ML20206H125
| ML20206H125 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/05/1987 |
| From: | Linnemann R RADIATION MANAGEMENT CORP. (RMC), SUFFOLK COUNTY, NY |
| To: | |
| References | |
| CON-#287-3106 OL-3, NUDOCS 8704150265 | |
| Download: ML20206H125 (102) | |
Text
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UNITED STATES OF AMERICA 5
BRANCH NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
- - - - - - - - - - - - - - - - - - -x In the Matter of:
Docket No. 50-322-OL-3 LONG ISLAND LIGHTING COMPANY (Emergency Planning)
(Shoreham Nuclear Power Station, Unit 1)
- - - - - - - - - - - - - - - - - - -x DEPOSITION OF ROGER E.
LINNEMANN Washington, D.
C.
Thursday, March 5, 1987 ACE-FEDERAL REPORTERS, INC.
Stertotype Reporters 444 North Capitol Street p/
Washington, D.C. 20001 (202) 347-3700 s
Nationwide Coverage 800-336-6646 8704150265 870305 PDR ADOCK 05000322 PDR T
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- CR30072.1 1.
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l UNITED STATES OF AMERICA 2
NUCLEAR REGULATORY COMMISSION l
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 3
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _x 4
- i In the Matter of:
- la
$ Docket No. 50-322-OL-3 5 jl LONG ISLAND LIGHTING COMPANY (Emergency Planning) j (Shoreham Nuclear Power 6
Station, Unit 1) 7 ;i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _x 8
j DEPOSITION OF ROGER E.
LINNEMANN 9
Washington, D.
C.
10 Thursday, March 5, 1987 11
()
12 Deposition of ROGER E.
LINNEMANN, called for examination h
at the law officer of 13 l pursuant ot notice of deposition, l Kirkpatrick and Lockhart, 1800 M Street, N.W.,
Suite 900, at 14 !
9 2:15 p.m. before KATHIE S. WELLER, a Notary Public within and 15 for the District of Columbia, when were present on behalf of i
16 1 the respective parties:
I JAMES N. CHRISTMAN, ESQ.
i MARY JO LEUGERS, ESQ.
18 :
Hunton & Williams i
707 East Main Street 19 j P.
O.
Box 1535 J
Richmond, Virginia 23212 20 )
On behalf of Long Island j
Lighting Company.
3 I
21 j
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-- continued --
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'N E APPEARANCES (Continued):
2!
DAVID T.
CASE, ESQ.
l I
Kirkpatrick & Lockhart 3,
1800 M Street, N.W.
f Suite 900, South Lobby 4l Washington, D.
C.
20036 on behalf of Suffolk County.
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CONTENTS l
6 g- -
2 WITNESS EXAMINATION Roger E. Linnemann 3
by Mr. Case 4
4 EXHI BI TS l
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LINNEMANN DEPOSITION NUMBER IDENTIFIED l
7 Exhibit 1 30
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Exhibit 3 38 9
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PROCEEDINGS 2
Whereupon, 3
ROGER E.
LINNEMANN 4
was called as a witness and, having first been duly sworn, 5
was examined and testified as follows:
6 EXAMINATION 7
BY MR. CASE:
8 Q
Dr. Linnemann, this is the deposition in the 9
Shoreham licensing procedure before the Nuclear Regulatory 10 Commission in Docket No. 50-322 OL-3.
I'm David Case.
I'm 11 with the law firm of Kirkpatrick & Lockhart, representing 12 Suffolk County.
13 Would you just please state your name for the 14 record and your business address?
15 A
Roger Edward Linnemann.
Business address is 5301 16 Tacony Street, T-a-c-o-n-y, Box DS, Philadelphia 19137, 17 Q
What did you do to prepare for this deposition?
18 A
Not much, other than look at some data on 19 contamination.
20 Q
What data did you review?
21 A
I just reviewed data on akin dose from 22 contamination.
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Q Did you look at any other documents?
2 A
No.
3 Q
Did you have any discussions with anyone?
4 A
No, other than my staff.
5 Q
Okay, did you have any discussions with counsel?
6 A
Yes.
7 Q
At this time, are you aware of any other witnesses i
8 who will testify in this hearing concerning reception 9
centers?
10 A
No, sir, I'm not.
11 Q
Have you had any discussions with anyone, either
{}
j 12 over the telephone or otherwise, who you believe to be or 13 will be a witness in the reception center issue?
14 A
No, I have not.
15 MS. LEUGERS:
Just a second.
I want to talk to 16 the witness.
17 (Discussion off the record.)
10 BY MR. CASE:
19 Q
After consulting with counsel, do yot have any i
20 changes in your answer?
21 A
No, she reminded me I have met some of the l
22 witnesses, but I have not had any discussions with them.
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Q Have you reviewed any transcripts from prior 2
depositions or earlier hearings concerning the Shoreham 3
nuclear power plant to prepare for this deposition?
4 A
I reviewed my transcript from when I appeared as a S
witness in the 1982, I believe, hearings at Shoreham.
6 Q
What was the subject matter you testified on at 7
that time?
8 A
At that time, I testified on the emergency medical 9
assistance program for accidents to employees on-site at i
10 Shoreham.
(
11 Q
You have been identified as a witness in this 12 proceeding on reception centers.
What issues will you be 13 addressing in this proceeding?
14 A
The major issue is the radiation effects.
15 0
Anything else that you are aware of that you will 16 be addressing?
17 A
Not specifically.
18 Q
When you say not specifically, is there anything
?
19 generally?
20 A
Not really, no.
21 Q
When you say radiation effects, what do you mean 22 by that?
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1 A
Effects of radiation on the human oody, whether it 2
is total body, deep organ effect or skin effect.
3 Q
What do you intend to testify about concerning the 4
radiation effects in the reception centers?
i 5
A I haven't written my testimony yet, but generally, 6
it will be in the area of effects of radiation on the skin 7
from contamination, and effects of radiation on the body as a 8
whole from contauination.
9 Q
What about the effects of the radiation on the lo skin?
Maybe you can educate me a little bit.
What is the 11 ef f ect -- well, let 's back up.
}
12 One of the issues that has been identified in the 13 case is the length of time it would take to arrive at the 14 reception centers fron wherever one was evacuated, and would 15 that increase health risks because of that length of time.
16 Have you formulated any opinion on that?
17 A
i have, and I don't believe, in my opinion, that 18 the length of time is material from a biological point of 19 view in contributing to additional exposure to a person.
20 Q
Why do you say that?
21 A
Decause primarily, if you look at the geometry of 22 radiation exposure and the contribution of the various Act!.FliDliRAl, Rt PonTrins. INC.
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factors that contribute to dose to the skin or total body, 2
what's on the skin itself turns out to be a small part of 3
that total contribution.
4 Q
What else contributes to the total dose, I believe 5
you called it?
6 A
If you have a person that is removed from an area 7
that has a plume or radioactivity going over that area, this 8
person will receive their dose from the sky shine or the 9
plume.
They will receive their dose from deposition of 10 radioactivity on the ground and from inhalation.
Those are 11 the three primary routes of dose contribution.
When you look
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12 at that picture, the amount that's on the body due to the 13 body surface turns out to be a small fraction of the total 14 doce, and I would say biologically it is not significant.
15 Q
What fraction is it of the total dose, or can you 16 generalize?
17 A
It would be a small fraction, in the area of one, 18 two percent.
19 Q
And the length of time between receiving your dose 20 on the skin and the time when you, an individual, is 21 ultimately decontaminated, is that of any relevance 22 biologically in terms of dose?
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A Not really.
Again, it is a small fraction of the 2
total amount, so that time is not the particularly primary 3
factor.
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Q Is time a factor when you have taken your dose, at 5
least partially, through inhalation?
6 A
I'm not sure I understand the question.
7 Q
The time between, let's say, when you have taken 8
your dose, and identification that you are in fact t
9 contaminated.
10 A
Could you rephrase that?
11 Q
Well, let's start more elementary.
Maybe I don't
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12 fully understand all of the processes here.
13 Assuming one has been contaminated, and you can
-14 receive your dose, as I understand it, in one of three ways, 15 from what you call the sky, through the ground or through 16 inhalation.
17 A
Yes.
10 Q
Is there -- and there's a time lag between when 19 you take your done and when you are identified as having had 20 such a done.
Let's start, how is one generally identified to 21 have exposure to radiation like this?
22 A
Well, the identification -- the dose that you have O
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1 taken is a dose -- and the definition of a dose is the 2
deposition of energy from the radiation.
You don't measure j
3 that later.
It is deposited in the body.
What you are l
4 measuring later is residual radioactive atoms on the skin, 5
and that is a different situation than having absorbed 6
radiation, which is not detectable.
The radiation isn't.
If 7
it is high enough, its effects will be detectable.
8 Q
So one determines the effects of the absorbed dose i
9 of radiation by measuring the radioactive atoms that are left I
10 within the body or on the skin?
11 A
No, one determines the effects of absorbed 12 radiation by looking at various biological parameters, for 13 example, blood tests.
You measure residual radioactive 14 contamination by using an instrument.
Whether that i
i 15 contamination causes an effect is a different stage.
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16 Q
so absorbed radiation is measured through
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t 17 biological tests?
i 10 A
Testing, right.
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19 Q
And you measure residual radioactive contamination 20 with an instrument of some variety?
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21 A
Hight.
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22 Q
ilow significant is it medically -- let me rephrase f
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that question.
What is the medical significance of any time j
2 delay between the absorption of the dose or receipt of the 3
dose and the time at which, let's start with at its measure, 4
at which one measures the residual radioactive contamination?
5 A
We're getting mixed up here a minute.
I have to j
6 have you repeat that, because I think we're getting exposure i
7 and contamination mixed up.
1 0
Q All right, you may be right.
What's the medical 4
i 9
significance of the lapse of time between contamination -- La 10 that an appropriate word?
i 11 A
Right.
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12 Q
And the measurement of that contamination, if any?
13 A
What I think I tried to testify to before is that 14 the additional done that would be absorbed in the skin or the j
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15 body as a whole from the radioactive contamination that is on J
16 the outside of the body, on the skin, is a small fraction, i
i 17 biologically speaking, compared to the done that was absorbed 10 from having been in the contaminated area in the first place; I
19 and that's the point I was trying to make, in that l
i 20 biologically that's not going to be significant in the e
21 overall dose absorption, absorption now.
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22 Q
Is it biologically significant in any other
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1 regard?
2 A
No.
3 Q
And you used the word biologically.
To your 4
knowledge, is it significant in any other way, 5
psychologically?
6 A
Psychologically, yes, it could be, depending on 7
the person's reaction to the whole affair.
l 0
Q In other words, some delay or some delay is 9
conceivably psychologically detrimental, although it may not f
10 be biologically detrimental, causing anxiety or whatever?
11 A
I'm certain there would be anxiety in this, yes.
12 Q
We have been talking about -- and you are going to 13 have to educate me on thin again -- we have been talking 14 about the done that you would receive from additional 15 exposure on the skin?
16 A
From additional contamination on the skin, right.
17 0
In other wordo -- lot me see if I understand this 10 correctly.
You have contamination on the akin, and what you 19 are saying in the additional contamination you would receive i
20 by a delay of time by having that?
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21 A
The additional exposure from the contamination on l
22 the skin.
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Is biologically insignificant?
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A Compared to the exposure the person got from t
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Q Okay.
Now, is ability to evacuate from the cloud 6
or exposed area, is the time in which you do that significant 7
biologically?
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Yes, it can be, depending on the nature of the 1
9 accident.
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10 Q
Okay, and what are the variables and the nature of f
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12 A
In general, the larger the amount of radioactivity 13 releaned, the higher the dose; and therefore, the time in l
14 important, to opend less time in that area.
15 Q
Now, is this a different situation -- let me back I
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I 17 Is there a difference between the exposure on your l
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k la skin, contamination on your ukin, and thyroid contamination?
19 A
Yes, thern la.
i 20 Q
What in that dif t'erence?
21 A
" Thyroid contamination," and that's in quoteo, 22 thyroid contamination or thyroid exponure mainly comen fron l
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inhalation of iodine, radioactive iodine, which is absorbed i
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2 in the blood and picked up by the thyroid gland because it 1
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has a propensity for concentrating iodine; so therefore, the l
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4 thyroid gland is getting its irradiation from radioactive j
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5 iodine atoms in the gland itself, because it concentrates it t
6 will be relatively higher dose than the exposure dose from 7
skin contamination.
8 Q
Okay, is there a medical significance to the time 9
between which one first receives thyroid contamination and 10 its diagnosis?
L 11 A
Again, the biological effects are relative more 12 proportional to the done, so it depends upon -- whether you 13 can detect biological effect depends on the dose.
The 14 thyroid contamination, as you say, or exposure, really major 15 part of that comes from inhaling or having been in the area.
16 Once you remove the person from the area, then there's no 17 longer a thyroid, additional thyroid exposure.
10 Q
okay, so annuming an individual is removed from 19 the area in which he han received this contamination, is 20 there any medical effect to any delay in identifying his own 21 personal thyroid contamination?
22 A
Again, depending on the done, yes, there are O
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guidelines for that, that at certain levels of exposure --
2 these are FEMA, I believe the State of New York has them also 3
-- that at certain levels you should protect the thyroid l
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4 gland with potassium iodide, and the sooner you give that the 5
better.
l 6
Q And thyroid contamination -- what's the better 7
word?
Is " contamination" satisfactory?
8 A
Incorporation of radioactive iodide in the ti roid 9
gland.
Some people say internal contamination, but thyroid i
1 10 incorporation of a radioactive iodide.
11 Q
That'e generally received through inhalation?
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l 12 A
The major part of that is inhalation.
There may 13 be some skin absorption, but most of it would be inhalation.
i I
14 Q
Would skin absorption ever cause what I will refer 15 to as thyroid contamination?
16 A
Again, it would be my opinion that the amount from 17 the skin absorption would be the small fraction of the amount la that you woul'1 inhale.
19 Q
Se eseentially, though, you can conceive of a 20 situation, iut it would be very remote, where just nimple 21 okin contamination wotild uitimately result in thyroid t
22 contamination?
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A No, because you would have to, in order to get the 2
skin contamination, you would have to come from an area that 3
had a lot of iodine first in the air, so you would always 4
have a higher proportion, fraction of the thyroid dose would 5
come from having been there in the first place.
6 Q
Now, to help me identify the consequences of this, 7
let me just try to construct a question along the following G
lines:
Assuming some skin contamination, and you are removed 9
from whatever it was that was contaminating you, the plume, I 10 queos, and you sit for 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> without being either 11 monitored or decontaminated, does that have a medical effect 12 on me or on the individual that's been so contaminated?
