ML19289C463
| ML19289C463 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 12/20/1978 |
| From: | Olmstead W NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | |
| References | |
| NUDOCS 7901120228 | |
| Download: ML19289C463 (23) | |
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BEFORE THE ATOMIC SAFETY AtlD LICENSIf!G BOARD In the Matter of Docket No. 50-305 WISCONSIN PUBLIC SERVICE CORPORATION
)
Amendment to License No. DPR-43
)
Wisconsin Power and Light Company
)
(Increase Spent Fuel S+.orage Madison Gas and Electric Company
)
Capacity)
)
(Kewaunee Nuclear Power Plant)
)
NRC STAFF'S ANSWER TO INTERROGATORIES 1, 2 AND 3 0F THE STATE OF WISCONSIN
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On October 2,1978, the State of Wisconsin filed three interrogatories to the NRC Staff in this proceeding. The NRC Staff's responses to Interrogatories 1, 2 and 3 are attached as Attachment A.
The affidavit of Frank M. Almeter which certifies that the indicated NRC Staff responses are true and correct to the best of his knowledge is included as Attachment B, accompanied by his statement of professional qualifications. The affidavit of Jack N. Donohew, Jr., will be supplied at a later date. Dr. Donohew's personal qualifications statement has been included as Attachment C.
Dr. Donohew is currently on travel.
IHIS DOCUMENT CONTAINS POOR QUAllTY PAGES 7w/2c222 cr
2 For purposes of this response the Staff has referenced particular contentions by the number and/or letter designation used by the Atorr.ic Safety and Licensing Board in its October 11,1978 order.
Respectfully submitted, W
William J. 01.istead Counsel for NRC Staff Dated at Bethesda, Maryland this 20%ay of PM /T 7I G
e
ATTACHMENT A Interrogatory No. 1 Briefly state the Staff's position as to the technical merit of each of the intervenor's admitted contentions in this proceeding.
Contention 2 (as revised)
Licensees have not shown that the cumulative radioactive emissions to the atmosphere resulting from spent fuel pool expansions at Kewaunee and Point Beach may not, under certain atmospheric conditions such as an inversion, exceed allowable levels.
Response to Contention 2 (as revised)
This contention is without merit as cumulative emissions have been addressed. The NRC staff has discussed the exposures to an individual at the site boundary and to the population out to 50 miles, from the cumulative radioactive emissions to the atmosphere from the spent fuel pool expansions at Kewaunee and Point Beach in Section 5.3.6, Impacts of Other Pool Ibdifica-tions, of the Environmental Impact Appraisal Relating to the Modification of the Spent Fuel Storage Pool dated December 1,1978, for Kewaunee (Reference 1).
The exposures addressed in Section 5.3.6 were calculated using annual average atmospheric diffusion conditions for the vicinity around Kewaunee.
If short term atmospheric diffusion conditions (e.g., accident conditions as dis-cussed in Section 2.3.4 in the Safety Evaluation dated July 24,1972 (Reference 2) for Kewaunee) had been assumed to exist for an entire year, instead of for only a sna11 fraction of the year as is the case, the exposures to the individual at the site boundary and to the population out to 50 miles could be about 0.1 mrem / year and 0.25 mrem / year, respectively. These inflated exposures are a factor of 100 higher than the exposures actually expected during the year from both the modified Kewaunee and Point Beach pools because the short term atmospheric di.' fusion conditions mentioned above are a factor of 100 greater than the annual average atmospheric diffusion conditions. These
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Response to Contention 2 (as revised) - continued inflated exposures would still be small compared to the fluctuations in the annual dose this population receives from natural background radia-tion and would still be a small fraction of the exposures allowed by the Technical Specifications for each plant.
They would also be a very small fraction of the requirements of 10 CFR Part 20. Therefore, the cumulative radioactive emissions to the atmosphere resulting from spent fuel pool ex-pansions at Xewaunee and Point Beach should not, under severe atmospheric conditions such as inversions, exceed allowable levels.
