ML20090K360
| ML20090K360 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/08/1983 |
| From: | Tuckman M DUKE POWER CO. |
| To: | |
| References | |
| A-090, A-90, NUDOCS 8405240177 | |
| Download: ML20090K360 (10) | |
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DUKE POWER COMPANY, et al. )
Docket Nos.
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50-414 (Catawba Nuclear Station,
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Units 1 and 2)
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TESTIMONY OF MICHAEL S. TUCKMAN 1
Q.
WHAT IS YOUR NAME?
2 A.
Michael S. Tuckman.
3 Q.
BY WHOM ARE YOU EMPLOYED?
4 A.
Duke Power Company.
5 Q.
IN WHAT CAPACITY ARI' YOU EMPLOYED BY DUKE POWER 6
COMPANY?
("'3 7
A.
I am employed by Duke Power Company as the Superintendent of V
8 Technical Services at the Catawba Nuclear Station.
9 Q.
HOW LONG HAVE YOU BEEN EMPLOYED IN THIS POSITION?
10 A.
I have been employed in this position since January,1978.
11 Q.
WHAT IS YOUR EDUCATIONAL AND PROFESSIONAL BACKGROUND?
12 A.
I obtained a Bachelor Degree in Electrical Engineering from Georgia 13 Institute of Technology in 1965.
I participated in the U.S. Navy 14 Nuclear Propulsion Training Program as an officer from 1965-1969 15 and 1972-1974.
I also attended graduate school at University of 16 Tennessee in Electrical Engineering.
I am an NRC Certified Senior 17 Reactor Operator and a Registered Professional Engineer in North 18 Carolina.
My work experience includes 6 years Navy nuclear 19 experience; 3 years Electrical Development Engineer at Union g
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20 Carbide Corporation, Oak Ridge, Tennessee; 3 years with Duke 8405240177 831208
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1 Power company as Oconee Licensing Engineer; and 5\\ years with
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Duke Power Company as Superintendent of Technical Services, 3
Catawba Nuclear Station.
Effective October 1,
1983, I will be 4
transferred to Oconee Nuclear Station as Assistant Station Manager.
5 My resume is included as Attachment 1.
6 Q.
WHAT IS THE PURPOSE OF YOUR TESTIMONY?
.7 A.
The purpose of my testimony is to address that part of Contention 8
16 which deals with the storage of Oconee and McGuire spent fuel 9
at Catawba.
In particular, I will address that part of the 10 contention which deals with the handling of the cask to unload 11 spent fuel assemblies and move them into position in the spent fuel 12 pool.
13 Q.
WILL CASK HANDLING BE NECESSARY TO UNLOAD ANY SPENT 14 FUEL ASSEMBLIES WHICH MAY ARRIVE FROM OCONEE AND 15 MCGUIRE FOR STORAGE IN THE CATAWBA SPENT FUEL POOL?
16 A.
Yes.
17 Q.
AS SUPERINTENDENT OF TECHNICAL SERVICES AT THE 18 CATAWBA NUCLEAR STATION WHAT ARE YOUR AREAS OF 19 RESPONSIBILITY?
20 A.
I am responsible for radiation protection, chemistry, performance 21 engineering, licensing, project engineering and emergency 22 preparedness at the Catawba Station.
23 Q.
PLEASE DESCRIBE YOUR FAMILIARITY WITH HANDLING SPENT 24 FUEL.
25 A.
My familiarity with spent fuel unloading and storage procedures is 26 based upon several years' supervision of the reactor engineering
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27 and health physics sections, which are responsible for review of 28 spent fuel handling procedures, radiation protection measures to be
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nuclear material.
3 Q.
HAS CATAWBA DEVELOPED PROCEDURES FOR THE HANDLING 4
AND STORING OF SPENT FUEL FROM DUKE POWER COMPANY'S 5
OCONEE AND MCGUIRE STATIONS AT CATAWDA?
6 A.
No.
