Text

Offsite Dose Calculational Manual
	ML19254D356
Person / Time
Site:	Brunswick
Issue date:	10/22/1979
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML19254D351	List: ML19254D350; ML19254D356;
References
	NUDOCS 7910250383
	Download: ML19254D356 (174)
	v • d • e

3 BRUNSWICK STEAM ELECTRIC PLANT OFFSITE DOSE CALCULATIONAL MANUAL (ODCM)

DOCKET NO. 50-325 CAROLINA POWER & LIGHT COMPANY

=)

1208 076 gg;3 7910250

TABLE OF CONTENTS

^h Section Title Pg Table of Contents i

List of Tables 11 List of Figures vii

1.0 INTRODUCTION

1-1 2.0 LIQUID EFFLUENTS 2-1 2.1 Monitor Alarm Setpoint Determination 2-1 2.2 Compliance with 10 CFR 20 (Liquids) 2-5 2.3 Compliance with 10 CFR 50 (Liquids) 2-9 3.0 GASEOUS EFFLUENTS 3-1 3.1 Monitor Alarm Setpoint Determination 3-1 3.2 Compliar.ce with 10 CFR 20 (Gaseous 3-12 3.3 Compliance with 10 CFR 50 (Gaseous)

)

3_30 4.0 RADIOLOGICAL ENVIRONMENTAL 4-1 MONITORING PROGRAM

)

APPENDIX A - Meteorological Dispersion A-1 Factor Computations APPENDIX B - Calculation of B and V.

B-1 Values For The Elevated Pfume APPENDIX C - Dose Parameters for C-1 Radiciodines, Particulates, and Tritium APPENDIX D - Lower Limit of Detectability D-1 d

1208 077 i

LIST OF TABLES 3

No.

Title Page 2.1-1 MPC's for Selected Radionuclides 2-4 2.3-1 A

Values for the Adult for the Brunswick 2-13 sr Steam Electric Plant

_A tI P for Liquid Dose 2-16 2.3-2 Values of e Calculations 3.1-1 Gaseous Source Terms 3-10 3.1-2 Dose Facters and Constants 3-Il 3.2-1 Releases from Brunswick Steam Electric 3-25 Plant 3.2-2 Distance to Controlling Locations as 3-26 Measured from the Brunswick Plant Center 3.2-3 Distance to Site Boundaries Based Upon 3-27 Brunswick Plant Center and Direction From the Stack 3.2-4 Dose Factors for Noble Gases and Daughters 3-2S 3.2-5 P; Values for an Infant for the Brunswick 3-29 Steam Electric Plant 3.3-1 thru R Values for the Brunswick Steam Electric 3 46 thru 3.3-19 Plant 3-64 4.0-1 Radiological Environmental Monitoring 4-2 Program A-1 X /Q Values at the Special Locations for A-5 Releases from the Turbine Buildings A-2 Depleted X/Q Values at the Special Locations A-6 for Releases from the Turbine Buildings A-3 D/Q Values at the Special Locations for A-7 Releases from the Turbine Buildings Ah X /Q Values at the Standard Distances for A-8 Releases from the Turbine Buildings

=l) 1208 078 li

LIST OF TABLES (continued) m No.

Title Page A-5 Depleted X/Q Values at the Standard A-9 Distances for Releases from the Turbine Buildings A-6 D/Q Values at the Standard Distances for A-10 Releases from the Turbine Buildings A-7 X/Q Values at the Special Locations for A-Il Releases from the Reactor Buildings A-8 Depleted X/Q Values at the Special Locations A-12 for Releases from the Reactor Buildings A-9 D/Q Values at the Special Locations for A-13 Releases from the Reactor Buildings A-10 X./Q Values at the Standard Distances for A-14 Releases from the Reactor Buildings A-ll Depleted X/Q Values at the Standard A-15 Distances for Releases from the Reactor Buildings A-12 D/Q Values at the Standard Distances for A-16 Releases from the Reactor Buildings A-13 X/Q Values at the Special Locations for A-17 Releases from the Stack A-14 Depleted X/Q Values at the Special A-IS Locations for Releases from the Stack A-15 D/Q Values at the Special Locations for A-19 Releases from the Stack A-16 X/Q Values at the Standard Distances for A-20 Releases ham the Stack A-17 Depleted X/Q Values at the Standard A-21 Distances for Releases from the Stack A-18 D/Q Values at the Standard Distances for A-22 Releases from the Stack A-19 Brunswick Plant Site Information to be Used A-23 for Ground Level Calculations with NRC "XOQDOQ" Program n-)

c9 120B d

m

5 LIST OF TABLES (continued) 7 No.

Title Pace A-20 Brunswick Plant Site Information to be Used A-24 for Elevated Release Calculations with NRC "XCQDOQ" Program B-1 Dose Parameters for Finite Elevated Plumes B-2 ENE Site Boundary B-2 Joint Frequency Distribution for ENE Sector (%)

B-3 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-3 Dose Parameters for Finite Elevated Plumes B-4 N Site Boundary B-4 Joint Frequency Distribution for N Sector (%)

B-5 Period 1-1-77 through 12-31 77, Brunswick Steam Electric Plant B-5 Dose Parameters for Finite Elevated Plumes B-6 NNE Site Boundary B-6 Joint Frequency Distribution for the NNE Sector (%)

B-7

]

Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-7 Dose Parameters for Finite Elevated Plumes B-S NE Site Boundary B-8 Joint Frequency Distribution for NE Sector (%)

B-9 Period 1-1-77 through 12-31-77, Brunsveick Steam Electric Plant B-9 Dose Parameters for Finite Elevated Plumes B-10 E Site Boundary B-10 Joint Frequency Distribution for E Sector (%)

B-11 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-Il Dose Parameters for Finite Elevated Plumes B-12 ESE Site Boundary B-12 Joint Frequency Distribution for ESE Sector (%)

B-13 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-13 Dose Parameters for Finite Elevated Plumes B-14 SE Site Boundary

-}_

1208 180 iv

LIST OF TABLES (continuted) l No.

Title Page B-14 Joint Frequency Distribution for SE Sector (%)

B-15 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-15 Dose Parameters for Finite Elevated Plumes B-16 SSE Site Boundary B-16 Joint Frequency Distribution for SSE Sector (%)

B-17 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-17 Dose Parameters for Finite Elevated Plumes B-18 S Site Boundary B-IS Joint Frequency Distribution for S Sector (%)

B-19 Period 1-1-77 through 12-31-77. Brunswick Steam Electric Plant B-19 Dose Parameters for Finite Elevated Plumes B-20 SSW Site Boundary B-20 Joint Frequency Distribution for SSW Sector (%)

B-21

}

Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-21 Dose Parameters for Finite Elevated Plumes B-22 SW Site Boundary B-22 Joint Frequency Distribution for SW Sector (%)

B-23 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-23 Dose Parameters for Finite Elevated Plumes B-24 WSW Site Boundary B-24 Joint Frequency Distribution for WSW Sector (%)

B-25 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-25 Dose Parameters for Finite Elevated Plumes B-26 W Site Boundary B-26 Joint Frequency Distribution for W Sector (%)

B-27 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-27 Dose Parameters for Finite Elevated Plumes B-2S WNW Site Boundary 1208 OBI v

m.

LIST OF TABLES (continued)

No.

Title Pane B-2S Joint Frequency Distribution for WNW Sector (%)

B-29 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-29 Dese Parameters for Finite Elevated Plumes

.B-30 NW Site Boundary B-30 Joint Frequency Distribution for NW Sector (%)

B-31 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-31 Dose Parameters for Finite Elevated Plumes NNW Site Boundary B-32 B-32 Joint Frequency Distribution for NNW Sector (%)

B-33 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant C-1 Parameters for Cow and Goat Milk Pathways C-15 C-2 Parameters for the Meat Pathway C-16 C-3 Parameters for Vegetable Pathway C-17

-)

1208 182

LIST OF FIGURES 3

No.

Title Pace 4.0- la Radiological Environmental Monitoring Program 43 4.0- 1 b Radiological Environmental Monitoring Program 4-6 3

1 t

=)

1208 08.,3 Vil

7

1.0 INTRODUCTION

This offsite i'ose Calculation Manual (ODCM) provides the information and methodologies to be used by Brunswick Steam Electric Plant (BSEP) to assure compliance with certain portions of BSEP's operating technical specification.

These portions are those related to liquid and gaseous radiological effluents. They are intended to show compliance with 10 CFR 20,10 CFR 50.36a, and Appendix I of 10 CFR 50.

This ODCM is based on " Radiological Effluent Technical Specifications for BWR's" (NU REG-0!+73, Draft),

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are provided elsewhere. These procedures will be utilized by the operating staff of BSEP to assure compliance with technical specifications.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM will be expated in the future. Any such changes will be properly reviewed and approved as indicated in the Administrative Control Section, Specification 6.13.2 of the BSEP Technical Specifications.

d 1208 084 1-1

2.0 LIQUID EFFLUENTS m

2.1 MONITOR ALARM SETPOINT DETERMIN ATION This procedure determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 x 10-4 pCl/ml for dissolved or entrained noble gases.

2.1.1 Setpoint Based on Analysis of Licuid Prior to Discharte The following method applies to liquid releases when determining the maximum accept-able discharge flow rate prior to dilution and determining the associated high-high alarm setpoint based on this flow rate for the Liquid Waste Effluent Monitor (D12RM-K604) when an analysis of the activity of ine principal gamma emitters has been made prior to each batch release.

]

2.1.1.1 Determine the maximum acceptable discharge flow rate prior to dilution:

Determine D (the minimum acceptable dilution factor):

a.

C.

1 (2.1-1)

D

=

MPC.

1 1

C g Radioactivity concentration of radionuclide "i" in the

=

liquid effluent prior to dilution (pCi/ml) from analysis of the liquid effluent to be released.

MPC g The liquid effluent radioactivity concentration limit for

=

radionuclide "i" (pCi/ml) from Tabic 2.1-1 or if not listed in Table 2.1-1 from 10CFR20 Appendix B, Table II, Col-umn 2.

T20s 085

..T>

2-1

b.

Determine f (the maximum acceptable discharge flow rate prior to dilution N'

(gpm)):

F (2.1-2) g

=

2D Dilution water. flow rate (gpm)

F

=

(n-1) 150,000 (gpm)

=

where n =

the number of operating circulating water pumps 2

=

An engineering factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.

c.

The liquid effluent discharge flow rate should be maintained at or below this f value.

)

2.1.1.2 Determine the monitor high-high alarm setpoint above background.

Determine C.R. (the calculated monitor count rate above background-(net a.

eps)).

C.R.

=

C E

(2.1-3) m m C

=

The total radioactivity concentration of the radionuclides m

(minus tritium and other radionuclides that do not emit gamma or X-ray radiation) in.the liquid effluent prior to dilution (pCi/ml).

E

=

The detection efficiency for the mixture of radionuclides m

in the liquid effluent prior to dilution (eps/pCi/ml) from RC&T file 3324.

r) 120g 086 2-2

b.

Determine HHSP (the monitor high-high alarm setpoint with background (eps)).

HHSP 2 C.R. + Bkg.

(2.1-4)

An engineering factor to prevent spurious alarms caused 2

=

by deviations in the mixture of radionuclides which affect the monitor response.

The background count rate (eps) due to internal contami-Bkg.

=

nation and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid.

L The monitor high-high alarm setpoint including background (eps), shall be c.

set at this HHSP value.

...y 2-3

TABLE 2.1-1 MPC's FOR SELECTED RADIONUCLIDES HTC (pCi/ml)

RADIONUCLIDE i

H-3 3 E-3 Na-24 3 E-5 Cr-51 2 E-3 Mn-54 1 E-4 Co-58 9 E-5 Fe-59 5 E-5 Co-60 3 E-5 Cu-64 2 E-4 Zn-69m 6 E-5 Sr-89 3 E-6 Sr-90 3 E-7 Sr-91 5 E-5 Zr-95 6 E-5 Mo-99 4 E-5 1-131 3 E-7 I-132 8 E-6 I-133 1 E-6

]

Cs-134 9 E-6 I-134 2 E-5 I-135 4 E-6 Cs-137 2 E-5 La-141 3 E-6 Np-239 1 E-4 Noble Cases 2 E-4 2-4 I209" Obb

,s)

m' 2.2 Comoliance with 10 CFR 20 (Lioulds) 2.2.1 Batch Releases 2.2.1.1 Prerelease The radioactivity centent of each batch release will be determined prior to release in accordance wita Table 2.1-2 of Appendix A of the BSEP's Technical Specifications. The BSEP will show compliance with 10 CFR 20 in the following manner:

The concentration of the various radionuclides in the batch release, determined in accordance with Table 2.1-2 of Appendix A of the BSEP Technical Specifications, is multiplied by the ratio of the maximum release rate of the potential batch release to the minimum dilution flow rate to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

3 C.

R

.\\fDF

( * -O

/

Conc;

=

where Cone; concentration of radionuclide i at the unrestric-

=

area, pCi/ml; C;

concentration of radionuclide i in the potentipi batch

=

release, pCi/ml; R

release rate of the batch, gpm;

=

MDF minimum dilution flow rate, gpm.

=

The projected concentration in the unrestricted area is compared to the concentrations in Appendix B, Table II of 10 CFR 20. These concentrations are given in Table 2.1-1. Before a release may occur, Expression ?.2-2 must be met.

1208 189 2-5

1; (Conc;/MPC;) < 1 (2.2-2) where maximum permissible concentration of radionuclide MPC;

=

i from Appendix B, Table II of 10 CFR 20, pCi/mi For the BSEP the liquid radwaste discharges go to the circulating water system.

Therefore, the minimum dilution flow rate (MDF) is a function of the number of circulating water pumps operating and the number of service water pumps operating. Each unit of the BSEP has 4 circulating water pumps and 5 service water pumps. Each circulating water pump provides 150,000 gpm. Each service water pump provides 7,500 gpm. For each unit, 2 service water pumps provide water to the nuclear header with one operating and the other as a spare. For each unit, 3 service water pumps provide water to the conventional header with 2 operating and the other as a spare. In the prerelease calculations, two circulating

)

water pumps and four service water pumps will be assumed operating.

The minimum dilution flow will be given by the following:

MDF = 2 150,000 + 2(7,500) gpm

= 330,000 gpm.

Releases from the BSEP liquid radwaste system may occur from the waste sample tank, floor drain sample tank, waste neutralizer tank and the detergent drain tank.

The maximum release rate is 200 gpm from all the release tanks except the detergent drain tank. The release rate for this tank is 50 gpm.

-)

1208 090 2-6

m 2.2.1.2 Postrelease The concentration of each radionuclide following release from a batch tank will be calculated in the unrestricted area in the following manner:

The total activity of radionuclide i released is divided by the actual dilution flow to obtain the concentration in the unrestricted area. This calculation is show: in the following equation:

Conc ik ADFk where the concentration of radionuclide i at the unrestricted Conc

=

ik area during release k, Ci/ml;

}

c ncentration of radionuclide i in the batch release during C

=

ik release k, gCi/ml; V

volume of liquid effluent released during release k, gal;

'k

=

actual volume of dilution water during release period k, ADF

=

k gal; To show compliance with 10 CFR 20, the following relationship must hold:

/MPC;) 5 1

(2.2-4)

F. ;(Concik The actual dilution water during release k (ADF ) is calculated by the following k

equation:

6 ADFk = (9.0 x 10 CW + 4.5 x 10 SW) At (2.2-5) k

3 1208 091 2-7

m where 6

5 1.5 x 10 gal / min x 60 min /hr; 9.0x10

=

5 flow rate from a circulating water pump, gpm; 1.5.10

=

conversion factor, min /hr; 60

=

total number of c.irculating water pumps operating at the CW

=

BSEP; 5

2 7.5 x 10' gal / min x 60 min /hr; 4.5x10

=

' 5x10 flow rate from a service water pump, gpm;

=

total number of service water pumps operating at the SW

=

BSEP; At duration of release k, hours.

=

k It should be noted that the terms CW and SW in Equation 2.2-5 are the total of each particular pump frcm both units operating during the release.

2.2.2 Continuous Continuous releases of liquid effluents do not presently occur at the BSEP. If they did occur the concentration of various radionuclides in the unrestricted area would be calculated using Equation 2.2-3 with C k, the concentration of isotope i in the continuous release.

To show compliance with 10 CFR 20, the rum of the concentration in the unrestricted area for both continuous and batch releases divided by MPC must again t,e less than 1.

_.}.

"~

1208 092 2-8

2.3 Comoliance With 10 CFR 50 2.3.1 Cumulation of Doses The dose contribution from the release of liquid effluents will be calculated once per 31 days and a cumulative summation of the total body and organ doses will be maintained for each calendar quarter. Since only batch releases occur at the BSEP the equations in the following sections will pertain only to batch releases. The dose contribution for all batch releases for the quarter will be calculated using the following equation:

i P D

E 1

A t C F e r

k i

ir k ik k where:

the cumulative dose commitment to the total body D

=

r or any organ r, from the liquid effluents for all releases, mrem; nd the leng;h of time of release k over which C k t

=

g F are averaged for all liquid releases, hours; k

the average concentration of radionuclide i,in C

=

ik undiluted liquid effluent during release k from any liquid release, pCi/ml; the site related ingestion dose commitment factor A

=

ir to the total body or any organ r for each identified principal gamma and beta emitter i, mrem-ml per br-pCi;

=3 1208 093 2-9

A radiological decay constant for radionuclidei, hours -

=

.693 (tg);

(t,);

y radiological half life of radionuclidei, hours;

=

t

=

average transport time to reach the point of exposure, p

hours; Fk the near-field average dilution factor for C during

=

ik any liquid effluent release. Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the site discharge structure to unrestricted receiving waters times 1.

(1 is the site-specific applicable factor for the mixing effect of the BSEP discharge structure as defined in NUR EG -0133.)

Yk

=

ADFk where V and ADF, are as defined in Equation 2.2-3.

The dose factor A w s calculated for an adult for each isotope using the following ir equation:

5 (5 Bl;

+ 21BF;) DFir A

1.14x10 (2.3-2)

=

ir where 1.14x10' =

10 pCi x 10 ml x 1 vr 6

oCi 1

3760 hr '

5 adult invertebrate consumption rate from Table E-5

=

of Regulatory Guide 1.109 Rev. I, kg/yr; O i

..g.

)}00 2-10

BI; bicaccumulation factor for radionuclide i in invertebrates a

from Table A-1 of Regulatory Guide 1.109 Rev 1,. pCi/kg per pCi/1; adult fish consumption rate from Table E-5 of 21

=

Rebulatory Guide 1.109 Rev.1, kg/yr; BF; bicaccumulation factor for radionuclide i in fish from Table

=

A-1 of Regulatory Guide 1.109 Rev.1, pCi/kg per pCi/1; DF dose conversion factor for radionuclide i for adults for

=

ir a particular organ r from Table E-Il of Regulatory Guide 1.109 Rev 1, mrem /pCi.

