.37E+3 1.98E+7 i To-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 i To-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 1.38E+9 5.81E+7 I-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 2.13E+7 5.79E+7 4 Cs-134 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.08E+8 7.74E+9 9.19E+7 1.45E+7 1.36E+7 1.13E+8 L Cs-136 4.29E+7 1.69E+8 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 i 5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ba-140 1.38E+8 1.69E+5 5.38E+8 2.16E+4 l c. '41 2.82E+5 1.88E+5 8.86E+4 1 1.30E+7 1.33E+10 2.83E+6 't. 4 5.27E+7 2.18E+7 143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 i l Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3 i l I 57 Rev.8{! l

l l Hope Croek ODCM 7/29/87 f l TABLE 2-4 (Con't) [N_-) PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(lo) VEGETATION PATHWAY FACTOR - CHILD (aren/yr per uCi/m3) for H-3 and C-14 (m2

• mren/yr per uCi/sec) for others 1

Nuclide Bone Liver Thyroid Kidney Luna GI-LLI Total Body 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 H-3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 9.30E+7 1.30E+8 P-32 3.37E+9 1.58E+8 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Cr-51 5.55E+8 1.76E+8 1.d5E+8 6.61E+8 Mn-54 2.40E+8 7.86E+7 1.31E+8 Fo-55 8.00E+8 4.24E+8 1.888+6 6.76E+8 3.23E+8 Fo-59 4.01E+8 6.49E+8 2.45E+8 6.34E+7 ?.9Pc+7 Co-57 3.77E+8 1.98E+8 6.47E+7 Co-58 2.10E+9 1.12E+9 3.78E+8 Co-60 1.42E+8 1.34E+9 Ni-63 3.95E+10 2.11E+9 3.80E+8 1.35E+9 1.36E+9 2n-65 8.12E+8 2.16E+9 (76 2.91E+7 2.78E+8 4.52E+8 1.39E+9 1.03E+9 L_ J9 3.59E+10 1.67E+10 3.15E+11 Sr-90 1.24E+12 2.49E+9 5.01E+5 Y-91 1.87E+7 Zr-95 3.90E+6 8.58E+5 1.23E+6 8.95E+8 7.64E+5 1.50E+5 Nb-95 4.10E+5 1.59E+5 2.95E+8 1,14E+5 Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 2.58E+9 1.74E+7 4.05E+7 1.96E+8 2.20E+9 1.23E+8 l Sb-124 3.62E+8 4.57E+6 7.78E+5 2.78E+8 1.19E+9 1.05E+8 [ Sb-125 4.99E+8 3.85E+6 4.62E+5 3.38E+8 4.67E+7 l To-125m 3.51E+8 9.50E+7 9.84E+7 To-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1.57E+8 l To-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 1.04E+9 1.33E+8 i 1.28E+7 8.18E+7 l I-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 Cs-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1.42E+8 5.54E+9 l 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-136 8.06E+7 2.22E+8 7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-137 2.29E+10 2.29E+10 Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+5 1.40E+8 1.62E+7 7.66E+7 9.12E+3 Cc-141 1.23E+5 6.14E+4 2.69E+4 2.21E+7' 1.04E+10 6.78E+6 pi44 1.27E+8 3.98E+7 1.60E+8 7.37E+3 t,143 1.48E+5 4.46E+4 2.41E+4 m 9.18E+7 4.49E+3 Nd-147 7.16E+4 5.80E+4 3.18E+4 l 58 Rev. dl

tiope Creek ODCM 7/29/87 l j TABLE 2-4 (Con't) ( PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES l R(lo) GROUND PLANE PATHWAY FACTOR (m2

• mren/yr per uCi/sec)

