ML20086N121

Affidavit of D Schweller in Support of Lilco Motion for Summary Disposition of Phase II Emergency Planning Contention 49 Re Dose Assessment Methods.Certificate of Svc Encl

ML20086N121
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/17/1983
From:	Schweller D ENERGY, DEPT. OF
To:
Shared Package
ML20086M832	List: ML20086M830 ML20086M846 ML20086M868 ML20086M882 ML20086M896 ML20086M915 ML20086M924 ML20086M936 ML20086M958 ML20086M981 ML20086M989 ML20086N008 ML20086N023 ML20086N035 ML20086N121
References
ISSUANCES-OL-3, NUDOCS 8402170233
Download: ML20086N121 (46)

Text

r-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322-OL-3

) (Emergenc'y Planning (Shoreham Nuclear Power Station, ) Proceedi ng)

Unit 1)

AFFIDAVIT OF DAVID SCHWELLER IN SUPPORT OF LILCO'S MOTION FOR

SUMMARY

DISPOSITION OF PHASE II EMERGENCY PLANNING CONTENTION 49 (DOSE ASSESSMENT METHODS)

David Schweller, duly sworn, deposes and says as follows:

My name is David Schweller. I an Manager of the Depart-ment of Energy Brookhaven Area Office.

1. DOE, at its Brookhaven National Laboratory has dedicated Emergency Equipment Kits and " state of the art" equipment for both the detection and measurements of radiation releases.

2. Brookhaven National Lcooratory and DOE have personne1' with expertise in dose calculation who could be called upon in the ever.t of 1

an incident at Shoreham. l

.. 3. The close proximity of Shoreham to the BNL facility is expected t'o minimize communications problems with respect to transmission of relevent data necessary to calculate dose assessments.

8402170233 840213 PDR ADOCK 05000322 U PDR ..

4 00E, through its RAP team was able to perform dose assessment activities at Three Mile Island with current dose assessment models, and similar resources are available for assistance in the event of a radiological emergency at Shoreham.

1 David Schwen er Subscribed and sworn to before me this l7 d day of hk ,1983.

My commission expires: $,[sr OhAME -

L

/ Notary (/Public Af a'i?:N J L e.Gi3 PWary P?"C S'. ate of New n ort !.:o. 30-C662M O'afifiec i.? Nsnac County Comcaseten Caf, ires Maren 30,1957 l

Attachment 1

. - FEMA REP-2

, qs -

SEPTEMBEP 1980 ,

i GUIDANCE ON -

OFFSITE EMERGENCY

. RADIATION. .

7

MEASUREMENT i l SYSTEMS  !

l Phase 1 - Airborne Release -- M l

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ABSTRACT {

l This report prepared by the Federal Interagency Task Force on Offsite Emergency Instrumentation for Nuclear Incidents provides interim guidance to State and f local agencies responsible for Radiological Emergency Preparedness in the event of a nuclear incident at a light water nuclear power plant. The guidance presented covers the selection and use of radiation measurement systems that are based on the protective action guidance as presented in the EPA " Manual of .

Protective Action Guides and Protective Actions for Nuclear Incidents" (September }

1975) and the guidance for the basis of planning provided in NUREG 0396, EPA 520/1-78-016 " Planning Basis For The Development Of State And Local Government Radiological Emergency Response Plans In Support Of Light Water Nuclear Power Plants" (December 1978). This initial report is limited to guidance on the establishment of emergency radiation detection and measurement systems for measurement of the airborne plume by State and local governments during such a nuclear incident. It is assumed that this system would be augmented during Future the course of the accident by an extensive Federal emergency response.

reports will address instrumentation requirements for measurement of the ingestion pathway, deposited materials and recovery operations.

The function of the measurement systems addressed in this report is to acquire radiation data that can be used to make protective action decisions that would ensure that radiation exposure to the public will be as low as is reasonably achievable (ALARA). By the same token, it is necessary to consider keepirsg the cost of the systems within reasonable limits, without compromising ALARA exposure, by utilizing existing instrumentation and resources whenever i >

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possible. Therefore, the design, planning and implementation of the systes must assure a rapid and positive response in the event of a nuclear incident.

The Task Force has elected to include in the report many topics which are

' ancillary to the specific instrumentation requirements of the emergency response organization.

