ML19296D831

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Affidavit Re Coalition for Safe Power Contention 22 Alleging Incomplete Analysis of Steel Plate Effects on Displacement. Discusses Analysis Performed & Explains Effect of Steel Plate Addition.W/Prof Qualifications & Certificate of Svc
ML19296D831
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 02/06/1980
From: William White
BECHTEL GROUP, INC.
To:
Shared Package
ML19296D792 List:
References
NUDOCS 8003130308
Download: ML19296D831 (7)


Text

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r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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)

PORTLAND GENERAL ELECTRIC COMPANY,)

Docket No. 50-344 et al.

)

(Control Building

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Proceeding)

(Trojan Nuclear Plant)

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)

AFFIDAVIT OF DR. WILLIAM H.

WHITE COALITION FOR SAFE POWER'S CONTENTION NO. 22 1.

My name is William H.

White.

I am employed by Bechtel Power Corporation (Bechtel) in the San Francisco Power Divi-sion as an Engineering Specialist.

I have been employed in this position since 1976.

My professional qualifications are contained in an attachment to this affidavit.

2.

I participated in the performance of the seismic analy-sis of the Trojan Control Building, Auxiliary Building and Fuel Building Complex (Complex) for the licensing proceedings on interim operation, and have either performed or supervised the seismic analysis of the Complex with the proposed modifi-cations.

These analyses determined, among other things, the displacements of structural elements of the Complex.

3.

The purpose of this affidavit is to address Con-solidated Intervenors' Contention No. 22 which reads as follows:

The effect of the steel plate on displacement in the Complex has not been completely analyzed.

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CFSP #22 Page 2 ef 6 Dr. W.

H.

White 4.

This affidavit will discuss the analyses that have been performed to determine displacements in the Complex and will explain the effect of the addition of the steel plate.

5.

During a seismic event, structures and their components undergo displacements.

These displacements are time-dependent, and at any moment different elements of a structure may exper-ience displacements of dif ferent directions and magnitudes.

One such relative displacement can be classified as an inter-structure displacement, which affects two adjacent structures such that if excessive displacements were to occur, they could strike each other.

6.

For interim operation, an analysis was performed for the entire Complex in the as-built condition to calculate the maximum displacements of the Control Building and the adjacent structures, both in the north-south and in the east-west directions.

Displacement values were obtained at all floor levels and all column lines.

The relative displacements were conservatively obtained by taking the absolute summation of the respective displacements at various levels.

The gaps provided between the Control Building and the structural elements of adjacent structures exceed the calculated relative displacements by a wide margin, assuring that the buildings will not touch.

7.

As part of the modification work, the west wall (R-line wall) will be strengthened by a steel plate which will be added to the west face of the wall between column lines 41

CFSP #22 Page 3 of 6 Dr.

W.

H.

White and 47, from el.

59'-3" to el.

97'-3".

This plate is three inches thick and will be secured to the wall by high strength bolts.

This plate and the addition of new concrete walls a-long column lines N, N',

and R will increase the stiffness of the Complex.

Because of the added stiffness, the displacements along any wall, including the R line wall, during a seismic occurrence will be smaller than they would have been prior to the modifications.

8.

If additional measures were not taken, the addition of the 3 inch steel plate would eliminate some of the existing gap between the Control Building and Turbine Building at el. 93' and 69',

where Turbine Building girders and floor slabs are located.

At all other levels and locations, the sufficiency of the existing gap is not af fected by the addition of the 3 inch steel plate.

To assure a sufficient gap remains following completion of the modification program, prior to the installation of the steel plate, the following will be perforr.ed in the Turbine Building:

1.

At el. 93' between column lines 41 and 47, 3 inches will be removed from the concrete slab and 2 inches will be removed from the steel girder flange.

2.

At el.

69',

between column lines 41 and 47, approx-imately 1 ft. 6 in of the overhanging part of the concrete slab will be removed without any modifica-tion to the steel girder.

CFSP #22 Page 4 of 6 Dr.

W.

H.

White 9.

An analysis of the modified Complex was performed to determine the displacements.

The following table lists the relative displacements of the two structures at the two sensi-tive levels, the absolute summation of such displacements and the " gap" which will be provided by the foregoing modifica-tions ac each level to assure that the two structures will not touch:

Control Building and Turbine Buildina Relative Displacements at Plate, and Gaps Provided Maximum EW Displacements (Inch) SSE.25g El. 93' El. 69' Turbine Building (TB) @ 5% damping 0.9 0.15 Control Building (CB) @ 5% damping 0.046 0.031 ABS Combination TB & CB 0.946 0.181 Gap provided after modifications are made 2.0 2.5 Maximum NS Displacements (Inch) SSE.25a El. 93' Turbine Building (TB) @ 5% damping 1.25 Control Building (CB) @ 5% damping 0.086 ABS Combination TB & CB 1.336 Gap provided at plate 4.0 (No modifications needed)

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CFSP #22 Page 5 of 6 Dr.