A values for an adult at the BSEP are presented in Table 2.3-1. Table 2.3-2 ir presents the radiological decay constant for the various radionuclides of Table 2.3-

)

I along with an evaluation of the term exp[-A t ] with t equal to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i p

The cumulative doses to the total body and all organs from all batch releases for a quarter and for a calendar year are compared respectively to one half the design objective doses and to the design objective doses. Expressions 2.3-3 through 2.3-6 should hold for the BSEP to show compliance with Technical Specifation 1.1.3.1 of Appendix A of the BSEP Technical Specifications. It should be noted that because releases from the 2 units cannot be separated, limits are double frem what they would be for a single unit.

For the calendar quarter, D

3 mrem total body (2.3-3) r D

10 mrem any organ (2.3 4) r

)}00

=)

2-11

3 For the calendar year, D

6 mrem total body (2.3-5) r D

20 mrem any organ (2.3-6) r The quarterly limits given above represent one half the annual design objective of Section II.A of Appendix I of 10 CFR 50. If any of the limits in Expressions 2.3-3 through 2.3-6 are exceeded a special report pursuant to Section IV.A of Appendix !

of 10 CFR 50 must be filed with the NRC.

2.3.2 Projection of Doses Doses reso. ting from the release of liquid effluents will be projected once per month. The doses will be projected using Equation 2.3-1 with F, now based upon g

the minimum dilution flow rate (MDF) as given in Equation 2.2-1 rather than ADF 'k C

is based upon the projected releases for the remainder of the calendar quarter.

g h

1208 096 4

2-12

7

- m m 4 m q P t g 4 ~ N 4.

M N CN~4NmNN<m eme wCCCCCCCCCCGCCCCCCGm Cw=CCGGOOCCC W I I

I l l 1 1 I

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==m-McCCCCCCCCCCCCCCCCCCCCCCCCCCCGCC wl 1 8 1 1 1 1 8 8 1 8 1 1 l l l l l l 1 9 1 9 1 wm Zuwaw-wwwwwww wawwwwwwwwwwwwww-ww

~Z CNCNCRCCCCCCCCCMCCCCCCCOCCCCCCCC p c "m?

CNwNCCCCCoceNCCCCCCCCCCCCCCC W-E e e o e e e e o e o e e o e e e e e e o e e e e e o e o e e e ZAJ NNWC*NNCCCCCC mWCCCCCCCCCCCCCCC C

E WUs

>=

-m-Cw

-wwm--=w

-====w w =

mm-----

h CO CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC WW l C l l l 1 8 l l 1 8 l l l l 1 8 8 8 1 1 1 0 l l l l l 1 1 1 a w w w w w w w w w w w w w w w w w w w "+ w w y w w w a v w

=UC w w I Cwd CNCNCCCCCCCCCCCCCCCCCC J CCCCCCCCC RCwQ M C P. C M C C C C C C C C C C C C C C C fs C C C C C C C C C C e

6=

e e e e e e e e e o e e e o e e e e e e a

e e e o e e e e o e N's WNNfCmCCCCCCCCCCCCCCCC CCCCCCCCCC

W-C E o

mm m_,Cm_-

-m--~,-~Nm~__~.CC_mCN~

Cmm

>CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC CC,a C l l

I l l 1 1 F i l l C~C-C..m-

~~C-~

.m.mwwwwmwwwmm_w

=wmmwwmwwmmwmmmwww

-m

=

ec

..--~~mo.~Cm

~m=

..m___,~~..

g=

=-

m~m

.Qs m_=

- e e e. e e e o. e. e... e. e e e e o e e. e e o e o e

=>m

~N

.,_rc-_

_--~.-.m~

C-m

--~~-.

wV&

f."=Y

_,_e_-~,

N-m_~

~---~CC_________

CCCCCCCCCCCCCCCCCCCCCCCCCCC, C C C C,

=

l l

l l,

I l l i l l i ml I=

wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww

=

>NC~eceCmemm<NemeCCCereCCCCCCeCC a" C T. C C C W # 7. C M C C O. N. W. MCCC.CCCCCC

<CM

. e.... e.

. e e. e e...

.. e e..

NNVW ON ded 4MMNN.CCCC@**CCCCCCCCC

~-

~--

,--C~--C

_CCCCCCOCOCCCCCCCCCCCCCCCCCCCCCC W I I

I I I I i 1

1 1 1 I I I I

i m__ _wwww-w-www_

_._-w--

6 CC.h W CCCacCCCNCa mCCCCCC&"CC4mCNC C C 3 7 C. C D e. C C C. C C C. 7 N m #. C W C m <

C C t. W C. C C C M e.. e e e

. e e. e..

C-.-=CC.CCC

~C-mCCCCCC._o e

e e e o e m..C E

W= -

~-...

-=m

=e-C_~C__N-

-~-

.......e.

m=CC====e,Cem-me y

Q EZZwwCC-M C Z Z % c E C C C.c.E.2 m C=UZhuhAwwuGZZWNN CCCcc=

1208'1,97 Z

2-13

.q6 g

T AillE 2.3-1(CDNT*0)

VALIIES FOR IllE A00LT FOR T ilE A"HRil:1541CK STEAM ELECTRIC PLAtli (fl R E P /ll R PfR HICPO-C1/PL)

NU CL II)E Oflh E LIVER T.Il00Y illy R 101)

KIONFY LilN G GI-LL1 19 95 1.59E 01 5.110 00 1.46F 00 0.00E-01 0.0?! 00 0.00E-01 1.62E 04 ZR 9T 0.0l[-01 1.700-01 0.13L-02 0.00L-01 2.60t-01 0.00E-01 5.510 04 NO 95 4.47f 02 2.49L 02 1.34[ 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 80 99 0.00[-01 1.20E 02 2.43E 01 0.00E-01 2.09E 02 0.00E-01 2.96E 02 IC 9 '3 M 1. 3 0 f - t) 2 3.660-02 4.66E-01 0.00E-01 5.56E-01 1.T9E-02 2.17E 01 10101

1. 31 L - 02 1.92E-02 1.000-01 0.00E-01 3.46L-01 9.01E-03 S.770-14 Rt103 1.07F 02 0.00E-01 4.60E 01 0.00E-01 8.

JTL 02 0.00E-01 1.25E 04 RU105 0.09F 00 0.00E-01 3.51E 00 0.00E-01 1.15E 02 0.000-01 5.44L 03 RU106 1.59E 03

0. 0 0 L- 01 2.010 02 0.000-01 3.06L 03 0 00L-01 1.03E 05 AG110M 1.56E 03 1.45F 03 0.600 02 0.900-01 2.05E 03 0.000-01 5.91L 05 If125H 2.lTE 02 7.06E 01 2.91E 01 6.5?E 01 0.02E 02 0.00E-01 0.66E 02 lll?7N 5.40L 02 1.960 02 6.60L 01 1.40E 02 2.23L 03 0.00E-01 1.840 03 IF121 0.90f 00 3.20E 00 1.930 00 6.60L 00 3.630 01 0.00E-01 7.03L 0?

IF129P 9.31E 02 3.47f 02 1.47E 02 3.20E 02 3.09E 03 0.000-01 4.69E 03 y

1I129 2.540 00 9.55E-01 6.19E-01 1.95L 00 1.0TL 01 0.00E-01 1.92E 00 TE131M l.40E 02 6.05E 01 5.710 01 1. 0I10 02 6.94E 02 0.00E-01 6.00E 03

~^

10131 1.59E 00 6.66F-01 5.03f-01 1.310 00 6.99E 00 0.00E-01 2.26E-01 TE132 2.04E 02 1.32E 02 1.240 02 1.46E 02 1.270 03 0.00E-01 6.24E 03 1 IJO 3.96E 01 1.17E U2 4.61E 01 9.91E 03 1.02E 02 0.00F-01 1.01E 02 I 131 2.18E 02 3.l?E 02 1.79E 02 1.02E 05 5.350 02 0.00E-01 8.23E 01 1 132 1.06L 01 2.05E 01 9.961: 00 9.96E 02 4.54L 01 0.00E-01 5.35E 00 1 133 7.45E 01 1.30E 02 3.95E 01 1.90E 04 2.26L 02 0.00F-01 1.16E 02 1 134 5.56I 00 1.51E 01 5.40E 00 2.62E 02 2.40L 01 0.00E-01 1.3?E-07 1 115 2.32F 01 6.00F 01 2.240 01 4.01E 03 9.75E 01 0.000-01 6.07E El

(($

C5134 6.040 03 1.63F 04 1.33E 04 0.00F-01 5.27E 03 1.TSE 03 2.85E 02 CZ)

E 5136 T.160 02 2.03E 03 2.04E 03 0.00E-01 1.57L 01 2.161- 02 3.21L 02 Co ES131 0.7FF 03 1.20F 04 7.1150 03 0.00E-01 4.07F 03 1.35E 03 2.32L 02 C5130 6.070 00 1.200 01 5.94E 00 0.00E-01 0.81E 00 0.T0E-01 5.12E-05 L)

QAt19 T.05E 00 5.590-03 2.30E-01 0.00E-01 S.23E-03 3.1TE-03

!.39E 01

'O D A 14 0 1.64f 93 2.06E 00 1.00F 02 0.00E-01 T.02L-01 1.100 00 3.30E 03 DA141

3. 0 l f 00 2.00E-03 1.291-01 0.00E-01 2.600-03 1.630-01 1.fl C F - 0 9 Co

J

,]

I Afl L E 2.3-1(CONT *ll)

A V1LilFS FOR THE AUUI I FOR Till "0 R il'I Sil l C K STEAP F LE C ill T C P L A ri l 01REN/IIR PER flICRO-C T /"L )

NUCllHE 110 h E LIVER T.UUDY IllV R I HO K 111N!! Y L tlN fi

., f -L t i PA142 1.72E 00 1.77E-03 1.00E-01 0.00E-01 1 500-03 1.00F-01 2.41E-19 L A 14 0 1.5 F I 00 7.94E-01 7.10E-01 0.000-01 0.00L-01 0. 0 ') E - 01 S.03L 04 LAl42 8.061.-02 1.67E-02 9.13L-03 0.000-01 0.00E-01 0.00L-01 2.60L 02 0E141 3.430 00 2.320 00 2.630-01 0.00E-01 1.000 00 0 000-01 0.060 03 CF141 6.04E-01 4.160 02 4.94I-02 0.00E-01

