ML19224D762

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Offsite Dose Calculation Manual
ML19224D762
Person / Time
Site: Rancho Seco
Issue date: 05/31/1979
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML19224D755 List:
References
TR-790531, NUDOCS 7907170014
Download: ML19224D762 (61)


Text

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RAfDiO SECO NUCLEAR GENEHATING STATIC.J OFFSITE DOSE CALCULATION HTNUAL (ODCM)

May 1979 SACRAMENTO FUNICIPAL UTILITY DISTRICT SACRAMENTO, CALIFORNIA 357 112

'907110c/5/;

,;o

je TABLE OF CONTENTS Pace

1.0 INTRODUCTION

1-1 2.0 LIQUID EFFLUENTS 2-1 2.1 bonitor Alarm Setpoint Detenmination 2-1 2.2 Compliance with 10 CFR 20 for Liquid Radioactive 2-6 Effluents 2.3 Coapliance with 10 CFR 50 for Liquid Radioactive 2-9 Ef fluents 3.0 GTSEOUS EFFLUENTS 3-1 3.1 hbnitor Alann Setpoint Determination 3-1 3.2 Compliance with 10 CFR 20 for Gaseous Radioactive 3-11 Effluents 3.3 Compliance with 10 CFR 50 for Gaseous Radioactive 3-16 Ef fluents APPENDIX A 357 113

,v 1.0 INURODUCTION This Of fsite Dose Calculation Manual (DD74) provices the inforTation and metnocologies tc ce ese: cj : e en:n: Se:: aclear Ge era-i c Liam-

  • c e ;.:e c

compliance with tnase parti:ns of tne Rancno Seco 0;erating

.e:nnica.

specification wni:n are relate t1 licuid anc gasecas racislogica. effiaent'.

The 000'1 is intencea to snou :nat Rancnn Seco corolie: airn.) CFP 2J, 1U CEL 50.36A, 10 CFR 50, Appendix A (GDC 60 & 64), and Appendix I.

This ODCM is based on " Radiological Effluent Technical Specifications for PNR's" (NUREG-0472, October 1978), " Preparation of Radiclogical Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133, October 1978),

and other information provided by the U.S. Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual have been developed.

These procedures are to be utilized by the operating staff of Rancho Seco to ensure compliance eith technical specifications.

35/

11,'

1-1

2.0 LIQUID EFFLUENTS 2.1 f ONITOR ALARM SETPOINT DETERMINATION The methcJology described in this section determines the monitor alann setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds (1) the concentrations specified in 10 CFR 20, Appendix B, Table II, Coluan 2 for radionuclides other than tritium and dissolved or entrained noble gases or (2) exceeus a concentration of 2 x 10-4 uCi/ml for dissolved or entrained noble gases.

The methodology described in Section 2.1.2 provides an alternative means of detennining monitor high alarm setpoints that may be used when an analysis is perfonned prior to release.

2.1.1 Setpoint Based on Conservative Raolonuclide Mix The following method applies to liquid releases when detenmining the high alarm setpoint for the regenerant hold-up tank discharge line aonitor during all operational conditions when the radwaste discharge flow rate is maintained constant at the maximum design flow rate.

2.1.1.1 Detennine the "radionuclide mix" (radionuclide identity and concentration) in the liquid effluent, a.

Determine Si (the fraction of the total radioactivity in the liquid ef fluent camprised by radionuclide 1) for each individual radionuclide in the liquid effluent:

S i / (:

A)

(2.1-1)

A i

=

1 i

ahere A

The radioactivity o'f radionuclide i in the liquio

=

i ef fluent f rom Table 2.1-1.

357 115 2-1

2.1.1.2 Determine Ct (the maximum acceptable total radioactivity concentration of all radionuclides in the liquid effluent prior to dilution

( Ci/cc)).

C F

f (2.1-2) t

=

fE (S )

i (MPC ),

1 where Dilution water flow rate = 800 gpm F

=

f The maximum acceptable discharge flow rate prior

=

to dilution = 300gpm MPC The maximum permissible concentration for

=

i radionuclide "i" ( pCi/cc) from Table 2.1-1 or, if not listed, use Reference (a) of Table 2.1-1.

2.1.1.3 Determine C1 (the maximum acceptable concentration of radionuclide i in the liquid ef fluent prior to dilution ( pCi/ml)).

C SC (2.1-3)

=

i it 2.1.1.4 DeteImine C.R. (the calculated monitor count rate attributed to the radionuclides (cpm)).

C.R.

ZCEii (2.1-4)

=

i where Ei Detection efficiency of the monitor for

=

radionuclide "1" (cpm /u Ci/ml) from Tau._ 2.1-1 or, if not listed, use Reference (b) of Table 2.1-1.

2.1.1.5 The monitor hign alarm setpoint should be set e+ the C.R. plus monitor background value.

Since only one tank can be released at a time, idjustrmnt of this value is not necessary to coapensate for releases from more than one source.

357 116 2-2

2.1.2 Setpoint Based on Analysis of Liquid Waste Prior to Discharge The following methods should be used to determine the setpoint for the maximum pcrmissible discharge flow rate prior to dilution and the associated high alarm setpoint based on this flowrate for the regenerant hold-up tank discharge line monitor during all operational conditions.

This setpoint is based upon actual analyses of liquid wastes.

2.1.2.1 Determine f (the maximum accootable di;. charge flow rate prior to dilution (gpm)).

Determine D.F. (the dilution factor needed to permit discharge of the a.

particular batch of liquid waste).

i (C /MPC )

(2.1-5)

D.F.

=

1 1

i where C

Concentration of radionuclide "1" in the liquid

=

i ef fluent prior to dilution ( pCi/ml) based on analysis of the liquid effluent to be released MPC The maxirrum permissiDie concentration for

=

i radionuclide "i" ( pCi/ml) from Table 2.1-1 or, if not listed, use Reference a of Table 2.1-1.

If the D.F. is less than or equal to C.8, the tank can be discharged b.

at any flow rate.

If the D.F. is greater than O.8, calculate "f" (the maximum c.

acceptable discharge flow rate (gpm), ior to dilution):

F/(1.25 D.F.-1)

(2.1-6) f

=

t he m Dilution water flow rate (gpm)

F

=

357 117 2-3

A correction factor applied to reduce the flow 1.25

=

rate in order to increase the monitor alann setpoint, preventing spurious alarns caused by deviations in the mixture of radionuclides that affect monitor response.

2.1.2.2 Determine C.R (the calculated monitor count rate attributed to the radionuclides (cpm)).

2.25 E C E (2.1-7)

C.R.

=

ii i

where The detection efficiency of the monitor for E

=

i radionuclide "i" (cpm / p C1/ml) from Table 2.1-1 or, if not listed in Table 2.1-1, from Reference (b).

A correction factor to increase the monitor 1.25

=

setpoint to prevent spuricus alarns caused by deviations in the mixture of radionuclides that affect monitor response.

2.1.2.3 The monitor high alaan setpoint should be set at the C.R. plus monitor background value.

Since only one tank can be be released at a time, adjustment of this value is not necessary to compensate for releases from more than one source.

