ML19305B748
| ML19305B748 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/26/1980 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | BIER, MILLS, CHRISTA-MARIA, ET AL |
| Shared Package | |
| ML19305B745 | List: |
| References | |
| NUDOCS 8003200235 | |
| Download: ML19305B748 (22) | |
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2/26/80 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CONSUMERS POWER COMPANY
)
Docket No. 50-155
)
(Big Rock Point Nuclear Power Plant))
ANSWERS OF CONSUMERS POWER COMPANY TO INTERROGATORIES PROPOUNDED BY CHRISTA-MARIA, ET AL.
Pursuant to 10 C.F.R.
S 2.740b and the schedule for discovery set forth in the Atomic Safety and Licensing Board's " Order Following Special Prehearing Conference,"
Consumers Power Company
(" Licensee") hereby submits answers to Interrogatories 9-16 through 9-21.
Interrogatory 9-16 What is the total amount of radioactivity from each radio-active source that would be stored in the existing spent fuel pool when filled to capacity?
A.
Answer:
Radioactive material will exist in spent fuel and other sources when the spent fuel pool is filled to present capacity.
The amounts of radioactive material in spent fuel for various decay times are listed by element in the attachment to the answer to Interrogatory 7-1.
The radioactive material per bundle for typical decay times in the pool may be obtained from this table as follows:
800320093h
Decay time Radioactivity per bundle / curies (Table amount x 2.7)
Time of Core offload 11,329,000 1 year 203,850 10 years 34,130 The total amount for the existing spent fuel pool is dependent on the residence. time of each spent fuel bundle in the pool.
Given the residence times of the 4
bundles and an arbitrary assumption for a schedule of fuel discharges leading to full capacity, the total amount of radioactivity can be calculated exactly (the Licensee has not performed this calculation) by use of the following expression, where At = radioactive con-tent in curies /MNt at the time of interest, Ao = orig-inal radioactive content of spent fuel at discharge, i=
nuclide of interest, e = natural logarithm base
~-
and K(= decay constant of the isotope of interest:
t Ati " Aoi* 71 Therefore, where n = number of isotopes in question, total activity = k Ati*
s Other sources of radioactive material are ex-pected to consist of:
32 control rod blades 20,000 Ci 34 incore flux detectors.
5,100 Ci 76 fuel channels.
5,200 Ci Misc. reactor core internals.
500 Ci 30,800 Ci
. In addition, Consumers Power Company participates in a program to produce radioactive cobalt (Co-60) at the Big Rock Point Plant.
This program is being ter-minated and no Co-60 is anticipated to exist in the spent fuel pool after the early part of 1983.
- Recently, however, approximately 151 cobalt rads totaling 520,000 curies of Co-60 were placed in the pool, and there are an additional 158 cobalt rods in the reactor.
Shipments of this Co-60 offsite, which reduces the amount in the pool, are made on a periodic basis about twice a year.
B.
Documents Relied Upon Letter dated February 4, 1980 from L. Monshor to J.
A.
Ranscholt, Annual Report of Cobalt 60 inventory.
C.
Documents Reviewed But Not Relied Upon None.
D.
Further Activities None.
Interrogatory 9-17 Please answer Question 9-16 with respect to the expanded capacity spent fuel pool when filled to capacity.
A.
Answer:
4 Radioactive material existing in spent fuel in the spent fuel pool when filled to expanded capacity, can be obtained in the same manner as described in the answer to Interrogatory 9-16, except that the calculations should be made for 441 spent fuel bundles instead of 193.
. Interrogatory 9-18 Is it possible for a loss of coolant accident in the spent fuel pool to lead to a fuel melt reaction in the pool?
Please explain in detail.
A.
Answer:
A postulated cask drop analysis, conducted by Licensee's consultant, was submitted by Licensee to the NRC Staff for review on July 1, 1974.
This analysis indicated that in the unlikely event of a drop into the spent fuel pool, as presently designed, of either a 60-ton or 24-ton cask, a leak larger than pool makeup capability (a loss of coolant accident) could result.
Subsequently it was determined that the 60-ton cask would not be used inside containment unless an energy absorbing device is installed on the floor of the pool.
