ML19296D482
| ML19296D482 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/27/1980 |
| From: | Clemenson F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19296D476 | List: |
| References | |
| NUDOCS 8003040668 | |
| Download: ML19296D482 (7) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC 5AFETY AND TICENSING BOARD In the Matter of
)
)
Docket No. 50-344 PORTLAND GENERAL ELECTRIC COMPANY, ET AL. )
(Control Buildiny
)
(Trojan Nuclear Plant)
)
AFFIDAVIT OF FRED CLEMENSON ON PGE MOTION FOR SU!O!ARY DISPOSITION WITH REGARD TO CFSP CONTENTION 17 STATE OF MARYLAND
)SS COUNTY OF MONTGOMERY)
I, Fred Clemenson, being duly sworn, depose and state:
1.
I am a Senior Systems Analyst, Plant Systems Branch, Division of Operating Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
2.
I have prepared the Statement of Professional Qualifications attached hereto and, if called upon, would testify as set forth therein.
3.
I am responsible for that portion of the NRC Staff's review of the proposed Trojan Control Building modifications related to the effect of the modification work on operator actions arising from construction-generated noise which could potentially interfere with communications between Control Room operators or with operators' hearing Control Room audible annunciators.
In this regard, I am responsible for addressing CFSP Contention 17 which states, 17.
Performance of modification work will hamper the ability of plant operators to respond to any emer-gency properly and thus poses an undue risk to the public health and safety.
80mo40 66 9
. 4.
I have reviewed in detail the proposed modification work which could generate noise that could potentially interfere with communications between Control Room operators or with operators' hearing Control Room audible annunciators.
5.
I have reviewed the Affidavits of Richard C. Anderson and C. Paul Yundt submitted in support of the Licensee's motion with regard to CFSP Con-tention 17.
6.
Based on my review and eraluation of the proposed modification sark and on the steps that will be taken to assure that construction noise will be minimized, I believe that the noise from such modification work will adversly affect operators' communication or the ability of operators not to hear annunciators in the Control Room.
7.
Based on my review described in paragraphs 4 and 5, above, I concur in and agrc.e with the statements set forth in paragraph 11 of the Richard C. Anderson Affidavit and paragraphs 5, 11 and 12 of the C. Paul Yundt Affidavit insofar as these paragraphs address the effects of noise.
8.
Based on my reviews described in paragraphs 4 and 5, above, I concur in and agree with the Licensee's statement of material facts set forth in Part II.H of the motion with regard to CFSP Contention 17.
sifeb Fred Clemes3on Subscribed and sworn to before me this 27th day of February,1980 Nota ([ Public My Commission Expires:
July 1, 1982
^
a Fred Clemenson PROFESSIONAL QUALIFICATIONS PLANT SYSTEMS BPANCH DIVISION OF OPERATING REACTORS I am employed as a Principal Engineering Systems Analyst in the Plant Systems Branch, Division of Operating Reactors. U.S. Nuclear Regulatory Comission. Washington,.D.C.
My duties consist of reviewing and evaluating the associated safety considerations on nuclear plant systems and associated engineering fields on power, test and research reactors.
In this capacity I am also responsible for coordinating the activities of other assigned branch members.
I am responsible for providing technical input to various documents including Safety Evaluations, technical positions for Cornission criteria as well as industry standards which have been assigned to the Branch.
After having served three years in the Navy (1942-1945) as an electronics technician, I attended University of Washington, Seattle, Washington and received a B.S. degree in Mechnical Engineering in 1948.
Whereupon I was employed as a instructor by the Mechanical Engineering Department of Oregon State College, Corvallis, Onegon, 1949-1950 where I taught courses in Statics, Dynamics, Elements of Mechanisms, Strength of Materials and Machine Design.
In September of 1950 I joined the General Electric Company's Reactor Design Division in Richland, Washington as a design engineer.
From that time to the present, my professional experience has been in the field of nuclear engineering.
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I have been a licensed professionel engineer in nuclear engineering from the State of California since March 1977, certificate number 1166.
