ML20099J697

Rev 5 to Offsite Dose Calculation Manual

ML20099J697
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/10/1984
From:	Birch M, Hampton J, Mcintosh M DUKE POWER CO.
To:
Shared Package
ML20099J651	List: ML20099J648 ML20099J680 ML20099J697 ML20136F854 ML20137X578
References
PROC-840910-01, NUDOCS 8503200041
Download: ML20099J697 (9)

Text

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l ATTACIDIENT IV REVISION 5 TO THE ODCM 8503200041 850301 PDR ADOCK 05000369 R PDR

September 7, 1984

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SUBJECT:

OFFSITE DOES CALCULATION h!Ah11AL - REVISION 5 The General Office Radwaste Engineering Staff is transmitting to you this date, Revision 5 of the Offsite Dose Calculation Manual. As this revision affects the manual's generic section, the approval of each station manager has been obtained. Please update your copy no. a9 , and discard affected pages.

REMOVE THESE PAGES INSERT THESE PAGES Page 1-1 Page 1-1 Revision 5 Page 1-2 Page 1-2 Revision 5 Table 1.2-2 Revision 1 Table 1,2-2 Revision 5 Page 3-2* Page 3-2 Revision 5 Page 3-3 Page 3-3 Revision 5 Page 3-9 Page 3-9 Revision 5 Table 3.1-3 (3 of 3) Table 3.1-3 (3 of 3) Revision 5 hUfE: As this letter contains "LOEP" infonnation, please insert this letter in front of the August 7,1984 letter.

Approval Date: // gzj//f/7 Approval Date: 3 - Ef-hd CN Effective Date: 9-10-8T Effective Date: 9-10-84 O

hfary L. irch Y A

[ .

l b W. Hampton, blanager System Engineer Catawba Nuclear Station Radwaste Engineering Approval Date: J M Approval Date: 8 fdi Effective Date: 9-10-84 Effective Date: 9-10-84 hl. D. McIntosh, blanager e - (AJCJM bl. S. Tuckman, blanager hicGuire Nuclear Station Oconee Nuclear Station If you have any questions concerning Revision 5, please call Jim Stewart at (70 373-5444.

a nw PM SBf James M. Stewart, Jr.

Associate Health Physicist b Radwaste Engineering d ht-2339 JMS/ncm

1 l

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f 1.0 RELEASE RATE CALCULATIONS

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The release rate calculations presented in the following sections are site l release limits. Sites containing two or more units shall administratively  !

control releases to assure that the release rate calculations limit releases as stated in the Technical Specifications. Administrative controls could limit the number of releases occurring at one '.ime and/or apportion the release rate between the units. l l

1.1 LIQUID EFFLUENTS To comply with Technical Specifications and to assure that the concentration of radioactive liquid effluents from the site to the unrestricted area is limited to the concentrations of 10CFR20, Appendix B, Table II, Column 2, the following release rate calculation shall be performed:

C f i F + (o I i )

! i=1 MPC.

1 where:

C.

• = The concentration of radionuclide, 'i', in undiluted liquid effluent, in pCi/ml.

f-~ MPC = the concentration of radionuclide, 'i', from 10CFR20, Appendix B, Table (j II, Column 2, in pCi/ml.

f = the undiluted effluent flow from the tank, in gpm.

F = the dilution flow from the site discharge structure to unrestricted area receiving waters, in gpm.

a = recirculation factor at equilibrium; this factor accounts for the fraction of discharged water reused by the station; this factor is one for stations on rivers or lakes where discharged water cannot be reused, and varies for sites where water is recirculated and is specified in the appropriate Appendix.

1.2 GASEOUS EFFLUENTS In order to comply with the Technical Specifications and to assure that the dose rate, at any time, in the unrestricted area due to radioactive materials released in gaseous effluents from the site is limited to 1500 mrem /yr to the total body and $3000 mrem /yr to the skin for the noble gases and is limited to $1500 mres/yr to any organ for all radiciodine and for all radioactive materials in particulates form and radionuclides other than noble gases with half lives greater than 8 days, the following release rate calculations shall be performed. These calculations, when solved for 'f', i.e. flowrate, are the release rates for noble gases and for radioiodines, particulates and other 3 radionuclides with half-lives greater than 8 days. The most conservative of 5

v/ release rates calculated shall control the release rate.