1. '17 L -01 0.000-01 1.670 04 00144 1.79I 02 T.47F 01 9.590 00

( 00E-01 4.43E 01 0.00L-01 6.04E 04 PR143 S.79E 00 2.J/E 00 2.87E-01 0.00E-Ul

1. 3 j. f t

y3
.o i
The constant for noble gas radionuclide "i" accounting for l
V
=
g the gamma radiation from the elevated finite plume (mrem / year / pCi/sec) from Table 3.1-2.
N 1, _
q e
".a, g,{fN
- l;-
3.1.2.3' Determine Q based upon the skin exposure limit.
t (3.1-9) 9l 3000 Q
=
(t(x79)s+l1B)S d,
t i
g 1
.:.~)
3-5 1208 '05
3 L; (X/Q)s + 1.1 B; =
The total skin dose coustant for long term releases (greater '.han 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months /ycar) due to emissions from noble gas radionuclide "i" (mrem / year /pCi/sec) from Table 3.1-2.
3.1.2.4 Determine Ct (the total maximum acceptable radioactivity concentration of noble gas radionuclides in the gaseous effluent ( pCi/sec/cfm)).
9 (3.1-10) t C
=
t f
NOTE:
Use the lowest of the Q values obtained in Sections 3.1.3.2 and t
3.1.3.3.
L The maximum acceptable effluent flow rate at the point f
=
of release (cfm) based on design flow rates.
86,000 cfm (Stack)
]
=
-.5 Determine the monitor high-high alarm setpoint above background:
Determine CR (the calculated monitor count rate above background attri-buted to the noble gas radionuclides (net eps)).
C, (3.1-11)
CR
=
Em The detection efficiency of the monitor for the " mix" of E
=
m noble gas radionuelides in the gaseous effluent (pCi/sec/cfm. cps) from RC&T file 3304.
b.
Determine HHSP (the monitor high-high alarm setpoint with background (eps)).
3-6 1208 100
=
T" CR + Bkg.
(3.1-12)
HIISP 3
Fraction of the radioactivity from the site that pay be T
=
m released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways.
0.40 for the Stack Monitor (D12-RM-K600 A&B).
=
The background count rate (eps) due to internal ecntami-Ukg.
=
nation and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid.
The monitor high-high alarm setpoint including background (eps), shall be c.
set at or below the HHSP value determined above.
3-7 1208 107
3.1.3 Condenser Air Eicetor Monitor Alarm Setooint Determination This procedure determines the alarm setpoint for the Condenser Air Ejector Monitor that will provide reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a fraction of the limits of10CFR100 in the event of an inadvertent release via the condenser air ejector.
3.1.3.1 The following method applies to gaseous releases via the Unit I and 2,
~
Condenser Air Ejectors when determining the high-high alarm setpoint for the Condenser Offgas Radiation Monitors (D12-RM-K601 A&B).
a.
Determine Cm (the total radioactivity concentration of the noble gases)in the condenser air ejector gas (pCi/sec/cfm).
9 t C
(3*1'13}
m i
Q t The total release rate ( pCi/sec) for the noble gas radio-
=
nuclides (based on NUREG 0133).
5.85 E+6 Ci/see
=
f The main condenser air inleakage rate plus the radiolytic
=
gas flow rate.
122 scf m
=
b.
Determine the monitor high-high alarm setpoint above background.
1.
Determine M.R. (the calculated monitor response attributed to the noble gas radionuclides (mR/hr)).
C M.R.
=
.1-1 0 Em E
The detection efficiency of the monitor for the " mix" of
=
m noble gas radionuclides in the gaseous stream
( Ci/sec/mR/hr.cfm) from RC&T file 3",24.
"2Ob
'd i
3 2.
The monitor high-high alarm setpoint (mR/hr) should be set at or below the M.R. value determined above.
L 3-9 1208 109
d
' TABLE 3.1-1 CASEOUS SOURCE TERl!SI TURBINE BLDC VENT REACTOR BLDC VENT STACK RADIO!!UCLIDE Ag (C1/yr)
Sg Ag (C1/yr)
Sg Ag (C1/yr)
St 3.0Ei4 2.86E-2 Kr-83m Kr-85m 6.8E+1 2.02E-2 6.0E0 1.73E-2 5.8E+4 5.52E-2 Kr-85 2.0E+2 1.90E-4 Krv87 1.3E+2 3.87E-2 6.0E0 1.73E-2 1.7Et5 1.62E-1 Kr-88 2.3E+2 6.85E-2 6.0E0 1.73E-2 1.9Et5 1.81E-1 2.0Et3 1.90E-3 Kr-89 Xe-131m 1.6Et2 1.52E-4 Xe-133m 3.0E+3 2.86E-3 w
J.
Xe-133 2.5Et2 7.44E-2 1.3E+2 3.75E-1 8.6Et4 0.19E-2 o
Xc-135m 6.5E+2 1.93E-1 9.2E+1 2.65E-1 7.4E+3 7.05E-3 Xe-135 6.3E+2 1.88E-1
6. 8E t t 1.96E-1 2.3Et5 2.19E-1 Xe-137 6.8Et3 6.48E-3 Xe-138 1.4Ef3 4.17E-1 1.4E+1 4.03E-2 2.7E15 2.57E-l Ar-41 2.5E+1 7.20E-2 Total 3.36E+3 3.47E+2
1. 05Ei 6
<l.0E-1
1. Source terms are based upon CALE code and not actual releases.
O.
CD
^1~
a
i0 J
)
TABLE 3.1-2 DOSE FACTORS AND CONSTANTS TOTAL WilOLE BODY TOTAL SKIN TOTAL BODY TOTAL SKIN IRADIONUCLIDE DOSE FACTOR DOSE FACToll DOSE CONSTANT FOR DOSE CON TANT FOlt
~
' (K )
(L 4 1.1 M;)
LONG TEllM llELEASES LONG TEllM RELEASES g
O (mrem /yr/pCi/m )
(mrem /yr/pCi/m )
i i
s i
(mrem /yr/pCi/sec)
(r.. rem /yr/pCi/sec)
Kr-83m 7.56 E-2 2.12 E+ 1 1.66 E-9 1.54 E-7 Kr-85m 1.17 E+ 3 2.81 E+ 3 9.18 E-5 2.14 E-4 Kr-85 1.61 E+ 1 1.36 E + 3 1.36 E-6 6.12 E-5 Kr-87 5.92 E+3 1.65 E44
'#.17 E-4 1.12 E-3 Kr-88 1.47 E + tl 1.91 E e ts 1.08 E-3 1.89 E-3 Kr-89 1,66 E + ts 2.91 E 4 6.55 E-4 1.53 E-3 Xc-131m 9.15 E+ 1 6.48 E e 2
' 2.17 E-5 5.8t# E-5
[
Xe-133m 2.51 E* 2 1.35 E+ 3 1.6's E-3 7.30 E-5
~
Xe-133 2.9t# Ee2 6.9t# E*2 1.72 E-5 4.28 E-5 Xe-135m 3.12 E + 3 te.41 E* 3 2.17 E-4 3.93 E-4 Xe-135 1.81 E+3 3.97 E + 3 1.47 E-4 3.25 E-4 Xe-13/
1.42 E + 3 1.39 E *4 5.64 E-4,
6.30 E-4 1.t 3 E
4 6.61 E ts 1.27 E-3 Xe-138 8.8 3 E + 3 Ar t 1 8.84 E+3 1,29 E e 4 7.86 E-4 IJ#2 E-3 0
CD W
M s
3.2 Comoliance With 10 CFR 20 (Gaseous) 3.2.1 Noble Cases The gaseous effluent monitors setpoints are utilized to show compliance with 10 CFR 2C for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet 10 CFR 20 limits may actually be met. Therefore, the following methodology has been provided in the event that if the alarm trip setpoints are exceeded a determination may be made as to whether the actual releases have exceeded 10 CFR 20.
The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem /yr to the total body and 3000 mrem /yr to the skin. Based upon NUREG-0133, the following are used to show compliance with 10 CFR 20:
I;
\\'iks + K; (X/Q)y ky
< 500 mrem /yr (3.2-1)
)
1 L (X/Q)s + 1.lB; qs ' (b
I*IM ) (X/9)v Sv
$3000 mrem /yr j
i i
(3.2-2) where K;
the total body dose f actor due to gamma emissions
=
3 for noble gas radionuclide i, mrem /yr per pCi/m ;
L; the skin dose factor due to beta emissions for noble
=
3 gas radionuclide i, mrem /yr per pCi/m ;
M; the air dose factor due to gamma emissions for noble
=
gas radione'ide i, mrad /yr per gCi/m ;
=)
3-12 1208 112
N the constant for each identified noble gas radionuclide V;
=
i accounting for the gamma radiation from the elevated finite plume, mrem /yr per pCi/sec; the constant for long-term releases (greater than 500 B;
=
hrs /yr) for each. identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad /yr per Ci/sec; the ratio of the tissue to air absorption coefficients 1.1
=
over the energy range of the photon of interest, mrem / mrad.
k3 the release rate of noble gas radionuclide i in gaseous
=
effluents from free-standing stack, pCi/sec; ky the release rate of noble gas radionuclide i in gaseous
=
effluents from all vent releases, Ci/sec.
At the Brunswick Steam Electric Plant (BSEP) gaseous releases may occur from:
1.
the turbine building vent 2.
the reactor building 3.
the stack Releases from the turbine building are ground level. The source of these releases are steam leakage thrcugh valve stems, pump seals, and flanged connections.
Releases from the reactor building are considered mixed mode in nature and the sources are also leakage through the valve stems, pump seals, and flanged connections. Releases from the stack are considered elevated. Their sources are the main condenser's steam jet air ejectors, exhaust from the radwaste building ventilation system, mechanical vaccuum pump exhausts during startup and gland seal of f-gases.
Noble gas releases may occur from all three points. To show compliance with 10 CFR 20, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release points for the BSEP.
T 1208 113
~='
3-13
3 For the total body dose 1
VQ
+1 K; (X /Q)rb $
X /9)tb q
$ 500 mrem /yr i
s rb tb.
(3.2-3)
For the skin dose 1.lM; (X /Q)rb $
~(
/9}+b q
< 3000 mrem /yr 1; L; ( X/Q)s + 1.lB; q 1;
L;
+
s rb tb (3.2-4) where k
release rate of radionuclide i from the stack, pCi/sec;
=
s release rate of radionuclide i from the two reactor buildings, g
=
pCi/sec; release rate of radionuclide i from the two turbine buildings, g
=
tb pCi/sec;
( X /Q)s=
annual average relative concentration for releases from the stack, sec/m ;
( X /Q)rb=
annual average relative concentration for releases from the reactor buildings, sec/m ;
( X /Q)tb =
annual aver ge relative concentration for releases 3
from the turbine buildings, sec/m.
All other terms remain the same as those defined previously.
=3 1208 114 3-u
m The determination of controlling location for implementation of 10 CFR 20 for noble gases is a function of the radionuclide mix, isotopic release rate and the meteorology.
The incorporation of these variables into Expressions 3.2-3 and 3.2-4 result in the following expressions for the controlling location for the BSEP. This location is the ENE site boundary.
For the total body I
V; Qj
+ 1 K; (7.2 x 10-k
+ 4.2 x 10-6 tb )
6 500 mrem /yr s
rb (3.2-5)
For the skin 1.lB )
k
+ I; (L;
E (6.3 x 10-9 L 1.W ) ( 7.2 x 10
+
~
i rb s
4.2 x 10-6 f
)-
5 3000 mrem /yr (3.2-6) 1 tb -
The radionuclide mix was based upon source terms calculated using the NRC GALE code. They were calculated based upon the present operating mode of the BSEP.
They are presented in Table 3.2-1 as a function of release point. It should be noted however that the releases in Table 3.2-1 do not reflect the actual BSEP release data to date.
The releases to date have been substantially less. This table was used as a calculational tool to determine the controlling location.
The X/Q values utilized in the equations for implementation of 10 CFR 20 are based upon the maximum long-term annual average X/Q in the unrestricted area.
Table 3.2-2 presents the distances from the reactor and turbine buildings to the nearest unrestricted area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal. Table 3.2-3 presents the distances and directions from the stack to the same site boundaries of Table 3.2-2.
Note that only distance has changed in relation to Table 3.2-2.
=h 3-15
D Long-term annual average (X/Q) values for the stack building release points from the BSEP to the speci l l, reactor build presented in Appendix A. A description of their derivation iocatio a
Appendix.
building, reactor buildings, and stack were o s also provided in this r ne respectively of the Appendix.
rom Tables A-1, A-7, and A-13 To determine the controlling location for implementati three highest site boundary ETQ values for on of 10 CFR 20, the two or conjunction with the radionuclide mix and release rate feach Since mixed mode and elevated releases occur fr or each release point.
value may not decrease with distance (i.e., the site b t eir maximum k-'TQ highest ETQ values).
~
oundary may not have the Therefore, long-term annual average M values we calculated at the the Appendix A.
mid-ccint of the 10 standard distances as given in Tab e
distance greater The highest two or three ~f"/Q values for each releas than point at a radionuclide mix to determine the controlling locatiot the
}
of release point mix and meteorology dominates in the d tA particula n.
trolling location. For the BSEP,it is the stack e ermination of the con-ENE site boundary.
and the controlling location is at the Values for K;, L and M;, which were used in the d j
location and which are to be used by the BSEP in Expressietermina compliance with 10 CFR 20, are presented in Table 3 2 4ons3.2-5 and 3.
from NUREG-0472 Revision 0 and were taken from T b These values originate Guide 1.109 Revision 1.
e B-1 of NRC Regulatory a
microcuries to picocuries for use inExpressions 3.2-6 to convert Values for V Equations 3.2-7 and 3.2-8.and B; for the finite plume model can be shown in the 16 sectors using the NRC code RABFINThey were calcula sectors are presented in Appendix B.
. Values of V; and S; for each of the 16
~-)
/
1208 14tu 3-16
B K
jk li F El I
A a
j (3.2-7) yyy i
rd ~[kY "j
I the results of numerical integration over the plume
=
spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (u;)
and atmospheric stability class k for a particular wind direction; K
=
a numerical cor., tant representing unit conversions, 260 mrad (radians) (m ) (transformation) 16 sectors sec (Mev) (Ci) 2rr radians 10-6 Ci (3.15x107 sec) pCi yr 2.1x10" mrad (m ) (transformation)/yr(Mev) ( Ci);
=
d the distance from the release point to the receptor r
=
)
iccation, meters; u;
the mean wind speed assigned to the jth wind speed
=
class, meters /sec; fjk the joint frequency of occurrence of the jih wind speed
=
class and kth stability class (dimensionless);
A;j the number of photons of energy corresponding to
=
the Ith energy group emitted per transformation of the ith radionuclide, number / transformation; Ej the energy assigned to the Ith energy group, Mev;
=
p3 the energy absorption coefficient in air for photon
=
energy E, meters.
j
=d 1208 ii7 3-17
The V factor is computed with conversion from air dose to tissue depth dose, thus; I
A E I
-F T jk li#a j
e T d (3.2-3)
.j 1.1 K vyy d
jkl u.
]
where:
T the tissue energy absorption coefficient for photons
=
2 of energy E, cm /gm; g
Td the tissue density thickness taken to represent the
=
2 total body dose (5 gm/cm );
1.1 the ratio of the tissue to air absorption coefficients
=
over the energy range of photons of interest, mrem / mrad.
3.2.2 Radioiodine and Particulates The dose rate in unrestricted areas resulting from the release of radiciodines and particulates with half lives greater than 8 days is limited to 1500 mrem /yr to any organ. Based upon NUREG-0133 the following is used to show compliance with 10 CFR 20:
v) 51500 mrem /yr U.2-9)
F.; P; (W 9
W s
is V
where
. P; dose parameter for radiolodines and particulates with
=
half lives greater than S days based upon the critical organ and the,ost restrictive age group:
mrem /yr per pCi/m for inhalation pathways and for,
=
tritium; mrem /yr per Ci/sec per m-2 for food and ground
=
plane pathways;
-)
~
1208 118
h;3 the release rate of radionuclide i, in gaseous effluents
=
s frorn free-standing stack, pCi/sec; Q ;y the release rate of radionuclide i in gaseous effluents
=
from all vent releases, gCi/sec; 4'
the highest calculated annual average dispersion parameter
=
y for estimating the dose to an individual at the controlling location due to all vent releases; W
= sec/m for the inhalation pathway; y
-2 W
= meters for the food and ground plane pathways; W
the highest calculated annual average dispersion parameter
=
s for estimating the dose to an individual at the controlling location due to stack releases; W = sec/m for the inhalation pathway; s
-2 W = meters for the food and ground plane s
pathways.
Radiciodine and particulates may be released from the stack, reactor buildings and the turbine buildings of the BSEP. To show compliance with 10 CFR 20, Expression 3.2-9 is now modified to incorporate the various release points for the BSEP:
T.; P; (W 9
tb q) 51500 mrem /yr (3.2-10) s rb S
^
s rb tb where W
the annual average dispersic 3arameter for the stack;
=
s
_.}
3-19 1208 119
the annual average dispersion parameter for the W
=
rb i
reactor buildings; annual average dispersion parameter for the turbine buildings;
=
tb release of radionuclide i from the two reactor buildings, pCi/sec; g
=
release of radionuclide i from the two turbine buildings, Ci/sec; Q
=
release of radionuclide i from the stack, pCi/sec.
Q
=
All other terms are the same as those defined previously.
In the calculation to show compliance with 10 CFR 20 only the inhalation, ground plane, cow milk, and goat milk pathways are considered for the BSEP. In deter-mining the dose at a particular location, W is a function of pathway. For the food and ground plane pathways W is in terms of D/Q (i.e., deposition). If the inhalation pathway is considered, W is in terms of X/Q.
Incorporation of the various
}
pathways into cxpression3.2-10 results in the following:
(P
+P
)
I P
( X/Q)s q +
(X/Q)rb q
( X/Q)tb
~i i
j
+
I s
rb tb.
G M
1
+ (D/Q)tb q
$1500 mrem /yr (3.2-11)
-(D/Q)s 9i (D/Q)b 9
+
s rb tb-where P;I dose parameter for radionuclide i for the inhalation
=
3 pathway, mrem /yr per pCi/sec ;
dose parameter for radionuclide i for the ground plane P
=
j pathway, mrem /yr per gCi/sec per m-2 ;
dose parameter for radionuclide i for either the cow milk P
=
j or goat milk pathway, mrem /yr per pCi/sec per m-2 M
_3 1208 120 3-20
(X7QI nnual verage relative concentration for rb =
releases ' rom the reactor buildings, sec/m ;
(XWtb =
annual average relative concentration for releases from the turbine buildings, sec/m ;
(X/Q)s annual average relative concentration for
=
3 releases from the stack, sec/m ;
(D/Q)rb annual average deposition for releases from the
=
reactor buildings, m-2 ;
(D/Q)tb annual average deposition for releases from the
