ML20237K439

Forwards Schedule for Corrective Actions from States of Mi & in for Weaknesses Identified During 870819-20 Joint Full Participation Radiological Emergency Preparedness Exercise

ML20237K439
Person / Time
Site:	Palisades
Issue date:	07/08/1987
From:	Weaver W Federal Emergency Management Agency
To:	Bickerton G, Jascewsky E, Snell B AGRICULTURE, DEPT. OF, ENERGY, DEPT. OF, NRC
Shared Package
ML18052B251	List: ML20237K439
References
NUDOCS 8708270178
Download: ML20237K439 (44)

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• u Region V 300 South Wacker,24th Floor, Chicago, IL 60606 (312) 353-1500 l

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July 8, 1987 j J ,Y i

@d, [:. f./h Menorandum For: Regional Assistance Comnittee USDA-G. Bickerton g'hf-.[- , J -_

DOE-E. Jascewsky EPA 4. Gulezian fi[tT '

DOT-R. Stokes PHS-E. Ellis/K. Jaffe FDA-J. Kraeger NRC-B. Snell DOI-S. Huff From: Wa

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('0>llace/J.

W Weaver, Chairman RegionId1 Assistance Comnittee

Subject:

Palisades Schedule Of Corrective Actions And Final Exercise Report Enclosed is a copy of the schedule of corrective actions from the State of Michigan and Indiana for the weaknesses identified during the August 19-20, 1986 joint, full participation radiological emargency preparedness exercise involving the Palisades Nuclear Power Plant. The schedule of corrective actions has been reviewed by FEMA Region V and foun3 to be adequate to correct the weaknesses identified during the exercise. Enclosed are copies of the FEMA Region V letters to the States of Michigan and Indiana accepting their schedule of corrective actions.

A copy of the revised cover and title page for the final exercise report are enclosed. Please replace these two pages in the copies of the draft exercise report which were provided to you earlier. These are the only L l'

changes to the draft exercise report which may now be considered final, FEMA Region V has recommended FEMA HQ transmit the final exercise report ard schedule of corrective actions to the Nuclear Regulatory Comnission.

lI JUL 10 937 1 8708270178 G70820 PDH ADOCK C5000255 F PDR ,

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FINAL THIS IS TIE 1986 PALISADES EXERCISE REPORT FINAL

1 Palisades Nuclear Power Plant Consumers Power Conpany Joint Exercise

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Facility Location: Located 11. the State of Michigan, Northwestern Van Buren County on the shore of Lake Michigan.

Exercise Date: August 19 & 20,.1986 Date of Draft Report: January 27, 1987 Dat'e of Final Report: July 8, 1987

Participants:

State of Michigan (full); Van Buren County (full);

Allegan County (full); Berrien County (full); State of Indiana (partial) and the' Consumers Power Conpany (full).

Fe3eral Emergency Management Agency Region V Natural and Technological Hazards Division Technological Hazards Branch i' 300 South Wacker Drive Chicago, Illinois 60606

\

Federal Emergency Management Agency Region V 300 South Wacker,24th Floor, Chicago, IL 60506 (312) 353-1500 July 8, 19U 1 Captain Arlyn F. Brower, Director Energency Management Division Michigan State Police Knapps Center, Suite 300 300 South Wbshington Square Lansing, Michigan 48913 )

Attention: F/Lt. James M Tyler

Dear Captain Brower:

i FEMA Region V has reviewed your schedule of corrective actions for the weaknesses identified during the August 19-20, 1986 joint, full participation radiological emergency preparedness exercise with the Palisades Nuclear Power Plant. 1 The proposed schedule of corrective actions are acceptable. It should be i noted, though, that criteria item K.3.a and K.5.b for Allegan County is acceptable only because the schedule of corrective actions indicates radiological monitoring training aM training of other personnel will be carried out over the year. The Radiation Exposure Records submitted by Allegan County as evidence these records were distributed is accepted.

