ML19309F053

Draft Offsite Dose Calculation Manual

ML19309F053
Person / Time
Site:	LaSalle
Issue date:	12/20/1979
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19276H800	List: ML19276H799 ML19309F052 ML19309F053
References
NUDOCS 8004280414
Download: ML19309F053 (150)

Text

_ _ __

O -

LA SALLE COUNTY STAT lON OFFSITE DOSE CALCULATION MANUAL l

l l

COMMONWEALTH EDISON COMPANY FEBRUARY 1979 ,

Revision I (

September 1979 1

DOCKET NUMBERS N

"'"'~"~~-

50-373 AND 50-374 --

U 80 0428 l .- - . _.

• 4 e

e lh e

j .

e

• e 9

/

r 9

l l

)

e i

\

t I

i l

l

• l l

i i

S 9

. e REVISION 1 SEPTEMBER 1979 TABLE OF CONTENTS PAGE

1.0 INTRODUCTION

1.0-1 2.0 OFFSITE DOSE LIMITS 2.1-1 2.1 AIRBORNE RELEASES 2.1-1 2.1.1 Noble Gases 2.1-1 2.1.1.1 10 CFR 50 Appendix I Design Objectives 2.1-1 l 2.1.1.1.1 Air Dose 2.1-1

~

2.1.1.1.1.1 Gamma Air Dose 2.1-1 2.1.1.1.1.1.1 Gamma Air Dose, Calendar Quarter 2.1-1 2.1.1.1.1.1.2 Gamma Air Dose, Calendar Year (Four Consecutive Quarters) 2.1-3 2.1.1.1.1.2 Beta Air Dose 2.1-3 2.1.1.1.1.2.1 Beta Air Dose, Calendar Quarter 2.1-3 2.1.1.1.1.2.2 Beta Air Dose, Calendar Year (Four Consecutive Quarters) 2.1-5 2.1.1.1.2 Whole Body Dose 2.1-6 2.1.1.1.2.1 Whole Body Dose, Calendar Quarter 2.1-6 2.1.1.1.2.2 Whole Body Dose, Calendar Year (Four Consecutive Quarters) 2.1-7 2.1.1.1.3 Skin Dose 2.1-7 2.1.1.1.3.1 Skin Dose, Calendar Quarter 2.1-7 2.1.1.1.3.2 Skin Dose, Calendar Year (Four Consecutive Quarters) 2.1-7 2.1.1.2 10 CFR 20 Release Rate Limits 2.1-8 2.1.1.2.1 Whole Body Dose Rate, Calendar Year (Four Consecutive Quarters) 2.1-8 2.1.1.2.2 Skin Dose Rate, Calendar Year (Four Consecutive Quarters) 2.1-8 2.1.2 Radioiodines, "Particulates," and Other (Nonnoble Gas) Radionuclides 2.1-9 2.1.2.1 10 CFR 50 Appendix I Design Objectives 2.1-9 2.1.2.1.l' Inhalation + Food Pathways Dose, Calendar Quarter . 2.1-10 2.1.2.1.2 Inhalation + Food Pathways Dose, Calendar Year (Four Consecutive Quarters) 2.1-16 2.1.2.2 10 CFR 20 Release Rate Limit 2.1-17 2.1.3 Symbols Used in Section 2.1 2.1-19 2.1.4 Constants Used in Section 2.1 2.1-22 2.2 RADIOACTIVITY IN LIQUID RELEASES 2.2-1 2.2.1 10 CFR 50 Appendix I Design Objectives 2.2-1 2.2.2 10 CFR 20 Maximum Permissible Concentrations in the Unrestricted Area 2.2-3 2.2.3 10 CFR 20 Maximum Permissible Concentrations at the Nearest Surface Water' Supply 2.2-4 i

l 1

G REVISION 1 SEPTEMBER 1979 TABLE OF CONTENTS (Cont'd)

PAGE 2.2.4 Symbols Used in Section 2.2 2.2-8 2.2.5 Constants Used in Section 2.2 2.2-9 2.3 ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE 2.3-1 2.3.1 Sources of Radiation and Radioactivity 2.3-1 2.3.1.1 Uranium Fuel Cycle - Definition 2.3-1 2.3.1.2 Radiological Impact of Uranium Fuel ,

Cycle Operations 2'.3-1 2.3.1.2.1 Milling 2.3-2 ,

2.3.1.2.2 Conversion 2.3-2 2.3.1.2.3 Enrichment 2.3-2 2.3.1.2.4 Fabrication 2.3-3 2.3.1.2.5 Generation of Electricity 2.3-3 2.3.1.2.6 Reprocessing 2.3-6 2.3.1.2.7 Waste Disposal Sites 2.3-6 2.3.1.2.8 Transportation 2.3-7 2.3.1.2.9 Storage of Spent Fuel in Offsite Facilities 2.3-7 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes 2.3-8 2.3.1.3 Summary 2.3-8 2.3.2 Numerical Models 2.3-8 2.3.2.1 Airborne Releases and Direct Radiation 2.3-8 2.3.2.1.1 Whole Body Dose 2.3-8 2.3.2.1.2 Thyroid Dose 2.3-10 2.3.2.1.3 Any other Organ Dose 2.3-10 2.3.2.2 Radioactivity in Liquid Releases 2.3-10 2.3.3 Symbols Used in Section 2.3 2.3-11 2.3.4 Constants Used in Section 2.3 2.3-12 3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE MODELS 3.1-1 3.1 METEOROLOGICAL DATA FOR MODELS 3.1-1 3.1.1 Current Record 3.1-1 3.1.2 Historical Record 3.1-2  !

3.1.2.1 Internal Dose 3.1-2 l 3.1.2.2 External Dose 3.1-4 l 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS 3.2-1 l l 3.2.1 Numerical Model 3.2-1 3.2.2 Source Configuration Considerations 3.2-2 3.2.2.1 Elevated Releases 3.2-2 1 3.2.2.1.1 Plume Rise (h ) .2-2 r

3.2.2.1.2 Terrain Correction (h ) 3.2-4 t

11 l l

,1

s a REVISION 1

- SEPTEMBER 1979 TABLE OF CONTENTS (Cont'd)

PAGE 3.2.2.1.3 Downwash Correction (C) 3.2-5 3.2.2.2 Vent Stack Releases 3.2-5 3.2.2.3 Ground Level Releases 3.2-6 3.2.3 Removal Mechanism Considerations 3.2-7 3.2.3.1 Radioactive Decay 3.2-7 3.2.3.2 Plume Depletion and Deposition 3.2-7 3.2.3.3 Relative Deposition Factor (D/Q) 3.2-8 3.2.4 Symbols Used in Section 3.2 3.2-9 3.2.5 Constants Used in Section 3.2 3.2-10 .

3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3-1 ,

3.3.1 Gamma Radiation 3.3-1 3.3.1.1 Gamma Air Dose - Finite Clead Model 3.3-1 3.3.1.2 Whole Body Dose Factors 3.3-2 3.3.2 Beta Radiation 3.3-3 3.3.2.1 Beta Particle Air and Skin Dose Factors 3.3-3 3.3.3 Symbols Used in Section 3.3 3.3-4 3.3.4 Constants Used in Section 3.3 3.3-5 3.4 MODELS FOR CALCULATING DOSE FROM RADIOIODINES, "PARTICULATES," AND OTHER RADIONUCLIDES 3.4-1 -

4.0 A00ATIC TRANSPORT AND DOSE MODELS 4.1-1 4.1 AOUATIC TRANSPORT 4.1-1 4.1.1 River Model 4.1-1 4.1.2 Lake Michigan Model 4.1-1 4.1.3 Symbols Used in Section 4.1 4.1-2 l 4.2 AQUATIC DOSE MODEL 4.2-1 4.2.1 Symbols Used in Section 4.2 4.2-2 l

4.3 AOUATIC TRANSPORT DURING TANK OVERFLOW -

CONDITIONS 4.3-1 4.3.1 River Model 4.3-1 4.3.2 Lake Michigan Model 4.3-1 4.3.3 Symbols Used in Section 4.3 4.3-2 l 5.0

SUMMARY

5.1-1 5.1 AIRBORNE EFFLUENTS 5.1-1 l

l 5.1.1 10 CFR 50 Appendix I Design Objectives 5.1-1 5.1.2 10 CFR 20 Release Rate Limits 5.1-3 111

0 l

'. l REVISION 1 SEPTEMBER 1979

~

TABLE OF CONTENTS (Cont'd)

PAGE 5.2 LIQUID RELEASES 5.2-1 5.2.1 10 CFR 50 Appendix I Design Objectives 5.2-1 5.2.2 10 CFR 20 Maximum Permissible Concentrations 5.2-1 5.2.2.1 Unrestricted Area 5.2-1 5.2.2.2 Nearest Surf ace Water Supply 5.2-2 5.3 ,IlRANIUM FUEL CYCLE 5.3-1 5.4 PRIMARY DRINKING WATER STANDARDS 5.4-1

6.0 REFERENCES

6.0-1 7.0 APPENDICES 7.0-1 7.1 DATA COMMON TO ALL NUCLEAR STATIONS 7.1-1 7.2 DATA SPECIFIC TO EACH NUCLEAR STATION 7.2-1 8.0 MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS

• 1-1 8.1 GASEOUS RELEASES 8.1-1 8.2 LTOUID RELEASES 8.2-1 iv

s REVISION 1

- SEPTEMBER 1979

~

LIST OF TABLES NUMBER TITLE PAGE 2.3-1 Numerical Models for Computing Radiation Dose from Uranium Fuel Cycle Operations 2.3-13 5.1-1 Maximum Doses Resulting from Airborne Releases 5.1-2 5.1-2 Maximum Instantaneous Release Rates 5.1-4 5.2-1 Maximum Doses Resulting from Liquid Effluents 5.2-3 5.3-1 Compliance Status: Uranium Fuel ,

Cycle Operations: 40 CFR 190 5.3-2 5.4-1 Projected Dose at Nearest Community , ,

Water System 5.4-2 7.1-1 to See Appendix 7.1 7.1-1 7.1-13 7.2-1 to See Appendix 7.2 7.2-1 7.2-8 (or 7.2-11, for Dresden only) f v

e

i REVISION 1 SEPTEMBER 1979 LIST OF FIGURES NUMBER TITLE 1.0-1 Flow Chart for Offsite Dose Calculations

- 7.1-1 Plume Depletion Ef fect for Ground-Level Releases 7.1-2 Plume Depletion Effect for 30m Releases 7.1-3 Plume Depletion Effect for 60m Releases 7.1-4 Plume Depletion Effect for 100m Releases 7.1-5 Relative Deposition for Ground-Level Releases 7.1-6 Relative Deposition for 30m Releases 7.1-7 Relative Deposition for 60m Releases 7.1-8 Relative Deposition for 100m Releases

,. 7.2-1 Unrestricted Area Boundary 7.2-2 Locations of Fixed Environmental Radiological Monitoring Stations O

I j vi c -

REVISION 1 SEPTEMBER 1979

1.0 INTRODUCTION

This document provides a concise description of the environmental ,

1 dose models and techniques used to calculate the offsite doses j

- resulting from the release of radioactive material from Com-monwealth Edison's nuclear power plants. A flow chart of these dose models and techniques is given in Figure 1.0-1.

Documentation for both airborne (Sections 2.1 and 3.0) and aquatic pathways (Sections 2.2 and 4.0) are included.

The models consider two release modes: airborne and liquid.

Airborne releases are further subdivided into two subclasses:

(1) radioiodines, particulates, and other nonnoble gas nuclides, and (2) noble gases. ,

t Radiciodines, Particulates, and Other Nuclides In this model it is assumed that there is an adult and infant living in each of 16 sectors around the station. Infant exposure occurs through inhalation and any actual milk pathway. Adult exposure derives from inhalation, assumed leafy vegetable and produce pathways, and any actual milk and meat pathways.

Doses to each of seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung, and GI-LLI) are computed from individual nuclide contributions in each of the sectors. Searching over sector and organ, the largest ofgan dose is compared to the 10 CFR 50 Appendix I design objectives. This dose calculation is performed monthly for infants and annually for adults. (The adult dose is computed annually to confirm the premise that the infant is the critical person. The adult will be substituted I

for the infant in the monthly schedule if found to be the critical person.) As necessary, the release rates of these nuclides will be converted to dose rates for comparison to the limits of 13 CFR 20.

1.0-1

REVISION 1 SEPTEMBER 1979

~

Noble Gases Exposure to the beta and gamma radiations of the noble ,

gases will result in a whole body and skin dose.

The maximum whole body and skin doses for each offsite sector are determined from the individual nuclide con-tributions and the maximum dose values are compared to the 10 C?R 50 Appendix I design objectives. This calculation is performed monthly. As necessary, the noble gas release rate will be converted to dose rates ~

f>r comparison to the limits of 10 CFR 20. - .

For liquid releases it is assumed that liquid effluents discharged into a river undergo mixing prior to consumption as either potable water or fish by adults. For releases to Lake Michigan a finite plume dilution factor is computed for.the potable water path-way and a hypothetical river model is created for the fish pathway. Doses to the seven critical organs are determined -

from individual nuclide contributions and the largest organ dose is compared to the 10 CFR 50 design objectives. Compliance with the 10 CFR 20 maximum permissible concentrations is done on a batch-by-batch basis prior to discharge.

Compliance with the various regulatory limits for offsite doses is demonstrated with the techniques of Section 5.0 All site independent data used in the calculations are given in Appendix 7.1. Site specific data are given in Appendix 7.2.

The models and techniques used to establish the alarm and trip setpoints of the gaseous and liquid effluent monitors are described in Section 8.0.

I i

1.0-2 k .-

R;1:sse Radionuclide Critical Environmental Critical Regulatory Compliance Frequency of Mode Class Person Pathway Organ Limit Methodology Calculation

-Inhalation -10 CFR 50 Dose Calculation Monthly l Infant Thyroid *

-Milk -10 CFR 20 Release Rate Calculatiou - When Necessary Radioiodines,

~Particulates -Inhalation

-Milk -10 CFR 50 Dose Calculatior. Annually A Adult --Meat Thyroid

• Airborne-

-Leafy Vegetabler -10 CFR 20 Release Rate Calculation- When Necessary

-Produce

-Whole Body -10 CFR 50 Dose Calculation 24onthly l

, -Noble Oases All Plume Exposure - -

. Persons Skin - -10 CFR 20 Release Rate Calculation - When Necessary b Adult Water Various 10 CFR 20 10 CFR 20, App. B, Ench Table 2, Col. 2 Batch Liquid All- -Fieh Thyroid Adult .

- or -10 CFR 50 Dose Calculation  ::onthly l

. '-Water Bone

• O Most likely critical organ; however, dose is computed for 7 organs. k H A The computation of dose to the adult is performed annually to confirm the premise that the infant is the n@ ,

critical person. :o g C

w FIGURE 1.0-1 l FLOW CHART FOR OFF-SITE DOSE CALCULATIONS

. /^

e

~

u C

0

REVISION 1 SEPTEMBER 1979 2.0 OFFSITE DOSE LIMITS 2.1 AIRBORNE RELEASES 2.1.1 No'ble Gases 2.1.1.1 10 CFR 50 Appendix I Design Objectives 2.1.1.1.1 Air Dose The average air dose in unrestricted areas due to noble gases released in gaseous effluents from each reactor shall be limited to the following expressions:

2.1.1.1.1.1 Gamma Air Dose 2.1.1.1.1.1.1 Gamma Air Dose, Calendar Quarter 3.17 x 10-8 }{' ,

S Ag +V A +G A fg

< 5 mrad (2.1) i -

-8 3.17 x 10 Conversion Constant (years /second)

Converts seconds to years.

Sg Gamma Dose Constant, Stack Release (mrad /yr per pCi/sec)

The gamma ray air dose constant for each identified noble gas radionuclide released from a stack ( Appendix 7.2) . The constant is evaluated for a finite plume using the methods explained in Subsection 3.3.1.2.

A Accumulative Radionuclide Release, Stack Release ls (pCi) .

The accumulative release of radionuclide i from a stack. Releases shall be cumulative 2.1-1

4 l

REVISION 1 SEPTEMBER 1979 over the calendar quarte'r or year (four  ;

consecutive quarters) ,as appropriate.  !

. i Vg Gamma Dose Constant, Vent Release 1 (mrad /yr per p Ci/sec)

The gamma ray air dose constant for each identified noble gas radionuclide released from a vent (Appendix 7.2). The plume may be elevated part of the time as determined by the criteria of Regulatory Guide 1.111 (Reference 6.4),. ,

part C.2.b.- The constant is evaluated for a finite plume using the method explained in Subsection 3.3.1.2.

A gy Accumulative Radionuclide Release, Vent Release (pci)

The accumulative release of radionuclide -

i from a vent. Releases shall be cumulative over the calendar quarter or year (four consecutive quarters) as appropriate.

Gg Gamma Dose Constant, Grcund Level Release (mrad /yr per pCi/sec)

The gamma ray air dose constant for each identified noble gas radionuclide released from a ground level release point (Appendix 7.2). The constant is' evaluated for a finite plume using the method explained in Subsection 3.3.1.2.

A ig Accumulative Radionuclide Release, Ground Level Release (pCi)

The accumulative release of radionuclide i from a ground level release point. Releases 1

shall be cumulative ov.er the calendar quarter 2.1-2 l

l 6

= '

l .

REVISION 1

• SEPTEMBER 1979 ,

I

~

1 1

~

or year (four consecutive quarters) as appropriate.

2.1.1.1.1.1.2 Gamma Air Dose, Calendar Year (Four Consecutive Quarters) 3.17 x 10 -8}{ g i Als + Yi A iv + Gg A gg 3 10 mrad.' .

1_ _ (2.2). .

2.1.1.1.1.2 Eeta Air Dose 2.1.1.1.1.2.1 Beta Air Dose, Calendar Quarter-3.17x10-8) L (X/0) s A'is + (X/0)y A'iy + (X/0)g A'ig i . .

< 10 mrad ( 2 . '3 ) -

1 Beta Air Dose Constant (mrad /yr per pCi/m )

The air dose factor due to beta emissions for each identified noble gas radionuclide.

(Table 7.1-13)

Relative Effluent Concentration, Stack (X/0) s Release (sec/m )

The highest calculated annual average re-lative concentration in a given direction at or beyond the restricted area boundary for stack releases (Table 7.2-6 or Table 7.2-9) .

Accumulative Radionuclide Release, Stack A'i s Release Adjusted for Radiodecay (p Ci) 2.1- 3

. 1 REVISION 1 SEPTEMBER 1979 l

The accumulative release of radionuclide i from a stack, adjusted to account for radiodecay in transit.

A 3 =Als * **E I~ Al R/3600 us ) (2.3a)

Ag Radiological Decay Constant (hr-1)

The radiological decay constant for radionuclide i. See Tables 7.1-9 and 7.1-11.

R Downwind Range (m)

The distance downwind to the

, point of interest. See Tables 7.2-6, 7.2-7, and 7.2-8.

3600 Constant (sec/hr)

Converts hours to seconds u

s Average Wind Speed (m/sec)

The average wind speed for a stack release. See Table 7.2-6.

(X/Q) y .. .

Relative Effluent Concentration, Vent

' Release (sec/m )

The highest calculated annual average relative concentration in a given direction at or beyond the restricted area boundary for vent releases. The partially elevated plume model of Regulatory Guide 1.111, part C.2.b (Reference 6.4) is used when necessary. See Subsection 3.2.2.3 and Table 7.2-6 or Table 7.2-9.

A y Accumulative Radionuclide Release from Vent, Adjusted for Radiodecay (UCi) j 2.1-4

REVISION 1 SEPTEMBER 1979

~

The accumulative release of radionuclide i from a vent, adjusted for radiodecay in transit.

A' y =A gy x exp (- 11 R/3600 uy) (2.3b) uy Average Wind Speed (m/sec)

The average wind speed for a vent release. See Table 7,2-6.

Relative Effluent Concentration, Ground (x/Q)9 3 ' '

Level Release (sec/m )

The highest calculated annual average relative concentration in a given direction at or beyond the restricted area boundary for ground level releases. (See Table 7. 2-6 or Table 7. 2-9. )

. Aj g Accumulative Radionuclide at Ground Level, .

Adjusted for Radiodecay (pCi)

The accumulative release of radionuclide i from ground level, adjusted for radiodecay in transit.

A'g = A gg x exp (- l g R/3600 ug) (2.3c) u Average Wind Speed (m/sec) g The average wind speed for a ground level release. See Table 7.2-6.

s 2.1.1.1.1.2.2 Beta Air Dose, Calendar Year (Four Consecutive Quarters) 3.17 x 10

-8]i g

(X/0)s A s + (X/Q)y A[y + (X/Q)g A' g

, .(2.4) l

< 20 mrad i 1 1

l 2.1-5

l REVISION 1 SEPTEMBER 1979 i

2.1.1.1.2 Whole Body Dose The average dose to individuals in unrestricted areas due to noble gases released in gaseous effluents from each reactor.

shall be limited to the following expressions:

2.1.1.1.2.1 'Whole Body Dose, Calendar Quarter (0.7) (1.11) (3.17 x 10~0) )b Sg Als + Vg A gy +G g A gg (2.5) 1- .

,2.5 mrem 0.7 Shielding and Occupancy Factor ~ ~ - '

The shielding and occupancy factor for pro-tection against gamma radiation.

1.11 Conversion Ccnstant (mrem / mrad)

Converts rads in air to rems in tissue.

5g Gamma Whole Body Dose Constant, Stack Release (mrad /yr per pCi/sec) 5 g is the constant S g multiplied by the shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Sub-section 3. 3.1. 2) .

Vg Gamma Whole Body Dose Constant, Vent Release (mrad /yr per pCi/sec)

The consti.nt f7 multiplied by the shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Subsection 3.3.1.2) .

Gg Gamma Whole Body Dose Constunt, Ground Level Release (mrad /yr per pCi/sec)

The constant G i multiplied by the shielding factor afforded by 5 cm of tissue; used to evaluate whole body dose. (See Subsec-tion 3. 3.1. 2. )

2.1-6

REVISION 1 SEPTEMBER 1979 2.1.1.1.2.2 Whole Body Dose, Calendar Year (Four Consecutive Ouarters)

(0.7) (1.11) (3.17 x 10-8) g his + Vi Aiv + Gi A fg i '. _ (2.6)

$5 mrem

~

2.1.1.1.3 Skin Dose The average skin dose to individuals in unrestricted areas due to noble gas released in gaseous effluents from each reactor shall be limited to the following expressions:

2.1.1.1.3.1 Skin Dose, Calendar Quarter (2.7)

-8 '

3.17 x 10 1.0 E i (X/0) s ^is + (X/0) y A'gy +

(X/0) g A'g i

+ (0.7) (1.11) (S g Ais + Vi A iv + Gi A ig) 17.-5 mrem l.0 Shielding and Occupancy Factor The shielding and occupancy factor for pro-tection against beta radiation.

Eg Beta Skin Dose Constant (mrem /yr per j 3

UCi/m )

, The skin dose factor due to beta emissions for each identified noble gas radionuclide l

I (Table 7.1-13). Accounts for attenuation of beta radiation during passage through I

7 mg/cm2 of dead skin.

1 1

2.1.1.1.3.2 Skin Dose, Calendar Year (Four Consecutive Ouarters)

(2.8)

-8 3.17 x 10 1.0 E 1 (X/0) s ^ s + (X/0)y A[y +

i .

(X/0)g A'g )i

+ (0. 7) (1.11) (S i Als + Vi Aiv + Gi Aig}

$ 15 mrem 2.1-7 .

. \

l REVISION 1 SEPTEMBER 1979 2.1.1.2 10 CFR 20 Release Rate Limits The maximum dose rate to individuals in unrestricted areas due to noble gases released in gaseous effluents from the site shall be limited to the following expressions:

2.1.1.2.1 Whole Body Dose Rate, Calendar Year (Four Consecutive Quarters) 1.11 x

}[

i -

S 1 Qis + i Oiv + 1 Q ig

< 500 mrem /yr (2.9)

(10 CFR 20.105 limit)

Q is Release Rate, Stack Release (pCi/sec)

The release rate for radionuclide i due to a stack release. .

O gy Release Rate, Vert Release (pCi/sec)

The release rate for radionuclide i due to a vent release.

O gg Release Rate, Ground Level Release (pCi/sec)

The rele'ase rate for radionuclide i due to a ground level release.

2.1.1.2.2 Skin Dose Rate, Calendar Year (Four Consecutive Quarters)

/ )

)[

i Lg (X/Q) s Ois + (X/Q)y O gy + (X/Q)g Q{gY~

l + (2.10) l.11 x (S g Qis + Yi Q iy +GgOgg) 13000 mrem /yr

~

(10 CFR 2d.105 limit)

Q s Release Rate, Stack Release, Adjusted for Radiodecay (sci /sec)

Qg 's " Dis * **P I- A i R/3600 us) (2.10a) 2.1-8

REVISION 1 SEPTEMBER 1979 The release rate for radionuclide i from a stack adjusted for radiodecay in transit.

. Og'y Release Rate,. Vent Release, Adjusted for Radiodecay (p C1/sec)

The release rate for radionuclide i from a vent, adjusted for radiodecay in transit.

Ojy =O gy x exp (- A y R/3600 uy) (2.10b)

Release Rate, Ground Level, Adjusted for Qjg Radiodecay (VCi/sec)

The release rate for radionuclide i from ground level, adjusted for radiodecay in -

transit.

Ojg=Ogg x exp (- A g R/3600 ug ) (2.10c) 2.1.2 Radioiodines, "Particulates", and Other (Nonnoble Gas)

Radionuclides 2.1.2.1 10 CFR 50 Appendix I Desion Objectives The average dose to an individual in the unrestricted area from radiciodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents released 'from each reactor shall be limited to the following expressions.

i i

l 2.1-9

REVISION 1 SEPTEMBER 1979 2.1.2.1.1 Inhalation + Food Pathways Dose, Calendar Quarter Inhalation: 3.17 x 10-8 x 10 6 p a , DFAija (X/Q)s A is i

+ ( X/Q) y A[y + (X/Q)g A[g

• + +

Food: + 365 ,DFIija U a

f P V a i .

1 7.5 mrem .

6 10 Conversion Constant (pCi/uC1)

Converts uCi to pCi.

Conversion Constant (yrs / day)

Converts days to years.

R, Individual Air Intake Rate (m /yr)

The air intake rate for individuals in group a.

See Tables 7.1-2 and 7.1-3.

t r

Deposition Time or Release Period (days)

Length of time for deposition.

DFA ija Inhalation Dose Factor (mrem /pCi)

The inhalation dose commitment factor for radionuclide i, organ j, and age group a.

See Table 7.1-1.

(X/Q) s See Table 7.2-6 or Table 7.2-9.

(X/Q)y See Table 7.2-6 or Table 7.2-9.

(X/Q)g See Table 7.2-6 or Table 7.2-9.

2.1-10

( . . .

REVISION 1 SEPTEMBER 1979 .

DFI Ingestion Dose Factor (mr em/pCi) g33 The ingestion dose commitment factor for -

radionuclide i, organ j, and age group a.

See Table 7.1-1.

P F Foodstuff Consumption Rates (kg/yr, liters /yr, Ua, U , U ,U kg/yr, kg/yr, respectively)

The annual consumption rates (usages) of produce (nonleafy vegetal; ,, "ruits, and grain),

milk, leafy vegetables, and ni_;t ( fle sh) , respec-tively, for individuals in age group a.

See Tables 7.1-2 and 7.1-3.

f,f p y Produce, Leafy Vegetable Fractions The respective fractions of the ingested produce and leafy vegetables that are grown ,

in the garden of interest; dimensionless.

See Table 7.1-2.

Cf, Cf, Cf, Cf Foodstuff Concentrations (pCi/kg, pCi/ liter, pCi/kg, pCi/kg, respectively)

The c'1? rage concantraticns of radionuclide i in produce (nenleafy vegetables, fruits, and grain), milk, leafy vegetables, and meat (flerh), respectively.

CfandCfarecalculated from Equation 2.12 below. l Cg Conce.itration in Vegetation (PCi/kg)

The concentration of radier.uclide i in vegetation.

l . .

_1 - exp (- A Ei DI exp (- t) d x r e. h *f A

C1= i Y A g f l

v Ei (2.12) 2.1-11 l

REVISION 1 SEPTEMBER 1979 dg Deposition Rate (pCi/m - hr)

The deposition rate of radionuclide i onto the ground.

A ls (D/0)s + Aiv (D/Q)y

d. = 10 6 2

24 x t ~

(2.13) r ,

+ A.

19 (D/Q)9 24 Conversion Constant (hr/ day)

Converts days to hours.

(D/Q) Relative Deposition Factor, Stack

~

Release (m )

The calculated annual average ,l relative deposition factor in a given direction at or beyond the restricted area boundary for stack releases. (See Subsection 3.2.3.3; see Table 7.2-6 or Table 7.2-9 for produce and leafy vegetable pathways; Table 7.2-7 or Table 7.2-10 for milk and meat pathways.)

(D/Q)y Relative Deposition Factor, Vent

~

Release (m )

. The calculated annual average relative deposition factor in a given direction at or beyond the restricted area boundary for vent releases. The partially elevated plume model of Regulatory Guide 1.111., part C.2.b is used. (See Subsection 3.2.3.3; see Table 7.2-6 or Table 7.2-9 1

for produce and leafy vegetable path-

)

ways; Table 7.2-7 or Table 7.2-10 for. milk and meat pathways.)

, 2.1-12 i

1 REVISION i l SEPTEMBER 1979 Relative Deposition Factor, Ground (D/Q)9 Level Release (m-2)

The calculated annual average relative deposition factor in a given direction I at or beyond the restricted )

area boundary for ground level releases. (See Subsection 3.2.3.3; see Table 7.2-6 or Table 7.2-9 for produce and leafy vegetable pathways; Table 7.2-7 or Table 7.2-10 for milk and meat pathways.)

r Crop Retention Fraction

• The fraction of deposited activity retained on crops; dimensionless; see Tables 7.1-2 and 7.1-3.

A Ei Effective Decay Constant (hr-1)

The effective removal rate constant for radionuclide i from crops.

A Ei Ai+A w

, (2.13a)

Ay Weathering Decay Constant (hr~1) 3 The removal constant for physical loss by weathering. 'See Tables 7.1-2 and 7.1-3.

I t, Effective Crop Exposure Time (hr) i The effective crop exposure time. See Tables i

7.1-2 and 7.1-3.

2.1-13 e

1 1

REVISION 1 SEPTEMBER 1979 t

h Harvest to Consumption Time (hr)

The time between harvest and consumption.

See Tables 7.1-2 and 7.1-3.

i Seasonal Growing Factor f

A factor which accounts for seasonal growth of vegetation. See Tables 7.1-2 and 7 1-3.

Yy Productivity Yield (kg/m )

The agricultural productivity yield. See Tables 7.1-2 and 7.1-3.

