ML20137N784

Rev 2 to Offsite Dose Calculation Manual

ML20137N784
Person / Time
Site:	Hope Creek
Issue date:	01/31/1986
From:	Public Service Enterprise Group
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ML20137N782	List: ML20137N776 ML20137N784
References
PROC-860131, NUDOCS 8602040247
Download: ML20137N784 (126)

Text

. - - . ..

OFFSITE DOSE CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION Revision 2 JANUARY, 1986 l

r l

l 9602040247 860131 PDR ADOCK0500g4 A

l - - - _ _ _ ____ __ _ - . _

LIST OF EFFECTIVE PAGES Dates of original and revised pages are:

Revision 0 -- April, 1985 Revision 1 -- December, 1985 Revision 2 -- January, 1986 .

Page Numbers Revision # Page Numbers Revision i Title 2 4.0 4.0-8 1 1 - ii 1 4.0-9' 2 iii - iv 2 .

4.0 4.0-17 1 v 1 5.0 5.0-9 1 1.0-1 1 2.0 2.0-28 1 3.0 3.0-3 1 3.0-4 2 -

3.0 3.0-11 1 3.0 3.0-13 2 3.0 3.0-42 1 3.0-43 2 3.0 3.0-47 1 3.0-47a - 3.0-48 2 3.0-49 . 1 3.0-50 2 3.0-51 1 3.0 3.0-52e 2 3.0 3.0-56 1 i

l m

TABLE OF CONTENTS Page List of Tables iii List of Figures iv References v

1.0 INTRODUCTION

1.0-1 2.0 LIQUID EFFLUENTS 2.0-1 2.1 Liquid Effluent Monitor Setpoint Calculations 2.0-1 2.1.1 Liquid Radwaste Discharge Line Monitor 2.0-2 2.1.1.1 Releases of Single Liquid Radwaste Streams 2.0-3 2.1.1.2 Simultaneous Releases of Liquid Radwaste Streams 2.0-11

2.1.2 Cooling Tower Blowdown Line Effluent Monitor 2.0-12 2.2 Liquid Effluent Dose Calculations 2.0-15 2.3 Definitions of Liquid Effluent Terms 2.0-24 3.0 GASEOUS EFFLUENTS 3.0-1 3.1 Gaseous Effluent Monitor Setpoint Calculations 3.0-1 3.1.1 Normal Setpoint Method 3.0-2 3.1.2 Startup Setpoint Method 3.0-5 3.2 Gaseous Effluent Dose Calculations 3.0-8

. 3.2.1 Site Boundary Dose 3.0-8 3.2.2 Air Dose 3.0-10 3.2.3 Dose to a Member of the Public 3.0-11 3.3 Meteorological Model 3.0-48 3.4 Definitions of Gaseous Effluents Terms 3.0-53 i -

Rev. 1, 11/85 L

TABLE OF CONTENTS (continued)

Page 4.0 SPECIAL DOSE CALCULATIONS 4.0-1 4.1 Necessity of Operating Effluent Treatment Systems 4.0-1 4.1.1 Liquid Radwaste Treatment System 4.0-1 4.1.2 Ventilation Exhaust Treatment System 4.0-3 4.1.3 Gaseous Radwaste Treatment System 4.0-4 4.2 Totai Fuel Cycle Dose 4.0-8 4.3 Initial Evaluation of Unplanned Gaseous -

Releases 4.0-9 4.4 Dose to a Member of the Public Due to .'

Activities Inside the Site Boundary 4.0-17 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.0-1 5.1 Sampling Program 5.0-1 5.2 Inte-. laboratory Comparison Program 5.0-13

/

11 Rev. 1, 11/85

LIST OF TABLES Number Title Page 2.1-1 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 2.0-13 2.1-2 Maximum Discharge Capacity of Liquid Radwaste Streams for the Hope Creek Generating Station 2.0-14 2.2-1 Site Related Ingestion Dose Commitment Eactor, A 2.0-19 it 2.2-2 Bioaccumulation Factors 2.0-21 2.2-3 Adult Ingestion Dose Factors 2.0-22 3.1-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 3.0-7 3.2-1 Pathway Dose Factors for Section 3.2.1.b (P io) 3.0-14 3.2-2 Pathway Dose Factors for Section 3.2.3 (R ijo) 3.0-22 3.2-3 Parameters Used in Dose Factor Calculations 3.0-44 3.2-4 Controlling Receptors, Locations, and 3.0-47a Pathways 3.2-5 Atmospheric Dispersion Parameters for 3.0-47c Controlling Receptor Locations 4.3-1 Infar.t Pathway Dose Factors for Section 4.3 (R ij) 4.0-10 4.'-2 3 Child Pathway Dose Factors for Section 4.3 (R ij) 4.0-13 5.0-1 Radiological Environmental Monitoring Program 5.0-2 iii Rev. 2, 1/86

LIST OF FIGURES Number Title Page 3.3-1 Plume Depletion Effect for 3.0-52c Ground-Level Releases 3.3-2 Vertical Standard Deviation of Material 3.0-52d Concentration in a Plume 3.3-3 Relative Deposition for Ground-Level 3.0-52e Releases 4.1-1 Liquid Radwaste Treatment System 4.0-5 4.1-2 Ventilation Exhaust Treatment System 4.0-6 ,

4.1-3 Gaseous Radwaste Treatment System 4.0-7 5.1-1 Onsite Sampling Locations, Artificial Island 5.0-11 5.1-2 Offsite Sampling Locations, Artificial Island 5.0-12 iv Rev. 2, 1/86

REFERENCES The following documents are referred to by number in the text of this Manual.

1. Radiological Effluent Technical Specifications, Hope Creek Generating Station, Draft, March 1985.

2. Final Safety Analysis Report, Hope Creek Generating Station, updated through Amendment 9.

3. Applicant's Environmental Report - Operating License Stage, Hope Creek Generating Station, updated through Amendment 4.

4. U. S. Nuclear Regulatory Commission, " Calculation of Annual Doses'to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Regulatory Guide 1.109, Revision 1, 1977. _

5. U. S. Nuclear Regulatory Commission, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Cffluents in Routine Releases from Light-Water-Cooled Reactors,"

Regulatory Guide 1.111, Revision 1, 1977.

6. U. S. Nuclear Regulatory Commission, " Preparation of Radio-logical Effluent Technical Specifications for Nuclear Power Plancs," USNRC Rept. NUREG-0133, 1978.

7. " Artificial Island Radiological Environmental Monitoring Program - 1983 Radiological Report," Public Service Electric and Gas Company, March 1984.

8. U. S. Nuclear Regulatory Commission, " Final Environmental Statement Related to the Operation of the Hope Creek Generating Station," USNRC Rept. NUREG-1074, 1984.

9. Lawrence Radiation Laboratory, " Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Rept. UCRL-50564, Rev. 1, 1972.

v Rev. 1, 11/85

Section 1.0  !

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS. As such the ODCM describes the inethodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents, and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.

The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Schematic configurations of liquid and gaseous radwaste effluent systems are also included. -

The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calcu-lations. Changes in the calculational methods or parameters will be incorpor'ated into the ODCM in order eo assure that the ODCM represents the present methodology in all applicable areas.

Computer software to perform the described calculations will be maintained current with the ODCM.

1.0-1 Rev. 1, 11/85

Section 2.0 LIQUID EFFLUENTS The Hope Creek Generating Station is located on the Delaware River which supplies service make-up water to the Cooling Tower Basin and receives water from the Cooling Tower Blowdown Line.

All releases from the liquid waste management system are made to the Liquid Radwaste Discharge Line which releases into the Cooling Tower Blowdown Line for dilution prior to discharge to the Delaware River.

2.1 LIQUID EFFLUENT MONITOR SETPOINT CALCULATIONS ,

Technical Specification 3.3.7.10 states, in part:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specifica. tion 3.11.1.1 are not exceeded.

The limits for radioactive liquid effluents presented below are as stated in Specification 3.11.1.1:

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified'in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gaser, the concentration shall be limited as shown in Table 3.11-1 (of RETS). [RETS Table 3.11-1 is included as Table 2.1-1 of the ODCM.]

The two liquid ef fluent monitors listed in Technical Specifi-cation Table 3.3.7.10-1 are the following:

RE4861 - Liquid Radwaste Discharge Line Monitor i

RE8817 - Cooling Tower Blowdown Effluent Line Monitor 2.0-1 Rev. 1, 11/85

The methodology of this section applies to setpoints for these two montiors. The setpoints calculated according to this section are regarded as upper bounds for the actual monitor setpoints. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value.

The actual monitor setpoint, which corresponds to the calculated concentration plus background for the specific monitor, is determined from calibration data or from operational data associated with. liquid sample analysis data.

For the hurpose of satisfying Technical Specification 3.3.7.10, the setpoints of each of the two station liquid effluent line monitors shall be established according to the met.hodology presented for each monitor below.

2.1.1 Liquid Radwaste Discharge Line Monitor - RE4861 The liquid radwaste discharge line monitor provides alarm and automatic termination of release functions prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification, the alarm / trip setpoints for the liquid radwaste discharge monitor and flow measurement devices are set to assure that the following equation is satisfied:

1 l

cf < C MPC (2-1) l F+f l

l where:

CMPC = the effluent concentration limit (Specification l 3.11.1.1) implementing 10CFR20 for the site, corresponding to the specific mix of radio-nuclides in the ef fluent stream being considered for discharge [uci/ml].

l 2.0-2 Rev. 1, 11/85 l

c = the setpoint [uci/ml] of the radioactivity monitor measuring the radioactivity concen-tration in the effluent line prior to dilution and subsequent release; the setpoint represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area.

f = the flow setpoint as determined at the radiation monitor location, in volume per unit time, but in the same units as F, below.

F = the dilution water flow setpoint as determined prior to the release point, in volume per ,,

unit time.

2.1.1.1 Releases of Single Liquid Radwaste Streams At the Hope Creek Generating Station, the Liquid Waste Sample Tanks, the Floor Drain Sample Tanks, the Detergent Drain Tanks, and the Condensate Storage Tanks all discharge to the Liquid Radwaste Discharge Line.

The effluent in the Liquid Radwaste Discharge Line is monitored prior to discharge into the Cooling Tower Blowdown Line to the Delaware River. The Cooling Tower Blowdown Line furnishes the dilution flow (F). The waste effluent flow (f) and the monitor setpoint (c) for the Liquid Radwaste Discharge Line Monitor-are determined and set to meet the conditions of equation (2-1) for a given effluent concentration, C. The method by 2.0-3 Rev. 1, 11/85

which this is accomplished is as follows:

Step 1) The potential liquid radwaste streams at the Hope Creek Generating Station are the following:

a) Waste Sample Tanks b) Floor Drain Sample Tanks c) Detergent Drain Tanks d) Condensate Storage Tank A sample is obtained from the tank (s) planned for discharge into the Liquid Radwaste Discharge Line.

s Step 2) The radionuclide concentration for a liquid waste tank to be released is obtained from the sum of measured concentrations as determined by the analyses required in RETS Table 4.11-1:

C f= C g

+ ( C, + C, + Cg+Ct i - g -

where:

Cg = the concentration of each measured gamma emitter observed by gamma-ray spectroscopy of each waste sample

[uci/ml].

l l

Ca = the concentration of alpha emitters l

in liquid waste as measured in the most recent QUARTERLY composite sample for the tank under consideration

[uCi/ml]. (NOTE: Sample is analyzed for gross alpha.)

2.0-4 Rev. 1, 11/85

Cs = t hee measured concentrations of Sr-39 and Sr-90 in liquid waste as observed in the most recent QUARTERLY composite sample for the tank under consideration

[uci/ml].

Cg = the measured concentration of re-55 in liquid waste as observed in the most recent QUARTERLY composite sanple for the tank under consideration

[uci/ml]. .

Ct = the measured concentration of .

H-3 in liquid waste as determined ,

from analysis of the most recent QUARTERLY composite sample for the tank under consideration [uci/ml]. i A new Cg term will be included in the analysis of each batch. Rissults from the most current QUARTERLY composite will comprise values used in the terms for alpha, strontiums, iron, and tritium.

Step 3) The measured radionuclide concentrations are used to calculate a Dilution Factor, DF, which is the ratio of total dilution flow rate to tank flow rate required to assure that the limiting concentrations of 10CFR20, Appendix B, Table II, Column 2 are met at the point of discharge to the Delaware River.

2.0-5 Rev. 1, 11/85

S, r(MP:: )

B, =

i C Ca C3 Cg Ct

, g

+

+ + + -- S F MPC g MPC a MPC s MPCg MPC t

~

9 where:

Ci =

the measured concentration of Cg,C ae C Cf and Ct as defined in Step 2.

3, MPC= MPC g, MPC a, MPC s, MPCg, and MPCt are limiting concentrations of the appropriate ,

r a d i'o n u c l i d e s from 10CFR20, Appendix B, Table II, Column 2. For dissolved .

or entrained noble gases, the concentra-tion shall be limited to the specific MPC values presented in Table 2.1-1.

. SF = the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurements.

The actual value to be used for the safety factor will be determined in implementing procedures.(For example, SF = 0.5 corresponds to a 100 percent variation.)

Step 4) The dilution flow rate setpoint for minimum dilution flow rate, Ed, is established at ninety percent of the expected dilution flow rate:

Fd =(0.9) X (Expected Cooling Tower Blowdown Line Flow Rate) 2.0-6 Rev. 1, 11/85

NOTE: If radioactivity from plant operations accumulates in the Cooling Tower Blowdown Basin such that measurable quantities of radionuclides are detected in the Cooling Tower Blowdown Basin, calculations of Fd must include a term to account for radioactivity present in the dilution stream prior to the introduction of the liquid waste tank effluent:

F d' =(Fd) X (1 - MPC fraction of th'e Cooling Tower Blowdown).

Step 5) For the case DF<1, the liquid waste tank effluent concentration meets the limits of 10CFR20 without dilution, and effluent discharge flow rate may be assigned any desired value. For DF>l, the setpoint for the maximum permissible effluent discharge flow rate, fe, must be calculated:

f, =F * " #

d t d d t DP Df where:

fe = maximum permissible effluent discharge flow rate (i.e., for effluent discharging through the Liquid Radwaste Discharge Line into the Cooling Tower Blowdown Line).

2.0-7 Rev. 1, 11/85

F d = the dilution flow rate setpoint from Step 4.

f t = the expected flow rate of liquid waste tank discharge. (This value will have an upper limit of the maximum discharge capacity of the particular liquid waste tank pump (s).) The maximum discharge capacities for the liquid waste tanks at HCGS are presented in Table 2.1-2.

DF = Dilution Factor from Step 3.

Step 6) The liquid radwaste effluent radiation monitor setpoint may now be determined based on the values of C i, f, and Fd which were specified to provide compliance with the limits of 10 CFR20, Appendix B, Table II, Column 2. The monitor response is primairly to gamma radiation; therefore, the actual.

setpoint is based on C The monitor g.

setpoint which corresponds to the particular setpoint concentration, c, is determined based on monitor calibration data or on operational data which correlates monitor response to sample analyses associated with actual effluent releases.

The setpoint concentration, c [uci/ml], is determined as follows:

c=A C g [uCi/ml]

9 2.0-8 Rev. 1, 11/85

where:

[ C g' = the sum of the concentrations of all measured 9 gamma emitters as determined in Step 2.

A = Adjustment factor which will allow the setpoint to be established in a practical manner for conve-nience and to prevent spurious alarms. So as to alarm should an inadvertent release occur, A is not to exceed 20.

f A

= e (See Note 2 below.) -

f t

~

where:

f e = maximum permissible effluent discharge flow rate determined according to Step 5 above,

^

f t = the expected flow rate of liquid waste tank discharge from Step 5 above.

l If A > 1, Calculate c and determine the maximum value for the actual monitor setpoint.

-If A < 1, Release may not be made as planned. Re-evaluate Steps 3,4, and 5.

i NOTE 1: The co cubced setpoint concentration, t

c, establishes the base value for the monitor setpoint. However, in establishing the actual

monitor setpoint for a particular monitor, background radiation levels must be considered. Normally, 2.0-9 Rev. 1, 11/85

the actual monitor setpoint includes the calculated setpoint value plus background. Background levels must be controlled such that radioactivity levels in the effluent stream being monitored can be accurately assessed at or below the calculated setpoint value.

NOTE 2: If DF<1, then A = (1/DF), not to exceed A = 20.

If calculated setpoint values are near actual concen-trations planned for release, it may be impractical to set the monitor alarm based on this value. In i:his case a new setpoint may be calculated by decreasing the effluent flow, increasing the dilution flow, or by decreasing Ci by further processing of the liquid radwaste planned for release, and by following the methodology presented in Steps 3, 4, and 5.

If no discharge is planned for this pathway, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.

2.0-10 Rev. 1, 11/85

2.1.1.2 Simultaneous Releases of Liquid Radwaste Streams If two or more liquid waste tanks (or liquid waste streams) are to be released simultaneously, then the Liquid Radwaste Discharge Line Radiation Monitor setpoint is determined as follows:

Step A) Perform Step 3 f rom Section 2.1.1.1 separately f or each liquid waste tank, solving the equation for DF using the values in the concentration term from the sample analyses of each liquid waste stream to be discharged -

simultaneously. (DF 1) = DF for Tank 1, (DF2) = DF for Tank 2, ... ~

Step B) Determine DF', which is the greatest value for DF selected from DF y, DP 2, DF 3 ... determined in Step A above. Use DF' in the determination Of f e in Step E below.

Step C) Determine f s, which is the sum of the expected flow rates for all waste tanks releasing simultaneously. Use f s in the determination Of fe in Step E below.

i f =

s ft1 + ft2 + ft3 Step D) Perform Step 4 of Section 2.1.1.1.

Step E) Perform Step 5 of Section 2.1.1.1, where f t = fs as determined in Step C above; DF = DF' as determined in Step B above; and where all other terms in Step 5 are as previously defined.

2.0-11 Rev. 1, 11/85

NOTE: If f, < f 3, Simultaneous releases may not be made as planned; Re-evaluate Sceps A, B, C and D.

If f e > f 3, Then individual tanks may be released at expected flow rates; proceed to Step F to determine the actual monitor setpoint.

Step F) Perfo~rm Step 6 of Section 2.1.1.1 to determine the monitor setpoint, where ft " fs sa determined in Step C above; and where the v'alue for bg Cg is the highest value for any of the ~

tanks releasing simultaneously.

~

2.1.2 Cooling Tower Blowdown Line Effluent Monitor (RE8817)

The Cooling Tower Blowdown Line is the blowdown line to the Delaware River, and it provides dilution for the liduid radwaste discharges. The radiation monitor has no control function, but serves as support (backup) for the Liquid Radwaste Discharge Line Monitor. The Cooling Tower Blowdown Line Effluent Monitor setpoint is established as follows:

C *

(b g

Cg) DF [uCi/ml]

where bg Cg and DF have values as determined in Section 2.1.1 Step 2 and Step 3 respectively for the liquid radwaste sample tank (s) planned for release.

(For practicality, for this monitor only, if DF is determined to be'< 1, DF may be set equal to 1 for the purpose of calculating the monitor setpoint.)

2.0-12 Rev. 1, 11/85

i l

Table 2.1-1 MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC (uCi/ml)

Kr 85m 2E-4 Kr 85 SE-4 Kr 87 4E-5 Kr 88 9E-5 Ar 41 7E-5 Xe 133m SE-4 Xe 133 6E-4 Xe 135m 2E-4 Xe 135 2E-4

• -- From Table 3.11-1 of Reference 1.

2.0-13 Rev. 1, 11/85

Table 2.1-2 MAXIMUM DISCHARGE CAPACITY OF LIQUID RADWASTE STREAMS FOR THE HOPE CREEK GENERATING STATION Maximum Discharge Capacity Liquid Radwaste Stream Flow Rate (GPM)

1. Waste Sample Tanks 176

2. Floor Drain Sample Tanks 176 *

3. Detergent Drain Tanks 25

• 4.

~

Condensate Storage Tanks 1300 +

t 1

i

• -- Section 11.2.3, Ref. 2.

+ -- Chapter 9, Ref. 2.

2.0-14 Rev. 1, 11/85 1

2.2 LIQUID EFFLUENT DOSE CALCULATIONS Technical Specification 3.11.1.2 states, in part:

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited:

a. During any ca'lendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or

~

equal to 10 mress to any organ.

There is no potable water pathway for liquids from HCGS. Thus, for 1,iquid dose calculations, only the fish and invertebrate consumption pathways are applicable (Ref. 2, Section 11.2.4).

The methodology by which dose computations shall be performed .

for the purpose of demonstrating compliance with this Technical Specification is presented below.

The dose contribution to an exposed individual by way of fish and invertebrate consumption from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expression:

I m

D t

^it 1 il 1 i l=1

'where:

Dt = the cumulative dose commitment to the total body or any orga1 t, due to radioactivity in liquid effluents for the total time period m

6, Section 4.3).

{At1 ^ [ mrem] (Ref.

l=1 2.0-15 Rev. 1, 11/85

_. .~ _ ._ - . _. _ _ _ _ _ _ - _ . - -

Atl = the length of the lth time period over which C il and F 1 are averaged for all liquid releases, [ hours].

Cil = the average concentration of radionuclide i, in undiluted liquid effluent during time period Atl from any liquid release [uCi/ml].

F1 = the near field average dilution factor for Cil during any liquid effluent release [ unit-less). Defined as the ratio of the undiluted liquid waste flow during release to the product of the average flow from the discharge structure to unrestricted receiving water times Z. .

F = (average undiluted liquid waste flow) 1 (average flow from the discharge structure during periods of radioactive materials release) *

(Z)

NOTE: The denominator is limited to 1000 cfs (448,000 gpm) or less. (Ref. 6, Section 4.3)

NOTE: If radioactivity in the Cooling Tower Blowdown Line becomes > LLD, prior to the junction with the Liquid Radwaste Effluent Line, that concentration must be included in the l dose determination. For this part of the dose calculation, F 1 = 1/Z and Atl = the entire time period for which the dose is being calculated.

Z = 10 , which is the applicable dilution factor for the receiving water body at the Hope Creek Generating Station, (Ref. 2, Chapter 11).

l '

2.0-16 Rev. 1, 11/85

Ait= the site related fish and invertebrate consumption dose commitment factor to the total body or any organ t for each identified principal gamma and beta emitter listed in Table 2.2-1 [ mrem /hr per uCi/ml].

Alt = Ko (Up . BFi} +(UI

• BI i) ,

DFi where Ko = Units conversion factor, 1.14 E+5' 8760

= 1 E+6 pCi

• 1 E+3 ml + hr uCi 1 yr UF = Adult fish consumption (21 kg/yr).

BFi= Bioaccumulation factor for radionuclide i, in fish, [pci/kg per pCi/l], from Table 2.2-2. The more conservative of salt and fresh water values for radionuclide i is incorporated into Table 2.2-2 for use in the liquid dose calculations (Ref. 4, Table A-1).

UI = Adult invertebrate consumption (5 kg/yr).

BIi= Bioaccumulation factor for radionuclide i, in invertebrates [pci/kg per pCi/l],

from Table 2.2-2. The more conservative of salt and fresh water values for radionuclide i is incorpotated into Table 2.2-2 for use in the' liquid dose calculations (Ref. 4, Table A-l').

, 2.0-17 Rev. 1, 11/85

t

.s L

Dri= Dose conversion factor for radionuclide i ,

i for adults in preselected organ t [meem/pci]

from Table 2.2-3 (Ref. 4, Table E-ll).

