ML20023D386

Rev 1 to Offsite Dose Calculation Manual.

ML20023D386
Person / Time
Site:	Mcguire, McGuire
Issue date:	04/15/1983
From:	Birch M, Mcintosh M, Stewart J DUKE POWER CO.
To:
Shared Package
ML20023D384	List: ML20023D383 ML20023D386
References
PROC-830415, NUDOCS 8305200440
Download: ML20023D386 (8)

Text

.-

April 15, 1983

Subject:

McGuire Nuclear Station Offsite Dose Calculation Manual l

The General Office Radwaste Engineering staff is transmitting to you this date, Revision 1, of the Offsite Dose Calculation Manual. Please update your copy No. 1 and discard affected pages.

Remove These Pages Insert These Pages Table 1.2-2 Table 1.2-2 Rev. 1 Page 3-6 Page 3-6 Rev. 1 Page 3-7 Page 3-7 Rev. 1 Table B4.0-2 Table B4.0-2 Rev. 1 Table B5.0-4 (1 of 3) Table B4.0-3 (1 of 3)Rev. 1 Table B5.0-4 (2 of 3) Table B4.0-3 (2 of 3)Rev. 1 Table B5.0-4 (3 of 3) Table B4.0-3 (3 of 3)Rev. 1 Note: As this letter contains "LOEP" information, please insert this letter s/ in front of the February 28, 1983 letter.

Approval Date: f/v[f3 '

Approval Date: O

//

Effective Date: 4/15/83 Effective Date: 4/15/83 gf M.L. rc M.D. McIntosh, Manager System Radwaste Engineer McGuire Nuclear Station If you have any questions concerning Revision 1, please call Jim Stewart at 704/373-5444.

Am*/ YS .

James M. Stewart, Jr.

Associate Health Physicist WC-2389 JMS/fke

1. 8305200440 830517 PDR ADOCK 05000369 P PDR

c .

DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, GASEOUS EFFLUENTS

• t P(I), DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATES IN GASEOUS EFFLUENTS Pathways Pathways Inhalation Milk and Ground Inhalation Milk and Ground (arem/yr per 2 (m . mrem /yr per (mrem /yr per (m2 . mrem /yr per Radionuclide pCi/m 3) pCi/sec) Radionum2ide pCi/m3 ) 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 1.5E110 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 1.1Ei10 j CO 58 1.106 E+06 5.8E+08 SB 124 3.240 E+06 1.4E+09 i

CO 60 7.067 E+06 4.6E+09 SB 125 2.320 E+06 9.1E+08 l 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 129M 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 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 Zn-65 for unidentified components.

Revision 1 4/15/83

0.75 = the fraction of total feed that-is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmos-pheric water.

Grass-Cow-Meat Pathway Factor, R [D/Q]

The integrated concentration in meat follows in a similar manner to the develop- ,

ment for the milk pathway, therefore:

(1-fpsf Je ^i th

~

Q ff -A.t if Ps ,

R [D/Q] = K' [(U*P)Ff (r)(DFLg ),

I w p y

s e

(m2 .

arem/yr per pCi/sec) where:

Ff = the stable element transfer coefficients, in days /kg, Table 3.1.11.

U,p = the receptor's meat consumption rate for age (a), in kg/yr.

U 0 ap (kg/yr) -- Infant Child 41

- Teen O - Adult 65 110 Taken from Regulatory Guide 1.109 (Rev. 1).

t g

= the transport time from pasture to receptor, in sec, 1.73 x 10s (2 days).

t = the transport time from crop field to receptor, in sec, 7.78 x 108 (90 h

days).

The concentration of tritium in meat is based gon its airborne concentration rather than the deposition. Therefore, the Rgis based on [X/Q]:

8 R"[X/Q]

I = K'K'"F Q Uf F ap(DFL.)a i [0.75(0.5/H)] (mrem /yr per pCi/m )

where all terms are defined above.

Vegetation Pathway Factor, RVg[D/Q]

The integrated concentration in vegetation consumed by man follows the expres-sion developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

? .. . .

) ib 4UfS ih R [D/Q) = K' y g) (DFLg ), fe g

v i w -

'v (m2 . mrem /yr per pCi/sec) where:

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

3-6 Revision 1 4/15/83

U* = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr.

Y* = (kg/hr) - Infant 0

- Child 26

- Teen 42

- Adult 64 U = the consumption rate of stored vegetation by the receptor in age group a

(a), in kg/yr.

, - Child 520

- Teen 630

- Adult 520 fg = the fraction of the annual intake of fresh leafy vegetation grown locally, (1.0). l f = the fraction of the annual intake of stored vegetation grown locally, 8

(0.76). l t g = the average time between 4 harvest of leafy vegetation and its consumption, in seconds, 8.6 x 10 (1 day).

th = the average time between harvest of stored vegetation and its consumption, in seconds, 5.18 x 10s (60 days).