(pCi/ liter)

( Milk Concentration The concentration of radionuclide i in milk.

(

is calculated from the following equation (af ter Regulatory Guide 1.109 [ Reference. 6.5]) .

I I

Cf=FM CfW g exp (- Ag t} M F Milk Fraction (days / liter)

M The average fraction of the animal's daily intake of radionuclicle i which appears in each liter of milk. See Table 7.1-4.

Cf Feed Concentration (pCi/kg)

The average concentration of radio-l nuclide i in animal feed.

l For milk and meat pathways, the following expression is to be used (after Regulatory Guide 1.109, [ Reference 6.5]) .

s Cf=f g f g Cf+(1-f) f C ,

( 2.15)  !

+f g (1-fg) C{

2.1-14 l --

s REVISION 1 SEPTEMBER 1979 f Pasture Grass Fraction 9

The fraction of daily feed that is pasture grass when the animal grazes on the pasture. See Tables 7.1-2 and 7.1-3.

C{ Pasture Grass Concentration (pCi/kg)

The concentration of radionuclide i in pasture grass (calculated using Equation 2.12 for Cf with fg = 1; other parameters are given in Tables 7.1-2 and 7.1-3).

C[ Stored Feed Concentration (pCi/kg) l The concentration of radionuclide i in stored feed (calculated using Equation 2.12 for fC with ff = 1; other parameters are given in Tables 7.1-2 and 7.1-3).

Wg Feed Consumption (kg/ day)

The amount of feed consumed by the animal each day. See Tables 7.1-2 and 7.1-3. l l

t M Milk Transport' Time (hr) l The average time from the production of milk -

to its consumption. See Tables 7.1-2 and 7.1-3.

1 I

l 2.1-15

REVISION 1 SEPTEMBER 1979 C[ Meat Concentration (PCi/kg)

The concentration of radionuclide i in meat.

Wg exp (- A gts} '

C[=FpCf (

• F Meat Fraction (days /kg) 7 The fraction of the animal's daily intake -

of radionuclide i which appears in each kilo- . ,

gram of flesh. See Table 7.1-4.

t s

Slaughter to Consumption Time (hr)

The time from slaughter to consumption.

See Table 7.1-2.

2.1.2.1.2 Inhalation + Food Pathwm/s Dose, Calendar Year .

(Four Consecutive Quarters) 3.17 x 10-8 x 10 6 g DFA (X/0) s ^is + (X/0) y A iy a ija i

+ (X /0) g A gg t c (2.17)

+yfg DFI ija U fp Cf + U Cf + U fy Cf+U Cf -

g 115 mrem 2.1-16 s

wwmm

REVISION 1 SEPTEMBER 1979 2.1.2.2 10 CFR 20 Release Rate Limit The maximum dose rate to an organ of an infant from all radio-nuclides and radioactive materials in particulate form and radionuclides other than noble gases shall be limited to the values given by the equations below. For purposes of demon-strating compliance with the Technical Specifications, the dose to the infant shall be considered limiting.

6R a ~

Inhalation: 10 j DFA gj, (X/0) s O s + (X/0) y O'y (Regulatory g _ _ .-.

Guide 1.109,

+ (X/0)g O'gg Equation 13)

. (2.18)

Reg latory

+

J DFI ija U C < 1500 mrem /yr Guide 1.109, i Equation 14)

K Seasonal Adjustment Factor K is a seasonal adjustment factor to account for nongrazing during the winter and partial grazing during the summer; = 0 for November-April; = 0.5 for May-October.

Cf Milk Concentration (pCi/ liter)

The concentration of radionuclide i in milk.

M C =F g Cf Wf exp (- A g t) M (2.19)

Cf Feed Concentration (pCi/kg)

The concentration of radionuclide i in feed.

Cf=d i xr 1 - exp (A Ei e (2.20) y Ei (Note that this assumes feed to be 100% pasture grass.)

2.1-17

_.em

, l 1

REVISION 1 l SEPTEMBER 1979 i 2 1 Jg Deposition Rate (pCi/m . hr) j 6

dg = 3600 x 10 x 0 (D/Q) s + 0 v (D/Q)y 9

, (2.21)

~

+Q ig (D/Q)g See Table 7.2-7 or Table 7.2-10 for milk pathway.

(D/Q)s (D/Q)y See Table 7.2-7 or Table 7.2-10 for milk pathway.

See Table 7.2-7 or Table 7.2-10 for milk pathway.

(D/Q)g l

2.1-18

-- -w -

REVISION 1 SEPTEMBER 1979  ;

1 2.1.3 Symbols Used In Section 2.1 SYMBfL NAME UNIT Sg Gamma Dose Constant, Stack Release (mrad /yr per pCi/sec)

A Accumulative Release, Stack (pCi) l ls Vg Gamma Dose Constant, Vent Release (mrad /yr per ECi/sec)

A gy Accumulative Release, Vent (pCi) l G Gamma Dose Constant, Ground (mrad /yr per pCi/sec) i Level Release A

gg Accumulative Release, (mci)

Ground Level Lg Beta Dose Ccnstant (mrad /yr per pCi/m )

(x/Q) s Relative Effluent Concentration, (sec/m )

Stack Release A' s Accumulative Radionuclide Release (WCi) ,

from Stack, Adjusted for Radiodecay (X/Q) y Relative Effluent Concentration, (sec/m )

Vent Release A'y Accumulative Radionuclide Release (pCi) from Vent, Adjusted for Radiodecay (X/Q)g Relative Effluent Concentration, (sec/m )

Ground Level Release A[g Accumulative Radionuclide Release (UCi) from Ground, Adjusted for Radiodecay R Downwind Range (m) u s' "v, u g

Average Wind Speed,' Stack, Vent, or (m/sec)

Ground Level Release l Sg Gamma Whole Body Dose Constant, (mrad /yr per UCi/sec)

Stack Release

{ Gamma Whole Body Dose Constant, Vent Release (mrad /yr per pCi/sec)

{ Gamma Whole Body Dose Constant, Ground Level Release (mrad /yr per ECi/sec) l

{ Beta Skin Dose Constant (mrem /yr per ECi/m ) ,

! Q is Release Rate, Stack Release (ECi/sec)

Qgy Release Rate, Vent Release (mci /sec) l l 2.1-19

' REVISION 1 SEPTEMBER 1979 SYMBOL NAME UNIT Q ig Release Rate, Ground Level Release (pCi/sec)

R Individual Air Intake Rate (m /yr) a Release Rate, Stack Release, (pCi/sec)

Qsi Adjusted for'Radiodecay Release Rate, Vent Release, (pCi/sec)

O'y Adjusted for Radiodecay Release Rate, Ground Release, (p Ci/sec)

O'ig Adjusted for Radiodecay DFA Inhalation Dose Factor (mrem /pCi) ija DFI ija Ingestion Dose Factor (mrem /pCi)

U Produce Consumption Rate (kg/yr) a (liters /yr)

( Milk Consumption Rate U Leafy Vegetable Consumption Rate (kg/yr)

Ua Meat Consumption Rate (kg/yr) fp Produce Fraction fy Leafy Vegetable Fraction Cy Vegetation Concentration (pCi/kg)

Cf Produce Concentration (pCi/kg)

Milk Concentration (pCi/ liter) l

~

Leafy Vegetable Concentration (pCi/kg)

Cf Cf Meat Concentration (pCi/kg) dg Deposition Rate *

(pCi/m .hr) t Deposition Time (day) l r

(D/Q)s Relative Deposition Factor, Stack (m- )

Release l 7

(D/Q)y Relative Deposition Factor, Vent (m )

Release (D/Q)g Relative Deposition Factor, Ground (m-2)

Level Release l r Crop Retention Fraction AEi Effective Decay Constant (hr-1) 2.1-20 .

_ . ~

REVISION 1 SEPTEMBER 1979 SYMBOL NAME UNIT

~

Ag Radiological Decay Constant (hr. 1)

Ay Weathering Decay Constant (hr-1) t e

Effective Crop Exposure Time (hr) t h

Harvest to Consumption Time (hr) ,

Yy Productivity Yield (kg/m )

F Milk Fraction (days / liter)

M Cf Feed Concentration (pCi/kg) fg ' Seasonal Growing Factor f

g Pasture Grass Fraction Cf Pasture Grass Concentration (pCi/kg)

Cs Stored Feed Concentration (pCi/kg)*

Wg Feed Consumption (kg/ day) tg Milk Transport Time (hr)

Fp Meat Fraction (day /kg) t s

Slaughter to Consumption Time (hr)

K Seasonal Adjustment Factor i

b 1

2.1-21 1

. I c

REVISION 1 SEPTD1BER 1979 2.1.4 Constants Used In Section 2.1 NUMERICAL VALUE NAME UNIT

-8 3.17 x 10 Conversion Constant (years /second)

O.7 Gamma Radiation Shielding I and Occupancy Factor .

1.0 Beta Radiation Shielding and Occupancy Factor 1.11 Conversion Constant (mrem / mrad) 6 10 Conversion Constant (pCi/PCi) 24 Conversion Constant (hr/ day) 365 Conversion Constant (day /yr) 3600 Conversion Constant (sec/hr) .

e d

\

l 1

2.1-22 9

i

REVISION 1 SEiTEMBER 1979 2.2 RADIOACTIVITY IN LIQUID RELEASES 2.2.1 10 CFR 50 Appendix I Design Objectives The dose contributions from mea'sured quantitles of radioactive materials identified in liquid effluents released to unre-stricted areas from each reactor shall be calculated using the following expression:

1-D 3 = (1.1 x 10

-3 x 8760)

UM EA g DFI ija **E I~ i

} +

3' (2.22)

EI f UM '['A

^~d g DFI ija i eXP (- A i t) pf D Cumulative dose (mrem) 3 The cumulative dose or dose commitment to the total body or an organ j due to an adult consuming water and fish, where:

D s 1.5 mrem to the whole body 3

in a calendar quarter, (2.23)

$ 5.0 mrem to any organ in a calendar l quarter, (2.24)

< 3.0 mrem to the whole body in any four l consecutive quarters, and (2.25) 110.0 mrem to any organ in any four l consecutive quarters. (2.26) 2.2-1

REVISION 1 SEPTEMBER 1979 f

U", U Usage Factor (liters /hr, l kg/hr)

Average consumption rate of water or fish.

See Table 7.2-1.

1/M", 1/M Additional Dilution Factor Additional dilution factor prior to withdrawal of potable water or fish. See Table 7.2-1.

~

F" Average Flow Rate (ft /sec)

Average flow of receiving body of water. See Table 7.2-1.

f

( F Near-Field Flow Rate (ft /sec)

Near-field flow of receiving body of water.

1 See Table 7.2-1.

A i

Total Radionuclide Release (mci)

Total release of radionuclide i during period of release.

DFI ija Ingestion Dose Factor (mrem /pCi)

The ingestion dose commitment factor for each l

identified gamma and beta emitter i, organ j, and age group a. See Table 7.1-1.

lg Decay Constant (hr )

Radiological decay constant of ith radionuclide.

(Table 7.1-11).

f t", t Elapsed Time (hr)

Average elapsed time between release and consump-tion of potable water or fish. See Table 7.2-1.

2.2-2

• i

. ', ' \

~

REVISION 1 )

SEPTEMBER 1979 i

By Bioaccumulation Factor (liters /kg) l Bioaccumulation factor. See Table 7.1-12. l 1.1 x 10-3 = factor to convert from (pCi/yr)/f t3 /sec) to pCi/ liters 8760 = number of hours per year 2.2.2 10 CFR 20 Maximum Permissible Concentrations in the Unrestricted Area The concentration of nonnoble gas radioactive material released from the site to unrestricted areas (C g ) shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 (MPCg ).

The concentrations of dissolved or entrained noble gases shall be limited to the concentrations saecified in Table 7.1-10. The sum of the fractional limits (E Cg + MPCi )

I must n,ot exceed 1.0 for each release. - _

The concentration of each radionuclide in the unrestricted area is calculated as follows:

D x F (2.27)

Ci=Ci p d,p r I

andthecombinationofCf,F, and F must meet the condition that:

t 100 x'E g = 100 x

• I ( * }

i i Fd+F r 1 MPCi Cg Concentration in the Unrestricted Area (pCi/ml)

The concentration of radionuclide i at the restricted / unrestricted area boundary.

Cf Concentration in the Discharge Tank (mci /ml)

The concentration of radionuclide i in the (radwaste discharge or other similar) tank.

2.2-3

\

, l REVISION 1 SEPTEMBER 1979 F Flow Rate, Radwaste Discharge (f t /sec)

The flow rate of radwaste from the discharge tank to the initial dilution stream.

F Flow Rate, Initial Dilution Stream (ft /sec) l The flow rate of the initial dilution stream which carries the radionuclides to the un-restricted area boundary (e.g., the blow-down from cooling tower or lake or the circulating cooling water flow) . '

MPC g Maximum Permissible Concentration (p Ci/ml)

The maximum permissible concentration of radionuclide i in water in the unrestricted area (from 10 CFR 20, Appendix B, Table II, Column 2 or Table 7.1-10 of the ODCM Appendix). ,

2.2.3 10 CFR 20 Maximum Permissible Concentrations at the Nearest Surface Water Supply The quantity of radionuclides, excluding tritium and dissolved or entrained noble gases, in outdoor tanks without overflow pipes connected to other storage tanks shall be limited to assure that in the case of an overflow, the annual average concentration of radioactivity in the potable water of the nearest surface water supply is less than the 10 CFR 20, Appendix B, Table II, Column 2 limits. This restriction is applicable only to Zion, for all other stations have outdoor tanks with provisions to handle overflow.

The annual average concentration of each radionuclide in the potable water of the nearest surface water supply is calculated as follows:

D F

C{ = Cf F y t M[ exp (- A g x t") x g{g (2.29)

\*+F )

2.2-4

. ', a

~

REVISION 1 SEPTEMBER 1979 C" Concentration in Water Supply (p Ci/ml)

The annual average concentration of radionuclide i in the surface water supply due to tank. overflow.

i D (pci/ml)

C Concentration in Tank The concentration of radionuclide i in the outdoor tank of interest. ,

F Maximum Flow Rate from Tank (ft /sec)

The maximum rate of overflow from the outdoor tank of interest. (Usually equal to the maximum tank feed rate). See Table 7.2-1.

l F" Flow Rate, Receiving Body of Water (ft /sec)

The minimum flow rate (from the most recent 10 year record) of the receiving body of water during overflow conditions.

See Table 7.2-1.

1/M" Additional Dilution Factor Additional dilution factor of overflowed water prior to use as potable water.

See Table 7.2-1. .

t" Elapsed Time (hr)

The total time between overflow release and consumption of water, equal to the transit time,- discharge point to intake, plus the process time at the water l treatment plant. See Table 7.2-1.

l l

l l

2.2-5 l .

REVISION 1 SEPTEMBER 1979 tg Release Time (hr)

The total period of the overflow conditions, assumed to be no greater than one work shift of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Hence the maximum quantity of radionuclide 1 (Af, curie) in each tank of interest, excluding tritium and the dissolved or entrained noble gases, which satisfies the limiting condition:

• C{

MPC -< 1 (2.30) f 1 is:

{ Af A y !F"+F) t t

(2.31)

MPC eXP ( xt)o <4 t

/

i i g p M"

• D A Tank Radioactivity (Ci)

The quantity of radionuclide i in the tank of interest.

V Tank Volume (gal)

The volume of each tank without overflow pipes connected to other storage tanks.

See Table 7.2-1.

Equation 2.31 may also be written in terms of the con-centration of radionuclido i in the tank of interest.

t Ci exp (- A i x t") <

[pw+Ft) o 1100

- (2.32) i MPC g (p t

/ M 2.2-6

', o REVISION 1 SEPTEMBER 1979 Derivation of Ecuation 2.31 Since, by Equation 2.30, C{ ~

< 1

~

(2.32a) i MPC g whereC"isgivenbyEquation2.29andCfinEquation2.29 .

is given by:

A x 10 Ci/Ci (4Ci/ml) (2.33 C D=

I t V x 3785 ml/ gal then:

C{ ,

Cf [ pt M" exp (- Ag t") t /8760 g < 1 (2.34) i MPC f MPC f p w 4p t

, F t ) [ M" \ 8 x 10 6

Af exp (- Ag t") <1 w t t 8760 TT5 g MPC g (g o 4 p/ k y / (2.35)

Mg

, l_ ! F Af exp (- Ag t") -

<1 (2.36) 4' p w 4p t yt i MPC f Equation 2.36 on rearrangement gives:

A i exp (- Atg g) w

<4 F" o + Fth [V t i (2.37) i k F /kM"/

2.2-7

E 1

.~ ', l

. 1 j

REVISION 1 SEPTEMBER 1979 2.2.4 Symbols Used In Section 2.2 NAME UNIT SYMBOL Cumulative Dose (mrem)

Dj (liters /hr, kg/hr)

U",U Usage Factor 1/M",l/ME,l/M" Additional Dilution Factor F" Average Flow Rate (ft /sec)

F Near-Field Flow Rate . (ft /sec)

(pCi)

Ag Total Radionuclide Release ,

Ingestion Dose Factor (mrem /pCi)

DFI ija A Decay Constant (hr-1) t",t ,t" Elapsed Time (hr) g Bioaccumulation Factor (liters /kg)

B f

Cy Concenu ation at Unre- (UCi/ml) stricted Area Madmum Permiss M e (pCi/mU MPC g Concentration Concentration in Tank (pCi/ml)

C F Flow Rate, Radwaste (ft /sec)

Discharge F Flow Rate, Initial (ft /sec)

Dilution Stream Concentration in Water (pCi/ml) j C"

Supply .

F Maximum Tank Over Flow Rate (ft /sec)

F Minimum Flow Rate, Receiving (ft /sec)

Body of Water Tank Radioactivity (Ci)

Af  !

D Tank Volume (gal)

V '

tg Release Time (hr)

I 2.2-8 t

REVISION 1 SEPTEMBER 1979 2.2.5 ConstantsIfsedInSection2.2 , l NUMERICAL VALUE NAME UNIT

-3 1.1 x 10 Converrion Factor (pCi/ liter)/ .(pCi/yr)/(f t /sec).

8760 Conversion Factor (hrs /yr)

• w e

G G

2.2-9

REVISION 1

, SEPTEMBER 1979 2.3 ENVIPONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE In accordance with the requirements of 40 CFR 190 (Reference 6.12), the annual dose commitment to any member of the public in the general environment (i.e., the unrestricted area) from all uranium fuel cycle sources, except those specifically excluded by the regulation, is limited to 25 millirems to the whole body, 25 millirems to any organ but the thyroid, and 75 millirems to the thyroid.

2.3.1 Sources of Radiation and Radioactivity 2.3.1.1 Uranium Fuel Cycle - Definition The uranium fuel cycle is defined in 40 CFR 190 (Reference 6.12) to include:

a. operations of milling of uranium ore,

b. chemical conversion of uranium,

c. isotopic enrichment of uranium,

d. fabrication of uranium fuel,

e. generation of electricity by a nuclear power plant using uranium fuel, and

f. reprocessing of spent uranium fuel.

Specifically excluded are:

1

a. mining operations,

b. operations at waste disposal sites,

c. transportation of radioactive material, and

d. the use of recovered nonuranium special nuclear or by-product materials from the cycle.

2.3.1.2 Radiological Impact of Uranium Fuel Cycle Operations Environmental Radiation Protection Standards, 40 CFR 190, require that the radiation dose resulting from'all operations of the 1

2.3-1

REVISION 1 SEPTEMBER 1979 uranium fuel cycle (except the specific exclusions noted) be considered in determining compliance. Therefore each of the operations will be discussed and the r:diological impact in the Commonwealth Edison Company (CECO) service area will be considered.

2.3.1.2.1 Milling Reference 6.13 (Page 4), Reference 6.14 (Section 2.4), and Reference 6.15 (Page IV F-29) indicate that the maximum indi-vidual doses due to milling will be less than 10 CFR 20 limits.

Therefore, the dose contribution to any person living in this service area due to milling operations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits.

2.3.1.2.2 Conversion Reference 6.14 (Section 3.4) and Reference 6.15 (Page IV F-40 and Table IV F-10) indicate that the maximum individual doses due to UF 6 conversion will be less than 10 CFR 20 limits.

Therefore, the dose contribution to any person living in this service area due to UF 6 conversion operations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits. -

2.3.1.2.3 -Enrichment Reference 6.14 (Section 4.4) and Reference 6.15 (Page IV F-51) indicate that the maximum individual doses due to uranium enricF ent will be less than 10 CFR 20 limits. Therefore, the dose contribution to any person living in this service area due to urcnium enrichment operations, all more than 100  !

kilometers distant, is expected to be negligible compared l to 40 CFR 190 limits.

2.3-2 .

l .

REVISION 1 SEPTEMBER 1979 2.s.l.2.4 Fabrication Reference 6.14 (Section 5.4) and Reference 6.15 (Page IV F-63) )

indicate that the maximum individual doses due to fuel element fabrication will be less than 10 CFR 20 limits. Therefore, the dose contribution to any person living in this service  ;

area due to fuel fabrication operations, all more than 100 kilometers distant, is expected to be negligible compared l

to 40 CFR 190 limits.

2.3.1.2.5 Generation of Electricity The generation of electricity using a nuclear power plant results in radioactivity released in gaseous and liquid effluents. .

The radiological impact of these requires assessment (using the methodology of Sections 2.1 and 2.2 of thic report) and I

comparison with 40 CFR 190 limits.

Also, boiling water reactors (BWR's) contain radioactive nitro-gen-16 (N-16) in their steamlines and turbines in sufficient enough quantities to result in measurable offsite doses.

The magnitude of this so-called skyshine dose must also be considered in determining 40 CFR 190 compliance. Offsite doses due to other contained sources in,the nuclear power l Plant are negligible compared to those due to effluents and N-16 skyshine.

i .

Measurements of the radiation environment due to N-16 have been made at the Dresden Station (Reference 6.19). An empirical fit to the measured data is given in Equation 2.38:

D (R, P) = SF OF (2.28 x 10-5) P exp (-0.007 R) (2.38) 2.3-3

REVISION 1 SEPTEMBER 1979 D(R,P) Dose Due to N-16 Skyshine (mrem)

The gamma dose due to BWR N-16 skyshine.

j SF Shielding Factor The shielding factor for protection against gamma radiation.

SF = 0.7 for a home.

OF Occupancy Factor The at-home occupancy factor:

For fisherman 0.95 -

For all others 1.0

-5 2.28 x 10 Constant (mrem /MWe-hr)

A constant to fit the equation to measured data.

P Electric Power Generated (MNe-hr)

The total electric energy generated in the time period of intertsc.

0.007 Constant (m-1) l A constant to fit the ecuation to I measured data.

R Distance (m)

Distance from the turbine to the dose point l of interest.

2.3-4 l

REVISION 1 SEPTEMBER 1979 This equation will be used at all CECO BWR's up to a distance of 1100 meters. Beyond that distance the fit (and data) are considered unreliable and, further, the dose at this range is at most 0.1 mrem /yr for CECO Stations.

In certain situations more than one nuclear power plant site may contribute to a radiological dose to be considered in making 40 CFR 190 dose assessment. At present (July 1979), the nuclear power stations in CECO's service area are sufficiently distant from one another that the radiological dose, if not negligible .

compared to 40 CFR 190 limits, is due to only one site. Hence, , ,

adding dose components from several stations is not required.

However, within CECO's service area the following future additive combination is considered. At some point within the triangle formed by the La Salle, Dresden, and Braidwood Stations, an additive dose from airborne releases may be postulated. However, the distances are such (La Salle to Dresden, 39 kilometers; Dresden to Braidwood, 18 kilometers; Braidwood to La Salle, 37 kilometers) that at any intermediate point postulated, the station-combined dose is less than that maximum calcr. lated for an individual station.

Therefore, the combined effect of airborne releases will not be considered further.

Such is not the case for future releases of radioactivity into the aquatic environment where, if more than one facility uses the same receiving body of water, the station-combined dose must be considered. Dresden and (the future) La Salle County Stations discharge their liquid waste into the Illinois River and (the future) Braidwood Station discharges into the Kankakee River which flows into the Illinois at Dresden. Quad Cities and (the j future) Carroll County Stations use the Mississippi River and (the future) Byron Station uses the Rock River which flows into l the Mississippi at Moline, Illinois, downstream of Quad Cities. l l

For these two situations the combined impact from upstream liquid waste discharges must be considered at.each downstream location. i l

2.3-5

i

. 1 REVISION 1 SEPTEMBER 1979 The dose contribution of nuclear power plants in other service area's need not be considered in CECc's 40 CFR 190 assessment. j The Duane Arnold Station is about 135 kilometers from Quad Cities; the Clinton Station is about 125 kilometers from Braidwood and La Salle; and the Bailly Station is about 100 kilometers from Dresden.

2.3.1.2.6 Reprocessing Reference 6.15 (Table IV E-12) indicates that maximum individual doses due to fuel reprocessing will be less than 10 CFR 20 limits.

Therefore, the dose contribution to any person living in this service area due to fuel reprocessing cperations, all more than 100 kilometers distant, is expected to be negligible compared to 40 CFR 190 limits.

2.3.1.2.7 Waste Disposal Sites The radiation dose associated with the burial of low level radio-active radwaste need not be considered in determining compliance with 40 CFR 190 as this source is specifically excluded by the law. Inasmuch as the licensed burial facility at Sheffield, Illinois, is near CECO's service area, at least a comment regarding it as a potential source is warranted.

The radiological impact of burial sites is discussed briefly in Chapter IV, Section F, Part 3.1.2.1 of Reference 6.15 (Page IV H-28 ff). No significant movement of radioactivity into the general environment is expected, though some tritium has been found in groundwater near the Sheffield facility. However, no significant dose contribution to a person living in the vicinity l

1 of CECO's nuclear power plants is expected. (The Quad Cities Station is about 60 kilometers from Sheffield; Byron and La Salle are each about 90 kilometers from Sheffield.)

2.3-6

~_

s ,

. REVISION 1 SEPTEMBER 1979 2.3.1.2.8 Transportation The radiation dose associated with the transport of low level radioactive waste and spent fuel is also excluded from consid-eration by the requirements of 40 CFR 190. This subject has been reviewed in References 6.16 and 6.17, and summarized again in Reference 6.15 (Chapter IV, Section G). The expected dose asso-

-3 clated with transportation is 3.4 x 10 mrem / person / reactor /yr.

. 2.3.1.2.9 Storace of Spent Fuel in Offsite Facilities The radiation doses associated with releases of radioactivity by independent spent fuel storage facilities (ISFSF) should also be considered in determining compliance with 40 CFR 190. One .

ISFSF is being operated within CECO's service area; that is General Electric Company's Morris Operations Plant at Morris, Illinois, adjacent to CECO's Dresden Station. Minute quantities of Kr'85 and other radioactive particulates are released in air-borne effluents. A dose assessment was performed using typical release data provided by the General Electric Company and the ODCM environmental dose assessment models for Dresden. (The effluent is released through a 300-foot vent stack; hence the similarity between the two facilities. However, no adjustments were made for differences in site boundary ranges or ranges to dairies. These differences are not expected to affect the con-clusion from the dose assessment.)

The estimated annual airborne releases from the GE Morris Oper-4 ation plant are 6 x 10 p Ci of tritium, < 55 x 10 6 Ci of Kr-85, 3 pCi of Co-60, and 1 pCi of Cs-137. The maximum whole body dose from these radionuclides is 4 x 10-4 mrem /yr. So long as this

plant remains a spent fuel storage facility and does not reprocess l the fuel the dose contribution to any person living in its vicinity will be negligible and not considered further in the Dresden 40 CFR 190 analysis. i l

l 2.3-7 .

O 8

REVISION 1 SEPTEMBER 1979 2.3.1.2.10 Long-Term Storage of High Level Radioactive Wastes The dose associated with the long-term storage of high-level radioactive wastes is excluded from consideration as far as 40 CFR 190 is concerned. The radiological impact is discussed in Reference 6.15 (Chapter IV, Section H, Part 3.2) and should be negligible in the CECO service area.

2.3.1.3 Summary The magnitude of radiological dose due to various operations of the uranium fuel cycle and its impact in the Commonwealth l

Edison Company service area has been reviewed with respect to the requirements of 40 CFR 190. The only. dose components requiring consideration are those due to: ,

a. radioactivity in nuclear power plant liquid and gaseous effluents, and

b. the direct radiation due N-16 in BWR steam piping, j turbines, and associated equipment.

2.3.2 Numerical Models 2.3.2.1 Airborne Releases and Direct Radiation l

2.3.2.1.1 Whole Body Dose The maximum whole body (WB) dose from airborne releases and direct radiation will be determined by adding, for each sector, the dose contributions, if applicable, from all (1) noble gases; (2) airborne radioiodines, "particulates", and other non-noble gas radionuclides; (3) direct radiation-from BWR turbine N-16 skyshine as computed at the nearest actual res-idence in each sector (Table 7.2-4) ; and at Dresden only, the contributions from (4) noble gases, and (5) airborne "particulates" l from the Morris operations plant if spent fuel is reprocessed.

2.3-8

REVISION 1 SEPTEMBER 1979 At Zion, sectors whose site boundary is over Lake Michigan will not be considered in the 40 CFR 190 analysis.

At Dresden and Quad Cities Equations 2.39 and 2.40, respectively,

. will be used to compute the direct radiation dose in sectors whose restricted area boundary is over water. This dose, which accounts for possible fishing activities in the vicinity, will then be added to the nearest residence dose compated with Equation 2.38 using an at-hv.T.: occupancy fcctor of 0.95 rather than the usual 1.0. An occupancy factor of 0.05 is used for fishermen (0.025 at each of two locations at Quad Cities) and a boat shielding factor of 1.0.

At Dresden:

3

-5 D(R,P) =

( 1. 0 ) '. 0 . 0 5 ) 2.28 x 10 P exp (-0.007 x R )

f i=1 (2.39)

Ry = 488 m R,R 2 3

= 610 m Pg Electric power generated (MWe-hr) by each unit in the year At Quad Cities:

D(R,P)\ = (1.0) (0.025) 2.28 x 10 -5 P exp (-0.007 R y ) +

exp (-0.007 R )

2 (2.40)

Ry = 100 m R2 = 400 m P Electric power generated (MWe-hr) by the station l

l l

2.3-9 l

1 9

REVISION 1 SEPTEMBER 1979 Table 2.3-1 shows the methodology for determining the maximum whole body dose from airborne releases and direct radiation.

2.3.2.1.2 Thyroid Dose The maximum thyroid dose from airborne releases and direct radiation will be determined by adding, for each sector, the dose contributions from the various sources in a manner similar to that for the maximum whole body dose, as described above and in Table 2.3-1. ,

2.3.2.1.3 Any Other Organ Dose In this class the dose from airborne releases and direct radiation to the GI-LLI, bone, liver, kidney, lung, and skin will be determined separately in each sector, and the ma::imum value chosen to represent "any other organ" (AOO) for purposes of determining compliance. The maximum AOO dose will be determined in a manner similar to that for the maximum whole body dose, as described in Subsection 2.3.2.1.1 and in Table 2.3-1.