With respect to the 24-ton cask, it has been outfitted with safety slings that provide a redundant means to i
support the cask should a failure occur with respect to the crane or its cabling.
For these reasons, no credible accident exists that would result in a loss of coolant in the spent fuel pool.
The Licensee has not performed calculations to determine whether spent fuel would melt if water was removed from the Big Rock Point spent fuel pool.
B.
Documents Relied Upon Attachment A (postulated cask drop accident study) to letter dated July 1, 1974 from R.
B.
Sewell to K.
R.
Goller (copy enclosed).
-S-Letter (NRC Staf f SER) dated February 6, 1976 from K.
R.
Goller to R.
B.
Sewell (copy enclosed).
Letter dated November 8, 1976 from R.
B.
Sewell to Director of Nuclear Reactor Regulation (copy enclosed).
Letter dated January 7, 1980 from D.
P. Hoffman to D.
L.
Ziemann (copy previously furnished).
Letter dated January 16, 1980 from D. P. Hoffman to D.
L.
Ziemann (copy previously furnished).
C.
Document Referred To But Not Relied Upon Benjamin et al.,
" Spent Fuel Heatup Following Loss of Water During Storage,"
NUREG/CR-0649, SAND 77-1371 (March 1979).
D.
Further Activities NUS Corporation is performing thermal and stress analyses of the spent fuel pool concrete structure, liner and racks to confirm that the effect of pool boiling will not adversely affect pool structures etc.
Interrogatory 9-19 Describe the three worst spent fuel pool related accidents that the Licensee considers credible.
a.
What would be the environmental and radiological conse-quences of these accidents with 193 fuel assemblies in the spent fuel pool?
b.
What would be the environmeacal and radiological conse-quences of these accidents with 441 fuel assemblies in the spent fuel pool?
A.
Answer:
The three worst spent fuel pool related accidents that Licensee considers credible are 1) fuel assembly drop in the spent fuel pool, 2) heavy object drop onto the spent fuel rack, and 3) fuel cask drop.
These accidents are described in Licensee's letter to USAEC Directorate of Licensing (Dkt 50-155) dated July 1, 1974.
. The environmental and radiological consequences of these accidents whether occuring with 193 Stored Spent Fuel assemblies or 441 Stored Spent Fuel assem-blies would in all cases be less severe than the con-sequences of the hypothetical accident described at
- p. 4-1 of Licensee's Environmental Impact Evaluation in this proceeding dated April 1979.
This hypothetical accident assumed that 506 fuel assemblies stored in the Big Rock Point spent fuel pool were crushed by some means, resulting in 100% release of available fission product activity.
The doses at the site boundary in this case would oe less than 8% of the thyroid dose limits, and less than 3% of the whole body dose limits, specified in 10 C.F.R. Part 100.
Licensee does not consider this hypothetical accident to be credible and further believes that the calculated consequences given in the preceding sentence exceed the effects of any of the three worst credible spent fuel related accidents identified above because (1) only 441 assemblies can be stored in the Big Rock Point Plant spent fuel pool, (2) the residence time of the assemblies assumed in the analysis was unreasonably short, causing an over-prediction in the fission product inventory available for release, and (3) no accident sequence has been identified which would result in crushing all the assem-blies stored in the spent fuel pool.
o
. See also the answer to Interrogatory 1-17.
B.
Documents Relied Upon Environmental Impact Evaluation, dated April 1979 for the spent fuel rack addition for the Big Rock Point Plant.
Attachment A (postulated cask drop accident study to letter dated July 1, 1974 from R. B.
Sewell to K.
R.
Goller.
NUS Analysis file 5148-PE-A5 (previously furnished on February 20, 1980 in answer to Interrogatory 2-17).
C.
Documents Reviewed But Not Relied Upon None.
D.
Further Activities None.
Interrogatory 9-20 Please describe all actions that the Licensee would take if each of the accidents described in response to Question 9-19 were to occur.
A.
Answer:
The following discussion applies to all three
" worst case" accidents identified in response to Interrogatory 9-19.
