ML19316B013
| ML19316B013 | |
| Person / Time | |
|---|---|
| Site: | 07002623 |
| Issue date: | 04/16/1980 |
| From: | Jeffrey Riley CAROLINA ENVIRONMENTAL STUDY GROUP |
| To: | |
| Shared Package | |
| ML19316B011 | List: |
| References | |
| NUDOCS 8005280164 | |
| Download: ML19316B013 (7) | |
Text
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O go' UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION b g 2 1 g * ;ff f
grs5'.Jgeidgottfe H Ltter of
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WhE ER COMPANY
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Docket No. 70-2623
@ CA dmenment to Materials License O
nu-'773 for Ocone. Nue1 ear Station
)
Spent Fuel Transportation and Storage
)
at McGuire Nuclear Station
)
4 SUPPLEMENTALTESTIMbNYOFJESSEL. RILEY Q.
Do you wish to supplement your previous testimony in the cask drop matter?
A.
Yes.
In addition to my analysis of the physics of the cask drop problem postulated by the NRC Staff and to the results obtained with a crude codel I have built and made trials with an accurate model of the. cask, cask pit, and pit / pool wall.
Q.
What was your reason for building an accurate model?
A.
The testimony provided by the parties, with the exception of that relating to an admittedly crude model, was analytical.
The Staff supported Applicant's conclusion that the cask would not fall into the pool, although, unlike Applicant, Staff did not provide analytical material in support of its position.
It frequently happens, in matters in which more reliable evidence is lacking, that the findings will support the majority view.
As the present matter is one with safety significance, and because a conceivable consequence would be an inadvertent criticality incident, it seemed that more relisble evidence should be obtained.
A Sandia study of the behavior of fuel casks under conditions of impact, authorized by the NRC, concluded, among other things, that a scale model accurately paralleled actual cask behavior.
s005280/4
, Under the instant circumstances, in which a trial with the actual components would be prohibitively costly, and in which there is conflicting testimony, I viewed the performance of an-actual model as providing the most reliable means o,f establishing the facts.
Q.
Will you describe the model?
A.
The dimensions of the NFS-4 cask were taken from,Uuclear Fuel Services drawing E 10078 T (CESG Exhibit
).
The model was made ons inch to one foot.
The significant cask and model
. dimensions are given in the " Cask Drop Model" table dated 3-24-1980 attached hereto.
The model cask is a solid steel.
cylinder weighing 22 pounds.
The impact absorbing ends are a plywood / Formica laminate.
These ends are attached to the cask by screws inserted in plastic liners of 17/64 inch diameter holes drilled axially.
The cask pit and pit / fuel pool walls are simulated by steel channel supported by steel angles and strips.
The structure is rigidly bolted together.
It weighs approximately 60 pounds.
All significant dimensions were met within one fiftieth of an inch.
This corresponds to 1/4 inch actual size.
Q.
Describe what you have done with the model.
A.
The cask pit assembly was placed on a slab of level concrete.
l Several trials were performed.
In the most conservative one the cask was placed with the axis vertical and just inside the plane of the cask pit wall.
Th cask v'ry s1ciny started its fall.
Accelerating, it struck the pit / pool wall, bounced slightly, and slid over the wall into the pool.
In a less conservative trial the vertical axis of the cask was placed
1 1/4 inches over the pit with the base resting on the pit wall.
The periphery of the cask was coincident with the plane of the pit wall.
On release the gask gyrated more rapidly toward the pit / pool wall than in the most conservative case.
On striking the wall it bounced appreciably, gyrated a bit and slid over the wall.
In the least conservative trial the cask was dropped 2 3/4 inches onto the P t wall.
The vertical i
axis was 1 1/4 inches ever the pit.
The result similar to that in the preseding trial.
The performance of the model taught a lesson not contemplated in either of the analyses: the cask after impacting the wall acquires a horizontal velocity component and slides in the final phase rather than pivoting on the edge of the pit / pool wall.
Q.
Has anyone else witnessed such a trial?
A.
Yes.
