ML20040H285
| ML20040H285 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/12/1982 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18023A006 | List: |
| References | |
| NUDOCS 8202180040 | |
| Download: ML20040H285 (6) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of TEXAS UTILITIES GENERATING COMPANY, Docket Nos. 50-445
_ET _AL.
50-446 (Comanche Peak Steam Electric
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Station, Units 1 and 2)
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AFFIDAVIT OF JAMES E. KNIGHT Q1. By whom are you employed, and what is the nature of the work you perform?
A1.
I am an Electrical Engineer, and am employed as a Section Leader of the Electrical Section, Power Systems Branch, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission. As Section Leader I am responsible for supervising the review of electrical systems of nuclear reactors in construction permit and operating license proceedings. A statement of my professional qualifications is attached to this affidavit.
Q2. What is the nature of your responsibilities you have regarding the Comanche Peak Steam Electric Station ("CPSES")?
A2. The Staff review of Section 8 of the CPSES Final Safety Analysis Report ("FSAR") was performed in the Electrical Section of the Power Systems Branch.
8202190040 920212 i-PDR ADOCK 05000445 0
. Q3. Would you describe the scope of the subject matter addressed in your affidavit?
A3.
I will address Contention 2, which alleges:
One or more reports used in the construction of computer codes for the CPSES/FSAR have not
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been suitably verified and formally accepted; thus conclusions based on these computer codes are invalid.
In particular, I have been asked to describe the subject matter of Report 14, and to state whether or not this report describes, constructs and presents verification for any computer codes.
Q4. What is the subject matter of Report 14?
A4. Report 14, WCAP-8424, "An Evaluation of Loss of Flow Accidents Caused by Power System Frequency Transients in Westinghouse Pressurized Water Reactors, Revision 1" (June 1975), was sub-mitted by Westinghouse Electric Corporation (Westinghouse).
This report addresses coolant flow transients caused by elec-
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trical system frequency disturbances. Report 14 develops a maximum permissible credible decay rate for a utility grid.
The Applicants referenced this report in Section 15.3 of the FSAR for CPSES.
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. Q5. 'Does Report 14 describe, construct and provide verification for any computer codes?
A5. No.
James ET K t'
Subscribed and sworn to before me,
' this p/4 day of February,1982.
W A1LL
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( Notary /Publy
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/ /f J M My Commission expires:
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PROFESSIONAL QUALIFICATIONS OF JAMES E. KNIGHT I am the Section Leader of the Electrical Section in the Power Systems Branch, Division of Systems Integration, Office of Nuclear Reactor Regula-tion, U.S. Nuclear Regulatory Commission.
I supervise the technical staff of the Electrical Section, Power Systems Branch. This section is responsible for reviewing and evaluating
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the safety-related electric power systems described in Safety Analysis Reports, Topical Reports and other data submitted for the licensing of nuclear power plants or in support of license amendment application to assure public health and safety; for resolution of related technical issues, licensing problems and operating reactor problems; and for accomplishment of other functions and duties performed by the section.
I provide expert technical assistance and authorative advice relating to the safety-related electric power systems aspects of nuclear power plants.
I received a Bachelor of Science degree with honors in Electrical Engineering from Lawrence Institute of Technology in 1967. Additional graduate studies were subsequently performed at Wayne State University.
Other educational background includes:
1.
Air Force electronics school,12 months; 2.
Air Force instructor training school, 3 months; 3.
The Rational Manager (Kepner-Tregoe Course) one week 1973; 4.
Nuclear engineering course covering Boiling and Pressurized Water Reactors - sponsored by Detroit Edison (6 months) 1974; 5.
Fire Protection for Nuclear Power Plants - NRC sponsored (2 weeks) 1977; 6.
Boiling Water Reactor Simulator school - NRC sponsored (2 weeks) 1978; 7.
Pressurized Water Reactor Simulator school - NRC sponsored (2 weeks) 1979; 8.
Government Management Seminar II (Kepner-Tregoe Problem Analysis-Division Analysis - Potential Problem Analyses) I week 1980.
I am a registered professional engineer of the State of Michigan.
I have been certified since October 1,1970.
From 1960 to 1967 I was employed by Atomic Power Development Associates Incorporated as an instrumentation and controls technician at the Fermi-I Plant and later as a test facility supervisor responsi-bile for design, installation, maintenance and calibration of electrical, and instrumentation and control equipment for special process loops and test rigs related to the Fenni I fast breeder reactor and the Government's fast breeder program.
From 1967 to 1973 I was employed as a senior electrical engineer for Atomic Power Development Associates Incorporated (APDA) respcnsible for electrical power, and instrumentation and control designs and modifications
' to the Enrico Fermi I power plant, the development of electrical testing procedures, analysis of test results for the Fermi I emergency power systems, and the development of specialized tools and instrumentation for liquid metal cooled reactors.
In addition, I was deeply involved in Liquid Metal Fast Breeder Reactor program for development of instrumentation for liquid metals.
I acted as an (APDA) consultant to the Detroit Edison Company for electrical systems on the Fermi II BWR.
I was a principal instrumentation and control contributer to a joint APDA, Detroit Edison and Central Research Institute of Electric Power Industry of Japan " Conceptual Design Study of a 350 MWE Demonstration Fast Breeder Reactor." I was a principal investi-gator ir. acoustic leak detection studies for nuclear steam supply systems which resulted in the following publications:
1.
Feasibility Studies for An Acoustic Leak Detection System for Nuclear Steam Supply Systems; J.E. Knight, C.C. Scott.
2.
The Development and Design of Acoustic Leak Detection Systems for Millstone-1 and Fenni-2; A.E. Klickman, J.E. Knight.
3.
Background Noise for Acoustic Emission in a Boiling Water and Pressurized Water Nuclear Power Reactor; S.P. Yink, J.E. Knight, C.C. Scott.
From 1973 to 1975 I was employed by the Detroit Edison Company as a senior electrical engineer, acting as system engineer in the project management office of the Enrico Fenni II Boiling Water Reactor. As a system engineer I was responsible for management of the design of instru-mentation and control systems for safety systems and balance-of-plant systems from concept to final design.
Responsibilities included design c
review and approval, resolution of safety and technical problems, and the development of the safety analysis report on instrumentation and control.
. From 1975 to present I have been employed by the Nuclear Regulatory Commission as a Reactor Engineer (Instrumentation) from January 1975 to January 1976 in the Electrical and Instrumentation and Control Systems Branch, Division of Technical Review; from January 1976 to September 2,1979 as an Engineering Systems Analyst and Senior Engineering Systems Analyst in the Division of Operating Reactors, from September 2,1979 to March 9, 1980 as Senior Electrical Engineer in the Systematic Evaluation Program Branch, from March 9, 1980 to May, 1981 as Principal Electrical Engineer in the Operating Experience Evaluation Branch, Division of Safety Technology, from May 1981 to November 1981 as Principal Reactor Engineer in the Instru-mentation and Control Systems Branch, Division of Systems Integration, and from November 1981 to the present as Section Leader of the Electrical Section Power Systems Branch, Division of Systems Integration.
In these capacities, I have been responsible for numerous safety reviews on boiling
' and pressurized water reactors including activities as a lead reviewer for systems and electrical areas in the fire protection reviews of fifteen operating reactors subsequent to the Browns Ferry fire.
I have also acted as an expert witness and provided written and verbal testimony for the hearings on the Trojan control building problem and on the Allens Creek Scram Discharge Volume contention.
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