However, Applicants have draft procedures for handling and 7
storage of Oconec and McGuire spent fuel at Catawba.
Because 8
there is no immediate need to transfer Oconee and McGuire spent 9
fuel to Catawba, we have not yet finalized written procedures for i
10 this process.
Catawba personnel are already generally familiar with 11 the procedures which will be used.
12 Q.
WHAT IS THE BASIS FOR YOUR STATEMENT?
j 13 A.
Applicants have had considerable experience in unloading and 14 storing Oconee spent fuel at the McGuire plant, and in transferring 15 Oconee spent fuel from one Oconee spent fuel pool to another 16 during re-racking activities.
The procedures which will be used 17 for unloading and storing Oconee and McGuire spent fuel at j
18 Catawba are essentially the same as those approved for use at both 19 Oconee and McGuire.
Catawba personnel have familiarized 20 themselves with these procedures, have observed fuel handling 21 operations, and in some instances have participated in fuel handling 22 operations at Oconee and McGuire.
23 Q.
WOULD YOU PLEASE DESCRIBE THE PROCEDURES THAT YOU L
24 CONTEMPLATE WILL BE UTILIZED IN THE HANDLING AND r
25 STORING OF OCONEE AND MCGUIRE SPENT FUEL AT CATAWBA?
l l
26 Q.
Based upon experience at Oconee and McGuire, I contemplate the O
27 following procedures will be utilized.
First, before Oconee or
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1-McGuire spent fuel is received and unloaded at the Catawba Station, O
2 certain measures will be taken. These include the following:
3 (a) The reactor engineer or the operation's fuel handling 4
supervisor will. receive notification of the spent fuel shipment 5
and will authorize receipt and storage.
6 7
(b) The Catawba health physicist or his representative will receive 8
notification of the shipment.
9 10 (c) Periodic tests of the 125-ton overhead fuel handling bridge 11 crane and the auxiliary hoist will have been performed 12 pursuant to applicable regulatory requirements. This includes 13 an inspection prior to use and completion of a checklist.
14 15 (d) Lifting equipment (short and long lift adapter, lifting yoke) 16 will have been periodically inspected as necessary.
17 18 (e) Water and air supplies will be available.
19 20 (f) Spent fuel building radiation monitors will have been checked 21 from the control room prior to transferring the spent fuel, in 22 order to assure that the monitors are operable.
23 24 (g) A radiation work permit for receipt of the cask will be issued 4
4 25 by the Catawba health physics section.
26 27 (h) The necessary tools and equipment will have been inventoried 28 and readied.
29 30 (i)
Sufficient underwater lighting equipment will be available.
31 j
32 (f)
The ventilation system of the spent fuel pool will have been 33 checked. to verify that it is operating in the filtered mode.
34 35 Q.
AFTER THESE PRELIMINARY MEASURES HAVE BEEN TAKEN, WHAT 36 ACTIVITY ENSUES?
4 37 A.
Once the flatbed carrying. the cask has been positioned in the 38 designated part of the receiving area in the spent fuel pool 39 building, health physics personnel then survey the transport trailer 40 and personnel barrier for external radiation contamination levels.
41 The flatbed and -personnel barrier are inspected by the operations 42 staff for any physical damage.
If the tamper seal has been broken 43 or damaged, or indicates an attempt to render it inoperable, the,-
1 shift supervisor will be contacted and work will cease.
A 2
designated Duke employee in the general office will then be 3
notified, and will decide whether to call the NRC.
If any damage 4
to the barrier or the flatbed is
- evident, the cask vendor 5
representative and the Duke representative must concur on the 6
advisability of continued use of equipment.
7 Q.
WHAT IS THE NEXT STEP?
8 A.
Bolts are removed from the personnel barrier on the flatbed.
Upon a
9 approval of health physics personnel, the personnel barrier is 10 removed and placed on a nearby concrete pad, or other suitable 11 location.