13 A
No, I think I testifled that the additional done 14 from that skin contamination from delay would be a small 15 fraction of the total done that was gotten from being in the 16 area in the firnt place, and would not be biologically 17 algnificant in contributing to the patient's effecto.
10 Q
Would that delay cause any othar medical -- would 19 there be any other medical effecto renultinq from that delay?
20 A
I don't think it would be significant.
21 Q
Any conceivably innignificant offecto?
22 A
No.
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1 effects it would be more than likely you could see it from f
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the 99 percent dose gotten here, and this 1 percent would not 3
change it.
It is not biologically titrated that carefully.
I 4
Q In the opinion you just testified to, what's the l
5 basis for that opinion?
i 6
A Calculations of dose from skin contamination 7
versus dose from having been in the area, from the cloud, 8
from the ground, et cetera.
9 0
Are such calculations compiled in a profesolonal 10 literature or --
11 A
There are people, physicista, who do that and 12 those calculations are made.
13 Q
You are obviously familiar with thore 14 calculations.
15 A
Yes.
16 Q
ilow did you become f amiliar with those 17 calculations; in it within your own practice?
10 A
Well, we have done skin calculations for many 19 reanono, for radiation, and this la just another one of physicints that do those kinds of 20 them.
.I have staff that 21 things.
22 0
Do they publish their resulta or la that an O
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in-house matter?
2 A
It is more or less part of their general knowledge l
3 of -- in order to practice in that profession, you know how 4
to calculate doses from radiation.
i 5
Q Okay --
[
6 A
There are books on it too.
L I
7 Q
All right, no in other words, there's Mt one L
0 manual that can give us the answer to this, because it 9
obviously depends upon your initial done?
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10 A
Yes, it dependa upon the accident parameters.
You 11 make some -- looking at ditterent inotopeo.
The method is a 12 pretty standard method for calculating doces.
13 Q
If you receive a small done initially, does the i
l 14 additional contamination you would receive from the skin l
15 resulting from a time delay, doen that become more
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l 16 uignificant or does it remain insignificant?
i l
17 A
Well, it would be hard to conceive of a attuation l
l 10 where you not a small doce here and a large done from 19 contamination, because there's a relationnhip to the amount i
20 that fell on the ground here and the amount that fell on you
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21 here.
They should bn roughly the came por nquare centimeter, f
I 22 no I don't conenive of that altuntion.
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1 Q
So in other words, the proportion remains 2
relatively constant?
3 A
Exactly.
The higher it in here the higher here, 4
but still remains the anall traction of the total dose.
5 Q
llave you reviewed the LILCO plans concerning 6
reception centers at all?
7 A
No, I have not.
O Q
Do you have any understanding of the purpose of 9
the reception centern within the lit.C0 plant?
10 A
I have a general understanding of reception l
11 centero, of what thnir purposes are, and 1,ILCO'n la a similar 12 purpose.
13 Q
What'n that general underntanding?
11 A
That's where you collect people to survey, monitor 15 them, decontaminato it necennary, et cetera.
16 Q
Do you know any of the specifica about the plan, 17 the reception contor aspect of the plan for the Shoreham la tacklity?
19 A
only that they are -- I believo it to thren LII.C0 20 facilitico that they would use to gather thono people.
21 Q
Do you know theatr location vla-a-vin the plume 1
22 EPZ?
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A only roughly in -- they are approximately 30, 40 2
milen, I believe, from the plant, in that general area.
3 Q
Do you have any understanding of how many people i
4 will arrive at the reception centers?
l 3
A No, I do not.
6 Q
Do you have any understanding of the planning 7
basin in terms of percentages that are to arrive at the 0
reception center?
9 A
No, I do not.
l 10 Q
Is it your understanding that the reception 11 center.: are to be the locationn where evacueen are to be 12 monitored, and it necessary, decontaminated?
13 A
Yes, that's my understanding.
l 14 Q
In your estimation, should there be medical 15 personnel at the reception centers?
16 A
I would think that it is pretty ntandard, when you 17 accumulate people for whatever reason, that there in some 1
10 medical nursing or peopio t h e r e., the firnt aid station type 19 thing.
That noemn reasonable.
20 0
In termn of radiological analysen, is it helptul 21 to have nome nort of trained medical tornon thorn at a 22 recept ion conter like you undorn tand t hene to be?
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1 A
Yes, I think so, in terms of people who can use 2
instruments and survey for contamination.
I would think i
3 that's pretti standard for a reception center for this l
4 purpose.
S Q
I guess I didn't conceive of the simple use of 6
instrumento na being the kind of training.
Maybe my question 7
wasn't precise enough.
l 0
In there some -- should there be some nort of 9
medical professional, meaning a physician or a technician or 10 nurse who is well trained in identifying contamination, both l
l l
11 thyroid and skin contamination, and its effects at tho l
12 reception centern?
I L
11 A
I wouldn't think you would need nurnen to do
(
l I
l 14 that.
I think somebody should, a radiation technician, and 15 they are usually better trained and experienced at doing 16 that.
I don't think that you would need a nutso Jpecifically 17 to do the nurvey.
i 10 Q
You indleated that there was thyroid I
19 contamination.
Time dulayn in treatment are of some medicil l
i 20 nignificance?
[
21 A
It depends on the done to the thyroid gland.
f 22 Q
11u t at a certain 1cvel of doonce, then the time O
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delays in medical treatment can become nedically significant?
4 2
A Yes.
3 Q
What's that ;evel of donage?
4 A
Well, the gu~delinea an established and put out by 4
5 the FEMA, and which mor t states adhere t o, in that if you 6
expect the thyroid gland to get a dose o.t radiation, then 7
potassium iodide shoult be administered.
i 0
Q And I believe your words before were "the sooner i
9 the better"?
j 10 A
Yon.
i 11 Q
llow does one, in your expertino, generally l
12 decontaminate nomeone who han surface contamination?
4
{
13 A
cenerally, in my experience, surface contamination 14 in soap and water will remove it.
It to basic)11y
'i l
15 contaminated dirt, if you want, invisible dirt, and noap and I
j 16 water unually removen it.
17 0
In thoro nome nort of atindard procedure -- let'n j
la phrano it thin way, if you take a a,ower and wash and it
}
l 19 doesn't work, what next?
20 A
That's hard to con <'niva if, that you wouldn't get j
21 mout of Lt att just with ono shower, soap and water.
It i
22 would be pretty hard to concetvo that it wouldn't como off.
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Q Is it conceivabic at all that it wouldn't come 2
ott?
3 A
tiot really.
Not under the circumstances.
It 4
would be hard for me to conceive of that, under the 3
j 5
circumstances tha' you are talking about with contamination
)
6 from an air drop oltuation, that it wouldn't be easily i
i 7
deepntaminated with soap and water, j
y,
]
8 Q
What kind of circumstances would make nurface 9
decontamination beyond the ucope of soap and water, let's i
j i
10 n a */ ?
I i
11 A
You might -- I have seen it with, maybe, rubbing l
12 it in or nome heavy une of handa in working with contaminated 1
13 matettal, it may take two or three wanhings, but I have not j
i 14 noen a real problem with renidual contamination, even with I
I 16 WorkerM.
i i
[
16 Q
Junt for my own curionity, I read your dratt 3
c 17 article on Chernobyl, and you doncribed a certain group of i
l 10 people there, firnmon, who had avakod clothen and kept then l
I 19 on a certain period of time, causing prolonged exponure.
Is
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i l
l 20 that thn nort of circumstancon or doen that vio beyond nimple j
- l I
21 nkin contamination?
f 22 A
Yon, that'n beyond pimpin nkin contamination.
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1 What the problem there was in you get the contamination in a 2
burn, in a thermal burn, as they did, and that radioactive g
3 material gets bound up in the scar of the burn, so it may.not 4
wanh out very cantly.
In that circumstance, when the debris 5
that burn, they eventually remove it and that's what they did 6
in Russia.
You would have to have special circumstances like 7
that where you get residual contamination.
O Q
Any other conceivable circumstances you can think 9
of at the present, like somehow got rubbed in or prolonged 10 handling of contaminated materials?
11 A
Yes, it would have to be.
Gomething on that order 12 where that's the only place, and then, as I say, it unually 13 only took two or three decontaminations and it was removed.
14 When you have rough skin, things like that.
15 Q
Are you familiar at all with the equipment that'n 16 to be used at the decontamination -- or excune me, at the 17 reception centers?
10 A
No, I'm not.
19 Q
Monitoring equipment that'n to be used there?
20 A
only in general, I'm pretty famillar with 21 radiatton detection instruments and how they operate, their 22 ditteront manufacturern; they all banically are the same ACl! 171!DliitAl. Riinoit rims. INC, 2024 Mne moonole cinmge m )tt, u.u.
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1 principle.
2 Q
Assuming you had a vehicle with four passengers, 3
how long do you believe it would take to monitor them for 4
contamination?
5 A
I think it would depend on the situation, on how 6
many vehicles with four passengers, and generally, you 7
approach a contaminated situation, if there's large numbers, 8
you do quick surveys to establish absence or presence of 9
contamination, sort out higher levels from lower levels, and 10 then continue in that process, so that's the general approach A
11 to that.
If you had a vehicle you might check this one very V
12 quickly and find it is a small amount, and this one is 13 higher, so you sort them out quickly and then get down to the 14 more detail.
15 Q
Go the system you are describing here is some sort 16 of triangle system where you would separate out those that 17 were, say, more highly contaminated from those with minimal 18 contaminatlon, and those who had none?
$Y AQ 19 A
- Yes, It in called a radiological t4 + + n c4=.,
sort 20 ot a quick thing firnt.
21 Q
How would that be done, this triangle system?
You 22 have a man there with a monitor --
O Acit.17 intinal. Riti>onriins. INC
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A Again, I'm just describing to you in general.
I 2
don't know these plans specifically, but if I had 10 people, 3
I would first look at hands and feet.
That's the most common 4
place you are going to have it, and sort that way, and if you 5
don't find it there I would set them aside and go to the next 6
ones until I ruled out the contaminated /no contaminated, then 7
I would go back to those with hands and feet and check the 8
rest of the body as you have time.
9 Q
The rest of the body, what else would you check?
10 A
I would go head, face, and then generally the 11 whole body.
}
12 Q
In other words, chest, stomach, legs?
13 A
Right.
14 Q
This initial triangle that you described, in a car 15 with four occupants, each one of which would have to be 16 checked, I assume you would check the car briefly --
17 A
That would be first.
18 Q
How long would that take, do you estimate?
19 A
That would be hard for me to say.
A matter of how 20 long does it take to put an instrument in certain areas, and 21 it doesn't take long.
22 Q
Does it take a little bit of time to get a reading i
Acu FEDERAL RuronTnas, INC.
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2 A
No, it doesn't.
For a sort of go or no go, it is 3
there or it is not.
If you want to do a slower survey and 4
check everything, it probably takes a couple of minutes.
5 Q
On an individual?
6 A
on a person.
7 MS. LEUGERS:
I would like to clarify for the 8
record that you are talking in generalities and not about the 9
LILCO plant in these questions?
10 MR. CASE:
The questions I asked were the 11 questions I asked.
He indicated no familiarity with the 12 LILCO plant.
13 MS. LEUGERS:
I just wanted to have that 14 clarification.
15 BY MR. CASE:
16 Q
In this triangle system you described, or any 17 situation where there's some individuals who have surface 18 contamination and others who don't, is there any medical 19 effect of what's called the mingling with those who have 20' surface contamination with those who don't?
21 A
I would say, again, insignificant.
I don't think 22 you would have much dose contribution from that.
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ACE FEDERAL REPORTERS, INC.
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(.i 1
Q Would there be some?
2 A
Not compared to the total dose they received from 3
having been in the contaminated area.
4 Q
Assuming someone who had not been in the 5
contaminated area at all, and they were with, for a period of 6
time, say a car, with someone who was contaminated, sitting 7
next to them, is there some sort of medical effect on the 8
person who was not contaminated?
9 A
I wouldn't say there would be a medical effect.
10 There would be an exposure and that would depend on how much 11 contamination.
12 Q
The amount of the exposure would depend on the 13 amount of the contamination?
14 A
That's right.
15 Q
And the amount of contamination means whose 16 contamination?
17 A
The contamination from the person who was brought 18 out of the area, as I understand your question, and placed in 19 a car with somebody who was not in the area --
20 Q
Yes.
21 A
No.
22 Q
so in other words, there would be exposure, but n.
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ACE-FEDERAL REPORTERS, INC.
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I the amount of exposure would depend on the degree of 2
contamination of the individual?
3 A
On the person.
4 Q
Who was brought from the contaminated area?
5 A
Right.
6 Q
Is there any medical effect -- we have been 7
talking about surface contamination -- to having someone with 8
thyroid contamination -- and that may not be the proper 9
technical term, but for shorthand -- having them with people 10 who don't have thyroid or have any contamination?
11 A
You mean, if I understand you right, is there a
{}
12 significant or a problem of somebody with radioactive iodine i
13 in their thyroid gland exposing somebody who doesn't have 14 radioactive --
15 Q
Yes, who doesn't even have surface contamination?
16 A
No, and I base that on the fact that in hospitals 17 we give much, much higher doses of radioactive iodine l
18 purposely to treat thyroid disease or to study thyroids, and 19 many studies have been done on the family of these patients, 20 et cetera, and the exposure is insignificant.
l 21 Q
Have you seen a proposed revision to the LILCO t
l 22 plant concerning reception centers?
O V
l
/\\CE. FEDERAL REPORTERS, INC.
20.!-347-3700 Nationwide Coverage 800-336-6M6
30072.1 KSW 30
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1 A
No, I have not.
2 Q
It is estimated in there that 10 percent of the 3
population who arrives at the evacuation centers will require 4
showering for surface exposure or surface contamination.
Are 5
you aware of any basis for that?
6 MS. LEUGERS:
I would like to object.
If you have 7
a document that you can show the witness and give him a 8
chance to review that --
9 MR. CASE:
Sure.
Let me have marked as Linnemunn 10 1,
the following package of documents.
/~^
11 (Linnemann Exhibit 1 identified.)
'(
12 THE WITNESS:
What was the question?
13 BY MR. CASE:
14 Q
I have given you a copy of what has been marked 15 Linnemann 1.
16 A
Right, I have it.
17 Q
If you would turn to what I think is the second 18 page, actually the third page labeled at the bottom 3.9-5, 19 cap A, you go halfway down, the second paragraph has a 20 heading " Decontamination."
l 21 A
Yes.
22 Q
About halfway down there's a sentence in that
/\\CE FEDERAL REPORTERS, INC.
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~30072.1 KSW 31 (C/
1 paragraph that says, "It is expected that less than 10 2
percent of the contaminated evacuees would require full 3
showering."
Are you aware of any basis for that estimate?
4 A
No.
