ML20084J865
| ML20084J865 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/08/1984 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20084J856 | List: |
| References | |
| OL-3, NUDOCS 8405110007 | |
| Download: ML20084J865 (61) | |
Text
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,0 LILCO, May 8, 1984 UNITED STATES OF' AMERICA' NUCLEAR REGULATORY COMMISSION
'84 May go gg;,4 Before the Atomic Safety and Licensing Boardo c e t-00C;Q; :,, ' '
w.m;ct In the Matter of
)
)
LONG ISLAND LIGHTING COMPANY
)
Docket No. 50-322-OL-3
)
(Emergency Planning (Shoreham Nuclear Power Station, )
Proceeding)
Unit 1)
)
LILCO'S TESTIMONY ON CONTENTION 49 (NOMOGRAM FOR THYROID DOSE)
PURPOSE This testimony shows that the proceduren used in the LILCO Plan to calculate a thyroid dose provide a reliable basis for making protective action decisions.
The assumptions and calcu-lations used in the procedure are detailed for use in air sam-pling in documents published by the NRC, FEMA, and the Depart-ment of Health and Human Services.
The nomogram used in the-procedure is simply a mathematical tool to assist in the calcu-lations.
The contention reflects two questions rained in the FEMA-RAC review.
The first is that the nomogram is non always uced to calculate the thyroid dose from radioactivity measured en the particulate filter paper.
In resp.onse to this, the i
l 8405110007 840500 PDR ADOCK 05000322 T
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- procedure has been modified so that the thyroid dose from the radioactivity on the particulate filter paper is always calcu-lated.
The second question is whether the thyroid dose deter-mination might not be accurate due to filtration, moisture in the} containment, and other removal processes.
As shown in the testimony, these effects only reduce the amount of radioactive material released, and the air samples taken in the field can be remeasured in laboratories where no assumptions concerning the release need be made.
Thus, the procedure and the incl'uded nomogram are an ef-factive means of rapidly determining a thyroid dose so that protective actions may be implemented.
Attachments LILCO Transition Plan OPIP 3.5.2,
- p. 56 of 56, Attachment 11, p.
1 of 1 2
FEMA-REP-2 Appendix B 3
LILCO Transition Plan OPIP 3.5.1 Section 5.3.7 4
LILCO Transition Plan OPIP 3.5.2, pp. 18 and 54 of 56 5
FDA 83-8211 Appendix H-4 l
a i
L LILCO, May 8, 1984 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i
Before the Atomic Safety and Licensing Board In the Matter of
)
)
LONG' ISLAND LIGHTING COMPANY
)
Docket No. 50-322-OL-3
)
(Emergency Planning (Shoreham Nuclear Power Station, )
Proceeding)
Unit 1)
)
LILCO'S TESTIMONY ON CONTENTION 49 (NOMOGRAM FOR THYROID DOSE) 1.
Q.
Please identify yourselves.
A.
My name is Matthew C. Cordaro.
My address is Long Island Lighting Company, 1660 Walt Whitman Road, Melville, New York, 11747.
My name is Charles A. Daverio.
My address is Long Island Lighting Company, 100 Edst Old Country Road, Hicksville, New York, 11801.
My name is Richard J. Watts.
My address is Impell Corporation, 225 Broad Hollow Road, Melvi'le, New York, 11747.
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2.
Q.
Please state your professional qualifications.
A.
[Cordaro]
I am Vice President, Engineering, for LILCO.
My professional qualifications are being of-fered into evidence as part of the document entitled
" Professional Qualifications of LILCO Witnesses."
I am sitting on this panel to provide the LILCO manage-ment perspective on emergency planning, and to answer j
any questions pertinent to management.
My role in emergency planning for Shoreham is to ensure that the needs and requirements of emergency planning are being met, and that the technical direction and con-tent of emergency planning are being conveyed to cor-porate management.
I accomplish this by supervising the development and implementation of the offsite emergency response plan for Shoreham; the manager of the Local Emergency Response Implementing Organiza-tion (LERIO) reports directly to me.
[Daverio)
I am employed by LILCO as Supervisor of Emergency Planning and Regulatory Services, and have been working on emergency planning for LILCO for over L
4 years.
I am also Assistant Manager of LILCO's l
Local Emergency Response Implementing Organization (LERIO).
My professional qualifications are being offered into evidenc6 is part of the document enti-tied " Professional Qualifications of LILCO i
L
$ Witnesses."
As Supervisor of Emergency Planning and Assistant Manager of LERIO, I am responsible for im-plementing LILCO's Local Emergency Response Plan.
As such, I am familiar with the issues surrounding the calculation of thyroid dose using the nomogram which relates iodine to total fission products, as indi-cated in the LILCO Plan in OPIP 3.5.2, Attachment 11.
[ Watts]
I am the Health Physics Supervisor for the Radiological Services Section of Impell Corporation.
My professional qualifications are being offered into evidence as part of the document entitled "Profes-sional Qualifications of LILCO Witnesses."
I have been retained by LILCO to serve as Radiation Health Coordinator of LERO and have participated in LERO drills in this capacity.
As such, I am familiar with the nomogram which relates iodine to total fission products for the calculation of thyroid dose in OPIP 3.5.2, Attachment 11.
l 3.
Q.
What is Contention 49?
A.
As rewritten by the Licensing Board in its April 20, 1984 order ruling on LILCO's motion for summary dis-position of Contentions 24.B, 33, 45, 46, and 49, Contention 49 reads as follows:
i r L The nomogram which relates iodine to total fission products for the calcu-lation of thyroid dose (OPIP 3.5.2 At-tachment 11) is not realistic.
- Thus, l
there is no assurance that this proce-I dure will provide reliable data for use in making protective action deci-sions.
Accordingly, there is no com-pliance with 10 CFR Section 50.47(b)(9).
Q.
4.
What is the legal standard cited in Contention 49?
A.
The legal standard cited in Contention 49 is the fol-i lowing:
10 CFR Section 50.47(b)(9)
[
(b)
The onsite and, except as provided in paragraph D of this sec-E tion, offsite emergency response plans for nuclear power reactors must meet the following standards:
(9)
Adequate methods, systems, and equipment for assessing and moni-i toring actual or potential offsite consequences of a radiological emer-gency condition are in use.
5.
Q.
Does the FEMA RAC review to the NRC on the status of offsite emergency planning at Shoreham, dated March 15, 1984, discuss the nomogram that is the subject of Contention 497 l
A.
Yes.
The FEMA RAC review found the following:
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[T]he nomogram which relates iodine to total fission products for the calcu-lation of thyroid dose (OPIP 3.5.2 At-tachment 11) may not be realistic in this aspect [that "even without core i
damage, radioiodine may be collected on the particulate filter if the io-dine is in elemental form.
Therefore, one cannot rule out activity on the particulate filter as not being io-dine.]
Furthermore, the amount of fission products collected from a core damage accident are [ sic] highly de-pendent on a number of parameters, such as moisture'in containment, filtration of release, distance from i
the site, etc., and are [ sic] not eas-ily amenable to the nomogram assump-tions.
FEMA Review at 29.
The Licensing Board in its April 20 order found that this comment from FEMA " clearly calls into question I
an important aspect of the entire system, viz, the reliability of the projected dose data available to decision makers when the calculations are being done l
in the manual backup mode."
