ML20134J870

From kanterella
Jump to navigation Jump to search
Rev 4 to Offsite Dose Calculation Manual
ML20134J870
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/23/1985
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20134J843 List:
References
PROC-850823, NUDOCS 8508290508
Download: ML20134J870 (62)


Text

~

BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE' CALCULATION MANUAL (ODCM) itFNISION 4

, DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY b

i 8508290508 850823 PDR ADOCK 05000324 R PDR ,

u

7___.-

LIST OF EFFECTIVE PAGES

j. ODCM Page(s) Revision i 4 ii-viii- 1 1-1 0 2-1 2-2 0 2 2-6 1 2-7 0 2 2-10 1 2 2-12 0 2 2-16 1 3 3-12 4 3-13 1 3 3-19 4 3 3-23 1 3-24 4 3-25 .

1 3 3-28 4 3-29 1 3 3-31 4 -

3 3-36 1 3 3-40 4 3 3-45 1 3 3-48 4 3 3-68 1 4-1 1 4 4-3 4 4-4 3 4-5 4 4 4-7 3 5-1 0 6 6-2 0

. 6-3 4 A-1 0 A-2 4 A A-4 0 A A-7 4 A A-9 0 A A-13 4 A A-15 0 A A-19 4 A A-21 0 A-22 4 A A-28 0 B B-33 0 C C-18 0' D-1-- D-2 1 E-1 4 E-2 3 E-3 4 F F-3 O G-1 1

(

ODCM-(BSEP) i Rev. 4

3.0- GASEOUS EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This procedu're determines the monitor alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas radionuclides in the gaseous efflu'ent released from the site to areas at and beyond the site boundary exceeds 500 mrem / year to the whole body or exceeds 3000 mrem / year to the skin.

3.1.1 S'etpoint Based on Conservative Radionuclide Mix (Ground and Mixed Mode Releases)

The following method applies to gaseous releases via the Units 1 and 2 Turbine Building Vents and via the Units 1 and 2 Reactor Building Vents when determining the high. alarm setpoint for the Turbine Building Vent Gas Monitors and Reactor Buildit g Vent Gas Monitors. .

3.1.1.1 Determine the " mix" (noble gas radionuclide composition) of the gaseous effluent (the " mix" can be determined from actual data or by using GALE code results of Table 3.1-1):

a. Determine the gaseous source terms that are representative.of -

the " mix" of the gaseous effluent. Gaseous source terms are the noble gas activities in the effluent.

Gaseous source terms can be obtained from:

Table 3.1-1; Turbine Building Vent Release l

Table 3.1-1; Reactor Building Vent Release Actual release data

b. Determine Sg (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide 1) for each individual noble gas radionuclide in the gaseous effluent.

l ODCM (BSEP) 3-1 Rev. 4 l

l l

g S

1

= i- (3.1-1)

IA f g

i

~

A'=

f The radioactivity of noble gas radionuclide i in the gaseous effluent from Table 3.1-1, Turbine Building Vent Release; Table 3.1-1, Reactor Building Vent Release; or' from analysis of gaseous effluent.

3.1.1.2 Determine the Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, pCi/sec) based upon the whole body exposure limit. .

Qg .= 500 (3.1-2)

'(x/Q) I (K gg S) .

i (x/Q)tb = The highest calculated annual average relative concen-tration of effluents released via the Turbine Building Vent for any area at or beyond the site boundary for all

. sectors (sec/m*) from Table A-1, Appendix A

= 7.50 E-6 sec/m* ,

, (x/Q)rb = The highest calculated annual average relative concen-tration of affluents released via the Reactor Building Vent for any area at or beyond the site boundary for all sectors (sec/m*) from Table A-7, Appendix A l

= 2.0 E-7 sec/m*

NOTE: Use the x/Q that applies to the monitor for which the alarm setpoint is being calculated.

Kg= The total whole body dose factor due to gamma emissions from noble gas radionuclide 1 (mrem / year /pCi/m*) from Table 3.1-2.

3-2 Rev. 4 ODCM (BSEP)

I

3.1.1.3 Determine Q g based upon the skin exposure limit.

Qg = 3000 (3.1-3)

(x/Q) I [(L + 1.1 M )S ]

1 1 i i Lg+ 1.1M g= The total skin dose factor due to emissions from noble gas radionuclide 1 (mrem / year /pCi/m') from Table 3.1-2.

NOTE: The Turbine Building radiation monitors are designed to input the monitor high alarm setpoint in pCi/sec or pCi/cc. The monitor setpoint in pC1/sec can be obtained by multiplying the lowest Qg value (obtained from Sections 3.1.1.2 and 3.1.1.3) by the T ,value found in Section 3.1.1.5.b. The pCi/cc setpoint can be obtained by dividing the pCi/sec setpoint by the design flow rate in -

cc/sec. The equations for calculating the setpoint in cpm are included for completeness and may be used if desired. .

3.1.1.4 Determine Cg (the maximum acceptable total radioactivity concen-tration of all noble gas radionuclides in the gaseous effluent, pCi/sec/cfm).

Ot C, = (3.1-4) f NOTE: Use the lower of the Qt values obtained in Sections 3.1.1.2 and 3.1.1.3.

f = The maximum acceptable effluent flow rate at the point of release (cfm) based on design flow rates

= 15,000 cfm (Turbine Building Vent)

= 172,800 cfm (Reactor Building Vent)

ODCM (BSEP) 3-3 Rev. 4 i

t

-3.1.1.5 Determine the monitor high alarm setpoint above background:

a. Determine CR (the calculated monitor count rate above background attributed to the noble gas radionuclides, net cpm).

= C

~

CR t (3.1-5)

E, E, = The detection efficiency of the monitor for the " mix" of noble gas radionuclides in the gaseous effluent (pCi/sec/cfm.cpe) from E&RC files

b. Determine HSP (the monitor high alarm setpoint with background, cpm). -

HSP = T,CR + Bkg. (3.1-6)

=

T, Fraction of the radioactivity from the site that may -

be released via the monitored pathway to ensure;that the site boundary limit is not exceeded during simultaneous releases from several pathways

= 0.10 for the Unit 1 Turbine Building Vent Gas Monitor

= 0.10 for the Unit 2 Turbine Building Vent Gas Monitor

= 0.20 for the Unit 1 Reactor Building Vent Gas Monitor

= 0.20 for the Unit 2 Reactor Building Vent Gas Monitor Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air ODCM (BSEP) 3-4 Rev. 4 5

c. The monitor high alarm setpoint including background (cpm) shall be set at or below the HSP value determined above.

^3.1.2 Satpoint Based on Conservative Radionuclide Mix (Long-Term Elevated Release

  • The following method applies to gaseous releases via the stack when ,

determining the high-high alarm setpoint for the Stack Monitor during '

continuous release via the stack.

3.1.2.1- Determine the " mix" (noble gases and composition) of the gaseous effluent:

a. Determine the gaseous source terms that are representative of the " mix" of the. gaseous affluent. Gaseous source terms are

~

the noble gases radionuclide. activity concentrations in the *

. effluent.

b. Determine Sg (the fraction of the total radioactivity in the

_ gaseous effluent comprised by noble gas radionuclide 1) for each individual noble gas radionuclide in the gaseous effluent.

= H, S

g i (3.1-7)

IA f i

Ag = The radioactivity of noble gas radionuclide i in the gaseous effluent from Table 3.1-1, Stack Release, or from analysis of gaseous effluent.

3.1.2.2 Determine Qg (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent, pCi/sec) based upon the

. whole body exposure limit.

l CDCM (BSEP) 3-5 Rev. 4 4

I

-Q = '500 I [V ti S}

l' V'

g

= The constant for noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume (mrem / year /pCi/sec) from Table 3.1-2

-3.1.2.3. ' Determine Q g based upon the skin exposure limit.

'Qg_= -3000 (3.1-9)_

E [(L (X/Q) + 1.1B )S ]

i i s i i

(

Lg(x/Q), + 1.1Bf = The total skin dose constant for long-term releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) due .

. to emissions from noble gas radionuclide 1

~

(mrem / year /pCi/sec) from Table 3.1-2).

NOTE: The stack radiation monitor is designed to input the monitor high-high alarm setpoint in pCi/sec or pCi/cc.

The monitor setpoint in pCi/sec can be obtained by multiplying the lowest Q, value (obtained from Sections 3.1.2.2 and 3.1.2.3) by the T,value found in

.Section 3.1.2.5.b. The pCi/cc setpoint can be obtained by dividing the pCi/sec setpoint by the design flow rate in

, cc/sec. The equations for calculating the setpoint in cps are included for completeness and may be used if desired.

3.1.2.4- Determine Cg (the total maximum acceptable radioactivity concen-  ;

, tration of noble gas radionuclides in the gaseous effluent, s .

pCi/sec/cfm).

ODCM (BSEP) 3-6 Rev. 4

y  ; , t. At L- ,

t-C= g ' 0t '

(3.1-10) f

l. .

K f NOTE: Use the lowest of'the Qg values.obtained in Sections 3.1.2.2 and.3.1.2.3.

f= The maximum acceptable effuent flow rate at the point of release (cfm) based on design ficw rates-

=- 86,000 cfm (stack)

, e

k. 3.1.2.5 Determine the monitor high-high alarm setpoint above background:

i i

a. Determine the CR (the calculated monitor count rate above background attributed to the noble g's a radionuclides, net cps).

CR = t (3.1-11)

E-

,, m 1

E, = The detection efficiency of the monitor for the " mix" l- of noble gas radionuclides in the gaseous effluent (pCi/sec/cfm* cps) from E&RC files i $? ;/ '

'o ,

.c b. Determine HHSP (the monitor high-high alarm setpoint with background, cps).

