ML20010B408
| ML20010B408 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/09/1981 |
| From: | Semmel H ANTIOCH SCHOOL OF LAW, WASHINGTON, DC, BIER, MILLS, CHRISTA-MARIA, ET AL |
| To: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8108140448 | |
| Download: ML20010B408 (28) | |
Text
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BELATED CORUESPONDFNCE fdG 12 NN >
UNITED STA1FS OF AMERICA
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NUCLEAR REGULA'IORY COMMISSION Mact BEFORE 7HE ATOMIG4r)EFDT%ND LICENSING BOARD h
r is In the Matter of (fg Docket No.
50-155 CONSUMFRS POWER COMPANY '
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CHRISTA-MARIA, E1 AL.,
INTERROGATORIES TO CONSUMERS POWER COMPANY (SET III)
PurFuant to 10 CFR Section 2.740, and in accordance with the ORDEF FOLLOWING SPECIAL PREFEARING CONFERENCE dated January 17, 1980, Intervenors Christa-Maria, JoAnn Biers, and James Mills request that these interrogatories be answered fully, in writing, and under oath by any employees or representitives of Consumers Power Company (" Licensee") who have personal knowledge of the facts or issues in question.
The answer to each interrogatory should contain the name and identification of each person supplying or contributing to the answer, whether or not he or she j
has verified the answer.
The answer should also explain the role j
of each individual in preparing the answer.
l l
For the purposes of these interrogatories, l
l (a) the term " spent fuel rack" ref ers to each c mpleted l
. assembly that is or will be installed in the spent fuel poo] to hold spent fuel.
An example appeOrs at page 3-3 of the Spent Fuel Rack-Description and Safety Analysis prepared for this application ano dated April 1979 l
(referred to as the Description and Saf ety Analysis).
The term includes both existing and proposed spent fuel racks unless otherwise specified.
(b) the term " component" means one of the parts with j
which something is manufacured or constructed.
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example, the componente of a spent fuel rack include, bat may not be limited to the spent fuel cells or cans, the top and bottom grids, the leveling legs, cnd the lead-in guides (See pp. 3-3 and 1-4 of the Description and safety Analysis), as well as rivets, nuts,.bolta, plates, insulators, weld wires, and other parts of the spent fuel rack.
Similarly, the pool liner constitutes a component of the spent fuel pool, as do any filters, demineralizers, water circulators, and other parts of the spent fuel pool system.
In addition, the term refers to all raw r.:aterials f rom which the component was made.
Each question is to be answered in four parts as follows:
A.
Provide the direct answer to the question.
B.
Identify and provide all documen*.s and studies, and the particular parts thereof, relied upon by Licensee as the basis for the answer.
C.
Identify and provide all documents and studies, and the particular parts thereof, examined but not relied upon by the Licensee, which pertain to the subject matter in question.
D.
Explain whether the Licensee or any independent contractor is presently engaged in further research or work that may bear on the issues covered in the
'in te r rog a to ry.
If so, please identify the research or work and the persons responsible for it.
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1.
State the amounts of airborne radiation in the atmosphere above the spent fuel pool (but within the containment) due to operation of the spent fuel pool for (1) normal operations and (2) -in the event of all credible accidents.
Answer both (1) and (2) as to the current situation and after the prcposed expansion of the spent fuel pool, a.
Please identify the constiuents of this airborne radiation per foot up to ten feet above the surface of the spent fuel pool.
Please answer for above ten feet.
b.
What amount of airborne radiation originating in the spent f uel pool are vented directly into the environment by the continous ventilation system?
c.
How much airborne radiation can be expected to be vented directly into the atmosphere as a result of all credible accidents involving the spent fuel pool, including those involving inadequate cooling of reactor fuel and core melt?
Answer both (b) and (c) as to the current rituation and after the proposed expansion.
2.
Please explain what effect an accident involving an explosion, inadequate cooling of the reactor fuel and core melt would have on (1) the spent fuel pool and its operation (2) the
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components of the spent fuel pool (3) the system components shared by the reactor and the spent fuel pool and (4) the fuel stored in the pool.
How'would these effects differ before and after the expansion of'the spent fuel pool?
't 3.
Please identify which of the components in Licensee's
. response to Invervnors Interrogatory number 3-3(a) Set I, including pool valves, strainers, pipeing, circulation pumps, pool filters, recondary cooling loop, pool walls, and pool liner are not seismically qualified.under 10 CFR-Part 50.
Which of these components can withstand a seismic event up to and including the safe system shutdown earthquake -(SSE) ?
4.
