ML20090K358

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Applicant Exhibit A-89,consisting of Testimony of Mc Green Re Differences in Design & Characteristics Between Current Spent Fuel Pools & Original Spent Fuel Pool
ML20090K358
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/08/1983
From: Matthew Green
DUKE POWER CO.
To:
References
A-089, A-89, NUDOCS 8405240175
Download: ML20090K358 (8)


Text

.

Y & c UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

,a \xi j Ef F.M BEFORE THE ATOMIC SAFETY AND LICENSING tHOAR(R 3 2 0 i'M>

l stavzcz raAuca

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SEcY- I;'O In the Matter of ) W /

DUKE POWER COMPANY, et al. ) Docket Nos. 50-41

) 50-414 (Catawba Nuclear Station, )

Units 1 and 2) )

TESTIMONY OF MICHAEL C. GREEN 1 Q. STATE YOUR NAME.

2 A. Michcel C. Green 3 Q. BY WHOM ARE YOU EMPLOYED?

4 A. Duke Power Company, 422 South Church Street, Charlotte, North 5 Carolina 28242.

6 Q. WHAT IS YOUR POSITION WITH THE COMPANY?

7 A. I am Supervising Design Engineer with the Design Engineering 8 Department. A copy of my resume is included as Attachment A.

9 Q. DESCRIBE THE NATURE OF YOUR JOB.

10 A. I supervise a group of engineers responsible for analyses and 11 designs of various buildings and structures at Catawba.

12 Q. WHAT IS THE PURPOSE OF YOUR TESTIMONY?

13 A. The purpose of my testimony is to address the differences in design 14 and characteristics between the current Catawba spent fuel pools 15 and the original spent fuel pools as described in the PSAR.

16 Q. WHICH BUILDING AND STRUCTURES AT CATAWBA COME WITHIN 17 YOUR RESPONSIBILITY?

18 A. Auxiliary Building, Diesel Generator Buildings, New and Spent Fuel 19 Pool Buildings, Auxiliary Service Building, Main Steam Doghouse O 20 Structures, Upper Head .njection Buildings, Steam Generator Drain 21 Building.

8405240175 831200 PDR ADOCK 05000 G

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1 Q. PLEASE DESCRIBE THE PERTINENT CHARACTERISTICS OF THE 2 ORIGINAL SPENT FUEL POOLS AS SET FORTH IN THE PSAR.

3 A. Originally, the fuel pools were each to be "L" shaped with a 12'-10" 4 width on the west end and a 20'-1" width on the east end. The 5 overall length of each pool was to be 56'-3\". The bottom elevation 6 of each pool was to be at elevation 558+6" with the top of the water 7 under normal operating conditions to be at elevation 598+4 3/4".

8 The original pool layouts would have accommodated 281 spent fuel 9 assemblies in each pool. The spent fuel assemblies would have been 10 spaced 21" center to center. The original design of the spent fuel 11 pool is depicted on the attached PSAR figure 9.1.1.-2.

12 Q. DID YOU SUBSEQUENTLY MODIFY THE STORAGE CAPACITY OF 13 THE SPENT FUEL POOLS?

14 A. Yes. The storage capacity of the spent fuel pools has been 15 modified twice since originally designed. First, the spacing of the 16 spent fuel assemblies was modified from 21" to 13\" center to l

17 center. This spacing, using the originally sized spent fuel pools, 18 but different storage racks (i.e. , more closely spaced racks) would 19 have accommodated 664 assemblies per pool. Subsequently, when 20 the overall size of the spent fuel pools was increased, the storage 21 capacity of the spent fuel pools was correspondingly increased to 22 1418 assemblies per pool. The spacing of the assemblies remains l 23 13\" center to center.

24 Q. HAS THE SIZE OF THE ORIGINAL SPENT FUEL POOLS BEEN 25 MODIFIED?

26 A. Yes. The final layout of the spent fuel pools is shown on FSAR

] 27 figures 9.1.2-2 and 9.1.2-3. The basic shape of the fuel pools 28 remains "L" shaped, with the overall length of the pools increased.

l

-- 1 While the overall length of the pools as originally designed was 2 approximately 56', the current pools have an overall length of 3 shghdy over 119' each.

4 The widths of each pool vary only slightly from the original 5 concept. The current pools are 12'-9" wide on the west end and 6 21'-6" wide on the east end (compared to original concept widths of 7 12'-10" and 20'-1") .

8 The bottom elevation of each pool remained at elevation 558+6 9 as originally planned and the water elevation in the final layout 10 remained at 598+4 3/4". Thus the depth of the pool remains the 11 same.

12 Q. DO THE ANALYSES PERFORMED ON THE SPENT FUEL POOLS, 13 WHICH ARE SET FORTH IN THE FINAL SAFETY ANALYSIS REPORT 14 (FSAR), UTILIZE THE ENLARGED DESIGN (I.E.,1418 ASSEMBLIES 15 PER POOL)?

16 A. Yes. All analyses and designs pertaining to the buildings and ,

17 storage racks set forth in the FSAR utilize the expanded building j 18 size and closer rack spacings.

19 Q. WHAT EFFECTS DO THE ENLARGED POOL AND CLOSER SPACING 20 HAVE ON THE STRUCTURAL INTEGRITY OF THE SPENT FUEL l

21 POOL BUILDINGS?

22 A. The height of the building, and depth of water contained therein, 23 has not changed from the original concept. Therefore, the bearing 24 pressure on the concrete foundation and rock below which results 25 from the water depth is not any greater with the expanded design 26 than what would have existed with the original concept.