Consideration of these topics was necessary to provi' a basis for the specific recomunendations with respect to incident notificatir

! I It is hoped that l exposure rate verification, response team manpower, etc. >

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, these topics will be useful to the planning agency in developing and estab-4 I lishing the emergency response organization.

The reconmendations and guidance presented in this report are based on radia-

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i tion instrumentation and methodologies that are currently available or expect q

to be available in the immediate future as a result of identified development efforts.

New and improved emergency radiation instrumentation, measurement j

methodologies and measurement systems are expected to evolve in the future,

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,i perhaps based on some of the Task Force recommendat. ions to the Federal

,l Interagency Central Coordinating Comunittee. Consequently, the use of this

• guidance should be modified by the planning agency to incorporate future i

developments as they evolve.

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t-11 k

y APPENDIX B '

AN AIR SAMPLING SYSTEM DEVELOPED BY BROOMiAVEN NATICi:AL LABORATORY eF T FOR EVALUATION ,THE THYROID DOSE C0m IT, MENT hi DUE TO FISSION PRODUCTS RELEASED FROM REACTOR CONTAINMENT B.1 Introduction E

Inhalation of radiciodines is expected to be the most important initial

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.g pathway of human exposure in the event of a release of radicactivity 3 during a nuclear power reactor incident. The thyroid gland will there- 3

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fore be the critical organ and will receive the largest dose should an accident occur.

Consequently, a method for monitoring for radioiodines, in the presence of fission gases (e.g. ,133Xe), which would be released in much larger quantities than radiofodines and particulate fission products, must be develcped to provide a data base for exposure control.

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Costly measurement methods using gamma analysis can be avoided by developing a sampler specifically for iodine, thereby permitting any beta j

t or gamma detector to be used for measurement (Figure B-1). Particulate fission products include dozens of noniodine radionuclides. Use of a prefilter (Figure B-2) before the adsorber bed separates the activity into gaseous and particulate fractions, and allows a determination of gaseous radiofodine.

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Adsorption of fission gases relative to iodine can be reduced by using an appropriate inorganic adsorber. Several commercial inorganic adsorbers were tested, but were too expensive or inefficient for the organic or I

hypoiodous acid forms of iodine. A silver impregnated silica gel adsorber l was developed that has over 90% efficiency for collection of radioiodine ,

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for sampling times of several minutes. The material provides corresponding xenon efficiencies of less than 0.04% at temperatures above 7*C.

j i The air sample size needed for reliable detectic.n of a given air 3 concentration depends on detector sensitivity, flow rate, and sampling time. Field monitoring under accident ccnditions tequires prompt measuremer.ts for proper use of time, equipment, and operator exposure.

For these reasons, the Federal Interagency Task Force on Offsite Emer-gency Instrumentation for Nuclear Incidents set a maximum of 5 minutes f

for air collection. Two degrees of freedom remain: detector sensitivity and flow rate.

I Flow rate is governed, in part, by the power available for air movement.

Air sampling away from power lines requires portable generators or power derived from automotive electrical systems. Battery power supplies are l

inappropriate due to excessive weight and expense. As mentioned earlier, the desirable solution'is a significant number of inexpensive air sampling I

, apparatus. Thus, use of automotive electrical systems is the least expensive solution (Figure B-3). Two power connections to automotive l

, batteries are economically possible: direct clamping or use of cigar lighter sockets. The safer and generally better solution is the latter.

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sampling rate for either power source.

Economy and long-term The remaining variable is detector sensitivity. desirable. GM calibration stability make Geiger-Mueller detectors i However, detectors are known for high beta and low tandard photon GM tubes, effic en photon sensitivity can be increased byZchanging cathodes. There-the s with stainless steel cathodes, to ones with higher Victoreen 6306 fore, a CD V-700 GM instrument, used d for this sampling with a high Z ca tube, may be used to provide the sensitivity desire i

. system.

B.2 The Air Mover i

fa The air mover housing, shown on Figures B-4 and B-forated motot tubular support structure, a front and back plate, and a p The tubular structure contains a handle, two impeller safety guard.