1 4

L

)

i, f

i l

l 1

1 ,

)

i t ,

E i

(

.l i

) , 2.0-18 Rev. 1, 11/85 i

f i

• e , y r -w , . .-r.,.-,e,g-m%,w-,--w, ,y,%,.,.&w-- ,-c-#.,,.mweww,--m---+ -w,--w--ny,-~w-+--*v-==-

l l

Table 2.2-1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A g (FISH AND INVERTEBRATE CONSUMPTION)

(mrem /hr per uCi/ml)

Page 1 of 2 HUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 C-14 4.60E+04 9.20E+03 9.20E+03 9.20E+03 9.20E+03 9.20E+03 9.20E+03 Ha-24 6.01E+02 6.01E+02 6.01E+02 6.01E+02 0.01E+02 6.01E+02 6.01E+02 P-32 4.95E+07 3.08E+06 1.91E+06 0.00E+00 0.00E+00 0.00E+00 5.57E+06 Cr-51 0.00E+00 0.00E+00 5.58E+00 3.34E+00 1.23E+00 7.40E+00 1.40E+03 Mn-54 0.00E+00 2.40E+05 4.59E+04 0.00E+00 7.16E+04 0.00E+00 7.37E+05 Mn-56 0.00E+00 6.05E+03 1'.07E+03 0.00E+00 7.68E+03 0.00E+00 1.93E+05 Fe-55 5.11E+04 3.53E+04 8.23E+03 0.00E+00 0.00E+00 1.97E+04 2.03E+04 Fe-59 8.06E+04 1.90E+05 7.27E+04 0.00E+00 0.00E+00 5.30E+04 6.32E+05 Co-58 0.00E+00 6.03E+02 1.35E+03 0.00E+00 0.00E+00 0.00E+00 1.22E+04 Co-60 0,00E+00 1.73E+03 3.82E.+03 0.00E+00 0.00E+00 0.00E+00 3.25E+04 Nt-63 4.96E+04 3.44E+03 1.67E+03 0.00E+00 0.00E+00 0.00E+00 7.18E+02 Hi-65 2.02E+02 2.62E+01 1.20E+01 0.00E+00 0.00E+00 0.00E+00 6.65E+02 Cu-64 0.00E+00 2.14E+02 1.01E+02 0.00E+00 5.40E+02 0.00E+00 1.83E+04 -

2n-65 1.61E+05 5.13E+05 2.32E+05 0.00E+00 3.43E+05 0.00E+00 3.23E+05 In-69 3.43E+02 6.56E+02 4.56E+01 0.00E+00 4.26E+02 0.00E+00 9.85E+01 Br-83 0.00E+00 0.00E+00 4.80E+01 0.00E+00 0.00E+00 0.00E+00 6.91E+01 Br-84 0.00E+00 0.00E+00 6.22E+01 0.00E+00 0.00E+00 0.00E+00 4.88E-04 Br-85 0.00E+00 0.00E+00 2.55E+00 0.00E+00 0.00E+00 0.00E+00 1.19E-15 Rb-86 0.00E+00 J.13E+05 5.27E+04 0.00E+00 0.00E+00 0.00E+00 2.23E+04

.76-63 0.00E+00 3.24E+02 1.72E+02 0.00E+00 0.00E+00 0.00E+00 4.48E-09 Rb-89 0.00E+00 2.15E+02 1.51E+02 0.00E+00 0.00E+00 0.00E+00 1.25E-11 Sr-89 3.97E+04 0.00E+00 1.14E+03 0.00E+00 0.00E+00 0.00E+00 6.36E+03 Sr-90 9.76E+05 0.00E+00 2.40E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+04 Sr-91 7.30E+02 0.00E+00 2.95E+01 0.00E+00 0.00E+00 0.00E+00 3.48E+03 Sr-92 2.77E+02 0.00E+00 1.20E+01 0.00E+00 0.00E+00 0.00E+00 5.49E+03 Y-90 6.06E+00 0.00E+00 1.63E-01 0.00E+00 0.00E+00 0.00E+00 6.42E+04 Y-91m 5.73E-02 0.00E+00 2.22E-03 0.00E+00 0.00E+00 0.00E+00 1.68E-01 Y-91 8.88E+01 0.00E+00 2.37E+00 0.00E+00 0.00E+00 0.00E+00 4.89E+04 Y-92 5.32E-01 0.00E+00 1.56E-02 0.00E+00 0.00E+00 0.00E+00 9.32E+03 Y-93 1.69E+00 0.00E+00 4.66E-02 0.00E+00 0.00E+00 0.00E+00 5.35E+0+

Zr-95 1.59E+01 5.11E+00 3.46E+00 0.00E+00 8.02E+00 0.00E+00 1.62E+04 Zr-97 8.81E-01 1.78E-01 8.13E-02 0.00E+00 2.68E-01 0.00E+00 5.51E+04 Hb-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Mo-99 0.00E+00 1.28E+02 2.43E+01 0.00E+00 2.89E+02 0.00E+00 2.96E+02 Tc-99m 1.59E-02 4.50E-02 5.73E-01 0.00E+00 6.83E-01 2.20E-02 2.66E+01 Tc-101 1.64E-02 2.36E-02 2.31E-01 0.00E+00 4.24E-01 1.20E-02 7.09E-14 Ru-103 1.10E+02 0.00E+00 4.73E+01 0.00E+00 4.19E+02 0.00E+00 1.28E+04 Ru-105 9.15E+00 0.00E+00 3.61E+00 0.00E+00 1.18E+02 0.00E+00 5.59E+03 2.0-19 Rev. 1, 11/85 1 _

Table 2.2-1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A.

1 (FISH AND INVERTEBRATE CONSUMPTION)

(mrem /hr per uCi/ml)

Page 2 of 2 NUCLIDE BONE liver T. BODY THYROID KIDHEY LUNG GI-LLI Ru-106 1.63E+03 0.00E+00 2.07E+02 0.00E+00 3.15E+03 0.00E+00 1.06E*05 Ag-110m 1.56E+03 1.45E+03 8.60E+02 0.00E+00 2.85E+03 0.00E+00 5.91E+05 Te-125m 1.19E+04 4.31E+03 1.59E+03 3.57E+03 4.83E+04 0.00E+00 4.75E+04 Te-127m 3.00E+04 1.07E+04 3.66E+03 7.6?E+03 1.22E+05 0.00E+00 1.01E+05 Te-127 4.88E+02 1.75E+02 1.06E+02 3.61E+02 1.99E+03 0.00E+00 3.85E+04 Te-129m 5.10E+04 1.90E+0'4 8.07E+03 1.75E+04 2.13E+05 0.00E+00 2.57E+05 Te-129 1.39E+02

~

5.23E+01 3.39E+01 1.07E+02 5.85E+02 0.00E+00 1.05E+02 Te-131m 7.67E+03 3.75E+03 3.13E+03 5.94E+03 3.80E+04 0.00E+00 3.73E+05 Te-131 8.74E+01 3.65E+01 2.76E+01 7.18E+01 3.83E+02 0.00E+00 1.24E+01 Te-132 1.12E+04 7.23E+03 6.78E+03 7.98E+03 6.96E+04 0.00E+00 3.42E+05 -

I-130 4.87E+01 1.44E+02 5.67E+01 1.22E+04 2.24E+02 0.00E+00 1.24E+02 1-131 2.68E+02 3.83E+02 2.20E+02 1.26E+05 6.57E+02 0.00E+00 1.01E+02 I-132 1.31E+01 3.50E+01 1.22E+01 1.22E+03 5.57E+01 0.00E+00 6.57E+00 .

I-133 9.15E+01 1.59E+02 4.85E+01 2.34E+04 2.78E+02 0.00E+00 1.43E+02 I-134 6.83E+00 1.86E+01 6.63E+00 3.21E+02 2.95E+01 0.00E+00 1.62E-02 I-135 2.85E+01 7.47E+01 2.76E+01 4.93E+03 1.20E+02 0.00E+00 8.44E+01 Cs-134 3.33E+05 7.93E+05 6.48E+05 0.00E+00 2.57E+05 8.52E+04 1.39E+04 Cs-136 3.49E+04 1.38E+05 9.91E+04 0.00E+00 7.66E+04 1.05E+04 1.56E+04 Cs-137 4.27E+0,5 5.84E+05 3.83E+05 0.00E+00 1.98E+05 6.59E+04 1.13E+04 Cs-138 2.96E+02 5.84E+02 2.89E+02 0.00E+00 4.29E+02 4.24E+01 2.49E-03 Ba-139 1.34E+01 9.53E-03 3.92E-01 0.00E+00 8.91E-03 5.41E-03 2.37E+01 Ba-140 2.80E+03 3.52E+00 1.83E+02 0.00E+00 1.20E+00 2.01E+00 5.77E+03 Ba-141 6.50E+00 4.91E-03 2.19E-01 0.00E+00 4.57E-03 2.79E-03 3.06E-09 Ba-142 2.94E+00 3.02E-03 1.85E-01 0.00E+00 2.55E-03 1.71E-03 4.14E-18 La-140 1.57E+00 7.94E-01 2.10E-01 0.00E+00 0.00E+00 0.00E+00 5.83E+04 La-142 8.06E-02 3.67E-02 9.13E-03 0.00E+00 0.00E+00 0.00E+00 2.68E+02 Ce-141 5.56E+00 3.76t+00 4.26E-01 0.00F+00 1.75E+00 0.00E+00 1.44E+04 Ce-143 9.80E-01 7.25E+02 8.02E-02 0.00E+00 3.19E-01 0.00E+00 2.71E+04 Ce-144 2.90E+02 1.21E+02 1.56E+01 0.00E+00 7.19E+01 0.00E+00 9.80E+04 l Pr-143 5.79E+00 2.32E+00 2.87E-01 0.00E+00 1.34E+00 0.00E+00 2.54E+04 Pr-144 1.90E-02 7.87E-03 9.64E-04 0.00E+00 4.44E-03 0.00E+00 2.73E-09 Nd-147 3.96E+00 4.58E+00 2.74E-01 0.00E+00 2.68E+00 0.00E+00 2.20E+04 W-187 2.98E+02 2.49E+02 8.70E+01 0.00E+00 0.00E+00 0.00E+00 8.15E+04 No-239 3.00E-01 2.95E-02 1.63E-02 0.00E+00 9.20E-02 0.00E+00 6.05E+03 l

l 2.0-20 Rev. 1, 11/85

Table 2.2-2 BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)*

ELEMENT FISH INVERTEBRATES H 9.0E-01 9.3E-01 C 4.6E+03 9.1E+03 NA 1.0E+02 2.0E+02 P 1.0E+05 3.0E+04 CR 4.0E+02 2.0E+03 MN 5.5E+02 9.0E+04 FE 3.0E+03 2.0E+04 CO 1.0E+02 1.0E+03 NI 1.0E+02 2.5E+02 CU 6.7E+02 1.7E+03 ZN , 2.0E+03 5.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 -

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 1.5E+01 5.0E+01 RU 1.0E+61 1.0E+03 RH 1.0E+01 2.0E+03 AG** 3.3E+03 3.3E+03 TE 4.0E+02 6.lE+03 I 1.5E+01 5.0E+01 CS 2.0E+03 1.0E+03 BA 1.0E+01 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+01 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W l.2E+03 3.0E+01 NP 1.0E+01 4.0E+02 Values in Table 2.2-2 are taken from Ref. 4, Table A-1, except as noted below. The more conservative of salt and fresh water values have been included in Table 2.2-2 for the purpose of liquid dose calculations.

• • -- Values for Ag are taken from Reference 9.

2.0-21 Rev. 1, 11/85

Table 2.2-3 ADULT INGESTION DOSE FACTORS *

(mrem /pCi ingested)

Page 1 of 2 NUCL10E SONE t,1vER T.ROGY TNYROIO K10NEY LONG G1-LLI

. . . . _ _ _ _ . _ . . - -- ... ~ ._ _ .._. .... _ .....

H 3 NO DATA 1.0SE-07 1.0 S E-0 7 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 C 14 2.04E-04 S.68E-07 5.6 8 E -0 7 S.68E-07 5.68E-07 S.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1. 70E-06 1. TOE-06 1.70E-06 1.70E-06 1.70E-04 P 32 1.93E-04 1.20E-05 7. 46E -0 6 40 DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 S.84E-10 3.53E-09 6.69E-07 MN S4 _ 90 OATA .

4.57E-06 8. 72 E-0 7 NO DATA 1.36E-06 NO DATA 1 40E-05 MN 56 NO DATA 1.1SC-07 2.04E-04 NO DATA 1.44E-07 NO DATA 3.67E-06 FE SS 2.fSE-06 1.90E-06 4.4 3C-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-04 1 02E-05 3. 91 E-0 6 NO DATA NO DATA 2.8SE-06 3.40E-05 CO 58 NO DATA 7.45d-07 1.47E-06 NO CATA NO DATA NO DATA 1 51E-05 '

CO 40 - NO DATA 2.14F-06 4. 72 C-0 6 NO DATA NO DATA ,NO DATA 4.02E-05 41 63 1.30E-04 9.01E-06 4.34E-04 NO DATA NO DATA 'NO DATA 1.88E-04 NI 65 S.28E-07 6.86E-08 3 13 E -0 8 NO DATA NO DATA NO DATA 1 74E-06 '

CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 No DATA 7.10E-06 i 2N 65 4.84E-06 1.54E-05 6. 96 E -0 6 No DATA 1.03E-05 NO DATA 9.70E-06 j ........_..... _ .___... _........... __ .....______..____......____._-_____

ZN 69 1.03E-08 1.97E-08 1. 3 7 E-0 9 NO DATA 1.28E-08 NO DATA 2.96E-09 SR 83 NO DATA NO DATA 4. 02 E -0 8 90 DATA NO DATA NO DATA S.79E-08 SR 84 NO DATA NO DATA S.21E-08 NO DATA NO DATA NU 0ATA 4.09E-13 SR SS NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 RS 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 R8 E8 NO DATA' 6.0SE-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RS 89 NO DATA 4.01E-08 2. 02 E-0 4 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.00E-04 NO DATA 8. 84 E-0 6 MO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1. 86 E-0 3 NO DATA NO DATA NO DATA 2.19E-04 SR 91 S.67E-06 NO DATA 2.29E-0 7 NO DATA NO DATA NO DATA 2.70E-OS SR 92 2.1SE-06 NO DATA 9.30E-06 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 No CATA MO DATA NO DATA 2.67E-10 Y 91 1.41E-02 NO DAT4 3.77E-09 N0 OATA NO DATA NO DATA 7.76E-OS Y 92 8.4SE-10 NO DATA 2.47E-11 NO DATA NO DATA No DATA 1.40E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 2R 95 3.04E-08 9.75E-09 6. 60E-0 9 NO DATA 1.53E-08 NO DATA 3.09E-OS 2R 97 1.68E-09 3.39E-10 1.SSE-10 NO DATA S.12E-10 NO DATA 1.0SE-04 MS 95 4.22E-09 3.46E-09 1. 86E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-OS NO 99 NO DATA 4.31E-06 8.20E-0 7 NO DATA 9.76E-04 NO DATA 9.99E-06 TC 99M 2.47E-10 6.90E-10 8. 09E-09 NO DATA 1 06E-04 3.42E-10 4.13E-07 l

l -

l Values in Table 2.2-3 are taken from Ref. 4, Table E-ll.

l 2.0-22 Rev. 1, 11/85

l l

Table 2.2-3 i

ADULT INGESTION DOSE FACTORS *

(mrem /pCi ingested)

Page 2 CME 2 NUCLICE SONE liver T.80DY TNYRO10 RIONEY LUNG GI-LLI FC101 2.S4E-10 3.66E-10 3. 59E -0 9 40 DATA 6.59E-09 1 8?E-10 1.10E-21 RU103 1.85E-07 NO DATA 7. 97E -0 4 NO DATA 7.06E-07 No DATA 2.16E-05 RU105 1.54E-08 NU OATA 6. 00E-09 40 DATA 1 99E-07 NO DATA 9.42E-06 RU106 2.75E-06 NO DATA 3. 4 8E-0 7 NO DATA 5 31E-06 NO DATA 1.783 04 AG110M 1.60E-07 1 48E-07 8.79E-04 40 DATA 2 9.1E-07 NO DATA 6.04E-05 TE125M 2.68E-06 9.71E-07 -3. 5 9E-0 7 0.06E-07 1 09E-05 NO DATA 1.07E.05 TE127M 4.77E-06 2.42C-06 8. 25E-0 7 1.73E-04 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2. 38E-0 4 4.15E-08 4.40E-07 NO DATA 8.48E 06 TE129M 1.15E-05 4.29E-06 1.82E-04 3.95E-04 4.80E-05 NO DATA 5. 79E-05 TE129 3 14E-08 1.18E-08 7. 6)E-0 9 2.41E-04 1.32E-07 NO DATA 2.37E-04 -

TE131M 1.73E-06 8.46C-07 7.0 5E-0 7 1.34E-06 0.57E-04 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09 6. 22 E-0 9 1.62E-08 8 63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1 63E-06 1. 53E-0 6 1.80E-06 1 57E-05 NO DATA 7.71E-05 '

1 130 7.56E-07 2.23E-06 8. 80E-0 7 1.89E-04 3 48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3. 41E-0 6 1.95E-01 1.02E-05 NO DATA 1.57E-06 8 132 2.03E-07 5.43E-07 1.90E-0 7 1.90E-05 0 65E-07 NO DATA 1.02E-07 I L33 1.42E-06 2.47E-06 7.5 3E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1 03E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 f 135 4.43E-07 1.16E-06 4. 2 SE-0 7 7.65E-05 1.86E-06 NO DATA 1.31E-06 C5134 6.22E-05 1.48E-04 1. 21E-0 4 NO DATA 4.79E-05 1.59E-05 2.59E-04 C5136 6.51E-06 2.57E-05 1. 85E-0 5 NO DATA 1 43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1 09E-04 7.14E-0 5 40 DATA 3.70E-05 1 23E-05 2.11E-06 C5134 5.52E-08 1.09E-07 5. 40E-0 8 NO DATA 8.01E-08 7.91E-09 4.65E-13

2. 84E-0 9 No DATA 6.44E-11 3 92E-11 1 72E-07, 4A139 9.70E-08 6.91E-11 8A140 2.03E-05 2.55E-04 1.3&E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 84141 4.71E-04 1.56E-11 1. 59E-0 9 40 DATA 3.31E-11 2.02E-11 2.22E-17 l

GA142 2.13E-08 2.19E-11 ..... 1 34E-09 40 DATA 1.85E-11 1.24E-11 1.00E-24 LA140 2.SOE-09 1.26E-09 J.33E-10 NO DATA NO DATA NO DATA 9.25E-05 i LA142 1.20E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07; CE141 9.36E-09 6.31E-09 7.18E-10 NO DATA 2 94E-09 NO DATA 2.42E-05 t 5.37E-10 NO CATA 4.56E-05 ,

CE143 1.65E-09 1.22E-06 1. 35E-10 NO DATA CE144 4.ASE-07 2.04E-07 2. 62 E-0 8 NO DATA 1.21E-07 NO DATA 1 65E-04 i PR143 9.20E-09 3.69E-09 4 56E-10 NO DATA 2.13E-09 NO CATA 4.03E-05 :

r

! PR144 3.01E-11 1.25E-11 1. 5 SE-12 NO DATA 7.05E-12 NO DATA 4.33E-18 l N0147 6.29E-09 7.27E-09 4. 35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 i W 197 1.03E-07 8.61E-04 3.01E-08 NO DATA No 0ATA NO*0ATA 2.42E-05 (

NP239 1.19E-09 1.17E-10 6. 45E-11 NO DATA 3.45E-10 NO OdTA 2 40E-05 i l .

Values in Table 2.2-3 are taken from Ref. 4, Table E-ll.

I 2.0-23 Rev. 1, 11/85

2.3 DEFINITIONS OF LIQUID EFFLUENT TERMS Section of Term Definition Initial Use A = Adj us t men t factor which will allow the (2.1.1.1) setpoint to be established in a practical manner for convenience and to prevent spurious alarms.

Ait = the site related fish and invertebrate (2.2) consumption dose commitment factor to the total body or any organ t for each ,

identified principal gamma and beta emitter listed in Table 2.2-1 [ mrem /hr per uCi/ml].

BFi = Bioaccumulation factor for radionuclide i, (2.2) in fish [pCi/kg per pCi/l] from Table 2.2-2.

BI i = Bicaccumulation factor for iadionuclide i, (2.2) in invertebrates [pci/kg per pCi/1] from Table 2.2-2.

l l

c = the setpoint [uci/ml] of the radioactivity (2.1.1) monitor measuring the radioactivity con-

. centration in the effluent line prior to dilution and subsequent release.

Ca = the concentration of alpha emitters in (2.1.1.1) liquid waste as measured in the most recent QUARTERLY composite sample for the tank l

under consideration [uci/ml].

2.0-24 Rev. 1, 11/85

- ~.

Section of Term Definition _ Initial Use C

g the measured concentration of Fe-55 in (2.1.1.1) liquid waste as observed in the most recent QUARTERLY composite sample for the tank under consideration [uci/ml].

= the concentration of each measured gamma C (2.1.1.1) 9 emitter observed by gamma-ray spectroscopy of each waste sample [uci/ml].

Ci =

the measured concentration of Cg,Ca, Cs, (2.1.1.1)

C g and Ct.

Cil = the average concentration of radionuclide (2.2) -

i, in undiluted liquid effluent during time Atl from any liquid release,[uci/ml].

CMPC = the effluent concentration limit (Speci- (2.1.1.1) fication 3.11.1.1)~ implementing 10CFR20 for the site, corresponding to the specific mix of radionuclides in the effluent stream being considered for discharge [uci/ml].

C3 = the measured concentrations of Sr-89 (2.1.1.1) and Sr-90 in liquid waste as observed

.-i n t h e m o s t recent QUARTERLY composite sample for the tank under consideration

[uci/ml].

=

Ct the measured concentration of H-3 in (2.1.1.1) liquid waste as determined from analysis of the most recent QUARTERLY composite sample for the tank under consideration

[uci/ml].

2.0-25 Rev. 1, 11/85

Section of Term Definition Initial Use i

DF = dilution factor; ratio of total dilution (2.1.1.1) flow rate to tank flow rate required to assure that the limiting concentrations of 10CFR20, Appendix B, Table II, Column 2 are met at the point of discharge to the Delaware River.

DF' = the greatest value for DF from DF 1, DF2,

, (2.1.1.2)

DF 3 ..., used in the determination of the monitor setpoint when liquid radwaste ,

tanks are releasing' simultaneously.

DFi = Dose conversion factor for radionuclide i, (2.2) for adults in preselected organ t [ mrem /pCi]

from Table 2.2-3.

Dt = the cumulative dose commitment to the (2.2) total body or any organ t, due to radio-activity in liquid effluents for the total m

time period atl [ mrem].

{ ,

l=1 f = the flow setpoint as determined at the (2.1.1)

' radiation monitor location, in volume per unit time, but in the same units as F, below.

l F = the dilution water flow setpoint as (2.1.1) determined prior to the release point, l

in volume per unit time.

{

Fd = the setpoint for minimum dilution flowrate (2.1.1.1) 2.0-26 Rev. 1, 11/85 i

Section of Term Definition Initial Use Fd' = the setpoint for minimum dilution flowrate, (2.1.1.1) considering the buildup of radioactivity from plant operations in the Cooling Tower Blowdown Basin.

fe = maximum permissible effluent discharge (2.1.1.1) flow rate.

F1 = the near field average dilution factor (2.2) during any liquid effluent release

[unitiess].

fs = the sum of the expected flow rates for (2.1.1.2) all waste tanks releasing simultaneously.

ft = the expected flow rate of liquid waste (2.1.1.1) tank discharge. The maximum discharge capacities for the liquid waste tanks at HCGS are presented in Table 2.1-2.

Ko = Units conversion factor, 1.14 E+5 (2.2) i MPC = MPC g, MPCa, MPCs, MPCg, and MPCt are (2.1.1.1)

. limiting concentrations of the appropriate radionuclides from 10CFR20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to the specific MPC values l presented in Table 2.1-1.

l 2.0-27 Rev. 1, 11/85 t

Section of Term De'finition Initial Use SF = the safety factor; a conservative (2.1.1.1) factor used to compensate for statistical fluctuations and errors of measurements.

1 Atl= the length of the lth time period over (2.2) which Cil and F1 are averaged for all liquid releases, [ hours].

UF = Adult fish consumption (21 kg/yr). (2.2)

UI = Adult invertebrate consumption (5 kg/yr). (2.2)

Z = 10, which is the applicable dilution (2.2) factor for the receiving water body at the Hope Creek Generating Station.

2.0-28 Rev. 1, 11/85 t

Section 3.0 ROUTINE GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITOR SETPOINT CALCULATIONS Technical Specification 3.3.7.11 states, in part:

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

Since, according to Section 5.1.1 of Ref. 6, "It is not considered practicable to apply instantaneous alarm / trip ,

setpoints to integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases," only noble gas monitor setpoints need be specified by the ODCM.

The noble gas limits established by specification 3.11.2.1 are quoted below in Section 3.2.1; they are instantaneous dose rates of 500 mrem /yr to the total body, and 3000 mrem /yr to the skin at any point outside the Site Boundary. The three noble gas effluent monitors listed in Technical Speci-fication Table 3.3.7.11-1 are the following:

RE4811A - the Filtration, Recirculation, and Ventilation System noble gas monitor RE4814A - the South Plant Vent noble gas monitor RE4875A - the North Plant Vent noble gas monitor The methodology of this Section applies to setpoints for these three monitors. The setpoints calculated according to this Section are regarded as upper bounds for the actual 3.0-1 Rev. 1, 11/85

[

monitor setpoints. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the new calculated value. If no radioactive discharge is planned for a given release point, the monitor setpoint for that release point should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inad-vertant release occur.

Two methods are given. The first (Section 3.1.1) is the method which is used normally. The second (Section 3.1.2) is used during startups when the concentrations of all plant-generated noble gases in the most recent sample for -

a given release point are all undetectable. Setpoints calculated by the two methods may be used on different ,

monitors simultaneously; only those release points for which the most recent sample yielded no detectable plant-generated noble gases will have their monitor setpoint established according to Section 3.1.2.

3.1.1 Normal Setpoint Method The following method applies to the normal circumstance that one or more plant-generated noble gases in the most recent sample for a given release point are detect-able. In this case, for the purpose of satisfying

' Technical Specification 3.3.7.11, the setpoints of each of the three station vent monitors are estab-lished as follows:

S = the lower of Syt or Sys, where y

500 ay SF X gy i

S .

- Fy (X/Q) [(K i

g Xgy]

3.0-2 Rev. 1, 11/85

3000 ay SF X gy .

S =

8 F

y (X/Q) [(L g + 1.1 Mg) Xgy]

i and where:

S = the candidate setpoint for vent v, based yt upon the total body dose rate limit of 500 mrem /pr [uci/cc].

S = the candidate setpoint for vent v, based ys

. upon the skin dose rate limit of 3000 mres/yr

[uci/cc].

500 = the whole body dose rate limit [ mrem /yr].

3000 = the skin dose rate limit [ mrem /yr].

ay = the administrative allocation factor for vent v [unitiess], which is the fraction of the station site boundary dose rate limit which is assigned to vent v. Allocation factors may be changed as necessary. However, normally, each allocation factor should be between 0.0 and 0.5 inclusive, and the sum of the three allocation factors should be less than or equal to 0.5.. (This limitation to 0.5 is to ensure that the combined releases from the Hope Creek and Salem Stations remain within the regulatory limits at the common Site Boundary.) Any increase in this total allocatibn factor above 0.5 will be coordinated with the' Salem Generating Station to ensure 3.0-3 Rev. 1, 11/85

that the total allocation factor for all units does not exceed 1.0.

Fy = the expected flow rate in vent v [cc/sec]. .

Flow rates in cfm may be converted to cc/sec by multiplying them by 472.

SF = the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurements. The actual value will be determined in implementing procedures.

X/Q = the highest annual average relative concentration at the site boundary in any sector.

= 1.0 x 10-5 sec/m3 Site boundary distances were determir.ed from Figure 2.1-1 of Ref. 2. ,

The listed value, in the SE sector, is the highest annual average X/Q at the Site Boundary.