Yy = the vegetation area density, 2.0 kg/m 2, and all other factors are previously defined.

Theconcentrationoftritiuminvegetationisbasegontheairborneconcentra-tion rather than the deposition. Therefore, the R gis based on [X/Q):

R [X/Q) = K'K'" [0.75(0.5/H)] (mrem /yr per pCi/m3 ).

Ufft + (f (DFLg ),

All terms defined previously'.

3.1.3 Direct Radiation Direct radiation is that radiation from confined sources and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary on-site radwaste storage tanks. Dose calculations using this method performed for Duke Nuclear Stations indicate direct radiation doses are much less than 0.01 mrem /yr. and, therefore, makes a negligible contribution to individual dose. Direct radiation doses will not be calculated routinely.

3.2 SIMPLIFIED DOSE PROJECTIONS O To estimate the cumulative dose contributions to the maximum exposed individ-V ual for 31 day dose projection calculations, the calculations presented in Section 3.1 can be simplified. The simplified calculations would be for an individual in the critical population using only data for the critical pathway 3-7 Revision 1 4/15/83

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/QTH 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

, SSW SW WSW W These values have been replaced by the maximum WNW values given in the McGuire SER, March 1978, NW Table 3 Appendix D.

NNW N

NNE NE ENE E

ESE SE SSE Revision 1 4/15/83

,/ TABLE B4.0-3*

(1 of 3) .

MCGUIRE NUCLEAR STATION ADULT A,g7 DOSE PARAMETERS ,

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII H 3 0.0 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 NA 24 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.4BE+02 l CR 51 0.0 0.0 1.49E+00 8.94E-01 3.29E-01 1.98E+00 3.76E+02 MN 54 0.0 4.76E+03 9.08E+02 0.0 1.42E+03 0.0 1.46E+04 MN 56 0.0 1.20E+02 2.12E+01 0.0 1.52E+02 0.0 3.82E+03 FE 55 8.87E+02 6.13E+02 1.43E+02 0.0 0.0 3.42E+02 3.52E+02 FE 59 1.40E+03 3.29E+03 1.26E+03 0.0 0.0 9.19E+02 1.10E+04 CO 58 0.0 1.51E+02 3.39E+02 0.0 0.0 0.0 3.06E+03 l l CO 60 0.0 4.34E+02 9.58E+02 0.0 0.0 0.0 8.16E+03 NI 63 4.19E+04 2.91E+03 1.41E+03 0.0 0.0 0.0 6.07E+02 NI 65 1.70E+02 2.21E+01 1.01E+01 0.0 0.0 0.0 5.61E+02 l CU 64 0.0 1.69E+01 7.93E+00 0.0 4.26E+01 0.0 1.44E+03 l ZN 65 2.36E+04 7.50E+04 3.39E+04 0.0 5.02E+04 0.0 4.73E+04 ZN 69 5.02E+01 9.60E+01 6.67E+00 0.0 6.24E+01 0.0 1.44E+01 N BR 83 0.0 0.0 4.38E+01 0.0 0.0 0.0 6.30E+01 BR 84 0.0 0.0 5.67E+01 0.0 0.0 0.0 4.45E-04 BR 85 0.0 0.0 2.33E+00 0.0 0.0 0.0 0.0 RB 86 0.0 1.03E+05 4.79E+04 0.0 0.0 0.0 2.03E+04 RB 88 0.0 2.95E+02 1.56E+02 0.0 0.0 0.0 4.07E-09 RB 89 0.0 1.95+02 1.37E+02 0.0 0.0 0.0 1.13E-11 SR 89 4.78E+04 0.0 1.37E+03 0.0 0.0 0.0 7.66E+03 SR 90 5.95E+05 0.0 1.60E+05 0.0 0.0 0.0 3.40E+04 SR 91 8.79E+02 0.0 3.55E+01 0.0 0.0 0.0 4.19E+03 SR 92 3.33E+02 0.0 1.44E+01 0.0 0.0 0.0 6.60E+03 Y 90 1.38E+00 0.0 3.69E-02 0.0 0.0 0.0 1.46E+04 Y 91M 1.30E-02 0.0 5.04E-04 0.0 0.0 0.0 3.82E-02 Y 91 2.02E+01 0.0 5.39E-01 0.0 0.0 0.0 1.11E+04 Y 92 1.21E-01 0.0 3.53E-03 0.0 0.0 0.0 2.12E+03

• Table provided by: M. E. Wangler, RAB:NRR:NRC on 2/24/83.

O TABLE B4.0-3 (1 of 3)

Revision 1 4/15/83 l

l - - - . . _._.