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Il the rubber cord. The flow rate control screw is located in the central f suction tube and is used to adjust spring tension on the bellows. The I

remaining two holes ventilate the interior of the bellows to maintain u

normal atmospheric pressure within the bellows. A rear view of the 4 The bellows consist of two metal cups, i bellows is shown on Figure B-5.

one attached to the front plate and the other capable of longitudinal movement. The flow rate control screw is used to adjust the spring loading. This tends to direct the movable bellows half toward the front plate, closing the air bleed port shown to the left of the spring. [

During motor operation, the reduction in atmospheric pressure will }

k counteract the loading spring, op ning this port. Thus, spring The difference d' adjustment controls the pressure inside the air mover. B between ambient pressure and pressure in the air mover governs the flow l e

rate through the filter adsorber. Dust loading is not a problem for the (

5 minute, 5 cfm sample.

I The rear plate serves as a vacuum bulkhead and as a mounting plate for ,

! the dual voltage motor and 3.c. speed centrol. The impeller and a.c.

speed control adjusting stub are shown in Figure B-4. The remaining

! perforated plate protects the operator.

The dual voltage motor is designed for about 240 watts on alternating i I

current, nearly double the d.c. power value. A 600 watt household lamp  !

dimmer is used to reduce tha a.c. power for the proper flow cate.

l Direct current power is derived from the cigar lighter socket of any 12 V  :

il l vehicle. An adapter plug provides for d.c. operation.

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B.2.1 Initial and Periodic Flow Rate Adjustment ,

l The air mover is operated at 12.8 V d.c. measured at the cigar lighter j socket. A filter canister is connected to a venturi flow rate meter which in turn is connected to the air mover suction tube with Tygon tubing. A venturi flow meter is a straight through flow device that operates with an acceptable pressure drcp of about 0.25 inches of water. 4 Theflowrateisadjustedto5cfmbyalternatelydisconnecting, adjusting l the flow adjusting screw shown on Figure B-4, and reconnecting the Tygon tubing to the air mover suction tube. l i

The dual voltage motor develops about twice as much power on a.c. as it does on d.c. For proper balance the a.c. voltage must be reduced. 1 I

After d.c. adjustment, the adaptor plug is removed ano the air mover is j

't operated on 110 il volt a.c. power. The a.c. speed control stub shown on Figure B-4 is turned to provide an indicated flow of 5 cfm.

O Air flow control characteristics for a.c. and d.c. power are shown on Figure B-6. The regulated d.c. flow rate change is less than 0.4% per 1%

voltage change, while the regulated a.c. flow rate change is about 0.8% f per 1% voltage change. l t

r 8.3 An Inorganic Adsorber with Low Noble Gas Retention , I A silver loaded silica gel has been developed as an adsorber for air monitoring subsequent to a release from containment power reactor accident.

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• Requirements of high efficiency for known radiofodine species under w ambient conditions of humidity and temperature and low noble ga efficiency are satisfied by the material.

Silver loadings from 2 to 24% by adsorber weight have been tested organic radiciodine, hypoiodous acid, elemental radiciodine, and noble fission gases.

Relative humidity was varied between 5 and 99%, and stay times of 0.11, 0.073, and 0.055 seconds were used.

Silver loading requirements depend on sampling duration and relative humidity.

Eavironmental monitoring requires about 25 ft 3 of air be sampled and analyzed for a dose projection.

The proposed analysis system consists of an air mover, an adsorber and a civil defense readout instr ment fitted with a special 6306 probe which is discussed in Section 4 .

This combination provides adequate sensitivity for dose predictions . A silica gel adsorber can be used eith a 4% silver loading for a of better than 93% with a 0.11 second. stay time, and for all ambient conditions tested.

Similar tests using 4% silver loaded 13X molecular sieve or about 60% silver zeolite yielded lower efficiencies.

Xenon adsorption was less than 5 x 10'3

% at 55'C with no post-release flushing.

This value was about 1/20 of the value for charcoa same conditions.