Kg .= total body dose factor for gamma emissions from noble gas radionuclide i [ mrem /yr per uci/m3], from Table 3.1-1.

X = the measured concentration of noble gas iy radionuclide i in the last grab sample analyzed for vent v [uci/cc). For the North Plant Vent and the South Plant Vent, such samples are taken at least monthly. For purges of contain-ment through the FRVS, a grab sample will be taken prior to intentionally initiating

- each such release, or as soon as possible af ter such a release is initiated automatically.

L = skin dose factor for beta emissions from i

noble gas radionuclide i [ mrem /yr per uCi/m3],

from Table 3.1-1.

3.0-4 Rev. 2, 1/86 9

--- -r . --r- ~ - - - -

,---v-w-,,,- -- - - -

from Table 3.1-1.

M i

= air dose factor for gamma emissions from noble gas radionuclide i [ mrad /yr per oCi/m 3),

from Table 3.1-1.

1.1 = a factor to convert absorbed dose in air due to gamma radiation, to dose equivalent in skin [ mrem / mrad].

The :ao n i t o r setpoint S y established by the method above shall be entered into the radiation monitoring system, along with the sample assay data (the X iy) that were used to calculate it. The operational value of the setpoint should contain an allowance for the ,,

monitor's background count rate and its variation.

However, effluent monitors at the Station will be maintained such that they are sensitive to radiation at the levels at which it is emitted from the effluent streams.

3.1.2 Startup setpoint Method The following method applies to the special circumstance that the assay of plant-generated noble gases in the most recent sample for a given release point yields

'no detectable radionuclides. It is conservative because

! it assumes that all the noble gas detected by the monitor is Kr-89, the most conservative radionuclide in Table 3.1-1. Thus, this method results in the overestimation of the true dose delivered by the actual l

noble gas mixture being released. It is therefore recommended that this method not be used except when it is necessary due to the undetectability of the j noble gases in the sample from a particular release l 3.0-5 Rev. 1, 11/85

point.

In this case, for the purpose of satisfying Technical Specification 3.3.7.11, the setpoints of any of the three station vent monitors may be established as follows:

S ye

the lower of Svt' or Sys', where 500 SF S '

a#

Fy (X/Q) K Kr-89 3000 ay SF V8 Fy (X/Q) (LKr-89

• I* "Kr-89) where S y' is the conservative setpoint for startup

[uci/cc], L Kr-89 and MK r-89 are dose f actors for Kr-89 from Table 3.1-1, and other terms are .ss defined above.

The monitor setpoint S ye established by the method above will be entered into the radiation monitoring system. For the sample assay data, the LLD for Kr-89 in the most recent sample for the particular release point will be entered into the radiation monitoring system. The operational value of the setpoint should contain an allowance for the monitor's background *

, count rate and its variation. However, effluent monitors at the Station will be maintained such that they are sensitive to radiation at the levels at which it is emitted from the effluent streams.

i l ,

t 3.0-6 Rev. 1, 11/85 l

5 t

1

Table 3.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES

• Dose to People + Dose to Air I Nuclide Gamma-Body (K) Beta-Skin (L) Gamma (M) Beta (N)

Kr-83m 0.08 ----

19.3 288 Kr-85m 1,170 1,460 1,230 1,970 Kr-85 16.1 1,340 17.2 1,950 Kr-87 5,920 9,730 6,170 10,300 Kr-88 14,700 2,370 15,200 2,930 Kr-89 16,600 10,100 17,300 10,600

~

Kr-90 15,600 7,290 16,300 7,830 Xe-131m 91.5 476 156 1,110 Xe-133m 251 994 327 1,480 '

Xe-133 294 306 353 1,050 Xe-135m 3,120 711 3,360 739 -

Xe-135 1,810 1,860 1,920 2,460 Xe-137 1,420 12,200 1,510 12,700 Xe-138 8,830 4,130 9,210 4,750 Ar-41 8,840 2,690 9,300 3,280 Notes:

Values taken from Ref. 4, Table B-1.

1. -- mead /yr per uCi/m3

+ -- , mrem /yr per uCi/m3 l

3.0-7 Rev. 1, 11/85

3.2 GASEOUS EFFLUENT DOSE CALCULATIONS 3.2.1 Site Boundary Dose Technical Specification 3.11.2.1 states:

The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives

. greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

The following two subsections give the methods by which dose computations are performed for the purpose ,

of demonstrating compliance with this Technical Speci-fication.

3.2.1.a Dose due to Noble Gases For the purpose of implementation of Technical Specifica-tion 3.11.2.1.a, the dose at the Site Boundary due to noble gases is calculated as follows:

t

= current site boundary total body dose i . rate [ mrem /yr]

= X/Q [K g h]

g i

D = current site boundary skin dose rate a

[ mrem /yr3

= X/Q [ (Lg + 1.1 Mg) h]

g i

3.0-8 Rev. 1, 11/85

where:

Qi = the release rate of noble gas radionuclide i as determined from the concentration measured in the analysis of the appropriate sample required by the Technical Specification Table 4.11-2 [uci/sec].

X/Q = the highest annual average concentration in anf sector, at the site boundary (for

. value, see section 3.1.1) [sec/m33 For post-release computations, the actual X/Q for the period of the release (calculated according to Section 3.3 of this ODCM) may be substituted for X/Q. ..

3.2.1.b Dose due to Radionuclides other than Noble Gases For the purpose of implementation of Technical Specifica-tion 3 ."l l . 2 .1. b , the dose at the Site Boundary due to radiciodines, tritium, and radionuclides in particulate form with half-lives greater than 8 days is calculated as follows:

b sb = current site boundary dose rate to organ o [ mrem /yr]

=

X/Q [P g0 h']

g i

where:

0' 1

= the release rate of non-noble gas radionuclide i as determined from the concentration measured in the analysis of the appropriate sample required by the Technical Specification Table 4.11-2 [uci/ soc].

3.0-9 Rev. 1, 11/85 i

X/Q = the highest annual average concentration in any sector, at the site boundary (for value, see Section 3.1.1) [sec/m3]. For post-release calculations, the actual site boundary X/Q in the affected sector for the period of the release may be substituted.

P io = dose parameter for radionuclide i and organ o, for ihhalation, from Table 3.2-1 [mres/yr

, per uci/m3].

3,2.2 Air Dose Technical Specification 3.11.2.2 states:

The air dose due to noble gases released in gaseous ,.

effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 meads for gamma radiation and less than or equal to le meads for beta radiation, and

b. During any calendar year: Less than or equal to 10 meads for gamma radiation and less than or equal to 20 meads for beta radiation.

For the purpose of demonstrating compliance with this

(

l Technical Specification, the air dose at the Site Boundary is determined as follows:

D g = 3.17 x 10 X/Q [Mg gg ]

i D

b

= . x -

X/O [N g h]g i

l 3.0-10 Rev. 1, 11/85

where:

D = the site boundary air dose due to gamma g

emissions from noble gas radionuclides [ mead].

D = the site boundary air dose due to beta emissions b

from noble gas radionuclides [ mrad].

3.17 x 10-8 = the fraction of one year which is one second.

= cumulative release of noble gas radionuclide i

i over the period of interest [uci].

X/O = the highest annual average concentration ,,

in any sector, at the site boundary (for value, see Section 3.1.1) [sec/m3]. For post-release calculations, the actual site boundary X/Q in the affected sector for the period of the release may be substituted.

N = air dose factor for beta emissions from i

noble gas radionuclide i [ mrad /yr per uCi/m3],

l from Table 3.1-1.

3.2.3 Dose to a Member of the Public Technical Specification 3.11.2.3 states:

The dose to a MEMBER OF THE PUBLIC from iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following-

a. During any calendar quarter: Less than or equal to 7.5 meems -to any organ, and

b. During any calendar year: Less than or equal

, to 15 mreas to any organ.

3.0-11 Rev. 1, 11/85

For the purpose of demonstrating compliance with this Technical Specification, a Maximum Exposed Individual is defined. This person has those residence and consump-tion patterns of real Members of the Population in the environment of HCGS which lead to the highest computed doses. Technical Specification 3.11.2.3 is then satisfied if the calculated doses for the Maximum Exposed Individual are less than the limits of the Tech Spec. The dose to the Maximum Exposed Individual is calculated as follows:

D mp = dose to organ o of a Member of the -

P u b'l i c , from radioiodines, tritiuu, and radionuclides in particulate form ,

with half-lives greater than 8 days

[ mrem]

~

= 3.17 x 10-8 [g ijo gij, gi, 3 ij where:

W ij' = relative concentration or relative deposition for the Maximum Exposed Individual, as appro-priate for exposure pathway j and radionuclide

i. W e is defined as follows, (where the 13

- selection of the numerical values is explained in the Note to Table 3.2-5):

. = X/Q' for inhalation and all tritium pathways, 1.1 E-07 sec/m3, and

= D/Q' for other pathways and non-tritium nuclides, 4.9 E-10 m-2, 3.0-12 Rev. 2, 1/86

R ijo = dose factor for organ o due to radionuclide i and pathway j, from Table 3.2-2 [mres/yr per uci/m3, or m2 - mrem /yr per uci/sec].

For the purpose of this calculation, the Site Maximum Exposed Individual is a hypothetical infant consuming the milk of a cow pastured at 5.0 miles in the SE sector.

Q'i

= cumulative release of non-noble gas radionuclide i over the period of interest [uci].

3.0-13 Rev. 2, 1/86 l

1

Table 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (P.io)*

Page 1 of 7: Dose Factors for Total Body I 190TOPEl IHLATi(DI I I ISOftPEI i n tATI(tei I 190T(PEI IHLATIW l in-3 1 1.125E+D) i 19-92 1 5.254 01 I 11 131 1 2.727E+H I IC.14 I 6.734E+03 I lY-94 1 1.196E+02 I 11 132 1 1.876E*n) I INb24 1 1.610E+64 I lY.91rl i 1.943E-02 1 11 133 1 7.696E+63 I IP.32 1 9.07M+64 I lY-91 1 2.439E+64 1 11-134 I 9.953E+t2 1 ICit-51 1 1.543E*02 I lY-92 1 5.000E.01 1 11-135 1 4.144003 I

.If96 54 - l 9.50 Dt3 I

............'... ... lY-93.

1 5.196E+tf I 1C5-134 i 2.246E+05 I If96 56 1 3.119E-Il 1 1251-95 1 3.700004 I ICS.136 1 1.162D65 i

. ................... .. . =............. ... ...................

irt.55 I 7.770D01 1 125 97 l 1.5 aDG1 i

.. ................... ....... ......'......... 1C5. 137 l 1.204D05 I IFE.59 1 1.669E*te i 19-95 1 6.54 1 1C5-136 1 5.550E*02 I

........................ ... ..........'E*03 100-59 '

1 3.164E+43 1 14 99 I 4.255E+nt i 19 4 139 I 5.365E 02 1 ICD-60 1 2.264E*t4 I ITC-99ft i 5.772E-02 I 184140 I 4.329D03 I lHI-63 1 2.7 i ITC-101 1 1.077E.03 I IIbl41 1 6.364E-03 I

. ............'?E+44.........

IN1-65 i 1.643E-Il i 1 6 103 1 1.073E+I) i 18 4 142 1 2.790E-03 I 10)-64 1 1.073E*t0 1 1 5 105 I 5.550E-81 1 ILA-140 1 7.548E*01 I 12K.65 l 7.030E+64 1 1 6 106 1 1.691E*l4 I ILA149 l 1.291601 I 12569 I 9.917E-83 1 14-11er! I 9.13 I ICbl41 1 2.897E+03 I

........................ ..... .......'E+03 IBR-83 1 4.736E+ 02 I ITE-125fti 9.139E*02 I ICE-143 1 2.875E*01 I Im-84 1 5.476D02 I ITE-127tlI 3.01M+03 I ICE-144 1 3.615D05 I 1 5 -85 1 2.531E*01 1 ITE.127 I 6.109E-01 1 1811-143 1 9.13 0 02 1 15 86 1 1.143E*I5 I ITE.129FII 3.941E+03 I iPIl-144 1 2.99?E-03 I 185 88 I 3.663Dt2 I ITE-129 1 2.383E.02 1 14-147 I 6.009D02 I

............. .... ... =............. ..................... .

115 89 1 2.097DB2 I ITE-131tlI 5.06*D01 1 114-187 I 4.32*D00 I 19 89 1 1.724DL 1 176131 1 6.506E.13 I l@-219 1 2.350E*01 I 19 90 I 6.430E*46 I ITE.132 1 2.634E+42 I 19 91 1 4.5R9DtB i 11 130 1 8.436003 I See Note, page 3.0-21 Units: mrem /yr per uCi/m3 3.0-14 Rev. 1, 11/85

Table 3.2-1 PATIDIAY DOSE FACTORS FOR SECTION 3.2.1.b (P.lo)*

Page 2 of 7: Dose Factors for Bone

.... . ~ . ... ......... ...... ..... ........ ..............

I 190TOPEI imAil01 1 I I!OTIPEI 1808LAfl0M i i 190TtPEI i m ATION I 14 3 1 0.00E*04 1 191- ? I 1.310E*t1 1 11 131 1 4.81aE*94 I 10-14 1 3.589E+04 6 lY.90 t 4.107E*t3 I 11 132 1 2.116E*03 I 1624 1 1.610E+S4 I lY.91M i 5.669E-Il i 11 133 1 1.658E*04 I 1 2.604E*I6 I 1 9.13 E*05 I 1 1.173E*03 I IP.32

. ........... .. ... .lY-91

.............'........11-134 10l.51 I 0.000E*09 I 'lY-92 1 2.935E+01 I 11 135 1 4.921E*93 I I196 54 .I 0.000E*04 I lY-93 1 1.065E*82 I ICS-134 1 6.512E*05, I lft6 56 I 0.QO0E*00 1 15 'S 1 1.899E*05 I ICS.136 I 6.512E*04 I IFE.55 I 4.736E*64 1 15-97 I 1.876E*t2 I ICS-137 8 9.069E*05 I

=-- .....~.....,........... - ===.............

IFE-50 1 2.068E*04 1 15-95 1 2.35E+04 I ICS-138 I 6.327E*02 I I 0.000E+44 I l@- 9 I 0.000E*00 I th.139 1 1.041E*00 I 100 59 100 60 1 0.000E+00 I ITE.99tl 1 1.780E-83 1 106-140 1 7.400E*04 I INI-63 1 8.214E+05 I ITE.lt! I 8.ll3E-05 I Im.141 1 1.957E-01 l

_=.......... . - ................... ......................

INI.65 1 2.990E*00 1 1 4 103 I 2.794E+03 1 10b142 1 4.995E-02 I ICt)-64 I 0.000E*06 ! 1 6 105 1 1.529E*00 I ILA-140 1 6.43E*02 1 12W-65 I5.255E*04 1 1 6 106 1 1.362E*05 I ItA 142 1 1.295E*04 I 12W-69 I 6.697E-02 I IAG-110M i 1.687E*04 I ICE-141 1 3.922E+04 1 10P=83 1 0.000E*06 I ITE-125M i 6.734E+63 I IE.143 1 3.65 I

....__ _ _ _ - - .. ................. .. ............'E*02 ........

IIP-84 1 0.00E*00 I ITE-127!11 2.486E+04 I ICE-144 1 6.771E*06 I ItW-85 1 0.000E*00 1 ITE-127 1 2.771E+tt i I E 143 1 1.846E+04 I 1486 1 0.000E+04 I ITE-l?ft11 1.920E+44 1 1 % 144 1 5.957E-02 I 1 4 88 1 0.000E+00 1 ITE-129 I 9.768E-02 1 19-147 1 1.000E+n4 I 194 89 I 0.000E*00 I ITE-131N I 1.343E*02 1 + 187 1 1.632E*01 i ICD-89 I 5.994E+05 I ITE-131 1 2.172E.02 1 1*.239 I 4.662E*02 I

. . - ... ... ==............... ..__..... .........

158 90 1 1.010E+08 I ITE.l}2 1 4. tite +02 I 19 91 1 1.214E*02 1 11-130 1 8.177E+03 I See Note, page 3.0-21 Units: mrem /yr per uCi/m3 3.0-15 Rev. 1, 11/85

Table 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (Pg}

• Page 3 of 7: Dose Factors for Liver I ISOTOPEl ll*WI.ATIGt i i 190TIFEl lefLATION I i 190ftFEl IIteLATI(M i IM.3 1 1.125E*t3 1 19 92 1 0.044E* H I 11 131 1 4 819E**4 I Ir.14 a 6.734F+03 I lY.90 1 0.000E+00 I 11 132 1 4.0;9E*03 I IN4-24 1 1.610E*44 I lY.91n 1 0.000E*00 1 11-133 1 2.031E 4 I IP.12 1 1.143E S I lY.91 1 0.0HE+H I II.134 1 2.161E*0) l ICII-51 1 0.000E*H I fY.92 1 0.000E*40 I 11 135 I 8.732E*03 I 1196-54 _I 4.292E*04 I lY.93 1 0.H0E*H I 105 134 1 1.014E+06 I 1106 56 1 1.658E*H I 13 95 1 4.181E+04 I ICS.136 1 1.74*E*05 I IFE.55 1 2.516E*04 1 13 97 I 2.716E*01 1 105 137 I 8.251E*t5 i

~

14 59 6 3.345E*H I 1495 I 9.176E*03 1 105 119 I 8.399E*02 I

.. _- = _= . .. .................... ........................

Ir0-59 1 1.772E*03 4 1 6 99 I 1.72(+02 1 104 139 I 9.842E-04 I .

100-60 1 1.314E+84 I ITU-99n i 3.482E-03 I 106-140 1 6.475E*01 I

.. ..==- ====....... . ............ ....... . ....................

INI.63 1 4.625E+44 I ITC-101 I 8.510E.05 1 1 5 141 l 1.092E.04 I INl.6E l 2.956E-Il i 1 4 103 1 0.000E*00 i t h 142 1 3.600E-05 1

- =........ ... . ..................... . ..................

100-64 1 1.994E+H I 1 6 105 1 0.000E+H I 11.A.140 1 2.250E*02 I 12465 1 1.132E S I 1 5 106 1 0.000E+H I It.A-142 ! 4.10?E-01 1 12469 I 9.657E.82 I las.11en i 1.140E*84 I ICE-141 1 1.954E+04 I 19R-83 1 0.000E+48 I 14-1291I 2.327E*43 I ICE.143 1 1. 90E+ 02 I 185 84 1 0.000E*H I ITE-127n 1 8.547E+03 I IE.144 I 2.116E*04 1 IE85 1 0.000E+44 I IM.127 I 9.509E-01 1 IPII.143 1 5.550E*03 I 1 5 86 l 1.983E+05 I ITE.129N I 6.84Wel) i IP4144 1 1.846E-02 I 1500 1 5.624E*t2 I ITE-129 1 3.497E-42 l 1 4 147 I 8.732E*03 I 186 89 1 3.452E*t2 I ITE.131n i 5.92nE*#1 I IS187 I 9.657E*00 I l

1999 1 0.000E+H I ITE-131 1 8.436E-43 I IMP-219 1 3.345E+41 I 19 94 1 0.000E*ll i 14 132 1 2.72W+t2 I t

19-91 1 4.000E*06 I II.130 1 1.63*E+ N I

.. .... .. ==. .. ...__......... ....

l I

See Note, page 3.0-21 Units: mrem /yr per uCi/m3

. 3.0-16 Rev. 1, 11/85 I

Table 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (Pg}

• Page 4 of 7: Dose Factors for Thyroid I ISOTUPEI Ipeell.Afl0M i i 190flPEl tieetATimt I i ISOTOREI lietitail0N I tw.3 i 1.129E+03 1 ISit- ? I 0.000E* H I II.131 1 1.624E+07 I 80 14 I 6.734E+03 I lY 98 6 0.000E*It i 11 132 1 1.935E*AS I twn.24 1 1.610E*l4 I lY.91M i 0.000E*00 I 11 133 1 3.840E*06 I IP 32 1 0.00E+04 I IV 91 1 0.000E+04 1 11-134 1 5.069E*04 I 100 51 1 8.54E+41 I IY 1 0.00nE*06 I II.135 1 7.919E*05 I

. ...... ..... . . ___-92_. ................. . ..............__.....

Iro6 94 .I 0.00E*00 I lY.93 1 0.000E+00 1 105-134 1 0.000E*00 I Il*6-54 1 0.00E+44 1 15-95 1 0.000E+H I ICS.136 1 0.000E+00 I IFE.55 1 0.000E+00 1 15-97 1 0.00E+M i 1C5-137 1 0.00E*00 l IFE-54 i 6.006E+64 1 19e.99 1 0.000E*it i ICir.116 i 6.060E*66 i 100 59 I 0.000E*00 1 15 99 1 0.000E+tt i 194 139 I 0.000E+00 I ..

100 60 1 0.n0E*00 I ITC-99N I 0.000E+04 I 152 148 1 0.000E*00 I Ihl.63 1 0.00E*t0 I ITC-101 1 0.000E+M i 194-141 1 0.000E*00 I INI.65 1 0.000E*00 1 1810 113 1 0.000E*I6 I 6m.142 1 0.000E+09 I 100 64 1 0.000E*t0 1 1110 105 1 0.000E*00 I iLA.140 1 0.000E+00 I IN-64 1 0.10E* tt i 1815 106 1 0.000E*00 I ILA.142 1 0.000E*00 1

= - ._ _ . . = .............. . .....................

IN-69 i 0.00E+04 t 1 4 110M I 0.000E*00 I ICE-141 1 0.000E*00 I 198 03 8 0.000E+00 1 ITE.125M i 1.924E+43 I ICE.143 1 0.060E+00 I Ige.Ga 1 0.00E+49 1 ITE-127H I 6.060E+03 I ICE.144 1 0.000E+00 I l

l 109-05 1 0.00E*M i ITE.127 1 1.961E+04 I IR.143 1 0.000E+00 I 189-04 1 0.000E*H I ITE.129n I 6.327E+03 I IPit.144 1 0.00E+00 I 191L09 I 0.00E*00 I ITE.179 I ?.141E.82 1 14-147 1 0.000E*00 I 19fL89 I 0.00E+04 I ITE.111M I 9.768E*01 I 18 187 1 0.00nE+00 I l ___

l 158 09 1 0.00E+08 I ITE.131 1 1.69AE-82 I 160 219 I 0.000E*00 1 1 --

I l

158 90 1 0.000E+99 I ITE.132 1 3.175E*02 I

( Ica.91 1 0.0tE*00 1 11 130 1 1.946E+t6 I l

l l

• -- See Note, page 3.0-21 Units: mrem /yr per uCi/m3 3.0-17 Rev. 1, 11/85 l

\

Table 3.2-1 1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (Plo)*

I Page 5 of 7: Dose Factors for Kidney I 190TOPEI II+cLAil0N I i 190ftPEI litetLATl@l i i 191m FEl llee u il0N I  ;

. ...... ........................ ........................ j IH-3 1 1.125E+43 I isp.e? I 8. HtE+H I II.111 1 7.991E*04 I IC-14 I 6.734E*03 I sy.90 1 0.000E*00 1 11-112 I 6.25tE*03 I 18#-24 1 1.610E*04 I ly.91n 1 0.00K+09 I II.131 1 3.37AE*04 I

.- = . . . - - . - - . . .. .................... ........................

IP-32 1 0.000E+H I ly.91 1 0.000E*88 I II.134 1 3.300E*03 I

. - ..=== - ....... ......................

109-51 I 2.431E*01 I ay.g2 I 0.00K+0g i 11-135 1 1.33*E*D4 i IMM-54 i 1.003E+H I ly.o) 1 0.000E*00 t 105-134 1 1.304E*05 1 leet.54 i 1.672E*H I 12R 95 I 5.057E+04 I IC5-116 I 9.546E+04 ~ l IFE.55 1 0.000E*60 1 129 97 I 3.885E+t1 1 105-137 I 2.923E*05 I -

IFE.59 I 0.000E+60 I igi.o5- i 8.621E+03 1 105-118 I 6.216E*02 1

=- . -.. . ........................ .. ............ ......

10115B 1 0.000E+H I leg).o, I 3.922E*82 I 194-139 I 8.621E.04 1 tr0-60 I 0.000E+H I ITC 99n 1 5.06*E-42 I 104-140 1 2.113E+01 I INI-6) l 0.000E*H I ITt.101 1 1.450E-93 1 184-141 1 9.472E-05 I fMI-65 I 0.000E+H I IDU-Ini I 7.030E+03 1 184142 1 2.912E.05 1

-.==- ...- .---

100-64 a 6.031E+H I 1m.6 105 l 1.343E*00 I ILA-140 l 0.000E*H I

.. =............ . .... ..... ............ ..................... .

12465 1 7.141E*H I 1110 - l % i 1.93*E 05 I ILA-142 1 0.000E*04 I

. - ....... - . . ~ ........................

12N-69 i 5.946E.62 I I4.llon i 2.124E*84 I ICE-141 I 8.547E+03 I 198-03 t 0.000E*00 I ITE.125n 1 0.000E*0s I IE-143 1 0.36?E*01 I 199 94 I 0.000E+00 1 ITE.127M I 6.364E*H I ICE.144 1 1.171E+06 I

.... ....= - ..

IIII.85 1 0.000E*H I ITE-127 I 7.067E+H I 184-143 I 3.001E+03 I

. . ~ . . . . - - . . ~ . .... ...... . .... - . . . . . . . . . . . . . . . - . .

185 06 1 0.000E+H I ITE.129M I 5.032E+H I 18W-114 I 9.769E.93 I

_=..............

198 84 1 0.000E*H I ITE-129 1 2.560E-41 I IND-147 1 4.81AE*43 I l 188-89 1 0.000E*04 I ITE-131n i 3.996E42 i IW-197 1 0.000E+09 I l 19-49 I 0.000E+H I ITE.131 1 5.093E.02 I l *-? l 9.731E+61 1 19 01 1 0.8HE+00 1 ITE.132 l 1.772E+83 I

...........===- ....