What effect would a design basis and SSE have on (a) each of the components of the spent fuel pool, (b) the components shared by the reactor and the spent fuel pool and (c) the spent fuel cooling system?
5.
Could a design basis or SSE result in the breach of the spent fuel pool?
State the tacts on which the anrwer is based.
In the event of a breach identify its effects and the measures available to a.
.contain the water in the spent fuel pool and containment.
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identify the amount of radiation contained in the water released during a breach.
c.
would water be discharged to the environment?
If so, how and in what amounts.
6.
In the event of a breach, or other credible accident such a s a core n.elt, explosion or inadequate cooling of core fuel, what steps would be taken to cool the fuel stored in the spent fuel pool?
a.
What is the source of the amergency cooling water?
b.
How is the emergency cooling water deli ~vered to the pool?
c.
How long does it take to return the water level in the pool to normal using this procedure?
d.
Are there procedures for cooling the spent fuel during the period before the emergency cooling system is operational?
Answer (a), (b), (c), (e) and (t) with -
regard to this cooling source.
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Is the emergency cooling system dependent on an e.
onsite or offsite-power source?
Specify the power source by location and type.
f.
What effect would failure of the power source identified in (e) above have on the ability to cool the fuel stored in the spent fuel pool.
g.
Is there offsite power available to operate the spent fuel pool and cooling mechanisms in the event of loss of power on site?
How long would it take to revive the cooling system using this power source?
7.
Is the spent fuel pool above grade?
What effect would an SSF have on the pool walls above grade?
8.
What effect will the increased density of spent fuel have on the ability to cool fuel in the spent fuel pool during an (a) l SSE (b) breach (c) loss of offsite power?
9.
Please identify.the level of radioactivity from the spent i
fuel pool reaching the environment and its pathways during normal operation of the spent fuel pool.
Please answer for (a) SSE and (b) meltdown.
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10.
What is the status of licensee's activities with regard to SEP Topic III-7D, SEP Topic VI-2, SEP Topic VI-4 and SEP Topic I
IX-20?
Please summarize the conclusions of each of the above.
11.
What is the impact of blasting by the Medusa and t
Pen-Dixie Cement Companies on the monitoring devices contained (a) within containment (b) within the spent fuel pool and (c) within the control room.
Are these devices examined regularly to determine whether blasting has altered their operation?
12.
Please identify the frequency and velocity of sound waves generated by blasting by the Medusa and Penn-Dixie Cement Companies?
a.
What are the effects of such blasting on the geologic formations underlying Big Rock Point?
b.
What effect do these vibrations have on the physical structure of the spent fuel pool and its components?
13.
Please identify the geologic formations underlying and within a one mile radius of Big Rock Point.
a.
Are there any limestone caverns underlying the Big Rock Point site?
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b.
If there are limestone caverns underlying Big Pock Point or within a one mile radius, how are vibrations from blasting by the Medusa and Penn-Dixie Cement Companies transmitted through such. caverns?
14.
How much I-29 is released from the spent fuel pool and what percent is this of the total I-29 release from the entire Big Pock facility?
15.
fIs there a stainless steel barrier plate on the pool floor to guard against a cask-drop?
16.
How many defective fuel elements have been placed in the spent fuel pool?
a.
What is the average number of defective fuel elements expected to be placed in the pool in the future if the modification is granted.
- 17. Has the Licensee ever failed.to seal containment during (a) an accidental release of radiation (b) during other events?
When?
a.
Fow many times has containment had to be cealed?
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b.
Has containemer t ever been sealed as a result of a malfunction or failure of the spent fuel pool or any of its components?
When?
18.
How much Krypton 85 is presently released from the spent fuel pool.
Please answer this question as to the current situation and after the proposed expansion.
19.
How did the Licensee analyze its spent fuel cooling system taking into account the proposed increase in fuel storage capacity?
Justify the assumption that Licensee will be able to keep the pool temperature at 140 for the normal case and 170 when only one pool cooling pump and one cooler is used.
20.
Identify by type and number all malfunctions, accidents, abnormal occurences, events and oversights that have occured at Big Rock Point ittvolving (1) the spent fuel pool, (2) back-up generators, (3) cooling systems and (4) isolation components.
How many of such occurances have been reported to the NRC pursuant to 10 CFR 20.4 03, 10 CFR Part 21 or 3 0 CFR 50. 7 2.
21.
What postulated accidents, which might affect the safety of plant operating personnel in the spent fuel storage building or which might result in the release of radiation or radioactive NN M 4 Oe h[@ M ab.tM Agg4 A g ij
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materials from the spent fuel pool have been anlayzed?