357 118 2-4

TABLE 2.1-1 LIQUID SOURCE TERMS Detection (d)

Radioactivity (b,c)

Efficiency MPC ( pCi/ml)(a)

(E )(cpm / LCi/cc)

(A )(Ci/yr)

Radionuclioe i

i i

bb-99 AE-5 2.65E-3 2.27E7 I-131 3E-7

1. 88E-3 1.02E8 I-132 8E-6 1.9E 4 2.52E8 I-133 lE-6
1. 86E-3 7.13E7 Cs-134 9E-6 3.3E-4 1.88E8 I-135 4E-6 5.4E-4 1.08E8 Cs-137 2E-5 2.5E-4 7.14E7 H-3 3E-3 3.0El OE0 Cr-51 2E-3 lE-3 9.90E6 bb-54 lE-4 7.90E6 Fe-59 SE-5 lE-5 8.07E7 Co-58 9E-5 1.2E-4 1.07E8 Co-60 3E-5 lE-5 1.52E8 Zr-95 6E-5 7.99E7 Total 3.000785El Notes (a) Based on 10 CFR 20, Appendix B, Table II, Column 2.

(b) Based on Appendix I Evaluation Report, Rancho Seco Nuclear Generating Station, Table 3.4-1.

(c) Based on 0.25% failed fuel.

(d) Based on Orignal Calibration Date (Victoreen Liquid Effluent Sampler, Model 841-3, with scintillation detector, Fbdel 843-30).

2-5

2.2 CCNPLIANCE WITH 10 CFR 20 FOR LIQUID RADI0 ACTIVE EFFLUENTS During normal operation, there are no radionuclides released in liquid effluents from Rcocho Seco.

The nonnal pathway in which radionuclides can be releay1 in liquid effluents is if there is a tube failure in the steam generators.

This would allow radionuclides to be released to the secondary side of the nuclear steam supply system.

These radionuclides would ultimately be collected in the regenerant holdup tanks.

These tanks are potentially the point of radionuclide release for liquid effluents.

If radionuclides are to be discharged via the regenerant holdup tanks, then compliance with 10 CFR 20 nust he demonstrated before the contents of these tanks can be released to the environment.

This is done by determining the concent ratic' cf radionuclides in liquid effluents and then comparing these concentrations with the maxinum permissible concentrations in Appendix B, Table II of 10 CFR 20.

Actual release data is used after completion of the discharge to verify conpliance. Methods for determining the radionuclide concentrations in the regenerant holdup tanks before release and after release as well as the methocology to show conpliance with 10 CFR 20 are described in the following paragraphs.

2.2.1 Eatch Releases 2.2.1.1 Premlease The maxirrum radionuclide concentration in each release to the unrestricted area from the regenerant holdup tank is deteImined prior to the release.

This is cone by using the following equation:

Conc C R/OOF+R)

(2.2-1) i i

=

where Concentration of radionuclide "i" at the Conc

=

i unrestricted area, pCi/ml Concentration of radionuc1ide "i" in the C

=

i potential batch release, uCi/ml 357 120 y

R Maximum release rate of the batch (gpm)

=

Maximum flowrate from the regenerant holdoo

=

tanks (gpm)

Minimum dilution flow (gpm) 60F

=

minimum cooling tower blowdown flow rate or

=

dilution flow from Folsom South Canal (gom)

The projected concentratico in the unrestricted area is canpared to the concentrations in Appendix B, Table II, of 10 CFR 20.

The maximum flowrate from the regenerant holdup tanks is 300 gpm.

The MDF for Pancho Seco is 800 gpm.

The following equation must be satisfied before the release is made to show compliance with 10 CFR 20:

E (Conc /MPC )

< 1 (2.2-2) 1 1

i whe re MPC; Maximum permissible concentration ( pCi/ml)

=

of radionuclide "i" fran Appendix B, Table II, of 10 CFR 20.

2.2.1.2 Pastrelease The concentration of each radionuclide in the unrestricted area is calculated following release fram a regenerant holdup tank by using the following equation:

Corc C R /(ADFk+R)

(2.2-3)

=

i ik k

w he re Conc The concentration of radionuclide "i" at the

=

ig site boundary, during the release period of time k, ( pCi/ml)

C Concentration of radionuclide "1" in the

=

t batch release,

( PCi/ml) 357 121 2:,

R, Average release rate of the batch during

=

time period "k",

(gpm)

Average flowrate from the regenerant holdup

=

tanks, (gpm)

ADFk Actual dilution flow during the time period

=

of release "k",

(gpm)

Average cooling tower blowdown flowrate or

=

dilution flowrate from Folsom South Canal during the time period of release "k",

(gpm).

The tirre period k is the actual time period over which the release occurs.

Compliance with 10 CFR 20 is demonstrated by use of the following relationship:

E (t'oncik/MPC )

1 (2.2-4) 1 i

357 122

2.3 COMPLIANCE WITH 10 CFR 50 FOR LICUID RADI0 ACTIVE EFFLUENTS Compliance with 10 CFR 50 is denonstrated only if radioactive releases are required from the regenerant holdup tanks (see Section 2.2).

If this is the case, then compliance with 10 CFR 50 must be demonstrated at least once every 31 days using the following equation:

D f

t (2.3-1)

E A,Cik k k

=

1 i

I where D

The dose commitment to the total body or any

=

organ "T",

from the liquid effluents for the period of release, (mrem)

Cik The average concentration of radionuclide

=

"i" in undiluted liquid effluents during time period "k", (u Ci/ml)

Rat.onuclide concentration in the regenerant

=

holdq] tanks A

1 The site related ingestion dose cannitment

=

f:- tor to the total body or any organ "T"

6... 'ach identified principal gamma and beta em'_tter "i", (mrem /hr per pCi/ml)

Fk Dilution factor due to cooling tuwer

=

blowdown flow or dilutior. flow from Folsan South Canal during liquid effluent (regenerant holdup tank) release.

Average regenerant holdup tank flow rate

=

divided by the sum of the average cooling tower blowdown flow rate or the dilution flow rate fran the Folsom South Canal and the flow rate from the regenerant holdup tank.

357 123 2-9

th g

Length of the k time period over which t

=

C and F are averaged for all liquid ik k

releases.

The dose factor A is calculated for an adult for each isotope assuming i

that the drinking water, fish and irrigation pathway exists as follows:

ir 1.14 x 10 (730/D, + 21BF +F)DFi A

(2.3-2)

=

i where 5

6 3

1.14 x 10 Conversion factor (10 pCi/ pCi x 10 ml/1)

=

(8760hr/yr)

Adult water consumption, (1/yr) 730

=

D Dilution factor for water, (dimensionless)

=

w DF Dose conversion factor for nuclide "i" for a

=

i preselected organ "T" of a person in any age group, (mrem /pCi)

F Factor that accounts for irrigation

=

8F Bioaccunulation factor for nuclide "i" in fish

=

i (pCi/kg per pCi/1) 21 Adult fish consumption (kg/yr)

=

Ia defining factor F the following terms are defined:

2 I

Total irrigation water used (1/m per hr)

=

U'h Usage factor for leafy vegetables (kg/yr)

=

2 Y

Yield of leafy vegetables (kg/m )

=

1y L(

Usage factor for non-leafy vegetables (kg/yr)

=

Yield of non-leafy vegetables (kg/m >

357 12a Y

=

y 2-10

Q 7 Feed consumption rate for animal (kg/ day)