158.H I 0.00E*00 1 it.13e 1 2.444E*t4 I See Note, page 3.0-21 Units: mrem /yr per uCi/m3

! 3.0 '8 . Rev. 1, 11/85 t

Table 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (Pg)*

Page 6 of 7: Dose Factors for Lung I ISOTOPfl lieutATION I I Iciottpfl llantATION I i 19)T(PEI IIMILATION I IM.) i 1.125E+0.1 1 IWJ2 1 2.441E*84 I 11-111 1 4.on e gg i Ir 14 1 6. 73*E+43 I IYAt i 2.616E*05 I 11-137 1 4.00aE+00 I lia-24 1 1.610E* H I lY.91M i 2.812E 43 I 11 111 1 0.000E*00 I I 0.000E*H I i 2.627E*t6 I

..lY-'....................

t 1 0.000E+04 I 18-32 11-114 109-51 1 1.699E*t4 I Y 92 1 2.380E*04 I 11 135 1 0.000E*A0 I

............... ... .'.. ............ ... . =...............

115 54 1 1.576E*04 I lY 93 I 7.437E*H I ICS-lid i 1.21nE*05 I Ilm-56 1 1.314E*te 1 IBt-M i 2.231E*te i 1C5 116 1 1.454E*06 I 181-55 l 1.110E*f4 1 129-97 1 1.132E*f5 1 1C5 137 1 1.040E*05 1 18T-59 6 1.269E*06 i 19-M i 6.14?E*05 I irs.l19 I 6.089E+01 1

-- =...........

100-58 8 1.10eE*06 I IPC ** 1 1.35 0 85 i 15 * -1 1 5.77?E*03 i 100-60 I 7.067F+46 I I TE.** n i 9.50*E+02 1 104-140 l 1.741E*06 I IMI.6.1 1 2.749E*05 I ITE.lhi 1 5.946E+02 I 194-141 1 2.91 0 03 I

..........= .... .... .. .......- _.. ... .. ....................

INI-65 I 9.177E*03 1 1110-14 1 1 6.621E*05 1 154-147 1 1.64tE*03 I

................. = ... ..... ............ ........................

ICO.64 i 9.583E*03 I iHU-In5 1 1.591E*t4 1 18A-140 1 1.029E*05 I

................. ...- =................ ........................

12N.65 i S.953E+05 I tilu-106 1 1.43?E+47 I ILA.142 1 8.6SSE*03 I 17N-ei i 1.4?tE*63 1 18G-Il0N I 5.4hE+06 I trE-lal I 5.43 0 05 I IE8-0* i O.i100E *04 I ITE-125M i 4.771E*85 I ire-143 l 1.154E*n5 I

. . . . . . . - - = . . . _ ... .................. ........................

Ile-Ga f 0.000E*M i ITE-127N I 1.400E+t6 I ICE-144 1 1.195E*07 I

........ .... = -

118-85 i 0.000E+44 I ITE-127 1 1.001E+04 I s pit-143 1 4.32 0 n5 I 185 06 1 0.400E*tt i ITE.129N I 1.761E+H I IPW-144 i 1.565E*03 i 1119- 9 9 1 0.000E*H I ITE-1? I 2.934E+03 6 15-147 1 3.20?Een5 I 189-85 I 0.n00E*00 l ITE-131M i 2.057E*05 i IW-197 I 4.107E* M i ISR-99 1 2.157E+66 I ITE-111 1 2.054E*t) i INP-230 t 5.000H I 158-H I 1.476E+67 I ITE.132 1 3.77 0 05 I 158.H I 5 12Rf*04. I Il-130 i S. tHE* H i See Note, page 3.0-21 Units: mrem /yr per uCi/m3 3.0-19 Rev. 1, 11/85

Table 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.1.b (P.lo)*

Page 7 of 7: Dose Factors for GI-LLI I ISOTnPEI lateLATION I i 15ff(FEl lleeL4 TION I i 190TIFEl lleelLATION I 166- 3 1 1.12*E+#3 I isp.92 1 2. 42*E+ M i Il-111 1 2.942E*03 I IC 14 I e.734E*43 I ly.00 I 2.67 E*H I 81-132 1 3.201E*03 i lieb-24 I 1.610E+44 1 IV.eln i 1.717E 8) 1 II.133 1 5.4hE*03 I IP.32 1 4.218E+44 I tv.91 1 1.83 I 81 134 i S.546E*02 I

.............____....... . .................'E*05 ....... ...- -

=

srs.51 1 1.n0*E+03 I iY.92 1 2.390E*05 i 11-1 % 4.440E*03 I ItW 1 2.290E+N I ly.93 i 3.095E+05 I 1C5-114 6 3.84AE*03 I

..~............ . . ................ ... ..... .....

ItW-56 1 1.232E*M i 129 99 I 6.105E+04 I 1C5-136 1 4.101E+t3 I IFE 55 1 2.860E+R3 1 12591 1 3.511E*05 1 1C5137 1 3.61'E+03 i

=................. . . . . . . . . . . . . . . . . _ . _ ._._.. ..._ .....

IFE 59 I 7.067E+04 I inst 05 I 3.700E+04 e irs.110 1 2.697E*02 i

.. . ........=== -

............... ....... ............=

100 50 1 3.437E*H I irc.o' I 1.265E+05 I ilm.19 I 5.77?E+04 1 -

1C0-60 I 9.620E+N I ITC 9N I 4.810E+03 4 104-148 1 1.010E*05 I

....= =- _=. ._....... ....._... .. ..... -.........

INI.63 1 6.32T+03 I lit.101 1 1.632E+41 I 186 141 1 2.753E*02 i lNI 65 1 0.390E*04 I IAU 101 8 4.474 64 I 194-142 1 2.742E*00 I ICU-64 I 3.670E+S4 I inj.1p i 9.9sTE+N I iLA-140 1 2.25T+05 I I?N-65 8 1.632E+04 I illi)-I ne i 4.297E*05 i ti.4 142 1 7.585E*04 I 12469 1 1.010E+04 I I4-110M i 1.003E+05 I ICE.141 I 5.661E+04 I 18P-93 I 0.000E+00 I ITE-125M I 3.378E+04 I ICE-143 I 1.27tE+05 I IE-04 I 0.000E+94 I ig.127N I 7.141E*34 I ICE-144 1 3.805E*05 I IlW-05 1 0.000E+00 1 ITE-127 I 5.62E+04 I IPII-143 1 9.731E*04 1

== ....... ... . ...___....... .. ...................

lHB-86 1 7.992E+03 I ITE.129M i 1.91T+05 I l* l 1.94E+02 I

.......= _....... ... . .................... ..'II.144 IR9-80 1 1.724E+01 1 ITE-179 I 2.54*E+04 I l@.147 8 9.214E*n4 i t e .........- .. . .........- _. _..................

l i89-89 4 1.091E*06 I iTE.131M i 3.070E*05 I IW.187 I 9.10?E+n4 I

..........._.... _ .............. ........ ___ =..............

l ISR-89 8 1.672E+05 l ITE.131 I 1.332E+n) i 1 *-?" 1 6.401E+04 I 159.90 1 3.434*t5 I ITE.132 l 1.376E+05 I 15R.el i 1.73*E+99 I 11 130 1 5.1 HE+03 I

• -- See Note, page 3.0-21 l

Units: mrem /yr per uCi/m' l

l 3.0-20 Rev. 1, 11/85

NOTE: The Pi o values of Table 3.2-1 were calculated according to the methods of Ref. 6, Section 5.2.1, for the child age group. The values used for the various parameters, and the origins of those values, are given below in Table 3.2-3.

i 4

i ,-

I 3.0-21 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R )*

Page 1 of 21: Dose Factors for Total Body I 11DTIFEl lutlLAilWI I GllMS pus (I GPS /COMILKl 84 1 1 6..anF+42 1 4.eteE*00 1 2.353E+43 I 10 14 i 4.106E*01 1 0.000E+00 I 7.9@te i

........ ............................====-- =

lee-24 1 1.056E+84 I 1.194E*t7 1 2.453E+47 I IP.32 I 7.742E+04 1 0.000E+llo I 9.000E*t9 I

.....===- - .......................... ._

irs.91  : 0. % E*01 1 4.65'E+06 I 2.565E*t5 I Ir*6 94 I 4.094E*t3 I 1.306E+09 1 1.406E+47 I

.. .- .........==-

1996 44 1 2.212E-01 1 9.035E+05 1 8.641E-43 1 tFE.99 I 3.332E+43 I l.000E+00 I 3.712E+07 I trE.s* I 9.479E+t1 1 2.727E*09 I 2.457E+46 I ICD 50 1 1.820E+83 1 3.811E+09 I 9.634E+07 I

~

ICtMO I 1.177E+44 I 2.157E*10 1 3.311E+48 1 tNI 41 1 1.161E+04 1 0.00nE+00 1 1.92*E+09 I INI-65 1 1.231E-91 1 2.970E+09 1 2.071E-01 I in44 1 7.742E.a1 i 6.067E+05 l 1.366E*05 I

. l2M-65 1 3.100E+44 1 7.463E*06 1 1.397E+10 I 12W-69 1 7.182E-43 I 0.000E+00 1 5.5%E-12 I iAR.81 I 3.000E+02 1 4.971E+03 1 1.48AE*00 I

_ __ ==. ..........

ine R4 i 4.004E+t2 1 2.026E*05 1 1.999E-22 I 114B-89 1 2.044E+01 1 0.000E+00 1 0.000E+00 I 118-86 I 9.820E+44 I 8.904E+06 l 1.749E+10 I IlW a# 1 2.97aE*07 I 3.3n?E+04 1 1.634E-44 I

................. ==......- ......... .....

IGB A9 1 2.099E+#2 i 1.23hE+n5 I 3.741E-52 I

...- ......... .=.............................

1 9 -09 l 1.141E+a4 I 2.162E*04 1 5.741E+00 I

.............- .- - -_=....... ...........

19 90 1 2.590E+ad I 0.000E+no i 4.925E+10 I

. ..._........== ...-- - ===... ..............

158 61 1 3.45AE+44 1 2.1 @ 46 1 1.564E+04 I See Note, page 3.0-43 Units: Inhalation - mres/yr per uCi/m3 Others -

m2 arem/yr per uCi/sec

, 3.0-22 Rev. 1, 11/85 r

(

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R )*

Page 2 of 21: Dose Factors for Total Body I 190TfWl heet ATIfW I G80UIC Pt.ApEI GIPMDhintit.KI 158-97 1 3.9A6E.01 1 7.769E*05 1 2.747E-01 I 17.94 I 8.020E*61 1 4.491E*03 1 2.90AE*01 I tv.91M i 1.taAE-02 1 1.002E*05 1 3.051E-20 i tv.91 1 1.5e0E*04 1 1.073E*06 1 3.104E*03 I IV-92 I 4.606E-01 1 1.804 + 05 1 2.404E-09 I ev.91 8 4.074D00 l 1.052E*09 I 9.745E-42 I 179 95 1 2.019f*04 1 2.446E+04 1 1.871E+03 I t79-97 t 1.170D01 1 2.960E*66 1 5.065E-01 I l

• 95 t 3.76aD03 1 1.4ASE*09 1 2.270D95 I t*C 99 I 3.234fe01 1 3.995E+04 8 6.453E+07 1 sir 90M i 3.724E-02 l 1.841E+n5 1 1.161E*t3 I

..... == _.....- -

ITr-101 1 0.120E-84 1 2.034E*04 1 4.525E 58 i

... ........... .............._ =.... .

iaktni I 6.790E* t2 1 1.004D06 1 4.615E*t3 I imbl05 1 4.102f.01 1 6.343E*05 1 4.315E-63 I

. ........= ............ ... ...... .....

lab 106 1 1.069D64 1 4.200E+09 1 3.781E+04 I tag.llan i 4.ogohg3 1 3.445E+09 1 2.965D64 I

... _- ..... ___.-- =. . .

ITE-125M i 6.5AnE+n2 I -1.552E+06 i 3.241D07 I

..............= _ --

ITE-127M i 2.072D03 I 9.165E*04 I 8.10SD07 I ITE-127 1 4.886E-81 1 2.994E*03 I 2.214E*03 I ITE.12*fti 2.226E*01 1 1.972E* 07 1 1.364E+00 I

.. =- ....-- .... . - - ---.....

ITE-124 I 1.876E-82 1 2.6ngE*04 1 7.798E.18 i ITF-131M i 3.626E+41 I 8.026E+06 8 1.785E+96 I

TE.131 1 4.998E-41 1 2.919E*04 1 1.53nE.32 I ITF.132 1 1. 764E* 62 1 4.22.iE+06 i 1.54eE+47 I II.13A i 5 572f*03 1 5.911D66 I 4.Ht7D 96 I See Note, page 3.0 Units: Inhalation - mren/yr per uCi/m3 Others - m2 arem/yr per uCi/sec 3.0-23 Rev. 1, 11/85 i

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 3 of 21: Dose Factors for Total Body I 19ff(PEI II6etail0ll I 99m00 pupEl GRS4tWolluti I1 131 1 1.96AE+84 1 1.771E+47 1 2.24X+P9 I Il-132 1 1.250E*03 1 1.245E*66 i 1.646E*99 I 11 133 1 5.60DE+03 1 2.491E+t4 1 2.469E+07 I 11-134 1 6.65 3E+42 1 4.46?E+05 1 2.83*E-11 I 11 1'I5 1 2.77x+a3 1 2.576E*06 1 1.296E*99 I 1C5-134 1 7.448E+04 I 6.961E+09 1 1.093E*10 I 1C5-136 1 5.?ME*S4 1 1.587E*06 1 3.44X+09 I 1 4.550E+44 1 1.834E+10 1 6.792E+99 I

.'CS-137 105 139 i 3.076E+02 1 3.52*E+05 1 1.051E-22 1

-____=,.. ............- ===..

l% 130 t 4.?9RE-82 1 1.061E*05 1 2.09'E-08 i 1%-140 1 2.R W +03 I 2.053E+07 l 1.976E*67 I 1 2 141 i 4.979E.43 1 4.172E+64 1 2.00EE.46 I

.............. ........... .....__ ===..

1%-142 i 1.960E a3 4.445E*A4 I 0.000E*00 I ILA-len I 5.152E*01 1 1.921E*07 I 6.551E+49 I It A.142 9.044E-02 I 7.60?E+05 1 2.41&E-11 !

ICE.141 1 1.909E*83 1 1.3HE+07 1 4.953E*43 I

__..... . ..=== -- - - ........

ire-143 1 2.212E*01 1 2.31?E+n4 1 4.779E*01 I

...............__ . = _ ....................

l l

ICE-144 1 1.764E*#5 I 6.946E*07 1 2.073E+Pi i l lPil.143 I 6.966E+82 I I.000E+00 1 1.172E+02 I l .. ........ ....... .... .. .. .....

l 88 1 2.400E-43 1 1.837E*03 I 5.215E-54 I

\ ..'II.144 I

t .

180-147 I 4.*CRE*02 1 8.400E*66 I 9.031E*0) I 4-197 1 1.122E+88 1 2.3e0E+06 1 2.340E+04 I le.239 1 1.876E+01 1 1.796E*t6 1 2.923E+49 i l

t 1

1 See Note, page 3.0-43 .

Units: Inhalation - mrea/yr per uCi/m3 Others - m2 arem/yr per uCf/sec l 3.0-24 Rev. 1, 11/85 l

i f

l

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 4 of 21: Dose Factors for Bone I INTpEl Imatail(M I Wikpe PueEl WS/EtnintILKI lH-3 1 0.AAM*at 0,004E+44 1 0.000E+00 I IC-14 1 2.64AE*04 1 0.00DE*00 1 3.72?E+t9 I 1624 8 1.05eE*l4 1 1.194E+47 1 2.453E+17 I IP-32 1 2.03nE+66 1 0.000E*00 1 2.549E+11 I 109-51 i Geo0nE*H I 4.6SSE*66 I 0.000E+H I It96-54 1 0.000E*t6 1 1.386E*09 I 0.000E*t0 I 1896- % 1 0.000E+00 I 9.835E+05 1 0.0lE+M I 14 95 1 1.074E+N I 0.00nE*08 1 2.15flE+00 t

.... ........... _ ...... ..... ... =... ....

14 59 1.157E*l4 i 2. 72E* 00 1 3.56*E*t0 I

...............= ==. _............ .. ...

ICG 50 i 6.00GE+60 i 3.911E+69 i 6.066E+H i ,.

ICD-40 1 0.00nE+86 1 2.15?E+10 1 0.000E*00 I INI-43 8 3.390E+95 I 0.00nE+00 I 5.559E+10 I

....... =======- -..............................

INI-45 1 2.304E+#6 1 2.97aE*05 I 5.576E+04 I .

..=- -- . =.- __=............................

ICtb64 1 0.000E+ho I 6.067E*09 1 0.000E+00 I 124-65 1 1.03?E+N I 7.463E+na I 9.033E+09 I 174-49 I 5.3eng.e2 1 0.000E*00 I 4.177E-Il I 19-63 1 0.000E**0 1 4.07)E+03 1 0.000E*00 I

.....== ...........................

1 5 -44 1 0. 000E*H I 2.076E*05 I 0.000E+80 I 1 5 -45 1 0.000E+H I 0.000E+06 1 0.000E+49 I 305 46 1 0.000E+H I 8.oa4E+06 1 0.000E*04 I 109 40 1 0.nonE+H I 3.307E*04 1 0.000E*00 I In6 99 0.000E*08 i 1.230E*05 1 0.000E+00 I

.................. - .....---- =......

1 9 -49 I 3.ShE+05 1 2.162E+84 1 2.002E*10 t

. ...........= .............................

19-HI i 4.099E*47 1 0.0ME*00 1 1.934E+11 I

................= ..............................

19 91 i 9.56?E+01 1 2.1*E+M I 4.320E+as i

............... _ =..........................

See Note, page 3.0-43.

Units: Inhalation - mrem /yr per uCi/m3 Others -

m2 arem/yr per uCi/sec 3.0-25 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o}*

Page 5 of 21: Dose Factors for Bone I ISOTIMI flesteilt i EsmMO PleMFI G86/C0lHelLI(I I48-92 1 1.059E*01 1 7.768E*45 8 7.395E*06 I lY.99 I 3.290E*03 1 4.49tE*03 1 1.004E*I) I Y 91N I 1 1.0n2E+ns I 8.954E-te i

.'.. . . ===----4.074E-01 Y-91 1 9.000E+05 1 1.673E+06 I

.'. .. ...................... ...... .. . .1.169E+05 I lY.92 1 1.639F+01 1 1.804E*05 1 8.554E-04 I

~

lY 93 6 1.49PE*02 I 1.852E+05 I 3.47V+00 1 170.95 1 1.1 W +05 1 2.44AE*08 1 1.06?E+94 1 129 97 1 1.499E+02 I 2.960E*04 I 6.462E*04 I -

It4L.95 1 1.560E*04 1 1.dn4E*08 I 9.532E+49 I

.be 44- 0.000E+69 i 3.945E+96 i 0.000E*46 I '

TC.95M i 1.394-63 1 I 4.372E+61 I

.'... .............. .... ...1.041E+05 .

ITC.10i I 6.510E-05 1 2.034E+04 I 3.630E-59 I tkt-1A1 I 2.016E*63 1 1.0a4E*00 1 1.300E*64 I

. ...===== - .. .-- .. -=

I 18'l-10' i 1.224E+00 I 6.341E*05 1 1.29tE-92 1 t#tt-104 I 8.600E+64 I 4.2 nae *00 I 3.027E+05 I

__ =.... ....--- ....

ser 110n i o.9a2E*03 1 3.446E+00 I 6.13 E+09 I ITE-125N I 4.760E+A3 I 1.552E*06 1 2.390E*09 i

~

lie-127N1 1 566E+64 I 9.165E+0 I 6.700E+99 I ITE-127 1 2.226E+t6 1 2.994E+63 1 1.430E+64 I ITE.12*n i 1.414E+84 1 1.972E*07 I 8.85AE*t0 I

ITE.129 I 7.682E-62 1 2.600E*04 1 3.340E-t* I l ...== -- - - ......- ...

~

ITE-13tM i 1. NAM +02 I 8.0NF 04 I 5.372E*06 I ITE-131 1 1.79E-92 1 2.910E*04 1 5.45?E.32 e i ...............=- . -

ifr-137 i 3.724E*02 1 4.??3E+06 8 3.346r+s7 i If-130 1 6.356E+03 I 5.511E+86 I 5.646E+64 I l

[

• -- See Note, page 3. 0 Units: Inhalation - mrom/yr per uCi/m3 Others - m2 arem/yr per uCi/sec l 3.0-26 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 6 of 21: Dome Factors for Bone I ISOTOPEI licentATIUM i GIOlse PueEl GIS/tmHiltXI 11-111 1 1.?* 4 04 1 1.721E*07 I 4.32?E+99 I 11 132 i 1.6%E*01 1 1.245E*4 1 2.280E+00 I 81 133 i 1.12d+04 8 2.451E* N I 5.769E+07 I 11-134 1 0.212E+n? I 4.467E+05 1 2.79 I

...............=__ _ - ........... ...'E-Il 81-115 i 3.864+n) i 2.526E+% 1 1.786E+05 I

..............=- = ..................... ....

ICS-134 1 3.S62E*a5 I 6.863E+R9 I 5.803E+10 I irs.136 i 4.ninE+04 1 1.502E+09 1 3.135E+49 I

... ...............-- -- ====...............

1C5-137 I 5.490E*05 1 1.030E+10 I 8.18?E+11 1 405-139 i 5.05aE*02 1 3.5F'E+05 l 1.334E-22 I 8AA-139 i 1.484*na I 1.061E45 1 7.21*E-07 I -

894-144 1 5.600E44 8 2.053E+07 I 3.835E+00 I l84-141 1 1.569E-nl I 4.17?E*04 1 6.611E-45 I

. ............ = = ........ ................ .

104-142 1 3.076 E.02 4 4.445E+A4 1 0.000E*04 I

..... ................===------- =..--- - - - - - . .

ILA-lan i 5.n54602 l 1.921E+07 1 6.460E+01 I ILA-142 8 1.030E+n8 I 7.602E+05 1 2.751E-It 1

=......................................

ICE.141 1 2.772E+he i 1.366E*07 1 6.899E44 I IfE.141 8 2.026F4? I 2.312E*06 1 6.311E42 I ICE-144 I 3.192E+N i 6.946E+07 1 3.699E+46 I 1911141 1 1.40nE44 1 0.0ARE+08 1 2.365E+03 I 1P11-144 I 4.784E.82 1 1.837E+03 1 1.035E.52 I l 110 147 1 7.91AE43 1 8.400E+4 1 1.404E*83 I

\

12-107 e 1.296E*#1 1 2.360E+06 I 9.738E*04 I l 18-239 I 3.710E42 1 1.7860M 1 5.794 Del I l

See Note, page 3.0-43.

, Units: Inhalation - mren/yr per uCi/m3 t

1

, others - m2 arem/yr per uCi/sec

, 3.0-27 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R )*

Page 7 of 21: Dose Factors for Liver I ISOftPEI  !* eel.nTimi I GilGM) Pue(I G8MDluf91LXI m1 6 6.468E+0? I 0.080F+04 8 2.391F*01 I IC-14 5 5.30AE*63 1 0.40nE*0A I 7.oanE*06 I

. ............... ..==- -..................

Iht-24 1 1.056E+64 1 1.194E*07 1 2.453E*07 I

............-- = ...... ................-

ip-32 1 1.124E+65 1 0.000E+98 1 1.49 m 16 I

....- .= =.. ....- ...... ........

(8.51 i at.onnF+a0 1 4.659E*04 1 0.000E+00 I

. . . . . . . . . . . . . . . . . . . . . . = = - - .-- ....

' Ir96 54 1 2.534E*04 1 1.386E+09 I 6.205E*07 1 If96 56 i 1.54K+00 1 9.035E*05 1 5.013E-82 I IFE-55 i 1.175F+04 1 0.000E*08 I 1.30*E+99 I ~

err.cs i 2.357E+04 1 2.727E*04 I 4.234E*04 I irn Sa i 1.21*C+A3 1 3.411E*Aa i 3.862E+47 I .

len.ed 1 0 022E+03 1 2.152E*14 1 1.402E+66 I lui-63 i 2.044F+04 1 0.0anF+00 t 3.43AE+99 I INI-65 e 2.94?E-01 l 2.970E*05 t 6.31?E-41 I 101L64 i 1.076E*t0 1 6. 067E* 05 1 2.9'1E+05 I 12W-65 1 6.248E+64 1 7.463E+A9 I 3.02*E+19 I

....===_ ==. - .................

122-69 i 9.674F-02 1 0.000E+0A I 7.521E-11 i Iss.83 1 4.000r+00 1 4.071E*03 1 0.000E*90 I 198 44 i 0.000E*00 1 2.026E+04 1 0.000E*04 I 198-45 1 0.000E+04 1 0.000E*0n 1 0.000E+00 I 1 8116- 4 4 1 1.904E*04 I 8.984E+06 1 3.540E+10 I 104-48 1 4.57?F+92 1 3.307E+94 1 2.*S?E-44 I IPIL-49 8 3.20AE*02 I 1.230E*05 I 5.43lE.52 I

............- - ......- ==.-

19 99 1 0.000E*00 1 2.14?E+44 1 0 00nE+At I

.. ..........= -

- =.......... .........