9
Contentien 8 Applicants fail to discuss problems associated with defective or deteriorating neutron absorber plates and how the specimens will be monitored for loss of neutron absorber material, bulging and swelling.
Response to Contention 8 This contention is without merit. The licensee's initial submittal, as supplemented,"K:waunee Nuclear Power Plant - spent Fuel Fool Mocification rescription and Safety Analysis and Environmental Impact Evaluation", clearly outlined a satisfactory surveillance program for periodic examination of neutron absorber material test coupons in the sper.t fuel pool (References 1, 2 and 3). The neutron absorber material of the Kewaunee facility cons' 7ts of a carbon bound B C that is inert to irradiation and water.
Tests 4
have shown that exposure up to 3.40 x 108 Rads caused no pressure build up or bulging and swelling of the stainless steel shrouding (Reference 2).
Neutron attenuation tests on Boral (B C) material show that no boron 4
was lost from the core of the Boral after 191/2 years in the reactor coolant of the Brookhaven Medical Research Reactor (Reference 4).
Furthermore, Electroschmelzwerk Kempten (ESK), manufacturer of the neutron absorber plates for Kewaunee, has performed tests to show that a total loss of 6-10% boron would occur after 40 years in a borated water spent fuel pool (Reference 2). This low depletion of boron is within the allowable limits for criticality (Reference 2).
9 9
Contention 12 (as revised)
Licensees have failed to provide a quantitative estimate of the incremental increase in low-level radioactive waste that will be produced as a result of tne spent fuel pool expansion.
Response to Contention 12 (as revised)
This contention is without merit. Tne NRC staff has addressed the estimate of the increment in lower level radioactive waste that will be produced as a result of the spent fuel pool expansion at Kewaunee in Section 5.3.3, Solid Radioactive Wastes, of the Environmental Impact Appraisal Relating to the Modification of the Spent Fuel Storage Pool dated December 1,1978 for Kewaunee (Reference 1).
t e
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e Contention 13 Applicant has not discussed the long-term integrity of the various components of and in the spent fuel storage pool in light of the proposed compaction in increased amount of spent fr91 at Kewaunce. The health, safety, environ-mental and economic impact of the loss of integrity of these components due to more dense and increased ste age of spent fuel for the period of licensing must be evaluated.
Contention 13a Applicara should evaluate the corrosive effects of borated water on spent fuel and its cladding, support franes, storage racks, fuel basin liner, neutron absorber plates, and any other components in contact with the storage fuel borated water. According to A. B. Johnson in Behavior of Scent Nuclear Fuel in Water Pool Storace, Battelle Northwest Laboratories, 2256, September 1977 at page 35:
...(P)ool and fuel bundle materials have appeared to function satisfactorily in boric acid fuel pool chemistry, but very few detailed analyses of the materials are avilable." These analyses are necessary to process the app 1tcation to amend Kewaunee's operating license tc F.orapact spent fuel and to store an unprecedented number of spent fuel assemblies as proposed by Applicant. These analyscs are also important because problems of spent fuel ctorage racks swelling associated with borated water have been experienced at the Connecticut Yankee facility and, consequently, the possibility of this situation being duplicated at Kewaunee must be examined and studies documented.
Response to Contention 13a This contention is without merit. Detailed analyses of materials is desirable. particularly when materials are used that are known to undergo
accelerated degradation in aqueous environments. At the Kewaunee facility, all spent fuel pool materials exposed to the pool water are stainless steel and the fuel bundle materials are Zircaloy (References 1 and 3). The corrosion rate of these materials i'. the Kuaunee Plant borated fuel pool water environment is expected to be less than 1 mil during the time period of the license amendment, as indicated from experience of these mater:als in similar water chemistries at other spent fuel pool storage facilities (References 5, 6, and 7). The surface film from the 1100*F heat treated 17-4PH will te removed to minimize stress corrosion cracking.
