ML20078H534

Offsite Dose Calculation Manual,Rev 2

ML20078H534
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/30/1983
From:	Stewart J DUKE POWER CO.
To:
Shared Package
ML20078H531	List: ML20078H528 ML20078H534
References
PROC-830930, NUDOCS 8310140207
Download: ML20078H534 (6)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

O September 30, 1983

SUBJECT:

Offsite Dose Calculation Manual - Revision 2 The General Office Radwaste Engineering staff is transmitting to you this date, Revision 2 of the Offsite Dose Calculation Manual. Please update your copy No.

.1. , and discard affected pages.

REMOSIE THESE PAGES INSERT THESE PAGES Page B-6 Page B-6 Revision 2 Page B-11 Page B-11 Revision 2 Page B-15 Page B-15 Revision 2 Table B4.0-1 Table B4.0-1 Revision 2 Table B4.0-2 Table B4.0-2 Revision 2 NOTE: As this letter contains "L0EP" information, please insert this letter in front of the April 15, 1983 letter.

-v'h3 Approval Date: J/[ff Approval Date:

Effective Date: 10/07/93 Effective Date: 10/07/83

$ !hhY M. D. McIntosh, Manager M. L. Bi ch System Radwaste Engineer McGuire Nuclear Station If ycu have any questions concerning Revision 2, please call Jim Stewart at (704) 373-5444.

arne /71. S A<w S /

~

James M. Stewart, Jr.

Associate Health Physicist WC-2389 JMS/dkt e

0 h P p

e O

's 2 s

I (Lg + 1.1 Mg ) [(X/Q)Qg ] < 3000 mrem /yr i

where the terms are defined below.

B2.2.2 Radioiodines, Particulates, and Others s

IPg [W Qg ] < 1500 mrem /yr i

where:

K. = The total body dose factor due to gamma emissions for each identified

• noble gas radionuclide, in mrem /yr per pCi/m3from Table 1.2-1.

L.

= The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3 from Table 1.2-1.

M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table 1.2-1 (unit conver-sion constant of 1.1 mres/ mrad converts air dose to skin dose).

s' P. = The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr per pCi/m3 and for the food and ground plane' pathways in m2 .(mrem /yr) per pCi/sec from Table 1.2-2. The dose factors are based on the critical individual organ and most restrictive age group (child or infant).

s

= The release rate of radionuclides, i, in gaseous effluent from all Q*. release points at the site, in pCi/sec.

X/Q = 7.2E-5 sec/m3 . The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary.

W = The highest es3culated annual average dispersion parameter for estimating the dose to an individual at the controlling location:

W = 1.2E-5 sec/m 3 , for the inhalation pathway. The location is the unrestricted area in the ESE sector (nearest residence).

W = 3.0E-8 meter 2, for the food and ground plane pathways. The location is the unrestricted area boundary in the E sector (nearest vegetable garden).

s Qg =kCf+k2 ig = 4.72E+2Cg f where:

/' = the concentration of radionuclide, i, in undiluted gaaeous effluent,

(__ C.

• in pCi/ml.

B-6 Revision 2 10/7/83

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

B3.2 GAS MONITORS

(

k./ The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133:

K(X/Q)Q1 (See section B2.2.1) s < 500 Q.1

= 4.72E+2 C.f 1 (See Section B2.2.2)

C.1 < 5.00E+01/f where:

Cg = the gross activity in undiluted effluent, in pCi/ml f = the flow from the tank or building and varies for various release sources, in efa K = from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m3 X/Q = 7.2E-5 sec/ma , as defined in Section B2.2.2.

As stated in Section B2.2, the unit vent is the release point for the contain-ment purge ventilation system, the coutainment air release and addition system, the condenser air ejector, and auxiliary building ventilation. Since all of these releases are through the unit vent, the radiation monitor on the unit vent may be used to assure that station release limits are act exceeded. .

For release from the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows:

C. < 5.00E+01/f = 6.10E-04 pCi/ml 1

where:

f = 54,000 cfm (auxiliary building ventilation) + 28,000 cfm (containment purge)

= 82,000 cfm For release from the continament air release and addition system, the waste gas decay tanks, the condenser air ejectors, and the auxiliary building ventilation system, a typical radiation monitor setpoint may be calculated as follows:

Cf < 5.00E+01/f = 9.26E-04 pCi/ml where:

f = 54,000 cfm (auxiliary building ventilation)

{

i

(

B-11 Revision 2 10/7/83

C *

• average e acentration of Cs-137 in undiluted effluent, in pCi/ml,

,-, Cs-137 during the time period considered.