10-96 e 0.00nregn I 0.000E*00 1 0.nonE*00 I 158.91 i 0.000E+60 1 2.140E+td I 0.000E*08 i See Note, page 3.0-43 ,

Units: Inhalation - mrem /yr per uCi/m3 Others -

m2 mrem /yr per uCi/sec l 3.0-28 Rev. 1, 11/85 t

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 8 of 21: Dose Factors for Liver I 19MWEI IIIEMIGl i M PUIEl IBileMetLKI 19-4 I 0.0 toe +#6 I 7.76aE+05 I 0.09E*M i IY- t 1 0.000E+00 1 4.401E+03 1 0.048E*H I lY 91M I 0.000E+nt i 1.00?E+R5 I I.00f(+M I lY.91 1 0.000E+00 1 1.073E+06 1 0. 00 f(+M i iY.92 1 0.000E+00 l 1.gn*E*05 1 0.000E*H I IV-9'l I 0.00nE+00 1 1.852E+05 1 0.000E*H I 124-95 1 2.796E*04 1 2.446E+n9 1 2.63AE+03 I I?lt.97 1 2.562E*01 1 2.960E+n6 1 1.10*E+M i 14 ** I 6.4?^E+03 1 1.40*E+na I 3.926E+05 I

... ............. ........==-- - ...............

t rf)- l 1.65?E+02 1 1.905E+96 1 3.30*E+at I ..

. .'9 ITE.*9M i 2.894E-03 I 1.841E+05 I 9.017E+91 I

..==-= = ---- ......... . .. ...............

ITE-101 I 0.232E.n5 1 2.034E*04 1 4.571E 59 I 1810-103 1 0.00nE+00 1 1.004E+09 I 0.000E+M i

.................. .__.== ................. ..

1110-1 05 1 0.00nE*00 I 6.36tE+05 I 0.000E*M i

......... ......- =............................

' lill.LIN I 0.n00E+00 I 4.209E+09 I 0.00nE*00 I 18G-11tn I 7.224E+03 1 3. 445E* H I 4.4GlE+08 I ITE-125M i 1.00aE*03 i 1.552E+n6 I 8.019E*I7 i ITE-127N I 6.002E+03 1 9.165E*04 1 2.222E+00 I ITE-127 8 9.934E-Il i 2.994E+0} I 3.450E*t3 I ITE-129M i 6.000E+03 1 1.97?E+07 1 3.030E*II I ITE.129 1 3.472E.a? I 2.608E+04 1 1.151E-09 I

.. ........._- ==............._......... ....

ITE-131M i 5.502E+01 1 0.026E+n6 1 2.163E+06 I

. ......== ..................................

ITE.131 1 0.218E-41 1 2.91 1 2.013E-32 I

. .. .......... ...........'E+04 -- ====

ITE.112 I 2.366E*62 1 4.223E+06 I 1.65N+07 i 11 139 1 1.16T+84 I 5.511E+N I 1.242E+07 See Note, page 3.0-43.-

Units: Inhalation - mrea/yr per uCi/m3 Others - m2 arem/yr per uCi/sec 3.0-29 Rev. 1, 11/85

l I

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R.jo)*

l i

Page 9 of 21: Dose Factors for Liver I 150TOPEI liessaTION I GelR90 Ple(I 9@011Ml1LKI 11 131 i 4.4 tee +A4 1 1.721E*67 I 5.09'E+09 I 1I.1t? I 3.54?E*03 1 1.245E*0a i 4.62*E*00 I

.. ............... == -- ==

II.13.1 e 1.91M*04 1 2.491E*06 8 8.3ME*07 I II.134 i 1.A76E*03 1 4.467E*05 I 5.733E-11 I II.139

• 7.e0?E+n3 1 2.524E*04 1 3.993E*05 I

- 1C5 134 1 7.07M+09 I 6.861E*04 1 1.88?E*11 I 1C5 134 1 1.344E*09 1 1.582E*09 I 9.219f*0' I 105 137 4 6.119E*05 l 1.03E*10 1 0.981E*18 1 les.13a i 7.Al?E+02 1 3.50*E*05 l 2.16*E-22 I IF4110 1 9.947E.04 1 1.061E*05 1 4.785E.10 I ,

IP6-148 1 5.40E*01 1 2.053E*07 I 3.835E*09 I

.... ... . =-_ ............. _

lea-141 i 1.878E-04 1 4.172E+04 I 4.529E-48 I 1 % 147 1 3.1n4E.09 I 4.445E+04 1 0.nonE+08 i liA.144 1 2.002E*02 1 1.923E*07 I 2.547E*01 I Ita.14? I 3.766E-01 I 7.60?E+09 1 1.010E-10 I ire-141 1 1.646E*04 I 1.346E+07 I 4.207E*04 I

.... .......... --=.. .... -

= . . .

trE-tet i 1.9t?E*02 1 2.312E*06 1 4.100E*05 I Irr.144 1 1 211F+86 6 6.946E+07 I 1.514E*06 I IP#.143 I 5.23AE*03 1 0.009E*00 1 8.844F+0? I 19#.144 1 1.94E-02 1 1.837E+03 1 4.004E-53 I

~

6 147 I 8.13#+03 1 8.409E*06 1 1.442E*03 l

.'.. ...= ___=...................................

lu-107 8 9.01AE*00 1 2.360E*06 I 6.772E*04 i l t W.2.14 1 3.11M+01 1 1.786E*06 1 5.174E*00 t See Note, page 3.0-43 Units: Inhalation - mrem /yr per uCi/m3 Others - m2 arem/yr per uci/sec 3.0-30 Rev. 1, 11/85

1 l

l l

1 l

l l

Table 3.2-2 1 PATINAY DOSE FACTORS FOR SECTION 3.2.3 (Rgg)

• Page 10 of 21: Dose Factors for Thyroid I ISOftPEI leew.ATISI I IMUS PueEl GIS/tth9tfLi(I 64 3 - t 6.469E+02 1 0.008E*00 1 2.35X*t3 I IC-14 1 5.306E*03 1 0.000E+00 1 7.940E+00 I iMA.24 1 1.056E*04 1 1.19 0 07 1 2.45W+07 I IP.32 1 0.000E+00 I 9.000E*00 1 0.000E*H I 109 51 1 1.75 0 01 1 4.659E*A6 1 1.674E*05 I t rt6-54 1 0.088E+00 1 1.386E*09 I 0.000E*H I m6-96 i C.000E*00 1 9.0ME+05 1 0.000E*H I 1E-95 1 0.000E+00 1 0.000E+00 1 8.000E*H I .

.'R 59 I 0.00 0 00 1 2.727E*08 1 0.000E*00 I

.............. == - - ....

100 59 1 0.00 0 00 1 3.811E+09 i O.000E*00 I

................ ............. __ __=........... .

ICD-40 1 0.00 0 00 1 2.152E+10 1 0.000E+88 i

. ........ ___=...... ..............

IN1-63 I 0.000E*00 1 0.000E*00 1 0.000E+H I INI-65 1 0.00aE+no i 2.970E*05 1 0.000E+08 I 1C13-64 1 0.00 0 00 1 6.06'E+05 1 0.000E*H I

, 12465 1 0.00 0 00 1 7.463E*09 I 0.000E+H I

= . . . . . . . . . . . . . .

I ?4-+9 I 0.00 0 00 1 0.000E*00 1 0.000E*te I

.......--= _.. .......- -

IM-83 1 0.00 0 00 t 4.071E+03 I 0.000E*30 I 1 9 -94 1 0.009E+00 1 2.026E+05 1 0.000H I IIIIMIS I 0.00 0 00 1 0.000E*00 1 0.000E*H I tilH16 1 0.00 0 00 1 9.994E+06 1 0.000E+H I IRB A9 I 0.00 0 00 I 3.307E*n4 1 0.00nE+44 I 1119-09 I 0.000E+00 1 1.23nE*05 1 0.00 0 00 I l 1 9 -09 1 0.00 0 06 1 2.lo?E+64 1 0.000E+99 I

.......-- - =.............................

6 9 -90 1 0.00 0 A0 1 0.OnnE*00 1 0.000E*H I 1 4 .01 1 0.00 0 00 l 2. idle + N I 0.999E*06 I

............==- ............ ... .......

• -- See Note, page 3.0-43 ,

o Units: Inhalation - mrem /yr per uCi/m3 Others -

m2 arem/yr per uCi/sec 3.0-31 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSF: FACTORS FOR SECTION 3.2.3 (Rqg)*

Page 11 of 21: Dose Factors for Thyroid 6 19fm1Pri liest ATION I G30lM PLaeEl G95/C0iMtfu(I 1 9 -92 1 0. ANE*H I 7.769E+05 1 0.000E*08 I tv.9a i 0.n04F+00 1 4.491E*01 1 0.000E+0A I tv.91tt i 0.000E*H I 1.002E+05 1 0.008E*00 I IV.91 I 0.000E+H I 1.073E+N l 0.00E*H I lY-92 8 0.000F+H I 1.8n4+05 1 0.0n8E+00 I lY-93 1 0. 00 AE*H I 1.952E*05 l 0.000E+H I

, 129-98 ,8 0.000r+00 I 2.446E*06 I I.00E+00 1 129-97 I 0.000E+00 1 2.960E+N I 0.000E+H I -

1 4 -95 i 0.000E+00 1 1.409E+00 1 0.00nF+H I im-98 1 0.0nk+H I 3395E*06 1 0.nenE*H I -

ITE-98N I 0.n00E*H I 1.941E*05 1 0.000E+H I iTC-101 1 0.000E*00 1 2.034E*04 1 0.000E+M i tott-101 1 0.000E+H I 1.094+00 1 0.n00E+00 I I h 105 1 0.000E+00 1 6.363E+05 1 0.000E*00 1

= ......

Ipl)-len 1 0.0A0E+00 1 4.200E*0a 1 0.00nE+00 I lag-11 2 i 4.000E+00 1 3.445E+09 1 0.000E+00 I ITr.12sm i 1.424E+03 l 1.55?E*04 I 9.071E+07 I

=......- .._ . ..

ITE-127M i 4.072E+03 I 9.165E*04 1 1.93EE+H I

ITE-127 1 1.948E+00 1 2.994+03 I 8.392E*03 1

=

1 l ITE.120M i 5.47E+03 1 1.972E*07 1 3.401E*II I ITE-129 I 6.740r-02 1 2.600E+04 1 2.74*E-09 I ITT-13tM i 9.93?F+01 1 0.026E+06 1 4.391E*H I

.. ..... ..- _=.. .. .....= __ ..

I ITE-111 8 1.5R2E-02 1 2.919E+04 I 4.863E-32 1

_==-- . ......-- ..._

! ITE-137 I 2.796E*02 1 4.223E*06 1 2.445E*07 I It-134 1 1.594E*H I 5.511E+46 I 1.193E*09 I

................- _............... =....

i l

See Note, page 3.0-43 l

t Units: Inhalation - meem/yr per uCi/m3 others -

m2 arem/yr per uCi/sec 3.0-32 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R.jo)*

l Page 12 of 21: Dose Factors for Thyroid I 190TOPEI IIceLATillis I Gil0ND pl#El GRS/Cthl/MILKI it.11f I 1.444E+n? I 1.721E*47 i 1.675E+12 i t!.132 i 1.694E+ns i 1,24sE*nd I 2.170E*02 I 11-111 I 1.55eE+n6 1 2.451E+06 1 1.527E+10 I 11-134 1 4.45?E*04 I 4.467E+05 l 1.337E-09 I 81 115 i a.05aE**5 1 2.5?AE+06 I 3.195E+87 I Irs.114 I n.000E+A0 1 6.9 ate +n9 7 0.00E+00 I 1C5 136 1 0.00nE+DO I 1.5B?E+n9 1 0.000E+tt i

~

105-137 1 0.00nE+60 i 1.0tnE+10 1 0.00nE+tt i

_ =.....=_ - = = . - - _ -................

105-1'8 8 0.008E*A0 1 1.549E**5 1 0.000E+nt t i9A-110 i n Def**nn i 1.0^1E+44 1 0.000E+49 I ..

.- - =__ _ .............................. .....

t94 140 1 0.008E+00 1 2.051E+07 1 0.000E*00 I 194-141 1 0 000E+00 1 4.172E*04 I 0.00nE St i

. = = =.... .................................

i94 142 1 0.00E+00 1 4. 444E* H I 0.00hE+44 1

==== - - - - _ = . . - - - ===...- ... .

ILA-140 1 0.00nE*00 1 1.9?iE*07 I 0.00nE*00 I ILA-142 1 0.00nE+n0 I 7.6 ?E*05 i O 000E*00 1 17 141 1 0 nnnE+ng I 1.3e6E*07 I 0.0ASE+00 t

............. _==......................___.....

irf-143 1 0.00nE+no 1 2.31?E+06 1 0.000E*00 I IE-144 1 0.00r(+00 1 6.944E*07 1 0.000E*00 I 18#.143 1 0.00nE*00 1 0.000E*00 I 0.000E+00 I IPR-144 1 0.000E+n0 1 1.917E+03 1 0.000E*99 I

. . . . . . . . . . . . . . . ...................... __=..14-147 I 0.00aE+00 1 0.4%E+n6 I 0.000E+89 I

..............- =...........................

IE 197 1 0.00nE*00 1 2.3*0E+44 1 0.00nE+04 I INP-219 1 0.0n4E+#6 i 1.744E+ % I 8.008E+89 I See Note, page 3.0-43 Units: Inhalation - mres/yr per uCi/m3 Others -

m2 arem/yr per uCi/sec 3.0-33 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 13 of 21: Dose Factors for Kidney I 19nTOPD Iwat ATION I GeolM Ple(I GDS /C0wfllLKi Iw.) 1 4.46ar.02 1 0.000F+0A I 2.353E+03 I IC.14 1 5.306D03 I t.00nE*00 1 7.94aE*00 I IN6-24 1 1.056E+64 1 1.194E+07 1 2.493E*t7 I

.. ............. ... ......... - -=. .

IP 32 1 0.400E+00 1 0.000E+00 1 0.00K+00 1 109.41 1 1.323D01 1 4.659E+06 1 3.657E*44 I

. 1796-54 I 4.004E*t) I 1.386E+09 1 1.375D07 1 1196 56 1 1.10nE+00 1 9.035E*05 1 4.300E-02 I 4-55 1 0.000Det I 0.It0E+60 1 6.00E*t0 1 irt.50 1 0.000E+00 1 2.727E*00 1 4.000E*t0 I Irn.49 1 0.00nE+00 1 3.811E+09 1 0.000E+00 I ..

................ _=

100-60 1 0.n0E+04 1 2.152E+10 1 0.00E+tt i INl.63 l GI000E*00 1 0.000D00 l 0.000E*t0 I INl.64 1 0.000E*00 1 2.970E*05 l 0.000E+00 I

. ..... .................. =__.......

10J-64 l 3.074D00 1 6.067E+0E I 4.9990 M i Ih5 1 3.2hE+64 i 7.463b00 154690105 87W.40 1 4.010F-t? I 0.000E*00 1 3.125E-11 1 ipe.83 6 0. A00D00 1 4.871E+03 I 0.000D40 I 188 04 1 0.000E*t6 1 2.026E+05 1 4.000000 1 198 85 1 0.000D00 I 0.000E*06 1 0.000Dtt i 189-06 1 0.000E*t0 1 0.984E* 06 I t.000D00 I top.80 1 0.000r+40 1 3.307E*04 1 0.004Dit i

.... .................. ... _ _=.....---

186-95 i 0.000D00 l 1.230E+05 1 0.00nE+06 I 158-99 I 0.000D00 1 2.162E*04 1 0.00AD46 I 158 94 1 0.fl00E+00 1 0.000E*00 l 0.000D66 I

............-- .............--- ==......

158- 0 1 8.800E*A0 1 2.14flE+46 1 0.tanDet I t

See Note, page 3.0-43 Units: Inhalation - mres/yr per uCi/m3 Others -

m2 arem/yr per uCi/sec 3.0-34 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R g)*

Page 14 of 21: Dose Factors for Kidney I 190T(PEI IttelLATION I GIGAO PueEl 9tS4:mHilLl(I iAN.92 1 6.000E+00 1 7.?e8E*M i 8.000E*tt I iY.00 6 0.00nE+04 I 4.491E*03 1 0.000E*00 I lY-91N i 0.000E*00 1 1.00?E*05 I t.000E+00 I iv.91 1 0.000E+00 1 1.073E+86 I 0.000E+00 I iv.92 I n:nonE*90 1 1.604E+04 1 0.000E+08 1 iY.81 1 0.000E+00 1 1.852E+05 I 4.00nE+00 I

......................... = . ...... .... ..

IN-M i 3.100E+nd i 2.446E*00 1 2.941E+03 I IN 97 1 2.590E+41 1 2.960E+06 1 1.110E*t0 I iiE 05 1 4.719E*43 i 1.400E.66 1 2.61E+05 I im.00 1 2.64^E+0? I 3.055E+06 i 4.944E+66 I -

ITC.com i 3.1paE.82 1 1.041E*45 I 9.760E+02 I

.........-__ =..............................

ITC.1nt i 9.78,i.04 I 2.014E+nd I 5.437E 90 I Illii.In1 8 4.242E+al I 1.094E+08 1 2.871E*04 I ley.105 I 9.9gaE.01 1 6.h3E+05 I 9.420E-t? I 199 106 1 1.0e 1 4.20AE*68 1 3.900E+n$ i

................"E+05 ....................................

IAG-110M i 1.097E*H I 3.445E*09 I 6.41pE*00 I ITE-195N i 0.00nE*60 1 1.552E*n6 1 0.000E*t0 I ITE-12711 1 3.75?E+04 1 9.16 E+04 1 1.64 E+49 I 5

ITE-127 I 4.058E+44 1 2.994E+03 1 2.513E+N I ITE.12*ft i 3.17AE+N I 1.972E*07 1 2.214E*t9 I l ITE.lM i 1.75nE-01 I 2.600E+n4 I g.315E-09 i

! ITE.131M i 2.44^E+n2 I g,g26E+n6 1 1.485E+07 I l ............. -...............................

ITE-111 1 3.99hE.n? I 2.91'E*04 1 1.394E.11 I ITE.112 1 1.035E+03 1 4.223E*06 1 1.03*E+Rt i 11-110 1 1.92AE*H I 5.511E+06 1. 1.H*E+07 i

• -- See Note, page 3.0-43 .

l Units: Inhalation - mre'm/yr per uCi/m3

! Others -

m2 ares /yr per uci/sec l 3.0-35 Rev. 1, 11/85 I

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (Rigg)*

Page 15 of 21: Done Factors for Kidney I ISOTC8tl ImnL4 TION I 91390 Pld8(l 9PS/E0luntuti II.131 1 5.igeE+94 1 1.721E+97 I i

................. ......... 5.'54+ 98..

il-131 8 3 048E+03 1 1.245E*06 1 5.169E*04 I

... ......... =...... _ . _ . .

II.131 1 2 ?4AE*64 1 2.451E+06 I 9.076E+47 I II.134 1 2 086E+03 1 4.467E+05 1 6.410E.11 I 11-138 i 8.47AE+63 1 2.526E*06 1 3.961E*19 i KS-134 1 1.994E*05 1 6.863E*09 1 2.796E+10 t irs.134 1 5.642E+44 1 1.502E*06 1 3.674*t9 I .

Irt-137 1 1.722E*05 1 1.030E+10 1 2.572E*10 I trs.13a i 4.102E*02 1 3.509E*05 1 1.092E-22 I

.... -..- ===--_ .= .

@-l N I 5.422E.04 1 1.661E*05 1 2.976E-18 I 11%.14A 1 1.343E*01 1 2.053E+07 I 9.104E+04 I are.141 1 6.496E-05 8 4.172E+04 I 2.723E-40 t 15%.14? I 1.904E.oS I 4.445E+04 1 0.000E+44 1

=- --- -

'.iLA-148 1 0.00AE+00 1 1.923E*07 I 0.00AE*tt 1

It A-147 1 0.000F*00 1 7.602E+05 1 0.004E*t0 I ICE.141 I 5.25E+03 1 1.46E*07 1 1.297E+44 I irf.141 I 5.64?E*01 1 2.312E*04 1 1.226E*02 I ire.144 4 5.376E*45 1 6.946E+07 1 6.120E*95 l

! IEI~41 1 1.974E+96 0.000E*04 1 3.297t+02 I N -144 I 6.720E-13 1 1.937E*03 1 1.451E.53 i i -

@ .147 4 3.150E*n3 1 q.40er+06 I 5.55'E*42 I t =- ..... .- . ............. ...

l 'u-197 8 0.000r+44 1 2.360E+06 1 0.0n*E*68 i ll*.219 I 6.622E+41 1 1.796E*t6 I 1.932E*01 I I

l I

l See Note, page 3.0-43 .

j Units: Inhalation - mren/yr per uCi/m3 Others -

m2 arem/yr per uCi/sec 3.0-36 Rev. 1, 11/85 l

I 1

l

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (Rg )g)*

Page 16 of 21: Dose Factors for Lung 1 INT (PEI leonaTICW I GilGM PulpEl ERS/CSMlltXI 1 6.469E*02 1 0.000E*no i 2.191E+91 I H-1 it.14 1 5.30AE+A3 I 0.00nE+60 1 7.940E*40 I Heb-24 1 1.056E+04 1 1.luE+87 1 2.453E*t? I IP.12 1 0.000E*00 1 0.000E+00 1 0.000E*H I Int 61 1 1:20 @ 04 1 4.65 I 3.257E+05 l

..............................'E+n6 .......... ...... ..

it96-54 1 0.04E+#5 i 1.306E+09 1 0.000E+M i IE56 I 1.291E+a4 i o.035E+ns I t . H0E* M i IFE.55 I 8.A4E*nd 1 0.008E+#9 I 6.78 E+47 I 1 4 .54 I 1.ntSE+a6 I 2.727E+A0 1 1.94?E+08 I

~

ICO.58 1 7.77AE+05 1 3.811E+09 I 0.000E*00 1 100 60 I 4.50AE+% I 2.19?E+10 1 0.000E*H I INI-63 1 2.096E+#4 I 0.000E+00 1 0.000E+00 I INI.A5 l @.17h[+$1 l 2.97Q[+05 I 0.000E+H I tbs 5"~i"UbE+03 I EIQ6M5 1 0.000ENt I 82WAS I 6.46AE*h5 1 7.46 E+n0 1 0.000E+ H I 1

IZN.69 1 1.470E+a3 1 0.000E+n0 l 0.000E+00 I Ilpl43 1 0.nonE+49 I 4.971E*03 1 0.000E*00 i

.. ...................................= ........

IP-04 1 0.000E*H I 2.076E+05 I O.000E*00 I 1 5 -05 I 0.000E+00 1 0.000E+00 1 0.000E+04 I 19546 I 0.000E**0 I 9.904E+n6 1 0.000E+06 I 189.ge i n.00nE+no I 3.307E+04 I 6.600E*04 I

.. ..-- - - - - - - ==.........................

tes.89 i 0.nonE*00 1 1.230E+45 1 0.000E*00 I 1 9 -89 1 2.03nE+n6 1 2.16?E+n4 1 0.000E+00 I Ice 90 I 1.124E*87 1 0.000E*00 1 0.000E+0C I

................= .. ....... ...----- .....

i 5.26aE*04 1 2.140E+N I.I.000E*00 t 9 91 See Note, page 3.0 Units: Inhalation - area /yr per uCi/m3 Others - m2 arem/yr per udi/sec 3.0-37 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 17 of 21: Dose Factors for Lung I 15nTripri I*steTKW I G80M Plaffi G#S/EtwnILI(I 458.92 1 2.tanE+04 1 7. 760E+ A5 1 0.009E*00 I av.9A i 230'F+05 1 4.491E*03 1 0.00E*06 i iv.*ln i 2.79+F*A3 1 1.00?E*05 1 0.000E*40 I iv.91 1 2.450f*06 1 1.073E+66 1 0.00E*00 I

.. =....... -- .....- --- . . . .

iv.M i 2.4snE+04 1 1.80 4 *05 1 0.neg+0g I

'. iv 93 i 7.e44E+04 1 1.e5?E*05 1 0.00E*00 I 129 95 i 1.75K+06 1 2.446E+09 1 0.064E*60 1

~

129-97 1 1.103E+05 1 2.* AGE *06 1 0.00E*06 i 14 05 1 4.78SF+45 1 1.409E+0d I 0.00AE+06 1 iMA-99 e 1.140E*95 I 3.995E*06 1 0.000E*00 I '.

....=_-- ___-

ITE.94N I A.106E*02 I 1.841E+05 1 4.713E+41 I ITE-101 1 5.039E*02 1 2.034E+04 I 2.494E-59 I IR.1-161 1 5.516F+05 l 1.044E+00 1 0.000E*04 I I Gi.i-10" i 1. 5* 0 E* 04 I 6.36'E*05 I 0.000E+04 i 19tL1d* I 1.156E+67 1 4.20AE+09 I 6.n00E+0A I

....=- - .= .. . . . . . .

is-Il0ft i 3.648F*06 I 3.445E+09 1 0.000E+00 I ITF-12 N I 4.46AE+05 l 1.552E+06 1 i

.......'........................................0.000E+04 ITF.127t11 1.112E*06 I 9.165E+04 I 0.000E+44 I ITE.127 1 1.015E*04 I 2.994E+0.1 1 0.008E*00 I ITE-12*N i 1.694+A6 1 1.972E+07 ! 0.00nE+00 I

... . ......... ===. ..................

ITE-129 I 2.896 E*93 1 2.60K+04 I 0.0nng+qq i

. ... ............ .......................- =

ITE.131M i 1.009E+05 1 0.026E*06 1 0.00ng+06 I ITE-131 1 2.050r+03 1 2.919F+04 1 0.000E*04 I l ITE.137 i 3.402E+49 I 4.223E*06 I 0.00nE*04 I it.13a 0 00 K+0a 1 5.511E+06 I 0.064E*06 I i _ _ _

I See Note, page 3.0-43 .

l l

Units: Inhalation - mrem /yr per uCi/m3 Others - m2 mrem /yr per uCi/sec

, 3.0-38 Rev. 1, 11/85 l

l i

1 l

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (Rgg)

• Page 18 of 21: Dose Factors for Lung I 190TOPEI liet4LAT10M I EINDe PLMEl 915/CIIMilull iI.111 a 0.nonE+nn i 1.721E+D I 0.000E+nt i 11-112 1 0.00nE+no i 1.2*5E+06 I 0.00nE*00 I 11 111 e n.00nE+nt i 2.441E+n6 1 0.000E+04 I

~

ii$h 1 I 0.00nE5Al I kIA6 7E 5 I~ 0.00nE 500 II 1" i 6.00nE**0 1 2.5?AE*66 I 8.00nE+nt i

~.