5 Q
You have described to me the effects of 6
radioactive contamination in terms of any delay in having an 7
individual monitor and your opinion as to that.
Do you 8
intend to testify on any other issue in this case?
9 A
No, not that I'm aware of.
i 10 MR. CASE:
Let me have this marked as Linnemann O
11 Exhibit 2.
d 12 (Linnemann Exhibit 2 identified.)
13 BY MR. CASE:
14 Q
Do you recognize this document?
15 A
I do.
16 Q
What is it?
17 A
That's my curriculum vitae, 18 Q
And is this a current curriculum?
19 A
It is.
20 Q
Did you prepare it?
21 A
I made the contributions to it.
My secretary 22 prepared it.
OV ACE FEDERAL REPORTERS, INC.
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(/
u.
1 Q
And not just contributions in the terms of you did 2
all these wonderful things, but you supplied her with the 3
information?
4 4
A Right.
5 Q
On the first page, it indicates that from 1986 to 6
the present, you are president of Radiation Management 7
Consultants?
8 A
Right.
9 Q
And from 1969 to 1986, you were president /CEO of 10 Radiation Management Corporation.
What's the difference 11 between Radiation Management Consultants and Radiation 12 Management Corporation?
13 A
Radiation Management Corporation was a larger and 14 more diverse organization than Radiation Management 15 Consultants.
In both -- Radiation Management Consultants 16 confines itself to emergency medical preparedness and 17 training of hospitals and other personnel for handling 18 radiation accidents.
Radiation Management Corporation did 19 that, plus radiological large environmental laboratories, and 20 still has, biological laboratories for studying terrestial 21 and aquatic organisms around a nuclear power plant.
So it 22 was a much larger, diverse organization.
Radiation ACE FEDERAL REPORTERS, INC.
202-347-3700 Nationwide Coverage 83)-336-6M6
30072.1 KSW 33 a
1 Management Corporation was sold to Canberra Industries in 2
1982, and I just repurchased in 1986 the medical part.if it 3
back and renamed it Radiation Management Consultants -- and I 4
see an error.
President / chief executive officer should be 5
1982, 1969 to 1982.
6 Q
And from '82 to present you have been --
7 A
'82 to
'86, I was vice-chairman of Radiation 8
Management Corporation, which was a wholly owned subsidiary 9
of Canberra Industries, so that needs to be corrected.
Thank 10 you.
11 Q
And what is Canberra Industries?
12 A
They are in Meriden, Connecticut.
They are 13 designers and manufacturers of radiation detection 14 instruments.
15 Q
And is Radiation Management Consultants a 16 corporation?
17 A
Yes.
18 Q
Who are the stockholders?
19 A
Myself and my son.
20 Q
Does Radiation Management Consultants have any 21 contract with LILCO?
22 A
Yes.
r
/\\CE FeoERAL REPORTERS. INC.
202-347-3700 Nationwide Coserage 80 4 336-6646
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Q What is that contract?
2 A
It is a contract to provide emergency medical 3
support in the event of an accident to employees on-site, 4
radiation injury to employees on-site, and also to maintain 5
their emergency medical assistance program for the same.
6 Q
Turn to the second page.
Under the professional 7
appointments, from 1982 to the present, it indicates you have 8
been a member of the American Medical Association Council on 9
Scientific Affairs, Subcommittee on the Management of 10 Radiation Accident Victims.
What does that position on that
/~s 11 subcommittee entail?
U 12 A
Oh, that was a subcommittee that was put together d
13 by the AMA to write a manual for -- a generic manual for
![
{n 14 hospitals to set up procedures for handling radiation 15 injuries.
16 Q
And was such a manual written?
17 A
It was.
There were a number of people on that 18 committee.
19 Q
Is that listed as part of your publications or --
20 A
No, it wasn't -- all of us contributed.
It was a 21 manual made by a committee, not any one person.
22 Q
What's the name of the manual?
O
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ACE FEDERAL REPORTERS, INC.
202-347-3700 Nationwide Coverage 800-33&6M6
ll 30072..
KSW 35 s
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1 A
Management of radiation -- Hospital Management of 2
Radiation Injuries, I believe.
I could get that name for you 3
if you would like.
4 Q
And you also, since 1979 to the present, have been 5
appointed to the Health Physics Society's Standards 6
Committee.
What does that entail?
7 A
That was a committee set up by the Health Physics 8
Association to write a manual for hospitals to use, a generic 9
manual for them to use in establishing a program to handle 10 radiation injuries.
11 Q
And did that manual get written?
12 A
No, that one is still in progress.
13 Q
I won't ask you why one got done and the other one 14 didn't.
15 A
No.
l 16 Q
If you would turn to the presentations portion of l
your resume or curriculum, I believe it is page 4, just for 17 i
18 my own information, what does DWK stand for?
l 19 A
DWK is a German company, firm.
j 20 Q
Is that what's listed under 1978, Deutsch 21 Gesellschaft --
l 22 A
Wait a minute.
Maybe we have it here.
- Yes,
('T
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202-347-3700 Nationwide Coserage 800-336-6M6
1 30072.1 KSW 36 I
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that's the one.
That's it.
2 Q
Okay, it is --
3 A
Same one, i
4 Q
It's a German corporation?
5 A
Yes.
It is a company that is primarily concerned 6
with disposal of radioactive wastes.
7 Q
Under 1982, you have a presentation to the Health 8
Physics Society annual meeting in Las Vegas, Nevada, a 9
keynote speech entitled " Medical and Public Health 10 Consequences of an Off-Sit Release of Radiation from Nuclear
< ~3 11 Power Facility."
's_s' 12 A
Yes.
13 Q
Is that address available publicly?
14 A
No, it was a keynote speech I gave, 15 Q
Do you know if it has been reduced to writing in 16 any form?
17 A
Not really, no.
I have some notes on it.
It was 18 mainly given verbally.
/'~'*
19 Q
If you would turn to the last page, please.
My 20 professional testimony.
In 1984, you apparently testified in 21 the Limerick Nuclear Generating Station.
What was the 22 subject of the testimony?
f~')%
~. _ -
ACE FEDERAL REPORTERS, INC.
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1 30072.1 KSW 37 O(_/
1 A
It was Limerick's emergency medical plan for 2
handling on-site radiation injuries.
3 Q
And in 1985, the Cleveland Electric Illuminating 4
Company emergency planning hearings, what was the subject of 5
your testimony there?
6 A
The same.
7 Q
On-site planning?
8 A
Plans for handling radiation injuries on-site.
9 Q
And the John Benek versus Pennsylvania Power 10 Company, et al. --
/~')
11 A
That one is one of those cases that I have not
%)
12 heard about it in many years.
I guess it went away.
It was 13 one of those legal cases.
Started and faded.
14 Q
_ What was your testimony there, if you recall?
15 A
That, if I recall, had to do with somebody was 16 initiating a legal action against the power company because 17 he lived near the site and felt he was getting overexposed or 18 would get overexposed to radiation.
19 Q
In the Union Electric Company emergency 20 planning / licensing hearings for the Callaway nuclear plant, 21 what was the subject there?
22 A
Medical plans and management of on-site radiation O
/\\CEJFEDERAL REPORTERS, INC.
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j 30072.1 KSW 38 A(-)
1 injuries.
2 Q
And 1983, the Pennsylvania Power & Light Company, 3
Susquehanna Steam Electric operating license hearing, what 4
was that?
5 A
The same.
6 MR. CASE:
Let's take a short break at this time.
7 (Recess.)
8 (Linneman Exhibit 3 identified.)
9 BY MR. CASE:
10 Q
Dr. Linneman, the court reporter has marked what I 11 believe is Linnemann Number 3, a document entitled " Soviet 12 Medical Response to Chernobyl," by Roger Linnemann, M.D.
Do 13 you recognize this document?
14 A
I do.
15 Q
What is it?
16 A
It is an article I wrote to submit it to the 17 Journal of the American Medical Association for possible 18 publication.
19 Q
As I recall, this grows out of a conference that 20 was held concerning the Soviet medical response to the 21 Chernobyl incident?
22 A
Right.
O ACE FEDERAL REPORTERS, INC.
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30072.1 KSW 39
[ ')
%/
1 Q
If you would turn to page 21, the third phase of 2
medical response, you identify or discuss 450 medical 3
brigades which were sent to Chernobyl, each consisting of a 4
physician, nurse and radiation technician, and these brigades 5
attended to evacuees and site personnel who had not received 6
doses of radiation sufficient to cause symptoms and 7
hospitalization.
Do you know how they attended to these 8
evacuees, these medical teams?
Was that discussed at all?
9 A
They did a number of things.
They surveyed for 4
10 contamination and decontaminated where necessary, or gave 11 them clean clothing where necessary.
They checked their 12 thyroids for radioactive iodine, and they administered 13 potassium iodide, were the main functions they did.
Those 14 are the main functions.
15 Q
It indicates that these brigades examined 135,000 16 evacuees and 100,000 children for a total, I guess, of 17 235,000 roughly?
J 18 A
Yes.
19 Q
Do you know how long it took them to accomplish 20 their mission of examining and decontaminating these people?
21 A
These people were evacuated after different times 22 from a period, probably a total period of about 10 to 12 n
v ace FEDERAL REPORTERS, INC.
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V 1
days.
2 Q
So it took the teams at least 10 to 12 days?
3 A
Yes, because that's how the evacuees were brought 4
in over that period.
5 Q
okay, and in the next to last sentence, it says 6
"In the first weeks over 100,000 thyroid scans and blood 7
counts and more than 100,000 whole body counts were 8
performed."
9 How long does it take to do a thyroid scan?
10 A
In terms of minutes.
11 Q
Minutes?
12 A
Yes.
13 Q
What is a thyroid scan?
14 A
You put a radiation detector over the thyroid 15 gland and measure the radiation that comes from the thyroid 16 gland.
17 Q
Why does it take minutes?
18 A
Because it is usually all you need.
19 Q
Okay.
It is a matter of minutes rather than 20 seconds?
21 A
Yes, I would say.
22 Q
On the same subject of monitoring, if you had four O
ACE FEDERAL REPORTERS, INC.
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, ~.
1 individuals in a car, an automobile, and we did this initial 2
triage system you have described, how long would it take, 3
roughly, to triage those four individuals in the automobile, 4
that initial scan, checking hands and feet of the 5
individuals?
6 A
Minutes.
7 Q
Minutes?
8 A
Yes.
For probably all four of them, you just 9
check hands and feet.
10 Q
So if you just checked hands and feet for the four 11 of them, it would take minutes, you believe?
bT 12 A
Yes.
13 Q
In your estimation, would it be an appropriate 14 method to simply monitor the car and the driver and not the 15 other three individuals?
7 16 A
Yes, that would be one way of doing your initia jY f-LOnt) 17 ngl e, depending, once again, on how many people you h 18 to monitor.
19 Q
But if you did that sort of initial triangle you 20 would then want to go back and monitor the other three 21 individuals later?
22 A
I would think so, yes.
O l
/\\CE. FEDERAL REPORTERS, INC.
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1 MR. CASE:
I have no further questions.
2 MS. LEUGERS:
We have no questions.
3 (Whereupon, at 3:30 p.m.,
the deposition was 4
concluded.)
S e0. p. -1AAA/L% & 6 7 ER E. LINNEMANN 8 Subt:(,be6 TM S*C" 3L Db' ggt:.) C1 / 10 l l.L >pgd.ic w gg,g y 11 (~# ^ ission EX9 Io, # / I 12 NY woon52$jC[p$,fpna sgELLWO f c3 patch 25p 13 p 14 15 16 17 10 19 20 21 22 Ad ace FEDERAt. REPonTEns, INC. l 202 347-370) Nationwide Gncrage Mo-33MM6
CERTIFICATE OF' NOTARY PICLIC & REPORTER 43 I, KATHIE S. WELLER the officer before whom the foregoing deposition was taken, do hereby certify that,'the witness whose testimony appears in the foregoing deposition was duly sworn by me; that the testimony of said witness was taken in shorthand and thereafter reduced to typewriting by me or under my direction; that said deposition is a true record of the testimony given by said witness; that I am neither counsel
- for, related to, nor employed by any of the parties to the action in which this deposition was taken;
- and, further, that I am not a relative or employee of any attorney or counsel i
i ,m. L) employed by the parties
- hereto, nor financially or otherwise interested in the outcome of this action.
i I WJ Notary Public~in and for the District of Columbia My Commission Expires NOVEMBER 14, 1989
4.2 Receotion Center The LILCO Operation Centers in Bellmore, Hicksville, and 73 () Rosyln are the designated general population reception These facilities are located approximately 40 centers. miles from Shoreham as detailed on Figure 4.2.1. Traffic guides will assist with traffic flow on the facility grounds. Monitoring stations will be set up in the facility parking lots to monitor evacuees arriving from the EPZ. Trailers, equinped with showers and sinks, will be used for decontamination of evacuees found to be contaminated. These trailers will also be used for equipment storage. OPIP 4.2.3 details the activation, layout and operation of the reception centers. All waste water from the decontamination trailers will be collected and contained in collapsible storage tanks. These tanks are sized to enable full-flow operations of the trailers for a period of 24 hours. Upon termination of the emergency the Recovery Action Committee will make arrangements for transportation of all potentially contaminated liquid and solid wastes to Shoreham. O i 4.2-1 DRAFT O 2/20/87 f%% Qo l
t m:nitoring will oithsr rgmsin at tho Emargsney Worker Decontamination Facility for possible reassignment, or may be released from duty, depending on his/her organi-i zational affiliation or the situation at the time. 5-Public Exposure Control Evacuees arriving at the reception centers will be monitored i within approximately 12 hours. Arriving vehicles will be i monitored by 3 personnel with sensitive radiation detection l equipment. A Traffic Guide will take a smear swipe of the auto-mobile hood and wheel well and the two monitors will check for radiation on the vehicle swipe and hands, feet, head and shoulders of the automobile passengers. If no contamination is found above i acceptable limits, then a " Clean Tag" will be attached to the car. Should contamination above acceptable limits be found, the vehicle will be directed to a decontamination area where the l vehicle and all passengers will be monitored for contamination. i Evacuees will be directed to trailers where they will be monitored for surface and thyroid contamination in accordance with OPIP 3.9.2. Trailers at each facility are equipped with sinks and showers to perform decontamination procedures. Paper overalls and booties will be available to replace any contaminated l i clothing. The evacuees will be issued " Clean Tags" after being remonitored and having been found not to have any contam-ination or thyroid contamination above acceptable limits, will be directed to hospitals capable of providing further medical i treatment. () i Evacuees requiring shelter assistance will proceed to congregate { care centers after having received a " Clean Tag". i 7 The American Red Cross will designate which congregate care i centers are to be activated and will operate them in accordance with their own procedures, I t The planning basis for the general population reception centers is as follows: L l Monitoring - Ih accordance with FEMA Guidance Memorandum of Richard K. Krimm dated December 24, 1985, emergency preparedness plans should include provisions at relocation center (s) in the form of trained personnel and equipment to monitor a minimum of 20 percent of the estimated population to be evacuated. For highly improbable radiological releases, in which it may be necessary to monitor more than 20 percent of the population, it { would be expected that ad hoc measures would be developed, supple-j mented if necessary, by federal and private sector resources, 1 i LERO complies with this guidance by providing 56 monitoring } stations. Since it requires approximately 100 seconds for each vehicle to cycle through a monitoring station, over 30% of the estimated 58,000 EPZ vehicles (summer population) could be () 3.9-5 DRAFT l 2/20/87 1 r i r ____.,,._.._.__,_____,_-,.__.,_,_mm.