=

3 U

Usage factor for milk (1/yr)

=

Fi,m Stable element transfer coefficients for milk (pCi/l

=

per pCi/ day)

Q[

Carscapiion rate of contaminated water by milk animal

=

(1/ day)

F Stable element transfer coefficient for meat (pCi/kg

=

i,mt per pCi/ day)

U[t Usage factor for meat

=

Q ConsuTytion rate of contaminated water by meat animal

=

(1/ day)

DFI Dilution factor for the irrigation pathway

=

2 Y

Yle.ld of pasture grass (kg/m )

=

g Fraction of deposited activity retained on crops r

=

E,i i+

w y is the radiological decay A

A where A A

constant of radionuclide i and A is the removal w

rate due to weathering ( A

= 0.0021 hr-)

The factor which uefiner radionuclide transpc"t for all nuclides except tritium in the biosphere is defined below.

la 2a 3

(Ill r/ l Yy ) + (IU r/Y F

A

=

y E,i y E,i 3a 3b f i,m rn /Yg,1 g,1) + (Q w i, 7,U )J ]}} a (IO F Ur F 2-11

4a 4b (2.3-3) +(IU$tfi,mt Of r/Y A E,i' + (0 wi,mt$t) U g where term la accounts for radionuclide deposition on leafy vegetables 2a accounts for radionuclide deposition on non-leafy vegetables 3a account. for milk contamination due to radionuclides 30 accounts for milk contamination due to animals drinking contaminated water Aa,4b same as 3a, 3b except that these apply to creat pathway which factors to (rI/ A E,i) (U y/Y1 ) + (U / Y) F = y + (Qr i,m y/Y ) + (Q F,mt t g F U U /Y ) g fi (Q*,F wi,gt$t} ( *-} i,m m) + ( F U U + Since Y =Y, 1y y a (rI/ A E,i) (U + U )/Y F (2.3-5) = + y i,m n + Fi,mtyt O (F U U + f g a (0 F U F U w i,m n + i mt In computing the value of F for tritium it is assumed that the tritium concentration in the irrigating water is the same as that in the plant being consumed. Thus, tritium, unlike other nuclides, does not accumulate in the plants. The factor that converts tritium concentration in the irrigatina water to tritlun concentration in the plant is 1 liter per kg. Hence F becomes 357 126 2-12

la 2a a a (U x 1) + (U x 1) (2.3-6) F = 1y y 3a 3b + (Q F7 i,nbm

  • 1) + (O F U
  • 1 f i,mt mt 4a Ab

+ (Q u

  • 1) + (C U
  • 3) aw i,m m aw 1,mt mt where tho quantity defined by each teIm is as defined er.rlier.

This equation can be factored as follows: U a+U a + O (F i,mt mt } F U + U = yy y g i,m m mt +Q F U +U F U (2.3-7) a i,m m aw i,mt mt The followirg parameters are taken from Regulatory Guide 1.109, Revision 1: o From Table E-3 60 liters / day Q = aw E Q 50 liters / day = aw Q 7 50 kilograms / day = o From Table E-15 0.25 r = 2 Y Y 2.0 kg/m = = 1y y 2 P 240 kg/m = 2 Y 0.7 kg/m = g yc 9, JJ/ /_ / 2-]3

o values of B F and F are taken from Table E-1 iy, i,m i,mt a o values of U U,U and U re taken from y, m t Table E-F The decontamination factor (D ) used for the drinking water exposure pathway o is 1.0. The irrigation water used (I) is 0.365 liter /m'/hr. The values of A are tabulated in Table 2.3-1. y Doses calculated every 31 days are added to the doses computed previously and compared to quarterly and annual limits. The following criteria must hold: For the quarter, l.5 mrem to the whole body D 5 mrem to any organ D For the calendar year. 3.0 mrem to the whole body D 10 mrem to any organ D The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report in accordance with the Ef fluent Technical Specifications should be submitted identifying the cause and corrective action to be taken. Doses resulting from the release of liquid effluents are projected at least once per month. The projected doses will be calculated from Equation 2.3-1. The dilution factor Fk will be calculated by replacing the term ADFk I" Equation 2.3-1 with the term (1/h0F) from Equation 2.2-1. The total sourcc term utilized for the most recent dose calculation should be used for the projections unless.information exists i'licating that actual releases could dif fer significar,tly in the next montr.. In this event, the source term should

e adjusted to Ieflect this information, and the justification for the Mjustment should be noted.

} 2-14

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3. 0 if 01 8.09E C1 2.83f C1 2.83E C3 1.29E C2 C.00E-01 1.52E 01 1 131 1.73F 92 6.59F 07 2.01E 02 9.67E 04 1.152 C3 0.00E-01 "5.91E C7~-

1 134 1.41I 01 4.02E G1 1.44E C1 6.96E C2 4.39E G1 C.CCL-01 3.50c-02 1 135 7.81E 01 2.06F C2 7.610 01 1.36E C4 3.31E C 2 - C. C C I -- 2. 3 3 E C2 C 513 r, 4.R 3 E 95 1.15E 06 9.40E C5 0.00E-01 3.720 05 1.24L 05 2.01t 04 CS136 4.11E "4 1.62f C5 1.17E CS C.CCE-C1 S.C4E C4 1.24E C4' 1.d5E 04 -~ 05137 6.4 3E 05 R.52E C5 5.50E C5 C.CCE-C1 2.89E C5 S.61C 04 1.6sf 04 C5139 ?.7tE n? 5.3%f 07 7.65E C2' O.00E-01' 3.93t 02 3.62E 01 2.20E-C1 PA131 9.9 3 F 30 7.0RE-03 7.91E-C1 0.COE-C1 6.62E-C3 4.01E-03 1.76L C1 Pi14C 1.78E 04 2.23E C1' !.16 E 0 3 ~- 0. C O E - C I-

7. 5 8 t C O
1. 2 9 E 01
3. 6 6 E - C 4 84141 4.57E 90 3.46E-03 1.54E-01 0.00E-01 3.21E-03 1.96E-03 2.16E-09

? V: .i.%,. --_.-6%. __m_ 4 { M g y &,9 o cn cf wl 9AA o

Tallf 2.1-1(Cf%T*0) f.11 V i t.U F 5 FOR THE ADUtT FOR THE 9ANCHC 5fC0 NLCLEAR Ct'. cATING STATION (1RE"/FR PER FTCRU-CT/*L) NUCLIPE PEhE LIVFP T.PCDY TFTRIPC V I O r.' ( ' ' ~~ LUNC --- 'GI-LLI ' - - - - ~ - ----~---- - -- -- Ftt41 2. 0 '. I JO ?.11f-Cl 1.290-C1 0.JPE-01 1.7'?i-03 1.20E-33 2.10L-11 LAls) 7.51T-01 1.10F-Cl 1.CCT-CI' O.CCF-Ci C.00[-01 C.00E-01' 2.79E C5 LA142 1.9/f-0/ 8.73f-03 2.171-Cl C.CCE-Cl C. C O' -C l C.CCf-01 6.37E C1 fF141 1.0 T E 01 7.21F 00 R.21t-01 0.COE-01 3.16L CO C. 0 0 E-31 ~ ~ ~7. 7 7 E C4 Cr141 1.(1I-11