[
l 6.
Q.
Where was this method for measuring radioactive io-dine developed?
i A.
The method used in OPIP 3.5.2 (see Attachments 1 and i
4 to this testimony) is described in " Guidance on Offsite Emergency Radiation Measurement Systems,"
FEMA-REP-2, September 1980, in Appendix B, entitled "An Air Sampling System Developed by Brookhaven
4 3 National Laboratory for Evaluation of the Thyroid Dose Commitment Due to Fission Products Released from Reactor Containment" (Attachment 2 to this testimo-ny).
- 7.
- Q.
Then the equipment and formulas used in OPIP 3.5.2 are the same as those recommended by FEMA in the above document?
A.
Yes.
The nomogram used is only a mathematical tool which assists in doing the calculation when a calcu-lator or computer is unavailable.
8.
Q.
What is the nomogram that relates iodine to total fission products for the calculation of thyroid dose?
A.
This nomogram is contained in OPIP 3.5.2 Attachment 11 (Attachment 1 to this testimony) and is identified as "TCS Air Sampler Offsite Thyroid Dose Nomogram -
Shoreham Station."
This nomogram compensates for l
four different variables within the sampling process:
(1) the iodine to total fission product; (2) decay of l
isotopes after reactor shutdown; (3) any exposure that has taken place to the public prior to the actu-al field measurement; and (4) duration of exposure (the amount of time that the population would be inhaling radioiodine from the plume, contributing to l
a thyroid dose.)
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J 9.
Q.
How is the nomogram used in calculating expected I
doses?
A.
-A nomogram is a graphic representation that consists of several lines marked off to scale and arranged in I
such a way that, using a straight edge to connect l
l known values on two lines, an unknown value can be l
read at the point of intersection with another line.
i It is essentially a mathematical tool that is of as-sistance when used in a calculation methodology.
3 To calculate doses under the LILCO Plan, personnel go
[
to the field and take measurements as described in OPIP 3.5.1 Section 5.3.7 (Attachment 3 to this testi-mony), and in OPIP 3.5.2.
These measurements are l
used in a calculation worksheet that directs the per-l L
son performing the evaluation to the nomogram.
The nomogram is used in making a series of calculations resulting in a total thyroid dose for the area in i
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which the air sample was taken.
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i
- 10. Q.
What is meant in the FEMA RAC review and the conten-l tion by the statement that the nomogram is "unre-i j
alistic?"
l A.
The FEMA review noted two areas in which FEMA thought the nomogram was unrealistic.
First, FEMA commented that without core damage, radioiodines may be b
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Therefore, it is conceivable that the activity measured on a particulate filter may be
-iodine.
'The second question in the FEMA comment notes that the amount of fission products collected from the core damage accidents is highly dependent on a number of parameters such as moisture, containment filtration of release, and other removal mechanisms that are not easily amenable to the nomogram assump-tions.
It is for these reasons that the FEMA review questions whether the nomogram is realistic.
- 11. Q.
As to the first concern, does the nomogram account for particulate iodine that may be collected on the particulate filter paper?
A.
Yes, the nomogram does account for particulate iodine l
collected on the filter paper.
A radioactive plume released during an emergency could consist of gaseous i
l and particulate material.
Both of these types of emissions could include radioactive iodine, which, when inhaled, would result in a dose to the thyroid.
The TCS Air Sampler System used in the LILCO Plan consists of an air pump and a sampler canister which l
l is filled with absorbent material and surrounded by a l
l particulate filter.
The outside filter is a very fine paper which is designed to trap particulate l
t
. material.
Particulate material present in a release could consist of radioactive iodine and other non-iodine particulates.
The inner canister contains an absorbent material that collects radioactive iodine only in gaseous form.
Thus, when the air sample col-lection is completed, the amount of radioactive io-dine collected in the inner absorbent material and on the outer particulate filter must be determined.
This is done in the field by use of a radiation sur-vey instrument, or in the laboratory using radiation analysis equipment.
The absorbent material in the inner canister would contain only radioactive iodine.
This measurement would require only correction for radioactive decay of the iodine from the time of re-acto'r shutdown to the time of sampling.
However, the outer filter paper may contain both io-dine and non-iodine particulate material.
The nomogram procedure assumes a certain mixture of io-l dine and non-iodine particulate material to be pres-ent on the filter paper; the radioactivity of this mixture is further assumed to vary as a function of time.
Thus, the nomogram allows one to calculate how much of the measured radioactivity on the filter l
paper is due to particulate iodine at various points in time.
l I
. i The nomogram procedure then allows the total thyroid dose from gaseous and particulate iodine to be calcu-lated.
This is accomplished by determining the gas-eous and particulate components of the thyroid dose separately, and then adding them.
- 12. Q.
What was the origin of the FEMA RAC review comment?
A.
The LERO procedure OPIP 3.5.2 states in notes on pages 18 of 56 and 54 of 56 (Attachment 4 to this testimony) that unless there is core melt or fuel i
l I
damage it is not expected that there will be any io-dine released in particulate form and therefore no iodine radioactivity will be found on the filter paper.
Thus, it is not necessary to calculate a thy-roid dose from the filter paper measurement but only from the inner canister.
Pursuant to FEMA's comment that even without core melt or fuel damage, ra-dioiodine may be released and collected on the particulate filter paper, the procedure will be modified in future revisions to the LILCO Plan to re-move the notes on pages 18 and 54.
Thus, the ra-dioactivity measured on the filter paper will always be included in the thyroid dose calculation.
. Q.
13.
As to the second concern, is the nomogram realistic?
A.
Yes.
The determination of the radiciodine fraction of the fission product release was based upon an t.
analysis of different release scenarios for BWR acci-dents.
The procedure uses a most probable io-dine / total fission product ratio for the accident scenarios analyzed.
- 14. Q.
Is the ratio used in OPIP 3.5.2 the same ratio recom-mended in the FEMA REP-2 report?
A.
Yes, it is.
f
- 15. Q.
Can valid thyroid dose determinations be made using this methodology?
A.
Yes.
As discussed above in this testimony, the particulato component of any accidental release will be accounted for by the TCS sampler method by always l
checking for the presence of radioactivity on the i
outer filter paper following sample collection.
Because radioactive material detected on the filter l
paper is likely to include a mixture of iodine and non-iodine particulates that varies with time, the l
nomogram includes a correction step to account for i
this variation.
The nomogram correction reflects the most probable ratio of particulate iodine to total l
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particulates as a function of time. When filter can-l t
isters are later reanalyzed by a laboratory, the spe-cific particulate mixtures present will be deter-mined.
It should also be noted that the nomogram correction for particulate mixtures was based upon BWR accident scenarios, which predict significant releases of ra-dioactivity in particulate form (known as dry release cases).
However, when other parameters are consid-ered, such as containment moisture, filtration, and other physical chemistry conditions, these influences would have the effect of suppressing the release of particulate material.
Little, if any, iodine or non-iodine particulate material would therefore be likely to be detecte.ble in the field.
Accordingly, the particulate iodine component of any computed downwind thyroid inhalation dose would be greatly decreased in magnititude.