Health physics personnel survey the cask for external 12 radiation contamination levels.
All work then stops on the cask 13 until health physics gives approval to continue.
i 14 Q.
WHAT HAPPENS AFTER APPROVAL IS GIVEN?
15 A'.
Once such approval is given, the impact-limiting structures on the 16 top and bottom of the cask are removed with the use of the 17 auxiliary hoist and sling and placed on the flatbed.
The cask 18 tie-down bolts are then removed and placed on the flatbed.
19 Q.
ONCE THE IMPACT-LIMITING STRUCTURES AND THE CASK 20 TIE-DOWN BOLTS ARE REMOVED, WHAT HAPPENS?
21 A.
A lifting device (consisting of the 125 ton overhead bridge crane, 22 the short lift adapter, and the yoke) is moved into position above 23 the cask.
The cask is raised to a vertical position, with the crane 24 moving as required to keep the hoist cable vertical. When the cask i
25 is fully vertical, it is raised, moved approximately 15 feet so that it 26 is positioned over the decontamination pit and lowered into the pit.
O 27 The decontamination pit is shown in FSAR Figures 9.1.1-1, 9.1.1-2 28-and 9.1.2-2. __
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DECONTAMINATION PIT?
3 A.
Once the cask is in the decontamination pit, the operating staff 4
then begins preparing the cask for the removal of the fuel 5
assembly.
The outer cavity drain valve covers are removed.
6 Next, the outer closure head bolts are removed and, using a sling 7
on the auxiliary hoist, the outer closure head of the cask is 8
removed and placed on the work platform in the decontamination 9
pit.
It is inspected for damage.
Health physics personnel then 10 survey the top portions of the inner closure head and adjacent cask 11 surfaces, and work halts until they give approval to continue.
12 Q.
WHAT HAPPENS AFTER APPROVAL IS GIVEN?
13 A.
Once approval is given the inner head valve covers are removed, in 14 preparation for flushing the cask.
A water supply hose and a vent 15 hose are then attached to the cask's inner head valves and the cask 16 is filled with water.
The displaced helium is routed by a 17 hose / filter system to the spent fuel ventilation system.
The inner i
18 head bolts are then loosened, but not removed.
The short inner 19 head guide pins are replaced with long inner head guide pins (for 20 later removal and replacement of the inner head.)
4 21 Q.
WHAT IS THE NEXT STEP?
22 A.
The lifting device (consisting of the 125 ton overhead bridge crane, 23 the short lift adapter, and the yoke) is then prepared and moved 24 into position for movement of _ the cask into the cask handling area 25 of the spent fuel pool.
After the yoke has been attached to the i
26 cask, the cask is lifted out of the decontamination pit, moved.about h
27 15 feet into position and lowered into the shallow portion (i.e., the 28 upper platform) of the ' cask handling area of the spent fuel pool.
1
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the ' ask is being lowered onto the upper platform, it is 1
-While c
2 sprayed with ' demineralized water in order to minimize cask 3
contamination.
4 Q.
IS THE CASK TOTALLY UNDER WATER ONCE IT IS POSITIONED' 5
ON THE UPPER PLATFORM?
6 A.
No.
Approximately 1\\ feet of the cask remains above the water at 7
this point.
8 Q.
WHAT TAKES PLACE ONCE THE CASK IS POSITIONED ON THE l
9 UPPER PLATFORM?
10 A.
When the cask rests in a vertical position on the upper platform, 11 the yoke is disengaged.
The short lift adapter is then 12 disconnected from the yoke and the 125 ton overhead bridge crane 13 hook, and is replaced with the long lift adapter.
This adapter is j
14 then connected to the overhead bridge crane hook and the yoke.
15 The inner closure head slings are then attached to the yoke. The 16 yoke is then engaged and the cask is lifted.
The inner closure 17 head is then attached to the yoke by means of the inner closure 18 head slings.