=
turbine buildings, m-2 ;
(D/Q)s annual average deposition for releases from the
=
stack, m-2,
In the case of tritium the W parameter for the food patfiway (cow or goat milk), is based upon X/Q.
Since tritium is a weak beta emitter, the ground plane contribution is zero for tritium. Therefore, the left-hahd side of Expression 3.2-I can be written as the following:
For tritium (P
D P
)
T T
T
-(#'I9)s 9T I XI9)rb 9T f X#9)tb 9
=
+
^
+
T I
M s
rb tb-(3.2-12) where b
dose rate due to tritium releases, mrem /yr;
=
T 1208 121
i) 3-21
P dose parameter for tritium for the inhalation pathway,
=
TI mrem /yr per pCi/m ;
PT dose parameter for tritium for the milk pathway, mrem /yr
=
per pCi/m ;
h release rate of tritium from the stack, Ci/sec;
=
Ts QT release rate of tritium from the two reactor buildings, pCi/sec;
=
g QT rele se rate of tritium from the two turbine b sildings,
=
tb pCi/sec.
Since P for tritium equals 647 and P; equals 2380, Equation 3.2-12 reduces j
I to:
b 3.0 x 10 (X7QI 3
IX/Cl T
s T
IX/9}rb T
=
+
tb T
s rb b
(3.2-13)
)
To show compliance with 10 CFR 20, Expressions 3.2-11 and 3.2-13 are evaluated first at the limiting site boundary. It should be noted that the sum of the dose rates from radiciodines and particulates and from tritium must be summed and their combined dose rate less than 1500 mrem /yr to show compliance with 10 CFR
20. If the 1500 mrem /yr limit is exceeded at the limiting site boundary when all pathways are considered present at the site boundary but the inhalation pathway contributes less than 1500 mrem /yr, then Expressions 3.2-Il and 3.2-13 are evaluated at the limiting real pathway location.
The limiting site boundary location is 0.91 miles NE. Expression 3.2-11 becomes:
For radiciodines and carticulates:
1; P; (3.3 x 10-8
+ 1.7 x 10-7 Q
1.9 x 10-6 q
).
+
P
) (1.3 x 10-9 h;
+ 3.3 x 10-9 d 1.2 x 10-3
) <l500 mrem /yr E (P;G
+
i j
M j
s rb
'tb (3.2-16)
=s) 1208 122 3-22
For the BSEP the limiting real pathway location is the cow milk pathway 0.79 miles 3
SSE. At this location Erpression 3.2-Il becomes:
E P;I (1.0 x 10-8 h;s 6.3 x 10-8 k
+ 7.0 x 10 f).
-6 t
rb tb 1
i
+ P'.M ) (5.4 x 10 h*. + 6.0 x 10 h*.
-10
-10
-8 k ) 61500 mrem /yr 1
(P 1.4 x 10
+
G s
r5 tb (3.2-15)
For tritium at the limiting site boundary Equation 3.2-13 becomes:
For tritium:
b 3.0 x 10 (3.3 x 10-8 h.g.
1.7 x 10-7 h 1.9 x 10-6 h)
(3.2-16)
=
+
+
T T
s rb
.b At the ilmiting real pathway location Equation 3.2-13 becomes:
For tritium:
b 3.0 x 10 (1.0 x 10-8 h
6.8 x 10 h
7.0 x 10 h)
(3.2-17)
-8
-6
=
+
+
T Tg The determination of controlling location for implementation of 10 CFR 20 for radioicdines and particulates is a function of the same two parameters as for noble gases plus a third, actual receptor pathway location. The incorporation of these parameters into Expression 3.2-11 results in the respective expressions at the controlling locations. The radionuclide mix was again based upon the source terms calculated using the GALE code. The mix and the source terms are presented in Table 3.2-1 as a function of release point.
In the determination of the controlling site boundary location the highest two or three site boundary D/Q values for each release point were utilized in conjunction with the radionuclide mix and the release rate for each release point. At the BSEP the combination of meteorology and release rate which dominates comes from the stack.
)
1208 123 3-23
In the cetermination of actual receptor controlling location, the highest two or three D/Q values from each release point to the pathway locations of Table 3.2-2 are utilized in conjunction with the radionuclide mix and release rate for each release point. For tne BSEP the controlling location is the cow milk pathway 0.79 miles SSE of the reactor building and turbine buildings.
Values for P; were calculated for an infant for various radionuclides for the in-halation, ground plane, cow milk, and goat milk pathways using the methodology of NUREG-0133. The P; values are presented in Table 3.2-5. The values of P reflect, for each radionuclide, the maximum P; value for any organ for each individual path ay.'f exposure. Because the goat milk pa+hway is not present at the BSEP, the cow milk pathway P; values were utilizec in the determination of the various co1 trolling locations. For the case of an infant being present at the site boundary or at the real pathway location, the ground plane pathway is not considered as a reasonable exposure pathway for the infant (i.e., PG=
However, P; values are cresented in Table 3.2-3 for completeness. Appendix C presents the methodology which was utilized in calculating the P. values.
Annual average D/Q values at the special locations for the stack. reactor building, and the turbine building release points, respectively, which were utilized in Expressions 3.2-14 through L2-17 were obtained from the tables presented in Appendix A.
The X/Q values in Expressions 3.2-14 through 3.2-17 were also obtained from the tables presented in of Appendix A.
D/Q values at the limiting site boundary location and the limiting real pathway location for releases from the turbine buildings, the reactor buildings, and the stack were obtained from Tables A-3, A-9, and A-15 respectively of Appendix A.
X/Q values at these same locations for these same release points were obtained from Tables A-1, A-7, and A-13 of Appendix A. A description of the derivation of the X/Q and D/Q values is provided in Appendix A.
3-2h 4
1208 124
3 TABLE 3.2-1 Releases from Brunswick Steam Electric Plant (Ci/yr per unit)
Turbine Building Reactor Building Stack Isotope (Ground Level)
(Mixed Mode)
(Elevated)
Kr-83m 0
0 3.0E4 Kr-85m 6.8El 6.0 5.3E4 Kr-35 0
0 2.0E2 Kr-87 1.3E2 6.0 1.7 E5 Kr-SS 2.3E2 6.0 1.9ES Kr-39 0
0 2.9E3 Xe-131m 0
0
1. 6 E2 Xe-133m 0
0 3.0E3 Xe-133 2.5E2 1.3E2 S.SE4 Xe-135m 6.5E2 9.2E1 7.4E3 Xe-135 6.3E2 6.3El 2.3E5 Xe-137 0
C 7.9E3 Xe-13S 1.4E3
1. 4 El 2.7 E5 Ar-41 0
2.5El 0
I-131
1. 9 E-2 3.4E-1 5.1 1-133
7. 6 E-2 1.4 2.lEl Cr-51 1.3E-4
6. 0 E-4
9. 0 E-3 Mn-54 6.0E-6
6. 0 E-6 3. 0 E-2 Fe-59 5.0E-6 8.0E-4
1. 5 E-2 Co-53 6.0E-6
1. 2 E-3
4. 5 E-3 Co-60 2.0E-5 2.0E-2
9. 0 E-2 Zn-65 2.0E-6 4.0E-3 1.5E-3 Sr-89 6.0E-5
1. 8 E-4 4.5E h Sc-90 2.0E-7 1.0E-5 3.0E-4 Zr-95 1.0E-6 8.0E-4
5. 0 E-5 Sb-124 3.0E-6 4.0E-4 5. 0 E-5 Cs-134 3.0E-6 S. 0 E-3
4. 5 E-3 Cs-136
5. 0 E-7 6.0E-4 4.5E-4 Cs-137 6.0E-6
1. l E-2 9. 0 E-3 Ba-140
1. l E-4 E.0E-4
1. l E 4 Ce-141 6.0E-6 2.0E-4
2. 6 E-3 C-14 0
0 9.5 H-3 0
3.0El 0
Calculations based upon GALE code and not actual releases 1208 125 g
3-25
TABLE 3.2-2 Distance to Controlling Locations as.\\leasured from the Brunswick Plant Center '11)
Site Atilk 1111k Meat Nearest Nearest Sector Boundary Cow Goat Animal Resident Garden NNE 0.64 1.10 0.91 1.39 NE 0.91 2.24 ENE 0.67 E
0.68 0.94 ESE 0.68 SE 0.67 0.79 0.82 0.94 SSE 0.74 0.79 0.80 0.79 S
1.04 1.48 1.57 SSW 0.96 1.44 1.44 SVV 0.89 1.70 0.89 1.04 WSW 0.74 1.00 1.00 W
0.69 1.08 0.87 0.87 WNW 0.64 0.79 0.81 NW 0.70 0.80 5.00 NNW 0.64 0.85 0.97 N
0.64 0.88 0.85
~~
1208 126 3-26
m TABLE 3.2-3 Discance To Site Boundaries Based Upon Brunswick Plant Center And Directions From The Stack Based on Center of From Stack to Site Boundaries Brunswick Plant of Table 3.1-2 Site Boundary Direction Distance (Mi)
Direction Distance (Mi)
NNE 0.64 NNE 0.74 NE 0.91 NE 0.97 ENE 0.67 ENE 0.69 E
0.68 E
0.66 ESE 0.63 ESE 0.61 SE 0.67 SE 0.57 SSE 0.74 SSE 0.55 S
1.04 5
0.92 SSW 0.96 SSW 0.87 SW 0.39 SW 0.S4 WSW 0.74 WSW 0.75 W
0.69 W
0.73 WNW 0.64 WNW 0.72 NW 0.70 NW 0.31 NNW 0.64 NNW 0.76 N
0.64 N
0.76 1208 127 g
3-27
<L s_/
)
TAllLE 3.2-4 DOSE FACTORS FOR HOBl.E GASES AND DAUGilTERS*
Total Body Gamma Air Deta Air Dose Factor Skin Dose factor Dose Factor Dose Factor K
L M
N I
3 3
Radionuclide (mrem /yr'per pC1/m )
(mrem /yrpbrpC1/m)
(mrad /yr per pCi/m )
(mrad /yr per pC1/m )
3 3
1.93E401 2.88E*02 Kr-83m
7. 56E- 02*
Er-85m 1.17E103 1.46EiO3 1.23Et03 1.97E403 Kr-85 1.61E*01 1.34Et03 1.72Et01 1.95Et03 Kr-87 5.92EiO3 9.73E+03 6.17 E + 03 1.03E+04 Kr-88 1.47E*04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01Et04 1.73E404 1.06Et04
[
Kr-90 1.56E+04 7.29E*03 1.63Et04 7.83E*03 Xe-131m 9.15Es01 4.76E+02 1.56Et02 1.llE403 X e-13 3m 2.51E402 9.94E+02 3.27E*02 1.48E+03 Xe-133
2. ';4 E i O 2 3.06Et02 3.53E+02 1.05E603 Xe-135m 3.12E403 7.11E+02 3.36E+03 7.39E*02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E403 Xc-137 1.420503 1.22E*04
1. 51 E + 03 1.27E+04 Xe-138 8.83E+03 4.13Et03 9.21Et03 4.75E+03
(($ Ar-41 8.84E+03 2.69E*03 9.30E+03 3.28Et03 a
~~lhe listed dose factors are for radionuclides that may be detected in gaseous effluents.
~2
*7.56E-02 = 7.56 x 10 r0 CJ
N T ABLE 3.2-5 P
VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC PLANT #
isotooe Inhalatig Ground Plane Cow Milk Goat Milk H-3 6.47E2 0
2.38E3 4.36E3 P-32 2.03E6 0
1.60E11 1.93E11 Cr-51 1.2S E4 6.67E6 4.79E6 5.65ES M n-54 1.00E6 1.09E9 3.89E7 4.6SE6 Fe-59 1.02E6 3.92ES 3.93E8 5.11E6 Co-58 7.77E5 5.29L:
6. 06 E7 7.2SE6 C o-60 c.51E6 4.40E9 2.10ES 2.52E7 Zn-65 6.47E5 6.39E8 1.90E10 2.29E9 Rb-86 1.90ES 1.23E7 2.22E10 2.67E9 Sr-39 2.03E6 3.16E4
1. 27E10 2.66E10 Sr-90 4.09E7 1.21 Ell 2.55 Ell Y-91 2.45E6 1.52E6 5.26E6 6.32E5 Zr-95 1.75E6 3.4SES S.2SES 9.95E4 Nb-95 4.79ES 1.95E8 2.06ES 2.48E7 Ru-103 5.52E5 1.55ES 1.05ES 1.27E4
)
Ru-106 1.16E7 2.99E8 1.44E6 1.73E5
~
Ag-110m 3.67E6 3.14E9 1.46E10 1.75E9 Te-127m 1.31E6 1.18E5 1.04E9 1.2hES Te-129m 1.68E6 2.86E7 1.40E9 1.68ES Cs-134 7.03E5 2.SIE9 6.79E10 2.0 heli Cs-136 1.35E5 2.13ES 5.76E9 1.73E10 Cs-137 6.12E5 1.15E9 6.02E10 1.SIEli Ba-140 1.60E6 2.94E7
2. 41 E8 2.S9E7 Ce-141 5.17E5 1.9SE7 1.37E7 1.65E6 Ce-144 9.34E6 5.34E7 1.33ES 1.60E7 I-131 1.4 S E7 2.46E7 1.06E12 1.27E12 I-132 1.69E5 1.7SE6 1.39E2 1.64E2 1-133 3.56E6 3.54 E6 9.30E9 1.18E10 I-135 6.96ES 3.67E6 2.27E7 2.68E7 3
Units are mrem /yr per pCi/m fo and mrem /yr per # Ci/sec per m~3 H-3 and the inhalation pathway for the food and ground plane pathways.
1208 129
-)
3-29
3.3 Comoliance Tith 10 CFR 50 (Gaseous) 3.3.1 Nobk Cases 3.3.1.1 Cumulation of Doses Section ll.B.1 of Appendix I of 10 CFR 50 limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. Based upon NUREG-0133, the air dose in the unrestricted area due to noble gases released in daseous effluents can be determined by the following expressions:
During any calendar quarter, for gamma radiation:
3.17 x 10-8 (
M;
~(X/Q(, Q1
( X/q)y q;y~
- B;Qis + b;qis 55 mrad
+
(3.3-1)
During any calendar quarter, for beta radiation:
3.17 x 10-5 N;
(X/Q)yQiy (X /q)yq;y (X/Q)s is + l #I9)s is 510 mrad, 9
9
+
+
(3.3-2)
During any calendar year, for gamma radiation:
3.17 x 10-I, M;
(X/Q)yQjy
( X / q)yqjy B;Q
+ b;qis
$10 mrad,
+
+
s (3.3-3)
During any calendar year, for beta radiation:
3.17 x 10-5, Nj (X/Q)yQiy (X /q)ygiy 9
9 (X/Q)s is + (X/q)s 1s 5 20 mrad
+
+
(3.3-4) 3-30
where:
The air dose f actor due to gamma emin:7ns for each M.
=
identified noble gas radionuclide i, mrad /yr per Ci/m ;
the air dose factor due to beta emissions for each N.
=
3 identified noble gas radionuclide i, mrad /yr per pCi/m ;
( X/Q)y=
the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater than 500 hrs / year): sec/m ;
( X/q)y =
the relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases (equal to or less than 500 hrs /y' ear), sec/m ;
(X /Q)s=
the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack releases (greater than 500 hrs / year), sec/m ;
(X /q)s =
the relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases (equal to or less than 500 hrs / year),
3 sec/m ;
qis the average release of noble gas radionuclide i in gaseous
=
effluents for short-term stack releases (equal to or less than 500 hrs / year), Ci; 9iv the average release of noble gas radionuclide i in gaseous
=
effluents for short-term vent releases (equal to or less than 500 hrs / year), gCi; i208 i31 3-31
the average release of noble gas radionuclide i in gaseous Q
=
s effluents for long-term free standing stack releases (greater than 500 hrs / year), Ci; the average release of noble gas radionuclide i in gaseous Q;y
=
effluents for long-term vent releases (greater than 500 hrs /yr), pCi; the constant for long-term releases (greater than 500 B;
=
hrs /yr) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad /yr per pCi/sec; the constant for short-term releases (equal to or less b
=
than 500 hrs /yr) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad /yr per pCi/sec;
-8 the inverse of the number of seconds in a year.
3.17 x 10
=
For the BSEP all releases are considered long term. The incorporation of the stack, reactor building and turbine building release points into Expressions 3.3-1 through 3.3-4 results in the following expressions for two units to show compliance with 10 CFR 50:
During any calendar quarter or year-Gamma Radiation
-8
+9 3.17 x 10 1 M;
-(X /Q)rb N
+9
+
i i
tb i
i rbl rb2 tbl tb2 -
B Qj
$10 mrad (per quarter) or 20 mrad (per year) (3.3-5) i s.
W 1208 132 3-32
Beta Radiation 3
3.17 x 10-8 I; N.
I9I*b (9*'
-( X /Q)rb I
+9
^
rbi rb2 tbl
tb2 l X/Q)s 9
$20 mrad (per quarter) or 40 mrad (per year)
(3.3-6) is-where:
(X/Q)rb annual average relative concentration for
=
releases from the reactor building, sec/m ;
(X /Q)tb annual verage relative concentration for
=
releases from the turbine building, sec/m ;
(X/Q)s annual average relative concentration for
=
releases from the sta.ck, sec/m ;
Q
, Q*.
release of radionuclide i from reactor
]
=
irbi rb2 buildings 1 and 2, respectively, Ci; Q;tbl, Q *.
release of radionuclide i from turbine buildings
=
tb2 I and 2, respectively, pC1; Q;
release of radionuc:!de i from the stack,
=
s Ci; At the BSEP the limiting location for noble gases is 0.67 miles ENE. Substitution of the appropriate X/Q values into Expressions 3.3-5 and 3.3-6 results in the following:
1208 '33 n) 3-33
3 During any calendar quarter or year-Gamma Radiation 3.17 x 10-8 I
M. 7.2 x 10-8 (Q
+Q
) + 4.2 x 10-6 (q
,9
)
1 I
I I
I 3, g *,
rbl rb2 tbl tb2 -
s.
< 10 mrad (per quarter) or 20 mrad (per year)
(3.3-7)
Beta Radiation 3.17 x 10-8 E N.
7.2 x 10-8 (Q
+Q
) + 4.2 x 10-0 (Q
+Q
)+
I I
i rbl rb2 tb1 tb2 x 10 Q;
< 20 mrad (per quarter) or 40 mrad (per year) 6.3 s-(3.3-8)
The determination of the controlling locations for implementation of 10 CFR 50 is
)
a function of parameters such as radionuclide mix, isotopic release and meteorology.
The incorperation of these parameters into Expressions 3.3-1 through 3.3-4 resulted in the expressions for the controlling locations as presented in Expressions 3.3-7 and
'.3-8.
The radionuclide mix was based upon source terms calculated using the NRC GALE Code and is presented in Table 3.2-1 as a function of release point.
The two or three highest site boundary VTQ values for each release point were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location.
Since mived mode and elevated releases occur from the BSEP and their maximum x/Q values may not decrease with distance (i.e., the site boundary may not have the highest X /Q values); X/Q values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest X/Q values for those distances, greater than the sita boundary, were also considered in conjunction with the radionuclide mix and releases to determine the controlling location.
g 1208 1R 3-34
In the cetermination of the controlling Ic ation, annual average X/Q values are utilized. These values are presented in tables in Appendix A.
X/Q values at the limiting site boundary location for releases from the turbine buildings, reactor buildings, and stack were obtained from Tables A-1, A-7, and A-13 respectively of A description of the derivation of the X/Q values is also presented in Appendix A.
A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For the BSEP, the controlling release point is the stack.
Values for M; and N;, which were used in the determination of the controlling location and which are to be used by the BSEP in Expressions 3.3-7 and 3.3-3 to show compliance with 10 CFR 50 were presented in Table 3.2-4. These values originate from NUREG-0472 Revision 0 and were taken from Table B-1 of NRC Regulatory 6
Guide 1.109 Revision 1.
The values have been multiplied by 10 to convert from picocuries to microcuries.
The following relationship should hold for the BSEP to show compliance with
)
Radiological Effluent Technical Specification 1.2.3.1.
For the calendar quarter D
10 mrad (3.3-9) y D
5 20 mrad (3.3-10) g For the calendar year D
5 20 mrad (3.3-11) y D
5 40 mrad (3.3-12) g t 7 r, 320nc n
d 3-35
m where the air dose from gamma radiation. mrad; D
=
y the air dose from beta radiation, mrad.
D
=
The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Excressions3.3-9 through 3.3-12 are exceeded a special report pursuant to Section IV.A of Appendix I of 10 CFR 50 must be filed with the NRC.
3.3.1.2 Projection of Doses Doses resulting from the release of gaseous effluents will be projected monthly.