7. lit C7 3.0?I-C2 C.CPE-C1
1. 2 C E -01 C.CCE-C1 1.J2E C4 CF144
7. 4 )f 12

'J. l l i C2 '3.950 C1~ 0. C C E - C I--~ 1. 8 4 E C2 ~C. 0 C E- 01 2.510 C 5 -- -~ ~- - ' FR143 H. llr 10 1.54E C 'l 4.34t-61 0.00F-01 7.04I C0 C. 0 E - 01 3.37i. C4 Pr144 4.44f-13 1.14f-01 2.26E-04 0.00E-01 1.CwE-C3 C.00F-01 -6.3SE-10 hC147 5.34C 00 6.17t C0 J.Mf -C i G.COE-C1 J.61t CO C.CCE-01 2.96E C4 h 197 3.lSF 92 2.64F 02 9.22C C1 0.00E-C1 0.07E-01 0.005-01 8.54C C4 hP739 3.11f-01 1.74F-C2 2.06E-02 0.J0E-01 1.17E-01 G.0CE-01 7.59E C3 - - +. e- --e.--- I ... -.. - -- -. ~. - -... - - - %J -_-w----*- ---. - -.e- - - - + - .-...--w-- e_ =-- m - -... -. -. ~ +e -m w-e.=.am -m.- e u,/ - ~ ~. -. - u jh1/y s . ~. _. - g#5 y;_ i u, k N

3.0 GASEOUS EFFLUENTS 3.1 NONITOR ALARM SETPOINT DETERMINATION The methodology described in this section is used to determine the monitor alann setpoint. The monitor is set to alann if the calculated dose rate to unrestricted areas due to noble gas radionurl. ides in the gaseous effluent released fran the site exceeds 500 mren/yr to the whole body or 3000 mran/yr to the skin. The methodology described in Section 3.1.2 provides an alternate means of detennining monitor high alann setpoints that may be used when an analysis is perfonned prior to release. If two simultaneous gaseous releases out of one vent occur, the setpoint for each release is calculated and the lower setpoint is used. 3.1.1 Setpoint Based on Conservative Radionuclide Mix The following method applies to gaseous releases via the Auxiliary Building Vent, the Radwaste Service Area Vent and the Reactor Building Vent when detennining the high alarm setpoint for the Auxiliary Building Stack Radiation Monitor, the Radwaste Service Area Vent Radiation Pbnitor, and the Reactor Building Atmosphere and Purge Radiation htnitor during the following operational conditions: 3. Continuous release via the Auxiliary ouilding Vent b. Continuous release via the Radwaste Service Area Vent c. Batch release of waste gas decay tanks via the Auxiliary Building vent d. Batch release of containment purge via the Reactor Building Vent 3.1.1.1 Determine the " mix ' (noble gas radionuclide identity and coaposition) of the naseous ef fluent: a. Obtain the source tenns that are representative of the 'inix" of the gaseous ef fluent from Table 3.1-1. 357 132 3-1

b. Determine S1 (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i") for each individual noble gas radionuclide in the gaseous effluent. S A/Ig i = i ( *1-1 i where Ai The radioactivity of noble gas radionuclide "i" = in the gaseous effluent from Table 3.1-1 3.1.1.2 Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent ( PCi/sec)) based upon the whole body exposure limit: Q 500/ ( X/Q) IKS (3.1-2) = t 11 i w are ( X /Q) The highest calculated annual average uispersion = factor for effluents released via the plant vents for any area at any point at or beyond the site 3 boundary for any sector (sec/m ) from Appendix A 3 2.2E-5 sec/m for continuous releases = 3 4.9E-5 sec/m for batch releases = K The total whole body dose factor due to gamma = i emissions from noble gas radionuclide "i" 3 (mrem / year per p Ci/m ) from Table 3.1-3. Whole body exposure limit (mrem /yr) 500 = 3.1.1.3 Determine Q based on the skin exposure limit: t 3000/(X /Q) Z ((Li + 1.1 M )Si U (3.1-3) = t 1 i 357 133 3-2

where Li + 1.1 Mi The total skin dose factor due to emissions from = 3 noble gas radionuclide "i" (mrem / year /pCi/m ) from Table 3.1-3. Skin exposure limit (mrem /yr) 3000 = 3.1.1.4 Determine Qi (the maximum acceptable release rate of noble gas radionuclide "i" in the gaseous effluent ( P Ci/sec) for each individual noble gas radionuclide in the gaseous effluent: Q SQ (3*1-4) = i 3t (NOTE: Use the lowest of the Q values obtained in Sections 3.1.1.2 and t 3.1.1.3) 3.1.1.5 Determine C1 (the mhximtm acceptable radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent ( p Ci/cc)) for each individual noble gas radionuclide in the gaseous effluent: (2.12E-3Q )/F (3.1-5) C = 1 i where The maximum acceptable effluent flow rate at F = the point of release (cfm) 57,000 cfm (auxiliary building vent) = 19,500 cfm (radwaste service area vent) = 74,000 cfm (reactor building vent) = thit conversion factor to convert 2.12E -3 = pCi/sec/cfm to p Ci/cc 3.1.1.6 Nte rmine C.R. (the calculated monitor count rate attributed to the noble gas racionuclide (nepm)): 357 134 3-3

C.R. ECE = ii (3.1-6) i where i The detection efficiency of the monitor for E = noble gas radionuclide "i" (cpm / PCi/cc) from Table 3.1-2. 3.1.1.7 Determine the Ironitor alarm setpoints above background: a. Determine HSD (the monitor high ala:m setcoint accve tackground (co-)): -5 :

.5:: ^-

~ s c-i::: :a: ;::r: '3.. 7, = D. Determine ASP (the monitor alert alarm setpoint above oackground (cpn)): ASP 0.10 C.R. plus monitor background (3.1-8) = NOTE: The values 0.80 for the HSP and 0.10 for the ASP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded because of simultaneous releases from several pathways. 3.1.2 Setooint Based on Gaseous Effluents Analyzed Prior to Release The following method applies to the gaseous releases via the Auxiliary Building and the Reactor Building Vent when determining the setpoints for the Nximum acceptable discharge flowrate and the associcted high alarm setpoint cased nn this flowrate for the Auxiliary Building Stack Radiation Monitor and the Reactor Building Atmosphere and RJrge Radiation Monitor during the following operational conditions: a. Batch release of waste gas decay tanks via the auxiliary building vent b. Batch release of containment purge via the reactor building vent -e _57 13'a 3 3-4

3.1.2.1 DeteImine the maximum peImissible discharge flowrate (prior to dilution by other sources of ventilation air): a. Determine f (the maximum peImissible gaseous discharge flowrate (cim)) based on the permissible whole body exposure limit: f 0.848T / ( X/Q) Z K C (3.1-9) = m yi i where 0.848 A constant, resulting from the 500 mrem /yr whole = body exposure limit multiplied by a unit conversion factor of 2.12E-3 (to convert ( PCi/sec/cfm to PCi/cc) and divided by a correction factor of 1.25 (to decrease the flowrate which permits the setpoint to be increased by a factor of 1.25 to prevent spurious alarms) ( X/Q) The highest calculated annual average dispersion = factor for effluents released via the plant vents for any point at or beyond the site boundaly for 3 any sector (sec/m ) from Appendix A 3 4.9E-5 sec/m for batch releases = K The total whole body dore factor due to ganTre = i emissions from noble gas radionuclide "i" 3 (mrem / year / PCi/m ) from Table 3.1-3 C i The radioactivity concentration of noble gas = radionuclide "i" in the gaseous ef fluent ( pCi/cc) from the analysis of the gaseous ef fluent to be released 357 i M 3-5