These Radiation Exposure Record cards submitted with your schedule of corrective actions show they were not properly maintained. These Allegan County emergency workers did not enter on the record card their final readings, their dose, their total exposure, nor did they date aM sign their record card. In essence, information on these record cards would not have enabled Allegan County to control the exposure of these emergency workers.

This area will be evaluated in future exercises to verify that the training conducted by Allegen County has corrected this weakness identified during the August 19-20, 1987 Palisades exercise.

A copy of the revised cover aM title page for the final exercise report are enclosed. Please replace these two pages in the copies of the draft exercise report which were provided to you earlier.

The final exercise report and your schedule of corrective actions are being provided to FEMA HQ for transmittal to the NRC. If you have any questions please call Dan Bement at FTS 353-3632.

Sincerely,

. M f Wallace J. Weaver, Chairman Regional Assistance Comittee

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.. -. . STATE OF MlClllGA_N g r .:

EMERGENCY M AN AGEMENT DIVISION kN A PPS C6:NTR5;. SUIT &:3co J AMES J.BLANCll ARD, GOVERNOR '""$[sf[a^"fj,$$[g"[,I,'""

DEPAItTMENT OF STATE POLtCE ,,,,,,,,,,,,.,,.,,,

CtH H T. DAVIR, DlH6,CTOR June 16, 1987 I:

Wallace J. Weaver, Chairman Regional Assistance Committee FEMA - Region V 300 S. Wacker,.24th Floor Chicago, IL 60606

Dear Mr. Weaver:

Attached is the Schedule of Corrective Actions for the State of Michigan and the Counties of Berrien, VanBuren and Allegan for the August 1986 Palisades full scale REP Exercise.

If you have any questions, please feel free to contact this office.

Sincerely,

_ ~

F/ . James , Tyler C maanding 'Ticer Pre-Disaster Services Section JHT/DMS/sc Attachments l

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1 CHAPTER 13 I

9 SAMPLING RADI0 ACTIVE MATERIALS l

11.1 BACKGROUND

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Radioactivity in the environment results from the decay processes of '

individual radionuclides, which are the unstable isotopes of the various chamical elements. Radioactive isotopes possess the same chemical  ;

1 properties as the stable isotopes of a given element. The rules and l precautions to be observed for collecting, handling and preserving samples 1 of o specific element or compound apply likewise to its radioactive forms. '

Guidance given elsewhere in this manual should be reviewed when sampling for radioactive material .

I Radioactive waste originates from such diverse nuclear facilities as I uranium and thorium mines and mills, fuel enrichment and fabrication plants, nuclear power plants, test reactors, fuel reprocessing plants, waste burial sitas, hospitals with nuclear medicine laboratories, nuclear weapons sites, {

radiochemical ' producers, research and test laboratories, and manufacturers q l

of products incorporating radioactive substances. Routine gaseous or liquid discharges from nuclear facilities to unrestricted areas contain relatively low concentrations of radioactive material; high level wastes are condensed, '

sealed and stored on site or transported to radioactive waste disposal sites. The types and amounts of discharged radionuclides vary widely with fac;1ity.

The Nuclear Regulatory Commisssion (NRC) regulates the discharge of radioactive material from nuclear facilities. Concentrations of radionuclides permitted in releases to unrestricted areas are specified in  ;

Section 20.106 of 10 CFR 20.(1) The EPA has established permissible concentrations of biologically significant radionuclides in drinking l j

l water.(2)

The pathways through which radionuclides in water reach man are shown in Figura 13.1. (3) The drinking water pathway is usually the one that contributes the most dose. Others of significance include consumption Less of plants and animals that live in water or are fed by irrigation.

important generally is the external dose received during work or recreational activity from radioactivity in nearby surface water, sediment i deposited near shorelines, or irrigated fields. (4) l

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.13.2 GENERAL CONSIDERATIONS 43.2.1. Background _ Radioactivity q

Many naturally-occurring radionuclides exist in soil, water, air and -

living matter. (5) In addition, man-made radionuclides have become Due to widespread in the natural environment during the past few decades. j their presence, background radioactivity at sampling locations must be assessed to determine the actual amount contributed by a nuclear facility to the environment. Control samples taken upstream of the liquid discharge point provide data on the types and amounts of background radionuclides.