t:nitorcd ct tha rscoption ccntors within approximately 12 hours. Should a greater number of evacuees require monitoring, LERO will request that additional trained monitors with equipment be provided by INPO. stations, established at the three reception centers.These monitors will m (]) If despite these efforts monitoring will still take more than about 12 hours, the Reception Center personnel will be directed to monitor only the vehicle and driver of the car if all the passengers traveled together. This should provide sufficient expediting to allow all EPZ vehicles to be monitored in approximately 12 hours. Decontamination - Neither NUREG 0654 nor any FEMA guidance memor-anda provide any indication of how many evacuees may need decon-tamination. NUREG 0396 recommends, however, that no special local decontamination provisions for the general public~~ equipment or property (e.g. blankets, changes of clothing, food be provided. If contamination is found on evacuees, special showers) , it is likely to be easily removable due to the dust-like nature of the partic-ulates and decontamination should be simply a manner of removing outer layers of clothing and/or washing of exposed skin surfaces. It is expected that less than 10% of the contaminated evacuees would require full showering. LERO has provided at the reception centers a total of four decon-tamination trailers containing a total of 36 sinks and 80 showers. buildings if needed, Additional sinks are available within the nearby LILCO p)s In the highly unlikely event of a radiological release causing (_ contamination of evacuees, LERO will first rely upon its own decontamination capacity. Should this not be adequate to respond to the situation, LERO will attempt to enlist the support of government and private resources that may be made available and provide necessary interface to effectively utilize these resources and facilities. If despite best efforts additional facilities don't adequately meet the need, LERO will recommend that those evacuees requiring congregate care proceed directly to their evacuation not destination and take showers and change into clean clothing. The shower capacity at the LERO decontamination trailers, assuming 15 minutes to cycle an evacuee through a shower, is sufficient to process more than the 10% of the 32,000 evacuees requiring full showers who will be proceeding to the Congregate Care Centers. The reception centers will remain open in order to monitor non-congregate care evacuees, who have already showered, and wish to reassure themselves that no contamination is still present. i O 3.9-5A DRAFT 2/20/87
RECEPTION CENTERS It is anticipated that a majority of the people asked to evacuate their homes will seek temporary lodging with friends or (_) relatives, or stay at hotels and motels for the duration of an incident, particularly since a large percentage of Suffolk County residents migrated from the New York metropolitan area and have relatives who still reside there. However, for those individuals with no such housing alternatives available, reception centers have been established. Evacuees requiring assistance will be directed to the LILCO Hicksville, Bellmore or Roslyn Operations Centers. Figure 27.2 in Section IV shows evacuation routes from the EPZ to these three Reception Centers. Figures 7.2, 7.3 and 7.4 show traffic flow in the immediate vicinity of each of these facilities. OPIP 4.2.3 details access control and vehicle and evacuee flow on the reception center's grounds. At these f acilities, evacuees will be monitored by LERO and assigned to Congregate Care Centers by LERO or the American ited Cross. l In establishing these reception centers, it became more advantageous to use several large f acilities as opposed to numerous small locations such as local schools. In minimizing the number of locations, it became easier to maintain control over evacuation routes and to provide supportive services (monitoring and congregate care assignment) for evacuees. The selection criteria used in choosing appropriate reception centers were as follows: Adequate distance from the EPZ boundary o Reasonable highway access o On-site security o 111-37 DRAFT - 2/20/87 l - - - - - - ~ - - - - - - - - - - - - - - - - - - - - \\
OPIP 3.6.1 Page 2 of 44 r~ ( j) 3.0 PRECAUPIONS 3.1 The dose-saving effectiveness of protective actions can be influenced by many variable factors such as expected duration of releases, involved population, weather conditions, projected evacuation times, and plant conditions. Whenever possible, these factors should all b3 considered prior to the recommendation of protective actions. 3.2 Sheltering is the preferred protective action if sufficient ?cotection is offered by sheltering, or if no additional 3enefit is gained by evacuation. The evacuation of hospitals and nursing facilities should be sought as a last mecue since sheltering is the least disruptive to the patients. 3.3 The evacuation time estimates used in this procedure,, account for variations in road conditions, seasonal population and mobilization of traffic guides. The uncertainty in these values is + 1/2 hour. In addition, the evacuation time estimates are sensitive to evacuee compliance with recommended routes, traffic shadow beyond ten miles and road accidents. The effect r~S of these factors on the time estimates is detailed in (_/, Evacuation Time Estimate Sensitivity Study. This study should be reviewed by the Radiation Health Coordinator and Evacuation Coordinator. 3.4 If there has been a release of radioactive material, with the potential to contaminate evacuees, have evacuees f rom downwind zones report to their designated reception center for monitoring. Have the Coordinator of Public l Information convey this information to the public via EBS messages. 3.5 If decontamination of general public evacuees is required implement the following steps: a) Utilize decontamination facilities at the trailers. b) When Federal / State / County resources become available provide necessary interf ace to utilize these additional f acilities and resources, c) If it becomes apparent that additional facilities are needed but unavailable direct evacuees not needing Congregate Care to proceed to their evacuation destination. They should put their clothes in plastic bags and take a shower using luke warm water and mild soap. They should then put on clean clothes. Evacuees going to congregate care centers should continue to the reception centers for monitoring and decontamination. DRAFT - 2/20/87
OPIP 3.6.1 Page 2a of 44 O d) Keep the reception centers open so that evacuees who took showers at their evacuation destination can have themselves and their bagged clothing checked. Have the Coordinator of Public Information convey the appropriate advisories to the public. 4.0 PREREQUISITES 4.1 The Shoreham Nuclear Power Station has declared an emergency. i I O i i O 1 DRAFT - 2/20/87 i -.,---,--r- -,,.-.-e -. = c, -y v-- --r --,---ww-,-~. ~ y
OPIP 3.6.5 Page 9 of 60 /~' Start with the zones closest to Shoreham o and work outward. Provide for the Homebound before the o Health Care Facilities. If hospitals or Suffolk Infirmary are to o be evacuated, provide for them last. 5.'6.3 Contact Peconic Ambulance Service and talk to the Dosimetry Record Keeper. Find out how man'y vehicles are available and a. their capacities. b. Using Attachments 1 and 2, assign pickups and reception facility to the vehicles available. Have the Dosimetry Record' Keeper complete the Dispatch Form, Attachment 13, and dispatch the vehicle. c. Direct the Dosimetry Record Keeper to return to the Riverhead Staging Area when all the vehicles have been dispatched. 5.6.4 Have the Emergency Medical /Public Service Commu-nicators or other available personnel proceed O downstairs to dispatch the ambulances /ambulettes from the EWDF in the following manner: Obtain the Ambulance /Ambulette Packets from a. the EOC Equipment Store Room. b. Identify an available room, near the EWDF that can be used for briefing and dispatch, and have the Ambulance /Ambulette Drivers proceed there, Ensure that all ambulance /ambulette drivers c. have been issued dosimetry. d. The packets are in boxes marked by zone and vehicle type. Issue a packet and the number of Dispatch Forms, Attachment 13, equivalent to the capacity of the vehicle. Have the driver fill out the remaining information on the Dispatch Form and return Part II of the three part form to you. e. Remind them that their procedure is in their packet. When they return to Brentwood for monitoring, combine evacuees on a single O vehicle as appropriate prior to their leaving for the special population relocation centers. DRAFT - 2/20/87
r OPIP 4.2.3 Page 3 of 29 (~') \\' 5.1.4 Ensure proper manning is maintained at the reception centers. Additional personnel may be requested from INPO by the Director of Local Response. 5.1.5 If more than 30% of the evacuees identified in ! are directed to a reception center take the following accions: 4 a) Attempt to dispatch excess personnel and personnel from underutilized facilities to the over utilized facility. b) When INPO personnel become available direct them to the f acilities as needed. c) If despite best efforts it appears that monitoring will take more than 12 hours then direct receptions centers to use the backup method described in step 5.4.7. 5.2 Decontamination Coordinator 5.2.1 Upon declaration of a Site Area or General Emergency contact the facility managers at Bellmore, Hicksville and Roslyn. (Their (-)/ numbers are in the LERO phone directory.) phone i s, Inform them of the Shoreham emergency and that LERO personnel will be arriving to set up the facility as a reception center. Note: The Reception Center Supervisors have keys to each of the f acilities. 5.2.2 When the Reception Center Supervisors call in, obtain a manning status and find out if any problems exist with f acility activation. 5.2.3 Maintain contact with the American Red Cross Coordinator in the EOC. If the Red Cross Coordinator has not arrived, contact the Red Cross in Mineola at 747-3500. Keep the Red Cross informed of the emergency status. 5.2.4 When an evacuation is recommended, use 20% of the population in the evacuated zones shown in to estimate the number of evacuees needing congregate care. Provide this number to the Red Cross. O DRAFT - 2/20/87
OPIP 4.2.3 Page 4 of 29 g> 5.2.5 Obtain from the Red Cross Coordinator a list of Congregate Care Centers and in what order they will be activated if an evacuation is recommended. Based upon proximity and capacity determine to which Congregate Care Center each reception center is to send those evacuees requiring shelter assistance. 5.2.6 Contact each of the reception centers and inform them of the evacuation recommendation, and when they should begin to arrive. (Approximatel Hours after the evacuation recommendation).y 2 Inform each reception center to which Congregate Care Centers they should send evacuees requiring shelter assistance. 5.2.7 Contact the reception centers on a regular basis and request the status of the following information: o Manning o Facility Set Up Are evacuees backing up onto the public roads o (]) Number of evacuees going to congregate care o centers and status of map distribution Number of evacuees requiring decontamination o and the zones from which they came o Any additional support recluired including additional monitors provid ed through INPO o Obtain status of LERO bus arrivals (Hicksville reception center only). Keep the Health Services Coordinator informed of the reception center status, i 5.2.8 Uhen contacted by a reception center Decontamination Leader with a request to assign an evacuee with contamination to a hospital do the followings Contact the Hospital Coordinator and have him a. contact hospitals near the reception center and request the placement of contaminated evacuees. Ensure the hospital understands that the arriving evacuee has fixed contamination and does not present a serious concern of spreading contamination. /~T U DRAFT - 2/20/87
I OPIP 4.2.3 Page 5 of 29 -() b. When the receiving hospital has been identi-fled, contact the Decontamination Leader with the name and location of the hospital. 5.3 Reception Center Supervisors 5.3.1 Upon arrival at the reception center contact either security or the facility manager and inform him (her) of the Shoreham emergency. 5.3.2 Drive around the facility and see if there are any impediments to the reception center set up such as a LILCO truck or automobile parked out of place. If necessary have the impediment moved. 5.3.3 Direct all arriving LERO personnel to the decontamination trailer area or a nearby enclosed area to await inicial sign in and dosimetry distribution. 5.3.4 Have Dosimetry Record Keepers set up for registration and distribution of dosimetry in the decontamination trailer. When ready have the LERO personnel go through the trailer to sign in {} and pick up identification and dosimetry. 5.3.5 Using Attachment 2, Reception Center Personnel and Zone Assignment, assign personnel to the various reception center positions. Assign a Dosimetry Record Keeper to act as a communicator on the phone in the Decontamination Trailer. 5.3.6 Have the Decontamination Leaders set up their areas of the facility as shown in Attachments 3, 4 and 5. 5.3.7 Contact the Decontamination Coordinator regularly and provide him with the information detailed in Section 5.2. i 5.3.8 Provide offsite intersection diagrams and traf fic control equipment to Nassau County Police if they arrive. 5.3.9 Redistribute personnel and equipment among the reception center areas as necessary in order to meet evacuee monitoring demands. 5.3.10 During inclement weather, rotate people out of (:) exposeo areas. DRAFT - 2/20/87 1 i
OPIP 4.2.3 Page 6 of 29 5.3.11 If evacuees need transportation to a Congregate Care Center, arrange for a bus from Hicksville to provide transportation. 5.3.12 Establish additional monitoring stations, at secondary monitoring stations detailed in the facility diagrams, as INPO monitors arrive. 5.3.13 Upon termination of the emergency, deactivate the i reception center in accordance with Section 5.9. 5.4 Decontamination Leader Assigned to Initial Monitoring 5.4.1 Have personnel obtain equipment and set up the facility as shown in Attachment 3, 4 and 5. 5.4.2 A traffic guide will hand an information sheet to every entering vehicle. 5.4.3 Three people will man each monitoring station. Each team will consist of two monitoring personnel and one traffic guide. The vehicle and passengers will be monitored within approximately ) 100 seconds. 5.4.4 The two monitors will: a) Monitor the passengers in accordance with OPIP 3.9.2. b) When the traf fic guide presents a swipe check it for contamination. c) If no contamination is found, one monitor will put a clean tag (marked ' vehicle') under the windshield wiper; the other monitor will issue to the driver a clean tag (marked ' person') for each passenger. 5.4.5 The traffic guide assigned to the monitoring station will: a. Using one cloth, take a swipe of approximately one quarter of the front hood and one wheel well. Have the swipe checked by either montf or for contamination. The swipe may be reused until either dirty or contaminated. b. Write down the license plate number of the car and the number of passengers on Reception Center Record Form. Check of f on the form whether or not clean tags were issued. DRAFT - 2/20/87 i