The cask is moved approximately 8 feet into position l
19 and lowered until it rests on the' deep end of the cask handling i
20 area (i.e., the lower platform).
21 Q.
IS THE CASK TOTALLY UNDER WATER ONCE IT IS POSITIONED I
22 ON THE LOWER PLATFORM?
23 A.
Yes.
24 Q.
HOW MUCH WATER IS ABOVE THE TOP OF THE CASK?
25 A.
Approximately 25 feet.
26 Q.
WHAT. TAKES PLACE ONCE THE CASK IS POSITIONED ON THE O
22 TOWER PtiTPORM?
l' 7
p 1
A.
With the cask resting on the lower platform, the yoke is
.O 2
disengaged.
At this point, the top of the cask is covered with 3
approximately 25 feet of water.
Thereafter, the lifting device is 4
raised.
As it is raised, the inner closure head slings become taut 5
and the inner head of the cask is lifted.
While remaining 6
underwater, the inner head is raised until it clears the upper 7
platform of the cask handling area and is moved away from the 8
cask.
9 Q.
WHAT PROCEDURES ARE UTILIZED TO REMOVE THE ASSEMBLY 10 FROM THE CASK?
11 A.
The appropriate spent fuel handling tool (the exact tool used will 12 depend upon the fuel assembly design) is then lifted by the east 13 manipulator crane auxiliary hoist, is positioned over the fuel 14 assembly, and is attached to the assembly.
The assembly is then 15 lifted clear of the cask, and transported through the open weir to 16 the location in the spent pool designated by the reactor engineer.
17 At the point at which the assembly is lifted clear of the cask, it is 18 covered by approximately 10 feet of water above the top of the 19 assembly.
Thereafter, the assembly is lowered into position, and 20 the fuel handling tool is disengaged.
The cask is then prepared 21 for re-use.
This activity completes the transfer of the assembly.
22 Q.
WHAT MEASURES ARE TAKEN DURING FUEL HANDLING 23 ACTIVITIES TO ASSURE THAT RADIATION EXPOSURES ARE 24 MAINTAINED AS LOW AS REASONABLY ACHIEVABLE (ALARA)?
25 A.
Various measures taken are designed to keep employee radiation l
l 26 exposure ALARA.
First, the design of the spent fuel cask O
27 provides shielding to workers.
In addition, health physics l
28 personnel perform surveys of the cask for radiation levels and l,
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contamination before unloading begins.
Additional health physics
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coverage is provided throughout the unloading and handling process 3
to assure that proper radiation protection practices are followed and 4
to detect any abnormalities.
The venting of the cask through a 5
particulate filter directly to the spent fuel pool ventilation system 6
also minimizes internal radiation hazards. Finally, the inner closure 7
head of the cask is removed under water to keep worker exposure 8
as low as reasonably achievable.
9 10 11 I hereby certify that I have read and understand this document, and 12 believe it to be my true, accurate and complete testimony, b.
16 Michael S. Tuckman 17 18 19 Sworn to and subscribed before me 20 this 39th day of September,1983.
21 22 23 y k snionrfi C Oca m ic_a (LDcdcro )
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ATTACHMENT 1 s
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t, RESUME OF MICHAEL STEVEN TUCIWAN l,
Holds a Bachelor Degree in Electrical Engineering from Georgia Institute of Technology - 1965 1
Attended Navy Nuclear Propulsiota. Training Program (Officer)
Graduate School at University of Tennessee in Electrical
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Engineering v.',
NRC Certified Senior Reactor Operator Q
i Registered Professional Engineer in Nor,th Carolina
'and South Carolina Work Experience i
/
6 years Navy, nuclear experience
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3 years Electrical Development Engineer, at Union Carbide N
Corporation, Oak Ridge,7 ennessee T
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3 years. Duke Power Company, Oconee Licensing Engineer l ' O ? ss year., Duxe,ower Company, Sugerintenderie of Technica1 Services, Catawba Nuclear Station s
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