ML19331B536
| ML19331B536 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/08/1980 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331B489 | List: |
| References | |
| ALAB-598, ISSUANCES-OL, NUDOCS 8008120401 | |
| Download: ML19331B536 (6) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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PACIFIC GAS AND ELECTRIC COMPANY
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Docket Nos. 50-275 0.L.
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50-323 0.L.
(Diablo Canyon Nuclear Power Plant
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Unit Nos. 1 and 2)
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TESTIMONY OF JAMES P. V.NIGitT Q.
By whom are you employed.
A.
I am employed by the U.S. Nuclear Regulatary Commission.
I am the Assistant Director for Components and Structures Engineering.
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directly to the Director, Division of Engineering.
Q.
Describe the nature of your work with respect to the Diablo Canyon operating license proceeding.
A.
I am generally responsible for the overall direction of the structures engineering analysis of the Diablo Canyon nuclear power plant.
It is within my respons ;1ty to assure that the Diablo Canyon facility meets the Commission's seismic and geological siting criteria for nuclear power plants as set forth in 10 C.F.R. Part 100, Appendix A.
In addition I also testified at the Atomic Safety and Licensing Board hearings with respect to particular technical issues raised by Joint 8008120
D Intervenors in the Diablo Canyon poroceeding. My direct written testi-mony is found in the record following Tr. 8697. My oral testimony begins at Tr. 8698.
Q.
Would you detail your professional qualifications?
A.
A copy of my professional qualifications is attached. My professional qualifications were also admitted as evidence in this proceeding following Tr. 8697.
Q.
Would you describe your participation in development of testimony in response to the Atomic Safety and Licensing Appeal Board's (Appeal Board) questions raised in the Appeal Board's Appendix to Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2),ALAB-598,SlipOp.(June 24, 1980).
A.
Generally, I was responsible for coordinating the efforts of Dr. Nathan M. Newmark, Dr. Pao-Tsin Kuo, Dr. Robert L. Rothman, and Mr. Richard M.
McMullen in developing their responses to the specific Appeal Board questions.
I participated directly in the working sessions during which responses to the questions were developed. During the develop-ment of this testimony I presented my technical opinions based on my experience and expertise on the questions raised by the Appeal Board.
In addition, my testimony provides the response to Appeal Board Question 8.
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Appeal Board Question No. 8 states:
We have received preliminary reports of the effect of IV-79 on the El Centro Steam Power Station.
(Board Notification December 17, 1979, Levin and Martore Observations; Rothman -
Kuo Affidavit, p.12).
In many respects, the structures and systems of that facility resemble those of the Diablo Canyon plant. Their response to a severe, well instrumented seismic event can be analysed to help confirm or refute analytical techniques and assumptions used in the Diablo Canyon seismic analysis. The parties should prepare and submit such an analysis.
Has the Staff or its consultants begun such an analysis?
A.
In March 1980, the Staff initiated a contract with Lawrence Livermore Laboratory to perform on an expedited basis a dynamic analysis of the El Centro Steam Generating Station which was subjected to the motions recorded at that Station during the Imperial Valley Earthquake. The study has not been completed, although early draft of the Livermore study has been received and after preliminary review is under revision.
I don't expect to have a fully evaluated analysis of the El Centro Station unt11 sometime in October of this year. Attached is a copy of the draft report dated June 24, 1980.
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o Professional Qualifications James P. Knight U. S. Nuclear Regulatory Comission Division of Systems Safety l
I am Assistant Director for Engineering responsible for the review and evaluation of design criteria for structures systems, mechanical components and materials, the dynamic analyses and testing of safety related structures, systems and components and the criteria for protection against the dynamic effects associated with natural environmental loads and postulated failures of fluid systems for nuclear facilities.
I received a B.S. Degree in Mechanical Engineering from Northeastern Univer-sity in 1957. Since that time, I have comoleted the equivalent of accrox-imately 35 semester hours at the graduate level in structural dynamics, nuclear engineering and fracture mechanics at the Massachusetts Institute of Technology, t.ehigh University and the George Washington University.
l From June 1957 to September 1059 I served as a comissioned officer with the U. S. Army Corps of Engineers.
From September 1959 to October 1963 I was employed by the Special Products Division of the American Machine & Foundry Company, Alexandria, Virginia.
In the latter period of this experience, I had full responsibilicy for design concept, material selection and analytical review for critical comoonents of high speed spin test equi; ment, re-entry simulation systems anc soin stabili:stion test systems for manned and un-canned scacecraft.
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In Octo:er 1963 I joined the Reactor Radiations Division at the National
, Bureau of Standards. During this period, I was responsible for the mecnanical and structural design, testing and certification of the NBSR core elements, c:ntml rod drive mechanisms and high level radiation handling equipnent; I was also fully resocnsible for the analytical review and excerimental certification of the NBSR reactor vessel and a variety of ex:erimental equipment to the requirements of the ASME Soiler and Pressure Yessel Code.
In early 1967, I was appointed Chief of the Engineering Services Section responsible for all mechanical and electrical engineering design services for both the NBSR facility and ex:erimental equi: ment development. Following receipt of the NBSR operating license, I was accointed Vice-Chaiman of the NBSR Hazards Cemittee responsible for review of the mechanical and structural hazards for all experiments proposed for insertion in the NBSR.
In Septacter 1968, I joined the U. 5. Atomic Energy Comission and have remained with this organizatien through the transition to the U. S. Nuclear Regulatory Ccmission. During this time, I have participated in the review and evaluation of over fifty c:nstruction permit and operating license applicaticns and participated in the review and planning activities for Government and industry sponsored programs such as the Heavy-Section Steel Technology Program, and develecment of the 331.7 Nuclear Power Piping Code and the ASME Nuclear Ccmcenent Code.
I have served as a meccer of werous indust:y code and standarts writing bcdies inclucing: the ASME Section III Subgrous on P essure Relief, the
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. ASME Section III Working Group for Design of. Valves, the AS4E Section III
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Working Group for Design of ?' sos. ANSI S16 Succomittee N - Steel Valves and ANSI 316 Subcommittee H - Valve Ocerability.
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