The doses will be projected using Expressions 3.3-7 and 3.3-3 as appropriate.
3.3.2 Radiciodine and Particulates 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10 CFR 50 limits the release of radiciodines and radioactive material in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radiciodines and particulates, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:
During any calendar quarter o year-3.17 x 10-8 1; R;(W 9
$.5 mrem (per quarter) or 7
is * *sh * *v91v ^ *v 1v )
9 9
s 15 mrem (per calendar year)
(3.3-13) 1208 136 3-36
where:
release of radionuclide i for long-term free standing Q
=
is stack releases (greater than 500 hrs /yr), pCi; release of radionuclide i for long-term vent releases (greater Q.
=
iv than 500 hrs /yr), pCi; gis release of radionuclide i for short-term free standing stack
=
releases (equal to or less than 500 hrs /yr), gCi; q;y release of radionuclide i for short-term vent releases (equal
=
to or less than 500 hrs /yr), pCi; dispersion parameter for estimating dose to an individ-W
=
3 ual at the controlling location for long-term free standing stack releases (greater than 500 hrs /yr);
sec/m for the inhalation pathway and tritium;
=
-2
=
meters for the food and ground plane pathway; the dispersion parameter for estimating the dose to W
=
y an individual at the controlling location for long-term vent releases (greater than 500 hrs /yr);
3 sec/m for the inhalation pathway and tritium;
=
-2
=
meters for the food and ground plane pathway; dispersion parameter for estimating the dose to an w
=
s individual at the controlling location fer short-term stack releases (equal to or less than 500 hrs /yr);
1208
,,,a
= -)
3-37
3 sec/m for the inhalation pathway and tritium; m
=
-2 for the food and ground plane pathwa'y;
=
meters the dispersion parameter for estimating the dose to w
=
y an individual at the controlling location for short-term vent releases (equal to or less than 500 hrs /yr);
3 sec/m for the inhalation pathway and tritium;
=
-2
=
meters for the food and ground plane pathway; 3.17 x 10-8 the inverse of the number of seconds in a year;
=
the dose factor for each identified racionuclide i, R
=
i of the organ of interest, mrem /yr per pCi/sec per
~
-2 3
m or mrem /yr per pCi/m.
Radioiodines and particulates may be released from the stack, reactor buildings, and turbine buildings of the BSEP. At the BSEP all releases are considered long term in duration. Therefore, incorporating the various release points into Expression 3.3-13 results in the following expression to show compliance with 10 CFR 50, for a particular organ:
3.1; x 10-8 1; R; W O
W s
i rb (91 i
tb (91 1
+9
^9 s
rbl rb2 tbl tb2 -
515.0 mrem (per quarter) or 30 mrem (per year)
(3.3-14) where:
W
=
dispersion parameter for releases from s
the stack; 1208 130
=)
3 dispersion parameter for relemes from W
=
rb the reactor building; 4' b dispersion parameter for releases from
=
t the turbine building; Q;
release of radionuclide i from the stack,
=
pCi; Q
, Q;rb2 release of radionuclide i from reactor buildings
=
j 1 and 2, respectively,pCi; Q
,Q.
release of radionuclide i from turbine buildir.gs
=
i A
tbl tb2 I and 2, respectively, pct; In determining the dose at a particular location, W, as in Section 3.2.2, is a function of the pathway. For the food and ground plane pathway W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q. Incorporation of the
]
various pathways into Expression 3.3-14 results in the following:
3.17 x 10-8 7.
(R
+R
)
+ R;V + R;B
-(D/Q)s Q
+ (D/Q)rb I9
'9
)
j j
1 i
G M
s rbl rb2
+ (UTQ)tb (91
+9
)
tbl tb2 -
1
-( X/Q)s 9 1
i + IX/9)rb R
+
s (Qj
+ Qj
) + (X/Q)tb (91 9
)
+
i rbl rb2 tbl tb2 515 mrem (per quarter) or 30 mrem (per year)
(3.3-15) 70 1208 t ;/
=)
3-39
where:
dose factor for an organ for radionuclide i for the R
=
G ground plane exposure pathway, mrem /yr per Ci/sec
-2 per m ;
R dose factor for an organ for radionuclide i for either laj the cow milk or goat milk pathway, mrem /yr per pCi/sec per m-2 ;
R;V dose f actor for an organ for radionculide i for the
=
vegetable pathway, mrem /yr per pCi/sec per m ',
dose factor for an organ for radionuclide i for the meat R
=
i pathway, mrem /yr per pCi/ sec per m-2 B
R dose factor for an organ for radionuclide i for the
=
I inhalation pathway, mrem /yr per Ci/m.
(D/Q)rb Annual average deposition for releases from the
=
reactor buildings, m-2 ;
(D/Q)tb annual average deposition for releases from the
=
turbine buildings, m-2; (D/Q) annual average deposition for releases from the
=
3 stack, m-2,
As discussed in Section 3.2.2, for tritium the parameter 'V for the food pathway is based upon X/Q.
The ground plane pathway is not appropriate for tritium.
Therefore, the left hand portion of Expression 3.3-15 may be modified for purposes of implementation of 40 CFR 190 as:
3-40 120e 4t u
For tritium:
m DT = 3.17 x 10 (R
+R
+R
+RT)
- X/9)s 9 T
T T
T
/9)rb N T
g1 V
B 1
s rbl Q
)
IX/9)tb (9T
9
}
T T
rb2 tbl tb2 -
(3.3-16) where:
D T dose resulting from tritium, mrem;
=
RT dose factor for an organ for tritium for the milk pathway,
=
M 3
mrem / yr per gCi/sec ;
R T dose factor for an organ for tritium for the vegetable pathway,
=
V 3
mrem /yr per pCi/m ;
R T d se factor for an organ for tritium for the beef pathway,
=
B 3
mrem /yr per Ci/m ;
R T dose factor for an organ for tritium for the inhalation
=
I 3
pathway, mrem /yr per pCi/m QT release of tritium from the stack, pCi;
=
s Q
'9 T
T release of tritium from reactor buildings 1 and 2 respectively,
=
rbi rb2 pCi; Q
'9 release of tritium from turbine buildings I and 2 T
T tbl tb2 respectively, pC1.
Equation 3.3-16 is used to show compliance with 40 CFR 190.
1208 141
.,3 3-41
To show compliance with 10 CFR 50, Expression 3.3-15 is evaluated at the controlling pathway location. At the BSEP the centrolling location is a milk cow 0.79 miles in the SSE sector. Expression 3.3-15 becomes:
At) 5.4 x 10-10 3.17 x 10-8 I, (R
R g
+
i G
s
-8(Q'tbl 6.0 x 10-10 (Q
+Q
)+
1.4 x 10
+
I I
rbl rb2
[+R'.
1.0 x 10'8 Q'.+ 6.3 x 10-8 (Q
+Q
)+
Q i
Itb2 -
I-s rbi rb2 7.0 x 10-6 (q 9
)
< 15 mrem (per quarter) or 30 mrem (per year) tb1 tb2 (3.3-17)
For tritium, for implementation of 40 CFR 190, Equation 3.3-16 reduces to:
T )
1.0 x 10-8 T = 3.17 x 10-8 (R Q
D R
+
T T11 1
s i
~
6.8 x 10-8 (Q
+ 9 i.
)
7.0 x 10-6 (q 9
)
Trbi rb2 tbl tb2 -
(3.3-18)
The determination of a controlling location for implementation of 10 CFR 50 for radiciodines and particulates is a function of:
(1) radionuclide mix and isotopic release (2) meteorology (3) exposure pathway (4) receptor's age.
1208 146-3-42
The incorporation of these parameters into Expressior. 3.3-14 results in the respective ecuations at the controlling location.
In the determination of the controlling location, the radionuclide mix of radiciodines and particulates was based upon the source terms calculated using the G ALE Code. This mix was presented in Table 3.2-1 as a function of release point.
In the determination of the controlling location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations.
The ground plane exposure pathway was only considered to be present where an infant was not present. Naturally, inhalation was present everywhere an individual was present.
For the determination of the controlling location, the highest D/Q values for each release point and release mode for the vegetable garden, cow milk, and goat milk pathways were selected.
The thyr id dose was calculated at each of these
)
locations using the radionuclide mix and releases of Table 3.2-1. Based upon these calculations, it was determined that the controlling receptor pathway is the cow milk /inf ant pathway. The ground plane exposure pathway is not appropriate for an infant. However, the R value for the ground plane pathway was not omitted from Expression 3.3-16 in the event that a land use census should indicate that a child, a teen, or an adult is the critical receptor at the controlling location. At the BSEP the controlling release point and mix is the stack.
Tables 3.3-1 through 3.3-19 present R values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.
These values were calculated using the methodology described in NUREG-0133 using a grazing period of S months. A discussion of their calculation is presented in Appendix C.
'=
o/',
3-43
/J i
In the determination of the controlling location annual average D/Q and X/Q values are utilized. D/Q values at the limiting real pathway location for releases from the turbine buildings, reactor buildings and the stack were obtained from Tables A-3, A-9, and A-15 respectively of Appendix A. X/Q values at the same location for these same release points were obtained from Tables A-1, A-7, and A-13 of Appendix A. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.
Long-term D7Q values for the stack, reactor buildings, and the turbine buildings are provided for the midpt 'nts of the following distar:es:
0.0-0.5 mi., 0.5-1.0 mi., 1.0-1.5 mi., 1.5-2.0 mi., 2.0-2.5 mi., 2.5-3.0 mi.,
3.0-3.5 mi., 3.5-4.0 mi., 4.0-4.5 mi., and 4.5-5.0 mi.
These values appear in tables in Appendix A. They may be utilized if an additional special location arises different from those presented in the special locations of Table 3.2-2.
]
The following relationships should hold for the BSEP to show compliance with BSEP Radiological Effluent Technical Specification 1.2.4.1 For the calendar quarter:
D s
15 mrem (3.3-19) 7 For the calendar year:
D 5
30 mrem (3.3-20) r where:
the dose to any organ r from radiodines and particulates, D
=
r mrem.
-)
1208 144
~
3-44
The quarterly limits given above represent one-half the annual design objective of Section llc of Appendix ! of 10 CFR 50. If any of the limits of Expressions 3.3-19 or 3.3-20 are exceeded, a special report pursuant to Section IV.A of Appendix L of 10 CFR 50 must be I' led with the NRC.
3.3.2.2 Projection of Doses Doses resulting from release of radioiodines and particulates will be projected monthly. The doses will be projected using Expression 3.3-17 W%
1208
',45 3-4s
TAJL: 3.3-1 a nLUd5 704 Tid MUN3<lIJK STE A ILiCTd!O PLANT
A flMy = lioJJJ s
NJLIDd T. 30lJ r G I-Til dold LI VElf
< !.)1d f TimaID LU.C SKIN
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4. 66 E ')$
4.$35 06 : 4.33E os : 4.i'E OS : 5.5lE 05
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Ja Td ' AY = V i3ET AGi JuoJ? EJUALS AD'JLT idlLIJs P.100/
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s
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t VALUE3 I.i UNITS OF M E :VY.'l PE7 'Ic to.cI/ 3 *+3
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'9 VALJE3 IJ U.1IT3 OF E 4/YR ?ER tI0do-JI/4**3 Fod I'CfALATION A10 TdIT!U1 A'O I4 UNITS OF 4**2 924/Y9 PE1 11Cdo-01/SEO M! ALL OPIE 15 3M
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1208 '64
.s 4.0 R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.0-1 contains the sample point description, sampling and collection fre-quency, analysis, and analysis frequency for various exposure pathways in the vicinity of the BSEP for the :adiological monitoring program. Figures 4.0-ta and 4.0-lb show the location of the various sampling points.
1208 165
-d 4-1
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T.\\ iLE 4.01 RADIOLOGICAL ENV RONdEN TAL MONIIOllING PitOGil AM Exposure Pathway Sample
Sample !% int Description, Samphng and Analysis and/or Sample Point Distance. and Direction Collection Frequency Frequency Analysis,)
g 1.
Airborne Informat on Center Particulate aa'
!.0 mi. W5W Radiolodine 2
Projected Maximum Annual Con-centration Point 0.6 mi. NE 3
CP & L Substation on Con-Contin sous Operating Weekly,
Cross Beta, struction Access Road Sampler with Sample Quar terly 1 131 1.0 mi. 5 Collection at least Composite Gamma Scan f
weekly n
4 Southport Substation 2.3 mi. SSW 3
Wilmington, N.C.
16 mi. N (Control Station)gc3 2.
Direct i
information Center Radiation 1.0 mi. WSW 2
Projected Maxirnum Annual Cor -
centration Point 0.6 mi. NE 3
'CP & L Substation on Cm-Continuous mea.
Monthly Gamma Dose struction Access Road surement with read 1.0 mi. 5 out at least once per month. (TLD's)
INJ 4
Southport Substation CD 2.3 mi. iSW CD 3
Wilmington, N.C.
16 mi. N IControl Station)(C)
CT CT
T/. 61 ;
3-1 (Cemeinuedt
, R A' HOLOGIC AL ENVIRObilEh /AL MONITORING l'ROGR AM Exposure Pathway Sample Sample l'oint Description, Sampling and Analysis and/or Sample Point Distan( r and Direction Cetlection Frequency frequency Analysis,)
g Intake C nal (Control Station)ICI Coniposite sample Monthly Gamma Scan, 3.
Waterborne 6
if-3
a. Surf ace Water with sample collgion at least monthly 7
Discharge Canal at Stillin.g Pond 4.9 mi. 55W
b. Ground Water 8
liighway-87 west side of Discharge Grab Sample Moi.thly Gamma Scan, Canal 11-3 1.0 mi. W5W 9
liighway 211 west sid: of Irs-
?,
charge Canal 1.3 mi. WSW
c. Drinking not required (C Water
d. Shoreline 10 Caswell Ocach at Discharge Pipe Semi-Annually Semi-Annually Gamma Scan Sediment 5.1 ml. 55W l
4.
Ingestion
a. Milk 11 Stevens Farm At least o.-
per Each Sample Gamma Scan, 0.79 mi. SSE 13 days when animals I-I31 are on pasturet at least once per 31 days at other times Jolmson Farm (Control Station)ICI 12 14.5 mi. NNW w
CD CD C~
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J Tant: 4. 3 I (Continued)
IIADIOI OGICAL ENV170NMF.NT/.L MONITORING PROGR AM Exposure Pathway Sample Sample Pd nt Description, Sampling and Analysis and/or Sample Point Distance and Direction Collection Frequency Frequency Analysis,y g
b. Fish 7
Discharge Canal (Location varies Semi-Annual Each sample Gamma Scan within Can.1) oa Edible Por tions
!) I^ish
2) Shellfish (Shrimp, crabs, oysters, etc.)
14 Atlantic Ocean; Detweer. Littic 7
River and Mansonboro Inle:t (No further out than 3 miles) (Control Station)
c. Food products 13 One location within 3 miles Annual at liarvest Each Sample 1-131, leafy vegetables of site in the sector with the Time Gamma Scan highest deposition rate baset. on the latest inforrration or his-torical data. (Location rnay vary) 16 One location greater than 3 miles from Plant site with the least deposition rate. (Control 5titien)(d (a) lhe LLD for each analysis is specified in Table 2.6-l di Appendix A.I of the ItadToiogical Ef fluent Technical Specification
~
for the Brunswick Steam Electric Plant.
(b) Particulate sarnples will be analyzed for gross teta radiation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. I ttform gamma scan on each sample when gross beta activity is 10 times the mean of control station.
(c) Control Station - These stations are presumed to be outside the influence of plant effluents.
(d) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
(e) Collection of drinking water samples are not required since bradish water is not used in reservoirs.
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APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) engaged the services of Dames and Moore to assess the transport and dispersion of the effluent in the atmosphere as outlined in Preoaration of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133 (USNRC,1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide (RG) 1.111, Revision 1 (USNRC,1977). The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.
Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are: (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line described in XOODOO Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (Draft), NUREG-0324 (USNRC, September 1977) would be used for generating the receired analyses of Appendix 1.
To provide a more realistic accounting of the variability of wind around the plant site, terrain / recirculation correction factors (TCF) were to be determined from a combined puff-advection/ straight-line scheme for a one-year meteorological data base.
Dames and Moore was provided a one-year record of meteorological data from the on-site meteorological program at the Brunswick Steam Electric Plant. This data consisted of all collected parameters at both the 11.46 meter and 104.55 meter tower levels for the year 1977. The description of the model used and the results of the computations are presented in Reference 1.
The following tabics A-1 1208
/,i
m from Reference 1 provide the basis for the meteorological dilution factor development of the Technical Specifications for Appendix I and were the source of the X/Q and D/Q values utilized to show compliance with 10 CFR 20 and 10 CFR 50 for noble gases and radiciodines and particulates.
Tables A-1 through A-6 Relative undepleted concentration, rela-tive depleted concentration and relative deposition flux estimates for ground level release for both standard distances and special locations.
Tables A-7 throgh A-12 Relative undepleted concentration, rela-tive depleted concentration and relative deposition flux estimates for mixed mode release for both standard distances and special locations.