4 a.
Which of the postulated accidente or their effects will be increased in probability, magnitude, or consequence if the proposed modifications are carried out?
b.
What provisions have been made to protect workers at the plant from the effects of such accidents?
c.
What provisions will be taken to protect plant workers from accidents during modification of the fuel racks?
d.
Will any of the workers involved in reracking be temporary employees?
What steps will be taken to ensure that radiation e.
doses to temporary employees do not combine with previous exposures to place the employee's exposure level beyond allowable limits?
22.
What is contained in the effluent released-from Big Rock Point?
a.
Fow is this ef fluent monitored?
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b.
What effect will increasing the amount of spent fuel in the spent fuel pool have on the amount of radioactive isotopes in the ef fluent discharged f rom Big Rock Point?
c.
How of ten are inplant ef fluent samples taken?
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d.
Who tests these samples?
e.
What isotopes are tested for?
f.
How long does it take to test these samples?
g.
How soon after the sa.,ple is taken is it tested?
h.
Is there a backlog in testing these samples?
i.
If there is a backlog, how long is it and what effect does it have on the accuracy of testing?
23.
Please answer 22(a) and 22(c) through (i) with respect-to environmental samples.
24 Are environmental samples from Big Rock Point routinely analyzed for alpha?
If not, why not?
a.
What is the testing schedule?
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b.
Who conducts the tests?
c.
How long after the samples taken are the tests performed?
d.
Is there a backlog in testing the samples, and if so what effect does it have on the accuracy of the test?
e.
On the occasions when environmental samples are tested for alpha, how much has been found?
Has the level of alpha ever exceeded that prescribed in 10 CFR?
25.
Are there any radioactive isotopes that instruments on site at Big Rock Point cannot or do not measure?
a.
Are these isotopes produced during operation of the reactor or storage of spent fuel at Big Pock Point?
b.
What are the effects of exposure to these isotopes?
c.
Is i t common practice within the nuclear industry to measure these isotopes on site.
26.
Please describe the maintenance procedures for the spent
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a.
How often is the pool drained?
b.
How often are the pool components such'as tiles, piping systems systems and racks inspected?
How often have such inspections resulted in repairs?
c.
d.
What were the nature of these repairs?
How long did such repairs take to complete?
e.
i f.
Fave such repairs ever involved the repair of cracks or breaks in the piping associated with the spent-fuel d
cooling system or the pool liner?
g.
How many times during the operation of Big Rock Point has the pool been drained for repair to the pool or its component parts?
l 27.
Pave spent fuel rods or bundles ever slipped out of the racks onto t re floor of the spent f uel pool?. When?
8 a.
Fow was this discovered?
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How long had the rod or bundle been on the bottom of the spent fuel pool before discovery?
c.
Was this event recorded by instrumentation in the spent fuel pool?
If not, why not?
d.
What effect did this event have on the spent fuel rod or bundle involved?
What effect did this event have on the pool liner?
e.
f.
How close to the south wall of containment was the rod or bundle located?
g.
What steps have been taken to prevent recurrance of this event?
28.
Has there ever been an unplanned drainage of the spent fuel pcol?
When?
a.
Fow did it happen?
b.
What happened to the water?
'Was any of.the water discharged directly into the c.
environment?
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What effect did such drainage have on the spent fuel pool and the fuel stored therein?
e.
How long did it take to restore the water in the poo] to normal.
29.
Is the spent fuel pool at Big Rock Point used to store any material other than spent fuel?
e a.
What is this material?
b.
How long h,s it or will this material be stored in the spent fuel pool?
1 What effect does storage of such material have on c.
the spent fuel and the amount and type of radiation l
l released from the pool?
l 30.
Fow many flights over Big Rock Point or within 5 miles by private, commercial, and-military-including air national guard-aircraft have occurred since 1975 by year and type of
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a.
What effect would crash of such an aircraft into the-l controlE room at Big Rock Point have on the operation of
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the. reactor and the spent fuel pool.
b.
In the event of such a crash, does Big Rock Foint have a technical support center from which operation of the reactor and spent fuel pool can be monitored and controlled?
i c.
Pave private, commerc ial.nd military aircraf t been rerouted away from the vicinity of Big Rock Point?
If so, how close will these aircraft now fly to Big Rock Point?
31.
How close is the-nearest groundwater to the spent fuel-pool?
Does any substance from Big Rock Point seep into the a.
goundwater?
I b.
If there is seepage, identify the composition of the-substance, its quantity and effect on groundwater quality.
l c.
Fas the groundwater ever been tested f or contamination by the spent fuel pool?
What were the results?