V; 0.59 = The ratio of the adult total body ingestion dose factors for Cs-134 and Cs-137 or 7.14E-05 + 1.21E-04 = 0.59 B4.3.2 Gaseous Effluents Meteorological data is provided in Tables B4.0-1 and B4.0-2.

B4.3.2.1 Noble Gases For dose estimates, simplified dose estimates using the assumptions in B4.2.2.1 and source terms in the FSAR are presented below. Gace operational source term data is availabic, this information shall be used to revise these calculations, if necessary. These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 contributes 45% of the dose.

s DY = 8.06E-10 [Q]Xe-133  %

(2.22)

Dp = 2.40E-09 [Q]Xe-133 ( * ) r where:

X/Q = 7.2E-05 sec/m a , as defined in Section B2.2.2 (g) 8.06E-10 = (3.17E-8)(353)-(X/Q), derived from equation presented in Section 3.1.2.1.

q 2.40E-09 = (3.17E-08) (1050) (X/Q), derived from equation presented in Section 3.1.2.1.

[Q]Xe-133 = the total Xenon-133 activity released in pCi 2.22 = factor derived from the assumption that 45% of the dose is contributed by Xe-133.

B4.3.2.2 Radioiodines, Particulates, and Other Radionuclides with T 1/2 > 8 days For dose esticates, simplified dose estimates using the assumptions in B4.2.2.2 and source terms it the FSAR are presented below. Once operational source term data is available, this information shall be used to revise these calculations, if necessary. These calculations further assume that the annual average dispersion / deposition parameter is used and that 95% of the dose is from Iodine-131 concentrated in goat's milk. The simplified dose estimate to the thyroid of an infant is:

D = 2.00E+04 w (Q)I-131 (1.05) where:

(\. w = 2.3E-09 = D/Q for food and ground plane pathway, in m _2 from Table B4.0-2 for the location of the nearest real goat (SSE sector at 1.5 miles).

B-15 Revision 2 10/7/83

O O O TABLE B4.0-1 <

(1 of 1)

MCGUIRE NUCLEAR STATION DISPERSION PARAMETER (X/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR Distance to the control location, in miles Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 S 1.3 E-5 3.4 E-6 1.4 E-6 7.4 E-7 4.7 E-7 3.3 E-7 2.4 E-7 1.9 E-7 1.5 E-7 1.3 E-7 SSW 1.6 E-5 4.2 E-6 1.7 E-6 9.0 E-7 5.7 E-7 4.0 E-7 3.0 E-7 2.3 E-7 1.9 E-7 1.5 E-7 SW 1.6 E-5 4.2 E-6 1.6 E-6 8.8 E-7 5.6 E-7 3.9 E-7 2.9 E-7 2.2 E-7 1.8 E-7 1.5 E-7 WSW 1.0 E-5 2.8 E-6 1.1 E-6 6.0 E-7 3.7 E-7 2.6 E-7 1.9 E-7 1.5 E-7 1.2 E-7 9.9 E-8 W 4.5 E-6 1.2 E-6 4.7 E-7 2.6 E-7 1.6 E-7 1.1 E-7 8.5 E-8 6.7 E-8 5.4 E-8 4.5 E-8 bH74 4.0 E-6 1.1 E-6 4.2 E-7 2.3 E-7 1.4 E-7 1.0 E-7 7.4 E-8 5.8 E-8 4.6 E-8 3.8 E-8 NW 9.0 E-6 2.4 E-6 9.7 E-7 5.3 E-7 3.3 E-7 2.3 E-7 1.7 E-7 1.4 E-7 1.1 E-7 9.2 E-8 NNW 1.4 E-5 3.6 E-6 1.5 E-6 8.1 E-7 5.2 E-7 3.7 E-7 2.8 E-7 2.2 E-7 1.8 E-7 1.5 E-7 5.8 E-5 1.5 E-5 6.1 E-6 3.4 E-6 2.2 E-6 1.6 E-6 1.2 E-6' 9.6 E-7 7.8 E-7 6.6 E-7 N