B-12

-.=

e 4

. * . O O

i F

FIGURE B-5 ,

,t ,

I I i B.4 Hioh Photon Sensitivity GM Tuby i l ,

Geiger-Muelter detectors are sensitive to ionizing events initiated by energetic charged particles within the active volume. /j

!!i 1

3 To increase phcton sensitivity, GM detectors should have high Z materials j within the active volumes. Bismuth is the optimum material since it is [

d i

the highest Z non-radioactive element.

k ei.--

Victoreen 6306 GM detectors contain bismuth coated wire mesh screens i positioned around the cathodes. Wire screening is used to increase the cathode surfact to volume ratio and thereby increase sensitivity. . c; Organic quenching must be used due to the chemical reactivity of bismuth with the halogens. i i

I

)

TGM Detectors, Inc. supplied a number of halogen quenched counters with i platinum plated cathodes. Type NP 358 detectors, with an inside diameter j of 15.2 mm, were shortened by TGM to 9.8 cm. All of the GM tubes were f operated with a standard CD V-700 instrument adjusted to 900 volts.

i 8.5 Energy Response Measurements j 1

GM detector energy responses were measured with heavily filtered x-rays i l

l and isotope sources. Some of the isotope sources used to determine ,

{'

l detector energy response were 131I (365 kev), 137Cs (662 kev) and ,

60 Co (1250 kev). X-rays from 74 to 200 kev effective energy were also j i

used.

1 I

l l B-13 3

l .

=:s-

.b6 MY ET[ ,, ,~[ ,(, - - -, -

J N .e

" ^  ! ,

,y - ..

l l l

l The measured energy responses of four bare Victoreen detectors are shown fr. Figure B-7. {

Good agreement betweert measurements and sales literature exists below 365 kev, while a sensitivity more constant with energy was t

measured above.

GM detector filter calculations were made to design a shield to attenuate the principal xenon decay photons more than the iodine, where the calculated and measured response is shown in Figure B-7 for a two element concentric filter of 0.127 cm Pb adjacent to the GM tube followed by 0.08 cm Cu. The shield and 6306 tube are shown in

' Figure 8-8. A comparison of the bare tube 135 Xe to I3I I ratio of L50/185 2 1.9 to the filtered tube ratio of 123/125 2 1 indicates that the shielding reduced the xenon to iodine response ratio by a factor of approximately 1.9.

The remait,ing xenon isotopes have lower energy decay gamma rays and are reduced by much large. factors.

Air sampling for iodine involves adsorption of gases and filtration of particles on a cylindrical canister. Readout requires the insertion af a shielded GM detector into the axial suction hole in the canister, as shown in Figure B-2.

The energy response of the 6306 probe within a

' canister with 4% by weight silver loaded on silica gel is shown in j

, Figure B-9.

Calculations indicate that approximately 50% of the adsorbed j

organic iodine is in the first 0.4 cm of adsorber.

To better account for i photon attenuation, a 0.4 cm void is placed in the periphery of the I adsorber bed and oriented normal to the photcn beam.

!, !n i

l i ,

B-14 l

i W '

- 1 1

FIGURE B-7 l

1 U

1 1

i i i i i i ii n

_ iii. > i i i i i iii li

'ITI

[

_ - j BARE (3) ,y

\

I l [

' IBARE, sB MEASURED _

- SI '

$100 .

4 '

\ g ljn1t E -

j

$ ~ l ', l -

51 SHIELDED 1 6 8

' MEASURED lV [

I ENERGY CORRECTION FOR THE - s l VICTOREEN 6306 BISMUTH -

i 10 -

2 LOADED GM TUBE WITH A .

[

0.127 cm Pb + 0.08 cm Cu SHIELD _  ;

f

''' ' ' ' ' - t 3

3 30 10 0 10 '

20 E, kev f

c Figure B.7 Energy response of bare and shielded 6306 GM detectors. >

t s .

B-15

- ~= n sm .:. &m , u,g,,, .

. 3

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

, ,; . ; . .n p-. ,_

l

.I J

l FIGURE B-8 1

I l

I

'l.

1 i

4 I

f

+* x'z ** ' .

?T*. y

<,*;p.1%. :r y ..

~. . .. .,

.3 ef r.: ~. . , -

. :s, u, .

. r. 4 .

Wmb, ...

1. 2% ._24 y,.^

.. .s se 4 a. .

a= ....

.i .-: . ...~ ..

3.*., .

e l . .. . ,

58 ' .. ' - g weie . 3 .

1 e g

.- M

- - . . 4,

.* o ,

i c.- n er r.:r ,- -

.4 / .

w - -

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' / t  :, .

fLvt e

/

-k.~,

.,f . ..= . . , . . . . . . ,

s c .

, . . . .a.

p j . . . . . . .:

s f.*,. " i '. - _' i Se' .}. . . - *n f. 's m.e. -

\. g

., . . - x.mu,. ..:. . .