2.3.2.2 Radioactivity in Liquid Releases The maximum whole body, thyroid, and AOO doses from radioactivity in individual station liquid releases will be determined using, for the fish pathway, the near-field estimate of dilution at the station; and using, for the drinking water pathway, the average flow of the receiving body of water at the nearest l

downctream community water system, if the water system is near the station. Otherwise, the drinking water pathway will not be considered. For situations involving combined-station releases, for the fish pathway, for releases from all upstream CECO facilities, the tissue doses will be determined using

, the average flow of the receiving body of water at the station.

I Table 2.3-1 shows the methodology for determining :hese doses.

2.3-10 e os oes

- REVISION 1 SEPTD1BER 1979 2.3.3 Symbols Used in Section 2.3 SYMBOL NAME UNIT D(R,P) Dose due to N-16 (mrem) skyshine P, P g Electric power generated (MWe-hr) by station or unit i 2 .

R Distance (meters)

SF Shielding Factor OF Occupancy Factor I

e e

2.3 11 O 4

.g

REVISION 1 SEPTEMBER 1979 2.3.4 Constants Used in Section 2.3 NUMERICAL VALUE NAME UN '.'T

-5 2.28 x 10 Fitted Constant (mrem /MWe-hr) 0.007 Fitted Constant (m~1) 0.7 Shielding Factor at home 1.0 Shielding Factor on a Boat 0.05 Occupancy Factor -

While Fishing 0.95 Occupancy Factor at Home for Fishermen 1.0 Occupancy Factor at Home for Everyone but Fishermen

\

l I

2.3-12

• pe" M

TABLE 2.3-1 .

NUMERICAL MODELS FOR COMPUTING RADIATION DOSE a

FROM URANIUM FUEL CYCLE OPERATIONS FUEL CYCLE CLASSIFICATION - Wi! OLE ANY OTHER ORGAN FOOT-OPERATION OF RADIATION BODY TIIYROID GI-LLI BONE LIVER KIDNEY LUNG SKIN NOTES REACTORS

1. Noble Gases Equation Equation Equation 2.5 Equation -

2.5 2.5 2.7

2. Airborne Equation Equation Equation 2.11 Equation b Iodine and 2.11 2.11 2.11 WB

[8 Particulates Component

3. Liquid Waste Equation Equation Equation 2.22 - - Equation c W 2.22 2.22 2.22 WB Component

4. Direct Equation Equation Equation 2.38 Equation d Radiation 2.38 2.38 2.38 FUEL STORAGE FACILITY

5. Noble Gases . N/k N/A Not Applicable N/A e

6. Airborne N/A N/A Not Applicable N/A e Particulates yg Nb

- a. The maximum sector doses for the whole body, thyroid, and any other organ, summed over all g$

classifications of radiation, will be added to similar tissue doses received from radioactivity 50

=

~

in liquid rel' eases, or combined-station releases, if applicable. The maximum dose of each tissue ~

class will be compared to the limits established in 40 CFR 190.10(a) . }

TABLE 2.3-1 (Cont'd) -

b. The dose to all organs will be determined first with Equation 2.11 then adjusted through multiplication by a factor 0.5/fg $ 1 where fg is given in Table 7.1-2.

c. Only the fish pathway portion of Equation 2.22 will be used unless the community water system is near the station. For combined aquatic pathway doses from more than one station the dose from each upstream CECO station will be determined with Equation 2.22, using M"/F" instead of M /F at the individual station.

d. Except for special considerations of fishermen at Dresden and Qutd Cities direct radiation from BWR turbine N-16 will be computed at the nearest actual resident u in each sector and not'at the site boundary. A shielding and occupancy factor of y 0.7 will be used.

e. So long as this plant remains a spent fuel storage facility and does not reprocess the fuel, its contribution to the total dose will not be considered further.

. 35 En ne

= r.

3

. 'l

'J

4 4

4 9

h

/

N ab7 O

3.0 ATMOSPHERIC TRANSPORT, DIFFUSION, AND DOSE MODELS 3.1 METEOROLOGICAL DATA FOR MODELS

. 3.1.1 Current Record Onsite meteorological data are used as input to all of the airborne dose calculations performed by a contractor. The data are obtained by means of an instrumented meteorological tower that measures wind speed and wind direction at several levels. The stability of the atmosphere is determined by means of the temperature lapse rate (differential temperature) between two levels on the tower. The contractor's analyras are used to supplement dose analyses performed with nistorical meteorological records.

l l

l For elevated releases a joint frequency table (stability wind rose) of wind speed, wind direction, and stability is developed using the upper level wind data and the average lapse rate measured on the tower.

The mixed-mode model for vent stack releases requires two stability wind roses: one to represent the elevated part of the release and one to represent the ground level portion of the rel' ease. .

These are developed jointly by considering the wind data hour l by hour. The criteria for deciding how to proportion each l hour's data between a vent release and ground level release l depend on the ratio of the exit speed to the wind speed.

When the criteria (Suosection 3.2.2.2) indicate part of the release should be considered as ground level, the ld-meter l wind data are used.

For ground level releases the stability wind rose is developed using the lower level wind data and lapse rate.

~

3.1-1

REVISION 1 SEPTEMBER 1979 The wind direction, wind speed, and atmospheric stability classification schemes are described in Tables 7.1-5 and 7.1-8.

Because the dispersion equations are very sensitive to low wind speeds, the hourly record may require editing to reflect the measuring limitations of the wind sensors at low speeds.

If the reported wind speed is less than the anemometer's threshold (Table 7.1-6), it is assigned a value equal to one-half of threshold speed. If the reported speed is less than the vane's threshold (calm), Table 7.1-6, a direction is assigned in proportion to the observed wind direction distribution

~

of the lowest noncalm speed class.

Diffusion estimates for monthly, calendar quarter, or annual releases are determined by combining hourly stabil-ity and wind data in the form of stability wind rose tables.

Wind speed, direction, and stability classifications are used to group the data and calculate the joint occurrences of the groups.

3.1.2 Historical Record Nuclear station operators will use the dispersion factors of Section 7.2 to demonstrate compliance with the Technical Spe-cifications. Depending on the station, there may be three classes (elevated, mixed mode, and ground level) of effluent release, each with four types of dispersion factors:

(1) X/0, (2) D/0, (3) Si , Vg , or Gg, and (4) 5{, Vg , or Gg ,

where i = 1 to 15 which are wind direction dependent. The first two types of dispersion factors are used with the internal dose models; (X/Q) and the last two types are used with the external dose models.

3.1.2.1 Internal Dose The recipient of the internal dose can either be an adult l

l

! 3.1-2 .

L

a or an infant. If the recipient is an adult, the internal dose can consist of contributions from inhalation (X/Q), leafy vegetables or produce (D/0), milk or meat (D/0). If the recipient is an infant, the total dose consists of contributions from inhalation (X/Q) and milk (D/Q). The dispersion factors for inhalation and leafy vegetable doses are calculated for the 16 wind directions. The dispersion factors for the milk cows and meat animals are only calculated for the direction (s) where these animals are located in the unrestricted area and at a distance no greater than 5 miles. .

Historical dispersion factors used in the internal dose models are found in Appendix 7.2. There is a set of these tables for each station. Appendix 7.2 contains the dispersion fac-tors for the 3 possible classes of release and the 16 wind directions for which X/O (inhalation) and D/Q (leafy vegetables or produce) are calculated. The radius specifies the location at which the dose is calculated. Only maximum X/Q and D/O values are used.

Also in Appendix 7.2 are the dispersion factors used to calculate the doses resulting from milk and meat consumption. Entries occur only for those directions where the nearby milk cows and meat animals are located.

The internal dose models are:

1. adult inhalation;

2. adult consuming leafy vegetables;

3. adult consuming produce;

4. adult consuming meat;

5. adult drinhing milk;

6. any combination of 1, 2, 3, 4, and 5; I 7. infant inhalation; 1

l 8. infant drinking milk; and

9. sum of 7 and 8. i l

3.1-3

3.1.2.2 External Dose f l

The wind direction dispersion factors used in the whole body and gamma air external dose models are found in Appendix 7.2.

For each station, the 15 tables correspond to the 15 radio-nuclides used to determine total external dose, which is the sum of the dose contributions from each radionuclide. The whole body (5 g

, V1 , or E g) and gamma air (S g , V1 , or Gy )

dose factors are computed for each of the 16 wind directions and each release class.

The dose factors for beta skin dose (Lg ) and beta air dose - ,

(Lg ) , two other types of external dose, are constants which do not vary with wind direction. However, they are combined in the dose models with X/Q factors, which are wind direction dependent.

3.1-4 ee ~ ~ ee

- REVISION 1 SEPTEMBER 1979 3.2 ATMOSPHERIC TRANSPORT AND DIFFUSION MODELS 3.2.1 Numerical Model

~

The model used is classed as a " constant mean wind direction model" by the NRC. Equation 3.1 shows how the concentration to emission ratio (x/Q) at any downwind range and direction is calculated.

[he)

- 1/2 3] (3.1)

~

x ( R ,0) f (u,0, stab) (uS ) exP

, 2.032 }{ { z u stab This model assumes that the effluent is uniformally distributed within each downwind sector and that the release rate is constant ,

during the time period modeled.

X/Q Relative effluent concentration (sec/m )

R Range to receptor (m)

O Direction to receptor (degree or sector)

(

f( ) Joint frequency table of the parameters within parentheses Stab Stability class u Wind speed (m/sec)

S z Corrected vertical dispersion coefficient (m) h, Effective stack height (m) l l

3.2-1 ,

3.2.2 source conficuration considerations The location of the source with respect to the buildings affects how the airborne effluent will disperse. The following describes the criteria used to model airborne releases from nuclear power plants and describes how the model evaluates each case.

3.2.2.1 Elevated Releases Release locations (chimneys, etc.) that are high enough to be out of the range of the effects caused by neighboring solid structures are classified as elevated releases. The concentra-tions at any range and direction can be calculated by Equation 3.1 when an appropriate value for the effective stack height (he ) is used to represent the height of the plume centerline above the ground.

The effective stack height is calculated by the following equation:

h, = h s +h r

-h t (3.2) h Physical stack height (m) s h Plume rise (m) r h

t Terraincorrectionbactor (m)

This equation states that the effective stack height (h,) is equal to the physical stack height (hs ) plus the plume rise due to buoyancy and momentumr (h ) less a correction for the variation in terrain (h tI

• 3.2.2.1.1 Plume Rise (hr )

?

The rise of an effluent plume is dependent on the stability 3.2-2

REVISION 1 SEPTEMBER 1979 .

~

of the atmosphere, the wind speed, the heat content of the plume, and the exit velocity of the plume. The procedure chosen has been selected to provide a conservative (low) es-timate of the plume rise in order to maximize the resulting calculated doses.

Under neutral and unstable atmospheric conditions the momentum-dominated plume rise equations are used. Equation 3.3 shows the basic relationship between h and other parameters.

r (hrlI = 1.44d (W o /u)2/3 (R/d)1/3 -C (3.3) _ , ,

Wg Exit velocity (m/sec) d Stack diameter (m) -

C Downwash correction factor (m)

Equation 3.3 would allow the plume to continue rising forever which is contrary to observation. In order to limit the rise, Equation 3.4 is evaluated and the lesser o,f Equations _3.3 an 3.4 is used in the calculations.

(br )2 = 3 (Wo /u)d (3.4)

Therefore, h can be represented by the following formula for r

neutral and unstable conditions.

I l

h r

= Min (br )1, (h )r 2 (3. 5)

Under stable atmospheric conditions, additional calculations l

are made as follows: .

(br )3 = 4 (F/S) (3.6)

~1/6 (3.7)

(hr )4 = 1.5 (F/u)1/ S l

3.2-3

F Momentum flux parameter (m /sec )

S Stability parameter (sec~)

where:

F=W (d/2)2, and S is given in the following table. (3.8)

~

Table of Values for Stability Parameter (S) (sec )

Stability Class S E 8.7 x 10~4

-3 F 1.75 x 10 G 2.45 x 10-3 i

The smaller value computed from Equations 3.6 and 3.7 is compared to the value obtained from Equation 3.5 and the smallest value is used to represent h under stable conditions. In r

other words, h

r

= Min (hrl, I (hr2, I (hr3, I (hr4I (3.9) 3.2.2.1.2 Terrain correction (h t)

The average difference in elevation H is computed for the rs point to be evaluated by subtracting the height of the terrain (Hs ) at the release point from the heigh,t of the terrain at tha receptor point (H ). The correction factor h is computed r

by quations 3.10 and 3.11.

H rs =H r -H (3.10) s

'H rs ; H rs >0 t (3.11) 0 ;H rs 50 l

3.2-4 l .

H Terrain height difference (m) rs H Terrain height at receptor point (m) r H

s Terrain height at source (m)

, 3.2.2.1.3 Downwash Correction (C)

If the ratio of the exit velocity to the wind speed is less than 1.5, the effluent can get caught in the downwash of the stack and the plume rise would be inhibited. This reduction is accounted for by the term (C) in Equation 3.3 and this term is computed by Equation 3.12.

C = 3 (1.5 - Wo/u) d (3.12)

{

l 3.2.2.2 Vent Stack Releases -

The constant mean wind direction model has been modified into a " mixed-mode" model. In a mixed-mode model the height of the release is proportioned between an elevated release (stack height equal to the vent height plus momentum plur rise),

and a ground level release (stack height equal to zero).

Separate wind and stability data are used for each release height and the X/0 ratios are calculated. Subsection 3.1.1 describes how the meteorological data are prepared for this calculation. This model is r'ecommended by Regulatory Guide l 1.111.

The fraction of the time that the plume is considered to be a ground level release (G ) is determined, from the ratio t

of the exit velocity of the vent (Wo ) to the wind speed (u),

by the use of the following relationships:

1.00  ; Wo /u $ 1.0 G

t

=

.58-1.58 (Wo /u)  ; 1. 0 < Wo/u <l.5 l0.3-0.06 (g37u)  ; 1. 5 < Wo /u < 5. 0 (3*13) 0.00  ; Wo/u25.0 3.2-5

G t

Fraction of time a vent release is considered a ground level release.

Therefore, the release can be considered as a ground level release 100G percent of the time and as an elevated release 100(1-G ) percent of the time.

t 3.2.2.3 Ground Level Releases

- To calculate the downwind concentrations resulting from ground level releases, Equation 3.1 is used with the effective stack height set to zero (h,=0). If the release is from a 4

structure of maximum height (D ) a correction is made to the z

dispersion parameter to account for the increased mixing caused -

i by the building's wake effect. Equation 3.14 shows how this is accounted for in the model.

o*  ; no wake effect S = J- -

(3.14) b cz +D /(2n)  ; wake effect o

z Vertical dispersion coefficient (m)-

D z

Maximum height of neighboring structure (m)

The dispersion parameter ( z) is given in Table 7.1-7.

When the wake effect is used the factor S z will be restricted by the condition:

S z$ U z (3.15) l 3.2-6 ,

l l

REVISION 1 SEPTEMBER 1979 3.2.3 Removal Mechanism Considerations 3.2.3.1 _

Radioactive Decay

- The loss of activity with time, due to radioactive decay is accounted for by adjusting the source term. This adjustment takes the following form:

Q[ = 0; exp (- Af t) =Q g exp (- AgR/3600u) (3.16)

Q[ Release rate of radionuclide i corrected for radio-active decay (pCi/sec)

Of Release rate of radionuclide i (pCi/sec) ,

A g Radiological decay constant (hr~)

t Transport time: point of release to receptor (hr) 3600 Converts hours to seconds (sec/hr) 3.2.3.2 Plume Depletion and Deposition As the plume travels downwind, the radioiodines and particulate material are deposited on the ground and thus removed from the plume., At all ranges (R) the model accounts for this depletion by multiplying the (x/0) ratios,by a fraction that is a function of release height and stability.

(X/Q) =

(X/Q)g P Ib , stab) d e (3.17) l P

d Plume depletion coefficient The function P d recommended by the NRC (Regulatory Guide 1.111 i

l Figures 2-5) is given in Appendix 7.1, Figures 7.1-1 to 7.1-4.

The plume depletion factors for the height closest to the actual release height are used.

3.2-7

REVISION 1 SEPTEMBER 1979 3.2.3.3 Relative Deposition Factor (D/Q)

The value of D/0 (m-2) is determined from one of the following equations:

fDr (stab, R, h s)

D/Q = (3.18)

D/Q = f ]

stab f (0, stab) D r

(stab, R, h) s (3.19)

~

D Relative Deposition Rate (m )

r , ,

The relative deposition rate is the deposition rate per unit downwind distance

~1 (pci s m ~1) divided by the source strength (uCi s~1)

For time periods A t < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Equation 3.18 is used. For time ,

period At> 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, when the meteorological data are.in the form of a stability wind rose, Equation 3.19 is used.

The values of D r

from Regulatory Guide 1.111, Figures 6-9, are reproduced in Appendix 7.1 as Figures 7.1-5 to 7.1-8.

Choose the value of rD closest to the release height (hs)*

For mixed mode releases, D *O (3.19a) r t (Dr }g + I1~O t (Drs l .

3.2-8 W

REVISION 1 SEPTEMBER 1979 3.2.4 Symbols Used In Section 3.2 SYMBOL NAME UNIT X/Q Relative Effluent Concentration (sec/m )

R Range to Receptor (m)

O Direction to Receptor (degrees or sectors) f( ) Joint Frequency Parameter Stab Stability Class u Wind Speed (m/sec)

Sg Corrected Vertical Dispersion coefficient hg Effective Stack Height (m) h Physical Stack Height (m) s

• h r

Plume Rise (m) h Terrain Correction Factor (m) t Wg Exit Velocity (m/sec) d Stack Diameter (m)

C Downwash Correction Factor (m)

F Momentum Flux Parameter (m /sec )

S Stability Parameter (sec~)

H rs Terrain Height Difference (m)

H Terrain Height at Receptor Point (m) r ~

H Terrain Height at Source (m) s o Vertical Dispersion Coefficient (m) g D Maximum Height of Neighboring Structure (m) z Gt Fraction of Time the Vent Release is Considered a Ground Level Release

~

D/Q Relative Deposition Factor (m )

D r

Relative Deposition Rate (m" )

Q'g Release Rate of Radionuclide 1 (pCi/sec)

Corrected for Radioactive Decay Og Release Rate of Radionuclide i (pCi/sec)

Ag Radiological Decay Constant (hr~1)

P Plume Depletion Coefficient l d t Plume Transport Time (hr) 3.2-9 ,

i

\

REVISION 1 SEPTEMBER 1979 1

4 3.2.5 Constants Used In Section 3.2 l

NUMERICAL VALUE NAME UNIT 3600 Conversion Constant (see hr~1) 16/2n Sector Width ~1 (Radians ~ )

i l .

1 i

i I

i 1

e 3.2-10 i

. ~ ~,-

REVISION 1 l SEPTEMBER 1979 3.3 MODELS FOR CALCULATING DOSE FROM NOBLE GASES 3.3.1 Gamma Radiation l

3.3.1.1 Gamma Air Dose - Finite Cloud Model The gamma air dose (Di ) is calculated from either of the following formulae:

• 4 DY(R,6) = t R x 2n/16 m u (3.20) 1 stab f(u,0, stab)Qj p ai yi (Il+ i 2) i DT (R, 6) =

60 x 10 R 2n/16

{l u

" { stab i

{ f(u,0, stab) x A{vi a vi III+ i 2) .

1 I* I DY(R,0) Gamma Air Dose (mrad) m Index For Release Period -

3 260 Conversion Co.nstant ( mrad-radians-m -disintegra-tion / sec-MeV-Ci )

10-6 Conversion Constant (Ci/ pci) 86400 Conversion Constant (sec/ day) 2n/16 Sector Width (radians) t" Length of Release Scy r )

I j i Index for Summation of ::cc1jdes l

l l 3.3-1 l

REVISION 1 SEPTEMBER 1979 Release Rate Corrected for' Radioactive Decay Q[

in Transport (uCi/sec)

A'g Release Corrected for Radioactive Decay' (p Ci) in Transport 9,g Air Energy Absorption Coefficient (m-)

(Table 7.1-9)

E7g Average Energy per Disintegration (MeV/ disintegration)

(Table 7.1-9)

I 1+ i 2) Dimensionless Numerical Integration Constant l defined in Section 7.5 of Reference 6.7.

(For K g values, see Table 7.1-9) ,

l The basic form of the above equation was taken from Meteorology and Atomic Energy (Eq. 7.63) and is equi-valent to Equation 6 in Regulatory Guide 1.109. The summation over the index m, represents the summing of the doses from all sources at the station (i . e . , elevated releases and vent releases).

Equation 3.20 was then used to compute the gamma air dose factors S g (for stack releases), Vg (for vent releases), and G y (for g'round level releases) mrad /yr per uCi/sec. Site-specific values of Si, Vf and G g using historical meteorological data are given in Appendix 7.2.

3 3.1.2 Whole Body Dose Factors The whole body dose factors, { (for stack releases),

{ (for vent releases) and { (for-ground level releases) in mrad /yr per pCi/sec, computed from DT(R,0 ) + (1.11 SFY 3.2~ x 10-8 ), ,

evaluated one nuclide at a time, are given in Appendix 7.2.

3.3-2

REVISION 1 SEPTEMBER 1979 ,

The whole body dose DT(R,0), calculated for preselected ranges in each downwind sector, is given by the equation that follows:

T (R,0) = 1.11 SF D Y ){) D{ (R,0) exp(-5 (ut li) '

i D (R,0) Whole Body Dose (mrem) 1.11 Conversion Constant (mrem / mrad)

SF Y Shielding and Occupancy Factor for Gamma Radiation p Tissue Energy Absorption Coefficient (cm /g) t (Table 7.1-9)

Df(R,0) Gamma Air Dose, Nuclide i (mrad)

The gamma air dose due to nuclide i only as evaluated from Equation 3.20. .

For this calculation, the shielding factor SF T is set to 0.7 and dose is computed at a depth of 5 cm in the tissue.

The factor 1.11 is the ratio of tissue to air energy absorption coefficients.

3.3 2 Beta Radiation 3.3.2.1 Beta Particle Air and Skin Dose Factors

( The beta particle air dose factor L g, (mr'ad/yr per pCi/m 3) and skin dose factor, L , mrem /yr per pCi/m3 are given 1

in Reference 6.5 and included in Table 7.1-13.

3,3-3

.' l REVISION 1 SEPTEMBER 1979 l 1

3.3.3 .

Symbols Used In Section 3.3 SYMBOL NAME UNIT D{ (R,0) Gamma Air Dose (mrad)

R Range to Receptor (m) 0 Direction to Reception (degrees or sector)

D (R,e) Whole Body Dose (mrem) m Release Period Index t" Length of Release (days) u Wind Speed (m/sec) i Nuclide Index Stab Stability Class f( ) Joint Frequency Parameter Release Rate Corrected for (pCi/sec)

Q{

Radioactive Decay in .

Transport

~

u,g Air Energy Absorption (m )

Coefficient Kg Average Energy per (MeV/ disintegration)

Disintegration I 1+Ki 2) Dimensionless Numerical Integration Constant Y

SF Shieldina and Occupancy Factor for Gamma Radiation A' Release Corrected for (pCi)

Radioactive Decay in Transport e~iR/3600u Correction for Radioactive Decay in Transport l

3.3-4

REVISIOM 1 SEPTEMBER 1979 .

l

- 1 3.3.4 Constants Used In Section 3.3 NUMERICAL VALUE NAME UNIT 3

260 Conversion Constant ([ mrad-radians-m _

disintegration] / [sec-MeV-Ci] )

10-6 Conversion Constant (Ci/pCi) 86400 Conversion Constant (sec/ day)

~

2n/16 Sector Width (radians)

~ .

O 1

3.3-5

REVISION 1 SEPTEMBER 1979 3.4 .MODELS FOR CALCULATING DOSE FROM RADIOIODINES, "PARTICULATES", AND OTHER RADIONUCLIDES The specific model for computing the dose to the various organs of an adult or infant is given in Equation 2.11. For the purpose of demonstrating compliance with the Technical Speci-fications, the dose to an infant who inhales air and drinks milk containing radioactive material shall be limiting. However, the dose model may be used to compute the dose to an adult who inhales radioactivity and ingests meat, milk, produce, or leafy. vegetables containing radioactivity. The choice of the infant as the critical person is based on previous calcula-tions of dose reported in semi-annual or annual reports.

Annually, the dose to an adult will be computed to confirm the choice of an infant as " critical person". ,

In the inhalation model, using historical meteorological information, radioactive decay but not plume depletion was considered. Plume depletion was not considered at this time because depletion for the D atmospheric class, a class repre-sentative of average meteorology, reduces the inhalation dose by, at most, 10% within the 3 kilometer range considered.

I

\

3.4-1 l l

l l

9 ,

s V .

8

• e r

f 9

D I i

REVISION 1 SEPTEMBER 1979 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1 AQUATIC TRANSPORT Dose via the aquatic pathway is discussed in Section 2.2.

Two dilution factors are considered; F, the flow of the receiving body of water; and 1/M, an additional dilution factor.

4.1.1 River Model For purposes of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total mixing of the discharge in the river flow (F") occurs prior to consumption. No additional dilution is assumed to occur; thus i 1/M" equals 1.0. The river flow is taken as the long-term (generally 10 years) average.

For the fish consumption pathway a near-field dilution flow F f is used; 1/M f = 1.0.

4.1.2 Lake Michican Model For purposes of calculating dose from liquid effluents dis-charged to Lake Michigan, it is assumed that the concentra-tion of radioactivity is diluted initially in the condenser cooling water of flow (F c) and then by an additional factor 1/M" of 60 prior to consumption as potable water. The dilution factor of 60 is the product of the initial entrainment dilution (f actor of 10) , the plume dilution (factor of 3 over approximately 1 mile), and the current direction frequency (annual average factor of 2).

For the fish ingestion pathway only, it is assumed the radio-activity is diluted fe?.ly in a hypothetical river of flow f

) F; 1/M = 1.0 '

4.1-1 e-

REVISION 1 SEPTEMBER 1979 .

4.1.3 Symbols Used In Section 4.1 SYMBOL NAME UNIT F Flow of the Receiving Body of Water 1/M Additional Dilution Factor F" Average Flow Rate (ft /sec) -

(Drinking Water Pathway) ~. ,

F f

Near-Field Flow Rate (ft /sec)

(Fish Ingestion Pathway) c Average Flow of the (gal / min)

F Condenser Cooling Water During the Period of Discharge 1/M" Additional Dilution Factor (Drinking Water Pathway) .

E 1/M Additional Dilution Factor (Fish Ingestion Pathway) i l .

4.1-2

.+',.

REVISION 1 SEPTEMBER 1979 4.2 AQUATIC DOSE MODEL The general model used to calculate the dose from radioactive i material released in liquid waste is given in Subsection 2.2.1. The maximum consumption rate of fish by an adult, i Uf = 2.4 x 10-3 kg/hr (21 kg/yr), given in Reference 6.5  !

(usNRC Regulatory Guide 1.109), is assumed for all nuclear stations except those sited along the Illinois River. For these stations, because of this river's very low productivity of desirable fish, a consumption rate one-tenth the maximum is assumed. , ,

I l

1 4.2-1

l

.- . -l i . .. .

' ~ REVISION l'-

i

' SEPTEMBER 1979 4

I l 4.2.1 Symbols Used in Section 4.2 4

i SYMBOL NAME ' UNIT l j.

I f U Usage Factor (liters /hr, kg/hr) 4 4

4 I

i =

l.

i i

a h

1 4

t i .

1 1

i i.

1 2 .

l'j

• i i

f I

l l

{

I i

i i

2 l

o .

4.2 .

' - - v

• rv ryn&-=<= -m,w,.p.., 4,, ,_,,_ - , ,

REVISION 1 SEPTEMBER 1979 -

4.3 AQUATIC TRANSPORT DURING TANK OVERFLOW CONDITIONS j In Subsection 2.2.3, the limiting quantity of radionuclide i in tanks without overflow pipes connected to other storage tanks was determined to be a function of two dilution factors  ;

characteristic of the receiving body of water: F", the minimum l flow of the receiving body of water during overflow conditions, and 1/M", an additional dilution factor.

4.3.1 River Model

~ .

For purposes of calculating the limiting quantity of tank radioactivity spilled into a river of flow FW and with a dam between the release point and the intake, it is assumed that total mixing of the discharge in the river occurs in the min. mum river flow of the most recent past 10 years.

, No additional dilution is assumed to occur; thus 1/M"g equals 1.0.

4.3.2 Lake Michigan Model

• For purposes of calculating the limiting quantity of tank radioactivity spilled into Lake Michigan, it is assumed that F", the initial dilution water, is zero and that the additional dilution factor 1/M"g is 1000. The 1000 factor represents an estimate of the dilution experienced by a shoreline-spilled water mass as it moves north along the shore and east into the lake, having to cross the northward moving lake current to reach the nearest water intake which is 6500 feet northeast (1.1 miles north and 3000 feet out in the lake) at a depth of 35 feet.

4.3-1

l REVISION 1 SEPTEMBER 1979 4.3.3 Symbols Used in Section 4.3 SYMBOL NAME UNIT.

F" Minimum Flow Rate, (ft /sec)

Receiving body of l

Water 1/M" Additional Dilution

~

Factor i

1 i

e 4.3-2 r .,-%

?

I .

t I

i-l l

t l

l e

I C) v- .

i 8

(

' REVISION 1 SEPTEMBER 1979 l 5.0

SUMMARY

5.1 AIRBORNE EFFLUENTS 1

l l- 5.1.1 10 CFR 50 Appendix I Desion Objectives I

The 10 CFR 50 Appendix I technical specification design objectives for the nuclear stations are summarized in Table 5.1-1. To demonstrate compliance with the Appendix I objectives l the dose for each time period of the quarter will be calculated using the dose equations noted in Table 5.1-1. The current quarter dose is the summation of the dose contribution from every effluent release during the quarter. The station will calculate the doses on a monthly basis. Each time the ,

station evaluates the dose equations, the new contribution is added to the current total for the quarter, and the new total is compared with the objective. Next, the new total for the quarter is combined with the totals for the previous three ,

quarters to determine the annual dose.

The results of each calculational run will be summarized in a format similar to that shown in Table 5.1-1. The maximum dose is printed with the associated wind direction. The values calculated for each wind direction and range must be stored for calculation of the maximum period, quarter, and annual dose. For the organ dose, the computer will

~

calculate doses to seven organs for up to 73 radionuclides, l and select the maximum period, quarter, and annual organ doses.

For each dose type and maximum value, the compliance status is calculated where the status (%) = 100 x maximum ' dose

+ dose objective.

5.1-1 .

• l.