Tables A-13 through A-18 Relative undepleted concentration, rela-tive depleted concentration and relative deposition flux estimates for elevated release for both standard distances and special locations.
It should be noted that the values of X/Q, depleted X/Q, and D/Q for the stack releases to the special locations take into consideration the offset of the stack from the plant center. This is not true for the X/Q, depleted X/Q and D/Q values at the standard distances. These values are based upon the distance from the stack to the point of interest.
These values should be good except for the close-in distances.
Future Operational Computations The NRC "XOQDOQ" Program (Revision 1) was obtained and installed on the CP&L comptuer system.
For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate roeteorological information for the standard distmces and special locations of interest without a terrain / recirculation factor.
The input to "XOQDOQ" for ground level releases are presented in Table A-19 and for elevated releases in Table A-20. The resulting computations will have applied the TCF's to produce a final atmospheric diffusion estimate for the site.
1208
'72 A-2
in general, it is concluded that the straight-line model is as reasonable a projection
.of concentrations as the puff-advection model.
By inclusion of the ' terrain correction factors developed by a combination of the puff-advection/ straight-line scheme with the results of the XOQDOQ Program, ready evaluation of on-site meteorological data may be made.
7 1208
'is Q
A-3
Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent
Technical Specifications: Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Brunswick Facility, Dames and Moore, January 18, 1979.
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Tatale A-4 X/O Values At The Standani Distances For Releases From The Turbine Buildings CANOLINA POWER AND LIGHT COMPANY HRUNSWICK RELEASE TYPE ANtlUAL RELEASE H00E: GROUND LEVEL VARIABLE: HELATIVE CortCENTRATION ISEC./CUflIC HETERI CALCULATION POINT 5I STANDARD H00 E L,8 SIRAIGHT LINE I ANtJx0091 APPLIC AII0rs of TERRAIN COPitECTION FACTORS 8 YES tunt0Ep or gunstuv4110r:S n678 UASE DISTANCE IN HILES / KILOMETERS AFID DESIGN SECT DIST
.25
.75 1 25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 HI 40 1 21 2 01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0.
1.5E-05 2.3E-06 9.4E-07 5.9E-07 3.5E-07 2.4E-07 1.9E-07 1.5E-07 1.2E-07 9.0E-08 NE 0.
2.0E-05 2.9E-06 1.3E-06 7.3E-07 4.5E-07 3.4E-07 2.7E-07 2.0E-07 1.7E-07 1.4E-0T ENE 0.
2.lE-05 3.2E-06 1.2E-06 6.SE-07 4.8E-07 3.6E-07 2.9E-07 2.lE-07 1.8E-07 1,4E-07 E
0.
2.9E-05 3.9E-06 1.5E-06 9.lE-07 6.6E-07 4.4E-0F 3.5E-07 2.8E-07 2.2E-07 1.9E-07 ESE 0.
3.2E-05 5.2E-06 2.2E-06 1.0f-06 6.SE-07 4.4E-0T 3.6E-07 2.9E-07 2.4E-07 1.9E-07 SE 0.
2.3E-05 3.4F-06 1.6E-06 7.9E-O F 4.HE-O F 3.3E-0 7 2.4E-0 7 2.2E-0 7 1.8E-0 7 1.6E-0 7 SSE 0.
4.4E-05 7.5E-es 3.10-06 1.8E-06 1.2E-06 7.7E-07 5.lE-07 3.9E-07 3.2E-07 2.5E-07 5
0.
2.7E-05 3.nE-06 1.6E-06 9.8E-07 7.2E-07 4.9E-07 3./E-OF 2.9E-07 2.2E-07 1.8E-07 SSW 0.
l.9E-05 2.HE-06 1.2E-06 H.00-0 7 4.9E-0 7 2.9E-O f 2.3E-0 7 2.2E-07 1.3E-07 1.lE-07 Sw 0,
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d Table A-5 Depleted X/O Values At The Standani Distances For Releases From Tlie Tushine Buildings C AROL itJ A POWER AND LIGHT COMPANY - HHUtJSWICK HELEASE IYPE8 AtirJUAL HELIASE H0DE1 G40bHD LEVEL V AHI AllLE : HfLAllvE DEPLETED C0tlCENTHAll0N (SEC./ Cut 91C HETEH)
CALCULAllON POINTSt STANDARD H00fLt STHAIGHT l !!JE ( Aidrar 0091 APPLICAftord 0F # E HH A l tJ COHRECi tors l' ACTORS: YES NtutitE P or OHSEHv4TIONSI A678 OASE DISTANCE IN HILES / ntLONETEHS J.F I D DESIGN SECT DIST
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.75 1.25 1 75 2.23 2.75 3.2s 3.75 4.25 4.75 HI 40 1.21 2.01 2.02 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0.
l.5E-05 2.0E-06 H.lE-OF 4.8E-07 2.AL-0F 1.9E-07 1.5E-07 1. lE-O F 8.9E-08 6.8E-0 8 tJE 0.
1.8E-05 2.6E-06 1.IE-06 6.!E-07 3.FE-07 2.6?
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2.0E-05 2.9E-06 1 0E-06 5.5E-07 3.9E-OF 2.0E-07 2.2E-07 1 6E-07 1 3E-07 1.0E-07 E
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2.7E-05 3.4E-06 1.30-06 7.6E-0F 5.1E-07 3.5E-07 2.6E-0F 2.2E-07 1.6E-07 1.4E-07
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2.2E-05 3 1E-06 1.3E-06 6.60-07 3.9E-07 2.6E-OF 1.9E-07 1.6E-07 1.30-07 1.2E-07 SSE 0.
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2.5E-05 3.5E-06 1.3E-06 8.lE-07 5.9E-07 3.9E-0F 2.9E-07 2.20-07 1.6E-OF l.4E-07 SSW 0.
1.9E-05 2.5E-06 1.0E-06 6.6E-07 4.0E-07 2.3E-07 1.8E-07 1.6E-07 1.0E-07 8.3E-08 SW 0.
1.7E-05 2.4E-06 9.8E-OF 5.5E-07 3.9E-07 2.3E-07 1.FE-OF l.3E-07 1.lE-07 9.0E-08 WSW 0.
1.4E-05 1.5E-06 6.4E-07 3.2E-07 2.2E-07 1.4E-01 1.lE-JF 9.2E-08 F.0E-08 5.9E-08 W
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Table A-13 X/O Values At Tlie Special Locations For Releases From The Stack Carolina Power and Light Company - ltronswick llelease Type: Annual Ilclease Mode: Elevated Variable: llel. Concentration Calculational Points: Special Model: Straight Line AppUcation of Terrain Factor: Yes Number of Observations: 8678 Accounting For Stack Center OfIset Affected Site Sector 150undary llairy Meat itesident Garden
-8
-8
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-8 NNE 1.3 x 10 2.2 x 10 1.9 x 10 2.4 x 10 NE 3.3 x 10-4.1 x 10-ENE 6.3 x 10-p E
3.0 x 10-4.9 x 10-'
ESE 5.9 x 10-'
7. 5 x 10-9 8.0 x 10-9 9.3 x 10-9 SE 5.7 x 10-'
SSE 5.9 x 10-l.0 x 10 1.0 x 10-8 1.0 x 10-8
-8
-9 S
6.3 x 10-9 9.1 x 10 9.4 x 10 SSW 8.7 x 10-9 1.4 x 10-8 1.4 x 10-8 SW l.6 x 10-8 1.8 x 10-8 1.6 x 10-8 1.7 x 10-8 WSW 9.0 x 10-9 1.4 x 10-8 1.4 x 10-8 W
9.7 x 10-l 1.4 x 10-3 1.2 x 10-8 1.2 x 10-8 CD WNW CD 4.8 x 10 6.2 x 10-'
-9 6.4 x 10 NW 7.0 x 10-7.8 x 10-9 7.0 x 10
^
CO NNW 4.2 x 10-6.0 x 10-9 6.8 x 10-'
N 4.8 x 10-9 6.8 x 10-9 10-9 6A v
siO d
J Table A-14 Depleted X/G Values At The Special Locations For Releases From The Stack Carolina Power and Light Cornpany - Brunswick Release Type: Annual Release Mode: Elevated Variable: Rel. Depleted Concentrations Calculational Points: Special Model: Straight Line Application of Terrain Factor: Yes Number of Observations: 8678 Accounting Foi Stack Center Of fset Af fected Site Sector Boundary Dairy Meat Resident Garden NNE 1.2 x 10-8 2.1 x 10-8 1.7 x 10 2.3 x 10-8
-8 NE 3.2 x 10-8 4.0 x 10
-9 ENE 6.2 x 10 1
E 3.0 x 10-9 4.9 x 10-9 as ESE 5.8 x 10-9 SE 5.7 x 10-7 7.4 x 10-9 7.9 x 10-9 9.3 x 10-9 SSE 5.8 x 10-9 9.9 x 10-9 9.9 x 10-9 9.9 x 10-9
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9.6 x 10-1.4 x 10-8 1.2 x 10-8
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,ch A-22
J
]
TAllLE A-19 BRUNSWICK PLANT SITE I!!FORMATI0d TO BE USED FOR GROUND LEVEL CALCULATIONS WITil NRC "KOQD0Q" PROGRAM Value to be Used Card Type Columns Description in XOQD0Q 1
1 1
Print Input Data 1
38 Calculate Annual X/Qs for Points of Interest 39 Calculate Annual X/Q Averages for Site Radial Segmento 1
41 Print out Set Distance X/Qs and D/Qs 1
55 Calculate Annual D/Q Averages for bhe Set Radial Segments 1
56 Allow Depicted X/Qs (If Decays (1), (2), or (3) is Negative) 1 58 Calculate Annual D/Qs for Points of Interest 1
}'
2 1-80 Title Card N/A U
3 1-5 thmtber of U1nd Velocity Categories 7
7 6-10 Number of Stability Categories 11-15
!! umber of Distances within Terrain Data for Each Sector 1
16-20 Total Number of Ilours in Joint Wind Frequency Distribution (1) 21-25 Increment in % for whicn 1 lotted Results are to b, Printed 5
25-30
!! umber of Titles of Receptor Types 31-35 Number of Release Exit Locations 1
11 4
1-5
.lleight of the Measured Wind 6-20 llalf-Life (days) Used in'the X/Q Calculatione 101.00 2.26
-8.00 5
!!/A N/A N
c:3 6
1-80 Joint Wind Frequency Distribution (1)
CD
( NJ
TAllt.E A-19 (c'ontinued)
Value to be Used in X0QD0Q Card Type Columns Description 200.
7 1-5 Wind Velocity Unito Correction 0.75 6-75 Maximum Wind Speed in Each Wind Class (m/sec) 3.50 7.50 12.50 18.50 25.00 26.00 All Are 100 8
1-80 Distance in Meters at Which Terrain lleights are Given All Are 0 9
1-80 Terrain lleights -(In Meters, Above~ Plant Grade) Correspond to Distances in Card Type 8 Site Boundary = 16 10 1-25 Number of Receptor Locations for a Particular Receptor Type Dairy = 1 g,
llent - 5 Residence = 14 e
Carden = 11 Site Loundary 11 1-16 Title of Receptor Type for Receptor Locations Dairy IIca t Res.tdence Carden (See Table 1) 12 1-80 Receptor Direction and Distance (1)
Title for Release Point Whose Charncteristico are Described 13 1-80 on Card Type 14
~~~
rs)
"1. 0 1-5 Vent Average Velocity (m/sec) 14 ff$
1.0 6-10 Vent Inside Diameter (m) 0.000 11-15 IIcight of Vent Release Point (m) 56.9 of the Vent's Hutiding (m) 2 lleight
' <3 16-20 2120.0 Minimum Crons-Sectional Area for the Vent's Building (m )
21-25 11, 26-30 Wind lleight lised for Vent Elevated Release 0,
31-35 Vent llent Eminulon Rate (cal /sec)
~.
J
}
TABLE A-19 (continued)*
Value to be Used in XOQD0Q Card Type Columns Description A
' 15 1
Identification for Release Point 0
2-5 Intermittent Releases 6-10 Number of Intermittent Releases Per Year for this Release Point 0
0 11-15 Average Number of Ilours Per Intermittent Release (1) Appropriate Data to be Supplied 9
e e
U O
em 4
0 M
N Ow
+4
('1
oi V
TAILLE A-20 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITil NRC "XOQD0Q" PROGRAli Valuo to be Used Card Type Colunno Dracription in XOQD0Q 1
1
~
l Print Input Data 4
Release to be Elevated 100% of the Time 1
38 Calculate Annual X/Qs for Points of Interest 1
39 Calculate Annual X/Q Averages for Sita Radial Segments 1
41 Print Out Set Distance X/Qs and D/Qs 1
55 Calculate Annual D/Q Averages for' the Set Radial Segments 1
56 Allow Depleted X/Qs (If Decays (1), (2), or (3) is Negative)-
1 58 Calculate Annual D/Qs for Points of Interest 1
N/A 2
1-80 Title Card 7
t 3
1-5 Humber of Wind Velocity Categories h-7 6-10 Number of Stability Categories 11-15 Humber of Distances Within Terrain Data for Each Sector, 1
16-20 Total Number of Ilours in Joint Wind Frequency Distribution (1) 21-25 Increment in % for which Plotted Results are to be Printed 5
5 26-30 Humber of Titles of Receptor Types 1
31-35 Number of Release Exit Locations 104 4
1-5 lleight of the Measured Wind
.6-20 llalf-Life (days) Used in the X/Q Calculations 101.00 2.26 rs)
-8.00 CD cn 5
' N/A N/A
'C) 6 1-80 Joint Wind Frequency Distribution (1) os
fi\\L s)
TABLE A-20 (continued)-
Value to be Used in XOQD0Q Card Type Columns Description 200.
7 1-5 Wind Velocity Units Correction 0.75 6-75 Maximum Wind Speed in Each Wind Class (m/sec) 3.50 7.50 s
12.50 18,50 15.;D0 26.00 All Are 100 8
1-80 Distance in Meters at which Terrain Heights are Civen All Are O 9
1-80 Terrain Heights (In Meters, Above. Plant Grade) Corresponding to Distances in Card Type 8 Site Boundary = 16 10 1-25 Mumber of Receptor Locations for a Particular Receptor Type Dairy = 1 Meat - 5 Residence = 14
'f' Carden = 11 y
11 1-16 Title of Receptor Type for Receptor Loc.,tions Site Doundary Dairy Meat Residence Carden 12 1-80 Receptor Direction sod Distance ~
(See Table 1)
Title for Release Point 1 hose Characteristics are Described (1) 13 1-80 on Card Type 14 4.66 rs)
C2) 14 1-5 Vent Average Velocity (m/sec) 3.58 CE) 6-10 Vent Inside Diameter (m) 100.9 11-15 lleicht of Vent Release l'oint (m) 0.0 16-20 lleight of Vent's Building (m) 2 0.0 Minimum Cross-Sectional Area for the Vent's Building (m )
sg 21-25 104.0
-a 26-30 Wind licight Used for Vent Elevated Release 0.
31-35 Vent Heat Emission Rate (enl/sec)
Qs V
J TABLE A-20 (continued)
Value to be Used Card Type Columns Description in X0QD0Q 15 1
Identification for Release Point A
2-5 Intermittent Releases 0
6-10 llumber of Intermittent Releases Per Year for this Release Point 0
11-15 Average Number of Ilours Per Intermittent Release
.0 (1) Appropriate' Data to be Supplied
?
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9 0
e O
J N
CD CC C2
APPENDIX B m
Calculation of V; and B; Values for the Elevated Plume Values of V; and B; were calculated for the elevated plume release from the Brunswick stack using the NRC computer program RABFIN. This program was used to determine the controlling location based upon the releases of Table 3.2-1.
In addition it was used to develop the V; and B; values for the various noble gas radionuclides at the site boundary at each of the 16 sectors. Table B-1 presents the V; and B; values for the ENE sector which is the controlling location for noble gases for showing compliance with 10 CFR 20 and 10 CFR 50. Table B-2 presents the joint frequency distribution for the ENE sector. Tables B-3 through B-32 present the V; and B; values cr.d the joint frequency distribution for the remaining sectors.
The inputs which were utilized in the RABFIN code are presented below.
1.
Height of Stack -
100.9(m)
]
2.
Stack Diameter -
3.6(m) 3.
Exit Velocity -
5.0 m/sec 4.
Wind Height -
104.6 (m) 1208
!??
B-1
TABLE B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY V;
B; Total Body Gamma Air
( mrem /yr }
[ mradlyr }
pCi/sec /
\\ gCi/sec /
Noble Gas Radionuclides Kr-83m 1.66E-09
1. 40 E-07 Kr-85m 9.18E-05
1. 36 E-04 Kr-85 1.36E-06
2. 06 E-06 Kr-87 4.17 E-04
6. 27 E-04 Kr-88 1.0S E-03
1. 62 E-03
)
Kr-89
6. 55 E-04 9.84E-04 Xe-131m 2.17 E-05
3. 41 E-05 Xe-133m 1.64 E-05
2. 66 E-05 Xe-133 1.72E-05
2. 67 E-05 Xe-135m 2.17E-04
3. 29 E-04 Xe-135 1.47E-04
2. 21 E-04 Xe-137 5.64E-05
8. 52 E-05 Xe-138 6.61 E-04
9. 93 E-04 Xe-139 2.03E-05 3.05E-05 Ar-41 7.86 E-04 1.18 E-03
'!he listed dose parameters are for radionuclides that may be detected in gaseous effluents.
1208 200 B-2
TABLE B-2 7
Joint Frequency Distribution for ENE Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1
0.00 0.00 0.00 0.00 0.00 0.00 0.00 2
0.00 0.00 0.00 0.00 0.00 0.00 0.00 3
0.17 0.00 0.01 0.01 0.07 0.03 0.05 4
3.30 0.02 0.17 0.61 1.21 0.33 0.46 5
4.81 0.02 0.18 0.31 1.63 1.39 C.73 6
1.14 0.05 0.20 0.28 0.27 0.14 0.20 7
0.46 0.01 0.12 0.15 0.09 0.09 0.00
}
Total 9.88 0.10 0.68 1.86 3.27 2.48 1.49 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 S.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.75 6.75 Harmonic 0.00 5.27 5.27 1208 201
=)
B-3
TABLE B-3 3
DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY i
B; Total Body Gamma Air l' mrem /yr }
[ mrad /yr }
Ci/sec /
\\ Ci/sec /
Noble Gas Radionuclides Kr-83m 8.98 E-10 1.llE-07 Kr-85m
4. 57 E-05 6.79E-05 Kr-85 6.76 E-07 1.02E-06 Kr-87 2.06E-04 3.10E-04 Kr-88
5. 41 E-04 8.llE-04 Kr-89 2.89E-04
4. 34 E-04 Xe-131m 1.09E-05
1. 72 E-05
}
Xe-133m 8.26E-06
1. 35 E-05 Xe-133 8.69E-06
1. 36 E-05 Xe-135m
1. 04 E-04 1.57E-04 Xe-135
7. 32E-05 1.10E-04 Xe-137
2. 40E-05
3. 63 E-05 Xe-138
3. 26 E-04 4.89E-04 Xe-139 6.87E-06 1.03E-05 Ar-41 3.89E-04 5.84 E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
.'. " ?du
73G
\\cvu B-4
TABLE B-4 Joint Frequency Distribution for N Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1
0.00 0.00 0.00 0.00 0.00 0.00 0.00 2
0.01 0.00 0.00 0.00 0.01 0.00 0.00 3
0.11 0.00 0.00 0.01 0.07 0.03 0.00 4
1.79 0.01 0.16 0.70 0.65 0.18 0.09 5
2.00 0.00 0.15 0.46 0.65 0'.29 0.45 6
0.68 0.02 0.06 0.29 0.12 0.07 0.12
}
7 0.15 0.02 0.10 0.01 0.00 0.01 0.01 Total 4.74 0.05 0.47 1.47 1.50 0.58 0.67 Entrapr ent 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.00 6.00 Harmonic 0.00 4.61 4.61 nqv
\\
B-5
TABLE B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY V;
B; Total Body Gamma Air (mrem /vr
[ mradlyr 4 Ci/sec /
\\ #Ci/sec /
Noble Gas Radionuclides Kr-83m 1.78 E-09
3. 33E-07 Kr-85m 7.77E-05 1.15E-04 Kr-85 1.13E-06
1. 71 E-06 Kr-87 3.45E-04 5.19E-04 Kr-88
8. 91 E-04
1. 34 E-03
)
Kr-89 5.42E-04 8.155-04 Xe-131m 1.89E-05
3. 00E-05 Xe-133m 1.42E-05 2.36E-05 Xe-133 1.52E-05
2. 40 E-05 Xe-135m 1.80 E-04 2.73 E-04 Xe-135 1.23E-04 1.S6E-04 Xe-137 4.70E-05 7.11E-05 Xe-138 5.47E-04 8.22E-04 Xe-139 1.68E-O' 2.52E-05 Ar-41 6.49E-04 9.74E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents 12 08
<-) n 1 us
-q B-6
TABLE B-6 Joint Frequency Distribution for the NNE Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1
0.00 0.00 0.00 0.00 0.00 0.00 0.00 2
0.07 0.00 0.00 0.01 0.05 0.01 0.00 3
0.45 0.00 0.00 0.03 0.25 0.15 0.02 4
4.51 0.01 0.16 0.56 1.79 1.38 0.61 5
2.90 0.00 0.17 0.21 0.88 0.78 0.86 6
0.65 0.02 0.12 0.22 0.09 0.07 0.13 7
0.45 0.05 0.14 0.08 0.07 0.10 0.01 Total 9.03 0.08 0.59 1.11 3.13 2.49 1.63 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithrr t:c 0.00 7.13 7.13 Harmonic 0.00 5.63 5.63
~3 1208 205 B-7
3 TABLE B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY V;
B; Total Body Gamma Air mrem /yr
[inrad/vr Noble Gas Radionuclides g Ci/sec /
\\ Ci/sec i Kr-83m 2.87E-09 8.70 E-07 Kr-85m 9.33E-05 1.39 E- 04 Kr-85 1.31 E-06 1.99E-06 Kr-87 3.99E-04 6.00 E-04 Kr-88 1.03 E-03 1.54 E-03
}