I/.l *-

.+l ) c '

[..

o 1 -t HHSP = T CR + Bkg m (3.1-12)

.$. =

T, Fraction of the radioactivity from the site that may.

be 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 ODCM (BSEP) 3-7 Rev. 4

Bkg = The background count rate (cps) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector-sample chamber is filled with uncontaminated air

c. The monitor high-high alarm setpoint including background (cps) shall be set at or below the HHSP value determined above.

.3.1.3 Condenser Air Elector Monitor Alarm Setpoint 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 small fraction of the limits of 10CFR100 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 Units 1 and 2 condenser air ejectors when determining the maximum allowable-alarm setpoint for the Condenser Off-gas Radiation Monitors.

g a-. Determine Q, the allowable release rate (uci/sec) at the air ejector for the noble gas radionuclides.

Specification 3.11.2.7 limits the gross radioactivity rate of noble gases measured at the main condenser air ejector to less than or equal to 243,600 pCi/sec (after 30 minutes' decay).

Assume that the noble gas conc 9ntrations at the, air ejector (t = 0) are representative of the GALE code. Since the holdup time between the air ejector and the stack (down the 30-minute holdup line) can vary due to operational conditions, the mix of the noble gases at the stack should be determined based on the actual decay time not to exceed 30 minutes. This mix can then ODCM (BSEP) 3-8 Rev. 4

'i -

i, ,

g be applied to the 243,600 pCi/sec limit and then back-calculated to determine the allowable release rate at the air ejector, Q. As an example, assume that the holdup time is 30 minutes. The mix of the noble gases after 30 minutes' decay (t' = 30 minutes) can be determined by the following table. .

GALE Code Fraction Steam (pCi/gm) Steam (pCi/gm) pCi/sec* e' UCi/sec of Mix Nuclide t=0 t=0 t=0 t = 30m t = 30m t = 30m (for 3400 MWt) (for 2436 MWt)

Kr-83m 9.1E-4 6.5E-4 8.58E+2 8.3E-1 7.1E+2 2.9E-2 Kr-85m 1.6E-3 1.1E-3 1.45E+3 9.2E-1 1.3E+3 5.3E-2 Kr-85 5.0E-6 3.6E-6 4.75E+0 1.0E+0 .4.8E+0 2.0E-4

,Kr-87 5.5E-3 3.9E-3 5.15E+3 7.6E-1 3.9E+3 1.6E-1 Kr-88 5.5E-3 3.9E-3 5.15E+3 8.8E-1 4.5E+3 1.8E-1 Kr-89 3.4E-2 2.4E-2 3.17E+4 1.5E-3 4.7E+1 1.9E-3 Kr-90 7.5E-2 5.4E-2 7.13E+4 3.8E-17 2.7E-12 1.1E Xe-131m 3.9E-6 2.8E-6 3.70E+0 1.0E+0 3.7E+0 1.5E-4

~

Xe-133m 7.5E-5 5.4E-5 7.13E+1 9.9E-1 7.0E+1 2.8E-3 Xe-133 2.1E-3 1.5E-3 1.98E+3 1.0E+0 2.0E+3 8.1E-2 Xe-135m 7.0E-3 5.0E-3 6.60E+3 2.6E-1 1.7E+3 6.9E-2 Xe-135 6.0E-3 4.3E-3 5.68E+3 9.6E-1 5.4E+3 2.2E-1 --

Xe-137 3.9E-2 2.8E-2 3.70E+4 4.2E-3 1.6E+2 6.5E-3 Xe-138 2.3E-2 1.6E-2 2.11E+4 2.3E-1 4.8E+3 2.0E-1 TOTAL 2.46E+4 1.0E+0

  • Steam Flow = (10,470,524 lbs/hr) (0.1260 gm/sec) = 1.32E+6 gm/sec lbs/hr Applying this mix to 243,600 pCi/sec (after 30 minutes' delay) and back calculating to t = 0 will yield the allowable pCi/sec per noble gases at the air ejectors; i.e.:

e Rev. 4 I ODCM (BSEP) 3-9 s

Fraction Tech Spec Tech Spec of Mix (pCi/sec) e'* (pCi/sec)

Nuclide t = 30 min t = 30 min t = 30 min t=0 Kr-33m 2.9E-2. 7.06E+3 8.3E-1 8.51E+3 Kr-85e 5.3E-2 1.29E+4 9.2E-1 1.40E+4

~

'Kr-85 2.0E-4' 4.87E+1 1.0E+0 4.87E+1 Kr-87 1.6E-1 3.90E+4 7.6E-1 5.13E+4 Kr-88 1.8E-1 4.38E+4 8.8E-1 4.98E+4 Kr-89 1.9E-3 4.63E+2 1.5E-3 3.09E+5

'Kr-90 ~1.1E-16 2.68E-11 3.8E-17 7.05E+5 Xe-131m 1.5E-4 3.65E+1 1.0E+0 3.65E+1 Xe-133m '2.8E-3 6.82E+2 9.9E-1 6.89E+2 Xe-133 8.1E-2 1.97E+4 1.0E+0 -

1.97E+4

- Xe-135m ,

6.9E-2 1.68E+4 2.6E-1 6.46E+4 Xe-135 2.2E-1 5.36E+4 9.6E-1 5.58E+4 Xe-137 6.5E-3 1.58E+3 -

4.2E-3 3.76E+5 Xe-138 2.0E-1 4.87E+4 2.3E-1 2.12E+5 -

TOTALS '1.0E+0 2.44E+5 1.87E+6 Therefore:

Q = 1.87E+6 pCi/sec (for 30 minutes' holdup) -

b. Determine C, (the _ total radioactivity concentration of noble gases) in the condenser air ejector gas (pCi/sec/sefm).

C, = Q/f (3.1-13)

Q = The allowable release rate (pCi/sec) at the air ejector t'or noble gases

. f = The main condenser air inleakage rate plus the radiolytic gas flow rate ODCM (BSEP) 3-10 Rev. 4 4

f.>

c. - Determine the monitor high-high: alarm setpoint above

-, -background.

(1) . Determine MR (the calculated monitor response attributed to'ths noble gas radionucl. ides, mR/hr).

~

tGt = m , .(3.1-14)

E, E, =f The detection efficiency of the monitor 'for the'

- " mix" of noble gas radionuclides in the gaseous stream ((pCi/sec)/(mR/hr*cfm)) from E&RC files (2) The monitor high-high~ alarm setpoint (mR/hr) should be set at or below the MR value determined above.

3.1.4 = Condenser Off-Gas Treatment System (A0G) Monitor Alarm'Setpoint

~

Determination- -

This method determines the monitor alarm setpoint that' includes sufficient' noble gas activity to cause an alarm at the stack effluent noble gas monitor.

J 3.1.4.1 ; Determine Qt (the maximum acceptable total release rate of all noble -

s gas radionuclides Jbt the gaseous ' effluent, pCi/sec) based upon the whole. body exposure (see Equation 3.1-8) and skin exposure (see Equation 3.1-9).-

NOTE: Use the lowest of the Qt values btained.

3.1.4.2 Determine Q, (the site adjusted maximum release rate, pCi/sec, for effluent' releases via the stack).

Q,

=

Q x T, (3.1-15)-

ODCM (BSEP) 3-11 Rev. 4 4

e.

~ Ty = Fraction of radioactivity from the site that may be released

'via the stack to ensure that the site boundary 1 Lait is not exceeded during simultaneous releases from several pathways

= 'O.4 for the stack monitor

~

3.1.4.3 Determine HSP (high alarm setpoint 'in~ pCi/cc).

HSP = Q,

  • f (3.1-16) f = . Maximum design flow rate of the A0G System

= 70,800 cc/sec (150 cfm)

'3.1.4.4 The monitor high alarm setpoint shall be set at or below the HSP value determined above.

I l

~^'

l ODCM (BSEP) 3-12 Rev. 4

l TABLE 3.1-2.

DOSE FACTORS AND CONSTANTS Total Body Total Skin Dose-Total Whole Body Total Skin Dose Constant For Constant for Do'se Factor Dose Factor Long-Term Releases Long-Term Releases Radio (Kg ) (Vg) (Lg (x/Q), + 1.1Bg)

(L1 + 1.1Mg )

8 8 nuclide (mrem /yr/uci/m )- (mrem /yr/pci/m ) (ares /yr/vCi/sec) (mrem /yr/uCi/sec)

Kr-83m 7.56E-2 2.12E+1 1.66E-9 1.54E-7 Kr-85m 1.17E+3 2.81E+3 9.18E-5 1.60E-4 Kr-85 1.61E+1 1.36E+3 1.36E-6 1.19E-5 Kr-87 5.92E+3 1.65E+4 4.17E-4 7.60E-5 Kr-88 ,

1.47E+4 1.91E+4 1.08E-3 1.80E-3 Kr-89 1.66E+4 2.91E+4 6.55E-4 1.16E-3 Xe-131m 9.15E+1 - . 6.48E+2 2.17E-5 4.09E-5 Xe-133m 2.51E+2 1.35E+3 1.64E-5 3.64E Xe-133 2.94E+2 6.94E+2 1.72E-5 3.16E-5 Xe-135m 3.12E+3 4.41E+3 2.17E-4 3.67E-4 Xe-135 1.81E+3 3.97E+3 1.47E-4 2.56E-4 Xe-137 1.42E+3 1.39E+4 5.64E-4 1.82E-4 Xe-138 8.83E+3 1.43E+4 6.61E-4 1.12E-3 -

A'-41:

r 8.84E+3 1.29E+4 7.86E-4 1.32E-3 ODCM (BSEP) 3-14 Rev. 4 4

3.2 ' COMPLIANCE WITH 10CFR20 .(GASEOUS)-

3.2.1 Noble Gases

.The gaseous' effluent monitors' setpoints are utilized to show compliance with 10CFR20 for noble gases. However, bacause they are based upon a conservative mix of' radionuclides, the possibility exists that the setpoints could be exceeded and yet 10CFP20' limits may not be exceeded. Therefore, the following l

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 10CFR20.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem / year to the tetal body and 3000 mram/ year to the skin.