T Fraction of the total gaseous radioactivity that = m may be released from the site via each release point to ensure that the permissible radiation exposure limit at the site boundary is not exceeded due to simultaneous releases from several pathways 10% (auxiliary building vent) = 80% (reactor building vent). = b. Determine f Dased on the skin exposure limit: f 5.09T / ( X/Q) E (Li + 1.lM )Ci (3.1-10) = m 1 i where A constant resulting from the 3000 mrem /yr skin 5.09 = exposure limit nultiplied by a conversion factor of 2.12E-3 (to convert p Ci/sec/cfm to p Ci/cc), and divided by a correction factor of 1.25 (to decrease the flowrate which permits the setpoint to be increased by a factor of 1.25 to prevent spurious alarms) The total skin dose factors due to emissions from L3 + 1.1 Mi = 3 noble gas radionuclide "i" (mrem / year / pCi/m ) from Table 3.1-3. c. Determine f by selecting the smaller of the calculated f value< based on the whole body exposure limit (Section 3.1.2.la) and based on the skin exposure limit (Section 3.1.2.lb). The actual flowrate (cfm) nust be maintained at or below this calculated f value or the discnarge can not be made from the vent. 357 157 3-6

3.1.2.2 Detennine the monitor high alarm setpoints above background. a. Determine C.R. (the calculated monitor count rate above background attributed to the noble gas radionuclides (ncpm)). C.R. (1.25f E C E )/F (3.1-11) = ii i where f The maximum acceptable gaseous discharge flowrate = (cfm) detennined in Section 3.1.2.1 The maximum design vent flowrate at the point of F = release (cfm) 57,000 cfm (auxiliary building vent) = 74,000 cfm (reactor building vent) = 1.25 Correction factor to increase the monitor alann = setpoint to prevent spurious alarns caused by deviations in the adxture of radionuclides that affect monitor response (the calculated flowrate has been decreased by this 1.25 factor) C i Radioactivity concentration of noble gas = radionuclide "1" in the gaseous effluent ( UCi/cc) from the analysis of the gaseous ef fluent to be released. Ei Detection efficiency of the monitor from noble = gas radionuclide "i" (cpm / pCi/cc) from Table 3.1-2. b. The monitor high alann setpoint above background (cpm) should be set at the C.R. plus monitor background value. 357 138 3-7

TABLE 3,7-1 CASEOUS SOURCE TERMS Aux. Bldg.. (a,b) Recator Bldg. (a) Oecay Tank Vent (A )(Ci/Yr) Nuclioe Vent (A )(Ci/Yr) Release (A ) i i 1 Kr-89n 3.GEO 3.OE0 Kr-85 5.OE0 9.3El Kr-87 1.0E0

0. 0 E0 Kr-88 6.OE0 4.0E0 Xe-131m 3.0E0 5.7El Xe-133n 7.0E0 6.5El Xe-133 5.3E2 7.8E3 (c)

Xe-135 1.0El 2.2E1 Total 5.65E2 8.04E3 Notes _ (a) Based on Appendix I Evaluation Report, Rancho Seco Nuclear Generating Station, Table 3.4-2. (b) This source term is also applicable for the Radwaste Service Area Ve nt. (c) For Waste Gas Decay Tank Release, consider Xe-133 as the only Radionuclide (S = 1.00). 35/ 139 3-8

TABLE 3.1-2 MONITOR DETECTOR EFFICIENCIES (a) Ef ficiency (E )(cpm /u Ci/cc)(b) Nuclide i Kr-83m

0. 0E0 Kr-85m 1.15E8 Kr-85 1.00E8 Kr-87 2.15E8 Kr-88 1.97E8 kr-89 2.20E8 Kr-90 1.97E8 Xe-131m 4.54E7 Xe-133m 8.47E7 Xe-133 3.90E7 Xe-3 '- 9n 3.18E7 Xe-133 1.25E8 Xe-137 2.20E8 Xe-138 1.90E8 Xe-139 0.0E0 Ar-41
1. 45E8 flotes

( a.' Based on Original Calibration Data (Victoreen Gaseous Effluent Sampler,Model 841-3, with scintillation detector Model 843-208) (b) icable to auxiliary bullding vent radiation monitor, reactor , ;ur bol J'ing atmosphere and purge radiation monitor, and the radwaste service area vent monitor. 357 140 3-9

TABLE 3.1-3 OCSE FACTORS AND 0]NSTANTS Total Whole Body Total Skin Dose Factor Dose Factor (Li4 1.1 Mi) (K )(mrem /yr/ p Ci/M3) (mrem /yr/p C1/M3) Radionuclide i Kr-83m 7.56E-2 2.12El Kr 89n 1.17E3 2.81E3 Kr-85 1.61El 1.36E3 Kr-87 5.92E3 1.65E4 Kr-88 1.47E4 1.91E4 Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15El 6.48E2 Xe-133n 2.51E2 1.35E3 Xe-133 2.94E2 6.94E2 Xe-139n 3.12E3 4.41E3 Xe-135 1.81E3 3.97E3 Xe-137 1.42E3 1.39E4 Xe-138 8.83E3 1.43E4 Xe-139 Ar-41 8.84E3 1.29E4 357 141 3-10

3.2 C(NPLI ANCE WITH 10 CFR 20 FOR GASEOUS RADI0 ACTIVE EFFLUENTS Dose rates resulting from the release of noble gases and radioiodines and particulates are calculated to show cortpliance with 10 CFR 20. The limits of 10 CFR 20 are applied on an instantaneous basis and must be met at the hypothetical worst case location. 3.2.1 Dose Calculation Methodology for Noble Gases Tne dose rate beyond the site boundary resulting from noble gas effluents is limited to 500 mrem /yr to the total whole body and 3000 mrem /yr to the skin. The setpoint determinations discussed in the previous section are based on the dose calculational methoo presented in NUREG-0133, Section 5.2. Establishing alarm set points in this manner will ensure that the limits of 10 CFR 20 are met for noble gas releases. Therefore, no routine dose calculations for noble gases are required to show compliance with 10 CFR 20. Routine calculations for doses from noble gas Ieleases aIe made to show compliance with 10 CFR 50, Appendix I, as discussed in Section 3.3.1. 3.2.2 Dose Calculation Methodology for Radiciodine and Particulates The dose rate beyond the site boundary resulting from the release of radioiodines and particulates with half lives greater than 8 days is limited to 1500 mrem /yr to any organ. The calculation of dose rate from radioicdines and particulates are performed for batch releases prior to the release and monthly for all releases. The calculations are based on the r ?sults of analyses obtained pursuant to the Rancho Seco Technical Specifications. The following general equation, based on NUREG-0133, Section 5.2, is used to show compliance with 10 CFR 20: D 1500 mrem /yr (3.2-1) z z o;jWQi = y ji 357 142 3-11

