ML19209C487
| ML19209C487 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/10/1979 |
| From: | Lagrange R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209C479 | List: |
| References | |
| NUDOCS 7910150649 | |
| Download: ML19209C487 (5) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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DAIRYLAND POWER COOPERATIVE
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Docket No. 50-409
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(Lacrosse Boiling Water Reactor)
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AFFIDAVIT OF ROBERT G. LAGRANGE ON CONTENTIONS 5(b)(2) and 5(c)
My name is Robert G. LaGrange.
I am employed by the Nuclear Regulatory Commission as a Mechanical Engineer in the Engineering Branch.
I have been employed in this position since November,1976. My qualifications are listed on the attached Qualification Sheet.
The purpose of my affidavit is to address intervenor contentions 5(h)(2) and 5(c) regarding the adequacy of the spent fuel pool modification for the Lacrosse Boiling Water Reactor.
Contention 5 reads as follows:
The inte.venors contend that an increase in the number of spent fuel locations from 134 to 448 would present a threat to the safety of the public and the maintenance workers that would be completely unacceptable for the fc11owing reasons:
5(b)(2) Ine two-tier and higher density design makes detection of problems in the lower tier difficult if not impossible.
Should any problems develop in stored spent fuel, they would be detectable by area radiation monitors or bi-monthly pool water chemistry checks.
Detection of problems in the lower tier can be satisfactorily accomplished by, 1.
Moving the fuel assembly in the upper tier, and 1134 308 2.
Removing the remotely installable fuel assembly support plate.
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Once the above is accomplished, access by television camera is then possible to the support feet, the storage cell itself, and the stored fuel assembly.
Therefore, the two-tier higher density design does not preclude detection of problems in the lower tier and thus presents no increase in risk to the safety of the public or the maintenance workers.
5(c) The two-tier design reduces the level of water over the assemblies from ten feet to thirty inches, and thus reduces the margin of safety so far as loss-of-coolant accidents in the SFP are concern-ed to an unacceptable level.
Water level above the spent fuel is currently maintained at twelve feet.
Following installation of the new two-tier racks, and since this contention was admitted, water level above spent fuel will be re;. ved to be maintained to at least sixteen feet.
Therefore, the water level abcve the fuel for the two-tier design will be greater than the present level of coverage, and the airg1'., of safety, so far as loss-of-coolant accidents in th SFP are concerned, will actually increase.
I have read the foregoiq affidavit and swear that it is true and accurate to the best of my knowledge, Y
d R66er't G. LaGrange Subscribed and sworn to before me this fa7M day of JulV,1979.
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PROFESSIONAL QUALIFICATIONS OF ROBERT G. LAGRANGE I am an Applied Mechanics Engineer in the Engineering Branch, Division of Operating Reactors, Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission.
My duties and responsibilities involve the review, analysis and evaluation of structural and mechanical aspects of safety issues related to reactor facilities licensed for power I
operation including recommendations to the formulation of safety standards and acceptance criteria.
I am also responsible for managing and coordinating various contractual technical assistance programs and consulting activities related to structural and mechanical aspects of licensing applications for operating nuclear plants.
I have a B.S. degree in Mechanical Engineering from the University of Maryland (1972) and have done graduate work at both the University of Maryland and George Washington University.
Prior to my present appointment, I was associated with Bechtel Power Corporation as a Group Leader in the piping stress analysis group. My duties and responsibilities included performing and supervising stress analyses of nuclear power plant piping, and related activities, with emphasis on seismic analysis.
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e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of DAIRYLAND POWER COOPERATIVE
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Docket No. 50-409 (La Crosse Boiling Water Reactor)
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(SFP License Amendment)
CERTIFICATE 0F SERVICE I hereby certify that copies of "NRC STAFF MOTION FOR
SUMMARY
DISPOSITION ON THE PLEADINGS (SPENT FUEL POOL MODIFICATION)" 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 by deposit in the Nuclear Regulatory Commission, internal mail system, this 30th day of July,1979:
Charles Bechhoefer, Esq., Chairman
- Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Cunnission Washington, D. C.
20555 Dr. George C. Anderson O. S. Hiestand, Esq.
Department of Oceanography George L. Edgar, Esq.
University of Washington Morgan, Lewis & Bockius Seattle, Washington 98195 1800 M Street, N.W.
Mr. Ralph S. Decker Route 4, Box 190D Frit: Schubert, Esq.
Cambridge, Maryland 21613 Staff Attorney Dairyland Power Cooperative 2615 East Ave., South George R. Nygaard La Crosse, Wisconsin 54601 Mark Burmaster Anne K. Morse Atomic Safety and Licensing Coulee Region Energy Coalition Appeal Board
- P.O. Box 1583 U.S. Nuclear Regulatory Commission La Crosse, Wisconsin 54601 Washington, D. C.
20555 Frank Linder Atomic Safety and Licensing i
General Manager Board Panel
- Dairyland Power Cooperative U.S. Nuclear Regulatory Commission 2615 East Ave., South Washington, D. C.
20555
.0 La Crosse, Wisconsin 5460!
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tl.S. fluclear Regulatory Comission Washington, D. C.
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