This would also diminish the signifi-cance of any uncertainty associated with the mixture of iodine and non-iodine particulates assumed to be present.
Q.
16.
Is this method (supported by the equipment, proce-dures,'and calculations used in the LILCO Plan) rec-ommended by any agency other than FEMA?
~ -
. i A.
Yes, the same methodology and assumptions are de-I L
tailed in Appendix H-4 of" Preparedness and Response in Radiation Accidents:
U.S. Department of Health i
and Human Services," FDA 83-8211 (August 1983) (At-tachment 5 to this testimony).
i Q.
17.
Will this method provide reliable data for use in l
making protective action decisions?
r l
r A.
Yes.
The method identified will provide an accurate and dependable means of determining the thyroid dose to the exposed population during the early stages of 1
an emergency when the determination and imple-mentation of protective actions are most critical.
In a slowly developing emergency where there is the l
potential for a release or where a radiological re-
[
lease takes place over a given period of time after the reactor shutdown, protective actions would be i
[.
recommended based upon factors that include plant l
conditions, in-plant radionuclide measurements, and i
environmental survey measurements.
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't APPENDIX 8 AN AIR SAMPLING SYSTEM OEVELOPE0 BY BROOKHAVEN NATIONAL LABORATORY FOR EVALUATION THE THYROID DOSE COMMITMENT DUE TO FISSION PRODUCTS RELEASED FROM REACTOR CONTAINMENT 8.1 Introduction Inhalation of radioiodines is expected to be the most important initial pathway of human exposure in the event of a release of radioactivity during a nuclear power reactor incident.
c The thyroid gland will there-fore be the critical organ and will receive the largest dose should an accident occur.
Consequently, a method for monitoring for radiofodines, in the presence of fission gases (e.g., 133Xe), which would be released in much larger quantities than radiciodines and particulate fission products, must be developed to provide a data base for exposure control.
Costly measurement methods using gamma analysis can be avoided by developing a sampler specifically for iodine, thereby permitting any beta or gamma detector to be used for measurement (Figure B-1). Particulate fission products include dozens of noniodine radionuclides. Use of a profilter (Figure 8-2) before the adsorber bed separates the activity into gaseous and particulate fractions, and allows a determination of gaseous radiofodine.
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L ~. ' J Figure B.1 Canister evaluation with a CD V 700 GM counter.
l B-2 l
L
i il I. -
Figure B.2 1
{
l I
l' l
t 1
I O
ADSOR8ER BED I
PREFILTER
- ;. '*. -'4,.,} ~7,
.A.
s l
t 1
Figure B.2 Canister assembly.
1 I
i B-3 id L.
L
~
Adsorption of fission gases relative to iodine can be reduced by appropriate inorganic adsorber.
Several commercial inorganic adsorbers were tested, but were too expensive or inefficient for the organic o*r hypoiodous acid forms of iodine.
A silver impregnated silica gel adsorber was developed that has over 90% efficiency for collection of radiofodin for sampling times of several minutes.
The material provides corresponding xenon efficiencies of less than 0.04% at temperatures above 7*C, The air sample size needed for reliable detection of a given air concentration depends on detector sensitivity, flow rate, and sampling time.
Field monitoring under accident conditions requires prompt measurements for proper use of time, equipment, and operator exposure For these reasons, the Federal Interagency Task Force on Offsite Emer gency Instrumentation for Nuclear Incidents set a maximum of 5 minutes for air collection.
Two degrees of freedom remain:
detector sensitivity and flow rate.
Flow rate is governed, in part, by the power available for air movemen I
A?r sampling away from power lines requires portable generators or derived from automotive electrical systems.
Battery power supplies are inappropriate due to excessive weight and expense.As mentioned earlier, the desirable solution is a significant number of inexpensive air sam apparatus.
Thus, use of automotive electrical systems is the least l
expensive solution (Figure B-3).
Two power connections to automotive i
batteries are economically possible:
i direct clamping or use of cigar itghter sockets.
The safer and generally better solution is the latter.
8-4
[
FIGURE B-3
~.
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'""~
~
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l A
'.~.h
^'
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Figure 8.3 Sample collection utilizing 12V d.c. power from an automobile cigar lighter socket.
B-5
~
Factory installed wiring limits this source to about 150 watts.
Vacuum motors of this size can move 4 to 7 cfm through the pressure drop of an adsorber-filter thereby setting the flow rate at 5 cfm.
For operational fle'xibility, the air sampler can also be used on standard 110V a.c. power.
Air flow regulation and control assures a uniform sampling rate for either power source.
The remaining variable is detector sensitivity.
Economy and long-term calibration stability make Geiger-Mueller detectors desirable.
GM detectors are known for high beta and low photon efficiency.
- However, photon sensitivity can be increased by changing the standard GM tubes, with stainless steel cathodes, to ones with higher Z' cathodes.
There-fore, a CD V-700 GM instrument, used with a high Z cathode Victoreen 6306 tube, may be used to provide the sensitivity desired for this sampling l
system.
8.2 The Air Mover The air mover housing, shown on Figures B-4 and B-5, consists of a l
tubular support structure, a front and back plate, and a perforated motor impeller safety guard.
The tubular structure contains a handle, two plate mounting rings and a switch mounting hole.
i l
l l
The front plate is shown on the lower right on Figure B-4.
The filter adsorber canister is placed on the central suction tube and retained with B-6 l
m
I i
2 6
b' HOUSING
)
e 3
lMLLER GuggaO A.C.SPEEDCONTROL
~%
E ca
- l 4
m' s,
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IhePELLER l
ELT SEALtNG
. GASKET FOR Nssygg FLOW A m ugyggggCREv e
I I
l
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I Figure !!.4 Air mover components: Exterior view of vacuum hulkheads.
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the rubber cord.
The flow rate control screw is located in the central suction tube and is used to adjust spring tension on the bellows.
The remaining two holes ventilate the interior of the bellows to maintain normal atmospheric pressure within the bellows.
A rear view of the bellows is shown on Figure 8-5.
The bellows consist of two metal cups, one attached to the front plate and the other capable of longitudinal movement.
The flow rate control screw is used to adjust the spring loading.
This tends to direct the movable bellows half toward the front l
plate, closing the air bleed port shown to the left of the spring.
During motor operation, the reduction in atmospheric pressure will counteract the loading spring, opening this port.
Thus, spring i
adjustment controls the pressure inside the air mover.
The difference between ambient pressure and pressure in the air mover governs the flow rate through the filter adsorber.
Dust loading is not a problem for the 5 minute, 5 cfm sample.
The rear plate serves as a vacuum bulkhead and as a mounting plate for l
1 the dual volta 3d motor and a.c. speed control.
The impeller and a.c.
f speed control adjusting stub are shown in Figure B-4.
The remaining perforated plate protects the operator.
The dual voltage motor is designed for about 240 watts on alternating current, nearly double the d.c. power value.
A 600 watt household lamp dimmer is used to reduce the a.c. power for the proper flow rate.
l Direct current power is derived from the cigar lighter socket of any 12 V vehicle.
An adapter plug provides for d.c. operation.
B-9
f a
l l
l l
I B.2.1 Initial and Periodic Flow Rate Adjustrent
)
The air mover is operated at 12.8 V d.c. measured at the cigar lighter socket.