OPIP 4.2.3 Page 7 of 29 () c. If clean tags were not issued, then direct the vehicle toward the decontamination area. d. If clean tags were issued then ask the driver if (s)he needs directions to a Red Cross Congregate Care Center. If yes, hand the driver a map. Direct the car toward an exit. If you begin to run low on maps, e. from the Dosimetry Record Keepers. quest more re 5.4.6 Ensure the traffic guides in your area understand their assignments and;are handling traffic flow correctly. Vehicles with more than six passengers or limited access should be directed to the monitoring stations identified on the facility diagrams. 5.4.7 If directed by the Reception Center Supervisor. expedite the processing of vehicles as follows: Have one monitor. check only the driver for a.- contamination. b. Have second monitor swipe vehicle exterior and issue clean tags if no contamination is found on either vehicle or driver. Traffic Guide will record license number and c. (]} issue map to congregate car center if required. d. If passengers did not travel together, monitor passengers from other locations. 5.5 Decontamination Leaders assigned to Decontamination 5.5.1 When directed by the Reception Center Supervisor initiate set up of the vehicle decon area and the decontamination trailer. Activation instructions for the trailers and waste water storage system are kept inside the trailer. The layout of the decontamination trailer is shown in Attachment 8. One side of the trailer will be designated for women the other side for men. Ensure a female monitor is assigned to the female side of the trailer. 5.5.2 When evacuees requiring decontamination arrive direct them to the vehicle decontamination area. Have the vehicle park in a designated spot. 5.5.3 Have the passengers leave the vehicle and proceed into the decontamination trailer. I DRAFT - 2/20/87 -[ . ~
i OPIP 4.2.3 Page 8 of 29 O (,j 5.5.4 While the passengers are in the trailer, monitor and decontaminate the vehicle in accordance with OPIP 3.9.2. If the vehicle cannot be decon-taminated place a contaminated vehicle tag under the windshield wiper. When the driver returns have a LERO worker in a paper suit drive the vehicle to a contaminated vehicle parking area. Use regular LILCO parking spaces for contaminated vehicle parking. If additional space is necessary park vehicles on the lawns. 5.5.5 Evacuees entering decontamination trailers will be monitored and decontaminated in accordance with OPIP 3.9.2. Issue clean tags to all evacuees with contamination below acceptable limits. 5.5.6 If there are a large number of evacuees awaiting access to the decontamination trailer, use the transportation building in Hicksville and Bellmore and the warehouse in Roslyn either as a holding area or for detailed monitoring and decontamination by removal of outer clothing. Establish a controlled entrance and exit and (3 designate a clean area as necessary. %) 5.5.7 If evacuees cannot be decontaminated below i acceptable limits contact the Decontamination Coordinator in the EOC. Request that a hospital be identified to accept a contaminated evacuee. When a hospital has been identified have the contaminated evacuee (s) drive themselves (if their vehicle is clean) to the hospital. Ensure that the evacuee has a copy of the Evacuee Exposure Record Form to take to the hospital. Tell the evacuee to enter the hospital via the emergency room entrance. 5.5.8 Ask the driver of cars issued clean tags if they l need a map to a Red Cross Congregate Care Center. If so, issue a map. 5.5.9 Have evacuees who do not have transportation to I use the LILCO district operations office as a temporary shelter until transportation to a Congregate Care Center can be arranged. Ensure the Reception Center Supervisor is aware of evacuees awaiting transportation. O'> DRAFT - 2/20/87 b n. , -,. ~ -,----a w,,
OPIP 4.2.3 Page 9 of 29 ( 5.6 Decontamination Leader assigned to monitoring evacuees arriving by bus at Hicksville. 5.6.1 Arriving buses will transport evacuees to the Hicksville Operation Center, northeast employee parking area, at the gate just north of the transportation building. 5.6.2 Evacuees will remain on the bus. Personnel at l this location will perform radiation monitoring checks and issue clean tags in accordance with OPIP 3.9.2. 5.6.3 If decontamination is necessary escort evacuee (s) to the decontamination trailers. 5.6.4 A dosimetry record keeper will have all bus evacuees sign out on the Clean Evacuee Log Out Form, OPIP 3. 9. 2, Attachment 4. 5.6.5 If Hicksville Operations Center has been designated as a Congregate Care Center then direct evacuees with clean tags to the check in area. 5.6.6 If Hicksville has not been designated as a Congregate Care Center, direct clean evacuees onto a bus that has been monitored. Give the bus driver directions to an activated Congregate Care Center. 5.7 Dosimetry Record Keepers 5.7.1 Uhen directed by the Reception Center Supervisor log in LERO personnel and distribute LERO identification badges. The LERO reception center roster is kept in the Decontamination Trailer. Set up a table in the Decontamination Trailer and route the LERO workers th rough. a. Request LILCO identification. b. Have LERO personnel sign and record the time of entry into the facility next to their name which is located under their LERO. job title on the LERO Reception Center Roster. If their name does not appear under their job title, have them fill in the required information in the space provided under their LERO job title on the Reception Center Roster. DRAFT - 2/20/87
OPIP 4.2.3 Page 10 of 29 (~') Issue green LERO badges to all the LERO c. Reception Center personnel. Instruct them that the badge is to be worn at all times in a visible place. 5.7.2 Issue dosimetry and Emergency Worker Dose Record Forms to all Reception Center Supervisors, Decontamination Leaders, Monitoring /Decontamina-tion and Traffic Guide personnel in accordance with Attachment 7, OPIP 3.9.1, Dosimetry and Exposure Control. 5.7.3 A Dosimetry Record Keeper will act as a communicator with the EOC and man the telephone in the Decontamination Trailer. 5.7.4 The Dosimetry Record Keepers (DRK) will handle dispatch to Congregate Care Centers as follows: The DRK communicator will receive, a. via phone, from the Decontamination Coordinator, a list of Congregate Care Centers activated by the Red Cross. b. () The DRK's will obtain maps, stored in the trailer, for the identified Congregate Care Center and distribute them to the Traf fic Guide at each monitoring station and the j Decontamination Leader at the decon trailer. Note: The number of maps provided is proportional to the capacity of the Congregate Care Center. When all the maps to a facility have been distributed by the Recorders, the Congregate Care Center is f ull. Regularly check with monitoring station c. Traffic Guides to ensure they are not running l low on maps. Contact the Decontamination Coordinator if it is necessary to activate additional Congregate Care Centers. d. If directing a bus full of evacuees to a Congregate Care Center give a map to the driver. Remove and discard 15 maps from your package to account for the extra people. (} DRAFT - 2/20/87
OPIP 4.2.3 Page 11 of 29 O \\/ If Hicksville is to be used as a Congregate e. Care Center have evacuees park on the f ront lawn and rear ball fields if additional space is needed. 5.7.5 When the emergency is terminated, collect all of the Clean Evacuee Log Out Forms and Reception Center Record Forms for transfer to the EOC Dosimetry Record Keeper. 5.7.6 At the completion of the emergency, bring the copies of all the completed Emergency Worker Forms and TLDs to the EOC Dosimetry Record Keeper. 5.8 Traffic Guides 5.8.1 Traffic Guides will be assigned to the posts designated in Attachment 3, 4 and 5 to facilitate the flow of traf fic through the reception center. 5.8.2 Follow the instructions in your Reception Center Traf fic Guide Procedure Attachment 7. 5.8.3 Traffic Guides at the Reception Center entrances (]) will hand out information sheets. 5.8.4 Traffic Guides assigned to monitoring stations l will implement Step 5.4. 5.
- 5. 9 Termination of Emergency and Deactivation of the Reception Center 5.9.1 If the emergency is terminated without an evacuation recommendation, inventory and repack all the emergency equipment.
Notify the Decontamination Coordinator at the EOC and LILCO facility management that you are leaving. 5.9.2 If an evacuation has been recommended, contact the Decontamination Coordinator, inform him that the evacuees are no longer arriving at the Reception Center and that you are ceasing monitoring and decontamination operations. Request that the Recovery Action Committee make arrangements for transportation of potentially contaminated water from liquid storage waste system and solid waste to Shoreham for disposal. O DRAFT - 2/20/87 l
OPIP 4.2.3 Page 15 of 29 Page 1 of 1 RECEPTION CENTER PERSONNEL AND ZONE ASSIGNMENTS l FACILITY 1 Positions -l Bellmore Hicksville Roslyn 1 Reception Ctr. Spyr. I 1 1 Area A Area B. Decon Ldr. Init. Mon. 1 1 1 1 l Init. Hon. Pers. { 28 1 28 3A l 26 l 1 Traffic Guides 14 1+ 14 14 l lDecon. Ldr. Decon. l 1 d 1 l 1 l I Vehicle Mon /Decon 3 6 2 Evac. Mon /Decon 10 20 8 i i Decon Ldr. - Bus l l l 1 Init. Hon. Pers. 1 l Traffic Guide l 12 i l 2 l Ii { Dos. Reed. Keepers 2 l 4 2 l l l Traffic Guide Onsice 10 18 l 7 TOTAL l i l 70 l 1 57 l tA Il i i t i l I I i i i I i Zones Assigned to i K-40,600 l Each Reception Center,1 N-ll,500 F - 29,000 A-5,400 l G-8,300 B - 3,800 l l and Total Population l IH-2,100 l C - 5,300 I l of Each Zone i II-1,600 D-600 l l l l L-7,200 1 Note: E - 4,900 1 l l Number of evacuees lM-7,600 l J - 4,600 i 0-5,000 Q - 7,900 requiring congregate P-5,500 l care is approximatelyl 20% of zones i R-6,900 l l S-1,700 evacuated. l l l l l l l 1 I I _I O DRAFT - 2/20/87
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OPIP 4.2.3 Page 23 of 29 Page 4 of 4 ) HICKSVILLE RECEPTION CENTER TRAFFIC FLOW AND ACTIVATION DIAGRAM (continued) RECEPTION CENTER TRAFFIC CONTROL POSTS (continued) Traffic Number of Control Traffic Post Location Guides Strategy HG-9 Vehicle Decontamin-1 Direct vehicles to decon-ation Area camination area and coordinate parking. HG-10 LILCO Property 1 Assist right hand turn of Access Road vehicles coming f rom Old Country Road and merge two lanes into one. Merg two lanes coming from New South Road into one lane and direct through gate. HG-11 LILCO Property Access 1 Assist exiting traf fic. A Road U HC-12,13 Hicksville Office Bldg. 2 Direct buses to monitorin. Northeast Employee area of gate just north o Parking Lot transportation building. HG-14,15 LILCO Storage Areas 2 Direct incoming vehicles toward available monitoring stations. Maintain separation of traffic heading toward decon area. HG-16 LILCO Employee 1 Direct incoming vehicles Parking Area toward available monitoring stations. Maintain separation with exiting vehicles. HG-17,*d LILCO Storage Area 2 Direct vehicles without clean tags toward decon area. Direct vehicles with clean tags toward exit. O DRAFT - 2/20/87
OPIP 3.9.2 Page 1 of 49 OkJ OPIP 3.9.2 RADIOLOGICAL MONITORING / DECONTAMINATION OF EMERGENCY WORKERS AND EVACUEES 1.0 PURPOSE To provide instructions for monitoring and decontamination of personnel, vehicles and personal belongings / equipment at offsite decontamination facilities. 2.0 RESPONSIBILITY 2.1 Decontamination Coordinator directs the efforts of the Decontamination Facilities. 2.2 Decontamination Leaders provide direction and coordination of the radiological Monitoring and Decontamination personnel at the facilities. 2.3 Monitoring / Decontamination personnel are responsible for implementing this procedure. 2.4 Responsibility for implementing portions of this procedure are as follows: (' Section Title 5.1 Decontamination Coordinator 5.2 Reception Center Supervisor or Decontamination Coordinator 5.3 Dosimetry Record Keepers 5.4 Monitoring Incoming Emergency Workers 5.5 Initial hanitoring at Evacuee Reception Centers 5.6 Monitoring Bus Evacuees and Special Population Evacuees 5.7 Expedited Monitoring at Evacuee Reception Centers 5.8 Decontamination of Evacuees 5.9 Vehicle Monitoring at EWDF 5.10 Vehicle Decontamination 5.11 Monitoring Equipment / Personal Articles 5.12 Decontamination of Equipment / Personal Articles () DRAFT - 2/20/87 n -,,,---%.--,w_,, .~w-------,, ..r --..,,- - +, -,- .---y-
l l OPIP 3.9.2 i Page 9 of 49 5.4.13 Send a copy of the Exposure Report Form with the individual to the medical facility. 5.4.14 l If monitoring showed the individual to be free of l both external and internal contamination, issue the individual a tag signifying that he is clean l (see Attachment 6). Direct the individual to the Dosimetr address,y Record Keepers to record his name, and telephone number on a Clean Emergency Worker Monitoring Record Form, see 5.4.15 The EWDF monitoring personnel will have LERO/LILCO family members bring their vehicle to the Vehicle Decontamination Area for monitoring prior to going through personnel monitoring. I 5.4.16 Emergency Workers will either remain at the Decontamination Facility waiting for reassignment or they will be released f rom duty. 5.5 Initial Monitoring Personnel Assigned to Evacuee Reception Centers !Q 5.5.1 Assist in set up of the Reception Center as detailed in OPIP 4.2.3. i 5.5.2 Obtain your dosimetry and fill our record forms l in accordance with OPIP 3.9.1. 5.5.3 Perform pre-operational checks of RM-14 in accordance with Attachment 1. 5.5.4 Determine background radiation levels in accordance with Attachment 2. 5.5.5 When monitoring for external contamination using the RM-14 with the HP-210 or HP-260 probe, ensure: l a. range selector is on XI position b. response time is fast volume switch is at maximum position c. d. alarm is set at 360 cpm above background. l 5.5.6 Each monitoring team will set up at the stations l detailed in OPIP 4.2.3. ^ (' T> DRAFT - 2/20/87 l
OPIP 3.9.2 Page 9a of 49 l() 5.5.7 Three people will man each monitoring station. Each team will consist of two monitoring personnel and one traf fic guide. l 5.5.8 The two monitoring personnel will l Position themselves on both sides of the a. monitoring lanes. b. Approach the vehicle when it comes to a full stop. Explain to the passengers in the vehicle that c. you are monitoring for possible contamination and ask for their cooperation. d. Each monitor equippped with an RM-14 and HP-210 or HP-260 prob'e. will scan the hands, feet, head and shoulders of each passenger in the vehicle, If no contamination above acceptable levels e. is found on the passengers issue clean tags O (marked " person") to the driver for each passenger. f. The first monitor to complete monitoring i vehicle passengers, will check the vehicle swipe for contamination. g. If no contamination above acceptable levels is found on the vehicle swipe, place a clean tag (' marked vehicle') under the vehicle windshield wiper. 5.5.9 Monitoring of each vehicle and its passengers should take no longer than 100 seconds.
- 5. 5. l o The Traf fic Guide will complete the Reception Center Record Form (OPIP 4.2.3 Act. 6), and direct the vehicle driver to the exit or decontamination area.