! O 27 The closer fuel spacings will increase bearing pressure on the l 28 foundation. ' However, the effect on the foundation is insignificant.

t

l. L

r~3 1 The total weight of one of our existing storage racks loaded with y

2 assemblies is 119,135 lbs. (This assumes use of heavier B&W fuel.

3 The total weight of a loaded rack would be 115,571 lbs. if full of 1 4 Westinghouse assemblies.) Each rack has four legs, so the weight 5 on each leg is approximately 30,000 lbs. (This is dry weight, so 6 the figure is conservative.) This 30,000 pounds results in a 7 maximum shear stress on the foundation of 24 pounds / square inch.

8 If similar racks were used with 21" spacing center to center, the 9 approximate shear stress on the concrete foundation would be 11

, 10 pounds / square inch. The capacity of the 4 foot thick foundation is 11 109 pounds / square inch . Thus the increase in shear stress is 12 insignificant.

, 13 l

14 15 16 I hereby certify that I have read and understand this document, and ,

17 believe it to be my true, accurate and complete testimony.

21 Michael C. Green 22 23 24 Sworn to and subscribed before me

. 25 this A9 u day of September,1983.

26

%Yh b AW 29 g/ Notary Public 30 O 31 co--i io zxvire /desd 24 /9tl

Attachment A

' ~

, MICHAEL CHARLES GREEN PERSONAL: Home Address: 6019-104 Lake Forest Drive Charlctte,.NC 23212 I Q Telephone: (704) 535-0654 (Home)

(704) 373-7119 (Office)

Age: 33 Height: 6'-0" Weight: 205 lbs.

FORMAL EDUCATION: University of Tennessee: BSCE, 1972 i

PROFESSIONAL ACTIVITY: Registered P.E. in North Carolina - #7993 Member ASCE- .

President Elect - N.C. Section of ASCE 1982-1983

, Vice President - N.C. Section of ASCE 1981-1982 President - Southern Branch of N.C. Section of ASCE 1980-1981 Vice President - Southern Branch of N.C. Section of ASCE 1979-1980 Chairman of Membership Comittee - Southern Branch 1978-1979 3 Chairman of Seminar on Hydro Electric Pump Storage - Joint Power

Generation Conference - St. Louis 1981 ,

ADDITIONAL l TRAINING:

MANAGEMENT TECHNICAL SEMINARS

1) Various STRUDL/DYNAL Seminars 1) Aberrant Behavior Training i 2) Foundation Engineering Seminars 2) Controlling Absenteeism M

U

3) Geotechnical Seminars
4) ACI Code Seminars
3) Effective Interviewing
4) Effective Management
5) Tornado Missile Impact Seminars 5) Management Development (ASCE Structural Convention) 6) Advanced Management Development
6) Engineering Economics Seminars 7) Productivity Seminars ,
8) Time Management
9) Space Allocation
10) Interviewing Techniques WORK EXPERIENCE: (All with Duke Power)

FROM TO TITLE PROGRAM i 6/76' Present Assistant Design Engineer Oconee Nuclear Station (6/76 to 6/78) Catawba Nuclear Station Supervising Design Engineer Bad Creek Project (6/78 to Present) l In charge of engineering subgroup responsible for the structural analysis and i

design of various aspects of the Oconee Nuclear Station, Catawba Nuclear Station, and the Bad Creek Pumped Storage Facility.

Oconee l

In responsible charge of the intial analysis and design of the Standby Shutdown O raciiity. The respaasibiiities iaciuded the preparation of the excavation r

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WORK EXPERIENCE (CONTli. 0)

FROM TO TITLE PROGRAM 6/76 Pre nt (continued) specification (which included blasting near the operating Reactor Building) as well as the static and dynamic analyses of the structure itself.

Catawba The responsibilities at Catawba included the structural analysis and design of the Auxiliary Building, the Spent Fuel Pool Buildings, the New Fuel Buildings, the Diesel Generator Buildings, the Upper Head Injection Buildings, the Auxiliary Service Building as well as various yard structures. Analysis requirements included both static and dynamic considerations, including earthquake, tornado missile impacts, pipe whip and jet impingements. ' Responsibilities at Catawba also included the analysis and design of various internals to the above mentioned buildings; i.e., Spent Fuel Storage Racks, New Fuel Storage Racks, various equipment supports, and miscellaneous platforms, etc...

Duties required by these responsibilities include the development of calculations, specifications, and drawings as appropriate. Duties also included vendor contact, interfacing with the NRC regarding the licensing effort as well as the day-to-day interfacing with Construction Department personnel.

Bad Creek The responsibilities of the subgroup regardino the Bad Creek Project center O primarily on the underground configuration of~the intake, tailrace and access tunnels as well as the powerhouse chamber orientation. A " pilot" tunnel was driven to determine charactecistics of the rock, with the results of these tests being used in the final design of the underground excavation.

Other duties pertaining to Bad Creek included the overall department scheduling, annu-al costestimate preparation, and interfacing with the FERC in the licensing efforts.

Supervise from 7 to 14 engineers in this time period.

Engineer Associate Catawba 12/73 6/76 l Responsible for the analysis and design of specific items pertaining to the Catawba Nuclear Station. Designs included: a) Groundwater drainage system; b) l i Frame analyses of the Auxiliary Building; c) Dynamic amplification factor determination from pipe whip transients; d) Miscellaneous equipment supports, stairs, platforms, etc.

12/73 Junior Engineer Belews Creek 6/72 Responsible for various designs relating to the Belews Creek Coal Fired Station including: a) Transformer bases; b) Switchyard bases; c) Conduit Manholes; d) Sewage Treatment Structures; e) Fuel Oil Storage Area; f) Miscellaneous Equipment Supports.

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