Automatic Action
- The containment ventilation system will be isolated automatically in the event of an area monitor high radiation alarm from either of the reactor deck area monitors.
o
- Immediate Action
- All personnel will immediately vacate the containment building.
- Close ventilation valves (if no automatic isolation signal -- radiation too low to trip area monitor high radiation).
- Notification of the U.S.
Nuclear Regulatory Commission.
Subsequest Action
- Operators will check to insure that containment ventilation valves are closed.
- Operators will monitor containment building radia-tion levels.
- Other actions are dependent upon specific factors present at the time of the event, and therefore cannot be pre-dicted in advance.
Corrective actions will be under-taken as soon as the extent of the difficulty has been determined.
B.
Documents Relied Upon Plant Emergency Procedure EMP3.4 (copy enclosed).
l C.
Documents Reviewed But Not Relied Upon None.
D.
Further Activities None.
o
- Interrogatory 9-21 What actions would Licensee take in each case discussed in response to Question 9-20 if the accident occurred while the containment was contaminated such that it could not be entered?
What if the containment became contaminated as a result of a reactor accident immediately following the spent fuel pool accident?
A.
Answer:
The accidents described in response to Interrogatories 9-19 and 9-20 cannot occur while the containment is inaccessible because each accident scenario requires the presence of personnel inside containment lifting loads over the spent fuel pool.
None of the emergency procedures discussed in response to Interrogatory 9-20 will be affected as a result of a reactor accident immediately following a spent fuel pool accident.
How-ever, some reactor accidents may preclude entry into containment for substantially longer periods of time than one of the accidents described in the answer to interrogatory 9-19.
B.
Documents Relied Upon Documents relied upon in answering interrogatories 9-19 and 9-20 C.
Documents Reviewed But Not Relied Upon None.
D.
Further Activities None.
i
'n District of Columbia) SS.
UNITED STATFS OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CONSUMERS POWER COMPANY
)
Docket No. 50-155
)
(Big Rock Point Nuclear Power Plant))
AFFIDAVIT OF CARL L.
LARSEN I, Carl L.
Larsen, of lawful age, being first duly sworn, do state as follows:
I am employed by Consumers Power Company as an engi-neering supervisor in the Generating Plant Modifications De-partment.
I have overall responsibility within the Company for technical, cost, and schedule aspects of the proposed spent fuel pool expansion at the Big Rock Point Plant.
My resume is attached.
I have primary responsibility for answering Inter-rogatories 9-18 to 9-21.
To the best of my knowledge and belief, the state-ments in this affidavit and in the responses to the inter-rogatories listed above are true and correct.
At r
l Carl p La sen l
Subscribed and sworn to before me l
'thi's,22nd day of February, 1980 t
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//}h,4A k kl Yl//*/1 No tlaip' Public,.,
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CARL LEE LARSEN_
EXPERIENCE:
Consu=ers Power Company since 1979 as Project Manager, responsible * ~
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1979 to for several major nodifications to operating nucicar power plants.
Present Responsibilities include technical, cost and schedule aspects in-cluding vendor selection and construction interface.
1974 to 1979 Gilbert /Coc=onwealth Associates, Inc.1973 to 1979.
1978-1979 Senior Licensing Engineer responsible for the preparation of-
~
security system, design descriptions for a nuclear power plant, responses to USNRC questions on fire protection systems and technical support for hearings before the ACRS concerning a CP stage license application for a nuclear power plant.
1976 - 1978 Responsible for the preparation of responses to USNRC questions during CP review of PSAR license application. Participated in technical meetings with USNRC Staff regarding USNRC questions on PSAR.
1975 - 1976 Lead Safety Licensing Engineer responsible for coordinating the preparation of a Preliminary Safety Analysis Report for a nuclear power plant. Responsibility for the licensability of technical information for the PSAR.
Coordinated the preparation of plant security documents and fire protection and energency planning.
Performed NSSS vendor evaluation and liaison between client and NSSS vendor.
1974 - 1975 Perforced technical and licensability review of PSAR,and related sections of the Environmental Report. Assisted with shielding design experiments conducted at the University of Michigan.
EDUCATION:
B.
. Nuclear Engineering, University of Michigan.