Nuclide Any Organ g_3 C-14 1 P-32 l Cr-51 4 68E 6 Mn-54 1.34E 9 Fe-55 Fe-59 2.75E 8 Co-58 3.82E 8 Co-60 2.16E10 Ni-63 2n-65 7.45E 8 Rb-86 8.98E 6 Sr-89 2.16E 4 O Sr-90 l Y-91 1.08E 6 Zr-95 2.48E 8 ) Nb-95 1.36E 8 ) Ru-103 1.09E 8 Ru-106 4.21E 8 t ] Ag-110m 3.47E 9 l l To-125m 1.55E 6 3 Te-127m 9.17E 4 Te-129m 2.00E 7 l I-131 1.7?E 7 I i Cs-134 6.75E 9 l l Cs-136 1.49E 8 Cs-137 1.04E10 l Ba-140 2.05E 7 l Ce-141 1.36L 7 i Ce-144 6.95E 7 i Pr-143 Nd-147 0.40E 6 a 1 \\ j 59 Rev. 8 l u \\

Hope Creek ODCM 7/29/87 l ) P 1 I APPENDIX A I EVALUATION OF DEPAULT MPC VALUES FOR LIQUID EPPLUENTS i 4 i l l i 1 I t l i I l l l 1 A-1 Rev. 8 l

Hope Crook ODCM 7/29/87 l APPENDIX A Evaluation of Default MPC Value for Liquid Effluents In accordance with the requirements of Technical Specification 3.3.3.10 the radioactive effluent monitors shall be operable with j alarm setpoints established to ensure that the concentration of ]j radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2. The 7 determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual ra.ionuclida distribution and corresponding MPC values. In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established. This default setpoint can be based on an evalaation of the ] radionuclide distribution frcm the Hope Creek FSAR, Section 11.2, Table 11.2-11 of the liquid effluents from Hope Creek and the l 3 effective MPC value for this distribution. b l The effective MPC value for a racionuclide distribution is calculated by the equation l 1 i i i j MPCe Ci / E (Ci/MPCi) (A.1) [ = l 4 2 where i an effective MPC value for a mixture of MPCe = radionuclides (uci/ml) concentration of radionuclide i in the mixture } Ci = the 10 CFR 20, Appendix B, Table II, Column 2 MPCi = i i j MPC value for radionuclide 1 (uCi/ml) i

• !O j

j A-2 Rev. 8

t t j Hopo Creek ODCM 7/29/87 () Based on the above equation and the radionuclide distribution in the effluents for Hope Creek from FSAR Table 11.2-11 (Expected Yearly Activity Released from Liquid Radwaste Management). Results are presented in Table A-1. a Considering the average effective MPC values from FSAR Table i 11.2-11 it is reasonable to select an MPC value of 1.9E 05 uCi/ml l as typical of liquid radwaste discharges. This value will be l f reviewed and adjusted as necessary based on the distribution [ l t history of effluents from Hope Creek. Using the value of uCi/ml i to calculate the default Llarm setpoint, results in a setpoint j ] that: a 1) Will not require frequent re-adjustment due to minor j variations in the nuclide distribution which are typical of routine plant operations, and; 2) will provide for a liquid radwaste discharge rate (as t evaluated for each batch release) that is compatible l l with plant operations (Refer to Table 1-1). 9 l k i A L I l 1 i l l t f i 0 I i i i 1 1 4 I l ( i A-3 Rev. 8 l 4

Hope Creek ODCM 5/17/88 TABLE A-1 CALCULATION OF EFFECTIVE MPC BOPE CREEK 1987 ACTIVITY NUCLIDE MPC RELEASED (Ci) l t i Na-24 3.0E-05 5.7E-01 i Cr-51 2.0E-03 4.5E-01 i Mn-54 1.0E-04 6.3E-02 Fe-55 8.0E-04 3.0E-02 I Mn-56 1.0E-04 1.3E-04 Co-58 9.0E-05 9.5E-02 + Fe-59 6.0E-05 5.2E-02 i j Co-60 3.0E-05 3.8E-02

)