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In addition, natural and artificial radionuclides occur as impurities '

in many materials used for sample containers, radiation detection equipment.

and shields, and chemical reagents. (6) For example, glass contains natural '

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X, natural water contains uranium, thorium, and their decay products.

Cerium compounds contain thorium. Since these contaminants can produce interferences in radionuclides analyses, their effects must be' evaluated before sampling. l 13.2.2 Radioactive Decay The half-lives of sampled radionuclides relative to the interval between sampling and measurement must be considered for determining analytical priority. Those with short (less than o'ne week) half-lives need immediate measurement Radionuclides concentrations are reported at levels occurring at the

-time of sampling. This requires that the times of sampling and analyses be J carefully recorded for accurate decay corrections. Note, however, that many j naturally occurring radionuclides possess long half-lives which eliminates the need for correction.

References 7, 8, and 9 list half-life values as well as radiation

. emission data. Reference 9, although comparatively old, provides comprehensive radionuclides data. Many chemistry handbooks provide data  !

pertaining to common radionuclides. UseFor recent editions since research to this reason, the data used in a F obtain more accurate values continues.

analysis must be recorded since the advent of more accurate values moy require revision of earlier calculations.

13.2.3 Detection Capability The ability to identify and amsure very low concentrations of l

.. j radionuclides depends on the types of counting instrumentation on hand and their sensitivity. An important element affecting detection capability is

• the instrument background level that results from radioactivity ambient in {

j the counting facility and present in the detector shield and the detection equipment itself. Counting equipment presently available together with  !

proper background control provides sufficient sensitivity to measure ' l

' radionuclides at levels below regulatory standards. i 315  !

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1:nowledge of detection capabilities aids in designing the sampling program, such as,. necessary somple volume.

tiinimum detectable levels -fer radionuclides frequently observed in water and analyzed.by routine- techniques are given in Table-13.1 (10) In some cases, several detection, limits are listed to show how they vary with method. Cross alpha and beta counting are preferred by some because the ~

instruments are relatively inexpensive anu sufficiently sensitive to determine compliance with certain standards such as those for ' drinking water.

Effective use of gross measurements, however, requires knowledge of radionuclides composition.

- 13'. 3 FREQUENCY OF SAMPLING 13.3.1 Reculatory As specifica in: 1) license or regulations issued by the NRC or NRC Agreement State; 2) EPA drinking water standards; or 3) permits from other governmental agencies.

13.3.2 Surveillance Base frequency of sampling on an evaluation of: l

1. types, amounts and potential hazards of radionuclides discharged,

2. . their behavior in the environment,

3. waste discharge practices.

4. nature of use of local environment, and S.

the distribution and habits of potentially affected populations.(5) <

A minimum grab' sampling program for surveillance of nuclear power reactors (4) that may be applicable to other types of facilities follows:

1. Surface water -- monthly 2.

Ground water from sources likely to be affected -- quarterly.

3. Drinking water supplies -- sample at the water intake with a continuous flow proportional sampler. If impracticable, obtain a monthly grab sample at the reservoir when its holding time exceeds one month; if less, make sampling frequency equal to reservoir i

holding time.

4. Sediment -- semi-annually ,

13.3.3 Other The frequency for testing effectiveness of waste treatment or control methods is determined by objectives of investigation.