Graduate Engineering Studies, University of Michigan.
SOCIETIES:
American Nuclear Society
s District of Columbia) SS.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CONSUMERS POWER COMPANY
)
Docket No. 50-155
)
(Big Rock Point Nuclear Power Plant))
AFFIDAVIT OF CHARLES E.
AXTELL 4
I Charles E. Axtell, of lawful age, being first duly sworn, do state as follows:
I am employed by Consumers Power Company as the Plant Health Physicist at the Big Rock Point Plant.
I have held this job for 12 years.
In this job my respon-sibilities include monitoring and controlling personnel exposure, ALARA considerations, controlling off-site releases of radioactive materials, and plant water chem-istry.
My resume is attached.
I have joint responsibility for the responses to Interrogatories 9-16 and 9-17.
2-To.the best of my knowledge and belief, the state-ments in this affidavit and the responses to the above interrogatories are true and correct.
Ofu s ?05ll Charles E.'Axtell Subscribed and sworn to before me this 22nd day of February, 1980 IAU/Y.N l
Notary Public
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My, CcmmLioa L.:. icj:.:ater 14,193; 1
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C. E. ATIELL, PLANT HEALTH PHYSICIST Mr. Axtell was assigned as a Senior Chemical Laboratory Technician at the Big Rock Point liuclear Plant in May 1961.
EDUCATION:
1.
About 2 years of college at Bay City Junior College, Jackson Junior College and North Central Michigan College. Night school, general college.
1958-1973.
2.
International Correspondence School, 1/58 - 1/60 (two years).
Chemistry (completed).
3.
Mathematics Course, Consumers Power Company, General Office, Jackson, Michigan, 5/61 (two weeks).
4.
Jackson Junior College, Jackson, Michigan, 6/61 - 7/61 (eight weeks).
Basic reactor technology; applied reactor physics and health physics; and, use and interpretation of radiation measurement equipment, in-cluding foil irradiation and use of actual monitoring equipment destined for the Big Rock Point Nuclear Plant.
5.
US Public Health Service, Cincinnati, Ohio,1/62 (two weeks).
Basics of Radiological Health.
Subjects covered: major sources of radiation exposure; modes of radiation injury; basic units of termi-nology; standards for radiation protection; and, use, operation and evaluation of monitoring equipment.
6.
US Public Health Service, Cincinnati, Ohio, 2/62 (two weeks).
Pollutants in water; methods and techniques for determination of radionuclides in the aquatic environment; and, lectures, problem sessions and laboratory practice.
7.
US Public Health Cervice, Cincinnati, Ohio, 2/62 (one week).
Pollutants in air;.nethods and techniques for determination of radio-nuclides in the air environment; and, lectures, problem sessions and
- 1aboratory practice.
8.
US Public Health Service, Austin, Texas, September 9,1968 (two weeks).
Occupational Radiation Protection.
Subjects covered:
beta and gamma shielding design; disposition of radioactive wastes; neutron instru-mentation; protection and biological effects; transportation accidents and regulations; emergency exposure and concentration guides; emergency planning and management; and eval.uation of radiation exposures.
9.
Consumers Power Company, Jackson, Michigan, September 30 - October 4, 1968 (one week).
Basics of Job Management.
Some of the subjects covered:
Company History and Organization; Work Management; Management by Objectives; and Decision Making.
.~
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EDUCATION (Contd) 10.
Consu=ers Power Company, Jackson, Michigan, November 11-15, 1968 (one week).
Basics of Job Management.
Some of the subjects covered:
Equal employment Opportunity Policy; Accounting Records; Rate Mhking; Union Relations; and Self-Improvement.
i 1
11.
US Public Health Service, Las Vegas, Nevada, February 24 - March 7, 1969 (two weeks).
,Radionuclide Analysis by Gnmma Spectroscopy. The course covered the theory and operation of a gamma spectrometer; considerations necessary for the selection of a spectrometer; and the procedures for evaluating its performance.
The course also covered the consideration of spectral analysis methods, including hand calculation and computer methods.
)
12.
US Public Health Service, Winchester, Massachusetts, August 10-14, 1970 (one week).