TABLE 5.1-1 i (Name) Unit (number)

MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES (PERIOD OF RELEASE FROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))

CURRENT CURRENT THIRD SECOND FIRST TYPE PERIOD QUARTER

• QUARTER QUARTER QUARTER ANNUAL Gamma Air (mrad) Eq.2.1 dose (dir.) - NOTE: This format should appear in all Eq.2.3 0 entries.

Bata Air (mrad)

Whole Body (mrem) Eq.2.5 Skin Omrem) Eq.2.7

' Organ (mrem) Eq.2.ll ,

Last period of release from (da te) to (da te) , calculated (date) .

COMPLIANCE STATUS 10 CFR 50 APP. I 10 CFR 50 APP. I TYPE QUARTERLY OBJECTIVE  % OF APP. I YEARLY OBJECTIVE  % OF APP. I Grmma Air (mrad) 5 10 Beta Air (mrad) 10 20 Whole Body (mrem) 2.5 ,

5 yh 8H Skin Onrem) 7.5 15 gg Organ (mrem) 7.5 ** 15 ***

w H

A The equation number of the model used to compute the dose for the period $

is listed here for information only.

• Cummulative dose fer the quarter including the current period.

• • The critical organ is (Name).

• • • The critical organ is (Name).

F

5.1.2 10 CFR 20 Release Rate Limits The compliance status with respect to the 10 CFR 20 limits l

is determined in the following manner and reported in the format of Table 5.1-2 for periods of unusually high release rate Q.

= (dose ~ rate from Ea. 2. 0 x 100 (%) whole body (5.1)

C.S.WB 500 mrem /yr

= (d se rate from Ea. 2.10) x 100 skin (5.2)

(%)

C.S.3 3000 mrem /yr C.S. = (dose rate from Ec. 2.18) x 100 organ (5.3)

(%)

1500 mrem /yr The value of C.S. must not exceed 100%. If it does, the station's release rate is too high and corrective action to reduce the release rate must he taken immediately.

e

\

5.1-3 .

_ _ _ _. w.

TABLE 5.1-2 (Name) Station MAXIMUM INSTANTANEOUS RELEASE RATES (PERIOD OF RELEASE FROM (DATE/ TIME) TO (DATE/ TIME).

DATE OF CALCULATION (DATE))

DOSE RATE, 10 CFR 20 LIMIT, COMPLIANCE ORGAN mrem / year mrem / year STATUS

• Whole Body 500 Eq. 5.1 Skin 3000 Eq. 5.2 0

(Name) Organ 1500 Eq. 5.3

\

A The organ with the maximum dose should be named.

• See text for definition. If C.S. -> 100, add this or similar footnote to the table: l

" Corrective action must be taken immediately to reduce-the release rate". Also, perhaps at the bottom of this table or on a separate sheet, the radionuclides and their release rate should be listed.

5.1-4

+-

~

REVISION 1

. SEPTEMBER 1979 5.2 LIQUID RELEASES 5.2.1 10 CFR 50 Appendix I Design Obiectives The total quarterly and annual whole body or organ doses due to radioactivity discharged in liquid wastes are computed in a manner similar to that for airborne effluents. The results, based on doses computed with Equation 2.22, are summarized in the manner of Table 5.2-1.

5.2.2 10 CFR 20 Maximum Permissible Concentrations 5.2.2.1 Unrestricted Area The concentration of non-noble gas radioactive material released from the site to unrestricted areas (C g ) shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 (MPC g). The concentrations of dissolved or entrained noble gases shall be limited to the concentrations specified in Table 7.1-10. The sum of the fractional limits (Cf + MPC g) must not exceed 1.0 for each release.

Hence: -

C 1

100 x I ( * }

1 MPC i s

i 5.2.2.2 Nearest Surface Water Supply At Zion, the quantity of radionuclides, excluding tritium and dissolved or entrained noble gases, in outdoor tanks without over-flow pipes connected to other storage tanks shall be limited to assure that in the case of an overflow, the annual average concentration of radioactivity in the potable water of the nearest surface water supply is less than the 10 CFR 20, Appendix B, Table II, Column 2 limits.

5.2-1 -

1 REVISION 1 SEPTD1BER 1979 Hence:

A {F"+F \ t

! i MPC f **E I~ A ixt)$4 pt M and Ci [F"+F \ 1100 (5.6) exp (- A x t")o $ ' I i MPC g i pt M'g

) .

• • % g l

e O

5.2-2 a.

TABLE 5.2-1 (Name) Unit (number)

MAXIMUM DOSES RESULTING FROM LIQUID EFFLUENTS (PERIOD OF RELEASE PROM (DATE) TO (DATE). DATE OF CALCULATION (DATE))

CU RRENT CURRENT TIIIRD SECOND FIRST TYPE PERIOD QUARTER

• QUARTER QUARTER QUARTER ANNUAL Whole Body (mrem) dose - NOTE: This format should appear in all 12 entries Organ (mrem) dose Critical Organ name During Period e Last period of release from (da te) to (date), calculated (date) .

COMPLIANCE STATUS 10 CFR 50 10 CFR 50, APP. I TYPE  % of APP. I YEARLY OBJECTIVE  % OF APP. I QUARTERLY OBJECTIVE Whole Body (mrem) 1.5 3 Organ (mrem) 5 ** 10 8H

$0 mo MZ

• Cumulative dose in quarter to date N

• • The critical. organ is (name) $g

• • • The critical organ is (name) j

l l

REVISION 1 i SEPTEMBER 1979 )

5.3 URANIUM FUEL CYCLE l

The compliance status, with respect to the 40 CFR 190 limits, is determined in the following manner and reported in the format of Table 5.3-1 at the end of each calendar year.

In accordance with the numerical models described in Subsection 2.3.2, the maximum whole body, thyroid, and any other organ (AOO) doses to a member cf the public in the general environment, i.e., the unrestricted area, will be determined and compared to the 40 CFR 190 limits to determine the compliance status.

9 l

5.3-1

REVISION 1 SEPTEMBER 1979 TABLE 5.3-1

.(Name) STATION (S)

COMPLIANCE STATUS: URANIUM FUEL CYCLE OPERATIONS: 40 CFR 190 -

Period of Release Date of This Calculation DOSE RATE 40 CFR 190 LIMIT COMPLIANCE ORGAN mrem / year (mrem / year) STATUS (% )

• Whole Body 25 Thyroid 75 Any Other Organ 25 (Name) l

• If > 10 0 % , this or a similar footnote must be added to the table.

" Corrective action might be needed to bring the facility into compliance with the regulations. If a variance for unusual l operations is required, petition the NRC in accordance with -

the requirements of 40 CFR 190.11."

l 5.3-2

REVISION 1 SEPTEMBER 1979

~

5.4 PRIMARY DRINKING WATER STANDARDS I The U.S. Environmental Protection Agency has promulgated regula-tions for the radioactivity content of community water systems (Reference 6.18). One part (40 CFR 141.16 (a) ) of these regula-tions involves man-made radioactivity, such as those in liquid waste from a reactor. It reads: "The average annual concen-tration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the whole body or any internal organ .

greater than 4 millirem per year." In 40 CFR 141.16 (b) the , , , ,

method for calculating this dose is described. The EPA dose calculation ma; hod differs somewhat from that described in ODCM Subsection 2.2.1. Furthermore, the 40 CFR 141 regulation applies to the operator of the community water system and not to CECO.

If a special report defining corrective actions to reduce ,

the releases of radioactive materials in liquid' effluents is required by the technical specifications,.it must include an analysis of the radiological impact on the down-stream drinking water source also. This analysis may include the data of Table 5.4-1.

If confirmatory measurements of radioactivity attributable to plant operations found at the nearest community water system are available, the following concentrations, taken singularly

~

or in combination (i.e. , the sum of the ratios of concentration to limit are > 1), shall define the 40 CFR 141 regulatory

' limit: stroritium-90, 8 pCi/1; tritium, 20,000 pCi/1; gross beta activity, 50 pCi/1; and for any other nuclide, the con-centration given in NBS Handbook 69 as amended in August 1963.

l f 5.4-1 i

. \

~

TABLE 5.4-1 (Name) Station, PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM *

(PERIOD OP RELEASE FROM (DATE) TO (Dr.TE) . DATE OP CALCULATION (DATE)

CURRENT CURRENT TIIIRD SECOND TYP2 PERIOD FIRST QUARTER ** QUARTER QUARTER QUARTEP ANNUAL Whole Body (arem) Dose NOTE: This format should appear in all 12 entries Internal Organ Dose (mrem) * *

• Critical Organ Name Name Name Name Name Name During Period ***

Last period of release from (date) to (date), carculated (date).

. COMPLIANCE STATUS b

TYPE 40 CFR 141 ANNUAL LIMIT 4 OF LIMIT Whole Body (;qrem) 4 Internal Organ (arem) *** 4 Critical Organ During Year *** Name This calculation of dose is based on techniques described in the Commonwealth Edison m ye Offsite Dose Calculation Manual. These techniques differ from those described in 40 CFR 141. A projected dose of 2 mrem using Ceco's techniques is approximately hh 9"

4 mrem using EPA methods. Any planned action should be. based on the requirements O of the regulation and not this ieport. p"

• • Cumulative dose in quarter to date.

.w

• • • Either thyroid, GI-LLI, bone, liver, kidney, or lung.

D

9

• gG S

e 0

- d u .

6 O

i I

t O

l,

i o.

6.0 REFERENCES

l 6.1 G. A. Briggs, " Plume Rise," U.S. Atomic Energy Com-mission, 1969.

6.2 J. F. Fletcher and W. L. Dotson, " HERMES. A Digital Computer Code for Estimating Regional Radiological Ef fects from Nuclear Power Industry," USAEC Report HEDL - TME 168, Hanford Engineering Development Laboratory, 1971. -

6.3 " Radiological Health Handbook," U.S. Department of Health, Education, and Welfare, Public Health Service, Rockville, Maryland, 1970.

6.4 Regulatory Guide 1.111, " Methods for Estimating Atmo-spheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," .

U.S. Nuclear Regulatory Commission, Washington, D.C.,

Revision 1, July 1977.

6.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. Nuclear Regulatory Commission, Washington, D.C., Revision 1, October 1977.

l l 6.6 J. F. Sagendorf, "A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station," U.S. Department of Commerce, Report No. NOAA TM ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, 1974.

6.7 D. H. Slade, " Meteorology and Atomic Energy 1968,"

U.S. Atomic Energy Commission,1968.

l 6.0-1 l

1 -

l l

. e. <

REVISION 1 SEPTEMBER 1979 6.8 D. C. Kocher, Ed., " Nuclear decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities," ORNL/NUREG/TM-102, August 1977.

~

6.9 R. L. Heath, " Gamma-Ray Spectrum Cat'alog," Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.

6.10 NUREG-0172, " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake," Battelle Pacific

- Northwest Laboratories, 1977.

6.11 D. B. Turner, " Workbook of Atmospheric Dispersion Estimates,"

U.S. Environmental Protection Agency, Office of Air Programs, Publication No. AP-26, revised, 1970.

6.12 U.S. Environmental Protection Agency, 40 CFR 190, Federal Register 42, 9, 2858, January 13, 1977.

6.13 NUREG-0511 "Draf t Generic Environmental Impact Statement on Uranium Milling," April 1979.

6.14 EPA-520/9-73-003-B, " Environmental Analysis of the Uranium Fuel Cycle," Part I, Fuel Supply, October 1973.

6.15 NUREG-0002, " Final Generic Environmental Statement on the Use of Recycled Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors," August 1976.

6.16 WASH-1248, " Environmental Survey of the Uranium Fuel Cycle," April 1974.

6.17 WASH-1238, " Environmental Survey of Transportation of Radioactive Materials To and From Nuclear Power Plants," December 1972.

i 6.0-2

i REVISION 1 SEPTEMBER'1979 .

6.18 U.S. Environmental Protection Agency, 40 CFR 141, Federal Register 4l,133, 28402, July 9,1976.

6.19 W. R. VanPelt, Environmental Radiation Survey of the  :

Dresden Nuclear Power Station," Environmental Analysis,  !

Inc., December 1971.

l

• % , s 1

I t

e t

I O

I e

6 I

f l

6.0-3

N' O

50 e

e e

A 1 V 1

\

l 1

e

REVISION 1 SEPTEMBER 1979 l

7.0 APPENDICES APPENDIX - 7.1 DATA COMMON TO ALL NUCLEAR STATIONS APPENDIX - 7.2 DATA SPECIFIC TO EACH NUCLEAR STATION t

l l

1 q

e 1-i l

l l

I J

O 4

J

' 7.0-1 l

i

6 4 0

4#

e t

=

D O

4 I

i l

l l

e

,-m___.. _ _ ._

REVISION 1 SEPTDiBER 1979 LIST OF TABLES FOR SECTION 7.1 NUMBER TITLE PAGE 7.1-1 Dose Commitment Factors 7.1-1 7.1-E-7 Inhalation Dose Factors for Adults 7.1-2 7.1-E-10 Inhalation Dose Factors for Infants 7.1-5 7.1-E-ll Ingestion Dose Factors for Adults 7.1-8 7.1-E-14 Ingestion Dose Factors for Infants 7.1-11 7.1-2 Miscellaneous Dose Assessment Factors -

Adult 7.1-14 7.1-3 Miscellaneous Dose Assessment Factors -

Infant '

7.1-16 7.1-4 Stable Element Transfer Data 7.1-17 7.1-5 Atmospheric Stability. Classes 7.1-18 7.1-6 Wind Sensor Threshold 7.1-19 7.1-7 Vertical Dispersion Parameters 7.1-20 7.1-8 Wind Speed and Wind Direction Classes 7.1-22 7.1-9 Airborne Isotope Data 7.1-23 7.1-10 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released From the Site to Unrestricted .

Areas in Liquid Waste 7.1-24 7.1-11 Listing of Radiological Decay Constants (A. 7.1-25 7.1-12 Biba)ccumulation Factors to be Used in the Absence of Site-Specific Data 7.1-27 7.1-13 Beta Dose Factors for Noble Gases 7.1-28 l

L

REVISION 1 SEPTEMBER 1979 LIST OF FIGURES FOR SECTION 7.1 NUMBER TITLE 7.1-1 Plume Depletion Effect for Ground-Level Releases 7.1-2 Plume Depletion Effect for 30 m Releases

- 7.1-3 Plume Depletion Effect for 60 m Releases

7.1-4 Plume Depl'etion Effect for 100 m Releases 7.1-5 Relative Deposition for Ground-Level Releases 7.1-6 Relative Deposition for 30 m Releases 7.1-7 Relative Deposition for 60 m Releases

7.1-8 Relative Deposition for 100 m Releases k

/

e k

ii .

l

REVISION 1 SEPTEMBER 1979 TABLE 7.1-1 DOSE COMMITMENT FACTORS PATHWAY INFANT ADULT Inhalation See Table 7.1-E-10 See Table 7.1-E-7 Ingestion See Table 7.1-E-14 See Table 7.1-E-ll E Tables from Regulatory Guide 1.109, Revision 1, October 1977. Each table contains seven organ dose factors for 73 radionuclides. E tables follow. For radionuclides not found in these tables dose factors will be derived.from ICRP 2 (1959) or NUREG-0172 (Reference 6.10).

l e

7.1-1

REVISION 1 SEPTD1BER 1979 TABLE 7.1-E-7 INHALATION DOSE FACTORS FOR ADULTS (mrem per pCi Inhaled)

HUCLICE dONE L!vER T.ROCY THYROID KIDNEY LUNO GI-LLI ~

H J NO DATA 1.5SE-07 1.5SF-07 1.596 ".7 1.58E-07 1.58E-07 1.58E-77 C 16 2.27E-C6 4.76E-07 *.26E-07 4.26E-07 4.26E-07 4.26E-C7 4.26E-07 NA 24 1.28E-06 1.28E-06 1.2FE-06 1.295-06 1.28E-06 1.2PE-06 1.285-06 . ,

P 32 1.65E-04 9.64E-06 6.2ot-36 ND DATA NC DATA NO CATA 1.0AE-05 LR 51 NO DATA NO DATA 1. 2 3 E -0 8 7.44E.09 2.a5E-09 1.80E-06 4.1>E-07 CN S4 NO DATA 4.9)C-06 1.AFE-01 NO DATA 1.23L-06 1.75E-04 9.67E-06 Mit 56 NU DATA 1.55f-10 2.21E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 Fi 55 1.0TE-C6 2.12C-06 6.9 tE-0 7 NO DtTA NO DATA 9.01E-06 T.54E-07 FE 59 1.475-06 1.47E-Oo 1.3/E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NC DATA 1.9PF-07 2.59E-17 NO CATA NC DATA 1 16E-04 1.13E-05 CO 60 NC UATA 1.**E-C6 1.0)E-36 NO DATA NC DATA 7.46E-04 1.56E-05 11 65 5.400-05 3.'3E-06 1.01E-06 4C DATA NO DATA 2.23E-05 1.67E-06 11 65 1.92E-10 2.o2C-11 1 15c.11 NO CATA NC DATA , 7.00E-07 1.54E-06 CU 64 NO DATA 1.936-10 7.6)E-11 NO DATA ).78E-10 e.48E-07 6.12E-06 ZN 65 4.05E-te 1.21F-05 3.82C-06 NO DATA R.62t-06 1 08E-04 6.68E-06 ZN 69 4.23t-12 6.14;-12 5.65E-13 NO Dafs 5.27E-12 1.15E-07 2 04E-C9 4R 63 NO DATA 40 CATA 3.01E-08 NO DATA NO CATA NO DATA 2.90E-OR HR 64 NO DATA NO CATA 5.91E-OR NO DATA NC DATA NO DATA 2.05E-13 0R 8) NO DATA Nn DATA 1.60E-09 NO DATA NC DATA NO DATA LT E-24 12 80 NO DATA 1.610-05 7.3/E-06 NO DATA NO DATA NO DATA 2.08E-06 90 88 NO DATA 4.P4E-n8 2.41E-18 NO DAT4 NC OATA NO CATA 4.18E-19 R8 89 NU DATA 3.2CC-08 2.126-08 NO DATA NC DATA NO DATA 1.16F-21 SA 89 - 3.8CE-05 NO CATA 1.09E-06 NO DATA NC DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 No CATA 7.62E-04 NO CATA NC DATA 1.20E-93 9.02E-05 SR 91 7.74E-04 NO CATA 3.llE-10 NO OATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-in NO CATA l.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO CATA 7.01E-09 NO DATA NU OATA 2.12E-05 6.32E-05 Y 91M 3 26E-11 NO DATA 1. 2 7 E-12 NO DATA NC CATA 2.40E-07 1.66E-10 Y 91 5.78E-05 N0 0%fA 1.55E-06 NO DATA NC DATA 2.13E-04 4.81E-05 Y 92 1.29E-01 N0 c1TA 3.77E-11 NO DATA NC DATA 1.96E-06 9.19E-06 7.1-2 9

e

. . _ . . k RINTISION 1 SEPTEMBER 1979 TABLE 7.1-E-7 (Cont'd)

NUELIJL 80NE LivFA T.nunY THYROID KIONFY LUNG GI-LLI y 93 1.126-05 NO UAIA 3.2 6 E-10 NO DATA NC CATA 6.06E-06 5.27E-05 ZR 95 1.34[-05 4.3CE-06 2.91E.06 NO DATA 6.77E-06 2.21E-04 1.38E-05 I ZR 97 1.21E-CA 2.45E-09 1.13E-09 NO CATA 3.71E-09 9.84E-06 6.54E-05 t NB 95 1.76E-06 9.17L-07 5.26E-07 No DATA 9.6 7E-0 7 6.3tE-05 1.30E-05 MO 99 WO CATA 1.51t-08 2. 8 7E-0 9 NO DATA 3.64E-08 1.14E-05 1.10E-05 ft 99M 1.29E-13 3.64E- ? 3 4.65E-12 70 DATA S.52E-12 9.55E-08 5 20E-07 l

IC101 5.22E-15 7.52E-15 T.3eE-14 NO CATA 1.35s-13 4.99E-08 1.36F-21

! .4U103 1.91E-07 NU DATA 6.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 HUICS 3.880-11 NC DAIA 3.89E-11 NO DATA 1.27t-10 1.57E-06 6.02E-06 l .............. ___........ .........................__ ..... ______.________

Rulec 8.b4E-C6 NO DATA 1.0)C-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AGla n F 1.35E-C6 1.252-06 7.4 SE-U 7 NO DATA 2.46E-06 5.79E-04 3.78E-05 5.842-09 1.llE-07 TE:25w 4.27E-07 1.0 E-07 1.55c-06 3.92E-05 d.83E-06 TE:27F 1.58E-C6 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.2CE-04 1.87E-05 TE127 1.75E-1C e . 0 5'i- 11 3.8 7E-11 1.12E-10 6.37E-10 8.14E-07 7.17E-06 IC129* 1.22E-06 5.h4E-07 1.1 o E -0 7 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22L-12 2.99E-12 1. 5's E -12 4. 4 7c- 12 2.34E-11 2.42E-07 1.96F-08 IE131M 8.14E-09 5.455-09 3 63r-09 6.dBF-09 3.86E-08 1.82E-05 6.95E-05 IF131 1.39E-12 7.44E-11 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 T[112 S.25E-08 2.69E-08 2.022-08 2.37E-08 1.82E-07 3.60E-05 6.37F-05 I 130 S.72E-07 1.685-06 6.6CE-07 1.42E-04 2.61E-06 NO CATA 9.61E-07 1 131 3.15E-06 4.47E-Oo 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.43E-07 4.07L-07 1. 4 d E -0 7 1.'3E-05 6.48E-07 NO DATA 5.08F-08 1 133 1 08E-06 1 855-06 5.65E-07 2.69E-04 3.2 3E-06 NO DATA 1.11E-06 I 134 8.05E-06 2.16E-07 7.69E-08 3.735-06 3.445-07 40 CATA 1.26E-10 I 135 3.55E-C7 8. 7 3E-07 3.21E-07 5.00E-05 1.39E-06 NO DATA 6.56E-07 .

C5134 4.66E-C5 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 C5136 4.8BE-C6 1 8 3E-05 1.39E-05 NO CATA 1.07E-05 1.50E-06 1.46E-06 C5137 5.98E-05 7.76E-05 5. 3 's E -0 5 NO DATA 2.78E-05 9.40E-06 1.05F-06 C5115 4.14E-08 7.76E-08 4.03E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 ItA139 1.17E-10 8.52E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 b

7.1-3  ;

1 1

. j

~ .

REVISION 1 SEPTEMBER 1979  ;

TABLE 7 1-E-7 (Cont'd)

NUCL I CE BONE tivCR T.dOCY THYR 010 KIDNEY LON- GI-LLI

~

MA140 4.98t-C6 6.13F-09 1.21E-0F NO Cala 2.09E-09 1.59E-04 2.73F-05

%A141 1.25E-Il 9.61E-15 4.2CE-13 NO CATA 8.75E-15 2.42E-07 1.45E-17 R4142 3.29E-12 3.385-15 2.07E-Il NO DATA 2.96E-15 1.49E-07 1.96E-26 L A140 4.10E-C8 2.175-08 5.750-09 NU OATA NO DATA 1.70E-05 5.73E-05 L A 14 2 8.54E-tt 3. P. 8 E - 1 1 9. 6 '* E - 12 NO DATA NC OATA 7.9tE-07 2.64E-07 CE141 2.4 9E-06 1.693-06 1. 91 L-0 7 NO CAT 4 7.R3E-C7 4.52E-05 1.50E-05 JFl43 2.33E-C8 1 72E-Os 1. 91 L -0 9 Nn Daft 7.60E-d9 9.97E-06 2.83E-05 '

• E144 4.29C-04 1,79E-04 2. 30F-0 5 NO Dait 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.905-09 10 DATA 2.70E-07 3.51E-C5 2.50E-05

, PRt44 1.76E-!? 1.368-12 1. 91 E-13 NO CATA 8.Ali-13 1.27F-07 2.69E-18

' NDl47 6.59E-C7 7.62C-07 4.56E-08 No DATA 4.65E-07 2.765-05 2.16E-05 W 187 1.06E-09 8.d5C-10 3 10E-10 NO CATA NC DATA 3.63E-06 1.94E-05 NP239 2.B7E-06 2.822-09 1.55E-09 NO CATA P.75E-09 4.705-06 1.49E-05 l

l l

i e

\

7.1-4 .

REVISION 1 SEPTDiBER 1979 TABLE 7.1-E-10 INHALATION DOSE FACTORS FOR ItEANT (mrem per pCi Inhaled)

NU; LICE BUNE LIVER T.300Y TetvRo t D KIDNEY LUNC GI-LLI

~

P J NU OATA 4.62E-07 4.62C-07 4.62F-07 4.62E-07 4.6?E-07 4.62F-07 C 14 1.89E-0) 3.79E-06 3.79C-06 3.796-C6 3.79E-06 1.79E-06 3.79E-06 NA 24 F.54E-06 7.542-06 7.5*E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 12 1.45E-03 8.03E-05 5.53E-35 NO DATA NO DATA NO DATA 1.15E-05 Ck 51 NO UATA NO DATA 6.31E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-02 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 NN 56 NO DATA 1.10E-09 1.53E-10 10 UATA 7.46E-10 P **c-06 5.l?E-05 rE 55 1.41E-05 H.39L-06 2.33F-06 NO UATA NO DATA t.21C-C5 7.82E-07 F E 51 9.69E-06 1.622-05 6.776-06 No DATA NO DATA T.'5E-04 1.77E-05 I

l CO 58 40 DATA 9.71E-07 1.30E.36 NO DATA NO DATA 5.55E-04 7.95F-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO CATA NO DATA 3.22E-03 2.28E-05 41 6s 2.42E-04 1.46E-05 8.29t-06 NO DATA NC DATA _ l.49E-04 1.73E-06 NI 6) 1.71E-07 2.01E-10 e.71E-11 NO DATA NO DATA 5.80E-06 3.59E-05 CU 64 NO CATA 1.34d-09 d.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 2N 65 1.18L-05 4.*7F-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 IN 69 3.25E-11 6.91E-11 5.15E-12 NO DATA 2.87E-11 1.05E-06 4.44E-06 RR 83 NO DATA NO DATA 2. 7?E-0 7 NU DATA NC DATA NO DATA LT E-24 HR 84 NO DATA NO DATA 2. 86E-0 7 NU OATA NO DATA NO DATA LT C-24 OR 82 NO DATA NO DATA 1.46E-98 NO DATA NC OATA NO DATA LT E-24 10 86 NO DATA 1.36L-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 10 88 NO DATA 3.98E-07 2.03E-0 7 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-n3 4.57E-05

$R 90 2.92E-02 NU OATA 1. 8 5 F -0 3 NO DATA NO DATA 8.03E-03 9.16E-05 l SR 91 6.63E-08 NO DATA 2 4TE-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA 40 DATA 1.70E.05 1.00E-04 Y 90 2.35E-06 NU OATA 6.30E-38 h0 DATA NO DATA 1.92E-04 7.43E-05 Y 91F 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 l Y 91 4.20E-04 NO CATA 1.12E-05 40 UATA NO DATA 1.75E-03 5.02E-05

( Y 92 1.17E-08 NU DATA 3.2 )E-10 NO DATA NO DATA 1.75E-05 9.04E-05

\ ............................................_...............................

I 7.1-5 .

O e

REVISION'l SEPTEMBER 1979 TABLE 7.1-1-10 (Cont 'd)

NUCLICE BONE LIVER T. BODY THY.10!D KIDNEY LUNG GI-LLI Y 93 1 07E-07 40 . .I A 2.91E-09 NO DATA NC DATA 5.46F-05 1.19E-04 2R 95 d.24E-0) 1.11E-05 1.45E-05 NO DATA 2.22t-05 1.25E-01 1.55E-05 ZR 97 1 07E-07 1.836-08 8.100-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 4 8 ? ?. 1.!?E-05 4.59t-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 40 UATA 1.18c-07 2.31E-08 NO Daft 1 89E-07 9.63E-05 3.48E-05 IC 99p 9.18E-11 2.06F-12 2.6eE-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 TC101 4.65t-14 5.*9E-14 5.80R-13 NO DATA 6.91E-13 4.17E-07 6.03E-07 RU103 1.44E-06 40 DATA 4.8 st.0 7 NO DATA 1.012-06 3.940-C4 1.15E-05 3U105 8.74E-10 NO DATA 2.95E-10 NO DATA 6.42E-10 1.12E-05 3.465-05 Rul06 6.200-05 NU DATA 7.77E-06 NU UATA 7.61E-05 8.26E-03 1.17E-04 AG1104 7.13F-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 IE125 3.40E-06 1.42C-06 4.70E-07

1. lee-06 NO DATA 3.19E-C4 9.22E-06 TE1277 1.19E-05 4.93E-06 1 49E-06 1.48E-06_ 2.69E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6. ele-10 3.41E-10 1.32E-09 3.47E-09 7.39E-06 1.74F-05 TE129e 1.01E-05 4.35E-06' 1.51E-00 1.91E-06 2.27E-05 1.20h-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.3*E-11 4.82E-11 1.2SE-10 2.14E-06 1.98E-05 TE131P 7.62E-0A 1.13E-08 2.51E-08 6.38E-08 1.89E-07 1.4?C-04 8.51E-05 TE131 1.245-11 5.67E-12 3. 5 7 E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69F-07 1. 2 6 E-0 7 1.796-07 7.19E-07 2.43E-04 l.15E-05 1 130 4.54E-06 9.91E.06 3.9AF-06 1.14E-Ol 1.99E-05 NO DATA 1.42E-06 1 131 2.71E-05 3.178.-05 1.40E-05 1.060-r2 3.70E-05 NO DATA 7.56E-07 I 132 1,?1E-06 2. 5 'E-06 8. 99E-0 7 1.21E-04 2.u?E-06 NO DATA 1.36E-06 1 133 9.4*E-06 1.57E-05 4.00E-06 2.54E-03 1.60E-05 NO DAT4 1.54E-06 1 13* 6.58t-07 1.34E-06 4. 75 E,-0 7 4.185-05 1.49E-06 NO DATA 9.21E-07 I 135 2 760-06 5.*l5-06 1. 9 ' E -0 6 4.97E-04 6.05E-06 NO DATA 1.31E-06 ,

C5134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.16E-04 5.69E-05 9.53E-07 C5136 3.45E-05 1.o16-05 3. 79E-0 5 NO DATA 4.01E-05 8.40E-n6 1.02E-06 C5137 3.92E-04 4.478-04 3.2';F-05 NC*OATA 1.23E-04 5.09E-05 9.530-07 C5138 1.61E-07 5.48E-07 2. A* E-0 7 NC CATA 2.93E-07 4.67E-08 6.26F-07 UAll9 1.06E-09 7.01E-13 3.0 7 E-11 NO DATA 4.21E-13 4.25E-06 3.64F-05 i

i I

7.1-6

. REVISION 1 SEPTDtBER 1979 TABLE 7.1-E-10 (Cont'd)

NHCLICE uGNE LivCP T.nUDY THYHCID KIDhtY LUNG GI-LLI S4140 4.00E-05 4.COC-08 2.C 7F-9 6 NO DATA 9.59E-09 1.14F-03 2 74E-05 e4141 1.12E-10 7.70r-14 3.55--12 NO DATA 4.64L-14 2.12f-06 1.39F-06 Mal 42 .