316 1

I

TABLE 13.1 RADIONUCLIdEDETECTIONCAPABILITIES Physical Sample Minimal Detect-Radionuclides Hal f-li fe Size, able Level Method liters pC1/ liter

• 3g 12.4y 0.008 200 LSC ,  :

14 C

5730y 0.2 30 LSC 60 5.27y 0.4 10 y-spect (Ge) $

Co 3.5 10 y-spect(Nal) f 89 5r 50.5d 1.0 0.5 CS and LBBC 90 28.5y 1.0 0.2 CS and LBBC Sr 131; S.04d 2.0 0.1 CS and LBBC 10.0 0.4 10R,y-spect 0.4 10 y-spect(Ge) 137 Cs 30.0y 0.4 10 y-spect(Ge) 1.0 0.3 CS and LBBC 3.5 10 y-spect (Hal) 226 1600y 1.0 0.02 RE Ra l 228 Ra 5.75y 2.0 0.1 CS and LBBC Ra (total) --

2.0 0.06 CS and IPC Gross alpha --

0.1 0.5 IPC 0.5 0.1 IPC Gross beta --

0.1 2.0 LBBC 0.5 0.5 LBBC

• Calculated at the 99.7'!. (three-sigma) confidence level, based on 1000-minute counting intervals and typical counting efficiencies and instrument background levels. <

Methods:

CS Chemical separation technique (10) 10R lon-exchange resin ,

IPC Internal proportional counter I LBBC Low background beta counter l LSC Liquid scintillation counter j RE Radon emanation and counting by alpha scintillation cell (10) l y-spect Gamma-ray spectroscopy, "Nal" denotes a 10 cm x 10 cm Nal (TI) '

3 detector and "Ge" an 85 cm Ge (Li) detector j

l 317 f

j 1

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. i 13.4. LOCATION OF SAMPLING ..

Unless specified in regulatory licenses, requirements or permits, selection of proper sampling locations is based on judgmer,t (see Section 13.3.2). As a guide, the. EPA recommends for surveillance of light-water  : i reactor sites: (4) l

- f i

1. Surface water -- At streams receiving liquid waste, collect one ,

l sample both upstream and downstream of the discnarge point. Obtain >

downstream sample outside of the restricted area at a location no  !-

closer than 10 times the stream width to allow for mixing and  !

dilution. At. facility sites on lakes or large bodies of water, sample near but beyond the turbulent area caused by discharge. .

Record the discharge flow rate at the time of sampling.

2. ' Drinking water -- Sample all water supplies with intakes downstream and within 10 miles of a nuclear facility. If none exists, sample the first water supply within 100. miles.  !

3. Ground water -- Monitoring is necessary when a facility ,

discharges radioactive waste to pits or trenches. When local ground water is used for drinking or irrigation, at a minimum,  !

sample the nearest affected well. Subsurface movement of most '

radionuclides is retarded by the filtering and ion-exchange i capacity of soil; tritium, however, moves more rapidly than most I q radionuclides. *

4. Sediment -- Samples to detect accumulation of undissolved or '

adsorbed radionuclides in beds of streams or other bodies of water receiving liquid effluents from nuclear facilities are collected: l

1) downstream near the discharge outfall but beyond the turbulent i' area; 2) downstream of the discharge at locations where sediment is  ;

observed to accumulate, such as at bends of streams or dam impoundments; and 3) upstream near the discharge outfall but beyond i]

, l its influence, to determine background radionuclides.

See also Section 8.4 of this manual for additional guidance in selecting proper sample locations.

13.5 SAMPLE VOLUME Determining necessary sample volume depends on the typats and number of analyses to be performed and the sensitivity of available analytical instruments. For surveillance purposes, obtain the following minimum volumes: ,

e 1

318 l

' b

. q 3

ee* _

-a

• et ?

Volume, liters Measurement 3.5* i Gamma-ray spectroscopy (Na! detector))

Gamma-ray spectroscopy (Geli detector 0.4 0.1 Gross alpha or beta only 0.01 Liquid scintillation - tritium only

" Water can be subsequently used for analyses requiring chemical separations l

(e.g.,895r, 90Sr)*

Sediment analyses usually require 1 kg. of sample. (5)

Increase the volumes or weights when sample splitting or replicate analyses is required for quality control purposes.