Cu-64 3.0E-04 9.6E-04 ) Ni-65 1.0E-04 3.3E-05 l 2n-65 1.0E-04 1.7E-01 j 2n-69 2.0E-03 3.4E-03 l () Se-75 3.0E-04 4.0E-04 i Sr-89 3.0E-06 3.2E-03 Y-91m 3.0E-03 2.8E-02 Y-91 3.0E-05 2.8E-03 1 Sr-92 7.0E-05 a.1E-05 ) Nb-95 1.0E-04 1.3E-03 Zr-95 6.0E-05 1.4E-04 Nb-97 9.0E-04 1.9E-03 l l 2r-97 2.0E-05 2.7E-05 Mo-99 4.0E-05 1.2E-02 f l Tc-99m 6.0E-03 1.3E-02 i Tc-100 3.0E-06 3.7E-05 I Ru-106 1.0E-05 1.lE-05 Sb-122 3.0E-05 7.7E-04 j Sb-124 2.0E 5 6.5E-03 l l Sb-125 1.0E-4 1.7E-04 { 1 I-131 3.0E-07 1.8E-04 j Te-132 3.0E-05 2.6E-04 4 r ( l A-4 Rev. 9 i

. _ _ _ _ _ - _ _ _ _ _. _. _. = _ _ _ _ _ _ _ _ _ _ _.. l l l I Hope Creek ODCM 5/17/00 t TABLE A-1 (CONT'D) l 3 i CALCULATION OF EFFECTIVE NPC ' l HOPE CREEK I ] I i i 1 f 1987 ACTIVITY NUCLIDE MPC RELEASED (Ci) I-133 1.0E-06 2.9E-03 i Cs-137 2.0E-05 1.2E-05 I i Ba-139 3.0E-06 1.3E-05 I Co-141 9.0E-05 1.0E-05 Co-143 4.0E-05 7.4E-06 i Co-144 1.0E-05 2.3E-03 j Np-239 1.0E-04 1.3E-03 j Hg-203 240E-05 1.9E-04 l TOTAL 1.58E+00 i i SUM (Ci/MPCi) 3.77E+U4 l MPCe (uCi/mt) 4.19E-05 l l l l l i, l l l l l l l i l I i I l A-5 Rev. 9

Hope Creek ODCM 7/29/87 l l i 1 j APPENDIX B TECHNICAL BASIS FOR EPPECTIVE DOSE PACTORS LIQUID RADIOACTIVE EPPLUENT i 1 i 1 I i 4 i I e 1 ~ B-1 key. 8

i Hope Crook ODCM 5/17/08 O APPENDIX B j i Technical Basis for Effective Dose Factors - i Liquid Effluent Releases j Cne radioactive liquid effluents from Hope Creek during 1987 were J tvaluated to determine the dose contribution of the radionuclide l distribution. This analysis was performed to ev'luate the use of a ilmited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the t dose limits of Technical Specification 3.11.1.2. For the i expected radionuclide distribution of ef fluents f rom Hope Creek during 1987, the controlling organ is the liver. The calculated i liver dose is predominately a function of the 2n-65 and Fe-59 releases. The radionuclides, 2n-55 and Fe-59 also contribute the large majority of the calculated total body dose. The results of i 4 this evaluation are pres.nted in Table B-1. i For purposes of simplifying the details of the dose calculation i process, it is conservative to 'dentify a controlling, dose ] significant radionuclide and limil.the calculation process to the l use of the dose conversion tactor tor this nuclide. i

j Multiplication of the total release (i.e., cumulative activity

) for all radionuclides) by this dose conversion factor provides { tor a dose calculation method that is simplified while also being conservative, 4 d For the evaluation of the maximum organ dose, Ut is conservative i to use the 2n-65 dose ccaversion factor (5.13E5 mrem /hr per liver). By this approach, the maximum organ dose will be i overestimated since this nuclide has the highest organ dose fraction of all the radionuclides evaluated. For the total body l calculation, the 2n-65 dose factor (2.32E5 mrem /hr per uCi/ml, j .i total body) is the highest among the identified dominant j

nuclides, i

For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the rollowing simplified equations may be i used: 4 j Total Body j ) 8.35E-04 VOL Ai,TB Ci j Dtb = CTBD I!O i l B-2 Rev. 9