where P Dose conversion factor for radiciodines and = ij particulates with half-lives greater than 8 days that yields the maximum dose to any organ of an infant for exposure pathway J. See Table 3.2-1 for P1j values 3 mrem /yr per LCi/m for inhalation pathways and = tritium 2 m (mrem /yr per p Ci/sec for the food pathways) = Qiy The total release rate of radionuclide "1" in = gaseous effluent from all vents, PC1/sec W The highest calculated annual average dispersion = y parameter for estimating the dose to an individual at the controlling location due to all releases 3 sec/m for the inhalation pathway for all = isotopes and for tritiun in the food pathway -2 = m for the food pathways for all isotopes except tritium. Dose conputations using the above equation yield the maximum dose to any organ of an infant for exposure pathway j. Radioiodine and particulate effluents are released from two exhaust points, as shown on Table 3.2-2. Compliance with 10 CFR 20 is demonstrated by computing the cose rates due to radionuclides released from these points to a hypothetical person located at the site boundary. All radionuclide releases are considered to be long term ground level releases for showing conpliance with 10 CFR 20. For radiciodine and particulates, the site boundary location with the highest calculated D/Q value occurs is always the location where the higN st computed dose occurs. This location is at a distance of 0.60 miles in 3-12

the ANN sector (see Oppendix A,'. The inhalation, cow milk or goat milk exposure pathways are asstred to exist at this location. The values of X /Q and D/Q are cocputed using the XOQD00 coaputer code provided by the tRC. Short tenn releases occurs as a result of containaent purging and waste gas decay tank releases. Before these releases are allowed to occur, dose calculations using Equation 3.2-1 are made to determine if the release can occur. The limiting dose for a short tenn release is not 1500 mrem /yr but is determined as follows: 1500 - D (3.2-2) BL = y where Limi*ing dose for the batch (mrem /yr) BL = D Computed dose rate for previous week from all = continuous vent releases (mram/yr). 357 144 3-13

TABLE 3.2-1 P j UALUES FOR AN INFANT i Isotope Inhalation (a) Cow Milk (b,C) Coat Milk (b,c) H-3 6.47E2 2.38E3 4.86E3 P-32 2.03E6 1.6 Cell 1.93 Ell th-54 1.00E6 3.89E7 4.66E6 Fe-59 1.02E6 3.93E8 5.llE6 Co-58 7.77ES 6.06E7 7.28E6 Co-60 4.51E6 2.10E8 2.52E7 Zn-65 6.47E5 1.90E10 2.29E9 RD-86

1. 90E5 2.22ElO 2.67E9 Sr-89 2.03E6 1.27ElO
2. 66E10 Sr-90 4.09E7 1.21 Ell 2.55 Ell Y-91 2.45E6 5.26E6 6.32E5 Zr-95
1. 75E6 8.28E5 9.95E4 Nt 4.79E5 2.06E8 2.48E7 r.

5.52E5 1.05E5 1.27E4 s-106 1.16E7 1.44E6 1.73E5 Ag-llan 3.67E6 1.46ElO 1.75E9 Cd-119n Sn-123 Sn-126 Sb-124 Sb-125 Te-122m 1.31E6 1.04E9 1.24E8 Te-129a 1.68E6 1.40E9 1.68E8 Cs-134 7.03E5 6.79E10 2.04 Ell Cs-136 1.35E5 5.76E9 1.73ElO Cs-137 6.12E5 6.02E10 1.81E11 83-140 1.60E6 2.41E8 2.89E7 Ce-141 5.17E5 1.37E7 1.65E6 Ce-344 9.84E6 1.33E8 1.60E7 I-1 31 1.48E7 1.06E12 1.27E12 I-133 3.56E6

9. 80E9 1.18E10 (a) Inhalation:

mrem /yr per uCi/m3 for all isotopes (b) Cow Milk and Goat Milk: m2 x rrrem/yr per pCi/sec for all isotopes except tritium (c) Cow Milk or Coat Milk: mrem /yr per uCi/m3 for tritium 357 145 3-14

TABLE 3.2-2 StJ4%RY OF GASEOUS RELEASE DATA USED IN THE ODCM Release Point Source of Radioactivity Actual Release Mode 1 Auxiliary Building Ventilation Exhaust Continuous (includes steam jet air ejector exhaust) 1 Reactor Building Purge Exhaust Batch 1 Wash Gas Decay Tank Exhaust Batch 2 adwaste Area Exhaust Continuous Notes: Release Point 1 is located on the side of the Reactor Building, at a height of 146 feet above grade. Release Point 2 is located on the auxiliary building roof, at a height of 60 feet above grade. 357 146 3-15

3.3 COMPLIANCE WITH 10 CFR 50 FOR GASEOUS EFFLUENTS Doses msulting from the release of noble gases, and radiciodines and particulates. rust be calculated to show compliance with fppendix I of 10 CFR 50. The calculations will be performed at least once every month for all gaseous ef fluents. 3.3.1 Dose Calculation Methodolooy for Noble Gases The air dose beyond the site boundary due to noble gases released in gaseous effluents is determined by the following expressions, which are based on NUREG-Ol33, Section 5.3.1; For ganma radiation: D 3.17 x 10-8E M ( X /Q) Q + ( X /q )yqiy (3.3-1) = i where the value of G, :,Ust be less than 5 mrad for any calendar quarter 10 mrad for any calendar year For beta radiation: D 3.17 x 10-0 E N ( X /Q)y iy ( X /q)yqiy (3.3-2) Q + = g i i where the value of D must be less than g 10 mrad for any calendar quarter 20 mrad for any calendar year where 1 The air dose factor due to ganma emissions for N1 = each identified noble gas radionuclide "i" 3 (mrad /yr per p Ci/m ) 357 147 3-16

"i The air dose factor due to beta emissions for = each identified noble gas radionuclide "1" mrad /yr per pCi/m3 (X /0)y The annual average relative concentration for = areas at or beyond the restricted area boundary for long-tenn vent releases (greater than 500 3 hrs / year), sec/m (X /q)y The relative concentration for areas at or beyond = the restricted area boundary for short-term vent releases (equal to or less than 500 hrs /yr), sec/m3 Q The total release of noble gas radionuclide "i" iy = in gaseous effluents for short-teIm vent releases (equal to or less than 500 hrs /yr), p Ci C The total release of noble gas radionuclide "i" iy = in gaseous effluents for short term release (equal to or less than 500 hrs /yr), p Ci 3.17 x 10-0 The inverse of the number of seconds in a year = Noble gases are released from Rancho Seco from two release point locations. The values of long-term and short-tenn X/Q are listed in Appendix A. All releases are assumed to occur at ground level. These values are computed using the XOODOQ computer code. Values of Mi and Ni are listed on Table 3.3-1 and are taken from Table B-1 of Regulatory Guide 1.109 Resision 1. Doses are calculated at least once every, month and added to the cumulative dose to date. Conparisons are then made to the quarterly and annual limits speelfied in Equation 3. 3-1 ant. ,iation 3.3-2. 357 148 3-17

3.3.2 Dose Comoutation Methodolor for Radiciodine and oarticulates The dose to an individual from radioiodines and particulates with half-lives greater than 8 days in gaseous effluents released to unInstricted areas is determined by the following expressions: During any calendar quarter or year based on NUREG-0133, Section 5.3-1: -8 3.17 x 10 IE R D