Furthermore, the protective oxide layer that forms on stainless steel and Zircaloy alloys should provide significant protection against accelerated corrosion in a borated PWR spent fuel pool for storage up to 100 years (Reference 5). The stringent surveillance of the pool water chemi.c try pro-posed by the licensee will provide assurance that aggressive material degradation is not occurring for the time period of the license amendment.
In addition, there is no basis in the claim that compaction of spent fuel in an expanded spent fuel pool storage facility accelerates the corrosion of materials.
The Connecticut Yankee spent fuel racks / tubes consist of 304 stainless steel and Boral neutron absorber plates (8 C/Al clad), (References 8 and 9) whereas 4
those at the Kewaunee facility consist of carbon bound B C(ESK) absorber 4
plates clad with stainless steel. Tests performed by the licensee (References 3 and 4) show that the ESK plates are resistant to degradation from irradiation effects. Since no aluminum is used, hydrogen generation cannot occur as a result of the corrosion of aluminum in water.
Furthermore, the carbon binder
is inert to irradiation and water which will prevent gas pressure buildup.
Therefore, it is unlikely the Connecticut Yankee situation will occur at Kewaunee.
Contention 13b Applicant should examine the effects of accelerated corrosion, micro-structural changes, alterations in mechanical properties, stress corrosion, cracking, inter-granular corrosion, and hydrogen absorption and precipitation by the zirconium alloys due to the proposed compaction and long-term storage of spent fuel at Kewaunee. The Nuclear Regulatory Commission Draft Generic
_ Environmental Imoact Statement on Handline and Storace of Scent Licht-Water power Reactor Fuel, NUREG-0404, Volume 2 March 1978, at page H-23 states that these corrosion effects in under-water spent fuel storage requires examination.
Response to Contention 13b This contention is without merit.
In compliance witn NUREG-0404, Volume 2, March 1978, I have evaluated the corrosion effects in under-water spent fuel storage. Based on my review (References 1 through 12) and the surveillance program proposed by the licensee, I conclude that there is no evidence which indicates accelerated corrosion, microstructural changes, alterations in mechanical properties, stress corrosion, cracking, and intergranular corrosion will occur in the borated FWR spent fuel pool at the Kewaunee Nuclear Plant for the time period of the license amendment.
The licensee has analyzed the effects of corrosion as a result of pool compaction of spent fuel bundles and storage during the time period of the
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license amendment (References 1 and 3).
If precipitation in zirconium alloys and/or hydriding could occur it would be from the high neutron fluxes and the high temperatures in the reactor.
I am not aware of any evidence that low level radiation (gamma) and/or the low temperatures (150'F max) in a PWR spent fuel pool causes such phenomenon in Zircaloy.
Furthermore, the combined af fect of low level radiation and temperature of the pool water would have an insig-nificant effect on the corrosion rate of Zircoloy (References 5, 6, 7, 10, 11 and12). Any oxyger: increase in the pool water from gamma radiation would enhance the passivation of stainless steel and Zircaloy and thus inhibit the corrosion rate.
Contention 13c Applicant must anaiyze the long-term electolitic (sic) corrosion effects of using dissimilar alloys for the pool's liner, pipes, storage racks, and storage rack bases.
Response to Contention 13c This contention is without merit.
The electrolytic potential for galvanic corrosion in the Kewaunee fuel pools is insignificant. Zircaloy and stainless steel alloys are the only materials that will be exposed to the water environ-ment in the spent fuel pools at the Kewaunee Facility. Zircaloy is slightly anodic in relation to stainless steel (Reference 11), i.e., anodic polarization could occur. However, Zircaloy is isolated from the stainless steel by its nonconducting Zr02 protective layer, which would increase the resistance to pitting corrosion. Since Zircaloy is a poor catalyst for cathodic oxygen reduction, it would be very resistant to localized corrosion (pitting).
Although, the pitting potential of stainless steel alloys is lower, no pitting
has been observed for 9 years in fuel pools (References 10 and 12).
Contention 13f Applicant should delineate anticipated thickness of crud layers and crud tendency to influence corrosion of spent fuel and its cladding due to increa.ed and more dense spent fuel storage as proposed for Xewaunee.