5.6 tionitoring/ Decontamination Personnel Assigned to Monitor Incoming Bus (Hicksville Only) _- Special Facility Evacuees (Brentwood Only) 5.6.1 Assist in the set up of the Emergency Worker i Decontamination Facility in accordance with OPIP ] 4.3.1. DRAFT - 2/20/87 i l l L
OPIP 3.9.2 Page 9b of 49 A\\J 5.6.2 Obtain your dosimetry and fill out record forms I in accordance with OPIP 3.9.1. 5.6.3 Perform pre-operational checks of RM-14 in I accordance with Attachment 1. 5.6.4 Determine background radiation levels in I accordance with Attachment 2. 5.6.5 Wear protective clothing in controlled area at all times in accordance with Attachment 7. 5.6.6 When monitoring for external contamination using the RM-14 with the HP-210 or HP-260 probe, ensure: a. range selector is on XI position b. response time is fast volume switch is at maximum position c. d. alarm is set at 360 cpm above background. l 5.6.7 (]) Monitor each arriving bus /special f acility I evacuees as follows: Have the individual remain in the vehicle. a. b. Hold the HP-210 or HP-260 probe about a 1/2 l inch away from body. c. Scan each individual slowly. This should take about 90 seconds. d. Pay particular attention to: o llands o Feet o Head o Shoulders While scanning individual, if the meter e. reading is fluctuating widely and is difficult to read, switch response time to slow and monitor the particular area for 30 seconds. O DRAFT - 2/20/87 L
r OPIP 3.9.2 Page 9e of 49 () f. If reading exceeds 360 cpm above background, I the individual is considered contaminated. 5.6.8 If individual is not externally contaminated, I proceed to section 5.4.10. 5.6.9 If individual is contaminated, direct the contaminated individual to the Decontamination Area and inform the Decontamination Leader or his designee that a contaminated person has arrived and the zone f rom which he/she evacuated. 5.6.10 If the individual is contaminated and non-ambulatory, notify the Decontamination Leader to arrange placement of the individual in a medical facility capable of handling a contaminated person. Attempt removal of contaminated clothing or other activity that will reduce the contamination. 5.7 If directed by the Decontamination Leader assigned to initial monitoring to expedite the processing of vehicles, each monitoring team will scan incoming cars and drivers as follows: () One monitor will take a swipe of a. approximately one quarter of the hood and wheel well of the vehicle, and monitor the cloth with an RM-14 with HP-210 or HP-260 probe. (The cloth may be reused until contaminated.) b. The second monitor will scan the hands, f eet, head and shoulders of the driver with an RM-14 with HP-210 or HP-260 probe. If no contamination found, place a cican tag c. (marked " vehicle") under the windshield wiper, and issue clean caps (marked " person") to the driver for all passengers d. If contamination above acceptable limits is found on either the vehicle or the driver, explain to the vehicle driver and passengers l that detailed monitoring is necessary. The Traffic Guide will complete the Reception e. Center Record Form (OPIP 4.2.3, Att. 6) and direct the vehicle to the exit or (} decontamination area, as necessary. DRAFT - 2/20/87 l L
OPIP 3.9.2 Page 20 of 49 {) Page 2 of 4 RM-14 COUNT RATE METER (continued) 5.1.2 The radiation count rate (cpm) is read on the f ront panel meter (0-500 cpm full scale. Switch selected ranges of X1, X10 and X100 are)provided. The response time of the meter can be selected by a " Fast / Slow" response switch. 5.1.3 The HP-210, HP-260, and HP-270 probes are used l with the RM-14 for personnel monitoring at the Emergency Worker Decontamination Facility and the Reception Center Decontamination Facilities. l 5.1.4 Topics covered in the procedure: 5.2 Operational Set-up 5.3 Battery Check 5.4 Range Selection (^} 5.2 Operational Set-Up V 5.2.1 Place selector st. itch in "0FF" position. 5.2.2 Connect either the HP-210, HP-260, or HP-270 l detector to the instrument as appropriate. 5.2.3 (Optional) Connect the power cable to the instrument and plug into 115 VAC power supply. 5.2.4 Set the meter alarm knob, located on the back of the instrument, to the desired alarm point. 5.2.5 Turn volume knob to maximum position. 5.3 Battery check 5.3.1 Turn the selector switch to the "BATT" position; the meter should read in the BATT OK range. NOTE: The instrument does not function properly even when plugged into 115 VAC, unless the batteries check O.K. O DRAFT - 2/20/87 e-- - -
OPIP 3.9.2 Page 21 of 49 Attachment I fs Page 3 of 4 RM-14 COUNT RATE METER (continued) 5.3.2 If the batteries check low, notify the Decontamination Leader for further instructions. 5.4 Range Selection 5.4.1 When monitoring with this instrument, it may be necessary to change ranges using the switch on the face of the instrument to bring the indicat-ing needle "on-scale". NOTE: If the alarm circuit is actuated, press the reset button. 5.5 Radiation Response Functional Test 5.5.1 Perform an upscale response test with the radioactive check source. Follow instructions ()' None 7.0 ATTACHMENTS 1. Figure 1 Eberline Model RM-14 and HP-210, HP-260, and l IIP-270 Probes O DRAFT - 2/20/87 L_
OPIP 3.9.2 Page 22 of 49 l O I Page 4 of 4 OPERATION OF EBERLINE HODEL RM-14 (continued) FIGURE 1 EBERLINE HODEL RM-14 AND PROBES l N (...; c w :va w ns.~.=- 'p 7[(p< ':g y;I),, ~~ ' r, .w, t , r,, N* [ .- i < c.,..s 'h -ll.lV.1. m. i ~ c, y.s ,y-y -n HP 270 .?.R O n -S p , r s , &.3 l ',.'.T..I : ' [f?f.!.&,Q,.'. ~ *:.
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OPIP 3.9.2 Page 23 of 49 Page 1 of 1 DETERMINATION OF BACKGROUND RADIATION LEVEL 1. Set the RM-14 to the 'X1' scale. 2. Set the response time to ' slow.' 3. Readout will fluctuate slightly; use approximate average of upper bound measurements. 4. Use the following table. l H TYPE OF l SHIELD l MAXIMUM ALLOWABLE MONITORING PROBE POSITION BACKGROUND I l External HP-270 Open 50 CPM Thyroid-Adult 1 ilP-270 Closed 50 CPM I l O l 1 HP-210 l Attach Plastic l l _ Thyroid-Child 1 Shield i 150 CPM i l i i (Reception Center l i l I l and EWDF Initial HP-210 and None i 150 CPM i Scan HP-260 I i l I ~l Vehicle-Interior HP-270 Open 50 CPM l_and Decon. i 5. Ensure background radiation level with HP-270 probe is performed for both shield open and closed. 6. Determine background level every 15 minutes. 7. If maximum allowable background is execeded, attempt to find and remove source of radiation. Otherwise move monitoring location. O DRAFT - 2/20/87
OPIP 3.9.2 .~ Page 27a of 49 Page 4a of 4 FIGURE 4 EVACUEE RECEPTION CENTER. INITIAL MONITORING FLOW DIAGRAM ENTER \\/ STOP AT INITIAL MONITORING STATION a SMEAR SWIPE MONITOR HANDS FLET,HCA0 ~ j 0F HOOD AND 'AND' FEET 0F3 AND WHEEL WELL 77 3 M RJ SHcutodps + b &F Virtu.LC Cau P A G, n EITHER V READING ABOVE 360 CPM NO VES \\/ v OBTAIN PROCEED TO DECON, CLEAN TAG TRAILER FOR j 3 DETAILED MONITORING. OBTAIN MAP TO FIGURE 1 CONGREGATE CARE CENTER IF NEEDED J PROCEED TO FACILITY EXIT O we 2./Ac,/6'T u ----
l OPIP 3.9.2 Page 49a of 49 Page 1 of 1 t'~N \\J DETERMINATION OF CONTAMINATION LINITS Contamination is indicated by the following: INSTRUMENT i MININUM READING FOR l TARGET RM-14 SURVEY CONTAMINATION METER WITH: (Above Background) Initial HP-210 Probe or 360 CPM (Evacuee) Monitoring HP-260 Probe 360 CPM (Vehicle Swipe) Shield Off Person - skin
- HP-270 Probe 150 CPM
__or clothing Shield Open 1 Adult Thyroid
- HP-270 Probe 150 CPM Shield Closed I i
i Child Thyroid
- llP-210 Probe l Anything above background (Under 12)
Shield On i ( Swipe from Vehicle
- HP-210 Probe 360 CPM (warrants full Shield Off survey with HP-270) l Equipment or l *llP-270 Probe l
360 CPM i Vehicles positive Shield Open l l_on Swipes l l l
- Nominal sensitivity llP-270 probe @ 1,200 CPM = 1 mR/hr.
Nominal sensitivity llP-210 probe @ 3,600 CPM = 1 mR/hr. Nominal sensitivity HP-260 probe @ 3,600 CPM = 1 mR/hr. I NOTE: Background readings must be taken with the same type probe and same shielding configuration as used to measure contamination. O DRAFT - 2/20/87
Hand Probe Model HP-210 O 1 /*e *
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= HIGH BETA SENSITIVITY a WINDOW PROTECTIVE SCREEN O A DevletON OP Tilermo Eberlm. e //6 Electr " H P *910 C O 84 88 0 ft A fiO N =
Model HP 210, Hand Probe O, GENERAL DESCRIPfl0N The Model HP 210 series hand probes provide The HP 210T with a high density tungsten a sensitive beta detector featuring a " Pan. cake" GM tube with a thin mica window. The shleid permits relatively low level beta open window which is protected by a sturdy monitoring in a gamma background. When low level beta monitoring is required in a low wire screen, p,ermite useful beta sensitivilles down to 40 kev. The detector is alpha background area, the HP 210AL with an senaltive (above 3 MeV). aluminum housing may be used, The HP 210 la designed for contamination surveys on personnel, table tops, floors, equipment, etc. SPECIFICATIONS HP 210T (DT 304) HP 210AL Operating Voltage: 900 2 50 V g00 s 50 V Plateau length: 100 V mlnlmum 100 V minimum Plateau Slope: ,0.1 percent per V maximum 0.1 percent per V maximum Dead Time: 50 ps maximum 50 ps maximum Temperature Range: -22 'F to + 167 'F - 22 'F to + 167 'F (- 30 'C to + 75 'C) (-30 'C to + 75 'C) Mica Window Thicknese: 1.4 to 2.0 mgicm' 1.4 to 2.0 mg/cm' Mica Window Slae: 1,75. Inch diameter 1,75 inch dlameter O Series Reelstor: 3.3 M0 (In probe) 3.3 M0 (in probe) (4.45 cm) 2.4 in' (4.45 cm) 2.4 in' Gamma Sensitivity: (Into window) a 3600 cpm /mR/h ('"Cs) m3600 cpm /mR/h ('8'Cs) Shleiding Ratlo: a 4:1 ("Co) at:1 (window: back)
- Sota Efficiency:
a45 percent "St "Y a45 percent "St "Y a30 percent "Tc m 30 percent "Tc a 10 percent "C m 10 percent "C Alpha Sensitivity: 3 MeV at window 3 MeV at window Connecton BNC series coaxlal DNC series coaxial Stae: 6.5 inches long x 3.5 Inches 6.5 inchos long x 3.5 inches wide x 3.8 inches high wido x 3.8 inches high Waleht: 4.25 pounds (1.9 kg) 1.5 pounds (0.7 kg)
- Efficiencies with screen in place. Screen removal willincrease efficiency by a45 percent of stated value. Efficiencies IIsted as porcontage of 2e emission rate from a ono. inch diamoter sOUfCo.
AVAILABLE ACCESSORIES Instruments Cables E 120 CA 136 E 140 CA136 i E 140N CA 18 60 l E 520 CA t 36 1 PRM 6 CA 16 60 PRS 1/ 2 CA 14 36 l RM 14 CA 160 i O mi na Eberline dEM"En E' ' " " MS3 CA 16 60 CC" * ^"o* Sample Holden SH 4A Post office Bos 2104 saia Fe, m unico em 7 83 tsospri.un twx:stoosscars
Hand Probe Model HP-260 0 $i[k;.,Nvi9., u.. Iit;
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O Model HP 260, Hand Probe GENERAL DESCRIPTION The Model HP 260 hand probe provides a sen. sitive beta detector, featuring a " Pancake" The HP 260 is designed for contamination GM tube with a thin mica window. The open surveys on personnel, table tops, floors, equipment, etc. window, which is protected by a sturdy wire screen, permits useful beta sensitivities down to 40 kev. The detector is alpha The long handle on the HP 260 makes it sensitive above 3 MeV. convenient for personnel and table top surveys. SPECIFICATIONS AVAILABLE ACCESSORIES Operating Voltage: 900 :e 50 V instruments Cables Plateau Length: 100 V minimum Plateau Slope: 0.1 percent per V maximum f,1 CA Dead Time: 50 s maximum A 1-E 520 CA 136 Temperature Range: -22 'F to + 167 'F MS3 CA 16 60 (- 30 'C to + 75 'C) PRM 6 CA 16 60 Mica Window Thickness: 1.4 to 2.0 mg/cm' ^' O Mica Window Size: 1.75 inch diameter RM A1 0 RM 20 CA 16 60 (4.45 cm); 2.4 in'(15.5 cm') RM 21 CA 16 60 Gamma Sensitivity: a3600 cpm /mR/h ("'Cs) (into window)
- 8 eta Efficiency:
a 45 percent "Sr."Y a 30 percent "Tc a 10 percent "C Alpha Sensitivity: 3 MeV at window Connector: 8NC series coaxial Size: 10 inches long x 2.75 inches wide x 2.5 inches high (25.4 cm x 7 cm x 6.4 cm) Weight: 1.25 pounds (0.57 kg)
- Ef ficiencies with screen in place. Screen removal will increase efficiency by a45 percent of stated value. Efficiencies l6sted as percentage of 2r emission rate, from a one inch diameter source.