  1. Cv iv + *v4 (3'3-3)

= i ak j i where the value of D is limited to: 7.5 mrem (per quarter) 15 mrem (per calendar year) whe re iy Release of radionuclide "1" for long-term vent Q = releases (greater than 500 hr/yr), u Ci Release of isotope "1" for short-term vent q = 1y releases (equal to or less than 500 hr/yr), u Ci The dispersion parameter nr estimating the doses W = y to an individual at the controlling location for long-term vent releases (greater than 500 hr/yr) 3 in units of X /Q (sec/m for the inhalation pathway for all nuclides 2 in units of D/Q (1/m ) for all nuclides except tritium for all pathways except inhalation 3 in units of X /Q (sec/m ) for tritium for all pathways 357 149 3-18

The dispersion parameter for estimating the dose = y to an individual at the controlling location for short-tenn vent releases (equal to or less than 500 hr/yr) 3 in units of X/Q (sec/m ) for the inhalation pathway for all nuclides 2 in units of D/Q (1/m ) for all nuclides except tritiun for all pathways except inhalation 3 in units of X/Q (sec'm ) for tritium for all pathways 3.17 x 10-8 The inverse of the nurrber of seconds in a year = R The dose factor for each identified radionuclide = ijak "i", pathway "j", age group "a", and organ "k", 2 3 m mrem /yr per PCi/sec or mrem /yr per PCi/m The above equation is applied to each combination of age group, organs and exposure pathways listed below: Age Group adult, teenage, child, infant Organs total body, GI-tract, bone, liver, kidney, thyroid, lung and skin Exposure Pathways ground plane, vegetable, meat, cow milk, goat milk and inhalation. The values of Rijak are calculated using the methodology described in Eection 5.3 of NUREG-0133. These values are listed on Tables 3.3-2 through 357 15r 3-19

3.3-20. Equation 3.3-2 is applied to the controlling location (i.e., the location ahere the maximum dose occurs), which will be one of the following: residence milk cow vegetable garden milk goat meat animal The dispersion parameters used in Equation 3.3-2 are computed using the XOCOOQ code provided by the NRC (see Appendix A). Doses are calculated at least every month and added to the cunulative dose to date. Comparisons are then made to the quarterly and annual limits specified in Equation 3.3-3. 3.3.3 Projection of Doses Due to Gascous Effluents Doses resulting from the release of noble gas as well as radiciodine and particulate gaseous effluents are projected at least once per month. The doses calculated for the present month are used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source term should be adjusted to reflect this information and the justification for the adjustment noted. 3.3.4 Critical Receptor Identification The critical receptors for cortpliance with 10 CFR 50, Appendix I, nust be icentified. For the roble gas specification the critical location will be based on the external exposure pathway only. This location will be the site boundary location with the highest reactor building vent X /Q and will be celected using the X /Q values given in Appendix A. This location will remain tho sate unless meteorological data is re-evaluated or the site boundary changes. 357 151 3-20

The critical location for radiciodire and particulates is selected by perfonning an annual usage survey within 5 miles of Rancho Seco. Then doses will be calculated using Equation 3,3-3 for all of the following: 1. Closest residence in each sector 2. Closest vegetable garden in each sector 3. All identified cow milk locations 4. All identified goat ndlk locations. The calculation includes only those pathways shown to exist at each location. The dispersion parameters given in this manual are to be enplayed. The totcl releases reported for the previous calendar year should be used as the source tenn. r ~ 'i 3 5 _/,t a't 3-21

TF1 E 3. 3-1 DOSE FACTORS FOR N0btE CASES AND DAUGHTERS (a) Total Body Gama Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K1 Li Mi Ni 'acionucliae (mrem /yr per p Ci/m3) (mrem /yr per.p Ci/m3) (mrad /yr per p Ci/m3) (mrad /y' per uCi/m3 Kr-8N 7.56E - 02(b) 1.93E + 01 2.88E + O2 K r -8 'xn 1.17E + 03 1.46E + 03 1.23E + 03 1.97E + 03 Kr-85 1.61E + 01 t.34E + 03 1.72E + 01 1.95E + 03 Xr-87 5.92E + 03 9.73E + 03 6.17E + 03 1.03E + 04 Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 Kr-87 1.66E + 04

1. ole + 04 1.73E + 04 1.06E + 04 Kr-90 1.55F + 04 7.29E + 03 1.63E + 04 7.83E + 03 Xe-13Lm 9.15E + 01 4.76E + O2 1.56E + O2 1.llE + 03 5 Xe-133m
2. 51E + O2 9.94E + O2 3.27E + O2 1.48E + 03 Xe-133 2.94E + Uz 3.06E + O2 3.53E + O2 1.05E + 03 Xe-13Sn 3.12E + 03 7.llE + O2 3.36E + 03 7.39E + O2 Xe-135 1.81E + 03 1.86E + 03 1.92E + 03 2.46E + 03 Xe-137 1.42E + 03 1.22E + 04
1. 51E + 03 1.27E + 04 Xe-138 8.83E + 03 4.13E + 03 9.21E + 03 4.75E + 03 Ar-41
8. 84E + 03 2.69E + 03 9.30E + 03 3.2bE + 03 G)

The listed dose factors are for radionuclides that may be detected in gaseous effluents. All others are O. .b)

7. 56E-02 = 7. 56 x 10-2, L4 LT1

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2. 6 2 f: 05 i 8.630 05 ; 4.8HL 06 ; 2.02E 06 ;

'.21E 06 i 0.00E-01 ; 1.33E 07 ; 0.00L-01 ; UNITS OF R VALUES: MREM /YR PER MICROCURIF/CU METER FOR ALL NUCLIDES IN INHALATION PATHWAY

  1. ew%,g AND F OR H-3 IN ALL PATHWAYS, MREM /YR PER MICR0 CURIE /SEC FOR THE REMAINING NUCLICES & PATHWAYF

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357 173 APPEf0IX A

TlaLE 1 Long Term (Continuous Release) Meteorological Data c LLASE 'rp-Cr UIELCTION DISTANCL X/ 0 x/w x/c 0/0 im L9L;'!EN INILES) (NE TERS) (SE C/ Lo b.ha T E R] ( St C/ LL u."E TL d l 155C/LUb.MfTERF 191R SU.NE T E R) NO D E C AY 2.2CJ 9 tY DEC AY 8.0u0 L AY f m AY UNDEPLEIED U:iE E PL E T E D DEPLLTED U

l. E A o t 5 7 *lLK CCm E 7.E 0.75 1207.

1.05-05 1.oE-05 9.1E-OL 6.3E-08 0 NEAM5f IIL K CCw SW 1.93 3107. 1.70-05 1.7E-05 1.6E-05 3.9E-08 0 Ni A4r 5T M ILK CCa w *> W 2.Ji ju21. 1.lE-05 L..:-05 9.7E-Co 3.2E-G8 0 otharst 't!LK CCh d 4.81 7741. 7.4E-U6 7.at-06 6.bE-Oo 3.1E-03 0 MEar ANIMAL r4 0.26

418, 7.2L-05 7.lt-05 6.6E-05
1. 4 E -0 7 U

M c '. T ANi/AL N NE 0.2d 451. 4.7E-05 4.7E-05 4.4E-C5 1.2f-07 0 McAT AN!iAL ta E 0.15 241. 1.7E-04 1.7E-04 1.6E-C4 4.6f-07 U MCAT ;. N 1 " A L L NE 0.11 177. 3.3E-04 3.3E-04

3. J E-C4 1.2E-C6 C

MEAT ANIMtt E 0.09 145. 2.5E-04 2.5E-04 2.4E-04 5.10-07 0 Ptaf ANIMAL E LE 0.11 177. 2.2t-04 2.J E- 0 4 2.2L-04 5.0f-07 0 Mt;T

1N AL SL 0.13 239.

