ML20052F516
| ML20052F516 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/05/1982 |
| From: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20052F515 | List: |
| References | |
| ISSUANCES-OLA, NUDOCS 8205130135 | |
| Download: ML20052F516 (8) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
) Docket No. 50-155-OLA CONSUMERS POWER COMPANY
) (Spent Fuel Pool
)
Modification)
(Big Rock Point Nuclear Power Plant)
)
AFFIDAVIT OF DAVID J.
VANDEWALLE i
District of Columbia: ss:
I, David J.
VandeWalle, of lawful age, being first duly sworn, do state as follows:
1.
I am currently employed by Consumers Power Company as Nuclear Licensing Administrator.
I have the responsibility within the company for all Nuclear Regulatory Commission (NRC) licensing activities.
2.
I hold a Bachelor of Science Degree in Nuclear Engineering and Master of Science Degree in Nuclear Engineering from the University of Michigan, Ann Arbor, Michigan.
Prior i
l to joining Consumers Power Company in November, 1976, I spent over three years at Westinghouse Electric Corporation-Pressurized Water Reactor Systems Division (PWRSD) in Monroe-l Ville, Pennsylvania. At PWRSD, I was involved in safety analyses of the reactor core and the nuclear steam supply system.
My duties included the preparation of accident and transient analyses for Chapter 15 of the Final Safety Analysis 8205130135 820505 PDR ADOCK 05000155 C
. Reports for new nuclear power plants, as well as safety analyses for operating plant reload fuel. Also included was the development of functional design criteria for reactor protection systems and engineered safety features.
3.
At Consumers Power Company, my duties include maintaining both formal and informal lines of communication with the NRC, interpreting regulatory guidance and developing Company positions on the guidance, tracking progress toward the meeting of commitments made to the NRC, maintaining all nuclear plant and material licenses, and evaluating and making final determinations of reportability under 10 C.F.R. Part 21, " Reporting of Defects and Non-Compliance."
4.
The purpose of this affidavit is to explain the urgency of Consumers Power Company's request to expand fuel storage capability at Big Rock Point and to point out that further delays in the licensing proceedings could je6pardize continued plant operation.
5.
The spent fuel pool at the Big Rock Point Plant will accommodate storage of 193 spent fuel assemblies.
Of these 193 storage locations, 132 are presently occupied with spent fuel bundles.
The remaining 61 unoccupied locations are inadequate to accept a full core off-load of 84 spent fuel assemblies. Thus, without storage locations being added to the pool in the form of additional spent fuel racks,
. there will be inadequate storage capacity to allow for a full core off-load during the next scheduled refueling outage.
6.
The ability to accommodate a full core off-load in the spent fuel pool is a matter of importance to plant operation, even thought it is not a safety requirement.
The
'f necessity to unload the entire reactor core may come about during either a planned or unplanned outage when access to areas normally obstructed by the core is required in order to perform maintenance activities such as inservice inspection of the reactor vessel or repairs to the reactor components.
Without sufficient storage capacity, an unplanned outage could become unpredictably long or required inspections could be delayed until the necessary storage locations become available.
7.
The next required inspection of the Big Rock Point i
reactor vessel is scheduled to be conducted during the next I
refueling outage.
This inspection is required by Part 50.55a of Title 10 of the Code of Federal Regulations.
10 l
C.F.R.
50.55a requires owners of nuclear power plants to 1
implement an Inservice Inspection Program based on Section l
l XI of the ASME Boiler and Pressure Vessel Code.
The Big Rock Point Inservice Inspection Program is currently abiding by the 1977 Edition with Addenda through Summer of 1978 of Section XI.
Table IWB-2500-1 (categories B-A, B-D and B-E )
l
. of Section XI requires that once in every ten-year interval, inspections must be completed on internal reactor vessel components such as nozzle and shell welds.
The Inservice Inspection which is scheduled for the next refueling outage will be the last opportunity during the current ten-year interval for Consumers Power Company to perform the required inspection of reactor vessel components.
In addition, because the ultrasonic inspection techniques that are available require removal of all of the fuel in order to inspect the vessel, additional spent fuel storage locations will be required in order to perform the inspection.
If additional spent fuel storage locations are not available at the next refueling outage, the reactor will have to remain shutdown until the additional storage locations are made available.
8.
Based on reactor physics calculations performed by our Reactor Engineering Department, the Big Rock Point Plant could enter the next refueling outage as early as March 15, l
1983.