6CS-114 1 7.96eE+H I 6.963E*09 1 1.142E+10 4 105 136 1 1.17AE+44 I 1.50?E+09 1 7.51?E+00 I 105 137 1 7.126E+M i 1.03nE*10 I 1.041E+10 I

...........== - - - =..........................

105 139 I 6.53AE*81 1 3.599E+n9 8 1.60*E-23 I IRA.119 I 9.osnE+n) i 1.061E*M i 2.901E.lt I 194 14A I 1.98+E*06 I 2.091E*07 I 2.355E*05 I 104 141 1 2.%BE*03 1 4.172E+04 1 2.754E-40 I IRA-la? I 1.554E+03 I 4.445E+04 1 0.00nE*84 I ILA.140 8 1.eenE+h5 i 1.921E+07 1 0.000E*tt I ILA.142 I 8.219E+ni I 7.60?E+ns 1 0.000E+04 I ICE-141 I 5.164E+09 1 1.366E*07 1 0.00DE+nt i ICE-141 1 1.162E+05 I 2.31?E+06 1 0.000E+44 I ICE-144 1 0. 942E+N I 6.946E+07 1 0.000E+06 I 180 143 1 4.12*E+95 1 0.00nE+at 1 0.00nE*00 I IPII.144 1 1.610E+03 1 1.037E+03 1 0.000E*00 I

.............-... ===..........................

l@.147 1 3.220E+89 I 8.4n8E+ne 1 0.000E*04 I 1W.187 1 3.%?E+84 1 2.3e0E*06 1 0.00nE+nt i w .214 1 5.gnE+ad I 1.7%E+% I 4.ltaE*00 I See Note, page 3.0-43 Units: Inhalation - mres/yr per uCi/m3 Others -

m2 arem/yr per uCi/sec

. 3.0-39 Rev. 1, 11/85

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R .

L30)*

Page 19 of 21: Dose Factors for GI-LLI i 19)Tf)Prl IMATION I GHG.80 PLM(l G85/C0lWill(I m.1 i 6.43ar+02 1 0.cnnr.ni) i 2.3c3E*03 1 ir.14 i s inaE*A3 1 0.800E*00 I 7.948E+99 I

....... ---- =. . - =...............

N4-24 i 1.c%r+04 1 1.19aE+07 1 2.45tF*07 I 18 32 i 1,610E*64 1 0.000E*00 1 3.44AE*t9 I iro.51 3 570E+02 1 4,659E*04 1 7.474E*A4 I im Ea i 7.04E*63 1 1.186E*09 1 2.27'E*07 I t res.44 i 7.16aE*04 I 9.0ISE+05 1 4.554E*94 I .

= _

irr 45 1 1.n9'E*B3 1 0.0n0E+0A i 1.761F+A7 I ire.go i 2 47ar*04 1 2.727E*08 I 2.9?SE+99 I

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . = = - - - -

tiTL5e i 1.113E*04 I 3.611E+0a I 9.423E+07 1 tro.60 i 3.192E+04 1 2.152E+10 1 3.337E*60 I INI-61 2.422E*93 1 0.000E*00 1 1.700r+98 1

.........= -

INI-6' i G.Al? rend i 2.970E*05 1 4.A05E+01 I

. t riL64 1 1.494r*04 I 6.0e?E*09 I 6.056E+66 I

.....- -..=_--

i7% 65 i 6.13ar+64 1 7.443E+00 1 2.94*F+10 1 87H.69 1 1.322E*04 I 0.00nE*0n I 6.133E-09 I

.......- =.....-

IA8-63 i 0 anne +0A I 4.07 d h.-- 3 I 0 .00nE+00=== I

.. .. - =- - ........'........ ....

ise.g4 0 n00E*0n 1 2.n2AE*05 1 0.000E*00 I IM~.is I 0.nonr+iin"l 0.0nnE+0i~I'~i$0iebik'~l 189 66 i 3.430E+83 i 6.904E+04 I 9.059E+ge I

.. === _ . . . . . . . . . - - .--- = .....

ton-98 i 3.taaF+a2 1 3.107r.q4 l 2,9n4E.44 I l - ........

..- -=

Ir4 99 i 6.41AE+#1 1 1.23nr+09 1 1.6 aE.92 I ico ao a 6.toar+nd i 2.162E*04 I 4.11*E+09 I Iq.en I 1.310E*0s 0.on0E+00 1 2.415E+09 I

.............- =....... - - - .....

i @ 91 1 7.34E+44 1 2.140E*96 1 5.119E+05 I l

l See Note, page 3.0-43 .

Units: Inhalation - meem/yr per uCi/m3 Others -

m2 mrem /yr per uCi/sec 3.0-40 Rev. 1, 11/85 1

t

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (R..1]o)*

Page 20 of 21: Dose Factors for GI-LLI I icninpFI IleataTION I 9100pe si.alEl 915/CDMiltXI iqt.97 i 1.4nnEd5 i 7.4pE+n9 I 7.M2E*01 I

.......................=== =-- ...............

iv.en i 1.040E+ns a 4.491E*63 I 1.496E*06 i i 2.15?E*01 1 1.00?E+05 1 2.995E-15 I

.'Y 91M lY.91 1 7.079E*04 I 1.071E+06 I 8.354E+N I e 1.2e6Ed5 e 1.An4E+A5 l 1.631E+01 I

.'Y 97

....................===- =......................

iv.91 1 1. ^^^E d5 l 1.05?E+05 1 2.926E*t4 I t/U 95 6 2.17aE+04 1 2.44AEd8 I 1.314E+46 1 179.97 1 1.40nEd5 1 2.96nE*06 1 7.073E*04 I 14 95 1 1.?6Tde i 1.4HE+00 1 3.31aE+08 i

.-- =......................................... s IMO.99 I 4.872E+04 1 3.995E+06 I 1.090E+#8 i ITE 9 M i 2.03hE+03 1

.....'.................- -1.841E+05_............. 1 2.610E+64 .... I ITC-101 I 8.44?E+0? I 2.034E+n4 1 7.771E-57 I Imi 101 1 1.61nE+04 1 1.n04E+08 1 1.67RE+a5 I

,im). Ins i 4 944Ed4 I 6.361E*05 1 5.096E*00 I

............- ==........................ ..

squ.la6 1 1.63EEd4 1 4.2n'E*00 I 2.299E+46 I

................. ....- ===...................

lar llnN I 1.104E+04 1 3.445E*09 1 2.324E+10 I

..........- =_- __...................._ .....

ITE.125M i 1 ?91E+nd I 1.54?E*06 1 1.141E+a0 I l ITE-12?M i 2.73f(+94 I 9.165E+04 I 2.703E+00 I ITE-l?7 1 2.41AE+04 I 2.994E*83 1 2.16?E*ll5 I I

ITE-129M i 6.00?E+04 1 1.972E+97 1 5.287E+44 I ITF.129 8 2.63?E+nd I 2.6nnE+A4 1 2.47nE.07 I Irt.111M i 1.19tEd5 I 8.07^E+46 1 3.640E*07 I iTE.111 i 9.21aFdi 1 2.919Ed4 1 2.202E.30 I

! iTE.117 1 4.410Ed4 I 4.221E+n6 1 6.13nE+t? I l 11 114 1 1.988E+01 1 5.911E+46 1 2. 661E+ % i 1

1 1

See Note, page 3.0 Units: Inhalation - meen/yr per uCi/m3 Others -

m2 mrem /yr per uCi/sec 3.0-41 Rev. 1, 11/85 1

Table 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3 (Ri ].o)*

Page 21 of 21: Dose Factors for GI-LLI l lanTOpri rieetaTION I G80lM PlacEl Gl@ttholitett 61 131 i 1.n59E*o3 1 1.7nE*47 i 1.02 M+ge i it.132 i 1.964E+93 1 1.245E*06 1 3.756E+04 I 11 131 I 2.154E*03 I 2.451E*06 1 1.421E+07 1 11-134 t 1.799E*83 1 4.467E+05 I 5.927E.11 1 I I-1.15 4 1.034E*43 1 2.526E*06 I 1.296E*49 i Irs.13e i 1.334+43 I 6.863E+09 I 2.9anE*00 I

. _=.....=_- __ ...... . .

irs-134 1 1.429E+43 1 1.rn2E+06 1 1.400E*00 I -

1C5-137 1 1.314+43 1 1.030E+10 1 2.9%E+08 I

.. .- -- ..===- .=

ir%13A I 8.764F+02 1 3.599E*05 1 3.4eAE.22 I

~

IBA139 I 5.096E+04 1 1.061E*05 I 4.972F.49 I 18A lan 1 3.016E*64 1 2.093E+07 I 9.419E+47 i i94141 1 4. N E*03 I 4.172E+04 I 8. 075E-44 I

...........== . ...

IRA 14? I 6.93nE*02 I 4.449E*04 I 0.000E* H I tt A14a I 9.4A4*04 l 1.973E*07 1 2.901E*09 I iin.147 i 5.oSOE+A4 I 7.602E+05 1 1.714-05 I irr.lat i 2.156E*A4 1 1.366E+07 1 2.174E*47 I

.- _ ==..........

ICE.141 1 4.970F+44 1 2.3t?E+06 I 2.444F+ N I

......... -. - - - _===.... .

ICE.144 1 1.464+45 1 6.946E*07 1 2.123E*08 1 185 141 1 3.72 4 *l4 I 4.000E*00 1 1.249E*H I 188 144 1 4.2A4+43 1 1.037E*03 1 1.843E.40 1 1 9 147 1 3.122F+44 1 9.40AE*06 I 9.137E*05 I lu tg7 i 3.554*ea i 2.3A0Een4 1 3.979E* 06 i

. ............- - ==-=.......__..... ...

W .230 1 2.402E*64 6 1. 746E+ 66 1 1. 4%E+ #5 I See Note, page 3.0 Units: Inhalation - aren/yr per uCi/m3 Others -

m2 mrem /yr per uCi/sec

. 3.0-42 Rev. 1, 11/85

l NOTE: The R ijo values of Table 3.2-2 were calculated according to the methods of Ref. 6, Section 5.3, for the pathways and age group of the designated Maximum Exposed Indi-vidual. The values used for the various parameters required for the calculations, and the origins of those values, are given below in Table 3.2-3. The selection of the designated Maximum Exposed Individual is explained in the Notes to Tables 3.2-4 and 3.2-5.

3.0-43 Rev. 2, 1/86

Table 3.2-3 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Page 1 of 4 Orgin of Value Table in Section of Parameter Value R.G. 1.159 NUREG-5133

• • • For P.***

1 L'FA Each Radionuclide E-9 BR .3755 m*/yr E-5

• • • For R (Inhalation)***

1 BR Each age group- E-5 DFA g Each age group, nuclide E-9 and and organ E-15

• • • For Ri (Ground Plane)***

SF .F.7 E-15 DFG.

1 Each radionuclide E-6 (Note 4) t 4.73 E+98 sec 5.3.1.2 3.s-44 Rev. 1, 11/85

Table 3.2-3 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Page 2 of 4 Orgin of Value Table in Section of Parameter Value R.G. 1.179 NUREG-7133

• • • For R g (Vegetation)***

r Each element type E-1 Yy 2.kkg/m* E-15

)pt -1 5.73 E-7 sec 5.3.1.3 -

DFL g Each age group, organ, E-13 and and nuclide E-14 ,,

U,L Each age group E-5 fg 1.5 5.3.1.5 tg 8.6 E+64 sec E-15 USa Each a'ge group E-5 f

g 5.76 5.3.1.5 th 5.18 E+06 sec E-15 H 8.1 gm/m' *** Note 1***

i , ***For Rg (Grass / Cow / Milk)***

! QF 5A kg/ day E-3 U,p Each age group E-5

~

i hw 5. 7 3 E'-97 sec 5.3.1.3 F, Each element E-1 i

3.0-45 Rev. 1,11/85

Table 3.2-3 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Page 3 of 4 Origin of Value Table in Section of Parameter Value R.G. 1.109 NUREG-0133

. r Each element type E-15 t

h 5.18 E+06 sec E-15 H

8.1 gm/m3 *** Note 1***

DFL i Each age group, organ, E-13 and and nuclide E-14 0.44 kg/m 2 Y

p *** Note 2***

Y 2 3 2.0 kg/m E-15 t

f 1.73 E+05 sec E-15 f

p 1.0 5.3.1.2 f

3 1.0 5.3.1.2

• • • For R i (Grass / Cow / Meat)***

• • • Note 3***

0F 50 kg/ day E-3 U

ap Each age group E-5 F

f Each element E-1 r Each element type E-15 t

h 5.18 E+06 sec E-15 H 8.1 gm/m3 *** Note 1***

DFL Ea E-13 and '

i anhh nuaSIi$eroup, organ, E-14 Y

p 0.44 kg/m 2 *** Note 2***

3.0-46 Rev. 1, 11/85

Table 3.2-3 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Page 4 of 4 Origin of Value Table in Section of Parame ter Value R.G. 1.109 NUREG-0133 Y

a 2.0 kg/m 2 E-15 t

f 1.73 E+05 sec E-15 f

p _ 1.0 5.3.1.2 f

s 1.0 5.3.1.2 Aw -1 5.3.1.3 5.73 E-07 sec Notes

1. Site-specific annual average absolute humidity, from Ref.

3, Section 2.1.3.4.

2. Site specific areal productivity of pasture feed grass,

• from Ref. 3, Section 2.1.3.4.

3. No evidence was found in any land use or demographic information that animals are kept for meat within 5 miles of the Station.

These values are included for reference only, should the need for them arise.

4 j 4. The " Total Body" dose factors from the referenced table were applied to all organs.

3.0-47 Rev. 1, 11/85

~_ -

Table 3.2-4 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS

• SECTOR (MILES / METERS) PATHWAYS @ _ AGE GROUP N

NNE 5.0 / 8,000 Vegetation, Child Grass / Cow / Milk NE

' 4.5 / 7,200 Vegetation Child I

ENE 3.4 / 5,500 Vegetation Child I

E 3.3 / 5,300 ---

Child ESE + ---

+

SE ---

5.0 / 8,000 Grass / Cow / Milk Infant SSE + ---

I S 4.2 / 6,800 Vegetation Child I

SSW 5.0 / 8,000 Vegetation Child SW

' 4.3 / 6,900 Vegetation Child -

I WSW 4.4 / 7,100 Vegetation Child W 4.9 / 7,900 Grass / Cow / Milk Infant I

WNW 3.4 / 5,500 Vegetation Child NW

' 4.0 / 6,400 Vegetation Child NNW

' 4.3 /'6,900 Vegetation Child See Note on following page for the method of choice of these controlling receptors.

Listeo pathways are in addition to inhalation and ground plane exposure.

I + -- This sector is uninhabited within 5 miles of the Station.

8 -- If a cow were located at 5.0 miles (8,000 meters) in this sector, an infant consuming its milk would receive a greater total radiation dose than would the real receptor listed.

• • - This hypothetical infant exposed to the Grass / Cow / Milk pathway represents the Maximum Exposed Individual for the Site.

l 3.0-47a Rev. 2, 1/86 l

l

Note: The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were obtained from Table 2.1-8 of Ref. 3, as updated by Appendix F of Ref. 7. A child was assumed at each location, except that where a milk cow was listed, an infant was also assumed. In addition, as a safeguard against underestimation of dose to people just beyond the 5-mile zone, a hypothetical Grass / Cow / Milk pathway was assumed at 5 miles from the Site, in each sector which does not have an actual Grass / Cow / Milk pathway within 5 miles (see Ref. 6, Section 5.3.1).

Annual average X/Q and D/Q values for each receptor -

were obtained by interpolation of values generated by USNRC Staff executions of the program XOQDOQ. ,,

These are the same parameters used by NRC Staff in the preparation of Ref. 8.

Expected annual releases of each nuclide were taken from Table 3.5-22 of Ref. 3.

The pathway dose factors given below in Tables 4.3-1 and 4.3-2 were then used in the methodology of Section 3.2.3 of this Manual to compute estimated annual doses to each candidate receptor location for the pathways existing at that location. The con trolling receptor

~

for each sector was then chosen as the candidate receptor i with the highest estimated total annual dose of any given receptor in the given sector. The Maximum Exposed Individual for the Site was selected as the candidate receptor with the highest estimated total annual dose of all candidates in any sector.

3.0-47b Rev. 2, 1/86

I I

i Table: 3.2-5 ATMOSPHERIC DISPERSION PARAMETERS FOR CONTROLLING RECEPTOR LOCATIONS *

' ~

SECTOR (MILES / METERS) 'X/Q (sec/m ) D/Q (m )

N NNE 5.0 / 8,000 8.6 E-08 2.4 E-10 NE 4.5 / 7,200 1.0 E-07 3.1 E-10 ENE 3.4 / 5,500 1.4 E-07 5.6 E-10 E 3.3 / 5,300 1.6 E-07 8.2 E-10 ESE + ---

+

SE ---

• • ~

SE 5.0 / 8,000 1.1 E-07 4.9 E-10 SSE + ---

S '4.2 / 6,800 1.6 E-07 4.2 E-10 SSW 5.0 / 8,000 8.8 E-08 2.2 E-10 SW 4.3 / 6,900 1.2 E-07 2.9 E-10 WSW 4.4 / 7,100 9.4 E-08 1.8 E-10 W 4.9 / 7,900 7.6 E-08 1.3 E-10 WNW 3.4 / 5,500 1.3 E-07 2.6 E-10 NW 4.0 / 6,400 1.6 E-07 5.8 E-10 NNW 4.3 / 6,900 1.1 E-07 4.0 E-10

• -- Annual average relative dispersion and deposition values for the locations in Table 3.2-4. (All receptors represent real pathways, except as noted.) X/Q and D/Q values were obtained, and analysis performed, as described in the Note to Table 3.2-4 of this Manual. The Maximum Exposed Individual for .the site was identified as a hypothetical infant consuming the milk of a cow pastured at 5.0 miles in the SE sector.

Therefore, the Site X/Q' and D/Q' (Section 3.2.3) are those from this Table for that location. [The real receptor with the highest estimated exposure would be a child consuming the milk of a cow pastured at 5.0 miles in the NNE sector, and eating the vegetables grown there.]

+ -- This sector is uninhabited within 5 miles of the Station.

! ** - This hypothetical infant exposed to the Grass / Cow / Milk pathway represents the Maximum Exposed Individual for the Site.

3.0-47c Rev. 2, 1/86

3.3 METEOROLOGICAL MODEL The dose calculation methods for gaseous effluents described in Section 3.2 require the use of annual average relative dispersion (X/Q) and relative deposition (D/Q) parameters.

When new or revised values of these parameters must be computed,- the method detailed below will be used. All release points are treated as ground level. The computation of the dispersion and deposition parameters is based on the onsite meteorological data, and is implemented in a sector-averaged diffusion model.

3.3.1 Meteorological Input Joint frequency distributions of wind speed and direction by atmospheric stability class are used for the dif fusion ,,

calculations. The meteorological tower is located approximately 1.0 mile southeast of HCGS. All meteoro-logical data are from the Artificial Island meteorological tower. The flat, uncomplicated terrain that surrounds the site for a considerable distance in every direction, ensures excellent representation of the regional airflow by the Artifical Island meteorological tower measurements.

Wind speed and direction data from the 33-foot tower level are used as input for the joint frequency distri-butions.

Joint frequency distributions of wind speed and direction by atmospheric stability class are computed for 22.5 degree sectors using the wind speed groups and atmospheric stability classes suggested in Regulatory Guide 1.23.

Joint frequency distributions of wind direction, speed, and stability from the 33-foot level are used as input for both vents.

3.0-48 Rev. 2, 1/86

With the excaption of the calm and the 25+ mph groups, the median speed from each wind speed group is used to represent the group in the diffusion calculations.

For conservatism, a wind speed of 0.38 mph, equal to one-half of the highest threshold of the vane and propeller, is assigned to the calms. A wind speed of 26 mph is used to represent the 25+ mph group.

3.3.2 Source Configuration Radionuclides are routinely released from two sources, the south and north vents. Their source characteristics >

are given as follows:

Parameter South Vent North Vent Height above grade, m 35.05 35.05 Exit diameter; m, the equivalent-circ diam for for rectangular vents 4.13 2.23

Exit velocity, m/s Summer (Apr - Sept) 15.54 5.08 Winter (Oct - Mar) 5.08 10.82 Both vents, pointing upward, are adjacent to the topa

~o f the turbine buildings, below the level of the reactor l contaiment dome. Therefore, the vents are affected l

by the nearby building aerodynamics with moderate to strong winds.

The release is assumed to be at ground level, and a l building wake correction factor (reactor building height squared) ofs 3819 m2 is used in accordance with the methodology of Fmgulatory Guide 1.111, Revision 1.

3.0-49 Rev. 1, 11/85 l

The building wake correction f actor takes into considera-tion the initial mixing of the plume within the building cavity.

The exit velocities for the south plant vent are signif-icantly higher than those for the north plant vent.

The assumption made in Regulatory Guide 1.111 (Revision 1) about the height of adjacent solid structures (i.e.,

reactor building dome) is simplistic in the case of effluents released at high exit velocities from vents oriented upward (versus horizontal). With the considera-tion of the reactor building dome as an adjacent structure, the projected effluent path becomes complicated because the transport wind and associated entrainment will

.be sector dependent. Therefore, the X/Q and D/Q values are conservative when based on a ground level release. -

3.3.3 Site Impact on Vent Releases The effect of the cooling tower on the relatively low-l e've l vent releases during neutral and unstable atmospheric conditions would be to enhance the vertical diffusion through increased mechanical turbulence, and thus reduce ground-level concentrations. Therefore, to be conservative in the estimation of ground-level concentrations for neutral and unstable conditions,

, , the wake effect of the cooling tower has been neglected.

l 3.3.4 Diffusion Model The sector-averaged Gaussian plume equation, as expressed in Regulatory Guide 1.111, Revision 1, is used for all X/Q calculations.

i 3.0-50 Rev. 2, 1/86

3.3.5 Terrain Correctors Changes in terrain elevation, though very small in the immediate vicinity of the plant, are applied at each receptor. Terrain heights above plant grade, which is 4 meters mean sea level (MSL), are used in the calculations, where applicable. The terrain height correction applied to any particular receptor is the highest terrain between the source and the receptor.

3.3.6 Atmospheric Stability Atmospheric stability classes are determined using the vertical temperature difference between the 300 l and 33-foot levels of the Artificial Island tower.

The seven lapse rate classes for stability classification are those recommended in Regulatory Guide 1.23.

3.3.7 Dispersion Coefficients The horizontal and vertial dispersion coefficients, sigma y and sigma z for each turbulence class, are computed using analytical approximations to the P-G sigma curves given in Regulatory Guide 1.111, Revision 1.

These dispersion coefficients were developed for flat l

to rolling terrain, similar to that surrounding the Hope Creek site.

3.3.8 Deposition 1

l l Relative depletion by dry deposition is estimated in accordance with Regulatory Guide 1.111, Revision 1.

The depleted by deposition X/Q values are obtained from the X/Q values by multiplying the X/Q values i 3.0-51 Rev. 1, 11/85 i

by the fraction remaining in the plume. These fractions are determined from Regulatory Guide 1.111, Revision 1, Figure 2.

Relative dry deposition is also estimated in acordance with Regulatory Guide 1.111, Revision 1.

3.3.9 X/Q Model The following ground level, wake-corrected form of the straight line flow model is used to implement the-methods discussed in Sections 3.3.1 - 3.3.8.

X/Q = the sector-averaged annual average -

relative concentration at any distance in the given sector (sec/m3) .

=

2.032h I N # U [ zj ij i 2.032 - = (2/g)l/2 divided by the width in radians of a 22.5-degree sector (0.3927 radians).

l g

= plume depletion factor at distance l r for the appropriate stability class

! from Figure 3.3-1.

i = windspeed class.

. n = number of hours meteorological conditions i,j are observed to be in a given wind l

. direction, windspeed class i, and atmos-

pheric stability class j.

N = total hours of valid meteorological 3.0-52 Rev. 2, 1/86 o

data, r = distance from the contaiment building to location of interest (m) ui = wind speed (midpoint of windspeed class i) at ground level (m/sec).

'( 7, + 3819/2 F)l/2 z = the lesser of or

,( 3 7 3) /2 where:

z = vertical standard deviation of the plume (in m) at distance r for ground ,

level releases under the stability category indicated by aT/ cZ, from Figure 3.3-2.

c T/ o Z = temperature differential with vertical separation (0K/100m).

3.3.10 D/Q Model The following relative deposition model for ground

, level releases is used to implement the mehtods discussed in Sections 3.3.1 - 3.3.8.

D/Q = the sector-averaged annual average relative deposition at any distance in a given sector (m-2),

2'.55 D n

= -

9 where, rN 3.0-52a Rev. 2, 1/86 e

, - - _mn ,. __ __ ,, . , , ,_ _ _ --- . _ . - .

Dg = deposition rate for ground-level releases relative to distance (r) from the contain-ment building (from Figure 3.3-3).

2.55 = the inverse of the number of radians in a 22.5 sector

" 1 (22.5 ) (0.0175 Radians /8) n . = number of hours wind is in given direction (sector).