Based upon NUREG 0133, the following are used to show compliance with 10CFR20.

~

~

'I f VfQj + -Kg (x/Q),Qt 5 500 mram/yr (3.2-1).

s. v .
f. . ,

I i

4 Lg(X/Q)_ + 1.1B g Qg + (L g + 1.1Mg )(x/Q) , Qg )$300 mrem /yr (3.2-2) s s v)

E where:

Kg = The total body dose factor due to gamma emissions for ncble gas radionuclide i, mram/ year per pCi/a*

Lg = The skin dose factor due to beta emissions for noble gas radionuclide i, mram/ year per pCi/m*

M = The air dose factor due to. gamma emis! ions'for noble gas radionuclIde i, mrad / year per pCi/m*

Vg =- The constant for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem / year per pCi/sec ODCM (BSEP) 3-15 Rev. 4

B =. The constant.for long-term releases-(greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) f for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad / year per pCi/sec 1.1 = The ratio of the tissue to air absorption coefficients over the

' energy range of.the photon of interest, mrem / mrad i = I The release rate of noble gas radionuclide i in gaseous effluents s-from free-standing stack, UCi/sec i = .The release rate of noble gas radionuclide i in gaseous effluents from all vent releases, pCi/sec At the' Brunswick Steam Electric Plant (BSEP), gaseous releases may occur from:

1.- The Turbine Building vent 2 .' The Reactor Building vent ,

3. ;The stack Releases from the Turbine Building are ground level. The sources of these releases are steam leakage through valve stems, pump seals, and flanged connections. Releases from the Reactor Building are considered mixed mode in nature, and'the source is also leakage through 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, Radwaste Building and A0G Building v.entilation system erhausts, mechanical vacuum pump exhausts during startup, and gland seal off gases.

Noble gas releases may occur from all three points. To show compliance with 10CFR20, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release poin'ts for BSEP.

For the total body dose:

I Qg +IKgg 5 500 mrem /yr (3.2-3) f -

(x/Q)rb N i + (*/0)tb N i s rb tb_

ODCM (BSEP) 3-16 Rev. 4 (

For the' skin dose:

E g Lg(x/Q), + 1.1Bf Qg.+If L g-+ 1.lM g (x/Q)rb 0~1 '+ (*IO)tb 0 1 s - - -

rb tb 5 3000 mres/yr (3.2-4) where:

1, , = Release rate of radionuclide i from the stack, pCi/sec i

rb.

= Release rate of radionuclide i from the two Reactor Buildings, UCi/sec i

th

= Release rate of radionuclide i from the two Turbine Buildings, pC1/sec. .

(x/Q), = 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 average relative concentration for releases from ,

the Turbine Buildings, sec/m*

~ All other terms ' remain' the same as those defined previously.

~The determination of controlling location for implementation of 10CFR20 for noble gases is a function of the radionuclide mix, the 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 locations for the BSEP. This

' location is 0.7 miles, the ENE site boundary.

ODCM (BSEP) 3-17 Rev. 4 i

Q W

~

-For-the total body-I ggt Vh +I fK[-(6.5 x 10 ' hg +3.2x10'h;-)s500 mrem /yr (3.2-5).

-s - -

rb tb

_ For1the skin:-

If (r.2 x 10

  • Lg+-1.1B)h 1 g

+

s I

f (L g + 1.lMg ) (6.5 x 10 ' h g + 3.2 x 10 ' h g ) s 3000 mram/yr- (3.2-6) rb tb '

The radicauclide mix was based upon source. terms calculated using the NRC GALE code. ~They were calculared based upon the present operating mode of 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

~1ocation. .

The x/Q values utilized in the equations for implementation of 10CFR20 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.

i

[

ODCM'(BSEP) 3-18 Rev. 4 l 4

i i

m

l l

Long-term annual- (x/Q) . values for the stack, Reactor Building, and Turbine Building release points from BSEP to the special locations in Table 3.2-2 are presented in Appendix A. A description of the derivation is also provided in this appendix.- . x7Q . values at the limiting site boundary for releases from the

Turbine Building, Reactor Building, and stack were obtained from Tables A-1, A-7, and A-13, respectively, of the appendix.

.To determine the controlling location for implementation of 10CFR20, the two or three highest site boundary x7Q values for each release point'were utilized in conjunction with the radionuclide mix and release rate for each release point. Since mixed mode and elevated ~ releases occur from BSEP, their maximum x74 value may not decrease with distance; i.e., the site boundary may not have the highest x/Q values. Therefore, long-term annual average x/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 of Appendix A. The highest two or three x7Q values for each release point at a distance greater than the site boundary were used in conjunction with the radionuclide mix to determine the controlling location. A particular combination of release point mix and meteorology dominates in the -

determination of the controlling location. For BSEP, it is the stack, and the controlling location' is at the ENE site, boundary.

Values for K g , Lg , and Mg , which were used in the determination of the controlling locations and which are to be used by BSEP in Expressions 3.2-5 -

and 3.2-6 to show compliance with 10CFR20, are presented in Table 3.2-4.

These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have-been 0 ~1 multiplied by 10 to convert picocuries to microcuries' for use in l Expressions 3.2-5 and 3.2-6.

Values for Vgand B yfor the finite plume model can be expressed as shown in Equations 3.2-7 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN. Values for V g and B f for each of the 16 sectors are presented in Appendix B.

ODCM (BSEP) 3-19 Rev. 4 i

I[ Pg (x/Q), Q + (x/Q)g Q + (x/Q)g Q +I (P g +Pg)

I -.. s rb tb- G M (D/Q),'Q g + (D/Q)rb 0 1- + (D/Q)tb O i $ 1500 mrem /yr. (3.2-11)

- s rb. ,t b -

where:

Pg =- Dose parameter for radionuclide i for the inhalation pathway, 3

mrem / year per pCi/sec Pg = Dose parameter for radionuclide i for the ground plane pathway, mram/ year per pCi/sec per m -2 .

Pg = Dose parameter for radionuclide i for either the cow milk or -

goat milk pathway, mrem / year per pCi/sec per m -2 (x/Q)rb = Annual avorage relative concentrations for releases from the 3

Reactor Buildings, sec/m (x/Q)tb = Annual average relative concentrations for releases from the 3 ..

Turbine Buildings, sec/m 1

(x/Q), = Annual average relative concentrations for releases from the 3

stack, sec/m (D/Q)rb = Annual average deposition for releases from the Reactor

~

Buildings, m (D/Q)tb = Annual average deposition for releases from the Turbine Buildings, m'

~

(D/Q), = Annual average deposition for releases from the stack, m ODCM (BSEP) 3-24 Rev. 4

i l

.1R) show compliance with 10CFR20, 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 radioiodines and particulates.and from tritium must be summed and their combined dose rates less than 1500 mres/ year to show compliance with

- 10CFR20. If the 1500 mrem / year limit is exceeded at the limiting site boundary when all pathways are considered present at the site boundary but the

' inhalation psthway-contributes less than 1500 mrem / year, then Expressions 3.2-11 and 3.2-13 are evaluated at the limiting real pathway location.

The limiting site boundary location is 0.7 miles NE. Expression 3.2-11 l becomes:

For radioiodines and particulates:

IPgg (2.5 x 10 ' h g + 2.0 x 10 7 h g + 2.9 x 10 8 h g )+ .

I s rb tb If (Pg + Pg ) (1.4 x 10 ' h g + 4.3 x 10 ' h g + 1.9 x 10 ' h g )

G M s rb tb 5 1500 mrem /yr (3.2-14)

For BSEP, the limiting " hypothetical" real pathway location is the cow mi1k pathway 4.75 miles NE. At this location, Expression 3.2-11 becomes:

IP gg (2.4 x 10 ' h g + 4.1 x 10 8 kg + 1.4 x 10 ' h g ) +

I s rb tb If (Pg + Pg ) (2.2 x 10 18 h g + 2.7 x 10 ** h g + 5.7 x 10 1' h)g G M s rb tb i

5 1500 mrem /yr (3.2-15) 4 ODCM (BSEP) 3-26 Rev. 4 e

c s

For' tritium, at. the limiting site boundary, Equation 3.2-13 becomes:

~

~

~

. For. tritium:

bT= 3.0 xL10 8 (2.5.x 10 ' hT + 2.0 x 10 h t +2.9x19ht ) '(3.2-16) 3 rb tb

'At the " hypothetical" limiting real pathway location, Equation'3.2-13 becomes:

' For tritium: ,

bT.= 3.0 x.10 8 (2.4 x 10 ' hT + 4.1 x 10 ' h g .+ 1.4 x 10 7 kg .) (3.2-17) s rb tb The. determination of controlling location for implementation of 10CFR20 for

'radioiodines and particulates is a function of the-same-two parameters as for.

~ -

noble. gases plus a third receptor pathway location. The incorporation of: l.

. 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 BSEP, the. combination of meteorology and release rate which dominates comes from the stack.

In the determination of 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 conjunetion with the radionuclide mix and release rate for each release point. For BSEP, the controlling l'ocation is a hypothetical cow milk pathway 4.75 miles NE of the Reactor Building and l

. Turbine. Buildings. 1 ODCM (BSEP) 3-27 Rev. 4

, Values for P g were calculated for an infant for various radionuclides for the inhalation,; ground plane, cow milk, and goat milk pathways using the methodology of NUREG 0133. The gP values are presented in Table 3.2-5. The values ~of 1P reflect. for each radionuclide, the maximum Pg value for any organ,for ea'ch. individual pathway of exposure. Because the goat milk pathway is not present at BSEP, the cow milk pathway Pg values were utilized in the-

'determinationIof the various controlling 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.,,P = 0). However, P g G

G

' comp 1 toness.- Appendix C' presents the methodology which was utilized in calculating Pg values.