• .. .\. .,.

a..

c.

. :w , . , .. ~ . ~ . .

c .

i.

a nn, . e.-

.. a.c m.r..

.:.,n.. w ,-

,q. n3 i

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' ' . '.; .. Q DQY' li'MO6Q;nu. U.

.e:.-L d i:i,r' u.,% n c.% ,a

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i .

l' I

l 1

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.r ,

B-16 t i l ,

k. 9 I -

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---_-p>- - - -

e.i

_ eda ma ese_ _ _

. _ _ - - _ _ _ _ _ _ _ - _ - _ _ _ . _ _ _ _ - - _ __ - -w _ _ . - _ _ _ _ _ es--- - _1 er~- N'a'w w m.eep-

o FIGURE B-9 i i.

,,,,,,,,,,,,,,,,,i,. - p

'* [ os ou j

[-

,~

3

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.c -

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ts

= E 1 s

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e

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,,,,,,,,i ,,,,,,,,i ,

o , , ,,,,,i 4 io 2 3 10 10 10 20 Ey, kev s

Shielded probe exposed m l ,

Figure B.9 ,

4% Ag-gel canisters.

8 O

l B-17 2\

-w==r. u a  %=2:1. ,7 ,'ig, . .,.q; . g '['.y@p.- .wg r.,y

.y - -- - : - u , a,- .

B.S Summary of Results_

a.

The critical GM detector requirement was taken to be the of air samples containing mixed fission products, b.

A filter was designed to attenuate the xenon decay phot i I3I I photons.

c.

The energy response for a probe having a filtered 6306 dete The energy response was also determined with a 6306 measured.

tube in a 4% Ag-gel loaded canister.

d.

In general, the 6306 GM tube was found to be more sensi photons from 0.25 to 0.5 MeV than the CD V-700 GM its standard GM tube.

AIR SAMPLING PROCEDURE f

Procedures are given for equipment check and field air tsam I i l the exposed filter-adsorber canisters, and internal thyroid dose e I

In order they are:

predictions for the people living in the aeasured area.

i I.

Equipment Check and Field Air Sampling

, A. The air sampling system l li i 1. Air mover.

. B-18 r

[a --. -

l I

l 11

. . . . Ip ..

. Ye l

I Y h 2.

Automobile,12 volt cigar lighter adapter.

3.

One or more quart cans each containing one filter-adsorber ,{.?

Take one can for each location you are to measure I V.

canister.  ;

n j '

and one spare. .*

4. CD V-700 GM counter modified with a 6306 GM tube. j

.j 9 5.

Screwdriver or 25 cent coin to open the quart can lids L ,

(immediately before use). t2 l

6.

Pocket or wristwatch to time the 5 minute 16 second sampling e period. ( i 6

7. Respirator, one per person, optional.

.5 3

B. Equipment checkout i l

( ,

1.

Turn on the, modified CD V-700 and test for an on-scale meter deflection of about 50 to 100 counts per minute on the X 1 Y i

range. The meter will jitter around on an average reading. i Read the midpoint value within the jitter band.

2.

Test the air sampler for operation with normal household a.c.  !

i i i

' electric power. Plug cord into a wall outlet and push the ,

i t

start switch near the handle. For proper operation, the t L

sampler will sound and feel like a small vacuum cleaner.

3.

Take all of the 7 items of part A plus a map and/or route l ,

instructions to a car or truck.

4. Plug the d.c. adapter on the end of the sampler power card into the cigar lighter or using the adapter make contact across the battery terminals and test sampler operation using the car B-19 i _ l- -

> -! l s .* _

e= 7 Q *' ~

} .

• f

• EE:s

.x . w . . . . .. ,

' e,

't ' " ~

}&"__...

g

Turn the sampler electrical systems with the engine running.

off.

C. Air sampling procedure 1.

Drive to the first location, keeping vehicle windows clo 2.

Parkatthefirstlocation,leaveenginerunning,openthe first quart can, and remove the' filter-adsorber canister.

3. Mount filter-adsorber canister over central stretch rubber retainer over the outer end of th 4.

Check to see that the air sampler is plugged into the ciga lighter socket and step out of the vehicle to the relaxe Keep vehicle door closed to the extent of the power cord.

extent possible while allowing the power cord outside v l l

' 5.