2.64E-Il 2.305-1* 1. 4 0 E - 12 NU OATA 1.36L-14 1.11E-06 4.95E-07 L A140 1.6tE-C7 1.44t-07 4. 0 si-0 3 NO DATA Nfl D A T A 1.20E-04 6.96C-05 L A142 7.36E-10 2. tat-10 e.*od-11 Nn DATA NC CATA 3.87F-06 4.25C-05 CE141 1.18E-03 1.19E-05 1.42t-06 No cara 3.F5t-06 s.69F-04 1.54C-05 CE143 2.39E-07 1.lut-07 1.54F-08 10 QATA 4.03E-08 8.30E-05 3.55E-05

• E144 2. 2 8 5 - 0 ~3 S.o56-04 1.?oE-04 NO DATA 3.H4E-04 7.0lE-03 1.06E-04 i val *3 1.00E-G5 1.74E-Oo 4. 91E -0 7 NO UATA 1.41E-06 3.09E-04 2.66E-05 PR144 5.42t-11 1.32E-11 1.12 E -12 NO CATA 4.90E-12 1 15F-06 3.06r-06 1014T *> . 6 7 t - D ei 5.R10-06 1.57E-07 t:0 D AT A 2.25t-96 2.30E-04 2.23E-05 w 187 9.26E-09 6.44E-09 2.2SE-07 NO UATA NO DATA 2.03E-05 2.54F-05 NP239 2.65E-07 2.17C-09 1.1*E-09 NO DATA 4.73L-Oe 4.25E-C5 1.78C-05 l

e 1

e 1

7.1-7

REVISION 1

. SEPTEMBER 1979 TABLE 7.1-E-ll INGESTION DOSE FACTORS FOR ADULTS  ;

(mrem per pCi. Ingested) -

HUCLILE RONE LIVER T.HOCY THYR 0!D KIDNEY LUNG GI-LLI H $ NO DATA 1.05C-0/ 1.CSE-07 1.C5d-07 1.156-07 1.05E-07 1.05E.07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68C-17 5.68E 07 5.68E-07 5.68E-07 NA 24 1.70F-06 1.7CF-06 1.70E-06 1.10E-06 1.70E.06 1.70E 06 1.70E-06 P 32 1.93E-04 1.20E-05 7.4bE-Oo NO DATA NC DATA NO DATA 2.17E 05 CR 51 t40 O A T A NO CATA 2.6cE-09 1.51E-09 5 86E-10 3.5SE-09 6.69E 07 MN 54 NO UATA 4.575-C6 9. 72 E-0 7 NO DATA 1 36E-C6 NO DATA 1.40E-05 MN 56 NO DATA 1 135-07 2 049-04 NO DATA 1 46E-07 NO DATA 3.67F-06 fC 55 2.75E-C6 1 70F-06 4.4$[-07 NO CATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-C6 1.C2C-05 3.11 E -0 6 NO DATA NC DATA 2.85E-06 3.40E 05 CO $8 NO DATA 7.45d-07 1.67E-06 40 UATA NO DATA NO DATA 1 51E-05 CO 60 NO DAIA 2.1*F-06 4. 72 C-0 6 NO DATA NO DATA NO DATA 4.02E.05 1.3CE-C4 9.01E-oo *.36E-06 NO UATA NO DATA NO DATA 1 88E-06 NI 63*

NI 6s 5.28E-07 e.e6E-05 3.13E-09 NO OATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 3.333 08 3.91C-Oe NO CATA 2.10E-07 NO DATA 7.10E-C6 ZN 62 4.84E-C6 1.>46-05 c.9uE-06 NO DATA 1.C3E.05 NO DATA 9.70E-06 2N 69 1.016-08 1.iTC-r8 1.J7E-09 NO CATA 1.28E-Oe NO DATA 2.96E-09 BR 83 40 D A T A NO DA7A 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 MR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E.13 OR 8) NO DATA NO DATA 2.14E-09 NO DAT1 NC DATA NO DATA LT E-24 RH d6 NO DATA 2.lli.95 9. 8 3 E -0 6 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO CATA 6.0SE-OS 5.21E-08 NO DATA NO DATA NO DATA 8.36E-19 M4 89 NO DATA 4.01E-09 2 82C-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-C4 NO DATA 8. 8 4 E -0 6 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO CATA 1.8cE-03 NO DATA NC CATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-97 NO CATA NC DATA NO DATA 2.70E-05 SR 92 2.15E-C6 NU CATA 9. 30E-0 8 40 DATA NC CATA NO DATA 4.26E-05 Y 90 9.62E-09 NU CATA 2 5dE.10 NO DATA NC DATA NO DATA 1 02E-04 Y 9tF  ?.09E-11 NO DATA 3.52C-12 NO CAft NO DATA NO DATA 2.67E-10 Y 91 1.4tE-C7 NU DATA 3.77E-09 NO CATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO CATA 2 47E-11 NO DATs NO DATA NO DATA 1.48E.05 e G 7.1-8 .

,t.

REVISION 1 SEPTEMBER 1979 TABLE 7 1-E-ll (Cont 'd) -

NUCL I CE tune LiviR T.EOCY THYROIC KIDNEY LUNO GI-LLI

.............._.........................._.............__s_................_

Y 93 2.68E-09 NC UATA 7.4]E-11 NO DATA NO DATA NO DATA 8.50E-05 E R 15 3.04E-0P 1.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 IR 97 1.68E-C9 3.s92-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04

'48 95 6.22E-C9 3.46E-09 1.86E-09 NO CATA 3.42E-09 NO DATA 2.10E-05 M D 19 NO DATA 4.31E-06 8.20E-07 740 D A T A 9.76k-06 NO DATA 9.99E-06 TC 97a 2.47E-10 6.985-10 S. 89E-0 9 NO DAf4 1.06E-08 3.42E-10 4 135-07 TC101 2 54E-lO 3.66E-1C 3. 5 9 E -0 9 NO DATA 6.59E-09 1.87E-10 1.10E-21 1U103 1.85E-07 10 LATA 7.97E-08 No DATA 7.06E-C7 NO CATA 2.16E-05 R0109 1.24E-08 NU CATA 6.0?E-09 NO DATA 1.99E-07 N O DAT,4 9.42E-06 3U106 2.75E-06 NO DATA 3.4SE-07 NC OtTA 5.316-06 NO DATA 1.78E-04 A0110e 1.60h-07 1.48F-07 8. 7 9 E-0 8 NO DATA 2.9tE-07 NO DATA 6.04E-05 fft25r 2.69E-06 9.7tE-07 3. 51E-0 7 8.065-37 1.09E-05 NO CATA 1.075-05 TE127* 6.77E-06 2.42E-06 8.25E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10t-0F 3.95E-C8 2.3HE-08 8.15E-C8 4.486-07 NO DATA 8.68E-06 TE129u 1.lbE-05 4.29c-Co 1.82E-06 3.95E-06 4.806-05 NO DATA 5.79E-05 TE129 3.14E-08 1. lee-08 7. o 2 E-0 9 2.41E-08 1.32E-07 NO DATA 2.37E-08 TEllik 1.73E-06 8.46E-07 7.05E-0 7 1.34C-06 B.57E-06 NO DATA 8.40E-05 TEl31 1.97E-C6 9.23E-09 6.22E-01 1.02E-08 9.63L-08 NO Daft 2.79E-C9 IE132 2.52E-06 1.c3E-06 1. 5 s E .0 6 L.8CE-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23C-06 8. 8 0E-0 7 1.89E-04 3.48E-Oo NO DATA t.92E-06 ,

i 131 4.16E-C6 5.952-06 3. 41 E -0 6 1.95E-03 1.02t-05 NO DATA 1.57E-06 I 132 2. ole-07 5.43F-07 1.90E-07 1.90E-05 8.65t-07 NO CATA 1.02E-07 I 133 1 42E-06 2.57f-06 7.5 3E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1. O s E-0 ? 4.995-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.10E-06 4. 2 S E -01 7.65E-05 1.96E-C6 NO DATA 1.31E-06 C5134 6.22E-C5 1.48~-04 1.2tE-04 NO DATA 4.79t-05 1.59E-05 2.59E-06 C5136 6.51E-06 2.57E-05 1.85E-05 SO DATA 1.43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1.C9E-04 7.146-05 NO DATA 3.70t-05 1.23E-05 2.llE-06 C5138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01k-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 5.92E-11 1.72E-07 l

l 7.1-9

. REVISION 1 SEPTEMBER 1979 TABLE 7.1-E-11 (Cont 'd) i MUCLitE BONF LIVER T.acDY THYRDIO KIDNEY LUNG GI-LLI 4A149 2.0$E-C5 2.55E-OS 1.336-06 49 DATA 4.67t-09 1.46E-08 4 18E-05 04141 4. TIE-08 3.46E-11 1.515-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 94142 2 13C-OR 2.19E-11 1 36t-01 40 DATA 1.95F-11 1 24E-11 1.00E-26 LA140 2. SOL-09 I.262-09 3 33E-10 NO DATA NC DarA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 40 DATA NC OATA NO DATA 4.25F-07 OE141 9.36E-01 6.jsF-09 T.19E-10 NO Daft 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-C1 1.??A-06 1.35E-10 NO Data 5.376-10 NO DATA 4.56E-05 CE144 4.R8E-07 2.04:-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR145 9.20E-09 3.69:-09 4.SoE-10 NO DATA 2.13 E -09 NO DATA 4.C3E-05 PRI44 3.01E-11 1.235-11 1.55E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND147 6.29E-C9 7.27E-09 4. 45E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 h 197 1.0 3E-0 7 9.61E-08 3.01E-36 NO DATA NO DATA NO DATA 2.82E-05 (4P239 1.19E-01 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05

\

l 1

i l

l l

l 7.1-10 .

REVISION'l SEPTDiBER 1979 TABLE 7.1-E-14 INGESTION DOSE FACTORS FOR INFANT (mrem per pCi Ingested)

NuCLict sone Liv 2R T . d D vY THY 1010 #10NEY LUNG GI-LLI H 3 NO DATA 3.C d".0 T $.01E-9 T 3.09F-07 1.03L-07 3.COE.07 3.09E-07 L I4 2. 3 FF-C5 5.C6f-00 5. 0 0E-C L 3.G6E-06 5.C06-06 5.C65-06 5.06E-06 NA 24 1.016-05 1.01E-03 1.01t-05 *

1. 01 ;- f. 5 1.nlE-05 1.01E-05 1.01E-C5 e 32 1.706-03 1.001-04 c.54c-05 40 OATA NC DATA NO DATA 2.lCE-Oi

". A 51 NU UATA NO DATA 1. 1E-08 9.20E-99 2.01E-09 I.79E-08 4.11E-07

.* N 54 NO DATA 1.995-02 4. 51 t -0 6 NO DATA 4.41E.06 NO CATA 7.31E-06 MN 56 Nu DATA A.1W.-07 1.41 r.0 7 Nu OAT / 7.01E-07 Nn Daft 7.43r-05 rE 55 1.39E-05 8.192-06 2.4;[-06 NO DATA NC DATA 4.19E-06 1.14E-06 rF 59 3.086-05 5.38~-02 2.12E-05 NO CATA NO DATA 1.59E-05 2.5 7F-05 CC 58 NO DtTA 3.00p-06 8.91r-06 NO DATA NO DATA NO UATA A.97E-C6 CG 60 NO 0AIA 1.0be-05 2.55E-05 NO UATA NC DATA NO DAT% 2.57E-05 NI 6 5 6.34E-C4 3.92s-05 2.20E-05 NO UATA NO DATA NO CATA 1.95E-C6 NI bi 4.70E-06 5.32E-07 2. 4Ji-0 7 NO DATA NO DATA NO DATA 4.05E-05

%U 04 NO DATA '

6.G9t-01 2. 8/ E-0 7 NO DATA 1.03C-06 NO Daft 1.25E-05 IN 63 1.14E-05 c.316-05 2.91E-03 NO DATA 1.06E-05 NO DATA 5.33E-05 IN 67 9.3JE-C8 1 06E-01 1.250-09 NO DATA 6.1PE-08 NO DATA 1.37F-05 HR 03 Nn DATA NO DATA 3. 61 E -0 7 NO GATA NC UATA NO DATA LT E-24 uR S, NO DATA N0 UATA 3.RJL-07 NU DtTA NO DATA NO PATA LT E-24 OR 83 NO DATA NO DATA 1.94E-0A NH DATA NC DATA NO DATA LT C-24 NB 86 NO DATA 1.102-04 8.4JE-05 NO DATA NO DATA fiO DATA 4.32E-06 4R 88 NO DATA 4.98E-07 2.7sE-01 NO DATA NO DATA 40 DATA 4.83r-07 RP .%1 NO DATA 2.U6E-07 1.97E-37 NO DATA NC OATi NO DATA 9.74E-08 53 89 2.51E-03 NG CATA 7. 2CE-0 5 NO DATA NO DATA NO DATA 5.16E-05 5R 90 1.056-02 Nu DATA 4. 71 E -0 3 40 QATA NO DATA NO DATA 2.31E-04 54 91 5.CCE-C5 NO 0%Ta 1.21E-06 NO DATA NO DATA 40 DATA 5.92C-05 51 12 1 92C-C5 No DATA 7.132-07 NO CATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 du CATA 2.32E-09 NO CATA NC DATA NO DATA 1.20E-04 Y 91m 8.lCE-IC NO DATA 2. 7 6 c.1 1 NO. DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 N0 DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 e

7.1-11

• REVISION 1 SEPTEMBER 1979

. TABLE 7 1-E-14 (Cont!d) - ,

NUCLICE BONE LIVER T.000Y THYROID KIDNEY LUNG GI-LLI

............ x...._............................... _.........................

~

Y 93 2.41E-08 NO DATA 6.62F-10 NO DATA NO DATA NO DAia 1.928-04 ZR 95 2.06E-07 5.02E-09 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50F-05 IR 97 1.49E-0R 2.54C-04 1.16E-09 NO DATA 2 56E-09 NO DATA 1.62E-04 No 95 4.20E-08 1.73E-08 1.03E-08 NO DATA 1.24t-08 NO DATA 1.46E-05

".O 91 NO DATA 3.4CZ-05 6. 6 3 E-0 6 NO DATA 5.08E-05 NO DATA . 1.12E-05 TC 91F 1.92c-09 3.96~-09 5.10E-09 HO DATA 4 26t-OR 2.07E-09 1.15c-06 IC101 2.27E-01 2.?6E-09 2.83E-0C 40 DATA 3.40E-09 1.56E-09 4.86E-07 RU103 1.*EE-06 NO UATA 4.95E-07 10 DATA 1.08E-06 NO DATA 1 80E-05 10105 1.36E-07 NO DATA 4.53E-38 10 GATA 1.00E-06 NO DATA 5.41E-05 RU106 2.41E-05 NO DATA 3.01E-06 NO CATA 2.95E-05 NO DATA 1.R35-04 4Gt10w 9;96E-07 7.27E-07 4. PIE-07 40 CATA 1.04E-06 NO DATA 3.77E-C5 TE12)P 2.33E-05 7.79E-06 3 12E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE127" 5.85E-05 1.h?-05 7. 0 a E-0 6 1.67E-05 1.44E-04 ho GATA 2.36E-05 TE127 1.00E-06 3.355-07 2.15E-07 8.145-67 2.44c-06 NO DATA 2.10E-05 TE129M 1.00E-04 3.4Sc-05 1.54E-05 3.84E-05 2.505-04 NO DATA 5.97E-05 TC129 2.84E-07 1.71E-09 6.61E-38 2.3eE-07 7.07E-07 NO DATA 2.27E-05 TE131w 1.52E-05 6.12E-06 5.0$E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 1E131 1.76E-07 6.50E-08 4.94L-08 1.575-07 4.50E-07 40 DATA 7.11E-06 TE132 2.0BE-05 1.03E-05 9.61E-06 1.5?E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.00t-06 1.325-15 5.30E-06 1.4RC-11 1.45E-05 NO DATA 2.83E-06 i 131 3.59E-05 4.23E-0) 1. 9 eE -0 5 1.39E-02 4.04E-05 NO DATA 1.51E-06 I 132 1.06E-06 3.47F-06 1. 2 0 E -0 6 1.59E-04 3.76L-06 NO DATA 2.73E-06 I 133 1.25L-05 1.62T-05 5.3tE-06 3.315-03 2.14E-35 NO DATA 3.08E-06 134 8.6?E -01 1.78C-0e 6. 3 3E-0 7 4.152.n5 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-44 9.07E-06 NO DATA 2.62E-06 C5134 3.77E-04 7.03E-04 7. l *t E-0 5 NO CATA 1.810-04 7.42E-05 1.11E-06 C5136 4.59E-05 1.55E-04 5.04E-)5 NO DATA 5.3eL-05 1.10E-05 2.05E-06 C5137 5.22E-04 6.11E-04 4.43E-05 No GATA 1.64E-04 6.64E-05 1.91E-06 C5138 4.816-07 7.L2C-07 3. 79E-0 7 10 DATA 3.90E-07 6.09E-08 1.25E-06 8A139 8.81E-07 5.84E-10 2.55E-18 Nu osTA 3.51F-10 3.54E-10 5 58E-05 l

i 7.1-12 I

l t

I

REVISION 1 1

SEPTDIBER 1979 TABLE 7.1-E-14 (Cont'd)

NUCL:JE B0r eE L i vE rt T..iCLY THYe010 K!DNEY LUNG Cl-LLI BA14u 1.7tE-04 1.71C-07 1.81E-06 NO DATA 4.C6E-08 1.05E-07 4.20E-05 Pat 41 4.25E-C7 2.112-10 1. 3

• t'-0 9 '40 DATA 1.75E-10 1.7FF-tC S.19E-06 rat 42 1.P4E-C7 1. Jc-10 9.00E-01 NO CATA 7.59E-07

.....................').............s.........................................

e.91E-It 9. 2 f> E-I t - -

LA140 2.llE-0P e.12C-C9 2.14E-09 NU uaTA NO 041A NO DATA 9. 7 7F-05 LA142 1 10E-09 4.068.-10 9.ctF-Il NO DATA NC DATA NO DATA 6.96F-05 CC141 7.87E-08 4.e0*-C8 3. c a,E -0 9 NO DATA 1 49t-C9 NO DATA 2.48E.05 CE143 1.48E-C9 9. 0 2 E - O c, 1.1)C-09 NO CATA 2.96c-C9 NO DATA S.73E-05 CCl44 2.962-06 1.22C-Ob 1. 6 7E-9 7 NO DATA 4.93E-07 NO DATA 1.ftt-04 PRl*3 e.13E-OR 3.c4L-09 4.0sE-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR144 2. 7 4L- 10 1.06E-10 1. 31E -11 *40 U A T A 3.44t-il NO DATA 4.93E-06 tip l 4 7 S.*>3E-C9 5.u B5 r,a 1.40E-09 NO DATA 2 19t-0R red DATA 1. 6 0 0 0 *>

w 18F 9.03E-07 6.2dt-07 2.17E-0 T NO CATA NO DATA ran DATA 1.69E-05 Nv211 1.IIE-C? 9.93L-10 S.616-10 10 UATA 1.98E-09 NO DATA 2 870-05 b

(

1 I

{

• l l

l 7.1-13

i

,a I i

TABLE.7.1-2 REVISION 1 l SEPTEMBER 1979 j MISCELLANEOUS DOSE ASSESSMENT FACTORS - ADULT M -

Ua = 310 liters /yr Eg = 8000 10 /yr P

Ua = 520 kg/yr V

Ua = 64 kg/yr U[=110kg/yr

, PP = .76 fy = 1.0 th = 0 for pasture grass (milk and meat pathways) tt = 24 hr (1 day for leafy vegetables) th = 1440 hr (60 days for produce) th = 2160 hr for stored feed (milk and meat pathways) te = 720 hr (30 days for milk and meat) t e = 1440 hr (60 days for produce or leafy vegetables) fr = 1.0 May-Oct.

fr = 0.0 Nov-April fg = 0 5 ,

Aw = .0021 hr~1 Yy = 2.0 kg/m2 for leafy vegetables and produce pathways 7.1-14

l L

l REVISION 1 SEPTEMBER 1979 l TABLE 7.1-2 (Cont'd)

Yy = 0 7 kg/m 2 for milk and meat pathways t = 480 hr (20 days) 3 r = 1.0 (iodines) 0.2 (others)

W p = 50 kg/ day I t = 48 hr (2 days)

M 6

k 7.1-15 ,

REVISION 1 i

SEPTEMBER 1979 TABLE 7.1-3 MISCELLANEOUS DOSE ASSESSMENT FACTORS - INFANT U = 330 liters /yr U,, U , U a

=0 3

R, = 1400 m /yr Wf = 50 kg/ day r = 1.0 (iodines)

• l 0.2 (others) t n 48 hr (2 days)

M

-1 A, = 0.0021 hr 2

Y, = 0.7 kg/m t, = 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> th = 0 for pasture grass (milk pathway) t = 2160 hr (stored feed and milk pathway) h f = 1.0 May-Oct.

f f = 0.0 Nov.-April f

f = 0.5 g

K = 0.5 May-Oct.

K = 0.0 Nov.-April

• The r factor provides for the non-deposition on grass of the -

organic forms of iodine. 1 7.1-16 L

l *

- REVISION 1

• SEPTEMBER 1979 D

TABLE 7.1-4 STABLE ELEMENT TRANSFER DATA

• F 7

F(M Element Meat (d/kg) Milk (d/1).

H 1.2E-02 1.0E-02 C 3.1E-02 1.2E-02 Na 3.0E-02 4.0E-02 P 4.6E-02 2.5E-02 Cr 2.4E-03 2.2E-03 Mn 8.0E-04 2.5E-04. .

Fe 4.0E-02 1.2E-03 i Co 1.3E-02 1.0E-03 -~ -

Ni 5.3E-02 6.7E-03 Cu 8.0E-03 1.4E-02 3

Zn 3.0E-02 3.9E-02 Rb 3.1E-02 3. 0E-02 Sr 6.0E-04 8.0E-04 Y 4.6E-03 1.0E-05 Zr 3.4E-02 5.0E-06 Nb 2.8E-01 2.5E-03 I Mo 8.0E-03 7.5E-03 Tc . 4.0E-01 2.5E-02 .

Ru 4.0E-01 1.0E-06 Rh 1.5E-03 1.0E-02 Ag 1.7E-02 .5.0E-02 Te 7.7E-02 1.0E-03 I 2.9E-03 6.0E-03 Cs 4.0E-03 1.2E-02 J Ba 3.2E-03 4.0E-04 La 2.0E-04 5.0E-06 4

Ce 1.2E-03 1.0E-04 Pr . 4.7E-03 5.0E-06 Nd 3.3E-03 5.0E-06 W 1.3E-03 5.0E-04 Np 2.0E-04 5.0E-06

. Br 2.9E-03** 1.4E-02***

• Data presented in this table are from NRC Regulatory Guide 1.109, Revision 1, (Reference 6.5), October 1977.

• • Used value for I' (no lite,rature available) .

• • • W. C. Ng " Transfer Coefficients for Prediction of the Dose to Man Via the Forage-Cow-Milk Pathway From Radionuclides Released to the Biosphere," UCRL-51939.

7.1-17

(

[ - w- 4e

_ . . - _ . _ =-

4

, , REVISION 1

, SEPTEMBER 1979 l'

! TABLE 7.1-5 ATMOSPHERIC STABILITY CLASSES 1,

4 ,

Description Pasquill Temperature Interval Stability Class (Degrees C/100 M)

Extremely Stable G at > 4.0 Moderately Stable F 4.0 > At 1 15 Slightly Stable E 15 > 4t > -0 5 Neutral D -05 > At 1-15 .

Slightly Unstable C -1 5 '> At > -1 7 Moderately Unstable B -1 7 > At > -1 9 Extremely Unstable A -1 9 > At r

l 7.1-18

...m o -- .

m

i y

. s .

• REVISION 1 SEPTEMBER 1979 l

1 j, TABLE 7.1-6 i

I i

WIND SENSOR THRES CLD 9

ANDIOMETER VANE i I,0 CATION WIND SPEED (mph) WIND DIRECTION (mph)

Dresden O.8 09 .

Quad Cities 0.6 0.8 Zion 0,5 0,7 LaSalle 05 o.7 Eraidwood 0.8 o,8

{

Byron o.8 0.8 Carroll County 05 07 9

e 7.1-19 ,

j l

1

TABLE 7.1-7 REVISION 1 SEPTI 51BER 1979 VERTICAL DISPERSION PARAMETERS (Based on Reference 6.11)

The vertical dispersion parameters are given in the following:

The general form of the exponential functions is o = (C) (X)P (meters) g The coefficients and exponents vary with stability.

In the case of O z these values also vary with range (x). .

Vartical Plume Width (02)

Stability Range (meters)

Class From Tjl Coefficient (C) Exponent (p) i A 100 300 0.0800 1.12 i 300 450 0.0095 1.49 450 1.397 0.0002 2.13 l

B 100 280 0.1271 0 96 .

280 540 0.1012 1.00 540 7,393 0.0555 1.10 C 100 215 0.1055 0 92 215 400 0.1287 0.89 400 5,000 0.1009 0 93 5,000 21,392 0.1267 0 90 0 100 210 0.0893 0.86 l

l 210 500 0.0979 0.84 500 900 0.1596 0 76 900 2,000 0.2799 0.68 2,000 15,000 0.4730 0.61 15,000 . 35,000 0.8368 0 55 35,000 -

1.6314 0.49 E 100 190 0.0650 0.87 190 300 0.0737 0.84 300 700 0.1279 0 74 700 1,400 0.1571 0 71 l

1,400 3,200 0 3740 0 59 3,200 13,000 0 7146 0 51 13,000 30,000 1 3970 0.44 -

l 30,000 54,000 4.2480 0 33

! 54,000 -

9 7058 0.26 7.1-20 e

REVISION 1 SEPTEMBER 1979 -

1

\

~

TABLE 7.1-7 (Cont'd) i Stability Range (meters)

Class From To, Coefficient (C) Expo te; (p) .

F 100 210 0.0548 0.81 .

210 400 0.0606 0 79 400 600 0.0564 0.80 600 1,000 0.0980 0.72 1,000 2,000 0.1947 0.62 2,000 4,000 0.4847 0 50 4,000 10,000 0.6706 0.46 10,000 20,000 1 5723 0 37 20,000 68,000 3 7561 0.28 68,000 -

3 9068 0.28 G 100 210 0.0329 0.81 210 400 0.0364 0 79 400 600 0.0338 0.80 600 1,000 0.0590 0 72 1,000 2,000 0.1168 0.62 2,000 4,000 0.2908 0 50 4,000 10,000 0.4024 0.46 10,000 20,000 0 9434 0 37 20,000 68,000 2.2537 0.28 68,000 -

2 3441 0.28 Note: For stability classes"A B and C oz is limited to 1 km.

I 1

7.1-21

'. l I

, REVISION 1

,,, SEPTDiBER 1979 ,

. ~

TABLE 7.1-8 ,

WIND SPEED AND WIND DIRECTION CLASSES Wind Direction Classes WIND DIRECTION CLASS (DEG) N WIND DIRECTION GT 348.75 AND LE 11.25 WIND DIRECTION CLASS (DEG) NNE WIND DIRECTION GT 11.25 AND LE 33 75 VIND DIRECTION CLASS (DEG) NE WIND DIRECTION GT 33 75 AND LE 56.25 WIND DIRECTION CLASS (DEG) ENE WIND DIRECTION GT 56.25 AND LE 78.75 WIND DIRECTION CLASS (DEG E WIND DIRECTION CT 78.75 AND LE 101.25

~

~

WIND DIRECTION CLASS (DEG) ESE WIND DIRECTION 101.25 AND LE 123 75 WIND DIRECTION CLASS (DEG) SE WlND DIRECTION r 123.75 AND LE 146.25 WillD DIRECTION CLASS (DEG) SSE WIND DIRECTION ST 146.25 AND LE 168.75 WIND DIRECTION CLASS (DEG) S WIND DIRECTION GT 168.75 AND LE 191.25 WIND DIRECTION CLASS (DEG) SSW WIND DIRECTION GT 191.25 AND LE 213 75 WIND DIRECTION CLASS (DEG) SW WIND DIRECTION GT 213 75 AND LE 236.25 WIND DIRECTION CLASS (DEG) WSW WIND DIRECTION GT 236.25 AND LE 258 75 WlHD DIRECTION CLASS (DEG) W WIND DIRECTION GT 258 75 AND LE 281.25 WIND DIRECTION CLASS (DEG) WNW WIND DIRECTION GT 281.25 AND LE 303 75 WIND DIRECTION CLASS (DEG) NW WIND DIRECTION GT 303 75 AND LE 326,25 WIND DIRECTION CLASS (DEG) NNW WIND DIRECTION GT 326.25 AND LE 348.75 Wind Speed Classes WIND SPEED CLASS (MPH) 1 WIND SPEED dE 0.0 AND LT ST*

WIND SPEED CLASS (MPH) 2 WIND SPEED GE ST AND LE 3.5 WIND SPEED CLASS (MPH) 3 WIND SPEED 35 WIND SPEED CLASS GT AND LE 75 (HPH) 4 WIND SPEED GT 75 AND LE 12 5 WIND SPEED CLASS (MPH) 5 WIND SPEED GT' 12.5 AND LE 18.5 .

WIND SPEED CLASS (MPH) 6 WIND SPEED GT 18.5 AND LE 24.5 WIND SPEED CLASS (MPH) 7 WIND SPEED GT 24.5 AND LE 31 5 WIND SPEED CLASS (MPH) 8 WIND SPEED GT 31 5 AND LE 38.5 WIND SPEED CLASS (MPH) 9 WIND SPEED GT 38.5 AND LE 46.5 WIND SPEED CLASS (MPH) 10 WIND SPEED GT 46.5 AND LE 99.8 l

l

• ST: Speed Threshold Value i

7.1-22  !

I

TABI 7.1-9 AIRBORNE ISOTOPE DATA .

Icotope Decay

• Average Energy

• Linear Energy A

Linear A Tissue Energy ** l Constant Per Disintegration Absorption Attenuation Absorption Coeff.