A filter canister is connected to a venturi flow rate meter which in turn is connected to the air mover suction tube with Tygon
)
tubing.
A venturi flow meter is a straight through flow device that operates with an acceptable pressure drop of about 0.25 inches of water.
The flow rate is adjusted to 5 cfm by alterriately disconnecting, adjusting
~
i the flow adjusting screw shown on Figure B-4, and reconnecting the Tygon tubing to the air mover suction tube.
The dual voltage motor develops about twice as much power on a.c. as it does on d.c.
For proper balance the a.c.. voltage must be reduced.
After d.c. adjustment, the adaptor. plug is removed and the air mover is l
operated on 110 il volt a.c. power.
The a.c. speed control stub shown on Figure B-4 is turned to provide an indicated flow of 5 cfm.
c l
l l
Air flow control characteristics for a.c. and d.c. power are shown on i
Figure B-6.
The regulated d.c. flow rate change is less than 0.4%' per 1%
l voltage change, while the regulated a.c. flo'w rate change is about 0.8%
per 1% voltage change.
B.3 An Inorganic Adsorber with Low Noble Gas Ratention A silver loaded silica gel has been developed as an adsorber for air monitoring subsequent to a release from containsent power reactor accident.
s-10
i FIGURE B-6
---UNREGULATED ( BELLOW
/
6.O DISABLED)
/
/
REGULATED
'/
5.5 (BELLOW IN USF)
/
/
/
5.0 G
5.5 E i
/
T CURRENT C
~
4.5 D
5.0 4.0 ff 4.5
/
/
I 3.5 95 10 0 l10 120 130 *0 4
a.c. VO LTS 1
I I
i I
I l
I I.I 11.6 12.8 13.9 15.0 d.c. VOLTS Figure B.6 Flow rate regulation.
l 6
i 1
a-11
Requirements of high efficiency for known radiofodine species under wide t
ambient conditions of humidity and temperature and low noble gas adsorption efficiency are satisfied by the material.
i Silver loadings fr'om 2 to 24% by adsorber weight have been tested against organic radioiodine, hypoiodous acid, elemental radiofodine, and noble fission gases.
Relative humidity was varied between 5 and 99%, and stay times of 0.11, 0.073, and 0.055 seconds were used.
Silver loading requirements depend on sampling duration and relative humidity.
Environmental monitoring requires about 25 ft3 of air be sampled and analyzed for a dose projection.
The proposed analysis system consists of an air mover, an adsorber and a civil defense readout instru-ment fitted with a special 6306 probe which is discussed in Section 4.
This combination provides adequate sensitivity for dose predictions.
A i
silica gel adsorber can be used with a 4% silver loading for an efficiency of better than 93% with a 0.11 second stay time, and for all ambient I
conditions tested.
Similar tests using 4% silver loaded 13X molecular i
sieve or about 60% silver zeolite yielded lower efficiencies.
r i
Xenon adsorption was less than 5 x 10-3% at $40C t't! no post-release flushing.
This value was about 1/20 of t.a vo'.s.
1
, ar charcoal under tne same conditions.
l l
i i
f l
L 8-12
B.4 High Photon Sensitivity GM Tubes Geiger-Mueller detectors are sensitive to ionizing events initiated by energetic charged particles within the active volume.
To increase photon sensitivity, GM detectors should have high Z materials i
within the active volumes.
Bismuth is the optimum material since it is the highest Z non-radioactive element.
Victoreen 6306 GM detectors contain bismuth coated wire mesh screens
. positioned around the cathodes.
Wire screening is used to increase the cathode surface to volume ratio and thereby increase sensitivity.
Organic quenching must be used due to the chemical reactivity of bismuth with the halogens.
l TGM Detectors, Inc. supplied a number of halogen quenched counters with L
platinum plated cathodes.
Type NP 358 detectors, with an inside diameter of 15.2 mm, were shortened by TGM to 9.8 cm.
All of the GM tubes were operated with a standard CD V-700 instrument adjusted to 900 volts.
s 8.5 Energy Response Measurements GM detector energy responses were measured with heavily filtered x-rays and isotope sources.
Some of the isotope sources used to determine l
t 131 detector energy response were I (365 kev), 137Cs (662 kev) and L
Co (1250 kev).
X-rays from 74 to 200 kev effective energy were also used.
t B-13 l
a The measured energy responses of four bare Victoreen detectors a in Figure B-7.
Good agreement between measurements and sales literature exists below 365 kev, while a sensitivity more constant with energy w measured above.
GM detector filter calculations were made to design a shield to attenuate the principal xenon decay photons more than the iodine, where the calculated and measured response is shown in Fig for a two element concentric filter of 0.127 cm Pb adjacent to the GM tube followed by 0.08 cm Cu.
The shield and 6306 tube are shown in Figure 8-8.
A comparison of the bare tube 135 I3I Xe to I ratio of 350/185 m 1.9 to the filtered tube ratio of 123/125 a 1 indicates that the shielding reduced the xenon to iodine response ratio by a factor of approximately 1.9.
The remaining xenon isotopes have lower energy decay gamma rays and are reduced by much larger factors.
Air sampling for iodine involves adsorption of gases and filtration of particles on a cylindrical canister.
Readout requires the insertion of a shielded GM detector into the axial suction hole in the canister, as shown in Figure B-2.
The energy response of the 6306 probe within a canister with 4% by weight silver leaded on silica gel is shown in Figure B-9.
Calculations indicate that approximately 50% of the adsorbed organic iodine is in the first 0.4 cm of adsorber.
To better account for
(
photon attenuation, a 0.4 cm void is placed in the periphery of the adsorber bed and oriented normal to the photon beam.
C i.
8-14
FIGURE B-7
_iiii1 i
i i i i i s ig i
i i i i i ii i
[
'IT BAREI3)
,y
/
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CALCULATED /
$100 SHIELDED,/
IBARE, MEASURED B
s x
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i i
E r
,i /
S
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l' O
s SHIELDED 1
', MEASURED lV I
ENERGY CORRECTION FOR THE 10 l
VICTOREEN 6306 BISMUTH 2
l LOADED GM TUBE WITH A 0.127 cm Pb + 0.08 cm Cu SHIELD l
30 20 10 0 103 E, kev l
Figure B.7 Energy response of bare and shielded 6306 GM detectors.
l l
l B-15
_. I' FIGURE B-8
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FIGURE B-9 I
e i iiisil i
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06 GM
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Figure B.9 Shielded probe exposed in 4% Ag-gel canisters.
P k
r i
l B-17 I
i B.6 Summary of Results The critical GM detector requirement was taken to be the evaluation a.
of air samples containing mixed fission products.
b.
A filter was designed to attenuate the xanon decay photons more than I3I I photons.
v c.
The energy' response for a probe having c filtered 6306 detector was measured.
The energy response was also determined with a 6306 GM tube in a 4% Ag gel loaded canister.
d.
In general, the 6306 GM tube was found to be more sensitive for photons from 0.25 to 0.5 MeV than the CD V-700 GM instrument with its standard GM tube.
l AIR SAMPLING PROCEDURE P
Procedures are given for equipment check and field air sampling, evaluation of the exposed filter-adsorber canisters, and internal thyroid dose equivalent 1
predictions for the people living in the measured area.