While holding the sampler about 4 feet above the ground,

(

on for 5 minutes +6 seconds.

f

't 6.

While the sample is being taken, mark the location cod di-l

.a first location on the can using a two part peel-away label

( .

After filling out both parts of the 9

I i

similiar to Figure B-13.

[ label, remove the peel-away part and mount on the pag Include any supplementary information on the data notebook.

! During this sampling <

I sample next to the label in the notebook.

l period a team member will make gamma measurem l These and 4 feet above the ground and inside the vehicle.

I readings will be added to both parts of the label with any supplementary notes added in the notebook.

B-20 I

i t

,--,e w o. -- - i-- -- , y * ~em -w = w e-% gy - 9 g. .wy, .

I ,

fully remove the canister k When the air sample is completed, caredified COV-700 probe into the 7.

from the sampler and insert of the canister.

the This mo measurement will be b' air suction tube h ground or inside the vehicle '

Record 1, made at either 4 feet above the lowest treading).

e ding of /

h, (depending on which location haseading obtained and the rea which location is used, the r label marked Evaluation, as h N the canister on the part of t e N vehicle is greater than f illustrated in Figure B-13. the reading at 4 feet or inside canister, the measurement ($

8. If the from the w 10% of the count rate obtained location where these readings

=

count rate should be performed at anotherFor example, if the canister inside the are below this level.reading at either 4 feet or {

is 2,000 c/m, then the 200 c/m. Pull the tape vehicle should beoutside less ofthanthe canister.

Locate tne tape on the Return the filter into quart

9. l th. f and remove the glass fiberdling. co can using a paper tissue for d han record this final entry and

10. Read the bare adsorber canister an .j 4

I date on the label. n containing the filter Return the canister to its quart ca t lid.

11.

communications system cloth and reseal with the t ver correc f Report data to EOC by radio or wha e 12 a new canister repeat has been made available.i ted

13. Drive to the next location and us ngIf previous ica I steps C2 through C12. from a newly measured one.

high activity, stack them away i B-21 s

~

f

l -

$ ' ' m. m iic & :.: '.2

. 1 II. Internal Dose Predictions The following calculations should be made at the EOC as the data is received from the monitoring teams in the field.

A. Glass filter cloth evaluation

1. Use Figure B-10 to account for the radioiodine on the glass i filter cloth for each set of measurements received. Note the type of reactor (BWR or PWR), and determine the number,of hours between shutdown and time of measurement.

2. Find the iodine to total released fission products correction factor (CF) on the vertical axis and calculate the difference in filter-adsorber and adsorber readings. This difference (D) is due to total fission product activity on the filter. The product CF x 0 is the corrected filter reading (F) at the time of the measurement due to iodine on the filter.

B. Filter-adsorber evaluation

1. The adsorber net counting rate (N) is determined by subtracting background (B) from the bare adsorber measurement (G), i.e.,

i the adsorber with a glass fiber cloth removed.

I

N=G-B B-22

I 0

l .. .

9 80 Figure B-10 1 t

I; I I-Ile 1.0 1 1 l l 1 l I p

%~~

- t PWR - ,e.

STpgog ,,__ ,

._ 3

- 3 (4 < ,

o s- l 3

o ,

O - 1 1 a: ~

}

c. -

z s ,

9 - i t

= _ ,

C  %*

O 4 w 5 -

<a 4 1.0 - -  !

5 - -

i.

e - -

N _ '% %

k.1 O

~

l 0 s

• BWR 1 TO 4 -  ;

swg g - 1 ,

5 -

) i 9 _ (g# 808  !

48qj

_ a 1 <

I 1 1 I 1 1 I I I O.1 100 10 1

HOURS AFTER SHUT DOWN I l

Figure B.10 Iodine to total fission products correction factor for shielded CD V-700 instruments. ,

I l

a l l

1 l l

1.

I \

B-23 t.

l l

W

W .

2. Add the corrected filter reading (F), t,tep 2 of Section A, to the net adsorber reading to obtain the total iodine counting rate (R).

l R=F+N l

3. Enter on your label the total iodine counting rate found in step 2, on Section B. From Figure B-ll follow a vertical to j the number of hours after reactor shutdown that the bare reading (G) was made. The ordinate is the predicted thyroid dose commitment to a 5 year old child at 'the site of the air sample for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> immersion.