(1/hr) (Mev/ dis) in air in air Ki A un u i pG EB (1/ meter) (1/ meter) = u - ua uh 2

Kr-83m 3 79E-1 2 58E-3 3.82E-2 37 37 0 4.87 Kr-85 7.38E-6 2.23E-3 2 51E-1 50 50 0 4.87 Kr-85m 1.55E-1 1 58E-1 2 55E-1 0.0033 0.017 4.15 0.0279 Kr-87 5.45E-1 8.04E-1 1 33 0.0037 0.0092 1.49 0.0318 Kr-88 2.44E-1 1 98 3.49E-1 0.0031 0.0058 0.87 0.0259 Kr-89 1 31EF1 1 71 l.31 0.0029 0.0054 0.86 0.0251 yKr-90 7.72E+1 1.26 1.30 0.003 0.0056 0.87 0.0254 Xe-131" 2.43E-3 2.00E-2 1.42E-1 0.065 0.098 0 51 0 533 Xe-133 5 51E-3 4.60E-2 1.35E-1 0.0066 0.028 3 24 0.0566 Xe-1335 1.32E-2 4.15E-2 1 90E-1 0.0076 0.03 2 95 0.0674 Xe-135 7.63E-2 2.48E-1 3 17E-1 0.0036 0.015 ,

3.17 0.0305 Xe-135m 2.66E+0 4.31E-1 9 58E-2 0.0038 0.012 2.16 0.0326 Xe-137 1.09E+1 1.82E-1 1.78 0.0035 0.016 3 57 0.0293 E Xe-138 2 93E+0 1.13 6.32E-1 0.0035 0.0075 1.14 0.0301 g$

o H

Ar-41 3 79E-1 1.28 4.64E-1 0.0034 0.0072 1.12 0.030 e e

• Computed from data in Reference 6.8 d

" The Conste.nts (ut) were obtained from Radiation Dosimetry, Vol. I, Attix and Roesch, editors, 1968, Academic Press (Table XXII).

60ther values from Radiological Health Ilandbook, Revised Edition, January 1970.

- REVISION -1

- SEPTEMBER 1979 TABLE 7.1-10 MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FRDM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC(uCi/ml)*

Kr 85 m 2E-4 85 SE-4 87 4E-5 88 9E-5 ,

Ar 41 7E-5 Xe 131 m 7E-4 133 m SE-4 133 6E-4

, 135 m 2E-4 135 2E-4

• Computed from Equation 20 of ICRP Publication 2 (1959),

adjusted for infinite cloud R = 0.01 rem / week, p submegsion in water, and

= 1.0 gm/cm , and P /P = 1.0.

y y t 7.1-24

' REVISION 1

+ SEPTEMBER 1979

. TABLE 7.1-11 LISTING OF RADIOLOGICAL DECAY CONSTANTS (A i) i DECAY CONSTANT

ISOTOPE A3(hrs-1)*

~

H-3 :6.40E-6 c-14 1 38E-8 Na-24 4.62E-2 P-32 2.02E-3 cr-51 1.04E-3 Mn-54 9 24E-5 Mn-56 2.69E-1 Fe-55 2.93E-5 Fe-59 6.47E-4 1 co-56 4.08E-4 00-60 1.SoE-5 Ni-63 8.23E-7 Ni-65 2.75E-1 cu-64 5.46E-2 .

2n-65 1.18E-4 Zn-69 7.29E-1 Br-83 2 90E-1 Br-84 1.31E+o Br-85 1.45E+1 Rb-86 1 55E-3 Rb-88 2 34EAo .

Rb-89 2 74E+o sr-89 5 71E-4 sr-90 2.77E-6 sr-91 7,29E-2 sr-92 2 56E-1 Y-90 1.08E-2 Y-91M 8.36E-1 Y-91 4.94E-4 Y-92 1 96E-1 Y-93 6.86E-2 zr-95 4.51E-4 Zr-97 4.loE-2 Nb-95 8.21E'4 Mo-99 1.05E-2 Tc-99M 1.15E-1 Tc-lol 2 93E+o Ru-103 7 34E-4 Ru-105 1 56E-1 7.1-25 .

t I

. REVISION 1

. SEPTEMBER 1979 TABLE 7.1-11 (Cont'd)

~

DECAY ISOTOPE CONSTAh})*

Ai (hrs -

Ru-106 7.84E-5 Ag-110M 1.15E-4 Te-125M 4.9dE-4 Te-127M 2.65E-4 Te-127 7.41E-2 Te-129M 8.59E-4 Te-129 5 97E-1 Te-13n: 2 31E-2 Te-131 1.66E+0 -

Te-132 8.86E-3 ' ' '

I-130 5.61E-2 I-131 3 59E-3 I-132 3 01E-1 I-133 3 33E-2 I-134 7.90E-1 I-135 1.05E-1 Cs-134 3.83E-5 Cs-136 2.20E-3 Cs-137 ' 62E-o Cs-138 a. 29E+O -

Ba-139 5 03E-1 -

~

Ba-140 2.26E-3 Ba-141 2.28E+0 Ba-142 3.89E+0 La-140 1.72E-2 IA-142 4.49E-1 Ce-141 8.88E-4 Ce-143 2.10E-2 Ce-144 1.02E-4 Pr-143 2.13E-3 Pr-144 2.41E+0 Nd-147 2.61E-3 W-187 2 90E-2 Np-239 1.23E-2

• Ai= Radiological Decay Constant Ti = Radiological Half-life Ai= (693 / Tifrcm Reference 6.8)

A For unlisted nuclides, see References 6.8 and 6.9.

l 7.1-26

, REVISION 1

, SEPTDiBER 1979 TABLE 7.1-12 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pCi/kg per pCi/ liter)*

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E403 9.1E+03

• Na 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 ,

Br 4.2E+02 3.3E+02 Rb 2.0E+03 1.0E403 Sr 3.0E401 1.0E+02 Y 2.5E+01 1.0E+03 Zr 3.3E400 6.7E400 Nb 3.0E+04 1.0E+02 Mo 1.0E401 1.0E401 Tc 1.5E401 5.0E+00 Ru 1.0E+01 3.0E+02 Rh 1.0E401 3.0E402 Te 4.0E+02 6.lE+03 I 1.5E+01 5.0E400 Cs 2.0E403 1.0E+03 Ba 4.0E+00 2.0E402 4

La 2.5E+01 1.0E+03 Ce ' l.0E400 1.0E+03 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E403 W l.2E+03 1.0E+01 Np 1.0E+01 4.0E+02' Ag 2.3E+00** 7.7E+02** l

• Values in Table 7.1-12 are taken from NRC Regul.- :ry Gside 1.109, Table'A-1, Revision 1, October 1977.

• • S. E. Thompson, " Concentration Factors of Chemi, i Elements in Edible Aquatic Organisms," UCRL-50564, Revis an 1, 1972.

4 i

i I

7.1-27 1

1 1

REVISION 1 SEPTEMBER 1979 TABLE 7.1-13 BETA DOSE FACTORS FOR NOBLE GASES Beta Air Skin Dose Factor Dose Factor T L Radionuclide (mrem /yrpdrpCi/m) 3 (mrad /yr per uCi/m3)

Kr-83m ---

2.88E+02*

Kr-85m 1.46E+03 1.97E+03 Kr-85 1.34E+03 1.95E+03 Kr-87 9.73E+03 1.63E+04 Kr-88 2.37E+03 2.93E+03 Kr-89 1.01E+04 1.06E+04 Kr-90 7.29E+03 7.83E+ 03 ,

Xe-131m 4.76E+02 1.llE+03 Xe-133a 9.94E+02 1.48E+03 Xe-133 3.06E+02 1.05E+03 Xe-135m 7.llE+02 7.39E+02 Xe-135 1.86E+03 2.46E+03 Xe-137 1.22E+04 1.27E+04 Xe-138 4.13E+03 4.75E+03 Ar-41 2.69E+03 3.28E+03

• 2.88 E+02 = 2.88 x 10+2 i

7..L-28

' o -

. i g

. ~

l l

! -jf. o.

t

' i e' i , i l _

0-i ., i i (

i f

/

/

/

o C

L'J

• b

, w l\ c n d S. -

M

' / i -

VJ l

.O ll e 1:

f $

. c

/. w a

C H ,

w m

B

?

. o-f ,

N f i ti I

/

/

I -

I o

O 9 9 h W, m 9 m* N e o o o o d g o d g E

31'Jn7d NI DNINIVW3U NOI.LOV83 P d -

i FIGURE 7.1-1 PLUl4E DEPLETION EFFECT FOR GROUiD-LEVEL RELEASES (ALL A1;:0SPldfalC STABILITY CLAS$ES)

(REGULATORY GUIDE 1.111 - FIcun; 3)

. . 4;i- ! - , ; . ,: -t +' ;4 , .l.t ;f ' !

3 0

c' 0

2 x

a9 .

N g% ,3 - 0 3

' j, .

- 0

- . 1

- s l

.i r -

. .- \ -

\

g

'\ .,6[Q-}-

\

.t g .E 4'

)

.e 1 L G. s ,

..

• w B F, g+s E E  %

-Q-

. TA )C.

L (

B f ,

3 3N B.

)

S

• s A N, A U (A R T  %,, E T

E SN.-

%.N.

0 0

1 T.

O

-s .

- - L

,- 1 i t k I

)

' - - - (

D t E

.( , - -

L - ll *t' -

C

- - N

. H A T *%. T S

U .- .[ I E .

D N ,, % L E

V N_g~%'

A R

l T ..

E

% 1; T

U L

0 F

,,j .

1 1

._1 .' ,

_J.l. .

_M O

s -

_J 1

. 0 0 9 g, 7 6 5 - 4- 3 2 1 1 0 g 0 0 0 0 0 0 0 3

A R eD,_a. 2 a.

c< , o Ho40 4 n

c.o

_ m ocntl u. ,toi 0 c:.m or:1,rmw

- r ou r,7mna , 1

,o:a tou 3 c1 rrgwmm r,4- w ,::

~ - - ) - m . :r. r ..4<

.,. - 2 .

r.n c cr:c., a>w*.c rr r J - F wwmm -

-- r r >4o- -2<- oc ar i m ~.D , Jm w-1

.  ! ~

e w i,f z

- .- d o

l c63

< 1:.

c

,/

.y

, /e "

w *3*I// '

i t

t' ,A o

.- .  :-l , e 8 . . t

. i . I b e i- r  ; .--- i U l i / s' i 6 l y 'r '

E l *

/ 4'

.a y1 s

< -. U c> ~c r- .. I C

We[#/ *J m e <y m m c:

24 w

/S/-!

F D-o3 H

W

, , F ,

o0--. '

' ~. _

n 1 - r I w s Ki 8 .

I L/c t,,

Ld/ t I 5 g

~

lI j Y

• i w E

'! D

.)

>~ o "-

ye ,

li i  ;

li ll 18 ti l

1 l

i l

l  ? i l

. o

• 9 e o o N'  % A w n N e o o o e o o o 3Wf17d NI DNINIVW38 NOI.I.0Vad 'P d FIGURE 7.1-3 PLUME DEPLET10:1 EFFECT FOR 60m RELEASES (LETTi.RS DEtiOTE PASQUILL STABILITY CLASSES) '

(REGULA10RY GilIDE 1.111 - FIGURE 4)  ;

}

t

.l'

. I>l

.ii . - gs 'l ,*,

0 I I l,i.* ,;. i;i' 1 l i

• !I

' 0

. 0 2

, \ ,

\.

_. 0

_ -\ - 0

. 0

_ .s".

- 1

5. -

. ,s

\

N ,

k

\

)

w D

(

L A

.N \ )

R cE S L R T B E U A) -

T E T c, E S

M D. 0 f.

f N% <

U (A . 0 OL

.

• 1

- _ t

- ~ _ *

) l

' .~

0 - (

' ~. - 1

=

E C

G I

t.

/

N T d I N

S

- I -

D A

1 L

) T E

G, N [ E V

^ F. TO R I

A El N R E

( O T .

L Q_N EP I LE T E.

C /

BD A U r

A R L TO P SN (

F 0 2 1 1

0 0 9 8 7 6 5 4 3 2 1 1 0 0 0 0 0 0 0 0 O nsag u _, G2EEnte u2o $tgu- ,[

n E M y*s.A ur c2m oi,Rdo= m7. K' " ,Oe

gc,_;mrm>p( M -

pn~mn5 c9Sr,,-i$5F t >5 r

o- r _Q nr>Smm-

=:q E r> $ 5 c5 E , ,

• i .n r .*

> n

. N m e.- -

10-3 . , ,

i

.  : , i .4+!  : . i i .

i  ; i i! i

• i ti - '

i ij.

I 1 i

-s -.-

. t 10-4 N i . .., . , , , . . i

- &~ .;.i . .  !

_ _ ii . .  ! _.

. . .. , i iiii i i i + i,,i  !

i i IM J I I i p I !e i .. 4 I I

• . 1 I I I I il

.c ,

a- l l l l l w ..\

c

~ N  %

w i -

< +%

c- \ '

_$_ 10-5 .

hs ,

i' .l l N- '

l a.]4 0 '.'

n. I I!t i  :~ I i - ii I!

w a

w i  ! 1 J 'k i {l I

> l

. N.l l l p Ni

\

a E \\

10-0 N _._,

• . , , ,- ,'.t- U y ,a!i ..

i . . , p . . . ,..t: ,

c j t # !  ! I i ii i li i 1 7I~ .

e ie i i ij j l I .lj.

I l l l

10-7 1 0.1 1.0 10.0 100.0 200.0 PLUME TR AVEL DISTANCE (KILOMETERS) 1 .

l FIGURE 7.1-5 RELATIVE DEPOSIT 10:4 FOR GROU?iD-LEVEL RELEASES

( ALL AT 'OSFliERIC STAGILITY CL ASSES)

(RELULATORY GUIDE 1.111 - FIGURE 6).

. - r ,,

l 10-3 ,

l i....

i  ;'

i t i i!

if I i

...u L ;_ .L j lI i

. I I .

i I i ~

UNSTABLE (A,B.C) 10 '

1. _M 1 I I iiI 3r -f , x.,. '

, i  :; l,.; , . .  !

,- .! .i..i , . i , , , , . .  ! ii.!, 1 W l l i -8 j_i i i II I i l l ~

l W [ ' b_ l l ll l II g [ \,'NJ NEUTRAL l . ,

m H /

/ \\N w

< .- Ni N E

z NEU TRAL (D')

\i\N 9 10-5 l l l llll  ;~ ~

STABLE ,

h l- i , .

--w a-H-i-H '

O ' ' - ' i  ! 'n ; iq.L o.,

W I' r

', i ii e i ,,i - - , . - '.i.ii '_.

! I i i t

... i . ' . Iiili O i i f,.' { -io-w /l i J

'i[ # .. i s ;... ) > I I i

< /

/ l [/l - \ I {*sij Y+

~

g / /'l *N- i fin -

e sS Il mo sJ m.

STABLE (5,F.G) .

.' e 10-0 ,/ , ,

I!IIi l\.\!-- a E. ' '

l. N u l ,

i ..

[ i i ii ,

O i i . 1 i  ; ii .  ; ;

H; l

' i  ! ii ti i i I I I i li i j n .

/ .

10-7 1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMLTERS) i

FIGURE 7.1-6 l

l RELATIVE DEPOSITI0'i FOR 30m REl EASES (LETTERS DEt:0TE PASQUILL STACILITY CL,*iSS)

(REGULATORY GUIDE 1.111 - F.IGURE 7)

._.s......---- . ._

1 104 - , , < >

.1 ii-

_ , , i. i 6 Ie i e , t  ! .F e i i j f I ' !

' i f .i L4 ! k i e i i 1 i 1[ } '

.' I I I eitit i _

le.-Mi i UNGTABLE (fs,8,C)I l

!, .[ *N l -.

_N

/ .

f, 10-5 / .'i l NEUTRAL (D) lNl' hl

", - i" ,

'- -/ i

-t ; , , iit. . . , . T-+ 1 4

' Iii, , i i i it 5i h

p / i i ..

i1 I I!

i e

t i

6 i t 61 . .s .1 i ! e t ii I lN T N ,l.IUNSTASLE E l il ill

/  !

l l \ll 'M.}

g / N1  %

MEUTRAL B N w /

k a: . f '\.- s \ ,

A ~ t,7 ,

o 10-u  :-: .-

i-+ - , i i- ,

.gi. t i . .

y 3 e 4 .

t i,

.I !i i i 6 l

i i t i6 i e 6 L i I.~I ,

/ i i 1 6t6 I it i! i i! 8 i O!

g O l 1l li  ! III I  ! i I/' __j y -

[I ll ll l l} I l/

~ V 5 I o UJ CC

/ STABLE (E.F,G)

=10-7 ,

' ', i -

-tti !

O ', -

ii-ill f i i l i :l l - i i i i  ; p i <j i 'l  ! i li 1-ll l l i 1 I i i i I f

10-8 h 0.1 1.0 10.0- 100.0 200.0 PLUV E TRAVEL DISTANCE (K:LO.,1ETERS)

FIGURE 7.1-7 RELAT!YE D90 SIT 104 FOR 60m RELEASES (LETTER 5 D ZTE PASQUILL STACILITY CLASS)

(REGULIOOCf GUIDE 1.111 - FIGURE 8 .

l l

l

. 1

- - . - _ . _ . . _ . . . . _ _ . . . . . . .. . . . . _ . . . _ _ _ . . . _ _ . _ _ _ _ . . . _ . _ . )

j 104 ,- ,

! i-m - . i ..j!

i

. i

.i i.. i, . .

Li_Fj!'

i

, ~.

i i

,it,. . ii.. '

5 l

Q[

li ,, i iili

!!u j[).,[ UMSTABLE (A,B.C) i l l i r %1

/I \

N NN 1-

10-5 ./ g .----- A ,

t c: /

..i,ii7

..i. ., ... .

i

.i.x-c.

i i

+

i i

,1 i

i p j-j

! i iiiii / NEUTRAL (D) i i , ,4 M. '; g  ! I ii rj. _,

y / ll 111 / i i i! .

N f' ' -(Ill! .

c: / i I/ I ll N 1 NJ w -

j 2

r ,

/ ,

W _ s .. N -

s s

C 5 10-c -; _

i

i , . . r+' i 1 >

i p, ,,j '  ;- j i ,  ! .

I,Li.  ; :!

l O I i :I ' ' I '

i dI

c. t ll

-~

6llit i l uJ ,3 :lii  ! I a 11 y / /l ll l l Ilil I I .

5 lil  ! I

.2 y / STADLE (2,F,G) l

[ NO DCPLETiON l I i i

• 10-7 ;L 4 _

u , , , , . . H ,

C ,

. .i,, . l .

m i .

i I'  ! t *i . i 1

! l Il i i i I

/ I II

/

10-8 0.1 1.0 10.0 100.0 200.0 PLUME TR AVEL DISTANCE IKILOT*E TERS)

FIGURE 7.1-8 RELATIVE DEPOSITIO:: FOR 100m RELEASES (LETTEPS DE!'OTE FASCUILL STA21LITY CLASC) ~

(REGULA!0 :Y CL'IDE 1.111 - FIG'JRE 9) e

S 4

s 4 0 9

e e

f (<

~ \1 v i

\

9

+

4 e

e 1

I i

e e

o e

REVISION 1 SEPTEfiBER 1979 l

. l I

APPENDIX 7 2 Data for La Salle Nuclear Power Station f

i

)

l I

I h

LA SALLE REVISION 1 SEPTEMBER 1979 TABLE OF CONTENTS FOR SECTION 7.2

. Page Table 7.2-1 Aquatic Environment Dose Parameters 7.2-3 Table 7.2-2 Annual Design Objectives Set by 10 CFR 50 Appendix I for La Salle Station 7.2- 4 Table 7.2-3 Station Characteristics 7.2 5 Table 7.2-4 Critical Ranges 7. 2- 6 Table 7.2-5 Terrain Correction Factors (h t) 7. 2- 7 Table 7.2-6 x/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary 7. 2- 8 Table 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 Miles 7.2- 10 Table 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors For Selected Nuclides 7.2-11 e

l l

, i y = we, = .. ... - ,. .

LA SALLE REVISION 1

. SEPTEMBER 1979

.; LIST CF FIGURES FOR SECTION 7.2 NUMBER TITLE 1

7.2-1 Unrestricted Area Boundary 7.2-2 Locations of Fixed Environmental ,

Radiological Monitoring Stations d

9 t

l t .

i e

I I

ii e

4 4'9"' -

v, ,- . - , , n .. .-,.-n - , . - - - e- --- .

4 4

4 e

6 4

e

- A 4..c. 7 c2 - /

,,,,, ,ja 3 0Y2 'A / /

c .

l O.

122

if

-st: .

. ' . . - g !i.tt g. -r----- - . . . 4 ,- , -

._. 1 i:+ biMHi ..i-L:.GWlJ.Wf ll!.I!y . I !

,w p n 3 ,. 44 %. tp. %oq ' i. . ,- C.

. , .. . .i s. x.c %s - + i, l,

y c_.

. 4. .

< hgg&.m. i W . a 9 -:'. , W t ,.

- l s. . T . r, i.

.c- a;

%,. .o. .,,a .I . . . , + .

. . . I.. .

y - oan

.j r N' ' ' : te -

~

I, M 1. ;I

.-3,. f b ,I s,s.'l M I'y 19.q!I,.. .

m .g-t *,.: '

d. g'tj l $ '~'t 5 d:.I 1 s o  %

w,. . f .0,. 4- .'.: i . j...

., d.,p D.! "-

a

- dx N .a:3 :3- .

;- ' l-. '. e a

l o em

r. ;. j 3

a ffy",h M.3 '

,u -.-- .

-s-- o ae l% * .% ,*].,. '.- ,,..

U;: . ' f p-

.,- _. ] ;i.l',.. ,, '- f~~ $.- 3 l g  ;-- M

. '" ,3

. .\. ..,,.a. s" . &., , -, .r.. ... '} -.,-. a s .! r. t..? . ; . ' :

's,%. r <

p

}e;.. - ~

/:/

L

-t* 'p-. c d w

'"***m (

• w .

l, s &

)e w .

. A. ,d. .J

< O u

,_. '3pd-jg E

s. . t. F. *G I * '

M If - v ~~ N  : ,f.3

.M J*pl+q 1 ' h p. --l m 5

.s <

WW 6,.$J% .

th.,. ., ..,4

.?.

. . .,'h. . _.  ; O,

• . .;,2.

.' 1,. .* . . ., !;. . 7..p .z he ,.. .. .y

• ~.- n c:-e! o . s.. ic'. q '.. ~ up,s . . .; :.'_

'.- .~.' - s .- )

m)  :,l ' .. Cl.(*r'0(?  : p

)l 3

. L6,.\..

. _ i, .:- V,%

3.i ;.1%. . .: p { , w. -7 s a q-w *y 9 ., y.f.)c:y .Q,

--".- - l

.u _, 5 ;, ,c r ..

_ . . ( . r . -

. f.. 3 . .-fr I 1

- ~ .-- ..,.- , A e ; m' ,,, I -

......J,,

l .g "-g.~,. ~l : ,

~

r~. .(.;.l.)l .

l

, y }>}- .:. . e

..c. } .(:J- T'@'.h,

.s- > <- ) ,A :,, y~A

..m . LW.?v(O.

.;_-c1. i 3 . w%m. l. <

s s

/c .-. . .- ,e \.u_d.y. .t v.a .

..:. g '+,'. . . 3.. m..* , > , *. .

q> .n

. ._. . s_. . .

- ';.<  : .,- .~,e.

- . L, . .w-4 . .,,. -,., -,(,- n,'\:. .:._ . -

x.s----- - .m t . .. --S - .] ,. . .b: l e

". .a 3,

, h.A, .7

~ ~.'g ;J.-(,$-} - ) ,. . .%..:3

- *\; q . ?. . j j.. ;p . g ,, j' *

!- ',.y,.'> >q'..y,q  ; J g .{. ,' 3 ., ,. . p L;.

l ,

, . y ,. g

.bb., b,( N

,. 5 Nl

), '.

...~i.

e m . Wa. .U 8h. ./1, ..

r-

, v: W .

w.<,.., ..a. I

, - L,

. . - 1.A . :., .t ..,.

I l d

.w .: t,

, s- _.-

3, .y . . s . -n.. -

h.pL /(c;' :. --M,*h .' [/. ,

' ~ *

• l

.}

... c. , Q $.,

, -. e . .. i (_.o..o. : . , s --

i f. ..

(, is .-.. .

.1 - ..

.l

.m. 3(

. , . .,,,.;,, 1 . .

. . .  :, .a,- h r- d i. .-n..%l.., 6 i, , ,  :- t-' '

o, .

.; Q )i *

- .k-- . J.y ? ' .

- \= :.q.--.-. . fh - l.

. . ,. \:.

- : /.-. . -

e- - -" +7h

h.  ; . :, : ~y-~*}

.pi

'.' y -

~ .. - .

. 1 :t .. 1q:Jp2 . .> y . . .. p - ..,- ' . % ;j s

__._4

. .s L . . n G.-e n

. c %, t-

., ,4.

.? . - J. l h .

t .4 .,. t , .

-s.-..

. . pw . ; l

1. .

3). +, -

' ,.f .'e u - ..

'>2

.4

. . ,'. .... 1'. ,.

..t.

. . .)7- sm r.....< dr . .'

le

. . . r

... ,, %x - . .TJ 'j 1,. - yei

.. I. . ,

.. . L .,* ~- 3 -J r" -

v% :

g.ig,c. . ,A gc . r. r N

. * *; Ec gJ.

.. ] d . .- t r- r t T

,.f y -4 3- .

.y, . q$

.p.

. , '.'. d( . 4 . . . . _ ... .:., , 7 .-

/, .. 3 , . .--

.a, _-. .-

g t g. ..j .

i

,..y, . .

.1. _

.. . ],, . v.. e. ,

.. ,e,.

7,

m. ,. l 7  :. el.,. g-, : _ ' h, -, .i , . ..r  !-  ;. i. .. .. i

.. g_- -

~

J e l

$ ./ E

,' E ' ,h* ' 'I J.

' [ ='J,.f .' l

i i

i

...e..

' b .' *-y e;]./

L,l.1.l 'j*'.

ye p. ,,.k .. .

y.

',9I i.. -!: .-n-

.e t. -

-. ., .j '.;..p.

..c - , .

c..~s

. . TV. ., ,

A, 6

.. g t

' b-':; ,,. ;- ~. .~t. J, t. -(. .. sq --. )' s . -

..-. f

. 1 *-

s

.u.

. .s.

• . . .!4.%,

.. .g.._ y, ..t.t. .-[: t

• l . . . . -

l ^ -., ,'.:.g,p.s A,..,. ,,.... . .'l v.' .wa .; . vb. .:,g "f : _ '.[!...-.. m.j;.,p ~ .J>, *. ..

s . .:. , ,}, d.m. g, . - ,.

..l .

-c -

1 .. . .

. l

.l' g .h *.I>l l *

'. ; . .* . 2.i .~b-. ~~. .

l

. . . . .  ? ? . , % . :. . Q: . .. l

}'.,.,.. ;, ,3..i,.7.a

-  :{

. ..r -

1*4 ', .' 3, . k, .~ ',.,

L.

v.. ?.- ...\;.

l

~ t. 0. . - I .' . ., .g., ~ .2.s

..s

.* , . . . , ,. . ,_. r f I

l 7_ '.% . l . m! u.fl. .-).'.* }-

4

.,- ..l.. .

..t,.<>/[

I g2 g~~ ~--',--'*P"-,----9--y'.,. .

p ..,

--.i

q. .

., . c.i-g ., .

.l. .

.y ,'

. .... ..g.

,t4 , . . . , , . ,. i ..;. ..

i . t .

,0. 4, .. e. i y g .. *1

.". r. ,

. t g n l .

i

. .. .a ....64. .g+ -

e . .

g . . . A,,

l . , g, . e

' '1 , ,

. j 1-l c 7'-

3 . c . .l . .... a

. f, .

._r .v%. .. i... .

7.r.1

Cy

' ~

5,5 88 ,

y ,

Ot.tawa , h5 .

l -

- f Marseilles 5 South 14 B. Rir8' Ottawa g Seneca ,

f el e2

, , PLANT ,

, slTE PROPERTY

. ** Grand Ridge .

Verona Kinsman II. Ransom ,

12 ,

ernan Str'eator 1 -Nearsite I ~

LA SALLE ~

COUNTY GRUNDY COUNTY

~

OVINGSTON COUlJTY 2-Onsite 2 3-Onsite 3 , , , ,, m3 SCALE, , 3 3 4.-Nears.te i 4 5-Onsite 5

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

6-Nearsite 6

~ 7 - Seneca 8 - Marseilles 9-Grand Ridge

~'

- S real0'r LA SALLE COUNTY STATION 11 - Rans0m FIGURE 7.2-2 LOCATIONS OF FIXED ENVIRONMENTAL 13-R0ute 6 at G0nnam R0ad RADIOLOGICAL MONITORING STATIONS .

I 14 -Ottawa i m

- - '2 d - L. _

. 1

\

LA SALLE REVISION 1 {

. SEPTEMBER 1979 TABLE 7.2-1 ,

AQUATIC ENVIRONMENT DOSE PARAMETERS PARAMETER ,

LA SALLE U", water usage, liters /hr 0.042

~4 U , fish consumption, kg/hr 2.4 x 10 1/M" l ,

i I 1 1/M 4

F", ft /sec 1.37 x 10 4

Ff, ft /sec 1.37 x 10 f 24 t, hr***

t", hr 0 97 B - Regulatory Guide 1.109, Revision 1, October 1977, Table f

A-1, column 2 for freshwater fish. See Table 7.1-12.

', F, ft /sec }

F", ft /sec }

1/M" } Not Applicable. No outdoor tanks without overflow pipes connected l

t*,

to other storage tanks.

hr }

D V, gal }

tg ,hr }

f

• • • t (hr) = 24 hr (all stations) for the fish ingestion pathway A t" (hr) = 97 hr (distance to Peoria is 97 miles; flow rate of 1 mph assumed)

~

7.2-3 9

l LA SALLE REVISION 1

. SEPTEMBER 1979 TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY*10 CFR 50 APPENDIX I FOR EACH REACTOR -

TYPE OF DOSE ANNUAL DESIGN OBJECTIVES Airborne Releases Gamma Air Dose ,

10 mrad l

i Beta Air Dose .

20 mrad

~

Whole , Body Dose 5 mrem Skin Dose 15 mrem Infant Thyroid Dose 15 mrem Liquid Releases Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mrem Skin Dose 10 mrem 6

7.2-4 l

, LA SALLE REVISION 1

, SEPTEMBER 1979 l

- TABLE 7,2-3 l STATION: La Salle ,

LOCATION: 6 miles south of Marseilles, Illinois - La Salle County CHARACTERISTICS OF ELEVATED RELEASE POINT ,

1 1

1) Release Height = 112.8 m 2) Diameter = 5.6 m ,

2) Exit Speed = 18.3 ms -1 4) Heat Content = 1.1E4 KCal s-1 l

l CHARACTERISTICS OF VENT STACK RELEASE POINT (NA) _,

l l 1) Release Height = m 2) Diameter = m

'3) Exit Speed = ms-1 ,

t l

CHARACTERISTICS OF G'ROUND LEVEL RELEASE (NA)

1) Release Height = 0 m l

2) Building Factor (D) = m i

s.