On March 24 representatives of Applicant (footnote 2, Applicant's April 1,1980 filing), and Staff witnessed a demonstration of the most conservative condition in which the cask is initially at rest with the vertical axis just beyond the p. lane of the pit wall.
. Applicant and Staff representatives were provided with the " Cask Drop Model" paper.
Measuring devices were provided so that relevant dimensions could be..
confirmed.
As it was raining the trial was conducted on a cover,d perch.
The pitch of the porch floor was such that the top of the pit /pcol wall was 1/4 inch hi her than the pit 6
wall.
This corresponds to a full scale elevation deifference of 3 inches.
This factor is in the direction of conservatism,.
that is it lessened the forces tending to propel the cask over the pit / pool wall.
.g.
into the fuel pool.
Although a rail cask would not be used in transfers between Oconee and McGuire, transfers between McGuire and Catawba, part of Applicant's plan as previously testified, could be done by rail.
The requirement that the pit / pool wall be raised appropriately, or some equally effective physical barrier, would dispose of this matter with finality, regardless of cask type, or the time which the operation took place.
Because there are significant deficiencies and uncertainties in the record in regard to a matter of safety, it is appropriate that material, relevant and reliable evidence, developed by CESG, be accepted and Applicant's motion to exclude it be denied.
CESG requests the Board to deny Applicant's motion to exclude CESG's supplemental cask drop evidence from the record.
Respec tfullyg'/
- ubmitted, l^
n Stil t/- ' 'U..:y esse L. Riley President, CESG At Charlotte, N.C.
April 16, 1980 t
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CASK DROP MODEL Scale 1"/18 A'e tual Model Theoretical Actual Full weight 50,000#
29#
22#
Length 8"
178 8
194" 16.17' 16.17" 26.27" Diameter at impact 30" 2.5' 2.5" 2.5" Bottom impact limiter length 8"
.67'
.67"
.67" diameter 50" 4 17' 4 17" 4 17" Cask pit width.
9' 9"
9" Fuel pool wall width 3'
3" 3"
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9 CESG 3-24-1980 l
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' he Matter of
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DUKE POWER COMPANY
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Docket No. 70-2623
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(Amendment to Materials License
)
l SNM-1773 for Oconee Nuclear
)
Station Spent Fuel Transportation
)
and Storage at McGuire Nuclear
)
Station)
)
AFFIRMATION OF SERVICE I hereby affirm thatcopies of "CESG's Response to Applicantis Motion to Deny Further Evidence in Cask DropIssue" and "Supplemen Testimony of Jesse L. Riley", both dated April 16, 1980, in the above captioned matter have been served upon the following by dep in the United States mail this 16th day of April,1980:
Marshall Miller, Esq.
Edward G.
Ketchen, Esq.
Chairman Counsel for NRC Regulatory S Atomic Safety and Licensing Board Office of the Executive Lega U.S. Nuclear Regulatory Commission Director Washington, D.C.
20555 U.S. Nuclear Regulatory Comm Washington, D.C.
20555 Dr. Cadet H. Hand, Jr.
Richard P. Wilson, Esq.
Director Bodega Marine Laboratory Assistant Attorney General University of California State of South Carolina P.O. Box 247 2600 Bull Street Bodega Bay, California 94923 Columbia, South Carolina 29 Dr. Emmeth A. Luebke David S. Fleischaker, Esq.
Atomic Safety and Licensing Board Natural Resources Defense Cc U.S. Nuclear Regulatory Commission 1735 Eye Street, N.W.,
Suite Washington, D.C.
20555 Washington, D.C.
20006 William Larry Porter, Esq.
J. Michael McGarry, III, Esq.
Associate General Counsel Debevoise and Liberman Duke Power Company 1200 Seventeenth Street, N.W.
P.O. Box 33189 Washington, D.C.
200036 Char'lotte, North Carol.ina
. We e
2-Chairman, Atomic Safety and Chairman, Atomic Safety and Licensing Board Panel Licensing Board Panel U.S. Nuclear Regulatory Commission U.S.
Nuclear Regulatory Washington, D.C.
20555 Commission Washington, D.C.
20555 Mr. Chase R.
Stephens Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C.
20555 O
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ps'se L. Riley
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