Annual average D/Q values at the special locations for the ' stack, Reactor

- Building, and Turbine -Building release points, respectively, .which were ,

utilized in Expressions 3.2-14 through 3.2-17 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 Appendix A. D/Q values at tho'

~

limiting site boundary location and the limiting real pathway. location for releases from the Turbine Buildings, the Reactor Buildings, and the stack were obtained frbs 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.

e f

ODCM (BSEP) 3-28 Rev. 4

TABLE 3.2-2 DISTANCE TO CONTROLLING-LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi)

Site Milk Milk

  • Meat Nearest Nearest Sector _

-Boundary Cow Goat Animal Resident Garden NNE 0.7' - -

1.4 1.4 1.4 NE 0.7 4.75* - - - -

ENE 0.7 - - - - --

.. .E 0.7 - -

1.1 1.3 -

ESE 0.7 - -

0.9 1.6 1.6 SE 0.7 - -

1.0 1.0 -

SSE 0.7 - -

0.9 0.9 -

0.9 5 0.8 - - -

1.4 1.8

.SSW :0.8 - -

1.5 1.4 1.5 .

SW 0.7 - -

1.0 1.0 1.0 WSW 0.7 - -

1.8 1.1 1.1 ,

W 0.7 - - -

0.9 0.9 WNW 0.6 - - -

0.9 0.9 NW 0.6 - - - 0.9 0.9 NNW- 0.6 - - -

0.9 0.9 N 0.7 - - -

0.9 1.0 .,

  • A." hypothetical" cow milk pathway is located at this point in accordance with 5.3.1 of NUREG 0133.

e I

e I

l.

ODCM (BSEP) 3-30 Rev. 4

TABLE 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON-BRUNSWICK PIANT CENTER AND DIRECTIONS FROM THE STACK Based on Center of From Stack to Site Boundaries

. Brunswick Plant of Table 3.2-2' Site Boundary Direction Distance (MI) Direction Distance (Mi) ,

NNE 0.7 NNE 0.7 NE 0.7 NE 0.7 ENE 0.7 ENE 0.7

'E 0.7 E 0.6 ESE 0.7 ESE

S 0.8 S 0.6 SSW 0.8 SSW 0.7 ,

SW 0.7 SW 0.7 WSW 0.7 WSW 0.7 W 0.7 W 0.8 WNW~ 0.6 WNW 0.7 NW 0.6 NW 0.7 NNW 0.6 NNW 0.7 N 0.7 N 0.8 4

OCCM (BSEP) 3-31 Rev. 4 6

e

I

' Gamma radiatlon:

(

01 + +3011 3.17 x 10 8 I f M[ '(x/Q)rb (Oi

~

) + (*!O)tb (Ni 1

)

rbi rb2 tbi - tb2 s/

5 10 mrad per' quarter or 20 mrad per~ year (3.3-5)

. Beta radiation:

3.17 x 10 ' I gg N (x/Q)rb (Oi +0 1 ) + (*/Q)tb C0 1 +0 1 )* (X/0)sQ i I rbi rb2 tb1 tb2 s-5 20 mrad'per quarter or 40 mrad per year. (3.3-6) where:

(x/Q)rb = Annual average relative concentration for releases from the 3

  • Reactor Building, sec/m (x/Q)tb = Annual average relative concentration for releases from the Turbine Building, sec/m (x/Q), = Annual average relative concentration for releases from the 3 '

stack, sec/m Q1 ,Q g = Release of radionuclide i from Reactor Buildings 1 and 2, rbi rb2. respectively, pCi Qg ,Q = Release of radionuclide i from Turbine Buildings 1 and 2, 1

j t1 tb2 respectively, pCi Qg = Release of radionuclide i from the stack, 9C1 At BSEP, the limiting location for noble gases is 0.7 miles ENE. Substitution l of the appropriate x/Q values into Expressions 3.3-5 and 3.3-6 results in the following:-

ODCM (BSEP) 3-37 Rev. 4

' During any calendar quarter or year:

i

' Gamma radiation:

t ~ ~

3.17 x 10 8 .I i M 6.5 x 10-8 (Q +Q ).+ 3.2 x 10-6 (q ,Q )

rb1 rb2 .tb1 tb2 -

3

+B f Qg y 5 10 mrad per quarter or 20 mrad per year

.(3.3-7) s)

Bete radiation:

-8 3.17.x 10 I Ng 6.5 x 10-8 (Q g +Q g ) + 3.2 x 0 (Q g +Q g )

rbi rb2 tb1 tb2

+ 7.2 x.10 Qg 5 20 mrad per quarter or 40 mrad per year (3.3-8) s- .

The determination of the controlling locations for implementation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology The incorporation of these parsmeters 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 3.3-8. 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 x7Q values for each release point were utilized in conjunction with the radjonuclide mix and release for each release .

point to determine-the controlling si::e boundary location. Since mixed mode i

} ..

'0DCM (BSEP) 3-38 Rav. 4 l.

is

n and elevated releases occur from BSEP and their maximum x7Q values may not decrease with distance (i.e., the site boundary may not have the highest X76 values);275valueswerecalculatedatthemidpointof10standarddistance intervals out to a distance of 5 miles. The two or three highest 27Q values were considered in conjunction with the radionuclide mix and releases to determine'the controlling location.

In the determination of the controlling location, 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 Appendix A. A description of the derivation of 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 BSEP the controlling release

- point is the stack. -

Values for M gand N ,g which were used in the determination of the ~ controlling location and which are to be used by BSEP in Expressions 3.3-7 and 3.3-8 to show compliance with 10CFR50 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 Guide 1.109, Revision 1. The values have been multiplied by 106 to '

convert from picoeuries to microcuries.

The following relationship should hold for BSEP to show compliance with Radiological Effluent Technical Specification 3.11.2.2.

For the calendar qucrter:

DT $ 10 mrad (3.3-9)

DS $ 20 mrad (3.3-10)

ODCM (BSEP) 3-39 Rev. 4 4

For the calendar year:

DT $ 20 mrad (3.3-11)

DS $ 40 mrad- (3.3-12) khere:

DT = The air dose from gamma radiation, mrad D6 = The air dose from beta radiation, mrad

. The quarterly limits given above represent one-half the annual design

. objective of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-9 through 3.3-12 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.

3.3.2 Radioiodines and Particulates 3.3.2.1 Cumulation of Doses -

Section II.C of Appendix 7 of 10CFR50 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 or year:

~0 3.17 x 10 I fRg (W, Qg +w ,qg +Wy Q 1 +wy q1 )

s s v v F

s 7.5 mrem per quarter or 15 mrem por calendar year (3.3-13) 6 ODCM (BSEP) 3-40 Rev. 4

To show compliance with:10CFR50, Expression 3.3-15 is evaluated at the controlling pathway location. At BSEP the controlling location is a milk cow 4.75 miles.in the NE sector. Expression 3.3-15 becomes:

-10 3.17 x 10-8.I (R g +Rg) 2.2 x 10 Q , + 2.7 x 10-10-(q

. ,q )+

g. G M -

s rb1 rb2

~

5.7 x 10-10 (q i

,g i ) +R g 2.4 x 10 ~0 Qg + 4.1 x 10-8 (q ,Q ),

tb1 tb2 - -

s rb1 rb2 h

1.4 x 10-7 (Q g +Q g ) , 5 15 mrem / quarter or 30 arem/ year (3.3-17) tb1 tb2 -

s For tritium, Equation 3.3-16 reduces to: .

DT = 3.17 x 10-8 (RT +RT) 2.4 x 10" QT + 4.1 x 10-8 (q ,q ) , .

M I - s rbi rb2

~

1.4 x 10 (Q T +NT ) (3.3-18) tb1 tb2 The determination of a controlling location for implementation of 10CFR50 for radiciodines and particulates is a function of: -

(1) Radionuclide mix and isotopic release (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Expression 3.3-14 results in the respective equations at the controlling location.

In the determination of the controlling location, the radionuclide mix of

.radiolodines and particulates was based upon the source terms calculated using the GALE code. This six was presented in Table 3.2-1 as a function of release

! point.

l ODCM (BSEP) 3-46 Rev. 4

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

In-the determination of the controlling location, all of the exposure pathsays, as presented in Table 3.2-2, were evaluated. These include cow '

milk, goat milk, beef and vegetable ingestion, and inhalation 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 silt pathways were selected. At BSEP, no cow milk or goat milk pathways ,

are present. In accordance with NUREG 0133, dose to a " hypothetical" cow milk pathway located 4.75 miles NE was evaluated against existing vegetable garden pathways. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1. Based upon these

  • I calculations, it was determined that the controlling receptor pathway is the L " hypothetical" cow milk-infant pathway in the NE sector, at 4.75 miles. -

Tables 3.3-1 through 3.3-19 present R g values for the total body, GI tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, and 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 d

NUREG 0133 using a grazing period of eight months. A discussion of their calculation'is presented in Appendix C.

' ~

In the determination of the cor. trolling location annual average 6M and x'7Q values are utilized. D/Q values at the limiting real pathway locations for

-releases from the Turbine Buildings, Reacter Buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A. x/Q ,

, i j

k j .

l ODCM (BSEP) 3-47 'Rev. 4

.i

. - - - , - - -..,-...,_..--_-m_ ,,,----.-v_._ m. _ , - - , . - , . . . - , - - - - -.... - . _ ,.-~, - ,-- ,- -

m 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 D74 values for the stack, Reactor Buildings, and Turbine Buildings

~

are provided for the midpoints of the following distances:

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. '4.5-5.0 mi.

These values appear in tables in Appendix A. These tables may be utilized if l an additional special location arises different from those presented in the special locations of Table 3.2-2. .