METEOROLOGICAL DATA ,

A 400 ft. Tower is Located 300 m SSW of elevated release point, Tower Data Used in Calculations l

l Release Point Wind Speed and Differential Direction Temperature Elevated 375 ft. 375-33 ft.

Vent (NA) ,

(NA)

, , Ground (NA) (NA) 7.2-5 .

. , a SALLg REVISION 1 SEPTEMBER 1979 TABLE 7.2-4 CRITICAL RANGES .

Direction Site Nearest Nearest Dairy Farm Boundary Resident Range "

(m) (m) (m)

N 1022 6155 NNE 1330 2253 NE' 2408 3058 ENE 4450 5311 E . 1996 5150 "_ 8047 ESE 838 2948 SE 884 2736 SSE 838 4506 5 829 966 SSW -

829 2736 SW 610 1609 WSW 509 1448

~

W 509 1448 l WNW 625 1448 NW 732 2736 NNW 848 2414

• Within 5 miles ',

j .'

7.2-6 L

4 LA SALLE REVISION 1

- SEPTEMBER 1979 TABLE 7.2-5

. TERRAIN CORRECTION FACTORS (ht ) *

(ht = 0 to stated Range, Then ht = Given Value)

DIRECTION RANGE _ .h,,1;,

u - O -

IME - 0 NE - O ENE - 0 l

E - O SE -

0 SSE -

O S 8.5 mi 13m SSW -

0 SW 1 5 mi 17m WSW 1.0 mi 17m W 1.0 mi 17m

~

WNW 1.0 mi 17m NW 2 75 mi 17m NNW -

0 0 Within 10 miles t

I 4

7 . 2 l

1 LA SALLE REVISION 1 1 SEPTEMBER 1979 l l

\

I i

e e m O m to e e e e so ao to to so ao a

4 N O. 0 0. . 0 0 0 0 0 0 0 0 0 0 0 0 Omme-en-NcNmenee

.O + m o w - e O c N cc - N w 5 O N v w N2 in ON g -

• nnOCn6Oinin6m@O**O. * = = - ' ' '

- p N co n .- - co 6' 5 * * - - * *-

• - * = ~

u w

.J w a > > b so > c h > > > @ ED @ W cp 5 m M 0000000000000000

.J +.e M N v 6 m > M c w m m to Cn M N O w oI m - w w r- to r- Cn N O O w o m e m

>NN w go O. in. v. Cn. c. N e. . m. e. e. n. w. to. N. m.

.J w e ID N m n

• su m 6 m - * - m - O M

w a

m en . . . . . . . . . . . * . * .

• a 3. m n O to O to to w co e e O ID m to N 80

>' c =w N m o m m m eo n N N

• OONmv =

a Or O n v v m aoaoaotoaoto o c @ b to .

e ew --Nv-O m2 w

O mmoOeeememeeemme e a

'O. 0. .000000 000000 N

e w de w D N in e ao o to N c cp M r 5 *- m w m O+ to e 5 to N m o o r- in m 6 e > O N a < NI g w 0% to. r=. M. an. n. in. o. an. N. M. n. C. aD. 5. m. .

J

• NebM-MN-**NNN-*N O w w W m e a > so so so e r- ce so ao ao to N 5 to ao ao o a m 0000000000000000 m

2+.

w 0E

• m in N O O N r- N (D b O v to w w

• oOt-o*NN-N D e w o N to (D e > NN w w xo - .- .b. O.N. e.in.m. m.io. v. . N. O.M. N.

w w

• en v n @ ~ Cn 6 @ m Cn - - m Cn p .J O in W O - >

E w .

w a .J ce c me . . . . . . . . . . . . . . . .

> w 3m N O co O e ao e so Cn m O e m in N co > d x =w NmommmenNN-OONM, ,

e O == 0> 0 m w w m ao so to to co e e o to r- e 3 e 2 2 4w --Nw- in .C N O a2 e u

• > w M c6 6 w g, so a

OOOOOmOOOOOOOOOO -*

so W b J m 4.N.

---

O.

e e e e e .e ....i e e s O e

e O mMOWMN@-Nmenceme O

< *)

• N n w w c O so co w w w e e tn N N n O q

-X CD. O. s. ce. co. *. n. iD. w. N. cp co. . m. w. to. N p t

• c%* . gg m e v Neo- @ v m b @ toe win h g x g y O @

in e H 3 x 4 a M u .C e w e nn . . . . . . . s es u I .J N. O . .e .O. to. .to.ew oO e m o N es. - M c w 3. . Crw N m o o m m co NN-OONMw N c.

O cr O> c.-

s <w 0

-.Nw-m. w w m to so -ao tu cc in o 40 r- so .O -

• O a mE O U y w < *4 M O u > .O 2 <

a to to to ao to to to so ao to co to so to to su < t c u

4 O C in m. O. 0 0. C. 0 0 0 0 0 0 0 0 0 0 0 0 g g O w ++ Ncovnebwecoc-ece J g N 0 02 o w N,5 N m O m w o m e c o m o e . g x w sN

> xu o. v. . n. n. . N. N. N. o. w. m . e. . m. .o e >

t < w NNNNnneNNNN---N- e +

l > in O $ >%

I W w J W tea

! .J O @

w a g y e 'm"* . . . . . . . . . . . . . O " ~

E5 Ok 8 88888 888888 so no e sotoso to so 60 to so to w .D T 4w NnNwNNNMNNNN NnM X C Cr X

• cc w w $4 W w4 Q 8 "m 8 U

.R.e e

> ., w w w w 3 3 3 w .C T U 2 2 w 2 w m w in m e 3 in 3 2 3 .J u O l W 22w W to O MM3 32 J W be i tr 4 gg g1. '

I O == en

• l CD + <

l 7.2-8'

l '

LA SALLE REVISION 1 {

. SEPTEMBER 1979 l

~

TABLE 7.2-6 (Cont'd)

LA SALLE COUNTY 1&2 ,

AVERAGE WIND SPEED FOR EACH RELEASE MODE Downwind Wind Soeed (m/sec)

Direction Elevated Release N 8.2 NNE 8.2 NE 7.9 ENE 7.7 E 8.0 ESE 8.2 SE 7.5 SSE 6.8 l l

S 6.1 SSW 5.5 SW 6.1 WSW 6.6 W 6.9 WNW 6.9 NW 7.1 NNW 7.7 o

7.2-9~

1

- . l l

I'. SALLE REVISION 1 I

. SEPTEMBER 1979 i

1 l

memOOmOOmommmmme w

m 4

0 0 0. e. ~Oe mmwemN->mewwOm=N e s -O-000004 e e e e e a, w MN-WMNomOW@mn-me J

N gw O. m. w. e. m. o. m. m. *. ~. O. O. O. M. O. N.

• 02 MN*NM*Wn*mvNNNne o

X .