N = total hours of valid meteorological data. ,,

~

I

.s l 3.0-52b Rev. 2, 1/86

Figure 3.3-1 Plume Depletion Effect for Ground-Level Releases ( h)

(All Atmospheric Stability Classes)

Graph taken from Reference 5, Figure 2 1A aA --

% s l OA s A

3 0.7

~

\ \

0.s g 'N .-

E 0A  %

l \A g 0.4 e

0.3 0.2 0.1 0.1 1A 10A 10BA 308A PUAGE TRAVEL DISTANCE (EMMWTERSI 3.0-52c Rev. 2, 1/86

Figure 3.3-2 Vertical Standard Deviation of Material Concentration in a Plume ( Uz)

(Letters denote Pasquill Stability Class)

Graph taken from Reference 5, Figure 1 l } /

I / /

/ / / .

• l r j f f l l ,f , f

[ /

/

/ ,/ ,,,

1ee A

/ l

/

l

/ .

/

V f V ,V }" J' J

[ f a Y' / af Y

) f 7 / / .. , * " - --~~

I ,/ / / rf/ /' -~

/

l /// .

V / . --

/(/// / ,/

e

/ af 1 1 , l

// / /

/ / /

/ /

/,l t /

1.8 10 100 0.1 PLUME TftAVEL DISTANCE (KILOMETEfts) l l

l Temperature Change Pasquill Stability with Height oT/ oz (dK/100m) Categories Classification

< al.9 A Extremely Unstable l

1

-1.9 to -1.7 B Moderately Unstable l -1.7 to -1.5 C Slightly Unstable

-1.5 to -0.5 D Neutral

-0.5 to 1.5 E Slightly Stable 1.5 to 4.0 .

F Moderately Stable

> 4.0 G Extremely Stable 3.0-52d Rev. 2, 1/86 l

l

I Figure 3.3-3 Relative Deposition for Ground-Level Releases (Dg)

(All Atmospheric Stability Classes)

Graph taken from Reference 5, Figure 6

,, a 104 \ _

• ., e u

N e T m '

E T w A E  %

e N '

lM h

u T.

x 5 . X 5 \

i: 5 5 \ '

n ,

E 104 '

i i

10-7 0.1 1A 10.0 100.0 200A PLUME TRAVEL DISTANCE (KILOMETERS) l l

3.0-52e Rev. 2, 1/86 l

3.4 DEFINITIONS OF GASEOUS EFFLUENTS TERMS Section of Term Definition Initial Use ay = the administrative allocation factor (3.1.1) for vent v [unitiess], which is the fraction of the station site boundary dose rate limit which is assigned to vent v.

D = ' the site boundary air dose due to beta (3.2.2) b emissions from noble gas radionuclides

[ mrad].

D = the site boundary air dose due to gamma (3.2.2) -

g emissions f rom noble gas radionuclides

[ mrad].

D mp = dose to organ o of a Member of the (3.2.3)

Public, from radioiodines, tritium, and radionuclides in particulate form with half-lives greater than 8 days [ mrem].

D/Q' = the annual average relative deposition (3.2.3) at the location of the Maximum Exposed Individual [m-2],

F = the expected flow rate in vent v (3.1.1) y

[cc/sec].

K i

= total body dose factor for gamma (3.1.1) emissions from noble gas radionuclide i

[ mrem /yr per'uCi/m3], from Table 3.1-1.

l 3.0-53 Rev. 1, 11/85

l Section of Term Definition Initial Use L

i

= skin dose factor for beta emissions (3.1.1) from noble gas radionuclide i

[ mrem /yr per uCi/m3], from Table 3.1-1.

M = air dose factor for gamma emissions (3.1.1) i from noble gas radionuclide i

[ mrad /yr per uCi/m3], from Table 3.1-1.

N = ~ air dose factor for beta emissions from (3.2.2) i noble gas radionuclide i

[ mrad /yr per uCi/m3], from Table 3.1-1.

P io = dose parameter for radionuclide i and (3.2.1.b) -

organ o, for inhalation, from Table 3.2-1 [ mrem /yr per uCi/mlQ.

bi = th'e release rate of noble gas (3.2.1.a) radionuclide i as determined from the concentration measured in the analysis of the appropriate sample required by the Technical Specification Table 4.11-2 [uci/sec].

i'

= the release rate of non-noble gas (3.2.1.b) radionuclide i as determined from the concentration measured in the analysis of the appropriate sample required by the Technical Specification Table 4.11-2 (uci/sec].

3.0-54 Rev. 1, 11/85

Section of Term Definition Initial Use i

= cumulative release of noble gas (3.2.2) radionuclide i over the period of interest [uci].

i'

= cumulative release of non-noble gas (3.2.3) radionuclide i over the period of interest [uci].

Rg . -. dose factor for organ o due to (3.2.3) radionuclide i and pathway j, from Table 3.2-2 [arem/yr per uCi/m3, or m2 - mrem /yr per uCi/sec].

s S

y = the normal radiation monitor setpoint (3.1.1) for vent v [uci/cc].

cc S y' = the conservative radiation monitor (3.1.2) se'tpoint for vent v, assuming all noble gas is Kr-89 [uci/cc].

S ys = the normal candidate setpoint for vent (3.1.1) v, based upon the skin dose rate limit of 3000 mrem /yr [uci/cc].

Sy ,. = the conservative candidate setpoint for (3.1.2) vent v, based upon the skin dose rate limit of 3000 mrem /yr, and assuming all noble gas is Kr-89 [uci/cc)..

S vt = the normal candidate setpoint for vent (3.1.1) v, based upoh the total body dose rate limit of 500 meem/yr [uci/cc].

3.0-55 Rev. 1, 11/85

- - - , _ _ - . . _ _ ._____-.--_..,-_.-._,,,__,..-,m, , . . - . . - .- .-- - - - -, --------r--- - - - - - -

Section of Term Definition Initial Use S

vt' = the conservative candidate setpoint for (3.1.2) vent v, based upon the total body dose rate limit of 500 mrem /yr, and assuming all noble gas is Kr-89 [uci/cc].

SF = the safety factor; a conservative factor used to compensate'for statistical fluctuations and errors of measurements.

W = relative concentration or relative (3.2.3) ij' deposition fors the Maximum Exposed Individual, as appropriate for exposure j pathway j and radionuclide i. Its -

value is X/Q' or D/Q', as appropriate.

X iy = the measured concentration of noble gas (3.1.1) radionuclide i in the last grab sample analyzed for vent v [uci/cc].

X/Q = the highest annual average relative (3.1.1) concentration at the site boundary in any sector [sec/m33 For post-release calculations, the actual site boundary i X/Q in the affected sector for the period of the release may be substituted.

X/Q' = the annual average relative (3.2.3) concentration at the location of the Maximum Exposed Individual [sec/m3],

l 3.0-56 Rev. 1, 11/85 i i

r i

Section 4.0 SPECIAL DOSE CALCULATIONS Sections 2.0 and 3.0 described calculations which are made in connection with each effluent release. In addition to these calculations, the Technical Specifications (Reference 1) require o'r imply that certain other types of dose calculations shall be specified in the ODCM. ,

These special dose calculations are described in the present section.

4.1 NECESSITY OF OPERATING EFFLUENT TREATMENT SYSTEMS ,

4.1.1 Liquid Radwaste Treatment System Technical Specification 3.11.1.3 reads:

The LIQUID RADWASTE TREATMENT SYSTEM shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to,the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 arem to any organ in a 31 day period.

The surveillance requirement for this Specification, which is Technical Specification 4.11.1.3, reads:

Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology

'and parameters in the ODCM.

The Liquid Radwaste Treatment System to which this decision process applies consists of the filters and domineralizers shown schematically in Figure 4.1-1.

Prior to rendering the system inoperable, and at least once each 31 days while the system remains inoperable, doses due to liqaid effluents shall be projected according to the following guidance:

4.0-1 Rev. 1, 11/85

1. Doses from all liquid effluents from all liquid radioactive waste management components shall be included. For the Hope Creek Generating Station this shall include releases from the Waste Sample Tanks, Floor Drain Sample Tanks, Detergent Drain Tanks, Condensate Storage Tank, and any radioactivity in the Cooling Tower Blowdown Line.

2. The projected release rates used in the dose calculation shall be appropriate to the projected modes of operation of all the liquid radwaste streams. That is, release rates from liquid effluent streams which are projected .

not to be t re ated' mus t be based on the analysis of pretreatment samples, and not of samples taken from ,

those streams when the treatment systems are in operation.

3. Doses due to radioactive materials in liquid effluents shall be computed according to the methods of Section 2.2. ,

4. The projected dose from Step 3 shall be compared to the Technical Specification limits above (0.06 mrem to the total body or 0.2 mrem to any organ). If the projected dose does not exceed the limit, the systems may be operated as assumed in the projection. If the projected dose does exceed the limit, one of two alternative courses must be implemented: a) the treatment systems on some of the streams must be brought into operation until the projected dose does not exceed

~

the limits; or b) all of the Liquid Radwaste Treatment System at the Hope Creek Station must be brought into operation. -

4.0-2 Rev. 1, 11/85

4.1.2 Ventilation Exhaust Treatment System Technical Specification 3.11.2.5 reads:

The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day period.

The surveillance r'equirement for this Specification, which is Technical Specification 4.11.2.5.1, reads:

Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM, when the VENTILATION EXHAUST TREATMENT

. SYSTEM is not in use.

The Ventilation Exhaust Treatment System to which .

this decision process applies consists of the charcoal and particulate filters shown schematically in Figure 4.1-2. Prior to rendering the system inoperable (other than for routine maintenance), and at least once each 31 day's while the system remains inoperable, doses due to gaseous effluents will be projected according to the following guidance:

1. All gaseous effluent pathways from the Hope Creek Station must be included (including those from the Gaseous Radwaste Treatment System).

2. The projected release rates used in the calculation shall be appropriate to the projected modes of operation of all the ventilation exhaust and gaseous radwaste treatment systems at both Stations.

That is, release rates from effluent streams which are p'rojected not to be treated must be based on the analysis of pretreatment samples, and not of samples taken from those streams when 4.0-3 Rev. 1, 11/85

the treatment systems are in operation.

3. Dose rates at the Site Boundary shall be computed according to the methods of Section 3.2.1, and multiplied by (31/365 = ) 0.0849 to convert them to a projected cumulative dose for 31 days. Doses to the Maximum Exposed Individual shall be computed according to the methods of Section 3.2.3.

4. The projected dose f rom Step 3 shall be compared

. to the Tech Spec limit above (0.3 area). If the projected dose does not exceed the limit, the systems may be operated as assumed in the -

projection. If the projected dose does exceed the limit, one of two alternative courses must ,,

be implemented: a)the treatment systems on some of the streams must be brought into operation until the projected dose does not exceed the limit; or b)all of the Ventilation Exhaust Treatment System at the Hope Creek Station must be brought into operation.

4.1.3 Gaseous Radwaste Treatment System Technical Specification 3.11.2.4 reads:

The GASEOUS RADWASTE TREATMENT SYSTEM shall be in

~ operation.

l l

l The APPLICABILITY of this Specification is "Whenever the main condenser air ejector system is in operation."

The Gaseous Radwaste Treatment System is shown in Figure 4.1-3. No dose projections are required prior to rendering thie system inoperable, but this shall not be done unless the main condenser air ejector system is rendered inoperable at the same time.

. 4.0-4 Rev. 1, 11/85

Figure 4.1-1 LIQUID RADWASTE TREATMENT SYSTEM

• 5 o

2 3 r..

=

h 8-

=

[3

=

&. a =

g ., ._

o 4 : .

.i i

.. . y-

-1: 1: [i  : I

[:2

.& g1 .:

g:-

-.2

• ;I o a g

o o a I

:  :  : 8 :

I .  ; ..~ 1 0 "

3: :  :: :  : : 1

.& 3 : .

C 3 :. 82a

& 8 8

"; e o il 8 : j : 0 t . -. 3 .

&1

'1 3 3 3 3 a n

=

)

:  :: . . 3 .

0

&j *

. 1 j

• g =: " 2

.  : 3 :* 1

=

2u .i. .

8 n n 1

_} } _

n n

u. -

2  :  : 1

: : . p

=

.- g :-  : - -: .

1 .::

.  : 1 .i. .l. i. .:

, 4.0-5 Rev. 1, 11/85

Figure 4.1-2 VENTILATION EXHAUST TREATMENT SYSTEM Gaseous Radwaste h l _ E as Treatment System ~

(from rigure 4.1-3) North Plant Vent Untreated Ventilation m Air Sources "

Redweste Decor.. _

Evaporator '

Reactor Building '

Purge Air R H ~

(Typ. of 3)

Auxiliary Building RE Radweste Area R H = W Ventilation Air _ South (Typ. of 3) Plant Vent Condensate Domineralizer' Room Air Pipe Chase Air  ;- R H C H +

Feedwater Heater _

Room Air ~

Untreated Ventilation _

l Air Sources "

I (Recirculation) ,,

,, f H H Reactor - - FRYS Building Air " H C H " C H _

~

System Vent (Typ. of 6) (Typ. of 2) 1

Legends R = Roughing Filter C = Charcoal rilter N = HEPA Filter RC = Effluent Radiation Monitor

• -- This Post-Treeteent Monitor is not an ef fluent monitor as designated by the RsT3.

4.0-6 Rev. 1. 11/85

Figure 4.1-3 GASEOUS RADWASTE TREATMENT SYSTEM Main or Auxiliary Steam SJAK ,

offgas g---

---g Preheater Recombiner ," ,

Condenser~

Offges l_ _ _ _

_ _ T picaly o_f,2f Recombigt Pjckages_l .

Holdup Pipes C I I

! Cooler "*# -

Reheater Bed Condenser l_ _ _ _ _

l HEPA Adeorber U To North _ ~

Plant Vent rilter Train (Figure 4.1-2) '!

I I l_ __ _

W i.".t

! C_her gal lystje _ l 4.0-7 Rev. 1, 11/85

i l

4.2 TOTAL FUEL CYCLE DOSE Technical Specification 3.11.4 reads in part:

The annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 meens to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

The total annual dose or dose commitment to a Member of the Public will be computed as the sum of the doses due to three components: doses due to radioactivity released in eff1 dents from the Hope Creek Station, doses due to effluents from othe uranium fuel cycle sources, and doses due to direct radiation from fuel cycle sources. When it is necessary to perform an evaluation of the total fuel cycle dose (see Technical Specification 3.ll.4.a), it shall -

be performed according to the following guidance:

1. Doses due to liquid effluents from the Hope Creek Station shall be calculated according to the methods of Section 2.2 of this ODCM, using total releases for the year from all release pathways at the Station.

2. -D os e s due to gaseous effluents from the Hope Creek Station shall be calculated according to the methods of Section 3.2 of this ODCM, using total releases

,for the year from all release pathways at the Station.

3. Effluent doses from the Hope Creek Station shall be summed with those from the Salem Station to determine the total dose due to effluents from the uranium fuel cycle.

4. Direct radiation' doses from the fuel cycle will be inferred from the evaluation of readings from environmental monitoring devices (see section 5.1).

4.0-8 Rev. 1, 11/85

4.3 INITIAL EVALUATION OF UNPLANNED GASEOUS RELEASES For the purpose of initial assessments of the impact of unplanned gaseous releases, dose calculations for the critical receptor in each af fected sector may be performed as follows.

For each location, X/Q' and D/Q' will be calculated according to the methods of Section 3.3 of the ODCM, using the measured meteorological parameters for the period of the unplanned release. The location of the critical receptors and the pathways j which should be analyzed for each critical receptor are shown in Table 3 . 2-4 . (For very rough calculations, the annual average X/Q and D/Q for each receptor are given in Table 3.2-5.) The R ij for the appropriate exposure -

pathways and age groups will be selected from Tables 4.3-1 and 4.3-2. ,,

e

[ 4.0-9 Rev. 2, 1/86

Table 4.3-1

• i INFANT PATHWAY DOSE FACTORS FOR SECTION 4.3 (Rg)

Page 1 of 3: Dose Factors for Composite Worst Organ I 190TUPEI IINILAilSt i Glulle PullEl EStBMilLKI N/tBMSWI W TATIGl I lH-3 1 6.46tE+02 I I.8HE+40 l 2.373E+05 1 0.IIE+40 1 0.040E*40 I IC-14 1 2.646E+14 1 0.000E*00 1 3.722E+09 1 0.00E*06 1 0.000E+00 I

... .... . =............... .................................. ..........

1946-2 4 1 1.056E*t4 i 1.385E+07 1 2.453E*07 1 0.000E*00 1 0.000E*t4 I

. ..................=___ ___ _==....... .. ......... _... .......... .

IP-32 1 2.030E+46 1 0.000E*00 1 2.549E*11 1 0.IIIE*80 1 0.000E*00 I 1C1151 1 1.284E*04 1 5.506E+86 1 7.478E+66 I I.000E+08 1 0.000E*t6 I 1f96 54 I 9.996E+05 i 1.625E+09 I 6.205E+07 1 0.000E+08 1 0.000E*It t IfM-56 -1 7.168E<04 1 1.068E+44 I 4.554E*lt i 8.000E+00 1 0.000E+tt i IFE.55 1 8.694E+04 1 0.000E*t4 1 2.15E+M i 1.00E+00 1 0.000E*t0 t IFE.59 1 1.015E+06 I 3.204+00 1 6.234E*00 1 0.00E+10 I I.00E+00 I 100-58 1 7.770E+05 1 4.464E*00 .I 9.634E+t? I 0.00E+00 1 0.IIIE*It i 100-60 '

1 4.508E+06 1 2.532E+10 1 3.337E+08 1 0.000E+00 1 0.00E+00 t IMI.63 I 3.388E*05 1 0.000E+08 I 5.55tE+10 1 0.000E+08 1 0.000E+00 1 INI-65 1 5.012E+04 1 3.451E*05 1 4.805E+01 I 0.000E*00 1 0.00tE+00 I 100-64 1 1.490E+04 1 6.876E+05 1 6.056E+06 1 0.000E+49 I 0.000E+00 I 12M 65 1 6.468E+05 I 8.583E*t0 1 3.029E+10 1 0.00K+00 1 0.000E*00 1 12N-69 1 1.322E*04 1 0.000E+00 1 6.133E.09 I 0.000E*00 1 0.000E+00 I iW-83 1 3.000E*02 1 7.079E+03 1 1.486E+00 1 0.000E+00 1 0.000E*06 I.

15 1 4.004E*02 1 2.363E*05 i 1.998E-22 1 0.000E*00 1 0.000E+00 t

_-84 . ..- ........ ...____.._..__. ...... .. .. .......... ..

15 85 1 2.044E+01 1 0.000E+10 I I.000E+08 1 0.00K+08 1 0.000E+00 I I 15 86 1 1.904E+05 1 1.027E+87 1 3.548E+10 1 0.000E+08 1 0.000E*06 I 1 5 -88 1 5.572E+02 1 3.779E+04 1 2.982E-44 1 0.000E+08 1 0.000E+I0 1 115 89 1 3.206E+02 1 1.476E+05 I 5.431E-52 1 0.00E+00 1 0.000E+00 I 1 5 -89 1 2.030E+06 1 2.509E+04 1 2.002E+18 1 0.000E+00 1 0.000E+00 1 1 9 -90 1 4.088E+07 1 0.000E+00 1 1.934E+11 1 0.000E+00 1 0.000E*08 i

.. ...... ........... =.... ............... ................ .........

19d1 1 7.336E+04 1 2.511E+96 I 5.115E*05 1 0.000E*00 1 0.000E*00 I I

i 1

1 f

i

( * --

See Note, page 4.0 i Units: Inhalation - area /yr per uCi/m3 Others - m2 mrem /yr per uCi/sec l

4.0-10 Rev. 1, 11/85 i

I

Table 4.3-1 INFANT PATHWAY DOSE FACTORS FOR SECTION 4.3 (Rg)

Page 2 of 3: Dose Factors for Composite Worst Organ I ISOTOPEI IIHLATION I G10 LAO PLNEl 91S/tSHilll(I EM/ClkfEATI UEEETATi(plI 15R-92 I 1.400E*t5 I t.631E*06 1 7.942E*01 I t.lttE+H I t.It0E+44 I lY-90 I 2.680E*05 1 5.300E+03 1 1.496E*06 1 0.000E+00 1 0.000E*04 i

=.......- -__

=....

lY-91M i 2.786E+03 1 1.161E*05 1 2.985E-15 1 0.000E+00 1 0.000E*06 I lY-91 1 2.450E+06 1 1.207E*06 I 8.354E*06 1 0.000E+00 1 0.000E90 i tv-92 l 1.266E45 1 2.142E*05 1 1.633E+01 1 0.000E+00 1 0.00K+04 I

.......= ....

lY-93 1 1.666E+05 1 2.534E*05 1 2.826E*04 1 0.000E*00 1 0.00E+H I 129-95 ' t 1.750E*06 1 2.837E+08 1 1.314E+04 1 0.H0E+00 1 0.000E+M i 12il.97 I 1.400E+05 I 3.445E+06 I 7. 073E+04 1 0.000E+66 1 0.00E+44 I 1 4 -95 1 4.78AE+05 1 1.657E*00 1 3.314E+08 1 0.000E+00 1 0.00E+44 I

.... ................................... .. ..... =. ...... .

IMO-99 1 1.348E+05 1 4.626E*06 I 4.944E+08 1 0.000E+00 1 0.00E*H I

................= .. .. ... .. ...... ... .

ITE-99M i 2.030E+03 I 2.109E+05 1 2.618E*04 1 0.000E+00 1 0.00E*H I ITE.101 1 8.442E+02 1 2.260E*04 1 7.771E-57 I 0.000E+00 1 0.000E+00 I tilu-103 I 5.516E+05 1 1.265E*08 1 1.678E*05 1 0.000E+00 1 0.000E+49 I 1 4 109 I 4.844E*04 I 7.212E+05 I 5.096E*00 1 0.000E+00 1 0.00K+M i 1 4 106 I 1.156E47 1 5.049E+08

.. .=== ......-

1 2.299E*06 1 0.000E*00 1 0.00K+08 1 18G 110M i 3.668E+06 1 4.019E*09 8 2.324E*10 1 0.000E+00 1 0.000E+00 I

.... ..- -_ .=_ .............. ........... ....

ITE-125N 1 4.466E*05 1 2.120E*06 1 2.399E+08 1 0.00K+00 1 0.000E+40 I ITE-127M i 1.312E+06 1 1.003E+05 1 1.649E+09 1 0.000E*00 1 0.000E+M l ITE-127 1 2.436E+04 1 3.293E+03 1 2.162E*05 1 0.00E+00 1 0.00K+00 1 ITE-129M 1 1.680E*06 1 2.305E+07 1 2.214E+09 1 0.000E+00 1 0.00E*04 1

= .. .... ... ............... . .

ITE-129 1 2.632E*04 1 3.076E+04 1 2.670E-07 1 0.000E+00 1 0.000E+04 I ITE.-131M i 1.989E*05 1 9.459E+06 1 3.640E*07 I 0.00E+00 1 0.00K+00 I ITE-131 1 8.218E+03 1 3.450E+07 1 2.202E-30 1 0.000E+00 1 0.000E*tt I ITE-132 l 3.402E45 1 4.960E+96 1 1.036E*06 1 0.000E+00 1 0.000E*M i 11-130 1 1.59E46 6.692E+N I 1.393E+49 I t.000E+00 1 0.00K+M i

- -..---- .... _.. . . - = ..=- .....

See Note, page 4.0-16 Units: Inhalation - arem/yr per uCi/m3 Others - m2 mrem /yr per uCi/sec 4.0-11 Rev. 1, 11/85

Table 4.3-1 INFANT PATHWAY DOSE FACTORS FOR SECTION14.3 (R.3)

Page 3 of 3: Dose Factors for Composite Worst Organ AGE GIOLF ( IWffli 1 ( M.A. ) ( IWANT ) ( !WANT ) ( IWilli )

I ISOT(PEI IINE.ATICbf I IM88 PUIEl UtS/COMILKl GIS/CSMEATI WlETATISI l 11-131 l 1.484E+07 1 2.099E*07 1 1.675E+12 1 0.000E*It i 1.000E+00 I

................. ==

11132 1 1.694E*05 1 1.465E+46 1 2.170E+02 1 0.000E*00 1 0.000E+00 1 11-133 1 3.556E+06 1 2.981E+ 06 1 1.527E*10 1 0.000E*00 1 6.000E+00 I 11 134 1 4.452E+04 I 5.30$E+05 1 1.337E.09 i O.000E+00 1 0.000E+44 11-135

.... ..i I 6.958E+05 1 2.947E*06 1 3.185E+07 1 0.000E*00 1 0.000E*H

............................___....__..........................-..I

.ICS.134'l ...

7.028E+05 1 8.007E*19 l 1.002E+11 1 0.000E+00 1 0.000E*40 I 1C5-136 1 1.345E*05 1 1.702E+H I 9.219E+09 1 0.000E*00 1 1.000E*t0 1 1C5-137 1 6.118E*05 1 1.201E+10 ....-

1 9.583E+10 1 0.000E+08 1 0.000E*H I 105-138 I 8.764E*02 1 4.102E+05 I 3.468E-22 l 0.000E+00 1 0.00E+44 I Ilh.139 I 5.096E+04 1 1.194E*05 l 4.572E-05 1 0.000E*00 1 0.00K+04 I 104 140 1 1.596E+06 1 2.346E+07 I 3.835E+08 1 0.000E+08 1 0.000E+00 I

. _ .....-...-.-......-....... --_=........... .................. . ...

Ilm-141 1 4.746E+03 1 4.754E+04 I 8.075E-44 1 0.000E+00 1 0.000E+08 i 184-142 i 1.554E+03 1 5.064E+04 1 0.000E+08 I 0.000E+00 1 0.000E* H I

--=.................. .............................. ._

.ILA-140

. .=- 1 1.680E+05

......=

1 2.180E+07 1 2.991E+05 1 0.000E*00 1 0.00E+H I ILA-142 1 5.950E+04 1 9.122E+05 l 1.716E-05 1 0.000E+00 l 0.00E+tt I

........_............................ ____ ....=- -......................