The following relationships should hold for BSEP to show compliance with BSEP Technical Specification 3.11.2.3.

For the calendar quarter:

Dt 5 15 mrom (3.3-19)

For the calendar year:

Dt 5 30 mrem (3.3-20) where:

Dt = The dose to any organ t from radiciodiines and particulates, mrem The quarterly limits given above represent one-half the annual design objective of Section II.C of Appendix I of 10CFR50. 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 I of 10CFR50 must be filed with the NRC.

ODCM (BSEP) 3-48 Rev. 4

8 g

m TABLE.4.0-1 g -

RADIOLOGICAL ENVilt0181 ENTAL NONITORileC Pit 0CitAN v

Q Exposure Pathmay Sample Sample Point Description, Approximate Sampilng and Analysis '

and/or Sample ID No. Distance,and Direction Collection Frequency Frequency Analysis (a)

DIRECT RADIATION 1 1.1 elles E - Refer to Figure 4.0-1a 0 0 Camma Dose and Figure 4.0-1b 2 1.0 miles ESE O O Camma Dose.

3 0.9 miles SE O O Camma Dose 4 1.1 miles SSE O O c - Dose 5 1.1 alles S 0 0 Casme Dose 6 1.0 alles SSW 0 0 Camma Dose l 7 1.0 miles SW 0 0 Camma Dose 8 1.2 miles W 0 0 Canna Dose-9 1.0 miles WNW 0 0 Camma Dose 10 0.9 alles NW 0 0 c - = Dose 11 0.9 miles NNW 0 0 Camma Dose p 12 1.0 miles N O O Camma Dose N

i 13 1.2 miles tele O O Camma Dose 14 0.5 miles NE O O Camma Dose 15 0.9 alles ENE O O Camma Dose 16 1.0 elles WSW 0 0 Camma Dose 17 1.5 alles ESE O O Camma Dose ,

18 1.7 miles SE O O Camma Dose 77 5.3 elles SSE O O Camma Dose 75 4.5 miles S 0 0 Camma Dose 76 4.8 alles SSW G 0 Camma Dose 22 5.3 miles SW 0 0 Camma Dose 23 4.6 miles WSW 0 0 Camuna Dose 24 3.0 miles W 0 0 Camma Dose 25 8.7 alles MNW 0 . O Camma Dose 26 5.9 miles NW 0 0 Camma Dose 27 5.0 miles telu O O Camma Dose 79 9.5 miles N O O c-a Dose 78 10.0 elles NME 0 0 Camma Dose 30 2.0 miles NE O O Canna Dose 31 2.6 miles ENE O O Canna Dose f 32 5.7 alles E O O Canna Dose l O

e

O O . TABLE 4.0-1 (Cont'd) 9 I

O N Exposure Pathway Sample Sample Point Description, Approximate

  • o Samp1tng and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a) .

DIRECT RADIATION 33 4.3 miles E O O c-a Dose (Cont'd) 34 S.S mile: ENE O O Camma Dose 3 81 10.0 miles WNW (C) 0 0 Camma Dose i 36 9.3 miles E O O Camma Dose

, 37 S.S alles NW 0 0 Camma Dose 38 11.0 miles W 0 0 Camma Dose 39 S.3 miles SW 0 0 Camma Dose 40 6.9 miles WSW 0 0 Camma Dose A1RBORNE

) R.diolodine and 200 1.0 alles SW Vistors Center Continuous sampler W Radiolodine j Particulate 201 0.6 alles E PNAC operation with sample Canister j 202 1.0 elles S Substation - Const. Rd. collected meekly or as 1-131 analysis j , 203 2.3 miles SSW Southport Substation required by dust load- Particulate sampler

i 204 23 miles NNE Sutton Plant - ControI(c) ing, mhichever is more -

Gross beta radlo-frequent. activity analysis j folloming filter

, change (b).

l 1

0 Comma isotopic analysis of composite by l location.

]

WATERBORNE

!' a. Surface 400 0.7 miles NE Intake Canal - Control (c) Composite Sample (d) Monthly n-a Isotopic-Collection - N O Monthly Tritium 1 401 4.9 miles SSW Discharge Canal at Still j Pond i

b. Sediment 500 4.9 alles SSW Discharge - Beach Semlannual Semiannual Camma Isotopic E

1 D B 1,

1

(

I Figure 4.0 - la I

a C >

.N-y i s s ,

g g

la

_s 3 p. 3$s it.

~

/1 k .s '

s . ,, .

-Gj , . ag"* -l, ;.  !

    • os n I .

e$d 8

[ I s

.. ,[

%h 4

  • \ ., , )

'T$

I E

\.k -

, A ;/

' ~ ",  !

I v., ~

Y' 2lfi $

A.,s

  • h E,

,)*' h < l,, .Q'ff,:f 1> ,

% R ,1 v1' t '.

i

.6 .

E f:

/ -

' y 'l ,, !

L l.*. E % jgInl .

  • I i N i

l,' .

f.. '

g ' I

'!, , ..,h \* g I .V r i j ,

I

., h ,

v ., .i r e- .!

.gi C .$,' $ ' i ii DS,.'

, $. ' . ! ' .I ...

,} ') '

\

I' INM ,,

h.

N 4

I

A,, ,m,

  1. I  ! Y

[.

(..

.a I

g 3l t I . I.f Q h]N'.Itj()$Mhf"'- 4-5 Rev. 4

. ODdM (BSEP) 5

e 6.3.2 Inhalation Dose The inhalation dose will be determined at tha. calculational locations for each age class-at risk according to the methods outlined in Section 3.3 of this manual.

'6.3.1- Indestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations'for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as < 1 ares /yr.

6.3.4 ,0ther Uranium Fuel Cycle Sources 4 . .

The dose from other fuel cycle sources will be treated as < 1 mrea/yr.

..v

.6.4 THYROID DOSE l

s* .

The dose to the thyroid will be calculated for each sector as the sum of l

- . inhalation dose and milk ingestion, dose (if existing). The calculational methods will be those identified in Section 3.3 of this manual.

6.4.1 , Dose projections can incorporate planned plant operations such as pot'r'reductica or outages for the projected period.

ODCM (BSEP) 6-3 Rev. 4 s

were the source of the X/Q and D/Q values utilized to show compliance with

'10CFR20 and 10CFR50 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 through 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 .alevated release for both standard distances and special locations.

Values for x/Q, depleted x/Q, and D/Q for releases to special locations are from the standard distance tables. The values used are from the distance '

nearest the special location in the appropriate sector.

Future Operation Computations The NRC "XOQD0Q" Program (Revision 1) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "X0QD0Q" Program will be run with the appropriate physical plant data, appro-priate meteorological information for the standard distances, and special locations of interest without a terrain / recirculation factor. The input to "XOQD0Q" for ground-level releases are presented in Table A-19 and for ODCM (BSEP)

A-2 Rev. 4

(

('

f Table A-1 x/Q Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company - Brunswick

, ' Release Type: Annual Release Mode: Ground Level Variable: Rela'tive Concentration (Sec./ Cubic Meter)

Calculation Points: 3pecial Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes-Number of Observations: 8678 Affected Site .

Ecctor Boundary _Deiry Meat Resident Garden

'NNE~ 2.3E-06 0. 9.4E-07 9.4E-07 9.4E-07 NE 2.9E-06 1.4E-07 0. O. O.

ENE 3.2E-06 0. O. O. O. -

E 3.9E-06 0. 1.5E-06 1.5E-06 0.

ESE' 5.2E-06~ 0. 5.2E-06 1.0E-06 1.0E-06 SE 3.4E-06 0. 3.4E-06 3.4E-06 0.

SSE 7.5E-06 0. 7.5E-06 7.5E-06 7.5E-06 S 3.8E-06 0. O. 1~.6E-06 9.8E-07 -

SSW 2.3E-06 0. 1.2E-06 1.2E-06 1.2E-06 SW 2.5E-06 0. 2.5E-06 2.5E-06 2.5E-06 WSW 1.8L-06 0. 3.8E-07 7.5E-07 7.5E-07 W 1.5E-06 0. O. 1.5E-06 1.5E-06 WNW 1.2E-06 0. O. 1.2E-06 1.2E-06 NW 9.7E-07 0. O. 9.7E-07 9.7E-07 NNW 1.3E-06 0. O. 1.3E-06 1.3E-06 N' 1.4E-06 0. O. 1.4E-06 1.4E-06 i

  • A zero indicates that this point was not calculated.

ODCM (BSEP)- A-5 Rev. 4

- - -~..,n,,-,a w -, ,_g.~ -

Table A-2 Depleted x/Q Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company - Brunswick

' Release Type: Annual Release Mode: Ground Level Variable: Relative Depleted Concentration (Sec./ Cubic Metcr)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident _ Garden NNE 2.0E-06 0. 8.1E-07 8.1E-07 8.1E-07 NE . 2.6E-06 1.0E-07 0. O. O. -

ENE 2.9E-06 0. O. O. O.

E 3.4E 06 0. 1.3E-06 1.3E-06 0.

ESE 4.6E-06 0. 4.6E-06 8.7E-07 8.7E-07 SE 3.1E-06 0. 3.1E-06 3.1E-06 0.

SSE -6.8E-06 0. ~6.8E-06 6.8E-06' 6.8E-06 -

S 3.5E-06 0. O. 1.3E-06 8.1E-07 SSW 2.5E-06 0. 1.0E-06 1.0E-06 1.0E-06 SW 2.4E-06 0. 2.4E-06 2.4E-06 2.4E-06 WSW 1.5E-06 0, 3.2E-07 6.4E-07 6.4E-07 W 1.3E-06 0. O. 1.3E-06 1.3E-06 WNW 1.1E-06 0. O. 1.1E-06 1.1E-06 NW 8.7E-07 0. O. 8.7E-07 8.7E-07 NNW 1.1E-06 0. O. 1.1E-06 1.1E-06 N 1.2E-06 0. O. 1.2E-06 1.2E-06

  • A zero indicates that this point was not calculated.