4 Hope Creek ODCM 5/17/88 t / Where: 4 dose to the total body (mrem) Dtb = 2.32E5, total body ingestion dose conversion Ai,TB = factor for 2n-65 where A is dose conversion factor, i is isotope which is 2n-65, and TB is the total body (mrem /hr per uCi/ml) volume of liquid effluent released (gal) VOL = total concentration of all radionuclides (uCi/ml) C = l. CTBD average cooling tower blowdown discharge rate = during release period (gal / min) i conversion factor (1.67E-2 hr/ min) and the near 8.35E-04 = field dilution factor 0.05 Substituting the value for the 2n-65 total body dose conversion factor, the equation simplified tos )) 1.94E2 VOL l Dtb Ci = l CTBD Maxieum Orcan 1 2 8.35E-4 VOL Aio, GI-LLI i Dmax Ci = j CTBD r Where maximum organ dose (mrem) Dmax = 1 Ai,0 5.13ES, liver ingestion dose conversion factor for = 2n-65 where A is dose conversion factor, i is isotope l which is 2n-65 and o is maximum organ which is the GI-LLI. (mrem /hr per uCi/ml). i Substituting the value for Aio the equation simplifies tot 3 4.28E2 VOL Ci Dmax = CTBD f i Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose l resulting from normal reactor releases is relatively negligible. l a 9 e B-3 Rev. 9

l ~ flopo Crook ODCM 7/29/87 I j i Near Field Dilution Factor I { { The near field dilution factor stems from NuReg-0133, Section l 4.1. For plants with cooling towers, such as Hope Creek, a l l dilution factor is applicable so that the product of the average I I i blowdown flow (in CPS) and the dilution factor is 1000 cfs or j less. The average minimum cooling tower blowdown for Hope Creek I is 1.90E4 GPM (from FSAR 11.2). This converts to 42 CFS, for conservatism a dilution factor of 20 will be used, giving a i j dilution flow of 880 CFS. This near field dilution factor of 20 f I is inverted ;o a multiple of 0.05, multiplied times the liquid j effluent dose equations. J f

l I

!O i 1 i t l f I i I f i i 1 ( l I i l I '\\ l l i 1O 4 f j B-4 Rev. 8 l

Hope Crook ODCM 5/17/88 O TABLE B-1 Adult Dose Contributions Fish and Invetebrate Pathways Hope Creek 1987 TB GI-LLI Liver Radionuclide Release (Ci) Dose Frac. Dose Frac. Dose Frac. Cr-51 4.5E-1 0.01 Mn-54 6.3E-2 0.01 Co-58 9.5E-2 0.01 Fe-59 5.2E-2 0.08 0.34 0.10 O Co-60 3.8E-2 0.01 2n-65 1.7E-1 0.91 0.59 0.90 Nb-95 1.3E-3 0.02 = Less than 0.01 i i l O B-5 Rev. 9

Hope Creek ODCM 7/29/87 l i l I 4 APPENDIX C l TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS l GASEOUS RADIOACTIVE EFFLUENT i l l l i 4 'l J i I l 4 C-1 Rev. 8 l 4

i Hope Creek ODCM 7/29/87 l APPENDIX C f Technical Basis for Effective Dose Factors - i Gaseous Radioactive Effluents j t f Overview l l The evaluation of doses due to releases of radioactive material l to the atmosphere can be simplified by the use of effective dose l 4 transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are base 6 j on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in 4 l the environitent. Instead of having to perform individual radioluclide dose analysis only a single multiplication (i.e., j Keff, Meff, or Neff times the total quantity of radioactive j material released) would b* needad. The approach provides a ( reasonable estimate of the actual dose while eliminating the need i for a detailed calculation technique. ) i Determination of Effective Dose Factors 1 I l Effective dose transfer factors are calculated by the following j o quations: e 1 t { (Ki

• fi) j Keff

= i j Where: i l Keff the effective total body factor due to gamma a emissions from all noble gases released. the total body dose factor due to gamma Ki = emissions from each noble gas radionuclide i I released. l I the fractional abundance of noble gas l fi = I radionuclide i relative to the total noble l } gas activity. l I ds l l (L + 1.1 M)eff = 1 ((Li + 1.1 Mi)