A OlveSION OF O Eberline EEE8 C O A 88 0 A A T I O N Post Office Bos 2108 Santa Fe, New Menaco 87501 (505)411 3232 TWx: 910 9850678 7 83
Hand Probes Models HP-270 and HP-290 O \\ \\ I Model HP 270 i O Model HP 290 M ENERGY COMPENSATED FOR GAMMA EXPOSURE RATE MEASUREMENTS M SLIDING BETA SHIELD (HP 270) !O Eberline IFEIEdiFj H P-270 e. e ~ e-H P-290 c o. o ...o ~ --- ----n---
O M dels HP-270 and HP 290, Hand Probes GENERAL DESCRIPTION The HP 270 is an excellent general purpose GM probe, with energy compensation and a The HP-290 is a higher range GM probe with beta shleid, making it the choice for most energy compensation, providing reliable ex-health physics applications. The energy com-posure rate measurement from 0.1 mR/h to 10 R/h. pensation permits reliable exposure rate measurement from background to 200 mR/h. SPECIFICATIONS HP 270 HP 290 Operating Voltage: 900 2 50 V 550 2 50 V Plateau Length: 100 V minimum 100 V minimum Plateau Slope: 0.1 percent per V 0.2 percent per V maximum maximum Dead Time: 100 gs maximum 20 ps maximum Temperature Range: - 40 'F to + 167 'F - 40 'F to + 167 'F (- 40 *C to + 75 'C) (- 40 *C lo + 75 'C) Wall Thickness: 30 mg/cm'(tube only) 90 mg/cm' (tube only) Wall Material: Stainless steel Stainless steel Gamma Sensitivity: a 1200 cpm /mRlh ("'Cs) a80 cpm /mR/h ("'Cs) J Energy Response: See curve See curve Housing: ABS plastic ABS plastic Connector: BNC series coaxial BNC series coaxlal Size: 1% inches in diameter x 1 % inches in diameter x 6 inches long 3% inches long (3.5 cm x 15.2 cm) (2.9 cm x 6.9 cm) Weight: 5 ounces (142 g) 2 ounces (57 g) AVAILABLE ACCESSORIES 26 HP 270 24 ^ f HP 290 22 Instruments Cables Instruments Cables 20 7 ,Hg,,,gggg, E 120 CA 136 E 530N CA 136 e 1 E-140 CA 136 MS3 CA 16 60 K 1A I" \\ I (( k E 520 CA 136 PRM 5-3 CA 14 36 $ d 12 o MS3 CA 16-60 PRM 6 CA 16-60 a: c 3o I2 PRM 5 3 CA 14 36 PRS 1/ 2 CA 14 36 $ $ .8 I/ PRM 6 CA 16-60 RM 20 CA 16 60 EE IM W4MN PRS-112 CA 14 36 RM 21 CA 16 60 s RM 14 CA 160 'j /// RM 20 CA 16 60 2 / RM 21 CA 16 60 ~ to iou 1000 _s GAMMA ENERGY @eW Energy Response of Models HP 270 and HP 290 7-83
Radiation O Monitor Model RM-14 [i, , I,:[,- c Hjj'E]['(*1 n o,s r i a-4: j ~'"" ...m I ? ., [ 5, f f j- ,., g ;..; - [ J. !.(ggg{[* 8ESPON58.h f M E VARIABLE HIGH LEVEL ALARM u SPEAKER WITH VOLUME CONTROL u TRICKLE CHARGED BATTERY u TIME CONSTANT SELECTION E RECORDER OUTPUT E SCALER OUTPUT l _ M TILT STAND l t _ O . e ~. e. o ~ e - Thermo Eberl.ine //E Electron RM-14 com oae.o~
C) uoe.i au.14, nadiation Monitor GENERAL DESCRIPTION The RM 14 Radiation Monitor is a small, ver-Circuitry in the RM 14 is all transistor and in-satile, alarming count rate meter operated by tegrated circuit mounted on a plug in board. a rechargeable gelled cell battery wh!ch is The top cover of the cabinet is easily trickle charged when the unit is plugged into the line. Three ranges are provided of 500, Sk, removable, allowing access to allinternal components. and 50k counts per minute (cpm) full scale. A battery check is provided on the meter. A The RM 14 is intended for use with 900 V speaker and volume control are provided for auralindication of the count rate. Geiger tube detectors, such as the Eberline HP 177C, HP 190, HP-210, HP 230A, or HP-270. The alarm point is adjustable over the scale 11 can be easily modified for use with detec. tors requiring other cperating voltages. Wt.en of the meter by a rear panel control. When ac-ordered with one of the Geiger detectors, a.n tuated, the alarm does not affect the meter reading and is Ir.dicated by a high frequency optional probe holder may be installed on the instrument. tone on the speaker. Rear panel connectors are provided for an external scaler and a 50 pA recorder. SPECIFICATIONS Meter: Scale length 2.37 inches (6 cm), marked 0 to 500 cpm. Temperature: The instrument is operational from -20 'F to + 140 'F ( 29 'C to 60 'C) with Range: Switch controlled X1, X10 or X100 less than 210 percent full scale change in yielding 500, Sk, or 50k cpm full scale, calibration and less than 2 20 percent full Response Time scale change in alarm point. Fast: Approximately 2 seconds' ize: n es @ x 7 Mes hp x Slow: Appaurrately 20 secends measured to es wide 03.3 cm x 17.8 cm x 19.1 cm). a 90 percent of tne final reading. Weight: 4% pounds (2 kg). Linearity: Within 2 5 percent of full scale, Finish: Baked enamel paint, brown panels, tan typically within 22 percent of full scale. cover. Battery Dependence: Calibration shif ts less than 10 percent with battery between limits on meter. AVAILABLE ACCESSORIES Alarm Point: Adjustable from 10 percent to Detectors greater than full scale. HP-190 Alarm Indication: Red light on front panel and HP 210T approximately 1 kHz tone on speaker HP 210Al independent of volume control. HP 230A Speaker: Internal 2 inch size. One click for 6 each event counted. Volume: Varles speaker clicks from maximum Associated Cable: CA 136, CA 160 loudness to zero. Scaler Out: Rear panel BNC connector. One Probe Holder for HP 210: Model ZP10534017 6 V positive pulse for each event counted. Recorder Out: Rear panel, % inch,3 wire phone plug with 0 50 gA de full scale. Power: 105125 V,50 60 Hz at approximately O inO Electrort Battery: Gelled cell, approximately 50 hour CORPORATION lifetime between charges. Charging time is Pm office eox 2108 approximately 50 hours. santa Fe, New Mexico 87501 1505) 471 3232 Twx: 910-9854678 S-83
Hand Probe Model HP-210 O / / N /
- )
( ^ /' /g d 0 '. S ef'.g HP 210AL H P-210T ~ ./ s $159 w J m THIN WINDOW " PANCAKE" GM ~ = HIGH BETA SENSITIVITY i m WINDOW PROTECTIVE SCREEN i l D ~5e~ms ^ Eberline f/Esectmn 1 HP-210 CO A PO A ATION -,e---..--,w-,--
,,-m-y_,,,
,_,---.b.m,, ..---- m -.,-r,----
Model HP 210, Hand Probe O GENERAL DESCRIPTION The Model HP 210 series hand probes provide The HP-210T with a high density tungsten a sensitive beta detector featuring a " Pan. shleid permits relatively low level beta cake" GM tube with a thin mica window. The monitoring in a gamma background. When open window, which la protected by a sturdy low level beta monitoring is required in a low wire screen, permits useful beta sensitivities background area, the HP 210AL with an down to 40 kev. The detector is alpha aluminum housing may be used. sensitive (above 3 MeV). The HP 210 is designed for contamination surveys on personnel, table tops, floors, equipment, etc. SPECIFICAYlONS HP 210T (DT 304) HP 210AL Operating Voltage: 900 50 V 900 2 50 V i Plateau length: 100 V minimum 100 V minimum Plateau Slope: 0.1 percent per V maximum 0.1 percent per V maximum Dead Time: 50 ps maximum 50 ps maximum Temperature Range: - 22 'F to + 167 'F -22 'F to + 167 'F (-30 'C to + 75 *C) (-30 'C to + 75 'C) Mica Window Thickness: 1.4 to 2.0 mg/cm' 1.4 to 2.0 mg/cm' Mica Window Size: 1.75 inch-diameter 1.75 inch-diameter r~s (4.45 cm) 2.4 in' (4.45 cm) 2.4 in' V Series Resistor: 3.3 MD (In probe) 3.3 MO (in probe) Gamma Sensitivity: a3600 cpm /mR/h ("'Cs) in3000 cpm /mR/h ("'Cs) (Into window) Shielding Rallo: a 4:1 ("Co) a 1:1 (window: back)
- Beta Efficiency:
a 45 percent "Sr "Y a 45 percent "Sr "Y a30 percent "Tc m 30 percent "Tc a 10 percent "C a 10 percent "O Alpha Sensitivity: 3 MeV at window 3 MeV at window Connector: BNC series coaxial BNC series coaxial Size: 6.5 inches long x 3.5 inches 6.5 inches long x 3.5 inches wide x 3.8 inches high wide x 3.8 inches high Weight: 4.25 pounds (1.9 kg) 1.5 pounds (0.7 kg)
- Efficiencies with screen in place. Screen removal will increase efficiency by a45 percent of stated value. Efficiencies listed as percentage of 2r emission rate from a one Inch-diameter source.
AVAILABLE ACCESSORIES Instruments Cables i E 120 CA 136 E 140 CA 1-36 E-140N CA 18-60 E-520 CA 136 l PR M-6 CA-16-60 PRS-1/-2 CA 14 36 RM 14 CA-160 i ^ .'!'Eem10 O' RM 20 CA 16-60 edne Esectrosi R M-21 CA 16 60 M S-3 CA-16-60 coaaoa^7'oN Post office Box 2106 Sample Holder: SH-4A Santa Fe. New Mexico 87501 (505) 471 3232 TWX:914985 4678 7 83
Hand Probe Model HP 260 0 . c y.u, O 4, 'h \\ m THIN WINDOW " PANCAKE" GM a HIGH BETA SENSITIVITY a WINDOW PROTECTIVE SCREEN i.. i ~ O .e~.e~. Eberline FEEeE*8 H P-260 c e o .1. e ~
O Model HP 260, Hand Probe GENERAL DESCRIPTION The Model HP 260 hand probe provides a sen-The HP 260 is designed for contamination sitive beta detector, featuring a " Pancake" surveys on personnel, table tops, floors, GM tube with a thin mica window. The open equipment, etc. window, which is protected by a sturdy wire screen, permits useful beta sensitivities down The long handle on the HP 260 makes it to 40 kev. The detector is alpha convenient for personnel and table top sensitive above 3 MeV. surveys. SPECIFICATIONS AVAILABLE ACCESSORIES Operating Voltage: 900 250 V instruments Cables Plateau length: 100 V minimum Plateau Slope: 0.1 percent per V maximum E;1 CA 1 Dead Time: 50 gs maximum E 520 CA 136 Temperature Range: -22 'F to + 167 'F MS-3 CA 16-60 (- 30 'C to + 75 'C) PRM-6 CA 16-60 Mica Window Thickness: 1.4 to 2.0 mg/cm, PR 1/-2 C^ p 4 CA1 C Mica Window Size: 1.75 inch diameter RM 20 CA-16 60 t4.45 cm): 2.4 in'(15.5 cm') RM 21 CA 16 60 Gamma Sensitivity: m 3600 cpm /mR/h ('"Cs) (into window)
- Beta Efficiency:
245 percent "Sr '*Y s30 percent "Tc a 10 percent "C Alpha Sensitivity: 3 MeV at window Connector: BNC series coaxial Size: 10 inches long x 2.75 inches wide x 2.5 inches high (25.4 cm x 7 cm x 6.4 cm) Weight: 1.25 pounds (0.57 kg)
- Efficiencies with screen in place. Screen removal will increase efficiency by 245 percent of stated value. Efficiencies listed as percentage of 2r emission rate, from a one inch diameter source.
A DavlSIO N O F O Eberline MEeM8 CO APO A AT40N Post Office Box 2108 santa Fe. New Mexico 87501 (505) 471 3232 TWx: 910 9E5o678 ~ 7-83
Hand Probes Models HP-270 and HP-290 I O Model HP-270 1 i O 5/ Model HP-290 E ENERGY COMPENSATED FOR GAMMA EXPOSURE RATE MEASUREMENTS ( E SLIDING BETA SHIELD (HP-270) O, A OlveSION OF Thermo H P-270 i l - Eberi.me F/E Electr " H P-290 CO APO A ATION
(~) Models HP-270 and HP 290, Hand Probes GENERAL DESCRIPTION The HP 270 is an excellent general purpose GM probe, with energy compensation and a The HP 290 is a higher range GM probe with beta shleid, making it the choice for most energy compensation, providing re!!able ex-health physics appilcations. The energy com-posure rate measurement from 0.1 mR/h to 10 R/h. pensation permits reliable exposure rate measurement from background to 200 mR/h. SPECIFICATIONS HP 270 HP 290 Operating Voltage: 900 50 V 550 2 50 V Plateau Length: 100 V minimum 100 V minimum Plateau Slope: 0.1 percent per V 0.2 percent per V maximum maximum Dead Time: 100 ps maximum 20 ps maximum Temperature Range: - 40 'F to + 167 'F - 40 'F to + 167 'F (- 40 'C to + 75 'C) (-40 'C to + 75 'C) Wall Thickness: 30 mg/cm'(tube only) 90 mg/cm'(tube only) Wall Material: Stainless steel Stainless steel Gamma Sensitivity: a 1200 cpm /mR/h ("'Cs) a 80 cpm /mR/h ("'Cs) hc Energy Response: See curve See curve Housing: ABS plastic ABS plastic Connector: BNC series coaxial BNC series coaxial Size: 1 % inches in diameter x 1 % inches in diameter x 6 inches long 3% inches long 13.5 cm x 15.2 cm) (2.9 cm x 8.9 cm) Weight: 5 ounces (142 g) 2 ounces (57 g) AVAILABLE ACCESSORIES 26 2.4 ^ HP 270 HP 290 2.2 Instruments Cables Instruments Cables 2.0 7
- j
,,g g,7g ggg, E 120 CA 136 E 530N CA-136 E 140 CA 136 MS3 CA 16 60 ? u / HP 290 e E 520 CA 136 PRM 5-3 CA 14 36 0 I I-A o cj 1.2 MS3 CA 16-60 PRM 6 CA 16 60 E C II PRM 5 3 CA 14 36 PRS 1/ 2 to CA 14 36 CA 16-60 @e $.a II PRM 6 CA-16 60 RM 20 e /g Wnma PRS-112 CA 14 36 RM 21 CA 16-60 3 RM 14 CA 1-60 ~j /// RM 20 CA 16-60 .2 ,/ RM 21 CA 16 60 'U 10 100 1000 O' GAMMA ENERGY (kev) Energy Response of Models HP 270 and HP 290 7 83
Radiation 6 Monitor Model 'RM-14 '1, ,j$ij hi ' S. . (..;. <;+;r.p y p.s t .3,. O; , ' 3,,.. 's!1. %l.. ~ y, .c..:. ;. }P.. Ivi A ? 3 a VARIABLE HIGH LEVEL ALARM l u SPEAKER WITH VOLUME CONTROL m TRICKLE CHARGED BATTERY u TIME CONSTANT SELECTION il - E RECORDER OUTPUT a SCALER OUTPUT l M TILT STAND i-l A OlviSIO N OF Thermo Eberline I/E Electron RM-14 c O e O m m,0 ~ I l
~ d Q s! m CURRICULUM VIJA,E June 9, _1986 [LOM,E. LINNJ,3fNN, _ M,.A Home Addr,;ss: 517 S. Providence Road Wallingford, PA 19086 Office Addrgss: RadiaLion Management Consultant.* 5301 Tacony Street - Box DS Philadelphia, PA 19137 E.a t e o t-sj_ tty
- dnuary I?, 1931 Place of Etirth
Ut. Cloud, Minnesota hgungy i or. : 19;? tiniversi'y of Minnesota, Minneapolis, M *J. H.A. (C*1m La udi-) 193S Univers Ly of Minnesota, Minneapolis, M.*4, 0.2. M.D. l '*.10 - 170 ' W41ter Reod Army Mc;pital. W.shington, D.C.; L NT6.P.'iSH II' ils2 1905 Walter Reed Army Ho:Pital. Washington, D.C.; RE01DEhCY (Radiology) 1963 1963 US Department of Agriculture tiraduate School (Evening). Wa:hington, D.C., Russian Lenguage Professipnal Exerlwneg: 1986 - present Pre's iden t, Radi4 Lion Management Consult. ants 1969 - 1986 President / Chief Executive Officer Radiallon Manag*inen t. Corpora t ion isla present l Clinical Assoriale Professor at Radiology. Univ *rsity of Pennsylvania School of Medicine 1911 - present Vicitins Aavociato Penressne, Clinical Radiology. Nort.hwest rn Universtly Medical School 1969 - 19/4 Assistant Profvuzor, Cilnical Radiology. university of Pennsylvania school of Medicine 2m 190s - 19a9 EXN9587 Muclear Medicine Consultant, Philadelphia Elcetric Company g{_ 3s+7 [, LJ NMM4gg e s.)