ODCM (BSEP) A-6 Rev. 4 4

Table A-3

, D/Q Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company . Brunswick _

Release Type: Annual Release Moda: Ground Level Variable: Relative Deposition (Meter **-2)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site .

Sector ,

Boundary Dairy Meat Resident Garden 1.3E-08 0. 4.8E-09 NNE 4.8E-09 4.8E-09 NE 1.9E-08 5.7E-10 0. O. O.

ENE 9.4E-09 0. O. O. O. -

E 8.6E-09 0, 3.1E-09 3.1E-09 . O.

ESE 1.3E-08 0. 1.3E-08 2.2E-09 2.2E-09 SE 8.4E-09 0. 8.4E-09 8.4E-09 0.

SSE 1.5E-08 0. 1.5E-08 1.5E-08 1.5E-08 S 3.3E-09 0. O. 3.2E-09 1.8E-09 -

SSW 7.7E-09 0. 3.0E-09 3.0E-09 3.0E-09 SW 1.1E-08 0. 1.1E-08 1.1E-08 1.1E-08 WSW 7.0E-09 0. 1.3E-09 2.7E-09 2.7E-09 W 5.1E-09 0. O. 5.1E-09 5.1E-09 WNW 3.8E-09 0. O. 3.8E-09 3.8E-09 NW 3.5E-09 0. O. 3.5E-09 3.5E-09 NNW 5.0E-09 0. O. 5.0E-09 5.0E-09 N 6.3E-09 0. O. 6.3E-09 6.3E-09

  • A zero indicates that this point was not calculated.

ODCM (BSEP) A-7 Rev. 4

- ..- uA m b +*% +B= a g Table A-6

  • j . D/Q Values at the Standard Distances for Releases from the Turbine Buildings M Carolina Power & Light Company - Brunswick-3 Release Type: Annual -

Release Mode: Ground Level .

. Variable: Relative Deposition (Meter **-2) .

l l Calculation Points: . Standard j Model: Straight Line (ANNX009) l Application of Terrain Correction Factors: Yes l Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3.62 - 4.42 5.23 6.03 6.84 7.64 NNE 0. 8.6E-08 1.3E-08 4.8E-09 2.8E-09 1.5E-09 9.9E-10 7.7E-10 5.7E-10 4.3E-10 3.3E-10 NE 0. 1.3E-07 1.9E-08 7.6E-09 4.0E-09 2.3E-09 1.6E-09 1.3E-09 8.8E-10 6.8E-10 5.7E-10 I

ENE 0. 5.8E-08 9.4E-09 3.2E-09 1.6E-09 1.1E-09 7.5E-10 5.5E-10 3.9E-10 3.0E-10 2.3E-10

> E 0. 6.2E-08 8. 6E-09 3.1E-09 1.7E-09 1.1E-09 6.9E-10 5.1E-10 3.9E-10 '2.9E-10 2.3E-10

b 0. 7.2E-08 1.3E-08 5.0E-09 2.2E-09 1.2E-09 7.6E-10
ESE 6.0E-10 4.7E-10 3.5E-10 2.6E-10 ,

SE 0. 5.1E-08 8.4E-09 3.3E-09 1.6E-09 8.6E-10 5.6E-10 3.8E-10 3.3E -10 2. 6E-10 2.2E-10 i SSE 0. 8.2E-08 1.5E-08 5.8E-09 3.0E-09 1.8E-09 1.1E-04 6.8E-10 4.9E-10 3.8E-10 2.9E-10 l S 0. 5.6E-08 8.3E-09 3.2E-09 1.8E-09 1.2E-09 7.5E-10 5.4E-10 3.9E-10 2.9E-10 2.3E-10 SSW 0, 5.2E-08 7.7E-09 3.0E-09 1.9E-09 1.1E-09 5.8E-10 4.3E-10 3.8E-10 2.2E-10 1.8E-10 SW 0. 7.5E-08 1.1E-08 4.3E-09 2.4E-09 1.6E-09 8.8E,10 6.4E-10 4.6E-10 3.7E-10 3.1E-10 WSW 0. 6.0E-08 7.0E-09 2.7E-09 1.3E-09 8.8E-10 5.2E-10 4.0E-10 3.3E-10 2.4E-10 2.0E-10.

j W 0. 4.1E-08 5.1E-09 2.0E-09 9.2E-10 5.7E-10 3.6E-10 2.6E-10 2.1E-10 1.7E-10 1.0E-10 i

WNW 0. 3.4E-08 3.8E-09 1.7E-09. 7.3E-10 3.9E-10 3.0E-10 1.9E-10 1.5E-10 1.1E-10 8.4E-11 l NW 0. 2.7E-08 3.5E-09 1.1E-09 6.6E-10 4.7E-10 3.3E-10 2.1E-10 1.7E-10 1.1E-10 9. 6E-11 i NNW 0. 3.6E-08 5.0E-09 1.9E-09 8.5E-10' 5.0E-10 3.8E-10 2.8E-10 2.4E-10 1.6E-10 1.3E-10

) N 0. 4.4E-08 6.3E-09 2.1E-09 1.3E-09 8.0E-10 S.6E-10 4.5E-10 3.5E-10 2.5E-10 2.1E-10

, Number of Nid Observations 8678

Number of ihvalid Observations 82 Number of Calms Lower Level 125 j
  • Number of Calms Upper Level 0

Table A-7 x/Q Values at the Special Locations for Releases From the Reactor Buildings

~ Carolina Power & Light Company - Brunswick Release _ Type: Annual

~ Release Mode: Mixed Mode Variable: Relative Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 .

.Affected Site .

Sector Boundary Dairy Meat Resident Garden NNE 1.0E-07 0. 7.8E-08 7.8E-08 7.8E-08 NE 2.0E-07 4.1E-08 0. O. O.

ENE 6.5E-08 0. O. O. O. -

E 4.8E-08 0. 3.5E-08 3.5E-08 0.

ESE 6.9E-08 0. 6.9E-08 3.9E-08 3.9E-08 SE 4.1E-08 0. 4.1E-08 4.1E-08 0.

SSE 7.6E-08 0. 7.6E-08 7.6E-08 7.6E-08 S 4.5E-08 0. O. 3.5E-08 2.8E-08 ~

SSW 4.7E-08 0. 4.7E-08 4.7E-08 4.7E-08 SW 6.4E-08 0. 6.4E-08 6.4E-08 6.4E-08 WSW 4.1E-08 0. 3.9E-08 4.3E-08 4.3E-08 i

W 3.4E-08 0. O. 3.4E-08 3.4E-08 WNW 1.8E-08 0. O. 1.8E-08 1.8E-08 NW 1.9E-08 0. O. 1.9E-08 1.9E-08 NNW 3.2E-08 0. O. 3.2E-08 3.2E-08 N 4.0E-08 0. O. 4.0E-08 4.0E-08

  • A zero indicates that this point was not calculated.

r ODCM (BSEP) A-11 Rev. 4

\

i i

Table A-8 Depleted x/Q Values at the Special Locations for Releases From the Reactor Buildings Carolina. Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./ Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes ,

Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden NNE 9.1E-08 0. 7.8E-08 7.8E-08 7.8E-08 NE 1.9E-07 3.7E-08 0. O. O.

-ENE 6.1E-08 0. O. O. O.

E ~4.4E-08 0. 3.2E-08 3.2E-08 0.

ESE 6.4E-08 0. ~6.4E-08 3.7E-08 3.7E-08 SE 3.8E-08 0. S.8E-08 3.8E-08 0.

. SSE 7.1E-08 0. 7.1E-08 7.1E-08 7.1E-08 ,

. S 4.2E-08 0. O. 3.3E-08 2.7E-08' SSW 4.3E-08 0. 4.4E-08 4.4E-08 4.4E-08

'SW 6.0E-08 0. 6.0E-08 6.0E-08 6.0E-08

-WSW 3.9E-08 0. 3.8E-08 4.2E-08 4.2E-08 W 3.3E-08 0. O. 3.3E-08 3.3E-08 WNW 1.'7E-08 0. O. 1.7E-08 1.7E-08 NW 1.8E-08 0. O. 1.8E-08 1.8E-08 NNW 3.0E-08' O. O. 3.0E-08 3.0E-08 N 3.7E-08 0. O. 3.7E-08 3.7E-08

  • A zero' indicates that this point was not calculated. .

ODCM (BSEP) A-12 Rev. 4

, S

- -, -c-y- ,,w-%--r-, , . , - -

Table A-9 D/Q Values-at the Special Locations for Releases From the Reactor Buildings

' ~

Carolina Power & Light Company - Brunswick Release Type: Annual

~ Release Mode: Mixed Mode

~ Variable: Relative Deposition (Meter **-2)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes s Number of Observations: 8678 ,

Affected Site Sector Boundary Dairy Meat Resident Garden NNE 2.0E-09 0. 1.1E-09 1.1E-09 1.1E-09 NE 4.3E-09 2.7E-10 0. . O. O.

ENE 1.1E-09 0. O. O. O. -

E 4.6E-10 0. 2.5E-10 2.5E-10 0.

ESE .1.1E-09 0. 1.1E-09 3.3E-10 3.3E-10

'SE 7.6E-10 0. .7.6E-10. 7.6E-10 0.

SSE '1.2E-09 0. 1.2E-09 1.2E-09 1.2E-09 S 5.7E O. O. 3.4E-10 2.3E-10 --

SSW 7.7E-10 0. 5.2E-10 5.2E-10 5.2E-10 SW 1.2E O. 1.2E-09 1.2E-09 1.2E-09 WSW 8.9E-10 0. 4'.1E 5.9E-10 5.9E-10 W 6.6E-10 0. O. 6.6E-10 6.6E-10 L

. WNW. 2.7E-10 0. O. 2.7E-10 2.7E-10 NW 3.1E-10 0. O. 3.1E-10 3.1E-10 NNW 4.0E-10 0. -0. 4.0E-10 4.0E-10 N 5.6E-10 0. O. 5.6E-10 5.6E-10

  • A zero indicates that this point was not calculated.