In order they are:
i I.
Equipment Check and Field Air Sampling 1
l A.
The air sampling system l
1.
Air mover.
1 I
B-18 1
o 2.
Automobile, 12 volt cigar lighter adapter.
3.
One or more quart cans each containing one filter-adsorber canister.
Take one can for each location you are to measure and one spare.
4.
CD V-700 GM counter modified with a 6306 GM tube.
5.
Screwdriver or 25 cent coin to open the quart can lids (immediately before use).
6.
Pocket or wristwatch to time the 5 minute t6 second sampling period.
7.
Respirator, one per person, optional.
B.
Equipment checkout 1.
Turn on the, modified CD V-700 and test for an on-scale meter deflection of about 50 to 100 counts per minute on the X 1 l
range.
The meter will jitter around on an average reading.
i Read the midpoint value within the jitter band.
l 2.
Test the air sampler for operation with normal household a.c.
[
electric power.
Plug cord into a wall outlet and push the start switch near the handle.
For proper operation, the t
sampler will sound and feel like a small vacuum cleaner.
3.
Take all of the 7 items of part A plus a map and/or route instructions to a car or truck.
4.
Plug the d.c. adapter on the end of the sampler power card into the cigar lighter or using the adapter make contact across the battery terminals and test sampler operation using the car l
r r
8-19 L
~
electrical systems with the engine running.
Turn the sampler off.
C.
Air sampling procedure 1.
Drive to the first location, keeping vehicle windows closed.
2.
Park at the first location, leave engine running, open the 1
1 first quart can, and remove the filter-adsorber canister.
l 3.
Mount filter-adsorber canister over central suction tube and stretch rubber retainer over the ' outer end of the canister.
4.
Check to see that the air sampler is plugged into the cigar lighter socket and step out of the vehicle to the relaxed extent of the power cord.
Keep vehicle door closed to the extent possible while allowing the power cord outside vehicle.
5.
While' holding the sampler about 4 feet above the ground, turn on for 5 minutes +6 seconds.
i 6.
While the sample is being taken, mark the location code of this
{
first location on the can using a two part peel-away label similiar to Figure B-13.
After filling out both parts of the
'i i
label, remove the peel-away part and mount on the page of the data notebook.
Include any supplementary information on the sample next to the label in the notebook.
During this sampling period a team member will make gamma measurements at 6 inches and 4 feet above the ground and inside the vehicle.
These l
readings will be added to both parts of the label with any l
supplementary notes added in the notebook.
l B-20 l
l 1
L
7.
When the air sample is completed, carefully remove the canister from the sampler and insert the modified COV-700 probe into the air suction tube of the canister.
This measurement will be made at either 4 feet above the ground or inside tha vehicle (depending on which locatian has the lowest reading).
Record which location is used, the reading obtained and the reading of the canister.on the part of the label marked Evaluation, as illustrated.in Figure B-13.
8.
If the reading at 4 feet or inside the vehicle is greater than 10% of the count rate obtained from the canister, the measurement should be performed at another location where these readings are below this level.
For example, if the canister count rate is 2,000 c/m, then the reading at either 4 feet or inside the vehicle should be less than 200 c/m.
9.
Locate the tape on the outside of the canister.
Pull the tape and remove the glass fiber cloth.
Return the filter into quart can using a paper tissue for handling.
10.
Read the bare adsorber canister and record this final entry and date on the label.
11.
Return the canister to its quart can containing the filter cloth and reseal with the correct lid.
12.
Report data to EOC by radio or whatever communications system has been made available.
13.
Drive to the next location and using a new canister repeat steps C2 through Cl2.
If previous canisters have indicated high activity, stack them away from a newly raeasured one.
B-21
II.
Internal Dose Predictions The following calculations should be made at the EOC as.the data is received from the monitoring teams in the field.
A.
Glass filter cloth evaluation l
1.
Use Figure B-10 to account for the radiciodine on the glass filter cloth for each set of measurements received.
Note the type of reactor (BWR or PWR), and determine the number of hours between shutdown and time of measurement.
l l
2.
Find the iodine to total released fission products correction 1
factor (CF) on the vertical axis and calculate the difference in filter-adsorber and adsorber readings.
This difference (D)
L is due to total fission product activity on the filter.
The product CF x 0 is the corrected filter reading (F) at the time of the acasurement due to iodine on the filter.
l B.
Filter-adsorber evaluation 1.
The adsorber net counting rate (N) is determined by subtracting background (B) from the bare adsorber measurement (G),
i.e.,
the adsorber with a glass fiber cloth removed, t
N=G-B l.
B-22
l Figure B-10 I
i 1.0 g
g y
g g
t PWR TPRoeg,,,
t a
t E
i 8
5 i
S 3
s s%
o s
i s
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r g
a
~~,
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~
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5 l
%sr,,*** ele; j
i I
I 0.1 1
10 100 HOURS AFTER SHUT DOWN Figure B.10 lodhe to total fission products correction factor for shielded CD V-700 instruments.
l.
[
B-23 l
r
2.
Add the corrected filter reading (F), step 2 of Section A, to the 9
not adsorber reading to obtain the total iodine counting rate (R).
R=F+N 3.
Enter on your label the total iodine counting rate found in step 2, on Section 8.
From Figure B-11 follow a vertical to the number of hours after reactor shutdown that the bare reading (G) was made.
The ordinate is the predicted thyroid dose commitment to a 5 year old child at the site of the air sample for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> immersion.
4.
If the immersion time is greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then Figure 8-12 can be used for the dose commitment to the 5 year old child.
For example, where the dose commitment (H=) for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> immersion is I rem, and the anticipated immersion time is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, multiply 1 rem x 2.5 = 2.5 rem.
C.
Evaluation of results The projected dose commitment values can be posted on a map corresponding to their locations.
If sufficient measurements were made, the location of the plume should be defined by significantly
' higher readings.
Predictions can be made of the dose commitment along the plume pathway.
This should improve the data base so that decisions can be made about stable iodine feeding, evacuation of exposed persons to reduce exposure to resuspended radioactive particles, and designath of contaminated pasturage.
I 8-24 m
g
___._m,_____._~_.4
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I B-25 i
FIGURE 8-12 100.0 30.0 20.0 b 15.0 0
[
! 10.0 l
t
/
7.0 5.0 7
3.0 2.0
/
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1.5 1.0 '
0 2
3 5
10 15 20 30 50 70 100 INHALATION DURATION, HOURS Figure B.12 Correction factors for cloud immersion times longer than 2 8-26 1
6
.o P
Figure 8-13 l-4 Location Time (Air Sample)
Date Area Reading at 4' c/m Area Reading at 6" c/m EVALUATION Location Reading (at
)
c/m Canister c/m Adsorber c/m Canister-particulate fdter Time Date Figure B.13 Sample fdter-adsorber canister label.
l i
4 l
B-27
~
i Appendix B.
Biblicaraphy 1.
U.S. Nuclear Regulatory Commission.
Reactor Safety Study - An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014), U.S. Nuclear Regulatory Commission, Washington, D.C.
20555 (October 1975).
t 2.