1-1 Revision 5 9/10/85

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n 1.2.1 Noble Gases O {Kg x [(X/Q)Qg ] <500 mrem /yr and N

i 1

{(L g + 1.1 M ) [(X/Q)Q ]

1 g g <3000 mrem /yr l

where: I t

K.

= The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in arem/yr per pCi/m3'from Table 1.2-1.

I

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

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

t i P.

• = The dose parameter for radionuclides other than noble gases for the i inhalation pathway, in eres/yr per pCi/m3 and for the food and ground i plane pathways in m 2

.(aren/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).

Q*. = The release rate of radionuclides, ' i'

, in gaseous effluent from all i release points at the site, in pCi/sec.

X/Q = The highest calculated annual average dispersion parameter for any 2

area at or beyond the unrestricted area boundary.

W = The-highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location.

Q.1 = k C.f 1 + k2 = 4.72E+2 C.f 1

\

where: 1 l

C.* = the concentration of radionuclide, i , in undiluted gaseous effluent ,

l in pCi/ml. I f = the undiluted effluent flow, in efs.

k2 =. conversion factor, 2.83E+04 al/ft 8.

k2 = conversion factor, 6.0E+01 sec/ min.

4 1 1.2.2 Radiciodines, Particulates, and Others

() P [W Qg ] < 1500 mrem /yr where the terms.are as defined above. -

7 4

1-2 Revision 5 l 9/10/85 e

g - .v---,,3 + , . - - , - = ~ - . - r w- -#,=- - - w- - . . - , -.-v --------w v . , . - - - . - , - --,.------,v.- - ry.s.y , -,e-, --- ,

c' TABLE D 2-2 O

(1 of 1)

DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE j PARTICULATE, GASEOUS EFFLUENTS * ,

l l'

P(I), DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATES IN GASEOUS EFFLUENTS Pathways Pathways Inhalation Food and Ground Inhalation Food and Ground (arem/yr per (m2 .arem/yr per ,.

(mrem /yr per (m2 . mrem /yr per Radionuclide pCi/m 3) pCi/sec) Radionuclide pCi/m 3) pCi/sec)

H3 1.125 E+03 2.4E+03 RU 103 6.625 E+05 1.6E+08 Alpha Act 1.100 E+08 1.8E+10 RU 106 1.432 E+07 2.0E+08 CR 51 1.698 E+04 1.1E+07 AG 110M 5.476 E+06 1.5E+10 MN 54 1.576 E+06 1.1E+09 CD 115M 2.920 E+05 5.2E+07

FE 55 1.110 E+05 1.1E+08 SN 123 3.550 E+06- 3.7E+09 FE 59 '1.269 E+06 7.2E+08 SN 126 1.120 E+07 1.1E+10 CO 58 1.106 E+06 5.8E+08 SB 124 3.240 E+06 1.4E+09 CO 60 7.067 E+06 4.6E' s SB 125 2.320 E+06 9.1E+08 NI 63 8.214 E+05 3.0E+10 TE 127M 1.408 E+06 1.0E+09 ZN 65 8.399 E+04 1.8E+10 TE 129H 1.761 E+06 1.3E+09 RB 86 1.983 E+05 2.1E+10 CS 134 1.014 E+06 5.6E+10 SR 89 2.157 E+06 1.1E+10 CS 136 1.709 E+05 5.7E+09 SR 90 1.010 E+08 1.0E+11- CS 137 9.065 E+05 5.0E+10 Y 91 2.627 E+06 5.9E+06 BA 140 1.743 E+06 2.6E+08 ZR 95 2.231 E+06 3.5E+08 CE 141 5.439 E+05 3.2E+07 NB 95 6.142 E+05 3.8E+08 CE 144 1.195 E+07 1.6E+08 MO 99 1.354 E+05 3.2E+08 I 131 1.624 E+07 1.0E+12 1

I 133 3.848 E+06 9.6E+09

, *If SR-90 analysis is performed, use P(I) given in I-131 for unidentified components. If SR-90 and I-131

! analyses are performed, use P(I) given in CS-137 for unidentified components. If SR-90, I-131, and CS-137 analyses are performed, use P(I) given in 2n-65 for unidentified components.

Revision 5 9/10/85

.-~ where:

\' 6 1.14E5 = 10 pCi/pCi x 103 ml/kg + 8760 hr/yr.