This date is based upon a reactor startup date of April 29, 1982, and a design core energy output of 5.52 gigawatt days per ton of fuel which equates to 287 days of l
operation at 208 megawatts-thermal followed by 34 days of coastdown after all of the control rods have been withdrawn l
l from the core.
l l
1
. 9.
I have been advised by counsel that if the hearings, which are presently scheduled during the first part of June, are postponed beyond June 16, it would be likely that the Licensing Board would reschedule the hearings after Labor Day because of Mr. O'Neill's concerns with his restaurant business during the summer months.
Based on this assumption, counsel also provided me with the following hearing scenario and schedule:
(a) Sept. 14, 1982 Hearings commence.
(b) Sept. 24, 1982 Hearings end.
(c) Nov. 18, 1982 Findings of fact and conclusions of law sub-mitted by all parties (55 days), including briefs on NEPA issues.
(d ) Dec. 18, 1982 Adverse ASLB ruling on NEPA issues.
(e) March 18, -1983 Complete environmental impact statement exercise or preparation of testi-mony on alternatives pursuant to Section 102 (2 ) (E ).
(f) March 31, 1983 Commence second phase l
of hearings regarding NEPA issues.
(g) Apr.
3, 1983 Complete second phase hearings.
(h) May 27, 1983 Findings of fact, etc.,
submitted.
(i) June 27, 1983 30 days contingency for time extension delays requested by the parties.
1
(j ) Aug. 13, 1983 Favorable initial ASLB decision on all issues.
(k) Aug. 18, 1983 License amendment issued by NRC Staff.
1 I was further advised by counsel that if the hearings were completed by June 16, 1982, the license amendment would issue, assuming the remaining assumptions were unchanged, by May 14, 1983.
10.
On the basis of the foregoing, I conclude that a delay in the hearings until e.f ter Labor Day could cause the refueling outage to be unnecessarily extended by as much as three months.
YdNJ Y jtyjg Subscribedj nd sworn to before me this SO day of May, 1982.
$ ;f M_
a NotargPublic
/
Mr Commision Expires Januarg I,1987 n
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
) Docket No. 50-155-OLA CONSUMERS POWER COMPANY
) (Spent Fuel Pool
)
Modification)
(Big Rock Point Nuclear Power Plant)
)
CERTIFICATE OF SERVICE I hereby certify that copies of MOTION TO SUPPLEMENT REPLY TO MOTION FOR TIME EXTENSION were hand-delivered to Judge Bloch, Judge Paris, Judge Shon, Janice Moore, and Herbert Semmel, and were served on the other persons listed below by deposit in the United States mail, first-class postage prepaid, this 5th day of May, 1982.
Peter B. Bloch, Esquire Atomic Safety and Licensing Admin ~istrative Judge Board Panel Atomic Safety and Licensing U.
S. Nuclear Regulatory Board Panel Commission U.
S. Nuclear Regulatory Washington, D.
C.
20555 Commission Washington, D.
C.
20555 Atomic Safety and Licensing Appeal Board Panel Dr. Oscar H. Paris U.
S. Nuclear Regulatory Administrative Judge Commission Atomic Safety and Licensing Washington, D. C.
20555 Board Panel U.
S.
Nuclear Regulatory Docketing and Service Section Commission Office of the Secretary Washington, D.
C.
20555 U.
S. Nuclear Regulatory Commission Mr. Frederick J.
Shon Washington, D.C.
20555 Administrative Judge Atomic Safety and Licensing Bcard Panel U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 i
1
' Janice E. Moore, Esquire Judd Bacon, Esquire Counsel for NRC Staff Consumers Power Company U.
S.
Nuclear Regulatory 212 West Michigan Avenue Commission Jackson, Michigan 49201 Washington, D. C.
20555 Ms. Christa-Maria Richard G.
Bachmann, Esquire Route 2, Box 108C U. S.
Nuclear Regulatory Charlevoix, Michigan 49720 Commission Washington, D. C.
20555 Mr. Jim Mills Route 2, Box 108 Herbert Semmel, Esquire Charlevoix, Michigan 49720 Urban Law Institute Antioch School of Law Ms. JoAnne Bier 2633 16th Street, N.W.
204 Clinton Washington, D.
C.
20555 Charlevoix, Michigan 49720 Mr. John O'Neill, II Route 2, Box 44 Maple City, Michigan 49664 o
C.Ll_
D jPhyllis D. Macey 4'
l l
.