ML20235E297

From kanterella
Jump to navigation Jump to search
Applicant Exhibit A-24,consisting of 850703 Memo Discussing Question of Whether Decontamination at Nassau Coliseum Requires Eis.List of Assumptions & Graph Re Fate of Fission Product Inventory Following LOCA Encl
ML20235E297
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 07/14/1987
From: Condon W
NEW YORK, STATE OF
To: Davidoff D
NEW YORK, STATE OF
References
OL-3-A-024, OL-3-A-24, NUDOCS 8709280050
Download: ML20235E297 (5)


Text

.

1 l.

60

.322-H 3

(_. f L & _ f;d l

N py/E 1 p9-2.4 7Yrk 7 ~es STATE OF NEW YORK-DEPARTMENT OF HEALTH mq:

o m.-

INTEROFFICE MEMORANDUM j

1

'87 SEP 1,7 All :59 To:

D. Davidoff - Field Operations Management Group gL:

From:

W. Condon - Bureau of Environmental Radiation Protection D:te:

July 3, 1985

Subject:

Decontamination at Nassau Coliseum

)

l The question of whether decontamination at the Nassau Coliseum requires an EIS was recently raised by DEC.

As far as I know, the impact of decontamination at reception centers has never been addressed since it would be a minor problem in any major release which resulted in ground contamination.

The most likely scenario for any accidental release at a nuclear power plant is the release of noble gases, which represent an external radiation hazard, but does not cause ground contamination.

Even the famous TMI incident, a severe type accident with significant core j

damage, released only a few Curies of fission products which were not i

noble gases, and there was no ground contamination off-site.

)

There is a graph (attached) in " Environmental Aspects of Nuclear Power" by Eichholz, which estimates the a=ount of fission products l

~

released to the atmosphere following a loss of coolant accident; prob-

{

ably the most severe type of accident at a nuclear plant.

Using the j

peak values at one day, the total amount of radiciodines and other solids released is about 100-200 Curies.

To calculate contamination off-site we can assume certain weather l

conditions, an average distance from the plant, and the amount of time vehicles or people might be in the plume to become contaminated, and a release of 100 Curies of fission products.

(About six times that re-i l

1 eased at TMI.)

l i

~

l If we do this, as shown in the attachment, we' conclude that people and/or vehicles have low levels of contaminat1on.

Assuming that 20,000

~

people and 5,000 cars go to the Nassau Coliseum for decontamination, we can make some estimates of the release to the sewers.

l Decontamination of vehicles could take place either in the parking lot of the Qoliseum, with subsequent' discharge to the storm se'wers*or.

on unpaved. areas, allowing the water to be absorbed on the soil.# Dis-charge to the storm sewer results in levels of radioactivity in water near the Part 16 limits for discharge to the environment.

Allowing the water to be absorbed on the ground would result in the fission products being rets.ined in the soil via ion exchange with subsequent radioactive decay before moving any appreciable distance in-soil or ground water.

g7280050070714 g

ADOCK 05000322' PDR

6 N\\A DN

's N

s.

' o' #%,,

h

,?~

'O

\\

4,

'l A+ sgy,e l

~;

l l

i l

5

. Decontamination of persons results in some release of contamination to sewers, but again at levels be. low Part 16 limits for discharge to the environment.

Further dilution at the sewage plant and subsequent decay l

and discharge of soluble radionuclides would lower levels even further.

i Concentration of insoluble materials in sewage sludge would prevent release to the environment.. Disposal of sludge would allow decay of these radionuclides before they could travel any app'eciable distance in r

ground water.

If there is any ground contamination from a nuclear plant release, the contribution of decontamination of persons or vehicles would be very small relative to the total quantity of contamination.

These calculations are very conservative and probably overestimate the release to sewers by a large factor.

It does not t.ppear that decontamination activities at re-ception centers following a release will produce any adverse impact on the

)

environment.

I I

l I

l a

1 1

1

\\

l l

s 1

1

..x.

.c l

._,2

~

i I. Contamination of People Assumptions:

1. 100 Curies fission products released
2. Class D stability.

)

3. Average of five miles distance to deposition
4. X/Q=5.4x10-6 for class D at 5 miles
5. Deposition velocity = 3x10-3 m/sec
6. Persons are in plume for 1/10 of.. total release time
7. 10% of body. surface is contaminated ~(.18m2)

Contamination level / person:

{

A = 100x5.4x10-6.18x1/10x3x10-3' l

x 2

A = 3x10-8C1/m =.03uci/ person i

II. Decontamination of Petaple Assumptions:

1. 20,000 persons with an average of.03uci/ person
2. Each showers with 40 liters (apprx.10 gal). of water
3. 100% removal of contamination Water activity = 20.000x.03 = 8x10-7uC1/ml 40x2000x1000 Part 16 limit for mixed beta gamma activity is 3x10-6uci/ml on an annual average basis.

III. Contamination of cars Assumptions:

1. Car surface area is 12m2 (about 6x18.ft.)
2. Each car is washed with 150 liters (apprx. 40 gal) of water
3. 100% removal of contamination
4. Cars are in plume for 1/10 of release time Contamination level / car A = 100x5.4x10-6x12x1/10x3x10-3 A = 2 uC1/ car WateraItivity=5000x2

= 1.3x10-5 uC1/ml 150x5000x1000 This is only about four times the Part 16 limit.

i

1 1

t 184 ENVIRONMENTAL ASPECTS OF NUCLEAR POWER im em ton com m e.e W

I i

y

._,,c>

s e

i

,g w w -

ie t

t

s, '\\.,

1 I

1 e

F s (

_i

\\

E t

~

5 9

s

.e L.1 t

i i (,_ !

[

i-lg%s i,.

i.

w s

i r

f i

\\

,4

\\-

w s

b l

\\\\

e p\\.,

i sgg s

n q

e5

!sa

,si i

as ii, i

=. -

i ',

i s

$Q s3(ql!

-- := r

/ i : 'i i I

thi 6

e i

e sh N q

i, e

=

is is

! N. _.

2.9 /Mf

--E-h o

.s

(

gi

. '.L

.; n -

u

-- ~h.,_

pr in r

.h.

Y'

,o' h

.k.

)

', \\

. 's;*\\

g 5'.'ti. WY c

E

[./

f s'

.A i

8 'i

\\

W

.. te/

'i

'l \\

I p <. rM.!h, <

e' t

//

d-

-/-f' W

g t

f t;s' t

%gr

/.

I 6

/ /

i j/

K io

'o

.m 1

y C$

l

.f

.I e

g

/

'/

~.i s p h7.

E!!g i,

~

i a gg;.

{#

s

//

./ !.

(

.(

\\

z =.

f-

^

k

~

/

gI/

u i%

cu.

i i.

it ex coe.

t-3 Figure 42. Fate of fission product inventory following loss of coolant accident (23).

O mIW'**

__._m___.__._____._.m.

....___..--_...m.

1