C. Distenfeld and J. Klemish, An Air Sampling For Evaluating The Thyroid Dose Commitment Oue To Fission Products Released From Reactor Containment, l
NUREG/CR-0314, BNL-50881 (November 1978).
3.
C. Distenfeld and J. Klemish, Environmental Radioactive Moitiroing To Control Exposure Exnected From Containment Release Accidents, NUREG/CR-0315, BNL-50882 (November 1978).
f l
f l
l l
l 6
8-28 b
~. -
l i
i l
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l 4
i 1
l r-I 1
L
=
.. to i
LILCO Tsatimonv on Contantion 49 i
OPIP 3.5.1 L
Page 5 of 53 t
and record these readings on Attachment 2.
l (If the 4 foot reading is noticeably higher than the 3 inch reading, it should be assumed i
that the predominant gamma source is the i
airborne plume).
l b.
If readings l'ncrease with decreasing height above the ground, assume that the source is on the surface.
In this case, take several i
smear samples (with gloves) over a 4" x 4" area of the ground and/or a soil sample when conditions permit.
t c.
Use a plastic bag for the soil sample and i
j fill out a label to tag the bag.
Label all l
samples with proper ID information:
sample j
number, sample location, initials, date, time, and team ID.
j
(
r i
d.
When monitoring, periodically check beta l
(open window of RO-2A) reading at 3 inches l
and 4 feet above ground.
Record any readings significantly different from the window-closed !
readings.
l 5.3.7 At the survey location, take an air sample, as
[, Item 10 (gical Survey Briefing Form, l required by the Radiolo 2), as follows:
plug in Leaving the vehicle engine running,for about l
a.
the TCS-EAS-1 air sampler.
Run it a 1/2 minute, warm-up period without the l
filter / canister installed.
j 1
b.
Open the TCS EAS-1 one quart can containing the canister.
Inspect the canister for visi-ble defects; the canister is not acceptable l
for use if the moisture check dot is blue.
l i
c.
Turn off the warmed-up sampler, center the canister over the auction opening on the side L
of the sampler.
Stretch the elastic retainer over the outer and of the canister, making l
sure the fit is tight.
l i
i d.
Position the air sampler 4 feet above the ground, as far away from the vehicle exhaust j
pipe as the cable will allow.
Rev. O 5/12/83
I OPIP 3.5.1 Page 6 of 53 e.
Adjust the flow rate to approximately 5 CFM.
i Set the timer to 25 5 minutes.
i
=
UFR (Rotate dial past the 5-minute mark, then turn back.)
l 4
4 f.
Start the sampler and record the starting flow rate on the ORS Data Sheet, Attachment f
2.
Use a stop watch to verify the run time.
l l
g.
When the air sample time is completed, record the final flow rate reading on the ORS Data 5
Sheet, Attachment 2.
Carefully remove the l
canister from the' sampler and put it in a j
plastic bag.
Avoid contact with the white i
filter cloth wrapped around the outside and i
the bare filter.
Be sure to record start /st6p!
times and flow rates on the ORS Data Sheet, l.
i i
h.
Connect the brass-shell GM-1 probe cable to the RM-14 count rate meter to " DETECTOR" input !
connection (see Attachment 5, Op' RESPONSE" to eration of Eberline Model RM-14).
Switch
" SLOW".
In this position, allow 20 seconds meter response time for each measurement.
l
.t 1.
Using the above setup, measure the background l
at 4 feet above the ground or inside the t
vehicle.
Record this background cpm on the r
ORS Data Sheet, Attachment 2.
J.
Insert the GM-1 probe into the center hole of the canister and adjust the scale of the RM-14 ;
as necessary.
Record the stabilized filter /
canister reading (cpm) on the ORS Data Sheet, Remove the GM-1 probe.
l I
k.
Cerefully remove the white fiber cloth which is wrapped around the canister by pulling the red tape on the top rim of the canister.
Hold t se canister in the plastic bag while r
doing this to avoid contacting the cloth and 4
to prevent silver zeolite crystal bits from i
falling out after the cloth wrsoping is removed.
Return the fiber clot s to the quart. !
can.
J I
{
I i
Rev. 0 5/12/83 i
,--.._..-w-
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--n-----c,
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[o OPIP 3.5.1 Page 7 of 53 1.
Insert the GM-1 probe into the center hole of the ce.nister and record the stabilized bare canister reading and time of measurement on the ORS Data Sheet, Attachment 2.
Place the bare canister with the plastic bag a.
l into the quart can and label the can with the following information:
Data and time of sample Map location Start and stop time Starting and ending flow rate Sample number (sequential)
Team ID n.
Place the quart can inside a plastic sample bag and ensure that a label is attached.
i o.
Report the ORS Data Sheet information for the air sample to the ESF.
5.3.8 Report dosimeter readings to the ESF at regular intervals (see OPIP 3.9.1, Dosimetry and Exposure I
I Control).
I t
i 5.3.9 Immediately report any equipment or supply l
shortages to the ESF.
5.3.10 Repeat Steps 5.3.2 through 5.3.8 as necessary for j
other survey locations.
j 5.3.11 When all survey and sampling activities are com-plated and the team receives no furt'her requests from the ESF or the team is relieved by a second team, return to the Emergency Worker Decontamina-tion Center, in Brentwood, unless instructed otherwise by the EST or the RAP Team Captain.
5.3.12,Do not remove protective clothing or respirator until instructed by Emergency Worker Decontamina-tion Facility personnel (see Attachment 6, Section i
5.5, Removing Protective Clothing; Attachment 6,
(
Section 5.7, Step-off Pad Use; Attachment 7, Section 5.5, Removing Respirator).
{
Rev. 2 10/18/83 a
1 i
I i
1 i
i 1
l I
i I
Attachmsnt 4 to LILCO Testimony r
on Contention 49
[
f i
l OPIP 3.5.2 i
Page 18 of 56 l t
i e
d.
Move vertically down until the time between l
reactor shutdown and time of measurement, item 8, is intercepted; if the start of
(
radiation exposure coincides with the time of j
measurement, move to the line marked Te = Tm.
i t
e.
Nove horizontally to the right until duration
[
of exposure, item 13, is intercepted.
[
f.
Move vertically up until the sample collection !
interval, item 2, is intercepted.
i
.g.
Move horizontally to the right to read off the thyroid dose commitment for the bare canister.
Record this in item 14a on the t
Thyroid Dose Commitment Worksheet, Attachment 9.
{
l 5.6.7 Filter Component l
NOTE:
If core or fuel damage has not occurred, no iodine release in particulate form is expected and any filter radioactivity will be void of iodine.
The total dose commit-ment value, item 15, will be the bare l
canister component only.
Otherwise, com-l plate the steps below.
[
i l
a.
Locate the net filter adsorber reading, item i
5, on the lower left-hand axis of the Thyroid Dose Commitment Nomogram, Attachment 11.
Move horizontally to the right until the slanted line corresponding to the number of hours between reactor shutdown and time of measurement, item 8, is intercepted.
l r
b.
Move vertically up until the time between reactor shutdown and measurement, item 8, is intercepted; for time values greater than 72
[
hours, use the line marked I-131.
l t
c.