A. B. Johnson, in Behavior of Spent Nuclear Fuel in Water Pool Storace at page 65, indicates that study of existing crud analyses and selected other analyses "... may determine whether the corrosion environments in crud layers are as inert as they currently are regarded to be."
Response to Contention 13f This content.]n is without merit. The crud in the PWR reactor is inert te Zircaloy cladding.
In the event crud layers could form aeration cells in the pool environment, the Zircaloy cladding is a poor catalyst for cathodic oxygen re 'uction, and therefore very resistant to localized corrosion attack (References 10 and 12).
PWR fuel is not particularly susceptible to crud releases and thus a significant potential for developing concentrating sites for chloride ions on stainless steel components does not exist. No stress corrosion cracking in PWR spent fuel pools has occurred after 11 years (References 6 and 11).
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Interrogatory No. 2 For each answer to Interrogatory No.1 above, please state the witness and/or witnesses expected to testify at the hearing on behalf of the Staff regarding the Staff's position.
Response to Interrogatory No. 2 The following individuals are expected to testify at the hearing on behalf of the Staff with respect to each admitted contention and Board question:
Witnesses Contention 2 :
Jack N. Donohe.1, Jr.
Contention 3 :
Frank M. Almeter Contention 12: Jack U. Donohew, Jr.
Contention 13a. b, c. f:
Frank Almeter G
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Interrogatory No. 3 For each answer to Interrogatory No.1 above, please state the technical report and/or reports or other documents relied upon by the Staff in formulating its position.
Response to Interrogatory No. 3 The documents relied upon by the Stif f in formulating its position are cited by appropriate reference nembers in its response to Interrogatory No.1.
The corresponding list of references is provided below.
References Contention 2 1.
U. S. Nuclear Regulatory Commission:
" Environmental Impact Appraisal by the Office of Nuclear Reactor Regulation Relating to the Modification of the Spent Fuel Storage Pool", Wisconsin Public Service Corporation, Kewaunee Nuclear Power Plant, Docket No. 50-305, December 1,1978.
2.
U. S. Atomic Ent gy Commission, Directorate of Licensing:
" Safety Evaluation of the Kewaunee Nuclear Power Plant",
Wisconsin Public Service Corporation, Docket No. 50-305, July 24, 1972.
Contention 8 1.
Letter, E. W. James, Wisconsin Public Service Corporation, to V. Stello, U. S. Nuclear Regulatory Commission, " Spent Fuel Pool Modification", November 14, 1977.
2.
Letter, E. W. James, Wisconsin Public Service Corporation to V. Stello, U. S. Nuclear Regulatory Commission, " Additional Information on Neutron Absorber Plates", July 10, 1978.
3.
Letter, E. W. James, Wisconsin Public Service Corporation to V. Stello, U. S. Nuclear Regulatory Commission, " Spent Fuel Pool Modification", September 5,1978.
4 Private communication, Dr. J. R. Weeks, Brookhaven National Laboratory, November 21, 1978.
References - Continued Contention 12 1.
U. S. Nuclear Regulatory Commission:
" Environmental Impact Appraisal by the Office of Nuclear Reactor Regulation Relating to the Modification of the Spent Fuel Storage Pool", Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant, Docket No. 50-305, December 1,1978.
, Contention 13a, b, c, f 1.
Letter Mr. E. W. James to Mr. V. Stello dated November 14, 1977, Docket No. 50-305, Operating License DPR-43, " Spent Fuel Modification".
2.
Letter Mr. E. W. James to Mr. V. Stello dated July 10, 1978, Docket No. 50-305, " Additional Information on Neutron Absorber Plates".
3.
Letter Mr. E. W. James to Mr. A. Schwencer, dated August 18, 1978, Docket No. 50-305, " Additional Information Regarding the Kewaunee Spent Fuel Pool Modi fication'.
N 4.