13.6 SAMPLE CONTAINERS use sample containers that minimize radionuclides losses by adsorption or other processes during collection and storage. Containers made of f' iorinated hydrocarbon material (e.g. Teflon) are preferred because of their resistance to adsorption. Polyethylene and polyvinyl chloride are also recommended.(ll) Glass and metal containers tend to retain radionuclides.(12) Glass bottles also are more subject to breakage during I handling. ,

When adsorption problems persist, wash containers and sampling apparatus with hcl or HNO3 before sampling or flush the containers and Test apparatus with the liquid to be collected before final sampling.(13) for adsorption by analyzing used containers by gamma-ray spectroscopy when this type of radionuclides emission is present. For other emitters, use successive acid leachings with hot aqua regia and analyze the leachate.(12)  ;

Discard containers after use to eliminate possibility of l cross-contamination through re-usage. If for economic reasons the more l

expensive containers must be used again, test for adsorbed contamination as '

described above.

13.7 SAMPLE FILTRATION Filter water and wastewater sample to segregate liquid and solids when the radionuclides contents are to be deterinined inFilter eitherasorsoon both as the suspended solids and dissolved matter fractions.

practicable after collection to assure that no redistribution occurs during storage before analysis.(12) Use membrane or glass fiber filters since these types resist adsorption effects.(ll) Filter before adding preservative or other substances to the sample since they can effect changes in distribution.(14) 319 i

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1

• i 13.8 SAMPLE PRESERVATION >

Radionuclides are subject to many little understood chemical and physical processes at the very low concentrations (parts per billion or less), which are typical of most environmental water samples.(11)(12)(15)

Variations in original sample concentration or homogeneity can result from:

1) adsorption on sampling apparatus, container walls or solid material in the sample;(5) 2) co-precipitation of radionuclides due to precipitation of Fe and Mn in ground water samples exposed to air;(15) 3) ionic exchange with components of glass containers;(12) 4) uptake by bacteria, algae or other biological matter in the sample;(13) and 5) formation of colloids.(12) Many of these problems are thought to occur because the amounts of stable isotopes are insufficient to serve as a carrier for the radioactive nuclides of the same element.(11)

The standard preservation technique for radionuclides in water and wastewater samples is acidification to a pH of < 2 with hcl or HNO .(14)(15)

Several exceptions exist: 3

1. Tritium - add no acid; begin analysis immediately upon return to the laboratory.(10)

2. Carbon 14 - see tritium

3. Radiocesiums - use hcl only

4. Radiciodines - see tritium: acid oxidizes iodides to iodines which are rapidly lost through volatilization.(12) For samples containing 3 H, 14C or 131 I along with radionuclides requiring preservatives, obtain duplicate samples and add acid to only one.

Add acid preservative after sample collection (but not before filtration - see Section 13.7) or as soon as practicable but do not delay beyond five days.(14)

When acid preservation is not desirable: 1) add isotopic carriers of the same elements as the radionuclides:(12) 2) refrigerate samples at or near their freezing temperature to retard chemical reaction rates and to inhibit bacterial growth.(16) 13.9 GENERAL SAMPLING PROCEDURE - WATER AND WASTEWATER The following procedure summarizes the elements of good practice for collecting and preserving samples of water and wastewater for radionuclides measurements. These guidelines apply to the situation where no unusual circumstances exist:

1. Flush sample lines, equipment or other apparatus and sample container with sample medium to minimize adsorption effects. Use type of containers recommended in Section 13.6.

2. Avoid . floating debris and bottom sediments when sampling surface waters. When aliquoting large samples containing significant amounts of suspended solids, vigorously shake or mix to assure -

320 L

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L 3. -Wash sampling apparatus with distilled water to minimize contamination of subsequent samples.

o 4. ~ Filter sample as soon as practicable after collection when -

radionuclides distribution in soluble and/or insoluble phases is to be determined (see Section 13.7). Use membrane or glass fiber

~

filters.-

5. . Add preservative of the required type to liquid samples (see Section13.8). When concentrated hcl or HNO 3 is the indicated type,. add to obtain a pH of 4 2. ~1n cases of mixtures of radionuclides, for some '(3H , 14C,131; -) .of which acid preservation is not recommended, collect replicate samples and treat only one -

with acid. '

6. Seal sample container tightly. Complete sample data _ label c including time of collection for decay corrections.

7. - Analyze samples containing short-lived radionuclides as soon as possible.