ODCM (BSEP) A-13 Rev. 4 i

,- - ., , . _ . . , . - , - , . , . , - _ _ _ . . . . . . , _ _ . - . . , , - . . _ . _ . . . . . , - ..,,m.

g Table A-12 o

[ -

D/Q Values at the Standard Distances for' Releases' free the Reactor Buildings q Carolina Power & Light Company - Brunswick Reiease Type: Annual Release Mode: Mixed Mode Variable: Relative Deposition (Meter **-2) l

~

Calculation Points: Standard .

Model: Straight Line (ANNX009) j Application of Terrain Correction Factors: Yes q Number of Observations: 8678

! Base Distance in Miles / Kilometers Design l Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 l Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 6.84 7. 64 1

{ NNE 0. 1.1E-08 2.0E-09 1.1E-09 7.2E-10 5.0E-10 3.5E-10 2.8E-10 2.2E-10 1.7E-10 1.5E-10 i

NE 0. 1.1E-08 4.3E-09 2.3E-09 1.5E-09 9.8E-10 7.2E-10 5.3E-10 4.2E-10 3.3E-10 2.7E 4 ENE 0. 1.9E-08 1.1E-09 5.8E-10 3.9E-10 2.8E-10 2.2E-10 1.7E-10 1.4E-10 1.1E-10 9.7E-11

[ E 0. 2.1E-09 4.6E-10 2.5E-10 1. 6E-10 1.2E-10 9.0E-11 7.5E-11 5.7E-11 4.8E-11 3.8E-11

ESE 0. 1.3E-09 1.1E-09 5.4E-10 3.3E-10 2.4E-10 1.9E-10 1.3E-10 1.1E-10 8.3E-11 6.9E-11 i SE 0. 1.3E-09 7. 6E-10 4.9E-10 2.8E-10 1.8E-10 1.3E-10 1.1E-10 8.9E-11 6.7E-11 6.1E-11 SSE 0. 2.4E-09 1.2E-09 6.7E-10 4.1E-10 2.8E-10 2.1E-10 1.6E-10 1.3E-10 1.0E-10 8.2E-11 S 0. 3. 6E-09 5.7E-10 3.4E-10 2.3E-10 1.7E-10 1.4E-10 1.0E-10 8.2E-11 6.5E-11 5.5E-11 ,

j SSW 0. 8.0E-09 7.7E-10 5.2E-10 3.5E-10 2.6E-10 1.8E-10 1.5E 1.1E-10. 9.3E-11 7.4E-11 l SW 0. 3.4E-09 1.2E-09 7.3E-10 4.5E-10 3.3E-10 2.3E-10 1.7E-10 1.4E-10 1.2E-10 9.4E-11 l WSW 0. 1.8E-09 8.9E-10 5.9E-10 4.1E-10 2.9E-10 2.1E-10 1.7E-10 1.5E-10 1.2E-10 1.0E-10 l W 0. 7.9E-10 6.6E-10 4.3E-10 2.9E-10 1.9E-10 1.5E-10 1.2E-10 8. 6E-11 7.7E-11 6.4E-11 l

I WNW 0, 5.8E-10 2.7E-10 2.0E-10 1.7E-10 1.3E-10 8.8E-11 6.8E-11 5.5E-11 4.2E-11 3.3E-11

NW 0. 5.4E-10 3.1E-10 2.3E-10 1.5E-10 1.1E-10 8.9E-11 6.9E-11 5.4E-11 4.4E-11 3.9E-11 NNW 0, 5.3E-09 4.0E-10 2.2E 1. 6E-10 1.0E-in 7.6E-11 6.1E-11 5.0E-11 4.2E-11 3.4E-11 N 0. 8.7E-09 5.6E-10 2.8E-10 2.1E-10 1.6E-10 1.4E-10 1.1E-10 8.1E-11 6.4E-11 5.7E-11 i i

, Number of Valid Observations 8678

  • l $ Number of Invalid Observations 82 Number of Calms Lower Level 12
  1. Number of Calms Upper Level 0

x . ..

t Table A-13 '

~.

.r x/Q Values at the Special Locations for Releases From the Stack o

' . Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Concentration Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes

, Number of Observations: 8678 Accounting for Stack Center Offset .

Affected Site.

4 Sector Boundary Dairy Meat Resident Garden NNE 1.3E-08 0. 2.3E-08 2.3E-08 2.3E-08 -

-NE- 2.5E-08 2.4E-08 0. O. O.

ENE 7.2E-09 0. O. O. O.

E 3.6E-09 0. 7.6E-09 7.6E-09 0.

t ESE 7.7E-09 0. 7.7E-09 1.3E-08 1.3E-08 SE 8.7E-09 0. 8.7E-09 8.7E-09 0. ~

, SSE 1.2E-08 0. 1.2E-08 1.2E-08 1.2E-08 S- 4.7E-09 0. O. 8.5E-09 9.6E-09 SSW 6.0E-09 0. 1.4E-08 1.4E-08 1.4E-08 SW 1.3E-08 0. 1.3E-08 1.3E-08 1.3E-08 WSW 9.0E-09 0. 1.8E-08 1.6E-08 1.6E-08 W. 1.0E-08 0. O. 1.0E-08 1.0E-08 WNW' 5.3E-09 0. O. 5.3E-09 5.3E-09 NW- 6.5E-09 0. O. 6.5E-09 6.5E-09 NNW 4.2E-09 0. O. 4.2E-09 4.2E-09 N 4.5E-09 0. O. 4.5E-09 4.5E-09 1

  • kzeroindicatesthatthispointwasnotcalculated.

l

- 0DCM (BSEP) A-17 Rev. 4  !

l 1

Table A-14 Depleted x/Q Values at the Special Locations for Releases From the Stack

~ Car'olina Power & Light Company - Brunswick Release Type: Annual

~ Release Mode: Elevated Variable: Relative Depleted Concentrations Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset .

Affected Site Sector - Boundary Dairy Meat Resident Garden NNE 1.2E-08 0. 2.2E-08 2.2E-08 2.2E-08 -

NE 2.5E-08 2.3E-08 0. O. O.

ENE 7.IE-09 0. O. O. O.

E 3.6E-09 0. 7.6E-09 7.6E-09 0.

ESE 7.5E-09 0. 7.5E-09 1.2E-08 1.2E-08 SE 8.7E-09 0. 8.7E-09 8.7E-09 0.

SSE 1.2E-08 0. 1.2E-08 1.2E-08 1.2E-08 S 4.6E-09 0. O. 8.5E-09 9.6E-09 SSW 6.0E-09 0. 1.4E-08 1.4E-08 1.4E-08 SW 1.3E-08 0. 1.3E-08 1.3E-08 1.3E-08 WSW 9.0E-09 0. 9.2E-08 1.5E-08 1.5E-08 W 1.0E-08 0. O. 1.0E-08 1.0E-08 WNW 5.1E-09 0. O. 5.1E-09 5.1E-09 NW 6.5E-09 0. O. 6.5E-09 6.5E-09 l

NNW 4.1E-09 0. O. 4.1E-09 4.1E-09 N 4.5E-09 0. O. 4.5E-09 4.5E-09

  • A zero indicates that this point was not calculated.

ODCM (BSEP) A-18 Rev. 4 i

i

. . ~ - . . . .

Table A-15

' D/Q Values at the Special Locations for Releases from the Stack

~

. Carolina Power & Light Company - Brunswick -

Release Type: Annual

~ Release Mode: Elevated Variable: . Relative Deposition (Meter **-2)

Calculation .:.,ints: Special

, Model: - Straighc Line

- Application of Terrain Correction Factors: Yes Number of Observationt.: 8678 Accounting for Stack Center Offset -

~

Affected Site Sector Boundary Dairy Meat Resident Garden NNE 6.0E-10 0. 5.3E-10 5.3E-10 5.3E-10 -

NE 1.4E-09 2.2E-10 0. O. O.

ENE. 3.2E-10 0. O. O. O.

E 1.6E-10 0. 1.3E-10 1.3E-10 0.

ESE '4.1E-10 0. 4.1E-10 2.0E-10 2.0E-10 SE 4.2E-10 0. 4.2E-10 4.2E-10 0. ~

.SSE . 5.4E-10 0. 5.4E-10 5.4E-10 5.4E-10 S 2.0E-10 0. O. 1.9E-10 1.4E-10 SSW 2.7E-10 0. 2.9E-10 2.9E-10 2.9E-10 SW 5.6E-10 0. 5.6E-10 5.6E-10 5.6E-10 3.8E-10 0. 3.0E-10 3.6E-10 3.6E-10 WSW W 3.9E 0. O. 3.9E-10 3.9E-10 WNW 1.7E-10 0. O. 1.7E-10 1.7E-10 NW 2.0E-10 0. O. 2.0E-10 2.0E-10 NNW 1.5E-10 0. O. 1.5E-10 l'. 5E-10 N 1.9E-10 0. O. 1.9E-10 1.9E-10

'* A zero indicates that this point was not calculated.