() TABLE B4.0-3 (2 of 3)

MCGUIRE NUCLEAR STATION ADULT A g DOSE PARAMETERS NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII Y 93 3.83E-01 0.0 1.06E-02 0.0 0.0 0.0 1.22E+04 ZR 95 2.77E+00 8.88E-01 6.01E-01 0.0 1.39E+00 0.0 2.82E+03 ZR 97 1.53E-01 3.09E-02 1.41E-02 0.0 4.67E-02 0.0 9.57E+03 NB 95 4.47E+02 2.49E+02 1.34E+02 0.0 2.46E+02 0.0 1.51E+06

MO 99 0.0 4.62E+02 8.79E+01 0.0 1.05E+03 0.0 1.07E+03 TC 99M 2.94E-02 8.32E-02 1.06E+00 0.0 1.26E+00 4.07E-02 4.92E+01 i TC 101 3.03E-02 4.36E-02 4.28E-01 0.0 7.85E-01 2.23E-02 1.31E-13 RU 103 1.98E+01 0.0 8.54E+00 0.0 7.57E+01 0.0 2.31E+03 j RU 105 1.65E+00 0.0 6.52E-01 0.0 2.13E+01 0.0 1.01E+03 1

RU 106 2.95E+02 0.0 3.73E+01 0.0 5.69E+02 0.0 1.91E+04 AG 110M 1.42E+01 1.31E+01 7.80E+00 0.0 2.58E+01 0.0 5.36E+03

, TE 125M 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.0 1.11E+04 i

TE 127M 7.05E+03 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.0 2.36E+04 O TE 127 1.14E+02 4.11E+01 2.48E+01 TE 129M 1.20E+04 4.47E+03 1.89E+03 8.48E+01 4.66E+02 4.11E+03 5.00E+04 0.0 0.0 9.03E+03 6.03E+04 TE 129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.0 2.47E+01 TE 131M 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.0 8.74E+04 f' TE 131 2.05E+01 8.57E+00 6.47E+00 1.69E+01 8.98E+01 0.0 2.90E+00 TE 132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 1.63E+04 0.0 8.02E+04

. I 130 9.01E+01 2.66E+02 1.05E+02 2.25E+04 4.15E+02 0.0 2.29E+02 I 131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.0 1.87E+02 I 132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.0 1.22E+01 I .133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.0 2.64E+02 I 134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01 0.0 2.99E-02 l I 135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.0 1.56E+02 CS 134 3.03E+05 7.21E+05 5.89E+05 0.0 2.33E+05 7.75E+04 1.26E+04 CS 136 3.17E+04 1.25E+05 9.01E+04 0.0 6.97E+04 9.55E+03 1.42E+04 CS 137 3.88E+05 5.31E+05 3.48E+05 0.0 1.80E+05 5.99E+04 1.03E+04 CS 138 2.69E+02 5.31E+02 2.63E+02 0.0 3.90E+02 3.85E+01 2.27E-03 BA 139 9.00E+00 6.41E-03 2.64E-01 0.0 5.99E-03 3.64E-03 1.60E+01 O TABLE B4.0-3 (2 of 3)

Revision 1 4/15/83 l

1 -- . - _ - - - . . _ . , - - .

.e TABLE B4.0-3 -

(3 of 3)

MCGUIRE NUCLEAR STATION ADULT A,g DOSE PARAMETERS NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII BA 140 1.88E+03 2.37E+00 1.23E+02 0.0 8.05E-01 1.35E+00 3.88E+03 BA 141 4.37E+00 3.30E-03 1.48E-01 0.0 3.07E-03 1.87E-03 2.06E-09 BA 142 1.38E+00 2.03E-03 1.24E-01 0.0 1.72E-03 1.15E-03 2.78E-18 l LA 140 3.58E-01 1.80E-01 4.76E-02 0.0 0.0 0.0 1.32E+04 LA 142 1.83E-02 8.33E-03 2.07E-03 0.0 0.0 0.0 6.08E+01 l CE 141 8.01E-01 5.42E-01 6.15E-02 0.0 2.52E-01 0.0 2.07E+03 CE 143 1.41E-01 1.04E+02 1.16E-02 0.0 4.60E-02 0.0 3.90E+03 CE 144 4.18E+01 1.75E+01 2.24E+00 0.0 1.04E+01 0.0 1.41E+04 PR 143 1.32E+00 5.28E-01 6.52E-02 0.0 3.05E-01 0.0 5.77E+03 PR 144 4.31E-03 1.79E-03 2.19E-04 0.0 1.01E-03 0.0 6.19E-10 ND 147 9.00E-01 1.04E+00 6.22E-02 0.0 6.08E-01 0.0 4.99E+03 W 187 3.04E+02 2.55E+02 8.90E+01 0.0 0.0 0.0 8.34E+04 NP 239 1.28E-01 1.25E-02 6.91E-03 0.0 3.91E-02 0.0 2.57E+03 l O l

O TABLE B4.0-3 (3 of 3)

Revision 1 4/15/83

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