6 ~ O Professional Esperience (Con't.): Jan - August 1968 Assistant Professor, Radiology, University of Minnesota School of Medicine (investi-gated use of radioisotopes in kidney function evaluation) 1937 - 1968 Medical officer in United States Army...... 1965 - 1968 Commanding Officer. Nuclear Medicine Research Detachment, Europe; Radiological Health Con-sultant, US Army-Europe (responsible for plans, procedures and training of military hospitals and personnel in the evaluation, evacuation and treatment of radiation casualties). In January, 1966 sent to Palcmares. Spain for evaluation of medical and environmental as-pects of the mid-air collision involving nuclear weapons) 1961 1962 Research Associate. Department of Radiobiology, Walter Reed Army Institute of Roccarch, W.ashington, D.C. (invostigated us.e of anti.. radiation drugs in treatment of cancer) O 1957 1961 General Medical Officer, Europe f.ang u a ge s : German, Russian Professional Appointments: 1982 - American Medical Association Council on Scientific Af, fairs Subcomunittee on the Manage-ment of Radiation Accident Victims 1979 - present Health g,[ly1 M S_ociott Standards Committee 1978 1981 General Dynamics _ Electric Boat Division Radiological Health Consultant 1978 - 1980 Edison Electric p.stitute Utility Radiation Standards Group I 1973 - present u_niversity of Pennsylvani,a, Nadiation Safety l Committee 1973 - 1983 The Atomic Indu1 trial Forum. Ts. Public Aff airs & Information Conunittee i
O-1970 The American Nuclear Society Subcommittee for Writing Emergency Procedures Standards 1969 Ataria Entray $2pmission ad hoc Committee on Medical Aspects of Radiation Accidents 1966 - present American Co11eze g{ Radiolony..... 1966 - present Commission on Radiological Units, Standards and Protection 1969 - 1980 Committee on Radiation Exposure of Women 1969 - 1983 Committee on Radiological Aspects of Disaster Planning 1961 - 1978 International Affairs Committec ypacialty Certification: 1964 Certified by American Board of Radiology 1972 Cert ified by American Board of Nuclear Medicine M nsure: Commonwealth of Pennsylvania, Illinois and Minnesota National SocJeties: American College of Radiology American Public Health Associatlon American Medical Association society of Nuclear Medicine Pennsylvania Medical society Radiological Society of North America, Inc. American Institute of Physicists /American Association of Physicists in Medicine American College of Nuclear Physicians j The New York Academy of Scinnees Awards & Honors: Association of Medicine & Security, Madrid, Spain (1978) University of Minnesota Radiological Research Scholar (National Nesearch Council) O United States Army Legion of Merit Listed in Who's Who in Frontlec Science and Technology - x -
(~ \\'-)' Presentations: 1983 DwK (see 1978) Munich, Germany - Appeared before as international expert 1983 DVK (see 1918) Hanover, Germany - Presented seminar " Medical Significance of Radiation Exposure" at University of Regensburg for medical and chemistry grad students 1982 Health Physics Society (Annual Meeting, Las Vegas, Nevada) - Presented keynote speech " Medical & Public Health Conscquences of an Off-Site Release of Radiation from Nuclear Power facility" 1980 .Xorea Women's Association (Seoul Korea) - Presented paper. " Energy: The Basis for Health in Developing and Developed Countries", at International Symposium on the Expulsion of Environmental Pollution 1980 <orean Association (or 3adiati_on Protection (Seoul, Korea) - Presented seminar on emergency management of radistion injuries D 1%0 lis m of Health (Madrid, Spain) - Presented t,a pe r. \\- " Definitive Treatment of Radiation injurics", at First Oeminar on Assistance to Those Wounded by Radioactive Elements and Ionizing Radiations 1979 Reinisch_ Westfalisches Elekrizitatswerk (Essen, Cormany) Presented paper, " Energy: The Basis for Health in Developing and Developed Countriec", at The Seventh Energy Workshop \\ l 1978 The Swedish State Power Boggd (Vallingby, Sweden) l Presented seminar, " Management and Treatment of FadiaLlon Injuries", and conducted radiation emergency medical exercise at the Ringhauls Nuclear Power Plant 1978 Deutsche Gesellschaft (HI Wiederaufarbeituna (Hanover, Gcemany) Appeared before the Prime Minister and Parti-amont of Lower Saxony as an International expert to testify on the safety of~a reprocessing plant at corleben, Cermany 1978 Interqstional Atomic Erlapy Agen_c,y (Vienna, Austria) PecJentation at Symposium on Late EffecLs of Ionizing-Radiation O
s' e Presentations (Cont M : 1978 Assoelacion S,e,Nedlelne y,Sogy,rldad e.,9 e_1,Traba_io de i Ugesa para la _I,r!.d.ggir,,1,,a gl.tctrica (Madrid, Spain) - Presented one-day seminar entitled. " Primary Manage ment of Radiation Injury" 1977 International M onic Energy gency (Vienne. Austria) - Presented paper. " Emergency Medical Assistance Programs for Nuclear Power Reactors", at Symposium on Handling of Radiation Accidents 1967 University of Freiburz Institute of Radiobiology (Freiburg, Germany) - Presented seminar on diagnosis and treatment of radiation injuries Publications: 1. Linnemann, Roger E. " Berlin: The Young Old Ci*.y" Sponlog. citizen (September 19o1). n 2. Linnemann, Roger E. "This Way to Berlin" Q American L.a. n,*d i c t i n e 9 e v i a w : 14 No. 4 (December 1963). 3 1.nnnemann, leger b. "The Acute Radiation Syndromt and its Tmpact on the Chain of Evacuation" Med i c al ts u ll.o t i,n,, tt. S. Army hurope: 22, No. I'/ (Decceber 1965). 4 Linnemann, Roger E. and Nobert 7. Wangemann. " Medical Support o t' Nuclear Weapons Accidents". (November 1967). Medical Bulle, tin,, Q A_rymy Euroog 5. Linnemann, Roger E. and O. Messerschmidt. bei Grosstlecen nach Ganzkoerperbestrahlung","Echolungsvorgaenge
- dem 6, Jahrbuch von der vereiniguna Duetscher Strahlenschutzaarzte (1968).
6. Linnemann, Roger E. "Consnand Radiation Guidance". MilitJII Medielne: 33, pp. 771-716 (September 1968). 7 Loken. Merle K., Linnemann. Roger E. and Ceorge S. untion of Renal Function using a Scintillation Camera and computer" Xush. " Eval- !Ladjg. logy: 2J. No. 1, pp. 85-94 (July 1969). 8. Linnemann, Roger E., Loken, Merle K. and Colin Markland puterized Compartmental Rancgeams to Study Kidney Function". "Com-Journal of U,c,plo.gy: ,103, pp. 533 537 (May 1970). 9. Linnemann. Roger E. and J.W. Thiessen. Management of kediatlon Accidents". " Regional Approach to the Journ,a,1, of, ge,A_m_oJ},c,a_n, ['u_hll e He a lt h A s sge l a t l og
- 6_1,, No. 6, pp. 1229 1235'(June 1971).
O
= j l a f) V Publications (continued): 10. Linnemenn, Roger E. and Robert N. Holmes. " Nuclear Accidents and Their Management". F.merzency Medical Care, pp. 281-292. Spitzer, Stanley and Wilbur W. Oaks (eds.) New York: Brune and Stratton, Inc. (1971). 11. Linnemann, Roger E., Rasmussen, N.C. and F.X. P!LLman. Nitclear Ener1Y: Issues and Answees. Atomic Industrial Forum. Inc. In cooperation with Pennsylvania Power & Light Company (April 1973). 12. Linnemann, Roger E. " Accentuate the Positive" Trial: 10, No. 4,
- p. 13 (July / August 1914).
13. Linnemann, Roger E. " Accentuate the Positive". Conr.rassional Recoed: 109, pp. 4964-4967. Washington, D.C. Ifnited Statws of America Proceedings and Debates at the 93rd Congress, second Session (July 23, l'174). 14 Linnemann Rer,er N. and J.W. Thiessen. Editorial, "Tn Defense of Radiation and Calls" The New York Times (May 23, 1974). 15.
- innemar.n. Roger E.
Nuclaer Rad {atica and Health. Spr i n r,v ill e, NY. Nuclear F.el Servi'as, Inc. (Septet.ber 23, 1974). 16. L i n n er.a n n, Roger R. Editorial "In Defense of Nuclear Ucwwr Plants", The Philadelphia Inquirar, p. 11A (March 6 19/5). 11 Linncmann, Rcgve E. " Nuclear Power Plants Fosc Minimal Health Risks", Perspective. News Bureau of the University of Pennsyl-vania, Philadelphia, PA (February 1975). 18. Linnemann, Hoge E. " Medical Aspects of Power Generallon", _Impu l s e. Massachusetts: Electrical Council of New England (June 19?S). 19 Linnemann, Roger E. " Bugs in the Nuc1 car Fuel Cycle" J'pechtum
- p. 59, Gadi Kaplan (ed.)
Piscelaway, NJ: The InsLitute of Elec-telcal and Electronic Engineers. Inc. (September 1975). 20. Linnemann, Roger E. and Frad A. Mettler. Jr. "Emergancy Medical Assistance Programs for Nuclear Power Roactors". International Atomic Energy Agency Symposium on the Handling of Hadiation Acci dents. IAEA-SM-215/22. Vienna, Austria (1977). 21. Linnemann, Roger E. "Why ALARA?" Trancactions of 1979 American Nuclcar Soclely Conference, Atlanta, CA (June 3-7, 1979), Vo. 32 TANS AD 37 1 837 ISSN 0003-018x (1979). 22. Linnemann, Roger E., Hackbarth, C.J. and Ray Crandall. "Tho s t, Contaminated and Injured Patient". Procecdings of Twenty Fourth Annual Meeting of the Health Physics Society, Philaditlphia, PA (July n-13. 19 79).
e e (Q 23. Linnemana. Roger E. "The Three Mile Island Incident in 1979: The V ilt111ty tosponse". Th.!g, Mgd,Qa_l,, hse foi R,a 24t3dnggg, K.F. Hubner and S. A. Fry (eds. ). Mal.lon Accident Pm pp. 501-509 (1980). Elsevior/ North-Holland, 24. Linnomann, Roser E. 91 Eadiation Protection. ,*4, No." initial Manage:uent of Radiation tajuries". fournal
- 1. pp. 11-75 (December 1980).
25. Linnemann Roger E., Kim, Stephen M. "Three Mlle Island: and Frazier L. Bronson. Radiation Accident". Medical and Public health Aspects of a No. 1. pp. 45 52 (October 1981). Journal _ of RadiaMRt. h t,ection 6 26. Linncmann, Roger E. " Facilities for llandlinF, the Contaminated Patient" Radtation Acciden Prepareda,e,gy: Modical and Mm, &.egial Aspicas. Science-Thru. Media Company: New York (1982). 27 Ltnnemann. Roger E. af Radiation Ir. juries","A System Approach to the Initial Managemeret Csre. Appleton Cent.ory-Crof ts:gysic_q.;, p.pngad tp Emerleac g Medica _1. N.tw York ( 19 8 *t ). 28. !.innemar.n. Moser E. "Rudiation Injuries" Current. Etrerrency Therapy. Editoes: Richard Edlich and D4ni.: Publica!. ion by Aspen Uystems Corporaticn !<ockvill1 Spyper; and Asp-n . PD (191%). ,Q M. Linnemar.n. Roger E. Commarcial Nuclear l'ower Plants"." National Emergency Medical Assistance Program fo V American Nuclear Soci ty Topicai Meet.ing o.)Fr*8*nted at the Sept rnher l986 "Rudiologicsl Accidar.ls: Perspectives and Emergency preparedness" 30. i.innemann Roger E. "Ooviet Medical Response to Chcenobyl." for publication by tha Jouenal of the American Medical Association Submitted (JAMA). January. 1987. I l
,f* O(m/ PROFESSIONAr. TESTTMONY 1984 Limerick Nuclear Generatlng Stallon Emergency Planning Hearings 1985 Cleveland Electric illuminating company Emergency Planning Hearings in progress John Benek vs. Pennsylvania Power Company et 11
- 99 of 1977 Eminent Domain 198a Long Island Lighting Company Emergency Planning Hearings for the Shoreham Nuclear Power St ation L983 Union Electric Company Emergency Planning / Licensing Hearin5s for Callaway Nuclear Pcwer Plant 1983 Pennsylvania Power & Light Company Susquehanna Staam Electric Operatin5 License Hearings 1982 Texss Utilities Generating Company Empegency Planning
- learings for the Comanche Peak Steam Electric Station 1981
() Flurida Power & Light Company Turkey faint Steam Generator Repair Hearings 1981 Southern California Edison Company tmergency Plannin6 Hearings for the San Onofre Nuclear Generating Staliun 1979 Corlehen Nuclear Fuels Reprocessing Plant Hearings before the Prime Minister and Parliament of Lower Saxony, Hanover. Germany 1979 Florida Power & Light company Turkey Point Nuclear Station Opcrating License Hearings 1971 Long Island Lighting Company Shoreham Nuclear Power Station Operating License Hearings 1970 Baltimore cas & Electric Company CalverL Cliffs Nuclear Power Plant Operating License Hoarings l 1970 Noetheast Utilit.les Service Company Millstone-Nuclear Power Stallon Operating License Hearings i O i ( ~}}