W.

H.

White 10.

The above discussion demonstrates that the effect of the addition of the steel plate on displacements in the modified Complex has been fully analyzed to assure that, in the event of a seismic occurrence, the gap between the Turbine and Control Buildings will be adequate to prevent the buildings from touching.

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CFSP #22 Page 6 of 6 Dr.

W.

H.

White I, William H. White, of lawful age, being first duly sworn, state that I have reviewed the foregoing af fidavit, and that the statements contained therein are true and correct to the best of my knowledge and belief.

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WILLIAM H.

WHITE STATE OF CALIFORNIA

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C ty of SUBSCRIBED AND SWORN TO before me this bT4. day of bAbrutus 197D.

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PROFESSIONAL QUALIFICATIONS OF WILLIAM H.

WHITE PRES ENT POSITION Engineering Specialist, Bechtel Power Corporation EDUCATION BS, Civil Engineering, University of Idaho; MS, Civil Engineering, University of Colorado; PhD., Civil Engineering, University of Colorado.

PRCSSIONAL Registered Professional Engineer, Oregon DATA Member, American Society of Civil Engineers.

SU MMARY 3 years:

Engineering Specialist 2 years:

Structural Engineer 6 years:

Assistant Professor 1 year:

Senior Engineer EXPERIENCE Dr. White has been employed as an Engineering Specialist with Bechtel's San Francisco Power Division since 1976.

He is assigned to the Chief Civil Engineer's Staff where he is responsible for seismic analysis.

Earlier, Dr. White was a Structural Engineer with the Tennessee Valley Authority for 2 years where he was responsible for seismic analysis of all Category I structures for a twin-unit nuclear power plant, including the seismic input for the design of the nuclear steam supply system.

From 1968 to 1974, Dr. White was an Assistant Professor at Oregon State University where he taught undergraduate and graduate courses in structural mechanics and analysis and computer applications.

Prior to joining Oregon State, Dr. White was em-ployed at the Bettis Atomic Power Laboratory for a year.

At Bettis, he was a Senior Engineer working on shock analysis of nuclear reactors a-board submarines and was involved in programs to assess the shock resistance of reactor internals.

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3 UNITED STATES OF AMERICA V

NUCLEAR REGULATORY COMMISSION

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BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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)

Docket 50-344 PORTLAND GENERAL ELECTRIC COMPANY,

)

et al

)

(Control Building Proceeding)

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(Trojan Nuclear Plant)

)

CERTIFICATE OF SERVICE I hereby certify that on February 7, 1980, Licensee's letter and Motion dated February 7, 1980 for Summary Disposition of Specified Conten* ions with attached arguments and documentation have been served upon the persons listed below by depositing copies thereof in the United States mail with proper postage affixed for first class mail.

Marshall E. Miller, Esq., Chairman Atomic Safety and Licensing Appeal Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Washington, D. C.

20555 Dr. Kenneth A. McCollom, Dean Docketing and Service Section (3)

Division of Engineering, Office of the Secretary Architecture and Technology U. S. Nuclear Regulatory Commission Oklahoma State University Washington, D. C.

20555 Stillwater, Oklahoma 74074 Joseph R. Gray, Esq.

Dr. Hugh C. Paxton Counsel for hTC Staff 1229 - 41st Street U. S. Nuclear Regulatory Commission Los Alamos, New Mexico 87544 Washington, D. C.

20555 Atomic Safety and Licensing Board Lowenstein, Newman, Reis, Axelrad & Toll Panel 1025 Connecticut Ave., N. W.

U. S. Nuclear Regulatory Commission Suite 1214 Washington, D. C.

20555 Washington, D. C.

20036 u~-_

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CERTIFICATE OF SERVICE Frank W. Ostrander, Jr., Esq.

Mr. David B. McCoy Richard M. Sandvik, Esq.

348 Hussey Lane Assistant Attorney General Grants Pass, Oregon 97526 State of Oregon Department of Justice Ms. C. Gail Parson 500 Pacific Building P. O. Box 2992 520 S. W. Yamhill Kodiak, Alaska 99615 Portland, Oregon 97204 Mr. Eugene Rosolie William Kinsey, Esq.

Coalition for Safe Power Bonneville Power Administration 215 S. E. 9th Avenue P. O. Box 3621 Portland, Oregon 97214 Portland, Oregon 97208 Columbia County Courthouse Ms. Nina Bell Law Library 728 S. E. 26th Avenue Circuit Court Room Portland, Oregon 97214 St. Helens, Oregon 97051 Mr. John A. Kullberg Route 1, Box 250Q Sauvie Island, Oregon 97231 f

Ronald W. Jo ison Assistant Gene Counsel Portland General Electric Company Dated: February 7,1980 sa7A21