Move horizontally to the right until the time i
between reactor shutdown and start of expo-r sure, item 12, is intercepted; if the start l
l of radiation exposure coincides with the time of measurement, move to the line marked Te =
Tm.
i
[
Rev. O i
I 5/11/83
[
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_ _. n __..... _. _._, _ _,, _ __
o f
i OPIP 3.5.2 Page 54 of 56 t
i Page 2 of 2 i
THYROID DOSE COMMITMENT WORKSHEET (continued) i 6.
Has core or fuel l
damage occurred?
l (yes or no) 1 7.
Time of reactor shutdown houra l
8.
Time between shutdown and measurement (item 7 - item in) hours l 9.
Time release started hours
[
i 10.
Plume travel time i
(item ic/ ground or elevated-windspeed (mph))
hours l
- i 11.
Time exposure started (item 9.+ item 10) hours !
12.
Time after shutdown exposure started (item 11-- item 7) hours.
13.
Release duration hours j
i 14.
Thyroid Dose Commitment a.
Bare canister component rem l
b.
Filter / canister f
component rem l
NOTE:
If item 6 is "No," then filter / canister component is zero.
7 15.
Total thyroid dose commitment i
(item 14a + item 14b) rem l
l I
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Rev. O 5/11/83 t
1
.,_._t.._
e L_
-A h
5t EE^8 men HHS Publication PDA 83 8211 i
on Contention k9 l
i l
l t
~
Preparedness and Response
)
in Radiation Accidents Sernard Shieien, Pharm.D.
l Certified Health Physicist, A8HP e
Office of Health Physics i
l l
t l
i HO CoRaboraeng Centers for-f W
W* A6aenst Nonesces Radiations
$tandardizate of Protocuon j
- Trainies and General Tasks in madunon w one l
. Nucwar mene r
e i
August 1983 f
U.S. DEPARTMENT OF HEALTH AND HUMAN SERVICES Public Health Service l
Food and Drug Administration Naglonel Center for Devices and Radiolopcal hlth l
Rocliville, Maryland 20057
(
i t
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l APPENDD' H-4 AIR SAMPLING PROCEDURE (from Distenfsid at Klemish, NUREG/CR-0314, USNRC, December,1978)
Procedures are given for three phases of the task. TW are equipment check and fleid i
air sampling, evaluation of the exposed filter-adsorber cantr'ers, and Internal thyroid dose g
equivalent predictions for the people living in the mtasured area. In order they aret i
- 1. Equipment Check and Field Air Sampling A. The air sampling system 1.
Air mover, similar to a vacuum cleaner 2.
Automoblie,12-mit cigar lighter adapter j
3.
One or more quart cans each contalr.Ing one filter adsorber canister. Tae one can for each location you are to measure and one spare.
i 4.
COV-700 G M counter j
S.
Pocket lanization chamber I.
r A.
% rewdriv c nr N ant enin en apan tha quart can lids (immediately before j
use).
l 7.
Pocket or wristwatch to time the S-minute 16-second sampling period.
8.
Respirator, one per person, optional.
8.
Equipment checkout l
1.
Turn cn the COV-700 and test for an on-scale meter deflection of about 10 to 30 counts per minute on the times I range with probe shield closed. The f
meter will jltter around on an average reading. Road the midpoint value within the jitter band. Reject an Instrument for zero reading or too high a reading in place where other CDV-700's read much lower. Twist metal t
shi.Id npen on penha and mnvn towed the test spot on right side of instru-ment. Meter should go t@scalo as probe moves toward spot. Close the l
probe shield and allow the instrument to remain on.
l
}
2.
Test the air sampine for operation with normal household AC electric power.
l Plus cord into a wall outlet and push the start switch near the handle.
For proper operatinn, the sampler will sound and feel like a small vacuum cleaner.
.- 3...-P.exero pocket lonisation chamber.
l I
4.
Take all of the seven items of Part A plus a map an?/or route Instructions to a car or truck t_tyt has a woewna ciw unhterr.
i S.
Plug the DC adapter on the end of the sampler power cord and test for
--" -semotervathm-dyg-tine c.ar vlecidta! mystem with the engine running.
l Twn the sampler off.
f l
I
o s
C. Air sampling procedure 1.
Keeping vehicle windows closed, drive to the first location.
i 2.
Arriving at the first location, leave engine running, open the first quart can, and remove the filter-absorber canister.
3.
Mount filter-absorber canister over central suction hole and stretch rubber retainer over the outer end of the canister.
4.
Check to see that the air sample is plugged into the cigar lighter socket and step out of the vehicle to the relaxed extent of the power cord.
5.
Turn on the sampler for exactly 5 minutes 6 seconds.
6.
During this period, the other team member will measure the general area
[
outside of the vehicle with the CDV-700 and will record the t me of day.
location, and general area reading on the empty quart can top abel similar to Figure A-4.
7.
When the air sample is finished, remove the cannister, replace in its quart can, and reseal can. Note: The canister may be warm to hot due to adsorption of moisture from the air, NOT radioactivity.
8.
Go to the next location and use a new canister.
l 9.
After the last measurement return promptly to the center for analysis of the filter-adsorber canisters.
i f
H. Evaluation of the Filter-Adsorber Canisters l
A.
Filter-adsorber readout can be accomplished by the measurement team or by another designated person.
1.
First check out a special modified CDV-700 instrument for operation. This instrument should have a background reading of 50 to 100 cpm on the times IX range. The probe does not open so the instrument will not respond to the test spot. Reject instruments that do not have on-scale readings.
2.
Locate a measurement place where the modified CDV-700 will have a background reading of 50 to 70 cpm. A basement location near the floor r
and in a corner may be suitable. If the recommended sandshleid was constructed, use this device for all measurements including background.
3.
Stack used canister assemblies within their quart cans several yards away from the measurement poirLt,.
4.
Open the first quart can and take the filter-adsorber out with a paper towel or f acial tissue.
5.
Insert the special CDV-700 probe into the air suction hole of the filter.
adsorber.
l l
6.
Record the time of day, background reading, and the filter-adsorber reading l
on the quart can label.
7.
Locate the rip cord-like thread on the outside of the canister and pull i
to remove the glass fiber filter cloth. Using f acial tissue for handling.
return the filter into its quart can at the storage point.
l 238 I
a l
l 8.
Read the bare adsorber canister and record this finaf entry and date v
~
the label.
I 9.
Rotwn the cardster to its quart can contairdn6 the futir cloth and resea!
with the coerect lid.
10.
Start on the next messwement.
k 5.
Upon conduelan of the messwements, mark the location code on each can with a i
felt marking pen and remove the peel-away labels. The labels shedd be momted 1
- i.
on pages of a school notebook or compoeltlon tak in meeswement sequence for s b each team. The location information should be chedcod and supplemented, if
[
necessary, with additionalinforrnation. The data shsutd then be taken or phoned i
to the local amergency coordination center.
E. Intemal Dose Predletions A.
Glass fllter doch evaluation i
i 1.
Use Figure H.3 to accomt for the radiolodine xi the glass filter doth for a set of measwernents noted <m a transfer labe. Enter the curve for the type r
h of reactor and the number of hours bor.u shatdewn and time of meas-t F
urement.
I 2.
Find the lodine to total fission prodacts correction factor, CF, above the i
i.
vertical axis and calculate the difference In. filter-adsorber and adsorber readings. This difference, F, is due to total fission product actlyity on the i
filter. The product CF x F is the corrected filter reading due to iodine at the time of the measurement.
