ML20009E296

Transcript of R Cheng Testimony on Behalf of Applicant Re ASLB Question 10 (Drywell Pressure Testing).Prof Qualifications Encl

ML20009E296
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	07/20/1981
From:	Cheng R EBASCO SERVICES, INC., HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20009E295	List: ML20009E294 ML20009E296
References
NUDOCS 8107280016
Download: ML20009E296 (3)

Text

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1 R E C Elt' b U s' 2 JUL21 Mi UNITED STATES Or AMERICA NyCLEAR REGULATORY COICIISSION 3 0FFICE OF AP E di C 1

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,, ,,ng 3 BEFOR?tTHT -t ATOMIC SAFETY AND LICENSING BOARD 4

In the matter of )

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, HOUSTON LIGHTING & POWER COMPANY ) Docket No. 50-466 0

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(Allens Creek Nticlear Generating )

7 Station, Unit No. 1) )

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S 9 DIRECT TESTIMONY OF ROBERT C. CHENG ON BEHALF OF HOUSTON LIGHTING & PC'WER COMPANY ON BOARD 10 QUESTION 10 ON DRYWELL PRESSURE TESTING 11 Q. Please state your name, business position and 19

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professional qualifications.

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I. My name is Robert Cheng. My business address 7

is 160 Chubb Avenue, Lyndhulst, New Jersey. I am the 15 lead Containment Building E1gineer employed by Ebasco 16 Services, Inc. on the Allens Creek Project. The statement 17 of my background and qualifications is attached as 18 Attachment RCC-1 to this testimony.

19 Q. What is the purpose of this testimony?

20 A. This testimony is to address Board Question 10 21 which requests the Applicant to verify that the ACNGS 22 drywell will be tested at some pre-specified value in g e:< cess of design pressure.

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l 2 Q. Has the Applicant made any commitments regarding 3 drywell testing?

A. Yes. As stated in PSAR Section 3.8.3.7 the 4

. Allens Creek drywell will be tested at 34.5 psig. This o

, is eg.u.ivalent to 115% of (:esign pressure (30 psig) in 0

accorde- *iith NRC Reg. Guide 1.18 recommendations for 7

concrete containments. Moreover, if the Allens Creek 8

drywell is determined to be a prototype at the time o."

9 testing, additional measurements such as drywell wall 10 strains and deflections will be recorded in accordance 1

1 with the Staff's technical p asition on " Structural Proof 12 Test of BWR Mark III Containment Drywell," as presented 13 in Appendix H of Supplement 1 to the NRC Safety Evaluation 14 Report of ACNGS.

15 Q. What is your conclusion?

16 A. The Applicant has committed to test the ACNGS 17 drys; ell to 115% of design pressure.

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Attachment RCC-1 Robel- C. Cheng I received a BSCE from Taiwan Provincial Cheng ,

Kung University in 1963. I received a MS in Structural Engineering from the Virginia Polytechnic Institute in 1965.

I received a PhD in Engineering Mechanics from Pennsylvania State University in 1972.

I have been employed by Ebasco since 1966, except for the period 1968-1971 during which time I was an instructor in the Engineering Mechanics Department at Pennsylvania State University where I taught courses in statics, dynamics and strength of materials and performed research on biomechanics topics for the National Heart Institute. Prior to 1966, I was employed as a Structural Designer for one year by the Chemplant Designer where I performed wind analysis and design for steel structured frameworks and heavy machine supports. I was a research assistant at Virginia Polytechnic Institute for one year where I performed research work on reinforced concrete and taught courses on reinforced concrete.

I also worked part time for two years as an assistant engineer for the TaiAnn Construction Corporation where I assisted in the stress analysis of reinforced concrete and steel structures.

My first two years with Ebasco, I was a Senior Design Engineer with responsibility for the performance of analysis and design for the prestressed concrete structures of reactor buildings. I am now a principal engineer and I am responsible for development of various structural analyses and test programs on nuclear projects. I have supervised I the dynamic analysis of containme"t loads, evaluated seismic and other dynamic qualification programs for safety related equipment, developed the Field Coil Integrity Test and the composite material test program for the Tokamak Fusion Test Reactor, prepared design specifications and supervision of dynamic and static stress analyses for reactor shield buildings and dry well structures, served as a special consultant for a stress analysis for a finite model study for the construction ,

of reactor buildings, performed computer analysis and design for the internal structure of reactor buildings and performed computer analyses and design for reactor building foundations.

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