• fi) 1 l

l Where: the effective skin dose factor due to (L + 1.1M)eff = ) beta and gamma emissions from all noble gases released. j lo l C-2 Rev. 8 l

Hopo Crcok ODCM 7/29/87 l [ ') (Li + 1.1 Mi) the skin dose factor due to beta and = 'v> gamma emissions from each noble gas radionuclide i released. Meff =[(Mi

• fi)

Where: the effective air dose factor due to gamma Meff = emissions from all noble gases released. the air dose factor due to gamma emissions Mi = from each noble gas radionuclide i released. ds Neff = ((Ni fi) Where: the effective air dose factor due to beta Neff = emissions from all noble gases released. the air dose factor due to beta emissions Ni = from each noble gas radionuclide i released. Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from Hope Creek have a ("] short history. So, to provide a reasonable basis for the (_/ derivation of the effective noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, "Source Term Specifications", Table 5 has been used as representing a typical distribution. The effective dose factors as derived are presented in Table B-1. Application To p. ovide an additional degree of conservatism, a factor of 0.50 is introeaced into the dose calculational process when the effective dose transfer factor is used. This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment. For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used: 3.17E-08 X/Q Meff

• { Qi Dx

= 0.50 and l [) s_s C-3 Rev. 8

. = _ _ - - _ _ 1 Hopo Crook ODCM 7/29/87 l O 3.17E-08 i X/O Neff

• { Qi Db

= 0.50 Where: l air dose due to gamma emissions for the D = cumulative release of all noble gases (mrad) [ air dose due to beta emissions for the ] Db = cumulative release of all noble gases (mrad) s l X/O atmosphericdisgersiontothecontrollingsite j = boundary (sec/m ) i 8.1E3, effective gamma-air dose factor (mrad /yr ] Meff = per uCi/m3) e 8.5E3, effective beta-air dose factor (mrad /yr 1 Neff = 3 j per uCi/m ) [ cumulative release for all noble gas t Qi = 4 radionuclides (uCi) i 3.17E-08 = conversion factor (yr/sec) l i conservatism factor to account for the I 0.50 = 7 1 variability in the effluent data i l Combining the constants, the dose calculational equations simplify tot 1 X/O

• { Qi f

5.14E-4 D = I X/O

• E Qi i

b 5.39E-4 D = i J The effective dose factors are to be used on a limited basis for i the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable. ) I i I i 1 3 l l l() j i I J C-4 Rev. 8 l 1

Hops Crook ODCM 7/29/87 ( TABLE L-1 Effective Dose Factors Noble Gases - Total Body and Skin Total Body Effective Skin Effective Keff (L + 1.1 M) eff Rad ionucl ide fi* (mrom/y per uCi/m3) (mrom/y per uCi/m3) Kr83m 0.01 Kr85m 0.01 1.0E1 2.8El Kr87 0.04 2.4E2 6.6E2 Kr88 0.04 5.9E2 7.6E2 Kr89 0.27 4.5E3 7.9E3 Xe133 0.02 5.9E0 1.4El Xe135 0.05 9.0E1 2.0E2 Xel35m 0.06 1.902 2.6E2 Xe137 0.31 4.4E2 4.3E3 Xe138 0.19 1.7E3 2.7E3 TOTAL 7.8E3 1.7E4 Noble Gases - Air Gamma Air Effective Betta Air Effective Meff Neff Radionuclide fi* (mrad /y per uCi/m3) (mrad /y per uCi/m3) 3.0E0 Kr83m 0.01 Kr85m 0.01 1.2El 2.0El Kr87 0.04 2.5E2 4.lE2 KrB8 0.04 6.1E2 2.0E2 Kr89 0.27 4.7E3 2.9E3 Xel33 0.02 7.0E0 2.lEl Xel35m 0.05 9.6El 1.2E2 Xe135 0.06 2.0E2 4.4El Xe137 0.31 4.7E2 3.9E3 Xe138 0.19 1.8E3 9.0E2 TOTAL 8.lE3 8.5E3 Based on noble gas distribution from ANSI N237-1976/ANS-18.1, "Source Term specification". I i C-5 Rev. 8