- ODCM (BSEP) A-19 Rev. 4 a

w 9?- *-y--t 9'-twM--w-7 ev 1WY =P **M vr M $ '9 +W*--WM'WT+'e+w-W"w"(PW"g'TM d y TW -

W'- e- e- V --r- '-9'r* -

7'

c) Table ic18 R

. D/Q Values. at the Standard Distances' for Releases from the Stack co

' --k) Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: . . Relative Deposition (Meter **-2)

[

Calculation Points: Standard Model: Straight Line (ANNX009)-

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75- 2.25. 2.75 3.25 3.75 4.25- 4.75 Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 6.84 7. 64 NNE 0. 1.2E-09 6.0E-10 5.3E-10 4.3E-10 3.4E-10 2.5E-10 2.0E-10 1. 6E-10 1.4E-10 -1.2E-10 NE 0. 1.4E-09 1.4E-09 1.1E-09 8.8E-10 6.7E-10 5.2E-10 3.9E-10 3.1E-10 2. 6E-10 2.2E-10 ENE 0. 1.8E-09 3.2E-10 3.0E-10 2.5E-10 2.0E-10 1. 6E-10 1.3E-10 .1.1E-10 9.3E-11 8.1E [ E 0. 2.2E-10 1. 6E-10 1.3E-10 1.0E-10 8.7E-11 6.6E-11 5.7E-11 4.4E-11 3.7E-11 3.1E-11 N

ESE 0. 1.9E-10 4.1E-10 2.7E-10 2.0E-10 1.7E-10 1.4E-10 1.1E-10 8.2E-11 6.6E-11 5.6E SE 0. 3.2E-10 4.2E-10 3.1E-10 2.1E-10 1.4E-10 1.1E-10 8.7E-11 7.3E-11 5.8E-11 5.3E-11 SSE 0. 5.8E-10 5.4E-10 3.9E-10 2.8E-10 2.1E-10 1.7E-10 1.4E-10 1.1E-10 8.5E-11' 7.1E-11 S 0. 5.4E-10 2.0E-10 1.9E-10 1.4E-10 1.1E-10 1.1E-10 8.3E 6. 6E-11 5.5E-11 4. 6E-11 SSW 0. 1.1E-09 2.7E-10 2.9E-10 2.4E-10 1.9E-10 1.4E-10 1.3E-10 9.5E-11 7.9E-11 6.5E-11 SW 0. 7. 6E-10 5.6E-10 4.3E-10 3.1E-10 2.4E-10 1.8E-10 1.4E-10 1.1E-10 9.5E-11 8.0E-11 WSW 0. 4.1E-10 3.8E-10 3. 6E-10 3.0E-10 2.3E-10 1.7E-10 1.4E-10 1.3E-10 1.0E-10 8. 6E-11 W 0. 2.8E-10 3.9E-10 3.0E-10 2.1E-10 1.5E-10 1.3E-10 1.0E-10 7.8E-11 6.9E-11 5.9E-11 WNW 0. 2.4E-10 1.7E-10 1.5E-10 1.4E-10 1.0E-10 7.4E-11 5.8E-11 4.8E-11 3.7E-11 2.9E-11 NW 0. 2. 6E-10 2.0E-10 1.7E-10 1.2E-10 8.8E-11 7.5E-11 6.0E-11 4.8E-11 4.0E-11 3. 6E-11 NNW 0. 7.2E-10 1.5E-10 1.3E-10 1.0E 7.3E-11 5.4E-11 4.3E-11 3.6E-11 3.2E-11 2. 6E-11 N 0. 8.1E-10 1.9E-10 1.5E-10 1.3E-10 1.1E-10 9.9E-11 7.9E-11 6.0E-11 4.9E-11 4.4E-11 po Number of Valid Observations 8678

  • O Number of Invalid Observations 82 Number of Calms Lower Level 0 Number of Calms Upper Level 0

APPENDIX E RADI0 ACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS I. Liquid Effluent Monitoring Instruments A. . Liquid Radwaste Radioactivity Monitor 2-D12-RM-K604 B. Liquid Radwasta Effluent Flow Measurement 2-G16-FIT-N057 Device 2-G16-FIT-N058 l C. Main Service Water Effluent Radioactivity 1(2)-D12-RM-K605 Monitor D. Stabilization Pond Effluent Composite 2-DST-XE-5027 Sampler E. . Stabilization Pond Effluent Flow 2-DST-FIT-5026 Measurement Device .

F. Condensate Storage Tank Level Indicating 1(2)-CO-LIT-1160 Device ,

/

ODCM_(BSEP) E-1 Rev. 4 1

5 .~ Main Condenser Off-Gas Treatment System (A0G) Monitor a.. Noble Gas Activity Monitor 1(2)-A0G-RM-103 l

6. Main Condenser Off-Gas Treatment Sys. tem Explosive Gas Monitoring System
a. Recombiner Train A

~

1. First Hydrogen Monitor 1(2)-0G-AIT-4264 l
2. Second Hydrogen Moniter 1(2)-0G-AIT-4285' -l
b. Recombiner Train B

~

1. First Hydrogen Monitor 1(2),-0G-AIT-4324 l

. 2. Second Hydrogen Monitor 1(2)-0G-AIT-4325 *

7. Hot Shop Ventilation Monitoring System .
a. Iodine Sampler Cartridge 2-VA-AX-5092 .
b. Particulate Sampler Filter 2-VA-AX-5093 9

+

ODCM (BSEP) E-3 Rev. 4

- -~ - - -- - - - - - - - - -- - ~- - -- - --- -

' fg. ; , < ~i .

.[, s .

[.

  • I

'c -

l_s ,.w N,fl- <

% ~

-^ ATTACHMENT 4.

t

~ 4 i s

~

Envirornental~ Monitoring: Program a

r cJanuary 1 to June 30, 1985

- -e ,

g v ENCLOSURE '1: . : Milk 'and Vegetable Sample Locations.

- ENCLOSURE.2: '. Land Us'e Census-A 6 5

? .{- - ,

j-

..r' 7

b l ' \

- d

- ~

c 6

'I

  • 8-s c

'O 1

J i

, sa -

yv.

- '"- -.4,,-,_,wwr,-,,,w,y,--.,...%,. .mm,-, ---w,m-c,,- ,,w,,,p,,wr,-mm,,,,.-,-,,,--,-1, ,4w,~ww%,-..wir, , - , ey rwew-.e.,--.y,wm

b. -

~

. . . =.i:. 8 ^

]

a+_ , .

l

,;u . .

E- .

.  : . v-?

ENCLOSURE 'l-

~

q, Milk'and'Vegetab'leSomplI[ Locations

~

r 16 Id _.

~

No milk sample locations were available'during . this time ~ period.- .

.'e ~ --Vegetable sample : locations.were unchanged during- this time period. .

s .

+-

1 T,

4 4 .

M A

(

)h I

Y '

J M

f f

5 m

a

,'Y-

'..(

,6.'.. , .

m.'. -

}.,-

._-_, _. ',2.

'-C,-

s g

~ - 4

c,

'1 s

.: -g- ENCLOSURE 2 LL=  ;-

w y.[ , Land Use Census'.

4  %

~ No new locations -were identifie[i that- are reportable .in the Semiannual:

'-< Radioactive Effluent Release Report as per Technical Specification' 3.12.2.a'

' jcftd b - .

> f.,

-w b

v e

L c-s EPc.,

9 1

, e-

?,

~ ' -

v T

4 a

S _

  • %C

r

~

ATTACHMENT- '5 '

4

, Inoperable Effluent Instrumentation

. January 1 to June 30, 1985 ENCLOSURE l': Radioactive L'iquid Efflu~ent Monitoring Instrumentation

.. ENCIDSURE 2i : Radioactive Gaseous Effluent Monitoring Instrumentation

- ENCLOSURE'3i Liquid Hold-Up Tank 4

Y

. i i

h '

'e

- , 41 , . _.

.g ,

[: ~.!b

ENCLOSURE-1

- e Y

~

~ Radioactive Liquid Effluent Monitoring ' Instrumentation q, '

- w. . - c, JNo1radwaste liquid ' effluent instrumentation was inoperable for greater than o.30-day period during January'1, 1985,.tofJune 30, 1985.

~

4.

,r .

I i t 9

gP .

'r 1.

', ' ?

4 4-i

k: --

i :,

v.

  • ww f

I

A ENCLOSURE 2

,5 e

p ^ Radioactive Gaseous . Effluent Monitoring Instrumentation '

f ,

- Unit 2 main condenser off-gas treatment system explosive, gas monitors, .2-0G-AIT-4284,.2-0G-AIT-4285,.2-0G-AIT-4324, and 2-0G-AIT-4325 were inoperable for greater, than La 30-day period during January 1,1985,' to' June 30, 1985.

..Due L to ~ design problems, these monitors were.not returned.to service within

- 30 days.-

4 k

)

4 0

J N

i: _ .-

m-ENCLOSURE 3 Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 Ci-limit between the dates of January 1, 1985, to June 30, 1985.

I

.O

o

' ) r ATTACHMENT 6 1

Major. Modifications to Radioactive Waste Treatment January 1 to June 30, 1985 i

' Discussion .of' major modifications to Radioactive , Waste Treatment Systems, if Ltny, will be submitted with Final Safety Analysis Report update as allowed by footnote 7 to Technical Specification 6.15.

1 l-t t

T t ,

i f-ATTACHMENT 7~

Meteorological _ Data Brunswick Steam Electric Plant January -- June,1985

- As required by Technical' Specification 6.9.1.10.a, the annual summary of meteorological data-will be reported within 90 days af ter January 1 of each year and is not included in this report. .

+

.k' ls

[.

v ATTACHMENT 8 Po'_ential Dose Assessment Brunswick Steam Electric Plant-January - June, 1985

~

As required ~ by Technica1 Specification .6.9.1.10.b, an assessment of radiation

, doses: due.to the radioactive liquid and gaseous effluents released during the calendar year will-be reported within 90 days af ter January 1.of each year Ond~is not included in this report.

t

+

)

1-

. 9

-__ . . . _ . . . , _ _ . _ . . . _ , _ . _ _ . _ , _ . - - - - _ . . . , . . . . _ . _ _ _ _ _ _ - . - , , _ _ _ . _ . _ . . _. _ . .. -