At the General Electric Company I designed an automatic shutdown mechanism and a remotely operated handling system for radioactive materials.
From November 1951 to May 1956 I was employed by American Machine and Foundry Co., (AMF) New York, New York. There I assisted in activities related to the design and development of a wide variety of specialized mechanical equipment for the production reactors at Savannah River Project, and AMF's line of swiming pool type research reactors.
During this time, I served as a development and testing engineer for the prototype and production models of the control and shutdown mechanisms for the Savannah River production reactors.
Following this I served as the senior company representative, field engineer and consultant to E.I. DuPont de Nemours and Company during the installation, checkout'and acceptance tesM of the control, shutdown and refueling equipment designed by American Machine and Foundry Company on all five production reactors. Following this, I directed the design, development, asserbly and testing of a versatile research reactor control rod drive mechanism and other accessories.
From May 1956 to June 1958 I was employed by Combustion Engineering Inc., Windsor, Conn. as a Nuclear Engineer III. During this time. I served as <the mechanical core design group leader where I directed the design of refueling equipment, fuel elements and supporting structure for a submarine reactor. Patent applications were applied for on two
rethods.I developed to support the fuel elements.
From July 1958 to June 1961, I was employed as a Staff Engineer by General Nuclear Engineering Corporation Duneden Florida.
I was responsible for the conceptual and detailed design of two prototype control rod drive mechanisns for a low enriched, gas-cooled nuclear power reactor, as well as a test stand to test a high temperature, high pressure gas manifold assen61y. A patent application was submitted on the method I developed to decelerate a control rod.
From September 1961 to October 1963. I was employed by the Atomics Division, Nuclear Space Group of American Machine and Foundry Company, Greenwich, Conn., where I developed a remote handling system used in the maintenance and disassen61y of the radioactive Nerva engine as well as assisting in other nuclear space proposals.
From October 1963 to April 1966. I was employed as a Senior Engineering Specialist by the Nuclear Division of Martin Marietta Company, Inc.
During this tine, I was responsible for the design and development of remotely operated handling equipment required in processing highly radioactive heat sources, the nanufacturing tooling required in the manufacture of thermo-electric devices, and the manufacturing tooling utilized for the fabrication of the fuel elements and control rods for the MH-IA, a floating nuclear. power plant built by the Department of the Amy.
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From May 1966 to the present I have been employed by the U.S.
Atomic Energy Comission and U.S. Nuclear Regulatory Conr.ission.
During the first two years I was in the Division of Reactor Standards where I worked on the development of standards and assisted the Division of Reactor of Licensing on a number of projects. For the next three years I was a project leader in one of the boiling water reactor project branches in the Division of Reactor Licensing.
In addition to working on a number of special technical assignments I participated in the review of the Southwest Experimental Fast Oxide Reactor (SEFOR) and the Enrico Fertni Atomic Power Plant Unit 2, a boiling water reactor.
From April 1972 to December 1975 I was assigned as a Senior Systems Engineer to the Auxiliary and Power Conversion Systems Branch of Division of Technical Review.
I was responsible for the review of the design, development and operation of auxiliary and power conversion systems of BWRs PWRs and HTGRs.
I developed generic positions on specific NRC concerns such as Ultimate Heat Sinks Fuel Cask Handling. Tornado Missiles Turbine Missiles and Fim Extinguishants.
I developed Standard Review Plans and participated in the development of industry standards on Safety Related Yalves and Emergency Onsite Diesel Generator Fuel Oils Storage and Supply Systems.
From December 1975 to the present I've been a member of the Plant Systems Branch, Division of Operating lieactors. My duties in this branch consist of safety reviews and evaluation of systems design and
- operation of nuclear power, test and research reactors. As required I prepare safety evaluations and make presentations to the Advisory Corrnittee on Reactor Safeguards. I have participated in the developtrent of industry standards Regulatory Guides, and NUREG documents relating to safety relief valves, emergency onsite diesel generators heavy load handling equipment and reactivity control system requirements and modifications.
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