-. = _. Hope Creek ODCM 7/29/87 J 4 APPENDIX D l TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETER i GASEOUS RADIOACTIVE EFFLUENT h 1 f i l i i i 1 .i l 1 l l i 1-D-1 Rev. 8 I

Hopo Crock ODCM 7/29/87 g APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide. This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3. For the infant age group, the controlling pathway is the grass - milk - cow (g/m/c) pathway. An infant receives a greater radiation dose from the g/m/c pathway than any other pathway. Of this g/m/c pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide I-131. The results of this evaluation are presented in Table D-1. l l For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose (~N conversion factor provides for a dose calculation method that is (,) simplified while also being conservative. 1 For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, 2 g/m/c, thyroid, I-131 pathway dose factor (1.67E12m mrem /yr per uCi/sec). By this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated. For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used: RI-131

• [;Oi 3.17E-8 W

Dmax = l l Wheret l l Dmax = maximum organ dose (mrom) l W atmospheric dispersion parameter to tha = l controlling location (s) as identified in Table l 2-3. Atmospheric dispersion for inhalation pathway and l X/O = 3 l H-3 dose contribution via other pathways (sec/m ) l l r5 l b l l l D-2 Rev. 8 l

Hopo Crock ODCM 7/29/87 l j I l D/O atmospheric disposition for vegetation, milk and = i ground plane exposure pathways (m-2) 1 ] Qi cumulative role. e over the period of interest for l a j radioiodines and particulates (uci) l ] 3.17E-8= conversion factor (yr/sec) 4 1 RI-131 = I-131 dose parameter for the thyroid for the l identified controlling pathway i i 1.675E12, infant thyroid dose parameter with the = 2 cow - milk - grass pathway controlling (m mrem /yr j j per uCi/sec) I 1 The ground plane exposure and inhalation pathways need not be j considered when the above simplified calculational method is used because of the overall negligible contribution of these pathways l ] to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground J exposure pathway may represent a higher dose contribution than J either the vegetation or milk pathway. However, use of the I-131 l l thyroid dose parameter for all radionuclides will maximize the j organ dose calculation, especially considering that no other l radionuclides has a higher dose p rameter for any organ via any l I 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 Hope Creek as identified by the annual ( j land-use census (Technical Specification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling i j pathways as identified in Table 2-3. [ a i l l r i f i i I i t I f i O i l l l l D-3 Rev. 8 L i

Hop 3 Crcok ODCM 7/29/87 l GV TABLE D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass - Cow - Milk Ground Plane l Total Body 0.02 0.15 Bone 0.23 0.14 Liver 0.09 0.15 Thyroid 0.59 0.15 l l Kidney 0.02 0.15 l l Lung 0.01 0.14 l l GI-LLI 0.02 0.15 l l l l TABLE D-2 Fraction of Dose Contribution by Pathway Pathway f Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation l I () 1 l D-4 Rev 8 l

Hope Creek ODCM S/17/88 i I l l l 4 i 1 fj APPENDIX E ) l i f RADIOt4GICAL ENVIItONNENTAL 9tDNITORIIOG PROGRAM - i SAMPLE TYPE,14 CATION AND ANALYSIS 1 O l 1 l l I 1 l l [ i O 1 i t E-1 Rev. 9