4. If the immersion time is greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then Figure B-12 can be used for the dose commitment to the 5 year old child.

For example, where the dose commitment (ib) for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> imersion is 1 rem, and the anticipated immersion time is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, multiply 1 rem x 2.5 = 2.5 rem.

5 C. Evaluation of results I The projected dose commitment values can be posted on a map l ., corresponding to their locations. If suffic w rt measurements were made, the location of the plume should be defined by significantly higher readings.

Predictions can be made of the dose commitment along the plume pathway.' This should improve the data base so that decisions can be made about stable iodine feeding, evacuation of exposed persoas to l

reduce exposure to resuspended radioactive particles, and designations

( of contaminated pasturage.

B-24

= - __________ - _________________ _ _ _ _

I I

! FIGURE B-11 l

l l

l l

e i

.9 i o E i llll11 I I l11111I I I I E l -

. l l l

.E 4 ~ 2 eman

~ \k -

j c

o E

, E o

• =

O V

.m g

2 o

~

m

~

m

'O

- </ . w a -

E '

5

- 2.

"U E 2

,, O

_ o o w m m.- aum T= h 44

== em W D

_ Z m

~

_ g

/ c

_ .. ,., . ~ -

8

, n - -

N

=

I o

.c 2

~ c.

O c

- v= o

~ M

~

w.

- O i

- C i

- .9

- 13A37 N g

4 E 31svio3130 WnnlN!W s~ \ U 8

% .m.

llll l l l l lll \ l I l  !  !!!! ! i "o -

. . - e

% o e 'o =

- - - - .e '.

W3W B-25

'* ' ' ~

M

__, , _- - -A -6 _ _ - - -w - ,

7

'..S~ -

S*e __ *

[N ~

i ,

I I

. '.. L' t

Il FIGURE B-12 l

TM.0 i

l 1

i 30.0 e

20.0 j e  ;

C 15.0

[ '

u.

2 i 0 10.0 g i E 7.0 /

C u

5.0 g 3.0

/

2.0 /

1.5 l( ,

l l

1.0 --

9 2 3 5 10 15 20 30 50 M 100 INHALATION DURATION, HOURS l

Figure B.12 Correction factors for cloud immersion times longer than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

l l

l l

l l

B-26 b,_. _ . . . . .. . . . _ - ._

= .

1 e

to

~

i Figure B-13 t

k Location V,

y ,

l k 4

Time (Air Sample) s Date j, Area Reading at 4' c/m .l

Area Reading at 6" c/m 2 1

EVALUATION i e '

Location i Reading (at- )- c/m I

, Canister c/m Adsorber c/m i Canister-particulate filter Time 1 Date l Figure B.13 Sample filter-adsorber canister label. .

B-27 . ..

rmer -. w. _ _--. _

-J_-. 'A e 4 es tik. .4 km 7' T A . Es - ,

rs $r . ,

l Appendix B. Bibliography

1. U.S. Nuclear Regulatory Commission.

Reactor Safety Study - An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014), U.S. Nuclear Regulatory Commission, Washington, D.C.

20555 (October 1975).

2.

C. Distenfeld and J. Klemish, An Air Sampling For Evaluating The Thyroid Dose Commitment Due To Fission Products Released From React NUREG/CR-0314, BNL-50881 (November 1978).

3.

C. Distenfeld and J. Klemish, Environmental Radioactive Moitiroing To Control Exposure Expected From Containment Release Accidents, t!UR BNL-50882 (November 1978). '

Iis 1

i 1

B-28 1

\ ** * = ,

,e I n.. w... 4 e-

,.4-z._.- -"

g

o

/

LILCO, February 13, 1984 CERTIFICATE OF SERVICE In the Matter of LONG ISLAND LIGHTING COMPANY (Shoreham Nuclear Power Station, Unit 1)

(Emergency Planning Proceeding)

Docket No. 50-322-OL-3 I certify that copies of j LILCO'S MOTION FOR

SUMMARY

DISPOSITION OF CON-TENTION 24.B (LETTERS OF AGREEMENT WITH THE DEPARTMENT OF ENERGY AND THE RADIATION HEALTH COORDINATOR);

LILCO'S MOTION FOR

SUMMARY

DISPOSITION OF CON-TENTION 33 (DOE-RAP MONITORING TEAMS COMMUNI-CATION);