I.etter Mr. E. W. James to Mr. V. Stello dated September 5, 1978, Docket No. 50-305, " Proprietary Version of the 8 C Plate Test Results 4
From ESX Material".
5.
Vesterlund, G. and Olsson, T. "Degraderingsmekenismer vid Bassanglagring och Hantering av Utbrant Kraftreaktorbransle", ASEA - Atom Prepring RB 78=29, January le, 1978.
6.
Johnson, A.
B., Jr., " Behavior of Spent Nuclear Fuel in Water Pool Storage", BNWL-2256/UC-70.
7.
Heeks, J. R., " Corrosion of Materials in Spent Fuel Storage Pools" BNL - NUREG Informal Report 23021, July 1977.
8.
Memorandum D. G. Eisenhut to V. Stello, Jr., dated June 15, 1978,
" Generic Issue - Spent Fuel Storage Rack Swelling Due to Gas Generation".
9.
Memorandum W. T. Russell to Connecticut Yankee Atomic Power Company /
Consumers Power Company dated May 25,1978, " Summary of Meeting Regarding Deformation of High Density Spent Fuel Storage Containers due to Gas Pressure Buildup".
- 10. Smyrl, W. H., " Behavior Candidate Canister Materials in Deep Ocean Environments", Paper No. 85 Corrosion /77, March 14-18,1977, San Francisco, Cali fornia.
References - Continued
- 11. Cox, B., " Stress Corrosion Cracking of Zircaloy 2 in. - Neutral Aqueous Chloride Solutions at 25'C", Corrosion, Vol. 29, No. 4, pp.157-166, April 1973.
- 12. Morgan, W. W., "The Management of Spent CANDU Fuel", Nuclear Technology, Vol. 22, pp. 409-417,1974
- 13. Private communcation Dr. J. R. Weeks, Brookhaven National Laboratory, November 21, 1978.
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ATTACHMENT 5 UNITED STATES OF AMERICA fiUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSIttG BOARD In the flatter of
)
Docket No. 50-305
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WISC0flSIN PUBLIC SERVICE CORPORATION
)
Amendment to License Nc. DPR-43
)
WISCONSIN POWER AtlD LIGHT COMPANY
)
(Increase Spent Fuel Storage MADISON GAS Af!D ELECTRIC COMPANY
)
Capacity)
)
(Kewaunee Nuclear Power Plant)
)
AFFIDAVIT OF FRAfiK M. ALMETER I, Frank M. Almeter, being duly sworn, depose and state:
1.
I am an Applied Mechanics-Material Engineer in the Engineering Branch, Division of Operating Reactors, U. S. fluclear Regulatory Commission, Washington, D. C.
20555. My professional qualifications are attached.
2.
I have answered Interrogatories 1, 2 and 3 submitted by the State of Wisconsin with respect to contentions 8 and 13(a), 13(b), 13(c), and 13(f) of Lakeshore Citizens for Safe Energy and hereby certify that the answers given are true and correct to the best of my knowledge.
SA?nmk Sellh Frank M. Almeter Subscribeo and sworn to before me this /'t'* day of December,1978.
h'-) / t_. <?w kuo'A M -
Notary Public y My Commission Expires: b~ i l'1 $ M
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FRANK M. ALMETER, Ph.D., B.Sc.
DIVISION OF OPERATING REACTORS U. S. NUCLEAR REGULATORY C0talSSION PROFESSIONAL QUALIFICATIONS I joined the Commission in October,1974/as a Materials Engineer and t...
presently an Applied Mechanics /Materici Engineer in the Engineering Br.ndi, Engineering and Projects, Division of Operating Reactors, Office of Nuc1 car Reactor Regulation.
Since October, 1974 my duties and responsi-bilities have involved the review and cvaluation of materials applicatien in nuclear power plants with specific emphasis on corrosien and water chemistry in PWR and BWR systems.
I have been appointed to the Electrichi Power Research Institute (EPRI) Corrosion Advisory Committee and the !"iC Corrosion Review Group for Reactor Systems.