% COOOOOOOOOmOOOOm e

• w

---

~~~~~O*---O. .

. w w e e e e e e e e e e e e e e e e s 0 04 @@wcMwa-movemwNM

= N ww womOcemmenNmmNew 3 O Kw

m. n. e. m. e. m. o.. m. m. O. &. W. m. N. N.

ww m s Em 4

emwnnwM-wn*>mmb-2 3

= = 0000000000000000 I 2 0 ---------*------ ---

> ( ww e e e e e e e e e e e e e e a e

= =e

> 44 m=mm-eon-m>>m-ow comowomemNmO->me -

3 -

< >w e w ws . o. n. e. n. e. w. o. n. n. e. e. @. *. m. m.

2 E aw e n ts N n M N

• n n e v n e n c Q wm

= >

> w a

. 4 w y a me . . . . . . . . . . . . . . . .

O 4 3a MmmcommNephmommN s w =w mm-OmvwommewmOOm 2 OH NNNo-enwmenemocN s (w NNnwegweNN--*---

4 EI J B w w 5

4 w 0000000000000000 w

a e e e e e e a e e e e e e a e e e e 4 membecommmmmmmwn >

4 w men--womONommenc 6 W w Oa e X

• 2w N. m. e.w w n. n. e. m.@.w. w. n.e.=. m N OM MMNNMMN-***---eN 6 N. D e M N 2 +

4 I 00000000--O**=*O m w w w -------------*-- 8 J 3 - e e e e e e e e e e e e e e e e e  %

e O w C4 W w M m

• La m e m > O m m M w - O 4 u Oww emN-memnommmONew n

> . N xa N M O =w m. e. n* w

• e. e . O. m. O. O. n. b. W. o. o. e a Ig --------mm-megg-

= 3 e X 0 0 00*O000--*------

--~~~~~------==*

e 0 >

M M ww e e e e e e a e e e e e e e e s  %

w s >m wmwNMmenkbO-wmom

• a = 44 wn-moo-Ommmmmmme N 4 I DW N. *. w. . W. W. O. N. O. w. m. w. o. m. . m. O w wa -

2 H aw --m---=memm>mmom M wn 4 W w >

I a 4

> 4

• O w ee . . . . . . . . . . . . . . . .

( >

4 Z sa ww Q>

65bb5bbb>>555555 wwwwwwvvvwwwwwww 0000000000000000 J

4 u

O dw mammmmmmmmmmmmme =

N 23 o O w O J

2 O i 00 a 2* O

=> w r U W W W W D 3 >

w 22WZwwwmmm3m3 3 w l 2 ZZW wmW mm3 Z I E*c w w

N W

d J

"M 4

4 J

e 7.2-10

e LA SALLE REVISION 1

. SEPTEMBER 1979 o

8880888888888888 emmONOnee@ONonN@

.uw

<e sowomwnnecomemme w

m om %. m.*.N.O. N. N.o.@.N.O.M M.w.m. .w.

< U mcNamemmem***mam w 3 J w 5 a O.O.O.b.O.O.O.O.O.b.O.O.b.b.b.b.

J > WWebmMNOewmNtoom w Os womm&>>*wo-wNONw

> c e. b. w. m. e. n. v. @. O. O. c. c. e. *. M. C.

w <

mehenemme*******

O Me * * * * * * * * ********

a Da NOmO@ewemSO@meNe O aw NmommmenNNa OONmv O> Onevemememcocche I <w e* Nwe n unw a

a 5m@@@mee x a U

e>>>>e9>000000000 0000000 a w mw M*NomMcNwomNOcm .

O e <m WOhmmmNeocNewmN a < mN N.W. M. w. m. W. O. O.m. m. O. N.m.@. O.

w y. .

e J U *mwncawmWW""*@**

2 w 3 O a w

. G 4

8888888888888888 m 2 > emNwNeeOomNewMme w >N mNwcmomemwnem>MO w > c m. e. m. b. o. m. e. m. me O. *. m. w. o. *. ee N m w <

e O w a "mwNW**mWhe***** J

• O O E w W > < k W l > 3 a J N X O mm * * * * * * * * * * * * * * * *

< w Da NomOcewemmommene >

. O x -w NmOpmmenNN*OONew w 6 u - CH OmvwommmmmWomede w E dw **Nwe m W E M1 M

= M J D w M Q J J

a >>>>>>>>>>>>>m>> e N m

• 4 4 w aw U C.000000000000000 eme**ODOwOw-OD>>

6 N

y J >

- w .m Owwwmwnsmo-ownNm O

M

• 2 m m% N w < @w m. *. O. m. e. d. e. w. C. *. m. O. *. o. c. h. p a w U NNN*NN"*NNNNNe**

J D e w w w

> a N

@cceccccccccccc@ e

= 0000000000000000 6 e a m e  %

b x > @MOe@@@NONM@mm*e

• k U @N 05cmwneN*mWoomme N O 4 O O

> < e. M. N. O. N. O. m. c. M. M. m. M. M. e. c e.

X M & NNNNMM**NNNNNe**

D w I 4 I O w >

w w 4 x > a O

< e me . . . . . . . . . . . . . . . .

E > Du NOmOwmwe@mOmmene J I w =w NmommmmmNNa OONmv 4 J o> Omvwemmmmmecocom u l w ww e*New w am O w 0 J

O O w e g

u

> . . . . . . . . . . . . . . . . O U a NOeO@ewommOmmene w

=mw NmommmmmnN*CONmv >

u > Omvwommmem@coche w edw **NT* I Mw2 wuw W E4 &

w 9-

-> www www >> > >

w J

U ZZZZwmeeWWWe> 2 J w 2 w W M M = 4 E M Ow 4 CO J O

7.2-11 -

o TABLE.7.2-8 (Cont'd) '

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXE0 MODE (VENT) RELEASE GROUND LEVEL RELEASL DIRECTION AREA 80UNO RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR *

(METERS) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAO/VR)/(UCI/SEC)

N 1022. 1022. 1.438-04 7.665-05 1022 1.040-04 f.022-04 1022. 5.816-04 2.999-04 p 4 NNE 1330. 1330. 1.145-04 6.100-05 1330. 1.473-04 7.775-05 1330. 4.292-04 2.217-04 7 NE 2408. 2408. 6.027-05 3.197-05 2408 7.299-05 3.849-05 2408. 1.787-04 9.267-05 Y ENE 4450. 4450. 3.374-05 8.722-05 1.780-05 4.628-05 4450.

1996 3.794-05 1.047-04 1.996-05 5.527-05 4450.

1996.

7.695-05 2.617-04 4.007-05 1.358-04 h

H E 1996. 1996. t-e hJ ESE 838. 838. 1.915-04 1.021-04 838 2.585-04 1.363 838. 8.036-04 4.141-04 t4 SE 884. 884. 1.292-04 6.887-05 884 1.708-04 9.010-05 884 5.459-04 2.812:04 M SSE 838. 838. 1.299-04 6.933-05 838 1.628-04 8.607-05 838. 5.638-04 2.904-04 5 829. 829. 1.221-04 6.507-05 829. 1.456-04 7.705-05 829. 4.859-04 2.507-04 SSW 829. 829. 1.514-04 8.070-05 829. 1.730-04 9.176 829. 6.214-04 3.205-04 SW 610. 610. 1.875-04 1.000-04 610. 2.264-04 1.198-04 610. 8.484-04 4.363-04 WSW 509. 509. 1.723-04 9.191-05 509. 2.204-04 1.164-04 509. 8.171-04 4.196-04 W SCn3. 509. f.682-04 8.973-05 509. 2.181-04 1.150-04 509. 8.254-04 4.230-04 WNW 625. 625. f.246-04 6.G47-05 625. 1.616-04 8.527-05 625. 5.801-04 2.978-04 NW 732. 732. 1.572-04 8.391-05 732. 1.976-04 1.044-04 732. 7.297-04 3.750-04 NNW 848. 848. 1.327-04 7.076-05 848. 1.720-04 9.078-05 848. 5.865-04 3.015-04 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL tn A MM

'U <l

• -3 H pm

.c n tn O MZ lC H

> s ,,

H

• e. .i 6 > %a 4 0 .l ..

W r . e4 '..

. 6 .. .

4 14 9.

- LA SALLE REVISION 1 SEPTEMBER 1979 O

8888888888888888

. zw meeOn-nwn--Ome-e i de omchemoenwemeONN i w

. m ao s_ m. e. n. e. m. e. r. .

. n. n. . w. o. m. O. ,O.

- o en-e-mone,econc w 3 -

J w

> 888.B.888888888888 a > comwnONOenemnn-w w

asc envemneme-nom--O w q n. m. O. w. m. e

. o w N m N ,. .e.-me.eem

m. N. n. o. n. e. m. n. . c.

g m 3m NOeoemvemmOOmeNe C = ka NnomenenNo-OONew "

op Onewommmecommeme e

<w --Nw-EE

e. -

o 8855588888888888 .

a w ww e

mnecewcomww>neco mem@mboenehmenen

.O . 4., s_m w 9. . . . N. o. n. n. . n. . o. c. N o. n.

. w a ...n.--.----. ..

W W 3 O u w

-G 1 m

g a

w 2

a 88.B.B.888888888888 Oen-mmenneeNmhem

• w >s owwenmoennew-OmW w > O M N e w a n.o.n.e n.*.*.O.n.N.e.>.>.O.w.

g e O w a N-mO*@NN*NNNNNNN J

• O E w O w >

U w

w s -

w a

3 O ne ................

< w 3m NomoemwemmommcNe >

m c x -w NnocenenNN-OOnnw w I u = ck Onwwmememmecomes w E gw --Nw- m N w I ME b

. s J

3 a

w n b 4 a em>Wheecheece@ee e m ~ 0000000000000000 >

N 4 w U N s > ww wcN~nonNoboce O* O 4 = wwm comnemvemenme me n m 2 o cN c om e. n. e. m. . m. O. O. m. n. o. n. n. . n. o.

N

< =

g w y *@wnhw-wp-wwww-w p

b w s

w 3

w s

a N a

ce>>ecceeeeeeeee e o

e - a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0. O. N 6 E > --meNewebwNvNmwk =

6 u mN mawncom-m->c-New N O 4 o e. m. o. b. . m. c h. m. o. w. n. N. W. O. W. O M E **S**N--eNNNN*N-w I 4 o w >

m w (

x * ^

Q q g ne ................

E > 3m NomOcewemmOmmmNe J w ww NnOconenNN-OONnw g s QM Onwvemmmmecceebe u w 4w -*Nw- =

EE O w O d

. O O w - a

> m ................ O uom NOecemvemmOmmene w wow NnommmenNN-CONne >

m > Onwwmememecoceme w M4w **Nwe X WwE wmw w

( E4 M 1

g e i

. 9-

-- www www >>> >

W s

l O 2222wemeedom3 2 a l w 2 m W @ M 3 4 a m

• 4 Q J 7.2-13

TABLE 7. 2-0 (Cont'd)' -

. LASALLE COUNTY 182 ,

MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 87 DOWNWIhD RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUDD. LEVEL RELEASL DIRECTION AREA BOUNO RADIUS S SBAR RADIUS V VBAR RADIUS G CBAR *

(METERS) (METERS) (MRAD /fR)/(UCT/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UC1/SEC)

N 1022. 1022. 6.081-04 4.444-04 1022. 7.471-04 5.442-04 1022. 1.780-03 1.285-03 p

[ NNE 1330. 1330. 4.687-04 3.424-04 1330. 5.593-04 4.074-04 1330. 1.287-03 9.295-04 7 y NE 2408. 2408. 2.356-04 1.720-04 2408. 2.700-04 f.966-04 2408. 5.395-04 3.899-04 g 9 ENE 4450. 4450. 1.236-04 9.011-05 4450. 1.344-04 9.784-05 4450. 2.247-04 1.626-04 Ed E 1996. 1996. 3.445-04 2.514-04 1996. 3.916-04 2.853-04 1996. 7.848-04 5.673-04

" ESE 838. 838. 8.102-04 5.923-04 838. 9.967-04 7.261-04 838. 2.451-03 1.769-03 M SE 884 884. 5.514-04 4.031-04 884 6.671-04 4.861-04 884. 1.679-03 1.212-03 D1 SSE 838. 838. 5.399-04 3.947-04 838. 6.312-04 4.602-04 838. 1.672-03 1.207-03 5 829. 829. 5.106-04 3.732-04 829. 5.758-04 4.200-04 829. 1.484-03 1.071-03

. SSW 829. 829. 6.131-04 4.481-04 829. 6.730-04 4.911-04 829. 1.813-03 1.308-03 .

SW 610, 610. 7.94G-04 5.809-04 610. *

'9.027-04 6.584-04 610. 2.543-03 1.836-03 WSW 509. 509. 7.514-04 5.494-04 509. 8.860-04 6.460-04 509, 2.511-0,3 1.813-03 W 509. 509. 7.274-04 5.319-04 509. 8.676-04 6.326-04 509. 2.510-03 1.811-03 WNW 625. 625. 5.393-04 3.944-04 625. 6.429-04 4.687-04 625. 1.784-03 9.288-03 NW 732. 732. 6.563-04 4.799-04 732. 7.693-04 5.610-04 732. 2.157-03 f.557-03 NNW 848. 848. 5.580-04 4.080-04 848. 6.677-04 4.867-04 848. 1.754-03 1.266-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL fn 'p MM

'tf <*

HH (n

H O

M 2:

30 H

H i W

• J W

i .* *

• e

LA SALLE REVISION 1

. SEPTEMBER 1979 mmmenMmmmmmmmmmm

. ww 0 0000000.000000000 emmbeccom--OO-mm

<w Nm-mewNomomonomN u mN

. y om N. m. o.v. w. w. C. O. c.w.o.m.m.N. m. N.

< u MNew*wmmNmwwwmmm h 3 a N menwmmmmmmmmmmmm a a 0000000000000000 a

W > MOmecmb-omem-Omb w cN wmNomv>cwo--c-mm

> O N. .m. e.m. e. m. o. n.w.

.m.m. n.N. N.

w <

a a weem-mmwnwommwew I

g w 3 *

• 0 0m ==**************

E Ds NOmoemememommene C =w NmommmmmNN-OONew Ce Omwwmmmmmmmmmebe = * - '

<w --Nw-e mE e w a m m w w w m'e m m m m m m m m e ~ ~ - -

x ^

0 0 0 0 0 0 0 0 0. O. 0 0 *0 0 0 0 U e e m w ww commONN-MOwnew-O O m em -omNmecNOmmmw-em - - -

w < mN w y. w. C.N.o.m. e.N. N. . m. o. c. c. N.w. N.

m a u eecNyeee-weeeeee e .

W w 3 O E w

> N mmwwwmmmmmMMmmMn -

U a a 0000000000000000 a < w a T 6 2 > -mme--->m>NMOmew

. w >N womwNewemNomemme w > Q 4 N e w < m n. e. m. m. s. c. o. v. e. ce. *. *. m. m. e g e O w & ~~cemN-**-NNNew J ,

- C O E w O O - >

Q w

E 1

a W

J 2 3 Q wm ................

3 4 w Da NOmocmwemmom@mNm >

m O c x=w NmommmmmNN-OONew w I O =Ce Omvwommmmecomene w E<w e-Nw- m N w I mE o e J D w n J J b < a n e w w e m m m w.m m m m m m m e m

• 0000000000000000 m -

p q w o N 4 J > aw omoebwwcMmON5mmm O

= w em domm-NeocNowOmme m Q z e mN 4 0- . N.o. m. e. m. O. O. m.N ......

ewwCNO N

m 4 a w o emwNo---m ......

V w J

w D

e

> E N

^

MMwwwmMmMmMMMMMM c

= 0000000000000000 m m a u s e e N h Y > cmcNeom--NommwNb -

6 U MN NmmmevmemmocNwm- N O < O O

> < m. . O. N.W. O. m. m. N m. O.m a. m. o.w.

3 m g wegegN--e-N-e-w-D w 1 4 X Q w >

m w <

x > a O

< < We ................

E > Da NOmocmemmmommene J w =w NmommmmmNN-OOnew <

J oe Omvwommmmecoccom u w qw e-Nv- =

EI O w O J

O O w a a e > w ................ O com NOmocewemmommmNm w wmW NmommmmmNN-OONmv >

k > Onewommmmmemoche w

>(w ~~Nwe E mWE wkw w E4 >

m i

9-

-> www www >>> >>>

=

J u zzzzwememomozzzz J

[

w 2 w w m o a 2 2 <

[

k m 8=O J l

7.2-15

TABLE 7.2 .8 (Cont'd) .

LASALLE COUNTV 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR MR 89 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELE ASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G G8AR *

(METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)

N 1022. 1022. 6.786-04 5.005-04 1022. 8.728-04 6.410-04 1022. 1.992-03 1.450-03 p 4 NNE 1330. 1330. 4.270-04 3.149-04 1330. 5.392-04 3.960-04 1330. 1.170-03 8.519-04 7 g NE 2408. 2408. 1.232-04 9.078-05 2408, 1.504-04 1.105-04 2408. 2.940-04 2.142-04 g l ENE 4450. 4450. 2.630-05 1.935-05 4450, 2.999-05 2.202-05 4450. 4.808-05 3.510-05 Fd E 1996. 1996. 2.265-04 1.669-04 1996. 2.703-04 1.985-04 1996. 5.104-04 3.720-04 m ESE 838. 838. 9.713-04 7.165-04 838. 1.250-03 9.180-04 838. 2.915-03 2.123-03 M 5.851-04 884 1.910-03 1.390-03 U3 SE 884 884 6.310-04 4.655-04 884 7.964-04 SSE 838. 838. 5.533-04 4.082-04 838. 6.826-04 5.017-04 838. 1.665-03 1.212-03 5 829. 829. 4.984-04 3.676-04 829. 5.891-04 4.332-04 829. 1.462-03 1.064-03

. SSW B29. 829. 5.179-04 3.820-04 829. 5.982-04 4.400-04 829. 1.478-03 1.076-03 .

SW 610. 610. 8.875-04 G.547-04 610. *

• 1.055-03 7.756-04 610. 2.731-03 1.989-03 WSW 509. 509. 9.934-04 7.330-04 509. 1.215-03 8.937-04 509. 3.258-Q3 2.372-03 W 509 509. 9.133-04 6.739-04 509. f.147-03 8.434-04 509. 3.113-03 2.266-03 WNW 625. *625. 6.671-04 4.923-04 625. 8.308-04 6.107-04 625. 2.201-03 1.602-03 NL' 732. 732. 6.690-04 4.936-04 732. 8.424-04 6.191-04 732. 2.157-03 1.570-03 NNW 848. 848. 6.055-04 4.467-04 848. 7.674-04 5.638-04 848. 1.843-03 1.342-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL tn tt wr 6% H D1 03

3. H tn O MZ A3 H

-H to 4

TABLE 7,2-8 (Cont'd) .

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FCR MR 90 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE _ GROUND L{ VEL RELEASE _

DIRECTIDN AREA BOUND RADIUS S 58AR RADIUS V V8AR RADIUS G G3AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /vR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC)

N 1022. 1022. 9.738-05 6.981-05 1022. 1.348-04 9.601-05 1022. 3.031-04 2.138-04

%J NNE 1330. 1330. 3.526-05 2.527-05 1330. 4.800-05 3.419-05 1330. 1.036-04 7.307-05 h

• NE 2408, 2408. 1.552-06 1.112-06 2408. 2.017-06 1.437-06 2408. 3.976-06 2.808-06 hJ ENE 4450. 4450. 1.111-08 7.939-09 4450. 1.299-08 9.260-09 4450. 2.081-08 1.471-08 U1

[, E 1996. 1996. 5.791-06 1.961-04 4.144-06 1.406-04 1996.

838, 7.210-06 2.685-04 5.137-06 1.913-04 1996.

838.

1.332-05 6.073-04 9.416-06 4.284-04 fl

-J ESE 838. 838. to SE 884. 884 9.875-05 7.080-05 884 1.340-04 9.549-05 884 3.078-04 2.171-04 DJ SSE 836, 838. 8.074-05 5.789-05 838. 1.073-04 7.649-05 838. 2.496-04 1.760'04 S 829. 829. 5.836-05 4.184-05 829. 7.640-05 5.446-05 829. 1.775-04 1.252-04 SSW 829. 829. 5.203-05 3.729-05 829. 6.493-05 4.631-05 829. 1.480-04 1.045-04 SW 610 610. 1.724-04 1.236-04 610. 2.240-04 1.597-04 610. 5.466-04 3.855-04 WSW 509. 509. 2.701-04 1.937-04 509. 3.623-04 2.583-04 509. 9.256-04 6.526-04 W 509. 509. 2.640-04 1.893-04 509. 3.658-04 2.607-04 509. 9.490-04 6.690-04 WNW 625. 625. 1.462-04 1.048-04 625. 2.021-04 1.440-04 625. 5.095-04 3.592-04 NW 732. 732. 1.268-04 9.097-05 732. 1.787-04 1.273-04 732. 4.373-04 3.083-04 NNW 848. 848. 1.049-04 7.523-05 848. 1.453-04 1.035-04 848. 3.368-04 2.376-04 LASALLE SITE METEOROLOGICAL OATA 10/1/76 - 9/30/78 375 FT LEVEL U1 M

. M3 F3 F4 b2 to 3: H to O D1 L$

53 Fa E'

W

,J S

e

TABLE 7.2-8 (Cont'd) .

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE131M A

DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE _ MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)

N 1022. 1022, 5.171-06 f.843-06 1022. 1.506-05 3.184-06 1022. 9.205-05 1.366-05 t1 M NNE 1330. 1330. 4.426-06 1.509-06 1330. 1.072-05 2.371-06 1330. 6.609-05 9.985-06 38 g NE 2408. 2408. 3.332-06 8.918-07 2408. 5.649-06 1.216-06 2408. 2.488-05 3.942-06 g g ENE 4450. 4450. 2.663-06 5.844-07 4450. 3.338-06 6.840-07 4450. 1.018-05 1.694-06 Fa E 1996. 1996. 4.682-06 1.274-06 1996. 7.730-06 f.708-06 1996. 3.641-05 5.777-06 CD - ESE 838. 838, 6.599-06 2.431-06 838. 1.972-05 4.214-06 838. 1.286-04 1.900-05 t1 SE 884 884 4.388-06 f.629-06 884. 1.259-05 2.741-06 884 8.763-05 1.291.05 M SSE 8?8. 838, 4.146-06 1.632-06 838. 1.055-05 2.503-06 838. 9.261-05 1.361-05 S 829. 829. 4.589-06 1.587-06 829. 3.154-06 2.209-06 829. 7.573-05 1.132-05 SSW 829. 829. 5.308-06 1.957-06 829. 9.403-06 2.520-06 829. 9.912-05 1.479-05 SW 610. 610. 6.104-06 2.351-06 610. 1.374-05 3.387-06 610. 1.430-04 2.073-05 WSW 509. 509. 5.500-06 2.134-06 509. 1.548-05 3.462-06 500. 1.401-04 2.007-05 W 509. 509. 5.506-06 2.103-06 509. 1.623-05 3.512-06 509. 1.483-04 2.090-05 WNW 625. 625. 4.112-06 1.557-06 625. 1.183-05 2.582-06 625. 1.001-04 1.431-05 NW 732. 732. 4.795-06 1.955-06 732. 1.314-05 3.067-06 732. 1.258-04 1.812-05 NNW 848, 848. 4.456-06 1.680-06 848. 1.238-05 2.745-06 848. 9.977-05 1.443-05 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL to MS MM 94 HH in

• H O

M 2:

1. f H

H 2 .

g i e q W

~

TABLE 7.2-8 (Cont ' d) .

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE _ MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA 800ND RADIUS S SBAR RADIUS V V8AR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC)

N 1022. 1022. 2.274-05 1.121-05 1022. 3.868-05 1.563-05 1022. 1.631-04 5.029-05 M 4 NNE 1330. 1330. 1.857-05 9.044-06 1330. 2.883-05 1.192-05 1330. 1.192-04 3.744-05 38

• 2408, NE 2408. 2408. 1.089-05 4.904-06 1.475-05 6.017-06 2408. 4.715-05 1.550-05 ENE 4450. 4450. 7.OG1-06 2.909-06 4450. 8.249-06 3.274-06 4450. 2.021-05 6.943-06 H E 1996. 1996. 1.557-05 7.054-06 1996. 2.074-05 8.576-06 1996. 6.908-05 2.276-05 W ESE 838. 838. 3.001-05 1.491-05 838. 5.121-05 2.080 838. 2.268-04 6.963-05 M SE 884. 884. 2.011-05 t,N t-05 884. 3.334-05 1.368-05 884. 1.541-04 4.713-05 M SSE 838. 838, 2.016-05 1.018-05 838. 3.052-05 1.306-05 838. 1.622-04 4.948-05 5 829. 829. 1.955-05 9.559-06 829. 2.695-05 1.162-05 82.9. 1.352-04 4.198-05 SSW 829. 829. 2.412-05 1.199-05 829. 3.083-05 1.388 829. 1.764-04 5.471-05 SW 610. 610. 2.904-05 1.459-05 610. 4.13G-05 1.801-05 610. 2.470-04 7.424-05 WSW 509, 509. 2.639-05 1.328-05 509. 4.216-05 1.754-05 509. 2.392-04 7.096-05 W 509. 509. 2.598-05 1.302-05 509. 4.271-05 1.747-05 509, 2.488-04 7.242-05 WNW 625, 625. 1.924-05 9.626-06 625. 3.141-05 1.291-05 625. 1.706-04 5.046-05 NW 732. 732. 2.417-05 f.230-05 732. 3.738-05 1.588-05 732. 2.158-04 6.441-05 NNW 848. 848. 2.074-05 1.036-05 848. 3.340-05 1.384-05 848. 1.719-04 5.155-05 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL

0) M MM

'04 8H 0)

H O

MZ W H H

- i n -

n. i e t , N W

e a a

TABLE.7.2-B (Cont'dl .

LASALLE COUNTY 182 ,

MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FDR XE133 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE _ MIXED MODE (VENT) RELEASE . GROUND LEVEL RELEASE.

DIRECTION AREA 80UND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR *

(METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)

N 1022. 1022. 2.329-05 9.006-06 1022. 4.138-05 1.403-05 1022. 1.830-04 5.346-05 M

-J NNE 1330. 1330. 1.928-05 7.397-06 1330. 3.098-05 1.067-05 1330. 1.345-04 3.978-05 >

'g) NE 2408. 2408. 1.163-05 4.236-06 2408. 1.607-05 5.502-06 2408 5.352-05 1.627-05 t ENE 4450. 4450. 7.840-06 2.709-06 4450. 9.213-06 3.114-06 4450. 2.308-05 7.199-06 h) hJ E 1996, 1996. 1.666-05 6.095-06 1996. 2.263-05 7.818-06 1996. 7.857-05 2.?92-05 t<

c) ESE 838. 838. 3.074-05 1.196-05 838. 5.482-05 1.865-05 838. 2.545-04 7.416-05 td SE 884. 884. 2.058-05 8.019-06 884 3.559-05 1.218-05 884 1.725-04 5.012-05 D1 SSE 838. 838. 2.048-05 8.058-06 838. 3.228-05 1.134-05 838 1.819-04 5.277-05 S 829. 829. 2.020-05 7.770-06 829. 2.862-05 1.012-05 829. l.522-04 4.469-05

. SSW 829. 829. 2.474-05 9.629-06 829. 3.242-05 1.179-05 829. 1.988-04 5.834-05 .

SW 610. 610. 2.946-05 1.155-05 610. * '4.342-05 1.542-05 610. 2.754-04 7.909-05 WSW 509. 509. 2.678-05 1.051-05 509. 4.443-05 1.531-05 509. 2.653-q4 7.546-05 W 509. 509. 2.635-05 1.032-05 509. 4.493-05 1.530-05 509. 2.741-04 7.694-05 WNW 625. 625. 1.947-05 7.609-06 625. 3.312-05 1.132-05 625. 1.892-04 5.375-05 NW 732. 732. 2.432-05 9.621-06 732. 3.916-05 1.367-05 732. 2.405-04 6.878-05 NNW 848. 848. 2.110-05 8.241-06 848. 3.539-05 1.217-05 848 1.914-04 5.484-05 LASALLE SITE METEDROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL 1J5 M

M 8H M in 3H tn O MZ W

H H

w

=J W

TABLE 7.2-8 (Cont'd)

• LASALLE COUNTY 152 MAXIMUM DFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE1354 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE _ GROUND LEVEL RELEASE, DIRECTION AREA BOUNO RADIUS S SBAR PADIUS V VBAR RADIUS G GdAR (METERS) (METERS] (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)

N 1022. 1022. 2.872-04 1.776-04 1022. 3.782-04 2.328-04 1022. 9.935-04 6.065-04 M Q NNE 1330. 1330. 2.117-04 1.309-04 1330. 2.699-04 1.662-04 1330. 6.753-04 4.127-04 >

' NE 2408. 2408. 9.634-05 5.948-05 2408. 1.167-04 7.184-05 2408. 2.562-04 1.568-04 M 2.595-05 4450. 4.754-05 2.926-05 4450. 8.430-05 5.167-05 M ENE 4450. 4450. 4.210-05 b E 1996. 1996. 1.482-04 9.149-05 1996. f. 769-04 f.090-04 1996. 3.829-04 2.344-04 h ps ' ESE 838. 838. 3.805-04 2.353-04 838. 5.045-04 3.106-04 838. 1.368-03 8.351-04 t4 SE 384. 884. 2.620-04 1.620-04 884. 3.381-04 2.083-04 884 9.497-04 5.797-04 D1 SSE 838. 838. 2.387-04 1.476-04 838. 2.989-04 1.842-04 838. 8.694-04 5.307-04 S 829. 829. 2.309-04 1.427-04 829. 2.738-04 1.688-04 829. 8.031-04 4.904-04 SSW 829. 829. 2.540-04 f.570-04 829. 2.932-04 f.808-04 829. 8.790-04 5.369-04 SW 610. 610. 3.613-04 2.234-04 610. 4.333-04 2.672-04 610. 1.351-03 8.241-04 WSW 509. 509. 3.G43-04 2.253-04 509. 4.548-04 2.802-04 509. 1.449-03 8.833-04 W 509. 509. 3.415-04 2.112-04 509. 4.358-04 2.683-04 509. 1.404-03 8.555-04 WNW 625. 625. 2.592-04 1.603-04 625. 3.283-04 2.022-04 625. 1.024-03 6.244-04 NW 732. 732. 2.854-04 1.765-04 732. 3.606-04 2.222-04 732. 1.112-03 6.783-04 NPN 848. 848. 2.537-04 1.569-04 848. 3.263-04 2.009-04 848. 9.335-04 5.696-04 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL LD M

M 8H M (n 2l: H tu O MZ N

H H

e 4

,; il) 1llll1l 4

F(nHO8 : H 3

pP 9 d1

. tU

• t1%3 n1 F 1 D lC s)J pu%w l

4445444444444444

) 0000000000000000

. C RE 2829951 65551 1 603 AS 24263351 3658471 6

- E B/ 21 389891 551 891 32.

S GI A C 431 51 53434655454 E U L (

E / 4444434444333444 R ) 000000000000'O000 R

L Y 1 51 2087488879352 E G/ 7G691 86780490905 V D 88406036551 .01 799 E A L R 7521 31 7768f 11 797

. M D (

N U ) -

O SS . . , . . . . . . . . . . . . .

R UR 2080684899099528 G IE 23059383221 00234 DT 0344988888655678 AE 1 1 241 5 RM 3 (

t E 4455544444444444 X ) 0000000000000000 C

R E RE 21 57969090904923 O S AS 51 43437392053099 F A B/ 41 .59992203766242 E VI S L C 1 1 527f f f 1 1 1 111 11 R E U O R (

T / 4445444444444444

) C ) ) 0000000000000000 A T R d F N V/

Y 29853908534781 47

' E 9524787734652469 E V D 60044532041 00273 t 2 S ( A .

n 8 O E R 221 51 32222333222 L o 1 D D O (

M E V

C

(

Y A M

)

- E T M L N M D SS . . . . . . . . . . . . . . . ,

U A EUR 2080684899099528 T 8 O G XlE 23059383221 00234 F

- C IUT 0344988888655678 2 E MAE 1 1 241 5 E M 4M 7

. . L U ( 3 7 L L A P 4555545554444544 8 S ) 0000000000000000 7 E A L

E T RE C - - - - - - - - - - -

707472025641 3575

- - - - - /

0 L I E AS 983396472631 8801 3 B .

N S B/ 0766648931 432420 /

A I F E A SI C 1 84261 999f 1 1 f 91 9

T L U 1

E E (

T R / 4455444444444444 6 I ) 0000000000000000 7 S ) R - - - - - - - - - - - - - - - - /

F K Y 841 9939346031 327 1 F C 5/ 2287301 425527537 /

O A D 0658278871 643728 0 T A . 1 M S R 21 841 211 1 22221 2f U ( M A M D ( T I E A X T ) D A A SS , . . . . , , . . . . , . . . .

M V UR 2080684899099528 L E I E 23059383221 00234 A L DT 0344988888655678 C EKE 1 1 241 I IM G

( O L

DD O EN) R TUS . . . . . . . . . . . . . . , .

O COR 2080684899099528 E IBE 23059383221 00234 T R T 034498888B655678 E TAE 1 1 241 M SEM ER( E RA T I

- N S

- DO NI E IT EEE EEE WWW WWW L WC NNNNESSSSSSSWNNN L NE N E E S S WWN A WR S OI A DO L J%*bJ $I I

4 TABLE 7.2-8 (Cont'd) .

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME CAMMA DOSE FACTORS FOR XE137 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC)

N 1022. 1022. 9.192-05 5.953-05 1022. 1.227-04 7.926-05 1022. 3.048-04 1.960-04 g

-4 NNE 1330. 1330. 5.984-05 3.874-05 1330. 7.806-05 5.042-05 1330. 1.839-04 1.183-04 5s NE 2408, 2408. 1.898-05 1.228-05 2408. 2.376-05 1.535-05 2408. 4.989-05 3.209-05 N ENE 4450. 4450. 4.730-C? 3.058-06 4450. 5.476-06 3.536-06 4450. 9.264-06 5.964-06 M b

to E

ESE 1996.

838 1996.

838.

3.389-05 1.291-04

2. wa-G3 8.360-05 W96.

838.

4.135-05 1.728-04 2.671-05 1.116-04, 1996 838.

8.391-05 4.409-04 5.398-05 2.835-04 h

t4 SE 884 884. 8.501-05 5.506-05 884. 1.112-04 7.183-05 884. 2.927-04 1.882-04 D1 SSE 838 838. 7.478-05 4.844-05 838, 9.532-05 6.161-05 838, 2.566-04 1.650-04 5 829. 829. 6.855-05 4.440-05 829. 8.301-05 5.366-05 829. 2.286-04 1.469-04 SSW 829. 829. 7.181-05 4.651-05 829. 8.471-05 5.478-05 829. 2.331-04 1.499-04 SW 610, 610. 1.187-04 7.686-05 610. 1.447-04 9.355-05 610. 4.158-04 2.673-04 WSW 509 509. 1.300-04 8.422-05 509. 1.641-04 1.061-04 509. 4.873-04 3 *ss-na w 509. 509. 1.195-04 7.743-05 509. 1.553-04 1.004-04 509. 4.654-04 2.991-04 WNW 625 . 625. 8.843-05 5.729-05 625. 1.138-04 7.351-05 625. 3.328-04 2.139-04 NW 732. 732. 8.980-05 5.818-05 732. 1.168-04 7.549-05 732. 3.307-04 2.126-04 NNW 848, 848. 8.141-05 5.274-05 848. 1.068-04 6.903-05 848. 2.822-04 1.814-04 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL EA W MM i e'Ifs4 I

M

, H

! O l

MZ l

N l H H

e

=J i -

l .

t . _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _

TABLE 7.2-8' (Cont'd) .

LASALLE COUNTY 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XEt38 DOWNWIMD RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GRDUNO LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RA01US V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCt/SEC)

N 1022. 1022. 7.062-04 5.142-04 1022. 8.855-04 6.413-04 1022. 2.092-03 1.497-03 7 NNE 1330. 1330. 5.154-04 3.751-04 1330. 6.294-04 4.559-04 1330. 1.419-03 1.015-03 h ha . NE 2408. 2408. 2.283-04 1.660-04 2409. 2.679-04 f.940-04 2408. 5.375-04 3.850-04 1.065-04 7.713-05 4450. 1.766-04 1.268-04 LO i t ENE 4450. 4450. 9.599-05 6.969-05 4450.

• y{ E 1996. 1996. 3.523-04 9.410-04 2.561-04 6.854-04 1996.

838.

4.085-04 1.184-03 2.959-04 8.579-04 1996.

838.

8.082-04 1.869-03 5.790-04 2.052-03 fl tg ESE 838. 838.

SE 884. 884. 6.470-04 4.713-04 884. 7.969-04 5.775-04 884 1.993-03 ,1.425-03 D2 SSE 838. 838. 5.896-04 4.295-04 838. 7.075-04 5.130-04 838. 1.815-03 1.298-03 S 829. 829. 5.682-04 4.138-04 829. 6.521-04 4.733-04 829. 1.680-03 f.201-03 SSW 829. 829. 6.224-04 4.533-04 829. 6.990-04 5.075-04 8'9. l.830-03 1.309-03 SW G10. 610. 8.907-04 6.488-04 610. 1.033-03 7.494-04 610. 2.823-03 2.018-03 WSW 509. 509. 9.041-04 6.588-04 509. 1.083-03 7.858-04 509. 3.038-03 2.171-03 W 509. 509. 8.464-04 6.168-04 509. 1.034-03 7.495-04 509. 2.938-03 2.100-03 WNW 625. 625. 6.430-04 4.685-04 625. 7.797-04 5.654-04 625. 2.147-03 1.534-03 NW 732. 732. 7.058-04 5.143-04 732. 8.540-04 6.193-04 732. 2.317-03 1.656-03 NNW 846. 848. 6.270-04 4.567-04 848. 7.698-04 5.579-04 848. 1.954-03 1.397-03 LASALLE SITE METEOROLOGICAL DATA 10/1/76 - 9/30/78 375 FT LEVEL MM

'O <

8H M to 3ll H to o D3 2:

30 H

i pa u) l

=J l

l

i i

. LA SALLE REVISION 1 l

, . SEPTEMBER 1979 1

l me v mmmmmmmmmen

- 0000000000000000 o

• Ew mm-mN-Ommech-Nmm se w-cNbenenamnwwmm w mN i ,

w Q- e. v ee. m. c. o. m. e c. o. b. b. b. m. m. m.

4 O *-mNmNM-*NNNN"N-w 3 a w w N mmwemmmmmmmmmmmm a a 0000000000000000 m

s > m*meONomvNmmmenN w CN

> 0q m*menomnoecommew w b. o. w. m. N. e. c. o. m. m. m. m. e. b. M. W.

J u NNeM*MNNNNMMMNMN E

w a e mm ................

2 32 NOmocevemeOmecNe U -w NmommmmmNe-OONmv On

,(w Omwwmeamem@mmeom

--Nge

• EE 9 w a wwwwwmewwwwwwevv g a 0000000000000000 0

• k w mw wem*bm**MommmNmm o e em omomOombwmNon-em s e w 3m N. m. o.o.w. n. C. o. b. . N.e.w.n. e. n. .

m J O bcN*w*beche@memb a w 3 O u w

>  % mwwwwmmtwMMMMwmm U a a n

C u

2 a

O.000000000000000 med*mmemm-ev-m-m

. w >N NmNoeOOO-mem-eb-M w > O N e w q . w. . *. m.m. o. c. h. o. m. m.m.e. *. C.

C e O w a *mvNm*-me=***m** a O

- O O a w U

w >

> < E w w > s a a 2 2 O me ................

.W D < w Du NomComwemmommmNe >

D c x =w NmommmenNN-OONms w l u = O* Omvwommmmecomebe N w I ow *-Nwe m w

a I mzw &

D M h d 4 e

m a a wwwwwwwwwwwwwvve e Q000000000000000 >

N <

s w

> 'mW o . N O

E A

z w (M m mN Oo.mOeOM-mmmm**em MC NemmNbN*wmem*M m N

4 = g e- w e. m. m. e. m. m. b. w. w. w. m. o. c. o. m.

. p 6 w u evn-mecomembemoc b J 3 e w w w

> a N a

vwwwwmvwwvmmmewe e

=

e m 0000000000000000 >

a s E X U WN

> -mememommmmewm-w

• b NmWNN-emmemNemmN N O 4 O O

> q - .O. m. m. n. N. N. *. e. M. *. *. C. o. m. e. -

I M & @bmem*meb@-**mme D w I 4 I O 'w >

w w (

x > a O

q ( MM ................

I > 32 NomomewmemommmNe J w =w NmommmmmnN=OONmv <

J w

OW (W

Omvwommmmwemmebe u

• -Nve -

EX U w O J

O O w a a

> e ................ O uom NOmoemwemmomecNe w .

=mW NmommmenNN*OONMw > '

E > Omvwommmmm@moche w '

-==

MWI

--Nv- a WEw w l E4 >

- 1 9.5

-> www www >>> >>> .

a =

u w

zzzzwemmemowszzz 2 w w e m 3 3 2 a

e

= m

( .

80 a i

1 7.2-25 J

l i

i

4 e

9 1

9 e

1 o

4 l

I

l

. LASALLE REVISION 1

. . SEPTEMBER 1979 SECTION 8.0-MODELS FOR SETTING GASEOUS AND LIQUID

• SFFLUENT MONITOR ALARM AND TRIP SETPOINTS

. TABLE OF CONTENTS PAGE 8.1 GASEOUS RELEASES 8.1-1 8.1.1 Station Vent Stack Monitor 8.1-2 8.1.2 Standby Gas Treatment Stack Monitor 8.1-3 .

8.1.3 SJAE Off-Gas Monitors 8.1-4 8.1.4 Allocation of Effluents from Common Release Points 8.1-5 8.1.5 Symbols Used in Section 8.1 8.1-6 8.1.6 Constants Used in Section 8.1 8.1-7 8.2 LIQUID RELEASES 8.2-1 8.2.1 Liquid Effluent Monitors ~ 8.2-2 8.2.2 Allocation of Effluents from Common t

Release Points ,

8.2-3 l

8.2.3 Adminstrative and Procedural Controls for Radwaste Discharges 8.2-3 8.2.4 Determination of Initial Dilution Stream Flow Rates 8.2-4 8.2.5 Symbols Used in Section 8.2 8.2-5 O

4

! i

~ .

LA SALLE REVISION 1 SEPTEMBER 1979 8.0 MODELS FOR SETTING GASEOUS AND LIQUID .

EFFLUENT MONITOR ALARM AND TRIP SETPOINTS

. 8.1 GASEOUS RELEASES Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air con-taining radioactivity are established to ensure that the re-lease limits of 10 CFR 20 are not exceeded. The setpoints

.are found by solving Equations 2.9 and 2.10 for each class of release.

For this evaluation the radioactivity mixture in the exhaust air is assumed to have the composition of gases listed in Table 3-3 from " Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms", NEDO-10871, March 1973, General Electric Company. This mixture of radioactive gases is representative of the activity found at the point of release from the fuel with no radioactive decay accounted for.

Equation 2.9 is rewritt'en using the fractional composition of each nuclide, f , and a total release rate, O , f r station f t vent stack

• releases (the principal point of release of ventila-tion exhaust air containing radioactivity):

1.11 < 500 "

s Q ts I L

fi) yr (8.1) f f

Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.

• The term " vent stack", as used in this section, is to be considered synonymous with " stack" as used in Section 2.1.

x 8.1-1

~ .

LA SALLE REVISION 1 SEPTEMBER 1979 Q ts Total Release Rate, Vent Stack Release (pCi/sec)

The release rate for all radionuclides due to p station vent stack release.

Q is

• O ts i

• Equation 8.1 can be solved for Q t f r re ease limit determinations.

Similarly, Equation 2.10 can be re-written: ,

Lg (X/Q)sO ts fi exp(-A R/3600u s) +

i

i .

1.11 S gQ ts fi < 3000 "y[" (8.3)

Equation 8.3 can be solved for Q and a cor esponding release ts limit be determined. The most conservative release limit l

determined from Equations 8.1 and.lB.3 will be used in selecting the appropriate alarm and trip setpoints for a vent stack release.

The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.

Surve'illance frequencies for gaseous effluent monitors will be as stated in Table 4.3.6.11-1 of the Technical Specifications.

Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.

8.1.1 Station Vent Stack Monitor j Releases of radioactive noble gases from the station vent I

stack release point are monitored by an offline monitoring system consisting of two instrument channels, each of which uses a G-M tube sensing element. Samples of the effluent stream are taken by an isokinetic probe just prior to' dis-charge into the atmosphere. Gas flow through the monitoring system, located largely on panel 0D18-P001, is assured by the ram effect of the gas on the probe tips and by the vacuum pumps through a constant flow network. j 8.1-2 ,

l

LA SALLE REVISION 1 SEPTEMBER 1979 Each monitoring channel consists of a G-M tube detector, a shielded sampli'ng chamber, a pre-amplifier, and a log count rate monitor. The log count rate monitor includes an integral power supply, for providing high voltage to the detector, and trip relays, whose output initiates h,igh radiation alarm annunciators. The channels share a common two-pen recorder.

The recorder, alarm annunciators, and remote control switches,

'for the station vent s' tack monitoring system, are located in the main control room. The sample panel, with pumps, detec-tors, and local controls, is located in the auxiliary building on elevation 815 feet just outside the turbine building exhaust fan room.

Power is supplied to the station vent stack radiation monitors from the Unit 1 125-Vdc battery systems via inverters. The monitor display has logarithmic scale with a range of 10-1 6

to 10 counts per second. The equipment identification numbers for the monitors are OD18-K602A and OD18-K602B.

8.1.2 Standbv Gas Treatment Stack Moni~ tor Release of radioactivity from the standby gas treatment system (SGTS) stack is monitored by the SGTS monitoring system. Each SGTS monitoring channel consists of a beta sensitive scintillation detector for particulate; a beta sensitive scintillation detector for low-range noble gas; a beta sensitive scintillation detector for high-range noble. gas; and a gamma sensitive scintillation detector for iodine. Provisions are made for system inlet and outlet grab samples.

The monitoring system uses a microprocessor to analyze the data from the beta and gamma scintillation detectors. This micro-processor performs background subtraction and compares the radi-ation values against operator entered alarm limits. A four-pen j strip chart recorder records the monitoring system output.

Alarms are located in the main control' room.

8.1-3 e

LA SALLE REVISION 1 SEPTEMBER 1979 Power is supplied to this monitor subsystem from Division 2 power. The equipment for each monitoring channel is skid mounted and located on the 786 ft 6 in. elevation in the auxiliary building.

8.1.3 SJAE Off-Gac Monitors The steam jet air ejector (SJAE) monitor subsystem continually measures and records the gamma radiation in the off-gas as it is drawn from the main condenser by the steam jet air ejectors before it passes through the holdup line and carbon beds enroute to the station vent stack.

A continuous representative sample is drawn from the off-gas system via a stainless steel sample line. A 14 cc serum vial is inserte'd into the sample chamber, evacuated, then filled with a representative sample of off-gas. This sampling equip-ment is located on panel 1D18-J034 (2Dl'8-J034) .

This monitor system consists of two channels. One channel contains a gamma sensitive ionization chamber and a linear radiation monitor and the other channel contains a gamma sensitive ionization chamber and a logarithmic radiation monitor. The ion chambers sensitivity is 1 to 10 6 mR/hr. The gamma sensitive ionization chamber RE-lD18-N002 (RE-2D18-N002) is connected to the logarithmic readout channel. This channel has alarm functions but no trip functions.

Power'is supplied from Unit 1 (2) 125-Vdc power supply via inverters and from the 120-Vac instrument bus for the recorder.

The gamma sensitive ionization chamber RE-lD18-N012 (RE-2D18-N012) is connected to the linear readout channel. Power is supplied to this channel from Unit 1 (2) 24-Vdc power supply and from the 120-Vac instrument bus for the recorder. Both channels measure the radiation levels in the off-gas and their recorders are located in the control room.

t 8.1-4 -

9

. LA SALLE REVISION 1

. . SEPTEMBER 1979 8.1.4 Allocation of Effluents from Common Release Points .

Radioactive gaseous effluents released from the plant vent stack are comprised of contributions from both units. Estimates of noble gas contributions from each unit will be allocated by considering appropriate operating conditions and measured SJAE off-gas activities. A11ocation of radioiodine and radioactive particulate releases to a specific unit is not as practical, and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation will be made using reactor coolant iodine activities. During unit shutdown or periods of known major -

in-plant leakage, the apportionment will be adjusted accordingly.

The allocation of the effluents will be estimated on a monthly basis.

O e

O e

8.1-5 -

l

\

LA SALLE REVISION 1 SEPTEMBER 1979 8.1.5 Symbols Used in Section 8.1 .

SYMBOLS NAME UNIT Q ts Total Release Rate, Vent Stack Release (#Ci/sec) 3g Gamma Dose Constant, Vent Stack Release (mrad /yr per #Ci/sec) fg Fractional Radionuclide Composition Lg Beta Skin Dose Constant (mrem /yr per #Ci/m )

(X/Q)g Relative Effluent Concentration' (sec/m )

Vent Stack Release

~

Ag Radiological Decay Constaht (hr )

R Downwind Range (m)

'u s

Average Wind Speed, Vent Stack Release (m/sec)

Qis Release Rate of Nuclide i, Stack Release (#Ci/sec)

Sg Gamma Dose Constant, Stack Release (mrad /yr per Ci/sec) 9 e

8.1-6 e

LA SALLE REVISION 1 SEPTEMBER 1979 8.1.6 Constants Used In Section 8.1 I

• NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) i I

3600 Conversion Constant (sec/hr) .

1 i

e 4

4 9

8.1-7

( . .

. LA SALLE REVISION 1 SEPTEMBER 19'i9 8.2 LIQUID RELEASES ,

. Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestr.icted area. The concentra-tion limit (Clim) in the discharge line prior to dilution in the initial dilution stream is: ,

d p""* + p"r"* I*I Clim = MPC pr max .

C lim Limiting Concentration in Discharge Line (uCi/ml)

The maximum concentration in the discharge line permitted to be discharged to the initial dilution stream.

MPC -

Weighted Maximum Permissible Concentration ( Ci/mi)

The lowest maximum permissible concentration calculated using liquid effluent isotopic data.

F max Maximum Flow Rate, Radwaste Discharge (ft /sec)

The maximum flow rate of radwaste from the dis-charge tank to the initial dilution stream.

d F Average Flow Rate, Initial Dilution Stream (ft /sec) e i

The average flow rate of the initial dilution I stream which carries the radionuclides to the l unrestricted area boundary. l Surveillance frequencies for liquid effluent monitors will

,s 1

be as stated in Table 4.3.6.10-1 of the Technical Specifications.

l .

Calibration methods will be consistent with the definitions

! found in Section 1.0 of the Technical Specifications.

8.2-1

LA SALLE REVISION 1 I

, SEPTEMBER 1979 I 8.2.1 Liquid Effluent Monitors i

The radwaste discharge li'ne, Unit 1(2) service water effluent header and Unit l'2) RHR service water effluent headers are continuously monitored for radioactivity by an offline mon-itoring system,which uses a NaI (T1) activated scintillation detector. Liquid effluent flow through each monitoring system is assured by a pump and a flow control valve located on local sample panels.

'. Each monitoring system consists o'f a scintillation detector, r- ..-.-

shielded sampling chamber, a preamplifier, and a log count rate monitor. The log count rate monitor includes an integral power supply, for providing high voltage to the detector, and trip relays, whose outputs initiate high radiation alarm annunciators. In addition, the radwaste discharge effluent monitor's trip relays initiate isolation of the liquid radwaste discharge header.

The service water effluent monitor provides a signal to a two-pen recorder which it shares with the RBCCW process radiation monitor.

The RHR service water effluent monitors share a common two-pen recorder in the main control room.

The radwaste discharge effluent monitor provides signals to a recorder in the main control room and a recorder in the radwaste control room.

1 All the process liquid monitors have logarithmic scales with I a range of 10-1 to 10 CPM. The monitors are powered from 6

the Unit 1(2) 125-Vdc batteries via inverters, with the excep-tion of the radwaste discharge monitor which is supplied from a local 120-Vac source through a d-c power supply.

. 8.2-2

LA SALLE REVISION 1 SEPTEMBER 1979 The equipment identification numbers for the monitors are OD18-K606, radwaste monitor; 1D18-K608 (2D18-K608), service water effluent monitor; 1D18-K604 (2D18-K604), RHR service

. water A effluent; and 1D18-K605 (2D18-K605), RHR service water B effluent.

8.2.2 Allocation of Effluents from Common Release Points Radioactive liquids released from the radwaste treatment system are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radio-activity between units. Consequently, allocation will normally be made evenly between units. During refueling outages or periods of known major in-plant leakage, the apportionment will be adjusted accordingly. The allocation of the effluents will be estimated on a monthly basis.

8.2.3 Administrative and Procedural Controls for Radwaste oischarges Administrative and procedural controls have been designed to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits.

The discharge rate for each batch is calculated by a technician and then independently verified by operating staff personnel.

All liquid radwaste discharges will be from one of two river discharge tanks, .lWF05T or 2WF05T.

The keylock hand switch, OHS-WF048, used for selecting high i

or low discharge flow is kept locked except when discharging.

l The key for this switch and the locked valves is under the administrative control of the Shift Engineer.

l .

A documented valve checklist is prepared for each' batch discharge.

The proper valve line-up is made by the Operator and rechecked by the Radwaste Foreman. The actual discharge is authorized by the Shift Engineer.

8.2-3 ,

. LA SALLE REVISION 1 SEPTEMBER 1979 1

The system is equipped with a radiation trip point which alarms and initiates automatic valve closure on the radwaste discharge line to pr5 vent the violation of 10 CFR 20 limits.

1 8.2.4 Determination of Initial Dilution Stream Flow Rates '

For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine  ;

the flow rate of the initial dilution stream. This instrumenta-tion will be operated and maintai.ned as prescribed by the Tech-- -- ..

nical Specifications. For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve position indication.

1 l

l l

1 l

l I

8.2-4

~

~

LA SALLE REVISION 1

• SEPTEMBER 1979

- 8.2.5 Symbols Used In Section 8.2 SYMBOL . NAME -

UNIT C yg, Liquid Release Limit (FCi/ml)

MPC Weighted Maximum Permissible (#Ci/ml)

' Concentration of Radionuclide Mixture .

F,3x Maximum Flow Rate, Radwaste (ft /sec)

Discharge F

ve Average Flow Rate, Initial (ft /sec)

Dilution Stream O

6 0

% g

, 8.2-5 -

e