8. _ Discard sample containers after use or test for contamination if expensive types of containers are to be used again.

l 13.10 RADIATION SAFETY- l Storage of-large_ numbers or volumes of samples containing radioactivity

' is a' potential source _of exposure to workers occupying the area. However,-

this' is unlikely with environmental samples due to low radionuclides content.

If in doubt, survey the area periodically with a beta-gamma survey instrument, such'as a Geiger-Mueller (GM) meter. Note that sample containers reduce all alpha-particle and much-beta-particle radiation. If radiation levels above instrument background occur at work stations, consult c a radiation safety specialist-for procedures to reduce exposure levels and for proper disposal techniques when samples are no longer needed.

13.11 REFERENCES

. 1. U.S. Nuclear Regulatory Commission. Standards for Protection Against Radiation. Title 10, Code of Federal' Regulations, Part 20, Federal Register, U.S. Government Printing Office, Washington, D.C. 1975.

2. Office of Water Supply, U.s. Environmental Protection Agency. National Interim Primary Orinking Water Regulation. EPA-570/9-76-003,U.S.

Government Printing Office, Washington, D.C.,1977.

3. Report by Committee 4 of the International Commission on Radiological Protection. Principles of Environmental Monitoring related to the Handling of Radioactive Materials. ICRP Publication 7, Pergamon Press,

'0xford, 1965. .

321 S

e" %

l

..e t 4..

U.S. Environmental Protection Agency, Office of Radiation Programs.

Environmental Radioactivity Surveillance Guide. EPA report No. ORP/SID -

72-2, 1972.

\

5.

\

, National ~ Councif on Radiation Protection and Measurements. l Environmental Radiation. Measurements. NCRP Report No. 50, 1976.-  !

6. DeVoe, J.R.

Research. Radioactive Contamination of Materials Used in Scientific i Nuclear Science Series Report34, No. National Academy of Sciences - Naj 1961. ,

7 Martin, M.J. , editor, Nuclear Decay Data for Selected Radionuclides.

Oak Ridge National Laboratory, ORNL-5114, March 1976. - ]

j 8

Martin, M.J. and P.H. Blichert-Toft. -i Tables A_8, Nos. 1-2, 1970. Radioactive Atoms. ~ Nuclear Data -

3

'9 . Lederer, C.M. , J.M. Hollander, and I. Perlman. R

~ John Wiley, New York, 1967. Table of Isotopes. I

10. Krieger, H.L. l U.S. Environmental Protection Agency, Report No. EPA-60 (Revised), March 1976.

11. Mitchell, N.T.

Radiological Examination.-Manual on Analysis for Water Pollution Control.

World Health Organization, to be published.

~

12. Kahn, B.

Determination Pollution Control Handbook, of Radioactive Nuclides in Water.Water New York, 1973. L.L. Ciaccio, ed., Marcel Dekker, Inc..-

13.

Corley, J.P. , D.H. Denham, D.E. Michels, A.R. Olsen and D. A. Waite. A 1 Guide for Environmental Radiological Surveillance at ERDA Installations.

• Report No. ERDA 77-24, March,1977.U.S. Energy Research & Develop 14

\

American Public Health Association. Standard Methods for the Examination of Water and Wastewater.

1976. 14th edition, Washington, D.C.,

15 Thatcher, L.L. , V.J. Janzer and K.W. Edward.

' Methods for Determination Book 5, Techniques of Water-Resources Investigations States D.C. Geological Survey. U.S. Government Printing Office, Washington, 1977.

i_ 16 l

.U.S.

Support Environmental Laboratory. Protection Agency, Environmental Monitoring and EPA Report Nol EPA-625/6-74-003a, 1974. Methods for Chemical Analysis 322

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William J. Patterson, Director Indiana Departenant of Civil Defense and Emergency Government .