1.6E-04 1.6E-J4 1.5E-04 3.6E-07 0 k ia T AN!4AL 55L 0.15 241. 1.2E-J4 1.2E-04 1.lt-04 1.5 E -0 7 0 ftEiT A114AL 5 J.13 209. 1.9E-04 1.4t-04 1.0E-04 1.3E-07 0 fi f.h T AN ld AL SSH 0.15 41. 1.9E-04 1.'/ E - 0 4 1.Ut-04 1.6E-07 0 PtAT ANivAL SW 0.2J 322. 1.2E-04 1.2E-04 1.mE-04 1.gr-07 0 MEAT AN L ' AL w SW J.22 3>4. 1.]E-04 1.0E-04

1. 0 t-C.

9.4E-Gd 0 PtAT ANIMAL W 0.20 s22. L.4E-J4 1.4E-04 1.3E-04 1.6E-07 0 MtAT AN IM AL WNW 0..' 6 418. 9.lE-05 9.I'-05 6.cF-OS 1.7f-07 U MEAT ANI9AL NW 0.34 597. 5.7L-US 5.6E-05

5. 3 L- 05 1.;f-07 0

MF.T AN 11 At ti N d 0.28 451. 6.UL-05 6.0f-05 6.*E-05 1.4 E -0 7 0 M at K GOAT LW 3.5)

5633, 3.(L-07 3.c t-0 7 2.uE-07 3.0f-10 0

NEAM ST h(51 DENT

t. L 1.09 1754 3.7t-00 3.tE-06 3.2E-06 1.5E-08 r

0 NEAPFST RE510rNY E l.E 0.75 1207. 1.0E-05 1.0E-05 9.ir-06 6.JE-OS 0 h ts ; s i P E 510 f N T E SE 2.99 4512. 2.9E-07 2.eE-07

2. 3 E- 0 7 8.7E-10 0

NLu-sT nE510CN1 LE 4.07 6550. 1.5E-07 1.5E-07

1. 2 f- 0 7 4.0!-10 0

NE;RfST Rf5:2fhT 5 ;E 3.4J 5472. 2.2E-07 2.lE-07

1. 7 L- 0 7
3. C E - 10 0

NEAefst >[SipFNT S 0.49 739. 1.30-05 1.3E-05 1.ZE-05 1.8F-Od 0 N E J. R b 5 T v. r 510 E N T L5W 0.56 901. 1.bt-05 1.LE-05 1.lf-05 2.1E-Od 0 N E /. R - S T RF5IDINT SW l.32 2124. 2.0t-OL 2.ct-06 2.4i-06 3.0E-09 C NE ARE LT k E 5 ICE NI nSW 1.23 1979. 3.4 t-Co 3.4E-06 2.9E-06

3. 0 E - 0 9 0
.t A R ? S T kFSIDENT W

1.99 3042. 1.4L-06 1.4E-06 1.2E-06 1.9f-09 0 NrAPPST WE51DENI uhW 0.03 1336. 1.1L-05 1.!E-05

9. 5 0- 0c 2.5E-00 Qg 0

NtAD'51 RESIDENT NW 3.76 6C51. 3.7L-07 3.6 E-0 7 2.CE-07 7.2E-10 0 NtAR*STNESIDENT NNd 4.1o 6695 2.50-07 2.5E-07 1.9t-07 4.5E-10 0 VLuflA3LF GARDEN ENE

u. 7 3 12U7.

1.00-05 1.eE-05 9.lE-00 6.3E-03 PD 0 VEufTAatt C/RDFN SC 4.07 6550. 1.5E-07

1. 5 E-0 7
1. 2 E- 0 7 4.0E-10 0

VLuFTA<ttL GriDEN 5SW 3.31 327. 3.3E-07 3.7C-07 3.CE-0 7 3.st-10 0 VEgFTAMLE L Af DEN SH 3.30 5633. 3.oE-07 ".oE-07 2.0L-07 3.cf-10 N 0 V i. u f i A u t E CARDEN W5W 1.75 2blo. 1.5f-06 1.5E-06

1. 3 E-Of.

1.LE-09 gl'qy. o VEoFredLF C?hDEN W 4.J1 7741. 2.3E-b7 2.JL-07

1. 7 E - 0 7 2.3E-10 0

VtvEranLF G tA D t re f:d 4.50 7242. 2.0E-07 . 60-07 2.0f-07 4.dc-10 W 0 S IT E IWUNDAklES N 0.58 933. 1.7E-05

1. 7 E - O ')
1. 6 E - 05 3.sf-08 g

0 SIT r elCNCAr!FS N f;L 0.64 1030. 1.1E-05 1.10-65

9. 7 E - Oc 3.2E-08 y

V 511 F M UN (' M' l F 5 NE C.83 1330. 7.4L-Oo 7.3C-06 6.5E-06 3.1E-08 46 ~ " 0 51T F U3 ul C A fs li 5 ENE 1.55 2494. 1.ot-Ou 1.6E-u6 1. E-06 9.9E-09 L. -- 0 5:TE vo 4CaalE S E 2.30 3j30. 3.4[-07 3.- 4 L - 0 7 2.ef-07 1.lf-C9 e../ 0 2 1Ir In nCARifs LLE 2.02 3251. 6.oE-07 6.5 E-0 7 5.4 E-0 7 2.M -09 '~ I O SliE ur UN C Ak i E S SL 0.53 933. 1.lt-US 1.1E-05 9.LE-C6

3. 7t -0 8 3

9 0 S li E hrrJ I A"! F 5 550 0.94 1513. 3.7E-Oc 3.7E-Of

3. 3 E- 0(

6.00-09 ^= 0 $ 1 T F. umr4 L AEl[ L 5

0. d 7 1 J0.

9.Jt-06 4.15-06

3. 7 L-OL 6.1E-09 na gp 0

$!T E ud% CARIES 55d 0.03 1336. 8.4E-06 0.3E-06 7. 4 E - C t. 1.CF-OS %g 0 3)IC CLtralia b l E S SW 0.54 369. 2.1E-05 1.1E-05 1.sE-05 2.2t-Od 0 SITE UUUN C AR I E S W5d 0.60 966. 1.L t'-0 5 1 7E-05 1.6 E - 05 2.05-08 g' O 51T E POO4 E At IES W 0.5u 901. 2.2E-05 2.JE-05

2. 0 t- 05 3.2E-C0 0

LIIE POUNCALIES WNd 0.40 966. 2.lE-05 2.1E-05 1.9E-C5 4.of-08 3 0 L Il l buu*4LARIES NW 0.79 1271. 1.2E-05 1.2 E-0 5 1.lt-05 3.2t-Od ~~ enc n..r.n.nvr< n. e r. 'sto. 1.or-es

1. t. r - 0 5

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