B. Filter-adsorber evaluation 1.
The adsorber net counting rate is determined by s&tracttng background I
from the bare adsorber measurement.
2.
Add the corrected filter reading, step A2, to the net sixber raading.
l 3.
Select the appropriate curve that corresponds to the total Inhalation _ time in the deuds for the people in the area.
l t
i 4.
Enter Figure H 6 with the total lodine counting rate found in step 52. Follow
[
a vertical to the number of hours afte-reactor shutdown that __the bare r
i i
readinz was m4de. The ordinate is the predicted thyroid dose commitment
~
to a 5-year-old ch1fd at the site of the air sample.
3.
Correct the dose commitment for the part that could have been received i
orior to the time of the predletion. Figure H-7 can be used to make the v
correction by iollowin6 fratructions treluded on the Figwe.
6.
Multiply the correction factor obtained in step 3 by tte dose commitment found earlier in step ~ 4.
7.
Figure M.g is a sample canister label.
L C.
Evaluation of result The projected dose commitment values can be posted on a map corresponding to their locations. If sufficient measurements were made, the path of the cloud should appear as algnificantly higher read 1rgs.-
239
)
I 8
e Predletions can be made of the dose commitment along the cloud track. This should improve the dats base so that decisions can be made about stabla lodine feedings, evacuation cf exposed persons to reduce cxpostro to resuspended radioactive particles, and designations of contaminated pasturage.
u,,,,
~
g I *:
%s seh g
l l
5 5
is n
e'
'a
}
4
/
~
l I
/
\\s
\\
een to 4
/
g
/e
. l.
l,-
d d
d d
v ner cru g,
l e
no Figure H-6.
Conversion of 6306 probe nouns arm wr ""
response to 3-year-old child thyroid dose commitment for 2-hour immer.
Figure H-3. Iodine to total fission pro-sion.
ducts correction factor for shielded COV-7000 Instruments.
i t
Location srte i nuo nast usmwim nuusen pacion er esmas anaa l
er nouns ama accosnt THAT Ctpotunt s7Aarto, samu, os =, po.st accesnr ami sw a nao secono utven raca er l
$
- J St ir Je*ocu M.
Time (Air sample)
E 2 ua E ' $ m'e'." " E.
D***
a em samu. : vac a.am E
. se a osvios sTre news av sw a wum.,:
Area Reading cpu susu, $.m EVALUATION
~
sa
8 Background
cys j
g Filter-Adsorber csst
{
g g, Adsorber cpr E
Time Date
{
i as* ' ' '
Figure H-8. Sample filter-nouIs arm acceevr
adsorher canister label.
38 Figure H-7. Correction for lodine isotope composition.
l
_~260 h
e--
,s
)V.
LILCO, May 8, 1984 CERTIFICATE OF SERVICE In the Matter of LONG ISLAND LIGHTING COMPANY (Shoreham Nuclear Power Station, Unit 1) j (Emergency Planning Proceeding)
Docket No. 50-322-OL-3 I certify.that copies of TESTIMONY OF MATTHEW C.
CORDARO, CHARLES A.
DAVERIO, AND WILLIAM F.
RENZ ON BEHALF OF LONG ISLAND LIGHTING COMPANY ON PHASE II EMERGENCY PLANNING CONTENTION 33 AND LILCO'S TESTIMONY ON CONTENTION 49 (NOMOG RAM FOR THYROID DOSE) were served this date upon the following by first-class mail, postage prepaid, or (as indicated by one as-terisk) by hand, or (as indicated by two asterisks) by Federal Express.
James A.
Laurenson, Secretary of the Commission Chairman
- U.S. Nuclear Regulatory Atomic Safety and Licensing Commission Board Washington, D.C.
20555 U.S.
Nuclear Regulatory Commission Atomic Safety and Licensing East-West Tower, Rm. 402A Appeal Board Panel 4350 East-West Hwy.
U.S.
Nuclear Regulatory Bethesda, MD 20814 Commission Washington, D.C.
20555 Dr. Jerry R.
Kline*
Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S.
Nuclear Regulatory U.S.
Nuclear Regulatory Commission Commission East-West Tower, Rm. 427 Washington, D.C.
20555 4350 East-West Hwy.
Bethesda, MD 20814 Bernard M.
Bordenick, Esq.*
David A.
Repka, Esq.
Mr. Frederick J. Shon*
Edwin J.
Reis, Esq.
Atomic Safety and Licensing U.
S.
Nuclear Regulatory Board Commission U.S.
Nuclear Regulatory 7735 Old Georgetown Road Commission (to mailroom)
East-West Tower, Rm. 430 Bethesda, MD 20814 4350 East-West Hwy.
Bethesda, MD 20814 Stewart M.
Glass, Esq.**
Regional Counsel Eleanor L.
Frucci, Esq.*
Federal Emergency Management Attorney Agency Atomic' Safety and Licensing 26 Federal Plaza, Room 1349 Board Panel New York, New York 10278 U.
S. Nuclear Regulatory Commission Stephen B.
- Latham, Esq.**
East-West Tower, North Tower Twomey, Latham & Shea 4350 East-West Highway 33 West Second Street Bethesda, MD 20814 Post Office Box 398 Riverhead, NY 11901 N
l.
4 Fabian G. Palomino, Esq.**
Ralph Shapiro, Esq.**
Special Counsel to the Cammer & Shapiro, P.C.
Governor 9 East 40th Street Executive Chamber New York, New York 10016 Room 229 State Capitol James B.
Dougherty, Esq.**
Albany, New York 12224 3045 Porter Street Washington, D.C.
20008 Herbert H. Brown, Esq.*
Lawrence Coe Lanpher, Esq.
Jonathan D.
Feinberg, Esq.
Christopher M.
McMurray, Esq.
New York State Public Service Kirkpatrick, Lockhart, Hill Commission, Staff Counsel Christopher & Phillips 3 Rockefeller Plaza 8th Floor Albany, New York 12223 1900 M Street, N.W.
Washington, D.C.
20036 Spence W.
Perry, Esq.**
Associate General Counsel Mr. Marc W.
Goldsmith Federal Emergency Management Energy Research Group Agency 4001 Totten Pond Road 500 C Street, S.W.,
Rm. 840 Waltham, Massachusetts 02154 Washington, D.C.
20472 MHB Technical Associates Ms. Nora Bredes 1723 Hamilton Avenue Executive Coordinator Suite K Shoreham Opponents' Coalition San Jose, California 95125 195 East Main Street Smithtown, New York 11787 Mr. Jay Dunkleberger New York State Energy Office Martin Bradley Ashare, Esq.
Agency Building 2 Suffolk County Attorney Empire State Plaza H.
Lee Dennison Building Albany, New York 12223 Veterans Memorial Highway Hauppauge, New York 11788 Gerald C.
Crotty, Esq.**
Counsel to the Governor Executive Chamber State Capitol y
Albany, New York 12224 3
-)
h,r> D 6wO /,y Re' nee R.
Falzone Hunton & Williams 707 East Main Street Post Office Box 1535 Richmond, Virginia 23212 l
DATED:
May 8, 1984