LILCO'S MOTION FOR

SUMMARY

DISPOSITION ON PHASC II EMERGENCY PLANNING CONTENTION 45 (DESIGNATION OF DOE PERSONNEL);

LILCO'S MOTION FOR

SUMMARY

DISPOSITION ON PHASE II EMERGENCY PLANNING CONTENTION 46 (CONTINUED AVAILABILITY OF DOE-RAP RESOURCES);

LILCO'S MOTION FOR

SUMMARY

DISPOSITION OF PHASE II EMERGENCY PLANNING CONTENTION 49 (DOSE ASSESSMENT METHODS) were served this date upon the following by first-class mail, postage prepaid, or (as indicated by one asterisk) by Federal Express.

i z_

James A. Laurenson,* Secretary of the Commission Chairman U.S. Nuclear Regulatory Atomic Safety and Licensing Commission Poard Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Atomic Safety and Licensing East-West Tower, Rm. 402A Appeal Board Panel 4350 East-West Hwy. U.S. Nuclear Regulatory Bethesda, MD 20814 Commission Washington, D.C. 20555 Dr. Jerry R. Kline*

Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regt)latory U.S. Nuclear Regulatory Commission Commission East-West Tower, Rm. 427 Washington, D.C. 20555 4350 East-West Hwy.

Bethesda, MD 20814 Bernard M. Bordenick, Esq.*

David A. Repka, Esq.

Mr. Frederick J. Shon* Edwin J. Reis, Esq.

Atomic Safety and Licensing U. S. Nuclear Regulatory Board Commission U.S. Nuclear Regulatory 7735 Old Georgetown Road Commission (to mailroom)

East-West Tower, Rm. 430 Bethesda, MD 20814 4350 East-West Hwy.

Bethesda, MD 20814 Stewart M. Glass, Esq.*

Regional Counsel Eleanor L. Frucci, Esq.* Federal Emergency Management Attorney Agency Atomic Safety and Licensing 26 Federal Plaza, Room 1349 Board Panel New York, New York 10278 U. S. Nuclear Regulatory Commission Stephen B. Latham, Esq.*

East-West Tower, North Tower Twomey, Latham & Shea 4350 East-West Highway 33 West Second Street Bethesda, MD 20814 Post Office Box 398 Riverhead, NY 11901 l

l l

t

(

Fabian G. Palomino, Esq.* Ralph Shapiro, Esq.*

Special Counsel to the Cammer & Shapiro, P.C.

Governor 9 East 40th Street  !

Executive Chamber New York, New York 10016  !

Room 229 State Capitol James B. Dougherty, Esq.*

Albany, New York 12224 3045 Porter Street Washington, D.C. 20008 Herbert H. Brown, Esq.*

Lawrence Coe Lanpher, Esq. Howard L. Blau Christopher M. McMurray, Esq. 217 Newbridge Road Kirkpatrick, Lockhart, Hill Hicksville, NY 11801 Christopher & Phillips 8th Floor Jonathan D Feinberg, Esq.

1900 M Street, N.W. New York State Public Service Washington, D.C. 20036 Commission, Staff Counsel 3 Rockefeller Plaza Mr. Marc W. Goldsmith Albany, New York 12223 Energy Research Group 4001 Totten Pond Road Spence W. Perry, Esq.*

Waltham, Massachusetts 02154 Associate General Counsel Federal Emergency Management MHB Technical Associates Agency 1723 Hamilton Avenue 500 C Street, S.W.

Suite K Washington, D.C. 20472 j San Jose, California 95125 4 Ms. Nora Bredes Mr. Jay Dunkleberger Executive Coordinator New York State Energy Office Shoreham Opponents' Coalition Agency Building 2 195 East Main Street Empire St. ate Plaza Smithtown, New York 11787 Albany, New York 12223 Martin Eradley Ashare, Esq.

Gerald C. Crotty, Esq.* Suffolk County Attorney Counsel to the Governor H. Lee Dennison Building 3' Executive Chamber Veterans Memorial Highway State Capitol Hauppauge, New York 11788

-~

Albany, New York 12224 Ka6[A.fPfla Kdthy 56 8- "oc1* ** *Y Hunton & Williams 707 East Main L:reet Post Office Box 1535 Richmond, Virginia 23212 DATED: February 13, 1984 l

l

.,_