L i Hopo Crook ODCM 5/17/80 i APPENDIX E i SAMPLE DESIGNATION i i Samples are identified by a three part code. The first two l letters are the power station identitication code, in this case 1 "SA". The next three letters are for the media sampled. ( I AIO = Air Iodine IDM = Immersion Dose (TLD) j APT = Air Particulates MLK = Milk t ECH = Hard Shell Blue Crab PWR = Potable Water (Haw) ESF = Edible Fish PWT = Potable Water (Treated) ESS = Sediment RWA = Rain Water (Precipitation) FPB = Beef SWA = Surface Water FPL = Green Leafy Vegetables VGT = Fodder Crops (Various) ( FPV = Vegetable (Various) WWA = Well Water j GAM = Game i j The last f our symbols are a location code based on direction and i diatance from the site. Of these, the first two represent each i of the sixteen angular sectors of 22.5 degrees centered about the i reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, t i 3=NE, 4=ENG, etc. The next digit is a letter which represents j the radial distance from the plants l S = on-site location E = 4-5 miles off-site A = 0-1 niles off-site F = 5-10 miles off-site [ 8= l-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = >20 miles off-site l D = 3-4 miles off-site i The last number is the station numerical designation within eah J sector and zone; e.g., 1,2,3,... For example, the designation SA-WWA-fiD1 would indicate a sample in the SGS program (SA), i l consisting of well water (WWA), which had been collected in j j sector aumber 5, centered et 90' (due east) with respect to the i reactor site at a radial distance ot 3 to 4 miles ott-site, l (theretore, radial distance D). The number 1 indicates that this is sampling station el in that particular sector. 1 l i I l E-2 Rev. 9 1 l l

i j Hopo Creek ODCM 5/17/88 l l SAMPLING IDCATIONS 1 l All sampling locations and specific information about the individual locations are given in Table E. Maps E-1 and E-2 show the locations of sampling stations with respect to the site. l TABLE E-1 i STATION [ CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent IDM j r 3S3 700 ft. NNE of venti fresh water holding WWA l tank [ l 5S1 1.0 ml. E of vent; site access road AIO, APT,IDM t 6S2 0.2 mi. ESE of vents observation building IDM 7sl 0.12 mi. SE of vents station personnel gate IDM l 10S1 0.14 mi. SSW of vent; site shoreline IDM i 1181 0.09 mi. SW ot vents site shoreline IDM 11A1 0.2 mi. W of vent; outfall area ECH, ESP,ESS, l SWA i 15Al 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line { 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line i 12Cl 2.5 mi. WSW of vent; west bank of Delawa re ECH,ESF,ESS, River SWA 4D2 3.7 mi, ENE of vent Alloway Creek Neck RoaC IDM 5D1 3.5 mi. E of vent; local farm AIO, APT,IDM, WWA 1001 3.9 mi. SSW of vent: Taylor's Bridge Spur IDM 11D1 3.5 mi. SW of vent GAM 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of venti local farm IDM O E-3 Rev. 9

Hopo Crcok ODCM 5/17/80 TABLE E-1 (Cont'd) STATION a CODE STATION LOCATION SAMPLE TYPES 3El 4.1 mi. NE of vent; local farm FP8,FPV, GAM, IDM,VGT,WWA l 3E2 5.7 mi. NE of vent; local farm FPV i 7El 4.5 mi. SE of vent; 1 mi. W of Man Horse ESF,ESS,SWA . { Creek 9El 4.2 mi. S of vent IDM j llE2 5.0 mi. SW of vent IDM l 12El 4.4 mi. WSW of vent; Thomas Landing IDM j 13El 4.2 mi. W of vent; Diehl House Lab IDM i l 13E3 4.9 mi. W of vent; local farm VGT i l 16El 4.1 mi. NNW of vent; Port Penn AIO, APT,IDM l I 1F1 5.6 mi. N of vent; Fort Elfaborg AIO, APT,IDM i IF2 7.1 mi. N of vent; midpoint of Delaware River SWA [ ] t 1F3 5.9 mi. N of vent; local farm FPL,FPV I 2F2 8.7 mi. NNE of vent; Salem Substation AIO, APT,IDM, 1 RWA l 1 2F3 8.0 mi. NNE of vent Salem Water Company PWR, PWI 2F4 6.3 mi. NNE of vent; local farm FPV f 2F5 7.4 mi. NNE of vent; Salem High School IDM ) 2F6 7.3 mi. NNE of vent; Southern Training IDM Center ) 2F7 5.7 mi. NNE of vent; local farm MLK,VGT 1 ) 3F2 5.1 mi. NE of vent; Hancocks Bridge IDM Municipal Building l i 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5F1 6.5 mi. E of vent FPV,IDM l E-4 Rev. 9