Management of Radiation Accidents.
Major attention was devoted to potential sources and types of accidents, preplanning first stage management and follow-up and public relations.
Selected accidents were reviewed in detail.
Class and panel discussions enabled the trainee to discuss specific problems with other class members, the training staff and consultants.
Field exercises were also held.
13.
Special Training Division, Oak Ridge Associated Universities, Oak Ridge, Tennessee, February 23 - May 1, 1976 (ten weeks).
The Health Physics Course included:
Radiation Physics, Spectral Analysis, Counting Statistics, Survey Instruments, Radiobiology X-ray Production, Neutron Production, Nuclear Medicine, Advanced Absolute Counting, Liquid Scintillation Counting, Radiation Protection Guides, X-ray Fluorescence, Industrial Hygiene, Neutron Activation, Solid State Spectroscopy, Radia-tion Accidents, Film Dosimetry, Radiophotoluminescent and Ther=olumine-scence Dosimetry, Emergency Plans and Procedures, Environmental Monitoring, Waste Disposal, Air Sampling, Laser Safety, Transuranius Health Physics, Accelerator Health Physics, Microwave and Accident Dosimetry.
- 14. Raspiratory Protection Programs,' conducted by the Los Alamos Scientific Laboratory, Boston, MA, November 3-5,1976.
Air Purifying Respirators, Atmosphere Supplying Respirators, Respiratory Physiology, Oxygen Deficient Atmosphere, Breathing Air Quality, ANSI Standard Z88.2-1969, Minimal Acceptable Respiratory Program, Concept of Protection Factors, Fitting of Respirators, Respiratory Fitting and Training of the Wearer, Medical Surveillance, Inspection and Maintenance, Respirator Use During Emergencies.
PUBLICATIONS 1.
R. W. Sinderman and C. E. Axtell, Personnel Radiation Exposure Asoects of
~
Ooeration, Maintenance and Refueling a Boiling Water Reactor, y,res,en,te,d,*at the Health Physics Society Mid-Year Topical Symposium, Los Angeles, Cali-fornia, January 29-31, 1969.
d
- In chronological order.
3.
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PUBLICATIONS (Contd) 2.
C. J. Hartman and C. E. Axtell, Unusual Corrosion Problems Associated with a Boiling Water Reactor, presented before the National Association of Corrosion Engineers, Houston, Texas, March 10-14, 1969.
3.
R. W. Sinderman and C. E. Axtell, Liauid Radioactive Waste Management, presented before the American Institute of Chemical Engineers, Cincinnati, Ohio, May 16-19, 1971.
4.
C. E. Axtell and B. L. Murri, Methods Utill ed to Reduce Radioactive Licuid Discharge, presented at the Health Physics Society Annual Meeting, Las Vegas, Nevada, June 12-16, 1972.
EXPERIENCE:
1.
9/57 - 5/61, Plant Laboratory Technician, J. C. Weadock Steam Generating Plant (614 MRe)
Assisted in chemical analysis and control; instrument calibration and repair; and plant efficiency analysis.
2.
9/61 - 10/61 (10 weeks), Vallecitos Atomic Laboratory.
Assigned to the Radiochemistry Section of Vallecitos Atomic Laboratory.
Participated in all phases of radiochemical analysis and control associated with a boiling water reactor.
3.
3/62 - 1/68 Assigned to the Big Rock Point Nuclear Plant as Senior Chemical and Radiation Protection Technician.
4, 2/68, Big Rock Point Nuclear Plant Assigned the title of Supervisor, Chemical and Radiati,on Protection.
5.
Secretary-Elect, Power Reactor Health Physicist Croup, 1972-1973.
6.
Member, Health Physics Society.
7.
Three-week (120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />) course,1975. Conducted Basic Health Physics Course for six Chemical and Radiation Protection Technicians. The course covered such topics as: Mathematics, Basic Physics, Radioactivity, Radiation and Contamination, Biological Effects, Units, Protection Against Radiation and Contamination, Standards and Guide Values, Detection and Measurement of
, Radiation and Contamination, Personnel Monitoring, Survey Techniques, Plant Monitoring of Radiation and Contamination, Decontamination, Waste Disposal, Environmental Safety, Emergency Actions, Shielding Calculations, 10CFR19, 10CFR20, Radiation and Respiratory Protection Program, Hazards Associated with Certain Isotopes, Portable Survey Instrument Calibration, Process Monitors, Detector Fundamentals, Technical Specification Requirements, Air Sampling, Shipment of Radioactive Materials, Site Emergency Plan, and Plant Procedures Manual.