NNE' 7.2 E-5 1.8 E-5 7.5 E-6 4.2 E-6 2.8 E-6 2.0 E-6 1.5 E-6 1.2 E-6 9.7 E-7 8.1 E-7 l

NE 4.0 E-5 1.0 E-5 4.2 E-6 2.3 E-6 1.5 E-6 1.1 E-6 8.2 E-7 6.5 E-7 5.3 E-7 4.5 E-7

! ENE 2.3 E-5 5.9 E-6 2.5 E-6 1.4 E-6 9.0 E-7 6.4 E-7 4.8 E-7 3.8 E-7 3.1 E-7 2.6 E-7 E 1.8 E-5 4.6 E-6 1.9 E-6 1.1 E-6 6.9 E-7 4.9 E-7 3.7 E-? 2.9 E-7 2.4 ,E-7 2.0 E-7 1.2 E-5 3.2 E-6 1.3 E-6 7.4 E-7 4.8 E-7 3.4 E-7 2.5 E-7 2.0 E-7 1.6 E-7 1.4 E-7 ESE SE 1.1 E-5 2.9 E-6 1.2 E-6 6.6 E-7 4.2 E-7 3.0 E-7 2.2 E-7 1.8 E-7 1.4 E-7 1.2 E-7 SSE 7.7 E-6 2.1 E-6 8.5 E-7 4.6 E-7 3.0 E-7 2.1 E-7 1.5 E-7 1.2 E-7 9.9 E-8 8.2 E-8 Revision 2 10/7/83

O O O TABLE B4.0-2 ',

(1 of 1)

MCGUIRE NUCLEAR STATION DEPOSITION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR l

l l

Distance to the control location, in miles Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 S 4.9 E-8 1.2 E-8 4.3 E-9 2.1 E-9 1.3 E-9 8.2 E-10 5.8 E-10 4.3 E-10 3.3 E-10 2.6 E-10 SSW 7.1 E-8 1.7 E-8 6.2 E-9 3.1 E-9 1.8 E-9 1.2 E-9 8.3 E-10 6.2 E-10 4.8 E-10 3.8 E-10 SW 9.4 E-8 2.3 E-8 8.2 E-9 4.1 E-9 2.4 E-9 1.6 E-9 1.1 E-9 8.2 E-10 6.3 E-10 5.0 E-10 WS' 5.3 E-8 1.3 E-8 4.7 E-9 2.3 E-9 1.4 E-9 8.9 E-10 6.3 E-10 4.7 E-10 3.6 E-10 2.9 E-10 W 1.3 E-8 3.1 E-9 1.1 E-9 5.6 E-10 3.3 E-10 2.1 E-10 1.5 E-10 1.1 E-10 8.6 E-11 6.9 E-11 WNW 1.1 E-8 2.7 E-9 9.8 E-10 4.9 E-10 2.9 E-10 1.9 E-10 1.3 E-10 9.8 E-11 7.6 E-11 6.0 E-11 NW 1.9 E-S 4.7 E-9 1.7 E-9 8.4 E-10 5.0 E-10 3.2 E-10 2.3 E-10 1.7 E-10 1.3 E-10 1.0 E-10 NNW 2.3 E-8 5.7 E-9 2.1 E-9 1.0 E-9 6.0 E-10 3.9 E-10 2.8 E-10 2.0 E-10 1.6 E-10 1.3 E-10 N 9.3 E-8 2.3 E-8 8.1 E-9 4.0 E-9 2.4 E-9 1.6 E-9 1.1 E-9 8.1 E-10 6.3 E-10 5.0 E-10 NNE 1.3 E-7 3.2 E-8 1.1 E-8 5.7 E-9 3.3 E-9 2.2 E-9 1.5 E-9 1.1 E-9 8.8 E-10 7.0 E-10 NE 7.1 E-8 1.7 E-8 6.2 E-9 3.1 E-9 1.8 E-9 1.2 E-9 8.3 E-10 6.2 E-10 4.8 E-10 3.8 E-10 ENE 3.8 E-8 9.3 E-9 3.3 E-9 1.7 E-9 9.8 E-10 6.4 E-10 4.5 E-10 3.3 E-10 2.6 E-10 2.0 E-10 E 3.0 E-8 7.3 E-9 2.6 E-9 1.3 E-9 7.6 E-10 5.0 E-10 3.5 E-10 2.6 E-10 2.0 E-10 1.6 E-10 ESE 3.0 E-8 7.4 E-9 2.7 E-9 1.3 E-9' 7.8 E-10.. 541.E-10 3.6 E-10 2.6 E-10 2.0 E-10 1.6 E-10 st * ,

SE 3.1 E-8 7.6 E-9 2.7 E-9 1.3 E-9 7.9 E-10. 35'.2 E-10 3.7 E-10 2.7 E-10 2.1 E-10 1.7 E-10 SSE 2.7 E-8 6.5 E-9 2.3 E-9 1.2 E-9 6.8 E-1$ 4..'5,E-10 3.1 E-10 2.3 E-10 1.8 E-10 1.4 E-10

. . ;a;;:

Revision 2 10/7/83

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