ICE.141 1 5.166E+05 i 1.540E*l7 1 2.174E+07 I 0.000E+00 1 0.000E+00 I ICE.143-1 1.162E+05 1 2.627E+16 1 2.444E+06 1 0.000E+00 1 0.000E+04 I

........=- _ ............... . .........- _ .............. .......

1 ICE-144 1 9.842E+06 I 8.032E+07 1 2.123E+08 1 0.000E*00 1 0.000E*00 1 IPil.143 1 4.326E*05 1 0.000E+44 1 1.248E+06 1 0.000E+08 1 0.000E+08 i IPit-144 1 4.204E*03 I 2.112E+43 1 1.663E-48 1 0.000E+08 1 0.000E*00 I 14-147 I 3.220E+95 1 1.009E+07 I 9.137E+05 1 0.000E+00 1 0.000E+00 1

__..__....... ...........__... ..........................=== ___===........

18 107 1 3.562E+44 1 2.740E+46 1 3.979E*t6 1

0. 8HE*H I S.000E+tl 1 l

! 116 739 I 5.950E+44 1 1.976E+46 1 1.496E+05 1 0.tteE*H I S.SteE+00 1 I

1 i

See Note, page 4.0-16 .

l Units: Inhalation - arem/yr per uCi/m3 Others - m2 mrem /yr per uCi/sec l 4.0-12 Rev. 1, 11/85

Table 4.3-2

• CHILD PATHWAY DOSE FACTORS FOR SECTION 4.3 (R..) O Page 1 of 3: Dose Factors for Composite Worst Organ I ISOTOPEl Ipe#LAfl01 l 911U0 PLMEl WS40lMllLKI WS/CDMEATI UEGETATISII IH-3 1 1.129E+03 1 0.048E+00 1 1.551E+43 1 2.312E*f2 I 3.959E+03 I =

..........- =......

IC-14

. . - 1 3.589E+04_..........--1 0.000E+00 1 1.901E+09 I 6.10K+08 I 8.894E*t0 I INA-24

...... ..1 1.610E+04 -_... 1 1.385E+07

...- 1 1.400E*07 1 2.744E-03 1 3.729E+f5 I

=-

lP-32

... .. 1 2.605E+06 1 0.000E*00 1 1.23E+11 1 1.179E+10 1 3.366E+49 I ICR-51 1 1.690E+04 1 5.506E+06 I 8.588E*66 1 7.415E*05 1 6.213E+46 ImS4 ...__........__................___..............I 1 1.576E*06 1 1.625E+09 1 3.336E+07 1 1.275E+07 I 6.648E*t0 I l % 56 'l 1.232E+05 1 1.068E+06 1 2.964E+00 1 3.877E 5 1 2.723E*43 I

._..___.......___....._____1 IFE-59 1 1.110E+05

. ....... 1 0.000E*H I 1.778E+08 I 7.273E*08 I 8.012E*It i IFE.50 1 1.269E*06 I J.204E+M

=--- ....-

i 3.221E+08 -. ... .. .-

1 1.008E+09 I 6.693E+N I IE0-58

...- I 1.106E+06 I 4.464E+N I 1.126E+08 l 1.527E+08 1 3.771E+N I ICD-60

.. _ ....l 7.067E+06 ... ____....___. 1 2.!32E*10

.- 1 3.805E*08 I 6.105E+08 1 2.095E*09 I INI-63 I 8.214E+05 - . - . l- 0.000E+00 1 4.716E+10 1 4.633E+10 1 3.949E+10 I INI-69

..-.......- 1 8.399E+04 -

= = .I -J.451E*05

- 1..__..

3.034 -

01 1 6.460E-51 1 1.211E+03 I ICll-64

-- 1 3.670E+04

....... . I....- 6.876E+05 1 5.572E+06 1 2.216E-05 I 5.159E*05 1 12465 I 9.953E+05 1 8.583E+N I 1.752E+10 1 1.591E* 1 2.164E*09 I 12W69

..........._..09___ ..._.__

... 1 1.018E+04 1 0.000E*00 1 1.786E-09 1 0.000E*00 1 9.893E-04 I 191P-81

. ..._- 1 4.736E+02 1 7.079E+03 1 6.999E-01 1 1.514E-56 1 5.369E*00 I 1911 84

.. 1 ...

. 5.476E+02 ..1 .2.363E+05 1 1.035E.22 1 0.000E+00 1 3.822E-11 I 195 85

_ _.___.. 1___.. 2.531E+01

__...... 1 0.000E+00 1 0.000E+00 1 0.000E+00 1 0.000E+00 1 1546

.- i 1.983E+05 1 1.027E+07 1 1.395E+10 1 9.171E+08 I 4.520E+08 i 199-88

. .......... I 5.624E+02

.. ____.. 1 3.779E*84

. 1 1.130E-44 1 0.000E+00 1 4.374E-22 I 188-89 I 3.452E*0 1 1.476E+05 1

. L.__ ______....2 ..- . __- 2.222E_52 _ .____.-

1 0.000E+00 1 4.695E-26 I 1949 - ..

1 2.15E+06 1 2.509E+04 1 1.053E+10 1 7.661E+08 1 3.593E+10 1 159 90 i 1.010E+08 1 0.000E*06 . _

1 1.777E+11 1 1.654E*10 1 1.243E*12 I 19 91 1 1.739E+85 1 2.511E*06 1 4.579E+05 1 8.419E-10 1 I

.... ___. ....___.. .... . __... .....................1.15 M+46 -

• -- See Note, page 4.0 Units: Inhalation - mrem /yr per uCi/m3 l Others - m2 mrem /yr per uCi/sec l

, 4.0-13 Rev. 1, 11/85

Table 4.3-2

• CHILD PATHWAY DOSE FACTORS FOR SECTION 4.3 (R..) 13 Page 2 of 3: Dose Factors for Composite Worst Organ 1 IIITIFEl IMLAT191 I Ginse PUuEl GSTSktt!I.XI 1RS/CaptOTI UEG

.. . ............. . . ..... ... .... .............ETATISI

.... ... i 191-92 1 2.424E*85 1 8.631E*05 I 6.577E+41 1 5.554E-48 1 i lY-98

....................................1.379E*04 ...........

1 2.679E+05 I 5.309E+03 1 1.459E*H I 7.762E*05 1 I lY-91M

.................. ............ 6.569E+07 ............

i 2.812E+03 1 1.161E+85 1 8.269E.16 1 0.000 1 1.737E-05 I

..................................__.........__............E*00 lY-91 l 2.627E*06 1 1.207E+06 I 8.272E+N I 3.818E+08 1 I lY-92

.......................... ... ...... ..__.. .............. 2.484E*09 ............

1 2.390E+05 1 2.142E*05 1 1.163E+01 1 1.107E.34 4.576E+44 I

.. .................................__........... ... .. ....1 ........ ....

lY I 3.885E+05 1 2.53E*05 1 2.502E+04 1 2.461E-07 1 12it-95

...... ... ..... ............... . ..... .. ... 4.482E+06 ..... _....

I 1 2.231E+06 1 2.837E*88 1 1.398E+06 I 9.715E+0 1 8.843E+08 i 12R-97

........................ ...........__............... 8. ......... ..

1 3.511E+05 .__.....

...................__ 1 3.445E*06 I 6.680E+64 1 1.116E+88 1 1.248E*07 I 116-95

.......... 1 6.142E+05_......-

1 1.657E+08 1 3.677E+08 1 3.621E*09 I 3.870E+08 1 IMO-99 '

1 1.354E+05 1 4.626E+86 1 2.764E+08 1 3.907E*05 i 1.647E*07 I ITC-99M i 4.810E+03

........ ......- 1 2.109E+05 1 2.345E+04 1 1.100E-17 1 5.255E+03 I ITC-101 1 5.846E+02

. .......- 1 2.260E*84 1 3.054E-58 1 0.000E+00 1 2.414E-29 I 111U-103 1 6.623E*05

= ........... I 1.265E*08

....- 1 1.762E*05 1 6.378E+09 l 1.971E+08 i 138)-105 I 9.953E+04 1 7.212E*85 1 3.966E+00 1 9.362E-25 I 5 I

... ... ... ................ ...............___ _. ............ 981E*04 . . _ . . .

till)-106 I 1.432E+07 1 5.049E+88 l 2.286E+06 1 1.098 1 1.159E+18 i

................................ ..............__.........E+11 ................. ..

LAG-110M i 5.476E+06

...... ==-- - .......---1 4.019E*89 1 2.669E+10 1 1.073E*09 1 2.581E+09 I ITE.125M i 4.773E+05 1 2.128E*N I 1.174E+08 I 9.052 1 1.506E*06 I

.. ........................... ...................____...E+08 ............ .......

ITE-127M ........ i 1.480E+06 ...... ......-1 1.083E+85 I 9.437E+08 I 8.050E*09 I 3.769E+09 I ITE-127 1 5.624E+04 1 3.293E*03 1 1.895E+05 1 2.557 1 3.903E+05 I

... ....................___.__ ...... ... .........E-08 ITE.129M

........ -- i 1.761E*06 1 2.305E+87 1 1.266E+09 1 8.345E+09 I 2.460E+89 I

.ITE-129 1 2.549E+04......-

......._............ 1 3.076E*84 I 9.809E-08 I 0.000E+88 1 7.204E-02 I ITE-131M i 3.078E+05 I 9.459E+N I 3.570E+07 l 1.562E+04 2.163E+07 I i

...........__ ............ _................................I . _...... ...

ITE-131 1 2.054E*03 1 3.450E*87 l 1.350E-31 1 0.000 1 1.349E-14 I

... ......................... ..........................E+00 .....................

ITE-132 1 3.774E+05 1 4.968E+86 1 7.240E+07 1 1.484

.................___..........__ .__...................... E+07................ 1 3.111E+07 .. I 11-138 1 1.846E+N I 6.692E+86 I 6.117E+08 I 1.075 1 1.370E+88 i

............ ...............__ _ ................. .....E-83 ..._.................

t I * --

See Note, page 4.0 !

Units: Inhalation - arem/yr per uCi/m3 Others - m2 mrem /yr per uCi/sec 4.0-14 Rev. 1, 11/85 L- .

Table 4.3-2 CHILD PATHWAY DOSE FACTORS FOR SECTION 4.3 (R.j)*l Page 3 of 3: Dose Factors for Composite Worst Organ I ISOTOPEI IteetATION I Gitue PLAlfl UlS/C0lsollLIll 915/COMEATI IKliETATION I 11 131 1 1.62(+97 I 2.00M+07 1 6.094+11 I t.759E+09 I 4.754E+10 I ==

.. . .....____ .- - . . . . . . . . . - . . . . . . _ _ . = -

I1 132 1 1.93EE*05 i 1.465E*06 I 9.368E+01 1 1.421E-56 1 7.869E+03 I

. .. ..... - - ==-.........____ ..._____.

11 133 6 3.848E*06 1 2.981E*M i 6.276E+09 I 2.074E+02 I .__ 8.113E+00 1

=_ ...__.... .___. ...... ..._

11-134 I 5.069E+04 I 5.305E*t5 1 5.766E-10 1 0.000E+00 1 6.622E-03 i

==-......... .....__. ____......___.

Il-139 I 7.910E+05 1 2.947E+46 1 1.369E+07.....__ l 1.653E-14 1 9.973E+44 I

... --=........_ .. .. -

105-134 .I 1.014E+06 I 8.007E+t9 I 5.910E+10 I 2.407E+09 1 2.631E+10 l 105-136 l 1.709E+05 1 1.702E+99 I 4.412E*09 1 7.041E+07 1 2.247E W I ICS.N7 I 9.065E+05 1 1.201E+10 1 5.129E+10 1 2.122E+49 I 2.392E+10 t

~

lCk-138 I 8.399E+02 1 4.102E+t5 I 8.794E.23 1 0.000E+60 1 9.133E.11 1 IBA.139 I 5.772kI0 5~ i 1.195d+05 i 1.958E-05 ..1 0.000E+00 ...__..

1 2.950E+04 ....

I ,

ll> 140 1 1.743E+06 1 2.346E+07 1 1.863E*00 1 6.975E*07 I 2.767E+00 1

104-141 1 2.919E+03 1 4.734E+04 I 3.112E-45 1 0.000E+00 - ..__._-

1 2.042E-21 I

194 142 l 1.643E+03 1 5.064E+44 1 0.000E+00 1 0.000E+00 1 4.105E-39 I _ .-- ..

ILA-140 1 2.257E+05 1 2.186E+07 1 3.012E+05 I 8.737E+02 1 3.166E+07 I ILA-142 1 7.585E+04 I 9.122E+05 1 8.278E-06 .........__ .

1 0.00E+00 1.__..__. 2.141E+01____

I ICE.141 I 5.43*E+05 l 1.540E+07 1 2.165E+07 1 2.198E*07 1 4.082E*00 1 ICE-143 1 1.273E*05 I 2.627E+M i 2.368E+06 I 4.003E+02 1 1.364E*07 1 ICE-144 i 1.195E+07 I 8.032E*t7 I 2.110E*00 1 3.011E*08 1 1.039E+10 l IPU.143 1 4.329E*05 1 0.000E+44 1 1.234E+06 1 5.742E+07 l 1.575E+99 I _

IP8 144 I 1.565E+03 1 2.112E+03 1 3.246E-50 1 0.000E+00 1 3.829E-23 1 160-147 1 3.202E+05 1 1.009E+07 I 9.087E+05 1 2.394E*07 I 9.197E*07 I 14-187 I 9.102E+04 1 2.740E+46 I 3.850E+06 1 4.438E+00 1 5.380E+46 .-_ .

I i .. - .... -.-.-__.__ ._ _ __-.

l 18-239 I 6.401E+44 1 1.976E+46 1 1.45(+45 I 3.551E+03 1 1.357E+47 I See Note, page 4.0-16 Units: Inhalation - arem/yr per uCi/m3 Others - m2 mrem /yr per uCi/sec 4.0-15 Rev. 1, 11/85

NOTE: The R ij values of Tables 4.3-1 and 4.3-2 were calculated according to the methods of Reference 6, Section 5.3.

The values.used for the various parameters and the origins of those values are given above in Table 3.2-3, with the following exceptions:

1) Rather than being organ-specific, the ingestion and inhalation dose conversion factors (DFL and DFA) were chosen for a composite worst organ.

That is, for each age group and radionuclide,

.. the dose conversion factor used was the highest of any for that age group and radionuclide.

2) The ground plane dose factors (DFG) used were the higher of those given for the total body .,

and the skin in the referenced table of Reg. Guide 1.109.

These R i values are therefore conservative and are most appropriate for initial or rapid assessments.

4.0-16 Rev. 1, 11/85

4.4 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY In the event that the annual land use census or other informa-tion should indicate that individual members of the public may be inside the site boundary for more than a few hours each year, doses to such members of the public shall be calculated according to the methods of Sections 2.2 and 3.2.

4.0-17 Rev. 1, 11/85 L_

Section 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Technical Specification 3.12.1 states, in part:

The radiological environmental monitoring program shall be conducted as specified in (RETS) Table 3.12.1-1.

A description of the Radiological Environmental Monitoring Program thus specified is presented in this section.

5.1 SAMPLING PROGRAM ,

The radiological environmental monitoring program will be conducted in accordance with Table 5.1-1 at the locations specified in Figures 5.1-1 and 5.1-2.

NOTE: For the purpose of implementing Technical Specifi-cation 3.12.2, sampling locations will be modified as required to reflect the findings of the Land Use Census.

l i

l

. 5.0-1 Rev. 1, 11/85 l

k.

EAFOSURE STATION TYPE AND FARQUENCY PATHNAY CODE LOCATION COLLECTION NETNOD OF ANALYSIS I. AISBORNE (ah P tra 5,.S al N of vent Continuous low volume air Grose beta analyals on each weekly A sampler. Sample collected sample. Gamma spectromet ry shall pg a 232 8.4 at NNE of vent every week along with filter be performed !! grose beta escende 3' T change. O ten times the yearly mean of >g I 2r2 8.7 al NME of vent Control Station value. )

'

• C >

' C)

U C1 3H34  !!S si NE of Station Gross beta analyele perf ormed > 24 pq L hr. efter sampling to allow for Redon ()

3=

A 19D1 3.9 mi SSN of vent and Thoron daughter actavity decay. r*

tu E 16El 4.1 et NNN of vent Gamma isotopic analysis on quarterly  ;?

S co mposi t e . [j T WH

' Ln (b) I S.S et N of vent A TEDA-lapregnated flow-through W () W e Ir1 todine-131 analysis performed on g) ;g gy Eb o 232 9.4 mi NNE of vent Charcoal Cartridge le each weekly sample. O UE >"

l D2 m

+ BJ D 2r2 S.7 el NME of vent Connected to air partlCulate kd GE 3N30 lle si NE of Station aanpler and is collected I

c) hf[A N 1901 3.9 at SSN of went weekly at filter change. "O C" Fd 1

E 16El 4.1 el NNN of vent (p ;g p.

S C3 Z

H II. SOIL h

Ir! 5.8 et N of went Soil aseples taken in general Games spectroaCopy on each sample 30 M

232 9.4 et NME of vent aCCordance with procedures out- et time of ColleCElon. g;

2E1 4.4 el NNE of went lined in NASL-300 (Rev. 5/73)

Gl 2r1 5 el NNE of vent le soll pluge to a depth of 6* Sr-90 analysis on one sample from eg over en area of 25 ft2, compos-2F2 8.7 mi NNE of vent each location at time of collect ion. ff 30 3G10 16.6 en NE of went ited and sealed In a pleetic bag C)

() 3D gg 3N36 11e et NE of Station at each location. A semple w111 y,

• UE SDI 3.5 at E of went be collected from each location

p. 1901 3.9 mi SSN of vent once every 3 years. If a cult-16El 4.1 el NNW of vent able sample Cannot be obtained at ps a location, a sample shall be ob-( tained from a new location, and CD Nec shall be notified in writing LD of the neu sample location.

9 Control Station e*

EIPOSURE STATION TYPE AND FREQUENCY PATuwAY CODE LOCATION COLLECTION METHOD Or ANALYSIS

!!I. DIRECT trl 5.8 mi N of vent 2 TLD's collected from each Comme dose quarterly 8

IG38 18.5 et N of vent location quarterly. >

232 9.4 et NNE of vent 2E! 4.4 et NNE of vent O 2r2 8.7 mi NME of vent

• 2r5 7.4 et NNE of vent O H

2N!0 34 mi NNE of vent Q 3El 4.1 et NE of "ent 3r2 5.1 mi NE of vent 3r3 8.6 et NE of vent g I

3G10 16.6 et NE of vent 4

. H

] 3N18 32 mi NE of vent z z6 1

,u, 3N3.

402

u. ei NE ., went a gg g 3.7 mi ENE of vent 4 3H SS1 1.8 et 3 of vent tT3 4 g g 501 3.5 el E of vent 8W Srl 8.8 mi E of vent O >*

en pp 632 0.2 al ESE of vent 6t! 6.4 et ESE of vent O 7St S.12 el SE of vent g 7F2 9.1 mi SE of vent d O

9El 4.2 et S of vent :n test 8.14 mL SSW of vent g" ISDI 3.9 mi SSW of vent O 19r2 5.8 el SSW of vent ,g 18C18 II.6 m1 SSW of vent z y 1151 0.09 el SW of vent C)  !!E2 5.0 en Sw of vent 50 e llr! 5.2 e4 SW of vent y 12El 4.4 et NSW of vent 12r1 9.4 el WSW of vent 13El 4.2 et u of vent H

p. 13r1 9.8 et u of vent

n,2 . 5 1 . of v.nt LA 13r3 9.3 et u of vent 6 Control Stetson

EXPOSLBE STATION TYPE AND FREQUSNCY FATNWAY CODE LOCATION COLLECTION NETNOD OF ANALYSIS Ill. DIRECT (cont'd) ,

14D1 3.4 mi WNW of vent 2 TLD's Collected from eaCh Gamma does quarterly.  %

14r2 6.6 mi NNW of vent location quarterly.

15r3 5.4 mi NW of vent M

16El 4.1 mi NNW of vent p 16r2 8.1 mi NNW of vent O O

16G10 14.8 mi NNW of vent H O

IV. NATER F (a) S 781 1 et w of Ned Norse Two-gallon sample to be collec- Gamma lectopic analysis monthly. grj u Crk.3 4.5 mi SE of vent ted monthly, providing winter Z l ,

a icing conditions allow sample H i r 11A1 658 ft su of vent co!! action.  %

O

! A C ZU O C 12C14 2.5 mi NSW of vent e aH pj g E W Z Hu 16rl CAD Canals O >+

6.9 mi NNW of vent Ui 3H (b) G 25) Onsite Two-gallon grab sample collec- N-3 enelysis om monthly sample, O g

a ted monthly, only if source is M d

O 3E10 4.1 mi NE of vent likely to be effected. Gamma isotopic analysis on quarter!Y O U compoalte.  %

N Z D

'O 23 (c) D 2r1 Salen Nater Co. (raw); Se el aliquot taken da!!y and Gross beta monthly. O M R 8 mi NME of vent composited into a monthly

' O I 2 gallon sample. Gamoa isotopsc analyssa on >

4 3 e N monthly composite.

H K

• g N=) on quarterly Compos &te.

H N

, N G

! (D W

$ Control Statnon s'

4 EXPOSURE STATION TYPE AND FARQUENCY

] PATNWAT CODS LOCATION COLLECTION METHOD OF ANALYSIS V. AQUATIC B 7El *1 mi W of Mad Horse Sample of benthic organiana' Gamma lectopic and Sr-98 analyses W E Crk.; 4.5 mi SE of went and associated sediment, taken on each semiannual sample.

N seslannually.

• F4 T 1141

• 658 ft SW of vent O.

g-1 m

• 0 O 12C18 2.5 mi WSW of went O

H S O t'

[TJ VI. INCESTION Z (a) R 2F4 6.3 mi NME of went Four-gallon grab esople of Gamma isotopic and Iodine-131 M

< 1 3Gi. 16.. .i .. o, v.nt ir... . 1= con. .d ... .ont , .nai,... on ..c., ...,i., on  ; gg

,U L Sr2 7.8 mi B of vent when cows are on pasture, co!! action. iO. Z O' 1

1333 monthly at other times. O (Pil E 4.9 mi w of vent

[

h 14r1 5.5 mi www of vent A Z H Ut O >e 11A1 Outta11 area; 9 (b) F i

• 658 ft SW of went Two key samples of fleh sealed in plastic bag or jar and Gamma tootopic analysis on edible portion, on co!! action. Ut "7

3 6-*

s frosen, sentennua!!y or when in a 12C10 West Bank, oppoalte season. H Artificial Island; H

O 2.5 mi WSW of vent M Z

(b) C 11A1 Outfall area; Two key samples of crab sealed Gamma isotopic analysis on edible R

• 658 ft SW of vent in plastic bag or jar and portion, on collection. 'O W

A frozen, semiannually or when in ()

, W 8 12C16 West sank, opposite season.

O Artificial Island; >

4 3 e 2.5 et WSw of vent H

=

W H $ Control Station

\

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EIPOSURE STATION PATNNAY CODE TYPE AND FREQUEmiCY LOCATION COLLECTION NETHOD OF ANALYSIS VI. INGESTION .*

(cont'd) 0 (d) FRUITS 3G18 19.2 mi N of sent Samples Collected during normal Radiolodine determination on green e-e j O. Q nor..! h.r..et ....on, ...).d VEGETA= 2E! 4.4 mi NNE of vent in' plastic, and frosen if le.f, .eg.ta. .., on con.m ion, g if any area le irrigated by water Q TION perishable. Sufficient sample into which plaat 11guld wastes 2rl 5.9 m NNE of vent collected to yield Sea grama have been discharged. >

of dry weight. F Games isotopic analysis on collecc ion, if any area la irrigated <

• , by water into whicle plant liquid g g LA

/

wastes have been discharged. m O os

• tQ Z CT 4 3W f (e) G sus Stetton vicinity, Muskrate skinned and Genoa isotopic analysis on edible

@ A E aide of estuary frosen sealannually. portion (only), upon co!! action.

QO H gn

• O >*

E same N side of estuary, m C* W B

3-5mi from vent U O

Z sus Nithin IS mi of H Beef portion of cow sampled and H

Station frosen semiennually, subject to O availabt!!ty of slaughtered cow. >4 Z

O

'o e Control Station O g- .ss . oc. n on t. b. . ..n .t ti of con.u ion. m 4 -

e 3 W

9 W

H

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Figure 5.1-1 ONSITE SAMPLING LOCATIONS ARTIFICIAL ISLAND ,

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18 31 6S2 I2 # 6 (N

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. 5.0-7 Rev. 1, 13,gg

_ . - - _ . _ _ , - - _ . _ _ _ . , , _ _ .__,--_-__m c- ---, - - - - - -

Figure 5.1-2 OFFSITE SAMPLING LOCATIONS ARTIFICIAL ISLAND I

~~

,eI9= es G 1 to 2 J

p.

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15 u ... 3 f

w' 9"' gf

E' F ,.e, @

f ] ,.,g e-.

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to ' a L- ens L"OI"l""J "O 1 Y

5.0-8 Rev. 1, 11/85 L

8.

5.2 INTERLABORATORY COMPARISON PROGRAM Technical Specification 3.12.3 states, in part:

Analyses shall be perfetmed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

Participation in an approved Interlaboratory Comparison Program ensures that an independent check on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices is performed. This check is performed as part of the QA program for environmental monitoring in order to demonstrate that the results are valid,for the purpose of Section IV.B.2 of Appendix I to 10CFR50.

A summary of the Interlaboratory Comparison Program results obtained is required to be included in the Annual Radiological l Environmental Operating Report pursuant to Technical Speci-fication 6.9,.l.11.

i i

l l

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l 5.0-9 Rev. 1, 11/85