I have the primary responsi-bility for the safety evaluation regarding the corrosion problems of PWR steam generator tubing, spent fuel storage pools, S?.'R and PWR pipinc systems, and snubbers.
I had responsibility for drafting the Technical Specification " Secondary Water Monitorino Requirements" for pressurized
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water reactors.
I also have the responsibility for the evaluation of reactor coolant chemistry in both Pressurized Water Reactors and Boiling Water Reactors.
I have provided the Division of Regulatory Standards with the technical bases required for the revision of Regulatory Guide 1.56, " Maintenance of Water Purity in Boiling Uater Reactors."
I presented testimony on " Steam Generator Tubt Integrity" at the Beaver Valley Unit 1, Pilgrim Station Unit 2, Jamesport Station Units 1 and 2, Byron /Braidwood Stations Units 1 and 2, and Prairie Island pub'ic hearings.
I also assisted in the preparation of testimony on this same subject for the South Texas Project Units 1/2 and the Washington Nuclear Project One public hearings.
I have a Ph.D. in metallurgy from the University of London (1959) and a D.I.C. degree in metallurgy from the Imperial. College (London 1955).
I received a B.Sc. degree in Metallurgical Engineering from the University of Missouri at Rolla in 1953.
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From June,1973 to October,1974, I was associated with the U.S. Consumer Projects Safety Com.nission as a metallurgist rcsponsible for the evaluation of engineering, manufacturing and quality centrol procedures within the consumer product industry to insure production of non-hazardous products.
I developed safety tests and basic engineering factors relative to the modi.fication of product safety standards.
In 1971 1 joined the Office of Saline Uater, Department of the Interior, as Assistant to the Ch'ef, Materials Division. My dutics and responsibilities were the planning and directing of contracts for the developmcnt, testing, and evaluation of materials utilized in the various desalination processes.
I prepared contracts for the develop-ment of economic materials to reduce the capital and maintenance costs of desclination plants and increast their reliability.
I also con-ducted inspections to evaluate the corrosion performance of materials in operating plants.
I performed highly technical studies of the
. corrosion, mechanical, physical, and fabrication propert'es of a wide range of materials.
From 1968 to 1971 I was Chief Metallurgist of corporate materials tcchr. ology for the Burndy Corporation with duties and responsibilities for the techniccl/ administrative ranagement of materials pertinent to process and product development. As manacer of the metallurgical R & D laboratory, I was responsible for program planning, cost estimates, budget control and recruiting.
I established, staffed and managed a new Metallurgical Service Center to support Engin-eering, Manufacturing, Purchasing, and Sales / Marketing Departments.
Before I became Chief Metallurgist with the Burndy Corporation, I was a rescarch scientist for l'0 years in the aerospace industry where I conducted basic and applied research in the areas. of surface science, precious metal coatings, corros; a of metals, mechanical /
physical metallurgy, fibreus compcsite materials, simulated high altitude environmental effects on materials, fracture and surface dar. age in retals, alloy development, heat treating, ferrous and nonferrous alloys, ceramic / dielectric ma:erials, and HERF forming of matals.
a From 1955 to 1958 I was a Consulting Metallurgir.t in the United Kingdom.
I specialized in the areas of precipitation-hardening, fatigue and tensile properties of Beryllium Bronzcs.
I am listed in the American Men of Science,12th edition and Who's Who in America,14th edition.
I was Cuest Lecturer, Fairleigh Dickinson University course on " Desalination Oper,tions", Dec.1972.
I was invited by the Electrical Power Research Institute (EPRI) to be secretary to the "First U. S. - Japan Joint Symposium on Light Water Reactors" (May 29 - June 2, 1978).
I have authored 17 publications in my professional field.
Current Publication:
"An Overvice of Water Chemistry for !!uclear Power Plant Safety by F.M. Almeter, Vol 28, pp 582-583,197S Transactions of the America:.
!!uclear Society.
I am a member of the American Society for I:etals, AIME Metallurgical Society, and flational Asscciation of Corrosion Engineers.