l l Hope Creek ODCM 5/17/88 TABLE E-1 (Cont'd) STATION j i CODE STATION LUCATIUN SAMPLE TYPES SF2 7.0 mi. E of vent; local farm VGT 1 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM j l 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM l l l 10F2 5.8 mi. SSW of vent IDM i llF1 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM [ 11F3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT j 12F1 v.4 mi. WSW of vent: Townsend Elementary IDM [ School 13F2 6.5 mi. W of vent; odessa, Delaware IDM 13F3 9.3 mi. W of vent Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14F1 5.5 mi. WNW of vent; local f arm MLK,VGT 14F2 6.6 mi. WNW of vent: Boyds Corner IDM l 14F3 5.4 mi. WNW of vent; local tarm FPV t i 15F3 5.4 mi. NW of vent IDM 16F1 6.9 mi. NNW of vent: C&D Canal ESS,SWA [ 16F2 8.1 mi. NNW of vents Delaware City Public IDM School { 1G1 10.3 mi. of N of vents local farm FPV IG3 19 mi. N of vent Wilmington, Delaware IDM i 2G1 12 mi. NNE of vent Mannington Township, NJ FPV 3G1 17 mi. NE of vent; local farm IDM,MLK,VGT 10G1 12 mi. SSW of vent Smyrna, Delaware IDM i l E-5 Rev. 9

Hopo Crook ODCM 5/17/88 TABLE E-1 (Cont'd) i STATION i CODE STATION LOCATION SAMPLE TYPES i 16G1 15 mi. NNW of vent; Greater Wilmington IDM l Airport l 3H1 32 L.i. NE of vent; National Park, New Jersey IDM j 3H3 110 mi. Ne of vent; Research and Testing AIO, APT,IDM k Labora tory [ l 3H5 25 mi. NE of vent; local farm FPL,FPV l i i l t l l l i I ()) i e-. l \\

Hopo Crook ODCM 5/17/60 ( ) SAMPLE COLLECTION AND ANALYSIS L; Sample Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change. be performed if gross beta exceeds 10 times the yearly mean ot the control station value. As well one sample is analyzed >24 hrs after sampling to allow for radon and thoron daughter decay. Gamma isotopic analysis on quarterly composites. Air Iodine A TEDA impregnated Iodine 131 analysis /~ charcoal cartridge is are performed on k_,3/ connected to air each weekly sample. particulated air sampler and is collected weekly at tilter change. Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and f rozen portion on collection semi-annually or when in season. Sediment A sediment sample is Gamma isotopic taken semi-annually, analysts semi-annually. Direct 2 TLD's will be Gamma dose quarterly collected from each location quarterly. 1 Milk Sample of tresh milk Gamma isotopic l is collected for each analysts and I-131 farm semi-monthly when analysis on each cows are in pasture, sample on collection. monthly at other times. O v_s \\ l E-7 Rev. 9 l l

Hope Creek ODCM 5/17/88 o(v) SAMPLE COLLECTION AND ANALYSIS (Cont'd) Sample Collection Method Analysis Water (Rain, Sample to be collected Gamma isotopic Potable, Surtace) monthly providing winter monthly H-J on icing conditions allow. quarterly surface sample, monthly oa ground water samp.s. u 1 () E-8 Rev. 9

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FIGURE E-2 Ot1 SITE SAMPLIEG LOCATIO11S O A su . g " '"' { e r * ** g f. 88 88' w 8 C { e, n i ' b f ~ sJ x !y l ' k;g x 5 ,a t Nf% k o h s. y ; 11 {o 1 C e [ A \\ ypf t n,, % ' Q I D % s / f1 ay 1Js. r 4x 7.~ m3)g t r 1 t',I-lu iq1, ni; 7 1 eA i ( "T/ gli o i A p I, s i 'It /" g- 'i g e g9 /E ,,, u o ,, o e K .i ROV. 9 5/17/88 -.}}