U, = Water consumption by age group, A/yr.

infant 330 child 510 teen 510 adult 730 D,= Dilution factor from the near field area to the potable water intake.

U,f = fish consumption by age group, kg/yr.

Infant --

child 6.9 teen 16 adult 21 BF.* = Bioaccumulation factor for radionuclide, 'i', in fish, pCi/kg per pCi/1, from Table 3.1-1.

DF,1 = Dose conversion factor for radionuclide, 'i' , by age group in pre-selected organ, T, in mrem /pCi, from Tables 3.1-2, 3.1-3, 3.1-4, and 3.1-5, respectively.

Using the above information, A for each site. This informati$n.Iisvalues for the provided adult in the have been calculated Table "X" 4.0-3 where "X" is the appendix for the site in question.

3.1.2 Gaseous Effluents The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be cal-culated for the maximum exposed individual using the following equations:

3.1.2.1 Noble Gases For gamma radiation:

DY = 3.17 E-8 I M.1 [(X/Q) Q ]

i=1 For beta radiation:

s Dp = 3.17 E-8 1 Ng [(X/Q) Q ]

i=1 where:

, 3.17E-08 = The inverse of the number of seconds in a year.

t

) Mg = 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.

3-2 Revision 5 9/10/85

N. = The air done factor due to beta emissions for each identified

(- j

• noble gas radionuclide, in mrad /yr per pCi/m3 from Table 1.2-1.

X/Q = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.

~

' Q*. = The release of noble gas radionuclides, 'i', in gaseous effluents, in pCi.

4 3.1.2.2 Radioiodines, Particulates, and Others These calculations apply to all radioiodines, radioactive materials in partic-ulate form and radionuclides other,than noble gases with half-lives greater than 8 days:

4 D = 3.17 E-8 Ii R.* [WQg ]

where:

3.17E-08 = The inverse of the number of seconds in a year.

Qg = The release of rodioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, 'i',

J O in pCi.

as appropriate.

Releases shall be cumulative over the calendar quarter or year W = The annual average dispersion or deposition parameter for estimating the dose to an individual at the controlling location.

W = (X/Q) for the inhalation pathway, in sec/m3 .

W = (D/Q) for the food and ground plane pathways, in meters 2, Rg = The dose factor for each identified radionuclide, 'i', in m .(mrem 2 /yr) per pCi/sec or mrem /yr per pCi/m3 , for each pathway. (Tables 3.1-12 + 3.1-30) where:

Inhalation Pathway Factor, R.I [X/Q]

1 Rf [X/Q] = K'(BR), (DFAg ), (area /yr per pCi/m3 )

where:

i K' = a constant of unit conversion, 108 pCi/pci.

(BR), = the breathing rate of the receptor of age group (a), in m3 /yr.

The breathing rates (BR) for the various age groups are tabulated below, as given in Reg"latory Guide 1.109.

3 Revision 5 9/10/85

,e. , - - , - - - , , -ra,,- . ,-- - -- -- - , - , , ,

I i

-l 3.3.4 Fuel Fabrication No fuel fabrication operations occur within fifty miles of any Duke Nuclear Station. The increment of dose from fabrication operations to any individual within fifty miles of any Duke Nuclear Station is negligible.

3.3.5 Nuclear Power Production The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent raleases will be calculated using the methodology presented in Sections 3.1.1 and 3.1.2. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions  ;

(see Section 3.1.3).

In certain situations more than one nuclear power station site may contri-bute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190. Situations involving more than one station will be presented in the section on site specific information.

3.3.6 Fuel Reprocessing No fuel reprocessing operations occur within fifty miles of any Duke Nuclear p Station. The increment of dose from reprocessing operations to any individual within fifty miles of any Duke Nuclear Station is negligible.

To summarize, only dose increments from nuclear power production operations (Section 3.3.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFR190.

O V

3-9 Revision 5 9/10/85

TABLE 3.1-3 (3 of 3)

INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08. 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-11 2.24E-08 NO DATA 4.65E-11 3.43E-11 1.43E-13 l

BA 142 2.99E-08 2.99E-11 1.84E-09 NO DATA 2.53E-11 1.99E-11 9.18E-20 LA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 LA 142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E NO DATA 3.04E-09 NO DATA 4.31E-05 PR 144 4.30E-11 1.76E-11 2.1PE-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05 NP 239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05

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TABLE 3.1 Revision 5

. (3 of 3) 9/10/85