S o
ATTACHMENT C
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s JACK N. DON 0 HEW, JR.
PROFESSIONAL QUALIFICATIONS DIVISION OF OPERATING REACTORS OFFICE OF NUCLEAR REACTOR RECULATION My name is Jack N. Donohew, Jr.
I am a Senior Nuclear Engineer in the Environ = ental Evaluation Branch in the Diyision of Operating Reactors, U. S. Nuclear Regulatory Co= mission (NRC). My duties include the review of rad-waste treatment syste=s and engineered safety feature ventilation syste=s for operating reactors.
I received a Bachelor of Engineering Physics Degree from Cornell University in 1965, a Masters of Science Degree in Nuclear Engineering from Massachu-setts Institute of Technology in 1968, and a Doctor of Science Degree in Nuc1 car Engineering from Massachusetts Inctitute of Technology in 1970. I received my Professional ingineers License in Nuclear Engineering from the Co==onwealth of Penns ilvania in 1974.
After graduation, I worked for Stone and Webster Engineering Corporation as an engineer in the Radiation Protection Group. I was responsible for esti-mating source terss, release rates and resulting doses for the Safety Analysin Report, Environmental Report,and response to NRC questions for boiling water nuclear reactors. I was also responsible for shielding design for the reactor water cleanup system.
In February,1973, I became a Power Engineer in the Process Engineering Group, Stone and Webster Engineering Corporation. I was lead engineer for the Shoreham Project and the equipment specialir,. for all nucicar plants 0
2-for the contain=ent iodine spray removal system, ventilation filter assemblies, and Boiling Water Reactor and Pressurized Water Reactor gaseous vaste treatment system.
In June,1975, I joined the Nuclear Regulatory Commission as a senior nuclear engineer in the Effluent Treatment Systems Branch, Directorate of Licensing.
I was involved in rad-waste system licensing reviews of nuclear power plants.
I have conducted generic studies of the degradation of charcoal adsorbers in ventilation filter asse blies.
In December,1975, I joined the Environ =crital Evaluation Branch in the Division of Operating Reactors.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COR11SSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
WISCONSIN PUBLIC SERVICE CORPORATION
)
WISCONSIN POWER AND LIGHT COMPANY
)
Docket No. 50-305 AND
)
Amendment to License MADIS0N GAS AND ELECTRIC COMPANY
)
No DPR-43
)
(Increase Spent Fuel (Kewaunee Nuclear Power Plant)
)
Storage Capacity)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF'S ANSUER TO INTERROGATORIES 1, 2 AND 3 0F THE STATE GF WISCONSIN", dated December 20, 1978, in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or, as indicated by an asterisk through deposit in the Nuclear Regulatory Commission's internal mail system, this 20th day of December, 1978:
Robert M. Lazo, Esq.
Patrick Walsh, Esq.
Atomic Safety and Licensing Board Department of Justice U.S. Nuclear Regulatory Commission 114 East, State Capitol Washington, D. C.
20555 Madison, Wisconsin 53702 Mr. Glenn 0. Bright Steven E. Keane, Esq.
Atomic Safety and Licensing Board Panel Foley & Lardner U.S. Nuclear Regulatory Commission First Wisconsin Center Washington, D. C.
20555 777 East Wisconsin Avenue Milwaukee, Wisconsin 53202 Dr. Oscar H. Paris, Member Atomic Safety and Licensing Board Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Appeal Board Washington, D. C.
20555 U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. William Cordaro 1412 New York Avenue Atomic Safety and Licensing Manitowoc, Wisconsin 54220 Board Panel U.S. Nuclear Regulatory Commission Mrs. Wend Schaefer Washington, D. C.
20555 3741 Koehler Dr.
Sheboygan, Wisconsin 53081 Ms. Mary Lou Jacobi Lakeshore Citizens for Safe Energy 932 N. 5th Street Manitowoc, Wisconsin 54220
- Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D. C.
20555
, /,,
.- -- /
William.!. Olmstead Counsel for NRC Staff 0