ML17264A265

Gamma-Body Offsite Dose Calculation.

ML17264A265
Person / Time
Site:	Ginna
Issue date:	11/16/1995
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A264	List: ML17264A263 ML17264A265
References
NUDOCS 9512010132
Download: ML17264A265 (9)

Text

Supplement to WCAP-13668 - Gamma-Body CNsite Dose Calculation Anal ical Assum tlons Source Term The noble gas concentrations In the primary coolant prior to the accident are based upon 1% fuel defects. This is approximately equal to the proposed Technical Specification limit for non-iodine nuclides of 100/E pCI/gm, Dose Calculations The following assumptions and parameters were used to calculate the noble gas activity released to the atmosphere and the corresponding gamma-body doses following a SGTR.

The mass of reactor coolant discharged into the secondary system through the rupture is presented in Tables II.5 and ll.6.

2. No retention of noble gas in the secondary system is assumed. All noble gas activity transferred to the secondary system, from the primary, is released to the atmosphere.

3. No credit was taken for radioactive decay during transport to the site boundary and outer boundary of the low population zone.

Offsite Gamma-Bod Dose Calculation Model Offsite gamma-body doses are calculated using the equation:

D ~ = 0.25 p Eyq g (IAR)IJ (

I J

")J Q

Where:

Dy-body gamma-body dose due to immersion in a semi-infinite cloud of noble gas average gamma energy of noble gas nuclide i in.mev/dis.

(Table Ill.7)

IAR)i integrated activity of noble gas nuclide i released during the time interval j in Ci (x/Q)) atmospheric dispersion factor for time period j in sec/m'5i20iOi32 95iiib 05000244 ..'

PDR ADDCK PD~R ~

Results Doses Rem Gamma-Bod Doses Case 1 Case 2 Guideline Exclusion Area Boundary (0-2 hr) 0.08 0.11 Low Population Zone (0-8 hr) 0.005 0.007

SV 0

Table lll.7 Reactor Coolant Noble Gas Activity (pCi/gm) and Average Gamma Energy (Mev./Dls)

Nuclide RCS Activity E (Mev/Dts)

(pCi/gm)

Kr-85m l.28EO O. l6 Kr-85 5.36EO 0.0023 Kr-87 8.11E-1 0.79 Kr-88 2.38F0 2.2 Xe-131m 2.39EO 0.0029 Xe-133m 3.5EO 0.02 Xe-133 2.03E2 0,03 Xe-135m 3.7E-1 OA3 Xe-135 6.4EO 0.25 Xe-138 4.61E-1 1.2

Attachment 2 RG&E to NRC Letter Dated 11/16/95 Site Plot and Photos

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