B-90 State office Building c1 100 North Senate Avenue il Indianapolis,. Indiana 46204 I

.J ATIENTION: Charles T. Wilson, Jr. .IJ Deputy Radiological Officer -;

1

Dear Mr. Patterson:

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EEMA Region V has reviewed your schedule of corrective actions for the aren '

requiring corrective action identified during the August 19-20, 1986 full ,

participation Palisades Nuclear Power Plant exercise. The State of Indiana .

partially participated in this exercise. We find the schedule of corrective ,

action satisfactory to correct the weakness identified during the exercise. t Your letter transmitting your schedule of corrective action dated February t.

25, 1987 has been forwarded to EEMA H0 for transmittal to the NRC; "

.,EEMA Region V will notify your office of .the date FEMA HQ provides the ,

i.

Nuclear Regulatory Comnission (NRC) with a copy of the final report of the August 19-20 Palisades exercise. We will also provide you with a copy of the final report.

Please feel free to contact Dan Bement, ETS-353-3632 if you have any . +

,i questions. - "i' sincerely, U2 >

Wallace J. Weaver, Chairman Regional Assistance Comnittee

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palls h DE S STATE - INDIANA i k INDIANAPOLIS,46204 4 1

DEPARTMENT OF CIVIL DEFENSE '

90 STATE OFFICE DUILDING \s%s is TELEPHONE: (317) 232 3830 100 NORTH SENATE AVENUE

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February 25, 1987 l

l Mr. Dan Bement (

Federal Emergency Management Agency J Region V I 300 South Wacker Drive, 24th Floor Chicago, Illinois 60606

Dear Dan:

As per our meeting of January 22, 1987, concerning the proposed scheduled completion date for Indiana'a State Radiological Emergency Response Plan, a goal of December 1, 1987, is realistically targeted. As a direct result of the February 3, 4, and 5, conference in Chicago, and subsequent to your introduc-tion of Bill Brenner e Commonwealth Edison Emergency Planning Supervisor for off-site plans, a meeting between Mr. Brenner, Ms. Mary Goodkind, Impell Corporation planning consultant for CECO, Mr.-Rex Ferrell, Indiana State Police, Mr. Hal Stocks, Mr Vlajia Davorjak, Dr. James Schuler, Indiana State Board of Health, and our staff at the Indiana Department of Civil Defense Office, was held on February 23, 1987, to familiarize the respective agencies of the purpose of the upcomihg Braidwood Nuclear Power Station Exercise, obtaining a full power license for Braidwood.

Mr. Brenner informed us that CEC 6 would be more than willing to support Indiana's effort in this exercise, by assigning Ms. Goodkind, who incidentally was instrumental in developing the original Marble Hill Plan, to constructively review and comment, either add or delete as necessary, the rough draft I annoted on the Marble Hill model. Ms. Goodkind will be in direct contact with myself or Mr. Bowser, by phone and in person to attend our scheduled State Agency meeting for coordination.

I feel, with the assistance of Ms. Goodkind's expertise, along with more clear and consice understanding of our goals and objectives, Indiana will be able to meet FEMA's mandates on a-State Radiological Plan and the exercise portion of our requirements.

We, of the Indiana Department of Civil Defense, fully intend to be supportive of both Illinois and Michigan's Nuclear Power Utilities l and State Emergency Management Agencies. '

([ .

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1 Pagel2L .

>'  : Dan C.Bement-1

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TFinally, I.would'like to thank you for your subtle' assistance concerning: the economic ' constraints of these projects during the luncheon ~at the O' Hare Conference. .The results of your' mediation ha ve;. lead to untapped technical and . financial- resources for 'this .  :!

program.'

l

,. . .If.you.have any' questions as.to the progress.of.the PLAN,. -

please call me at- 317/232-3842. I would be happy to discuss-or 1 clarify any points of. confusion or_possible misunderstanding.

V Sincerel'y,- i bh '

Charles T.. Wilson, Jr.

Deputy Radiological 1 Officer CTW/mvm I

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