8.
3/76 - Assigned the present title of Plant Health Physicist.
i
e District of Columbia) SS.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CONSUMERS POWER COMPANY
)
Docket No. 50-155
)
(Big Rock Point Nuclear Power Plant))
AFFIDAVIT OF ROGER W.
SINDERMAN I,
Roger W. Sinderman, of lawful age, being first duly sworn, do state as follows:
I am employed by Consumers Power Company as a corporate Health Physicist.
In this job I am respon-sible for all corporate matters relating to radiological control.
My resume is attached.
I have joint responsibility for the responses to Interrogatories 9-16 and 9-17.
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. t To the best of my knowledge and belief, the state-ments in this affidavit and the responses to the above interrogatories are true and correct.
)%oD N s:J
'Roder W.
Sindermain Subscribed and sworn to before me this 22nd day of February, 1980 t
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ldfl Notary Public
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My, Com:mnian Expires September 1+,1982 i
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ROGER WILLIAM SINDERMAN Education:
B.S.
Science Engineering, University of Michigan M.S.
Health Physics, University of Michigan M.P.H.
Health Physics, University of Michigan Experience:
Consumers Power Company as Corporate Health 1974 to Physicist responsible for all aspects of radio-Present logical control at Consumers Power Company nuclear facilities.
These responsibilities include radia-tion exposure to empicjees, environmental sur-veillance, radioactive waste and effluent control.
1973-1974 Consumers Power Company as Palisades Plant Health (6 month Physicist responsible for radiation protection, period) effluent and environmental control at the Palisades Plant.
1971-1973 Consumers Power Company as Environmental Health Physicist responsible for environmental radiological surveillence and control of radiological effluents from the Company's nuclear facilities.
1958-1971 Consumers Power Company as Health Physicist respon-sible for Big Rock Point Plant radiological control and Palisades Plant construction activities related to radiation protection.
1966-1968 Consumers Power Company as Associate Engineer, General Engineer, and Chemical and Radiation Pro-tection Supervisor at the Big Rock Point Plant responsible for Plant radiation protection activ-ities and various engineering tasks.
Societies:
Health Physics Society American Public Health Association 1
I 3
N s
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
CONSUMERS POWER COMPANY
)
Docket No. 50-155
)
(Big Rock Point Nuclear
)
Power Plant)
)
CERTIFICATE OF SERVICE I hereby certify that copies of " Answers of Consumers Power Company to Interrogatories Propounded by Christa-Maria, et al.,"
and attached affidavits and the documents indicated to be enclosed in the above-captioned proceeding were served upon the following persons by de-positing copies thereof in the United States mail, first class postage prepaid, this 26th day of February, 1980.
Herbert Grossman, Esq.
Janice E. Moore, Esq.
Atomic Safety and Licensing Counsel for NRC Staff Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C.
20555 Washington, D.C.
20555 John O'Neill, II Dr. Oscar H.
Paris Route 2, Box 44 Atomic Safety and Licensing Maple City, Michigan 49664 Board Panel U.S. Nuclear Regulatory Christa-Maria Commission Route 2, Box 108C Washington, D.C.
20555 Charlevoix, Michigan 49720 l
Mr. Frederick J.
Shon Atomic Safety and Licensing Atomic Safety and Licensing Appeal Board Panel Board Panel U.S. Nuclear Regulatory U.S.
Nuclear Regulatory Commission Commission Washington, D.C.
20555 Washington, D.C.
20555
1 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docketing and Service Section U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Karin P. Sheldon, Esq.
Sheldon, Harmon & Weiss 1725 I Street, N.W.
Suite 506 Washington, D.C.
20006
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Jo ph/Gallo e of the Attorneys for Consumers Power Company Y
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