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32.
Does Consumers Power currently, or plan in the future to uFe the Big Pock Foint site for purposes other than a nuclear generating station, such as a hazardous waste storage f acility?
If so, what will the site be used for?
33.
Does Consumers Power have any plans to construct a rad waste reprocessing building within the compound at Big Rock Point?
a.
Wi*at purpose will such a building serve?
b.
Describe in detail the activities performed in such a building, the radiological hazards associated with such activities and the amounts of radiation released during such activities.
c.
Could irradiated spent fuel hardware, such a old or defective racks, pool tiles or valves be stored in such a building?
I d.
Could any other irradiated equipment be. stored in this building?
34.
Was containment at Big Rock Foint designed to withstand the effects of tornado loading or the impact of tornado missiles?
- a.
Pave any studies been performed which assess the i
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potential effects of such occurances on containment?
If.so, what were the results of these studies?
b.
Please answer (a) above.with regard to the control room at Big Rock Point.
3h What effect will the increased use of plutonium enriched fuel elements at Big Rock Point and the reduced proximity of same to each other under the revised storage plan have on the safety margin or safety factor of safe storage?
36.
Following reracking of the spent fuel pool, what will be done with the old spent fuel racks?
a.
Where will these racks be stored?
b.
If the old racks are to be stored offsite, describe in detail the shipping and packing process and all steps taken to reduce the risk of radiocctive exposure to the public and the environment.
3 7. - Has the spent fuel pool at Big Rock Point ever been -
evaluated as a source of radioactive material with the potential to be released during an accident?
a.
What were the results of this evaluation?
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b.
In the event of such a release, identify the amount of radiation that would be released to the environment and the environmental pathways it would follow.
c.
Does Consumers Power consider this to be a credible event?
If not, why not?
38.
In the event of a core melt accident, how long would it take to seal containment?
a.
How long af ter isolating the containment could reentry of containment occur?-
During isolation is emergency cooling equipment b.
accessible?
39.
What is the potential that more "leakets" will be stored-in the spent fuel pool?
i a.-
Does storage of " leakers" in the spent fuel pool increase the amount or radiation released from the spent fuel pool?
Please answer by amount and kind of isotope.
40.
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on site standby and emergency diesel generators have f ailed to operate.
a.
Please state the total amount of time such generators have been unavailable for emergency service.
b.
During a loss of on site power or a reactor accidenc would offsite power be available if the standby generators were inoperable?
41.
How many times has Licensee failed to isolate containment because of malfunctions of isolation components?
Please state the reason for such failures and date on which they occurred.
i 42.
How do " compacting" and "high density racking" differ?
Will expansion of the spent fuel pool at Big Rock Point result in compaction of the spent fuel stored therein?
43.
What types.of fuel are stored in the spent' f uel pool?-
a.
Phat kind of interaction takes place between the -
experimental cladding, U 235 and mixed oxide fuel stored at-Big Rock Point?
b.
What are the ef fects of such interaction on the radiation levels inside containment?
m
i c.
What effect do " hot spots" have on mixed oxine fuels stored in the spent fuel pool at Big Rock Point?
44.
Does the feedwater train to Big Rock Point operate on offsite power?
a.
What effect would loss of offsite power have on the feedwater train and the operation of Big Rock Point?
b.
What redundant power and water sources are available in the event cf loss of offsite power or *ailure of the feedwater train?
c.
What is the source of the redundant cooling water?
d.
How is this water delivered to the spent fuel pool i
and the reactor?
e.
Can this (these) water source (s) operate independently of the eedwater train?
f.
Is this redundant water source capable of cooling the fuel stored in the spent fuel pool and the reactor durino a core melt'or other accident for which isolation of containment is necessary?
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45.
What effect would failure of both heat exchangers and both pun.ps in the cooling system have on operation of the spent fuel pool and the spent fuel stored therein?
i 46.
Have there ever been any unplanned releases'from Big Rock Point?
If so, identify the number and. nature of the release.
47.
Please identify which radiation survey'instruaents use
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type probes".
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c.
Please indicate f:he maximum effect that !a) humidity, (b) temperature, (c) vibrations, and (d) 1 usage, can have on the accuracy of these instruments and explain how these instruments are read giving examples of maximum high readings due to the four f actors listed above.
b.
How long have radiation survey instruments using G.M.
type probes been calibrated annually?
c.-
Have these radiation instruments ever been used longer than a year without calibration?
If so how long were.they used before calibration and when were they
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Provide documentation of such calibration.
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Please explain in lay terms how these instruments are calibrated.
e.