Kr-89 6.05E-04 9.10E-04 Xe-131m 2.37 E-05 3.85E-05 Xe-133m 1.79E-05 3.05 E-05 Xe-133 1.96E-05 3.15 E-05 Xe-135m 2.09E-04 3.18 E-04 Xe-135 1.46E-04 2.20E-04 Xe-137 5.25 E-05 7.94 E-05 Xe-138 6.34 E-04 9.52E-04 Xe-139 1.48E-05 2.23 E-05 Ar-41 7.47E-04 1.12 E-03
The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
c:h
~
1208 206 B-8
TABLE B-8 Joint Frequency Distribution for NE Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Ste sm Electric Plant MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7 50 10.00 12.50 1
0.02 0.00 0.00 0.00 0.01 0.00 0.01 2
0.21 0.00 0.00 0.00 0.05 0.10 0.06 3
1.13 0.00 0.00 0.03 0.28 0.50 0.32 4
7.30 0.01 0.15 0.63 2.50 2.51 1.50 5
5.15 0.03 0.09 0.30 1.21 1.99 1.53 6
1.04 0.01 0.06 0.32 O.33 0.24 0.08 7
0.41 0.01 0.12 0.10 0.13 0.03 0.02 Total 15.26 0.06 0.42 1.38 4.51 5.37 3.52 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 7.81 7.81 Harmonic 0.00 6.63 6.63 1208 an7
.. u i B-9
TABLE B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUB 3ARY V;
B; Total Body Gamma Air (mrem /vr mrad /vr pCi/sec /
\\ gCi/sec /
Noble Gas Radionuclides Kr-83m 9.63E-10
7. 31 E-08 Kr-85m 5.94E-05 8.82E-05 Kr-85 8.93E-07 1.35E-06 Kr-87 2.73 E-04
4. l l E-O h Kr-88 7.17 E-04 1.08E-03
}
Kr-89 4.02E-04 6.04E-04 Xe-131m 1.39E-05 2.17E-05 Xe-133m 1.05E-05 1.70E-05 Xe 133 1.09 E-05 1.69E-05 Xe-135m
1. 38 E-04 2.10E-04 Xe-135 9.59E-05
1. 44 E-04 3.37E-05 5.10E-05 Xe-137 Xe-138
4. 32 E-04 6.49E-04 Xe-139 1.08E-05 1.62E-05 Ar-41 5.18E-04 7.77E-04 The listed dose parameters z.re for radionuclides
+
that raay be detected in gaseous effluents.
=)
g08 200 B-10
TAE' E B-10 Joint Frequenc, _ s+
iution for E Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND 'YEED (m/sec)
Stability A.1 1.50 3.00 5.00 7.56 10.00 12.50 1
0.01 0.00 0.00 0.00 0.00 0.01 0.00 2
0.03 0.00 0.00 0.00 0.01 0.01 0.01 3
0.09 0.00 0.00 0.03 0.02 0.01 0.03 4
1.42 0.01 0.15 0.55 0.32 0.23 0.16 5
2.07 0.03 0.10 0.62 0.74 0.50 0.08 6
1.08 0.02 0.14 0.30 0.38 0.15 0.09 7
0.64 0.03 0.13 0.24 0.10 0.08 0.06
]
Total 5.34 0.09 0.52 1.74 1.57 0.99 0.43 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 5.80 5.80 Harmonic 0.00 4.41 4.41 g) 1 2 0 8
"' O
B-11
~
TABLE B-Il DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY B;
i Total Body Gamma Air mrad /yr (mrem /yr }
pCi/sec /
pCi/sec /
Noble Gas Radionuclides Kr-83m
1. 08E-09 1.89 E-07 Kr-85m
5. 51 E-05 8.18E-05 Kr-85 8.12E-07
1. 23 E-06 Kr-87 2.51E-04 3.78E-04 Kr-88
6. 42E-04
9. 63 E-04 Kr-89
4. 30 E-04 6.46E-04 Xe-131m 1.31 E-05 2.07E-05 Xe-133m 9.91 E-06
1. 62 E-05 Xe-133
1. 04 E-05
1. 63E-05 Xe-135m
1. 34 E-04
2. 04 E-04 Xe-135
8. 81 E-05
1. 32E-04 Xe-137 3.795-05 5.7 3 E-05 Xe-138 3.99E-04
5. 99 E-04 Xe-139 1.70E-05 2.55E-05 Ar-41 4.73E-04
7. 09 E-04 The listed dose parameters are for radionuclides
+
that may be detected in gaseous effluents.
~d 1208 210 B-12
TABLE B-12 Joint Frequency Distribution for ESE Sector (%)
Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1
0.06 0.00 0.00 0.01.
0.00 0.05 0.00 2
0.15 0.00 0.00 0.01 0.03 0.06 0.05 3
0.31 0.00 0.00 0.02 0.13 0.03 0.13 4
1.71 0.00 0.07 0.31 0.58 0.46 0.29 5
2.02 0.01 0.08 0.31 0.52 0.80 0.30 6
0.85 0.03 0.06 0.17 0.18 0.36 0.05 7
0.46 0.01 0.07 0.12 0.07 0.07 0.12 Total 5.56 0.05 0.28 0.95 1.51 1.83 0.94 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 7.15 7.15 Harmonic 0.00 5.67 5.67 d
1208.y,t B-13
TABLE B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY V
B; Total Body Gamma Air mrem /yr mrad /yr Noble Gas Radionuclides 4Ci/sec s pCi/sec Kr-83m 1.36E-09
3. 68 E-07 Kr-85m 6.01 E-05 8.93E-05 Kr-85 8.80E-07 1.33E-06 Kr-87 2.72E-04 4.10E-04 Kr-88 6.95 E-04
1. 04 E-03
}
Kr-89 4.68E-04
7. 04 E-04 Xe-131m 1.45E-05
2. 31 E-05 Xe-133m 1.10E-05
1. 82E-05 Xe-133 1.16E-05
1. F 3 E-05 Xe-135m
1. 46 E-= 04 2.22E-04 Xe-135 9.58E-05 1.44E-04 Xe-137 4.14E-05 6.26E-05 Xe-138
4. 33 E-04 6.50E-04 Xe-139 1.87E-05
2. 81 E-05 Ar-41 5.12E-04
7. 68 E-04 The listed dose parameters are for radionuclides th-
may be detected in gaseous effluents.}
'th B-14
TABLE B-14 Joint Frequency Distribution for SE Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.11 0.00 0.00 0.00 0.00 0.06 0.05 2 0.31 0.00 0.00 0.01 0.14 0.15 0.01 3 0.53 0.00 0.00 0.14 0.18 0.18 0.03 4 1.44 0.02 0.08 0.25 0.51 0.41 0.17 5 1.46 0.01 0.09 0.31 0.50 0.46 0.09 6 0.89 0.02 0.05 0.02 0.30 0.44 0.06 7 0.63 0.01 0.13 0.09 0.14 0.21 0.05 ) Total 5.37 0.06 0.35 0.S2 1.77 1.91 0.46 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 S.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 6.78 6.7S Harmonic 0.00 5.37 5.37 1208 213 g B-15
^ TABLE B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY V; B; Total Body Gamma Air (mrem /vr mrad /vr gCi/sec / gCi/sec / Noble Gas Radionuclides Kr-83m 1.31E-09 2.51E-07 Kr-85m 6.46E-05 9.59E-05 Kr-85
9. 55 E-07 1.45E-06 Kr-87 2.96E-04 4.45E-04 Kr-88

7. 58 E-04 1.14 E-03
) Kr-89
5. l l E-04 7.69E-04 Xe-131m

1. 54 E-05 2.43E-05 Xe-133m 1.17E-05 1.91 E-05 Xe-133

1. 22E-05

1. 91 E-05 Xe-135m

1. 58 E-04

2. 39 E-N Xe-135

1. 03E-04 1..*>E-04 Xe-137 4.52E-05 6.83E-05 Xe-138 4.70E-04 7.06E-04 Xe-139 2.17E-05 3.26E-05 Ar-41 5.58E-04

8. 37 E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
=) 1208 ?l#' B-16
~ TABLE B-16 Joint Frequency Distribution for SSE Sector (96) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.01 0.00 2 0.13 0.00 0.00 0.02 0.02 0.09 0.00 3 0.49 0.00 0.00 0.14 0.24 0.09 0.02 4 2.35 0.05 0.16 0.32 0.80 0.70 0.32 5 1.40 0.00 0.08 0.23 0.46 0.58 0.05 6 0.34 0.02 0.05 0.13 0.13 0.31 0.15 7 0.32 0.03 0.02 0.05 0.07 0.13 0.02 Total 5.55 0.10 0.31 0.89 1.78 1.91 0.56 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 6.81 6.31 Harmonic 0.00 5.21 5.21 =J 1208 215 B-17
TABLE B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY V; B; Total Body Gamma Air [ mrem /yr } [ mrad /yr Noble Gas Radionuclides \\ Ci/sec / \\ pCi/sec / Kr-83m
8. 30 E-10 1.84E-07 Kr-85m 3.54 E-05

5. 26 E-05 Kr-85 5.20E-07

7. 88 E-07 Kr-87 1.54 E-04 2.32E-04 Kr-88 4.18 E-04 6.27E-04 Kr-89

2. 00E-04 3.00E-04 Xe-131m 8.70E-06 1.39E-05 Xe-133m 6.58E-06

1. 09 E-05 Xe-133

7. 01 E-06 1.llE-05 Xe-135m 7.40E-05 1.12 E-0.4 Xe-135 5.66E-05 8.51E-05 Xe-137 1.64E-05 2.48E-05 Xe-138

2. 42 E-04 3.63E-04 Xe-139

4. 28 E-06

6. 43 E-06 Ar 41 2.93 E-04 4.40E-04 The listed dose parameters are for radionulides
+ that may be detected in gaseous effluents. 1208 2iC B-18
TABLE B-IS 3 Joint Frequency Distribution for 5 Sector (%) Period 1-1-77 through 12-31-77 Brunswir k Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.03 0.00 0.00 0.00 0.03 0.00 0.00 3 0.16 0.00 0.00 0.02 0.14 0.00 0.00 4 1.74 0.01 0.13 0.28 0.55 0.54 0.23 5 1.32 0.03 0.08 0.25 0.45 0.46 0.05 6 0.93 0.02 0.08 0.17 0.24 0.33 0.09 7 0.37 0.05 0.03 0.05 0.12 0.07 0.05 Total 4.55 0.11 0.32 0.77 1.53 1.40 0.42 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 6.57 6.57 Harmonic 0.00 4.84 4.84 rd 1208 217 B-19
TABLE B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY V; B; Total Body Gamma Air (mrem /yr [mradlyr uCi/sec / \\pCi/sec / Noble Gas Radionuclides Kr-83m 1.09E-09 2.15E-07 Kr-85m 4.68E-05 6.95E-05 Kr-85 6.80E-07 1.03E-06 Kr-87
2. 07 E-04

3. I I E-04 Kr-88

5. 39 E-04

8. 09 E-04
} Kr-89
2. 98 E-04 4.48E-04 Xe-131m 1.14E-05

1. 82E-05 X e-133m 8.63E-06 1.43E-05 Xe-133

9. 22 E-06

1. 46 E-05 Xe-135m 1.06E-04

1. 61 E-04 Xe-135 7.44E-05 1.12 E-00 Xe-137 2.52E-05 3.81E-05 Xe-138 3.28E-04 4.92E-04 Xe-139 6.80E-06

1. 02 E-05 Ar-41 3.89E-04 5.84 E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents, 1208 218 g
B 20
TABLE B-20 Joint Frequency Distribution for SSW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 0.19 0.00 0.00 0.07 0.05 0.06 0.01 4 2.47 0.01 0.03 0.53 0.99 0.62 0.29 5 1.88 0.01 0.15 0.37 0.56 0.74 0.05 ] 6 1.12 0.01 0.12 0.14 0.23 0.55 0.02 7 0.51 0.01 0.03 0.10 0.22 0.13 0.02 Total 6.17 0.04 0.33 1.21 2.10 2.10 0.39 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 6.61 6.61 Harmonic 0.00 5.44 5.44 1208 2il g B-21
3 TABLE B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY O i i Total Body Gamma Air mrad /yr (mrem /yr Ci/sec / \\ gCi/sec Noble Gas Radionuclides 1.35E-09
3. 69E-07 Kr-83m

5. 24 E-05

7. 79 E-05 Kr-85m 7.60E-07 1.15E-06 Kr-85 2.29 E-04 3.45E-04 Kr-87

6. 04 E-04 9.06E-04
) Kr-88 3.21E-04 4.82E-04 Kr-89 1.30E-05 2.08E-05 Xe-131m 9.83E-06 1.64E-05 Xe-133m 1.05E-05 1.67 E-05 Xe-133 Xe-135m 1.15E-04 1.75E-04
8. 33E-05 1.25E-04 Xe-135 2.69E-05

4. 07 E-05 Xe-137 3.63E-04 5.45E-04 Xe-138 7.09E-06 1.07 E-05 Xe-139 4.33E-04

6. 50 E-04 Ar-41 The listed dose parameters are for radionuclides
+ that may be detected in gaseous effluents. 1208 ^20 B-22
m ' TABLE B-22 Joint Frequency Distribution for SW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.00 0.00 0.01 0.00 2 0.10 0.00 0.00 0.02 0.07 0.01 0.00 3 0.53 0.00 0.02 0.10 0.30 0.09 0.02 4 2.32 0.01 0.14 0.50 0.98 0.52 0.17 5 1.71 0.02 0.09 0.39 0.40 0.68 0.13 6 0.88 0.05 0.05 0.20 0.46 0.12 0.00 7 0.56 0.00 0.07 0.15 0.22 0.!: 0.00 Total 6.11 0.08 0.37 1.36 2.43 1.55 0.32 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIWD SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 6.22 6.22 Harmonic 0.00 4.98 4.98 120S 221 B-23
3 TABLE B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY i B; Total Body Gamma Air (mrem /yr { mrad /vr } pCi/sec / \\ gCi/sec / Noble Gas Radionuclides Kr-83m 1.41E-09
3. 28 E-07 Kr-85m

5. 94 E-05 8.83E-05 Kr-85

8. 66 E-07

1. 31 E-06 Kr-87

2. 63 E-04 3.97E-04 Kr-88 6.87E-04 1.03 E-03 Kr-89 3.90E-04 5.87 E-04 Xe-131m 1.45E-05

2. 32E-05 Xe-133m 1.10E-05

1. 83 E-05 Xe-133 1.17 E-05 1.85E-05 Xe-l?5m 1.35E-04 2.05E-04 Xe-135 9.46E-05

1. 42 E-04 Xe-137

3. 32 E-05 5.03E-05 Xe-138 4.18E-04

6. 27 E-04 Xe-139

9. 43 E-06

1. 42 E-05 Ar-41 4.97E-04 7.45E-04 The listed dose parameters are for radionuclides
+ that may be detected in gaseous effluents. '208 222 d B-24
TABLE B-24 Joint Frequency Distribution for WSW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant M AXIMUM WIND SPEED (ndsec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.02 0.00 0.00 2 0.18 0.00 0.01 0.00 0.14 0.00 0.03 3 0.36 0.00 0.01 0.15 0.15 0.05 0.00 4 2.64 0.00 0.15 0.54 1.12 0.75 0.08 5 1.73 0.02 0.09 0.37 0.84 0.39 0.02 6 0.87 0.02 0.08 0.25 0.37 0.14 0.01 7 0.36 0.03 0.03 0.13 0.17 0.00 0.00 Total 6.16 0.07 0.37 1.44 2.81 1.33 0.14 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Veloc!!y 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 5.97 5.97 Harmonic 0.00 4.91 4.91 c.h B-25
3 TABLE B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY V; B; Total Body Gamma Air mrem /vr / mrad /vr Noble Gas Radionuclides s uCi/sec ( pC1/sec Kr-83m 1.36E-09 2.97E-07 Kr-85m 6.29E-05
9. 34 E-05 Kr-85 9.33E-07

1. 41 E-06 Kr-87

2. 81 E-04

4. 23 E-04 Kr-88

7. 49 E-04 1.12E-03 Kr-89

3. 82 E-04

5. 73 E-04 Xe-131m 1.52E-05 2.42E-05 Xe-133m 1.15E-05 1.90E-05 Xe-133 1.21 E-05 1.91 E-05 Xe-135m

1. 38 E-04

2. 09 E-04 Xe-135 1.01E-04

1. 52 E-Oh Xe-137 3.16 E-05 4.77E-05 Xe-138

4. 42 E-04

6. 64 E-04 Xe-139 8.!:.E-06

1. 23E-05 Ar-41

5. 33 E-04 8.00E-04 The listed dose parameters are for radionuclides
+ that may be detected in gaseous effluents. 1208 '2" B-26
TABLE B-26 3 Joint Frequency Distribution for W Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.05 0.00 0.00 0.00 0.35 0.00 0.00 2 0.10 0.00 0.00 0.00 0.10-0.00 0.00 3 0.37 0.00 0.05 0.18 0.12 0.02 0.00 4 1.95 0.02 0.10 0.47 1.07 0.29 0.00 5 2.00 0.01 0.14 0.53 1.07 0.22 0.03 6 0.85 0.07 0.10 0.29 0.36 0.01 0.02 ] 7 0.37 0.06 0.08 0.18 0.05 0.00 0.00 Total 5.69 0.16 0.47 1.65 2.82 0.54 0.05 Entrapment 0.00 0.00 0.00 0.00 0.00 0100 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 5.30 5.30 Harmonic 0.00 4.13 4.13 d 1208 225 B-27
TABLE B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY V; B; Total Body Gamma Air (mrem /yr } mrad /yr Ci/sec / \\ 4Ci/sec / Noble Gas Radionuclides Kr-83m
9. 33 E-10

2. 26 E-07 Kr-85m

4. 30 E-05 6.39E-05 Kr-85 6.41E-07

9. 71 E-07 Kr-87 1.92 E-04 2.89E-04 Kr-88 5.18E-04

7. 77 E-04 Kr-89

2. 41 E-04

3. 62 E-04 Xe-131m

1. 04 E-05

1. 66 E-05 Xe-133m 7.92 E-06 1.31E-05 Xe-133 8.31E-06 1.31E-05 Xe-135m 9.15E-05

1. 39 E-04 Xe-135

6. 91 E-05

1. 04 E-04 Xe-137

1. 93 E-05

2. 92 E-05 Xe-138

3. 01 E-04

4. 53 E-04 Xe-139

4. 51 E-06 6.77E-06 Ar-41 3.65E-04 5.48E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
=-) 1208 ^26 B-28
TABLE B-28 Joint Frequency Distribution for WNW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.09 0.00 0.00 0.08 0.01 0.00 0.00 3 0.24 0.00 0.05 0.17 0.02 0.00 0.00 4 1.03 0.01 0.10 0.45 0.45 0.02 0.00 5 1.19 0.03 0.14 0.37 0.50 0.13 0.02 6 0.63 0.05 0.12 0.28 0.17 0.01 0.00 7 0.19 0.03 0.03 0.07 0.06 0.00 0.00 Total 3.38 0.12 0.44 1.43 1.21 0.16 0.02 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmet c 0.00 4.65 4.65 ~ Harmonic 0.00 3.58 3.58 -s' 1208 227 B-29
3 TABLE B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY V; B; Total Body Gamma Air (mrem /yr mrad /yr } Ci/sec /
Ci/sec /
Noble Gas Radionuclides Kr-83m 9.87 E-10 2.60E-07 kr-85m 4.iaE-05 6.14 e-05 Kr-85 6.09 E-07
9. 23 E-07 Kr-87 1.80E-04 2.72E-04 Kr-88 4.92 E-04 7.38E-04 Kr-89 2.llE-04 3.17E-04 Xe-131m 1.02E-05

1. 63 E-05 Xe-133m 7.73 E-06

1. 2S E-05 Xe-133

8. 20 E-06

1. 30E-05 Xe-135m 8.45E-05 1.28E-04 Xe-135 6.62E-05 9.95E-05 Xe-137 1.65E-05

2. 49 E-05 Xe-138 2.83 E-04 4.25E-04 Xe-139 3.74E-06

5. 61 E-06 Ar-41 3.43E-04 5.15E-04 The listed dose parameters are for radionuclides
+ that may be detected in gaseous effluents. "d 1208 ^21 B-30
TABLE B-30 ~ Joint Frequency Distribution for NW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.12 0.00 0.01 0.08 0.03 0.00 0.00 3 0.24 0.00 0.02 0.17 0.05 0.00 0.00 4 1.14 0.01 0.16 0.54 0.33 0.09 0.01 5 1.08 0.02 0.12 0.40 0.23 0.10 0.16 6 0.57 0.05 0.17 0.17 0.16 0.01 0.01 7 0.35 0.03 0.07 0.12 0.13 0.00 0.00 ] Total 3.51 0.11 0.55 1.49 0.98 0.20 0.13 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.4S Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) Mean Ground Elevated Combined Arithmetic 0.00 4.81 4.81 Harmonic 0.00 3.59 3.59 mj 1208 vl,' B-31
i TABLE B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY i B; Total Body Gamma Air mrem /yr mrad /vr Noble Gas Radionuclides 4Ci/sec / \\ gCi/sec / Kr-83m
6. 84 E-10

1. 03 E-07 Kr-85m 3.67E-05

5. 44 E-05 Kr-85 5.51E-07 8.35E-07 Kr-87 1.65 E-04

2. 48 E-04 Kr-88 4.46E-04 6.70E-04 Kr-89

2. 09E-04 3.14 E-04 Xe-131m

8. 75 E-06 1.38E-05 Xe-133m

6. 63 E-06

1. 08 E-05 Xe-133 6.91 E-06 1.08E-05 Xe-135m 7.85E-05 1.19 E-04 Xe-135 5.91 E-05 8.89E-05 Xe-137

1. 63 E-05 2.54E-05 Xe-138 2.59E-04 3.89E-04 Xe-139 4.89E-06 7.34E-06 Ar-41 3.14 E-04 4.72E-04 The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
g 1208 230 B-32
TABLE B-32 Joint Frequency Distribution for NNW Sector (%) Period 1-1-77 through 12-31-77 Brunswick Steam Electric Plant MAXIMUM WIND SPEED (m/sec) Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.02 0.00 0.00 0.01 0.01 0.00 0.00 3 0.12 0.00 0.00 0.06 0.06 0.00 0.00 4 1.00 0.01 0.14 0.36 0.37 0.09 0.03 5 1.17 0.02 0.12 0.27
0. ',)
0.12 0.39 6 0.82 0.02 0.13 0.23 0.17 0.03 0.24 7 0.34 0.05 0.10 0.14 0.00 0.05 0.00 Total 3.47 0.10 0.49 1.07 0.86 0.29 ...o Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec) plean Ground Elevated Combined Arithmetic 0.00 5.89 5.89 Harmonic 0.00 4.02 4.02 -9 1208 231 B-33
3 APPENDIX C DOSE PAR AMETERS FOR R ADIOIODINES, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radiciodines, particulates, and tritium to show compliance with 10 CFR 20 and Appendix I of 10 CFR 50 for gaseous effluents. These dose parameters, P; and R;, were calculated using the methodology outlined in NUREG-0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the P; and R; values for the various exposure pathways. C.1 Calculation of P; The parameter, P;, containec in the radiolodine and particulates portion of Section 3.2, includes pathway transport parameters of the ith radionuclide, the receptor's usage of the pathway media and the dosimetry of the exposure. Pathway usage rates and the internal dosimetry are functions of the receptor's age; however, the youngest age group, the infant, will always receive the maximum dose under the exposure conditions for Technical Specification 1.2.2.l(b). For the inf ant exposure, separate values of P may be calculated for the inhalation pathway which is combined with a W parameter based on O(/Q), and the food (milk) and ground pathway which is combined with a W parameter normally based on (D/Q), except for tritium. The following sections provide in detail the methodology which was used in calculating the P; values for inclusion into this OOCM. C. I.1 Inhalation Pathway K'(BR) DFA. (C.1-1) P. = I 1; where: dose parameter for radienuclide i for the inhalation pathway, P = I ~ mrem /yr per Ci/m ; 12 0 8 L,) L. 977 C-1
a constant of unit conversion: K' = 6 10 pCi/gCi; = 3 the breathing rate of the infant age group, m /yr; BR = the maximum organ inhalation dose factor for the infant age DFA = group for radionuclide i, mrem /pCi. The age group considerad is the inf ant group. The infant's breathing rate is taken as 3 1400 m /yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the infant, DFA, are presented in Table E-10 of Regulatory Guide 1.109 in j units of mrem /pCi. The total body is considered as an organ in the selection of DFA;. The incorporation of breathing rate of an infant and the unit conversion factor results in the followir.g: 1.4x10 DFA. (C.1-2) P. = 1 1; C.I.2 Ground Plane Pathway - A*. t P;G K'K"DFG; (1-e )/A (C.1 -3) = where: dose parameter for radionuclide i for the ground plane pathway, P. = G mrem /yr per Ci/sec per m-2; a constant of unit conversion: K' = 6 10 pCi/ Ci: = a constant of unit conversion: K" = S760 hr/yr: = -I the radiological decay constant for radionuclide i, sec A; = +3 1208 233 C-2
the exposure period; t = 7 3.15x 10 sec (1 year); = DFG; = the ground plane dose conversion factor for radionuclide i, 2 mrem /hr per pCi/m. The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for radionuclide i, DFG;, are presented in Table E-6 of Regulatory Guide 1.109 Revision 1. Resolution of the units yields: A.t P. 8.76x10' DFG. (1-e * )/A *. (C.1 4) = I G C.I.3 Milk K'r Q (Uap) F,, - A;tf F P; ) - DFL e (C.1-5) = where: P; dose parameter for radionuclide i for the cow milk or goat milk = pathway, mrem /yr per pCi/sec per m-2, K' a constant of unit conversion: = 6 10 pCi/pCi = OF the cow's or goat's consumption rate of feed, kg/ day (wet weight): = U the infant's milk consumption rate, liters /yr: = ap 2 Y the agricultural productivity by unit area, kg/m ; = P T.) 1208 234 C-3
3 the stable element transfer coefficient, pCi/ liter per pCi/ day; F = m fraction of deposited activity retained on cow's or goat's feed r = grass; the maximum organ ingestion dose factor for radionuclide i, DFL; = mrem /pCi; -I the radiological decay constant for rt.dionuclide i, sec ; A; = the decay constant for removal of activity on leaf and plant = w -I surf aces by weathering, sec ; -I (corresponding to a 14 day half-time); 5.73x10-7 sec = the transport time from pasture to cow or goat to milk to infant, i = f sec. A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering processes. Various parameters which were utilized to determine the P values for the cow and goat milk pathways are provided in Table C-1. Table E-1 of Regulatory Guide 1.109 Revision 1 provides the stable element transfer coefficients, Fm, and Table E-14 of the same regulatory guide provides the ingestion dose factors, DFL;, for the infant's organs. The organ with the maximum value of DFL; was used in the determination of P f or t... pathway. The incorporation of the various constants of Table C-1 into Equation C.1-5 results in the following: For cow's milk for radiciodines and particulates: 10 'm -A.t Pi g, 3pt if ('.1-6) 2.4x 10 = e d 1208 23
For the goat milk pathway for radiciodines and particulates: 7, 9 rF* -A tif e (C.1-7) A; +A, DFL. 2.Ex 10 P. = 1 ly For tritium, the concentration of tritium in milk is based on its airborne concentration rather than the deposition rate. K'K"'F N'F apDFL 0.75(0.5/H) (C.1-8) U P = m T Tg where: dose parameter for tritium for the cow milk and goat milk P.;. = pathways, mrem /yr per p.Ci/m ; a constant of unit conversion; K "' = 3 10 gm/kg; = 3 absolute humidity of the atmosphere, gm/m ; H = the fraction of :otal feed that is water; 0.75 = the ratio of the specific activity of the feed grass water to the 0.5 = atmospheric water; maximum rgan ingestion dose factor for tritium, mrem /pCi. DFLT= C.2 Calculation of R.1 The radiciodine and particulate Technical Specification 2.3.1.2 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age grcups indicates the maximum potential exposc e occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. R; values have been calculated for the adult, teen, child, and infant age groups for the ground mj 1208 236 C-5
plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below. 3 C.2.1 Inhalation Pathway K' (BR)a (DFA;)a (C.2-1) R; = where: R;I dose factor for each identified radionuclide i of the organ of = 3 interest, mrem /yr per Ci/m ; K' a constant of unit conversion; = 6 10 pCi/ Ci: = (BR)a = breathing rate of the receptor c1 age group a, m /yr: (DFA;)a = rgan inhalation dose factor for radionuclide i for the receptor of age group a, mrem /pCi. The breathing rates (BR)a f r the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109 Revision 1. 3 Age Grouc (a) Breathine Rate (m /vr) Ir.fant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose f actors (DFA;)a f r the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1. =$ 1208 3'7 C-6
C.2.2 Ground Plane Pathway -A;t
1. K'K"(SF)DFG. (1-e
)/A*. (C.2-2) R. = 1 G where: R. dose factor for the ground plane pathway for each identified = 'G radionuclide i for the organ of interest, mrem fyr per Ci/sec per -2 m ; a constant of unit conversion; K' = 6 10 pCi/pCi; = a constant of unit conversion; K" = 8760 hr/ year; = the radiological decay constant for radionuclide i, sec~ A = ) the exposure time, sec; t = 8 4.73x10 sec (15 years); = DFG; = the ground plane dose conversion factor for radionuclide :; 2 mrem /hr per pCi/m ; the shielding factor (dimensionless); SF = factor to account for fractional deposition of rec.ienuclide i. I; = For radionuclides other than iodine, the f actor I is equal to one. For radiciodines, the value of I; may vary. however, a value of 1.0 was used in calculating the R values in Table 3.3-2. 208 m .. J u C-7
A shielding f actor of 0.7 is suggested in Table E-15 of Regulatory' Guide 1.109 Revision 1. A tabulation of DFG; values is presented in Table E-6 of Regulatory Guide 1.109 s Revision 1. C.2.3 G_r, ass-Cow or Goat-Milk Pathway ~A t > E;te) B;y (1-e i b) - -A;tf - (1-e r R; = I; K' Qp U Fm (DFL;)a
II ap p s. Y A PA;
-A t
ib E *e)
B;y (1-e y_ - (1-e r II-I I ) K.2-M ps, Y A PA; s E. 1 where: dose factor for the cow milk or goat milk pathway, for each R;\\1 = identified radionuclide i for the organ of interest, mrem /yr per Ci/sec per m ; a constant of unit conv~sion; K' = 6 ) 10 pCi/gCi; = the cow's or goat's feed consumption rate, kg/ day (wet weight); Q = p the receptor's milk consumption rate for age group a, liters /yr; U = ap the agricultural productivity by unit area of pasture feed grass, Y = 2 kg/m ; the agricultural productivity by unit area of stored feed, kg/m ; Y = s F the stable element transfer coefficients, pCi/ liter per pCi/ day; = fraction of deposited activity retained on cow's feed grass; r = the organ ingestion dose factor for radionuclide i for the receptor (DFL;)a = in age group a, mrem /pCi; C-8
A A i+Aw; = g 1 -I the radiological decay constant for radionuclide i, sec ; A = i the decay constant for removal of activity on leaf and plant A = -I surf aces by weathering, sec ; 5.73x10-7 -I (corresponding to a 14 day half-life); sec = the transport time from feed to cow or goat to milk, to receptor, t = f sec; the transport time from harvest, to cow or goat, to consumption, t = h sec; peri d of time that sediment is exposed to gaseous effluents sec; t = b concentration factor for uptake of radionuclide i from the soil by B = y the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil); ) effective surface density for soil, Kg (dry soil)/m ; = fraction of the year that the cow or goat is on pasture; f = p fraction of the cow feed that is pasture grass while the cow is on f = s pasture; peri d of pasture grass and crop exposura during the growing t = e season, sec; factor to account for fractional deposition of radionuclide i. I; = =i) 1208.au C-9
For radionuclides other than iodine, the f actor I; is equal to one. For radiciodines, the value of I; may vary. However, a value of 1.0 was used in calculating the R values Tables 3.3-9 through 3.3-16. Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f was considered unity in lieu of site-specific information. The value 3 of f was 0.667 based upon an S-month grazing period. P Table C-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1. The concentration of tritium in milk is based on the airberne concentration rather than the deposition. Therefore, the R is based on X/Q : (C.2 4) K'K'" F 9F ap(DFL;), 0.75(0.5/H) R = T m y where: dose factor for the cow or goat milk pathway for tritium for the R.;. = 3 organ of interest, mrem /yr per Ci/m ; a constant of unit conversion; K '" = 3 10 gm/kg; = absolute humidity of the atmosphere, gm/m ; H = the fraction of total feed that is water; 0.75 = the ratio of the specific activity of the feed grass water to the 0.5 = atmospheric water. and other parame rs and values are given above. A value of H of S grams / meter, was used in lieu of site.gecific information. =~-) 1208 ~.T C-10
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore: 't -AE.I e' B (1-e )- -A.t + R = I K' Qp U,p Fm (DFL;)a
II
^ i - ps A PA; P E. 1 -A *b i A t E *) B (1-e k -A t - (1-e i y jh r II-f I I ps_ Y A PA; (C.2-5) s E.I where: R;B dose factor for the meat ingestion pathway for radionuclide i for = any organ of interest, mrem /yr per Ci/sec per m-2 ; the stable element transfer coefficients, pCi/Kg per pCi/ day; F = f ) the receptor's meat consumption rate for age group a, ~<g/yr; U = ap the transport time from slaughter to consumption, sec; t = s the transport time from harvest to animal consumption, sec; t = h Period of pasture grass and crop exposure during the growing t = e season, sec; factor to account for fractional deposition of radionuclide i. I; = For radionuclides other than iodine, the factor I; is equal to one. For radiciodines, the value of I; may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8.
3 1208,.u,
~ C-11
All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used in calculating R; for the meat pathway The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R; is based on X/Q. K'K"'F Q UF ap(DFL;)a 0.75(0.5/H) (C.2-6) R = f TB where: dose factor for the meat ingestion pathway for tritium for any R = T 3 E> organ of interest, mrem /yr per Ci/m. All other terms are defined in Equatior. 2-4 and C.2-5, above. C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression ] developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore: A *'b), l -A - (1-e E.*e) B.tv (1-e -A tiL r t R = I; K' (DFL;)a U fL* 1 -A *b) ~ i -A t -At B II-* 5 h r(1-e 'l *) iv ag Y A PA (C.2-7) y E. i I where: dose factor for vegetable pathway 'or radionuclide i for the organ R. = I of interest, mrem /yr per yCi/sec per m ?~; V a constant of unit conversion; K' = 6 10 pCi/ Ci; = 3J 1208 m C-12
L the consumption rate of fresh leafy vegetation by the receptor in U = a age group a, kg/yr; 5 the consumption rate of stored vegetation by the :ceptor in age U = a group a, kg/yr; the f raction of the annual intake of fresh leafy vegetation grown f = L locally; the fraction of the annual intake of stored vegetation grown f = locally; t the average time between harvest of leafy vegetation and its L consumption, sec; the average time between harvest of stored vegetation and its t = h consumption, sec; 2 the vegetation areal density, kg/m ; Y = y Period of leafy vegetable exposure during growing season, sec; t = e factor to account for fractional deposition of radionuclide i. I; = For radionuclides other than iodine, the factor I; is equal to one. For radiciodines, the value of 1; may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5. All other f actors were defined above. Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1. =3 1208 ZG C-13
In lieu of site-specific data default values for f and f,1.0 and 0.76, respectively, g were used in the calculation of R;. These values were obtained from Table E-15 of N Regulatory Guide 1.109 Revision 1. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R; is based on X/Q: T, L + Uffg. (DFL;)a 0.75(0.5/H) (C.2-8) R K 'K '" JI g where: dose factor for the vegetable pathway for tritium for any organ of R.;. = V 3 interest, mrem /yr per Ci/m. All other terms remain the same as those in Equations C.2-4 and C.2-7. m 1208,
C-14
TABLE C-1 3 Parameters For Cow and Goat Milk Pathways Parameter Value Reference (Rec. Guide 1.109 Rev.1 Qp (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 p (kg/m ) 0.7 Table E-15 Y f (seconds) 1.73 x 10' (2 days) Table E-15 t r 1,0 (radiciodines) Table E-15 0.2 (particulates) Table E-15 (DFL;)a (mrem /PCi) Each radionuclide Tables E-Il to E-It Fm (PCi/ day per pCi/ liter) Each stable element Table E-1 (cow) Table E-2 (goat) b (seconds) 4.73 x 10 (15 yr) Table E-15 t Ys (kg/m ) 2.0 Table E-15 2 p (kg/m ) 0.7 Table E-15 Y h (seconds) 7.78 x 106 (90 days) Table E-15 t ap (liters /yr) 330 infant Table E-5 U 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 e (seconds) 2.59 x 106 (pasture) Table E-15 t 5.18 x 10 (stored feed) B;y (pCi/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil)) 2 P (Kg (dry soil /m ) 240 Table E-15 ~N C-15
TABLE C-2 Parameters For The Meat Pathway Reference (Re2. Guide 1.109 Rev.1) Parameter Value 1.0 (radiciodines) Table E-1) r 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/ day) Each stable element Table E-1 U^P (Kg/yr) 0 infant Table E-5 41 child Table E-3 65 teers Table E-5 110 adult Table E-5 (DFL;)a (mrem /pCi) Each radionuclide Tables E-Il to E-14 2 Table E-15 0.7 p (kg/m ) Y 2 2.0 Table E-15 Ys (kg/m ) 4.73 x 10 (15 yr) Table E-15 } b (seconds) t 1.73 x 106 (20 days) Table E-15 s (seconds) t 7.78 x 106 (90 days) Table E-15 h (seconds) t 2.59 x 106 (pasture) Table E-15 e (seconds) t 5.18 x 106 (stored feed) 50 Table E-3 Qp (kg/ day) B (pCi/Kg (wet weight) Each stable element Table E-1 jy per pCi/Kg (dry soil)) P (Kg (dry soil)/m ) 240 Table E-15 =} m g 7.4 i C-16
TABI.E C-3 3 Parameters for the Vegetable Pathway Parameter Value Reference (Rec. Guide 1.105 Rev.1 r (dimensionless) 1.0 (radiciodines) Table E-1 0.2 (particulates) Table E-1 (DFL;)a (mrem /Ci) Each radionuclide Tables E-Il to E-14 U (kg/yr) - Infant 0 Table E-5 - Child 26 Table E-5 - Teen 42 Table E-5 - Adult 64 Table E-5 Uf (kg/yr) - Infant 0 Table E-5 - Child 520 Table E-5 - Teen 630 Table E-5 - Adult 520 Table E-5 g (seconds) 8.6 x 10 (1 day) Table E-15 t h (seconds) 5.18 x 106 (60 days) Table E-15 t 2 Y (kg/m ) 2.0 Table E-15 y t (seconds) 5.13 x 106 (60 days) Table E-15 b (seconds) 4.73 x 10 (15 yr) Table E-15 t P(Kg(dry soil)/m ) 240 Table E-15 _;J y(pCi/Kg(wet weight) Each stable element Table E-1 B per pCi/kg (dry soil)) ,n T208 ,4" C-17
APPENDIX D LOWER LIMIT OF DETECTABILITY The lower limit of detectability (LLD) is the smallest concentration of a radioactive materialin an unknown sample that will be detected with a 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal. The minimum detectable activity (MDA) is the smallest indicated activity in an unknown sample that can be said to be greater than background with a 5% probability that a true activity of zero will be falsely recorded ts a detectable activity. To ensure that the LI.D is detected 95% of the tim? it is present requires that activities down to the MDA level be recorded as present in the sample. Both LLD and MDA are given by the following equations: 4.66 b 'LD E V 2.22 Y exp(-A;t } (D*l'1} e 2.33 ab 'MDA E V 2.22 Y exp(-A;t ) (D.1-2) e 3 / where (N/t ) "b = b standard deviation of background (cpm) = background count rate (cpm) N = time background counted for (min) t = b E counting efficiency = V volume or mass of sample = conversion factor (dpm/pCi) 2.22 = Y fractional radiochemical yield = ~.y ,3, 1208 4' D-1
radioactive decay constant of ith nuclide (sec-I) A; = elapsed time between sample collection and counting (sec) t, = In calculating the LLD and MDA for a radionuclide determined by gamma ray spectroscopy, the background shall include the typical contributions of other radio-nuclides normally present in the sample (e.g., potassium-40 in milk samples). Analysis shall be performed in such a manner that the LLD's listed in Tables 2.1-2, 2.2-2, and 2.6-1 of Ref.1, will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence or interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. In addition, Table 6.9-2 in Section 6.9.2.a(6) of Ref. I gives the reporting levels for radioactivity concentrations in environmental samples. The methodology preseited in Ref. 2 and Ref. 3 to determine LLD and MDA may be used in lieu of Equations D.1-1 and D.1-2. s References 1. Radiological Effluent Technical Specifications for Brunswick Steam Electric Plant. 2. HASL-300 (Suppl. 4), HASL Procedures Manual, (1972). 3. NBS SP456 "The Minimum - Detectable - Activity Concept," 3. D. Lockamy, (1976). D-2 3}}

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1.0 INTRODUCTION

1.0 INTRODUCTION

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