Are these instruments currently being calibrated on a quarterly basis?
If so, what prompted the change anu when did this more frequent calibration schedule begin?
f.
Which calculations of spent fuel pool radiation are measured by these instruments?
48.
What was done with the leaky fuel bundle mentioned in the November 12, 1965 letter of Travelers Insurance Company to Mr. Haueter?
a.
What effect did this problem have on the spent fuel pool?
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b.
Could this happen again in the future?
L 49.
Please explain what the pocket ionization chambers referred to in the August 29, 1979 letter of American Nuclear Insurers to Mr. Cooper are.
a.
Why do these chambers require drift checking?
b.
What is drift checking?
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Is drift checking currently being conducted on a regular basis?. If not, why not?
50.
How would the spent fuel pool be maintained. safely in the event that a large electrical fire destroyed-'(a) the control room and (b) the electrical equipment room?
Is this.a credible event?
If not, why not?
51.
Fow would the spent fuel pool be maintained safely in the event that a fire at the Big Rock plant resulted in a loas of f
AC power?
Is this a credible event?
If not, why not?
52.
Has Consumers Power. Company complied with all the fire prevention and protection : ecommendations made in the Nuclear.
Mutual Limited Property Loss Prevention Reports of 1973 through 19817 i
a.
What recommendations concerning fire prevention and protection have not been complied with?
b.
Are the control room and the Big Rock plant generally in compliance with the recommendations made in the report?
List all non-compliances.,
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What is the likelihood of a fire. destroying or incapacitating in any way (a) the control room, (b) the electrical equipment room, or 02) the computer room?
53.
Please list and explain all problems that Consumers Power Company has had in isolating the containment.
54.
Explain in detail the "f:.'.rther activity" listed in Licensee's response to Intervenors Interrogatory 7-2 Set II.
55.
What is the probability that containment would be isolated if a high radiation signal were given as of August 1, 1981?
Explain the basis for this response.
56.
How would-pool safety be.g. water level, cooling, etc. )
be maintained if containment was sealed due to a severe accident preventing reentry?
57.
Please list all rediation monitors in containment and provide a schedule of how often they are checked for accuracy and calibration.
a.
Please indicate any problems Consumers Power has had with radiation monitors including calibration.
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Fow do the radiation monitors at Big Rock Point differ from those currently being installed at new nuclear facilities?
Have any radiation monitors ever been replaced at c.
Big Rock Point?
If so, why?
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How old are the radiation m.gnitors used ast Big Rock Point?
58.
Based on CAMS and Grab samples, have radiation releases from Big Rock Point ever exceeded allowable limits?
If so, when, and by how much?
i Respectfully submitted,
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As (He'rbert Semmel ~
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Antioch School of Law 2633 16th Street, N.W.
Washington, D.C.
20009 Counsel for Intervenors Christa-Maria, et al.
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Dated August 9, 1981
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,7 CERTIFICATE OF SERVICE I hereby certify that copies of Intervenors Interrogatories Set III to Licensee dated August 9, 1981 in Consumers Power Comany, Big Rock Point Nuclear Power Plant, No. 50-155, were served on all persons identified in the attached list by.
depositing copies in
'e United States mail, first class, postage prepaid, the 10th day o." August, 1981.
/
h Scott. Warner
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Atenic Safety and Licensing Jeesph Cal *e, Esquire Inha, Linco3n and Beale Scard Panel 3
1120 Conneccicutt' Ave, N.W.
U.S. Nuclear Regulatory Suite 325 Commission Washington, D.C.
20555 Washington, D.C.
20036 Philip P. Steptoe, Esquire Herbert Grossman, Esq., Chairman Isham, Lincoln and Beale Atomic Safety and Licensin8 One First National Plaza suite 4200 Board Panel Chicago, Illinois 60603 U.S. Nuclear Regulatory Commission Washington D.C.
20555 Atonic Safety and Licens:n, Appeal Board Panel U.S. Nuclear Regulatory Dr. Oscar H. Paris Commission Atomic Safety and Licensing Washington, D.C.
20555 Board Panel U.S. Nuclear Regulatory Docketing and service Section Commission of fice of the Secretary Washington D.C.
20555 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Fredrick J. Shon Atomic Safety and Licensing John O'Neill, II Board Panel Route 2, Box 44 U.S. Nuclear Regulatory Maple City, MI 49664 Commission Washington D.C.
20555 Janice E. Moore, Esq.
Counsel for NRC Staff U.S. Nuclear Regulatory Commission Washington, D.C.
20555 John A. Leithauser Energy Resources Group General De~ ivery Levering, MI 49755 l
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