ML19312D781
| ML19312D781 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/17/1980 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312D762 | List: |
| References | |
| NUDOCS 8003250326 | |
| Download: ML19312D781 (7) | |
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9 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING E0ARD In the Matter of-
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PORTLAND GENERAL ELECTRIC
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Docket No. 50-344 COMPANY, ET AL.
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(Control Building)
(Trojan Nuclear Plant)
NRC STAFF TESTIMONY OF CHARLES M. TRAMMELL, III IDENTIFYING STAFF PERSONNEL WHO PREPARED THE SAFETY EVALUATION REPORT AND RESPONDING TO LICENSING BOARD QUESTION ON PROPOSED LICENSE CONDITION Q.1 Please state your name and position with the NRC.
A.1 My name 'is Charles M. Trammell, III.
I am a Senior Project Manager, Division of Operating Reactors, Office of Nuclear Reactor Regulation.
Q.2 Have you prepared a statement of your professional qualifications?
A.2 Yes. A copy of my statement of qualifications is attached to this testimony.
Q.3
'What are your responsibilities with regard to the NRC Staff's review of the proposed modifications to the Trojan Control Building?
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-A.3 I am the NRC Staff's project manager for the Trojan Nuclear Plant.
In this capacity, I am responsible for the overall coordination of all aspects of the Staff's review of the proposed modifications and for adninistration of license changes which may be required as a result of the proposed modifications.
In addition, I am respon-sible for specific aspects of the review itself.
Q.4 What is the purpose of this testimony?
A.4 The purpose of this testimony is to identify the authors of-the NRC Staff's Safety Evaluation Report (SER) relating to the design modifications to the Trojan Control Building dated February 14, 1980, and errata dated February 15, 1980 and to respond to a Licensing Board question at the Prehearing Conference on March 11, 1980 as to the Staff's proposal to impose a licensee response to interrogatories as a condition on performance of the modifications.
Q.5 Identify those NRC Staff personnel who prepared the SER sections that the Staff plans to introduce into evidence and indicate what sections of the SER each prepared.
A.5
- The authors are:
Charles M. Trammell Kenneth S. Herring
.. 'Drme Persinko Fred Clenenson James E. Knight Walter _Pasedag
.'The following table identifies the authors of the specific SER sections:
SER Section Author (s) 1.0 Trammell 2.0 Trammell 3.0 Herring 4.0 Trammell 4.1 thru 4.5 Knight 4.6 thru 4.8 Clemenson 4.10, 4.11 and 4.13 Herring and Persinko 4.14 Trammell 5.0 thru 5.6 Herring and Persinko 5.7 (first para.)
Herring-
.5.7-(remainder)
Trammell 5.8 Knight 5.9 Pasedag 5.10, 5.11 Trammell 5.12.(firstpara.)
. Herring r
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5.12 (remainder)
Knight 5.13 Knight 6.0 thru 6.2 Trammell (except for 6.1.2) 6.1.2 Herring 7.0 Trammell 9.0 Trammell Q.6 At the prehearing conference on March 11, 1980, the Licensing Board inquired as to a license condition proposed by the Staff for
'the modifications.
Specifically, why has the NRC Staff included
" Licensee's Responses to Interrogatories Dated August 27, 1979 From the State'of Oregon" (dated September 17,1979) in its rectm-mended license condition (SER para. 6.2.2)?
A.6 This interrogatory response, which is 22 pages in length, contains information regarding the testing of place handling equipment (overhead cranes, chains, slings, etc.), operator qualification and supervision, and information regarding the welds to join the plates that were relied upon by NRC Staff in concluding that these aspects of the proposed modification program are acceptable.
Responses by PGE to all other interrogatories (from anyone) were either included in other PGE letters which 'are contained in the recommended' license condition.or not relied upon by the NRC Staff.
- '- J The NRC Staff would have asked PGE to supply this information by letter had it not been furnished in its response to these Oregon interrogatories.
The' license condition'would require that the proposed modifica-tions be as described in and be performed in accordance with the analyses, evaluations, procedures and commitments set forth in PGE-1020, the referenced letters from the Licensee to the NRC, and the referenced Licensee responses to interrogatories of the State of Oregon. While these documentary materials are large in volume, they constitute a complete description of the proposed modifica-tions, the analyses supporting them, and the procedures for imple-menting them.
Their inclusion as e license condition on how the modifications are to be performed is appropriate to assure that the modifications will be performed in accordance with the licensee's commitments.
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CHARLES M. TRAMMELL, III
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DIVISION OF OPERATING REACTORS U. S. NUCLEAR REGULATORY COMMISSION PROFESSIONAL QUALIFICATIONS I ~am a senior project manager in the Division of Operating Reactors, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission.
As such, I am responsible for managing and participating in the safety and
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- environmental reviews associated with licensing actions regarding the
. design and operation of assign'ed operating power and research reactors.
This includes planning and coordinating the efforts of other Comission personnel involved in the reviews.
I have a Bachelor of Arts degree in mathematics from Brown University, and one year of graduate studies in mathematics at Rennselaer Polytechnic Institute where I worked as a graduate assistant.
From November 1962 until February 1964, I attended U. S. Naval Destroyer School at Newport, Rhode Island, and was subsequently assigned as Engineer Officer of USS Farragut (DLG-6),~ where I was ' responsible for all aspects of propulsion engineering and related auxiliary equipment.
My experience in the nuclear field began in 1964, when I entered the Navy Nuclear' Power Program.
I' attended a one-year course in naval nuclear
. power, and was subsequently selected for a staff position at the Navy's prototype nuclear. power plant (DlG) at Uest Milton, New York. There I f
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Professional Qualifications Charles M. Tramell, III was in charge of a shift crew which operated the plant for training and engineering testing.
I was responsDie for the training and nuclear qualification cf esdgned officers and enlisted men.
From 1967 uatil 1974,'I was employed by Public Service Electric and Gas Company where I was responsible initially for the Preliminary Safety Analysts Report for the Salem Nuclear Generating Station. Later, I attended the Westinghouse Reactor Operator Training Program (10 months) which led to certification of equivalency as Reactor Operator thereby establishing eligibility for a " cold" senior reactor operator license at Salem.
In 1969, I was promoted to Reactor Engineer at
.e Salem station where I was responsible for developing physics and core performance tests and fuel handling procedures while the plant was under construction.
Training at Westinghouse Nuclear Operations Division and startup testing experience at Indian Point, Ginna, H. B. Robinson and Surry stations led to qualification as nuclear engineer in accordance with ANSI Standard
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In September 1973, I was promoted to the position of Quality Assurance Engineer at the Salem site, where I was responsible for developing the quality. assurance program for the operational phase of the Salem station..
I have held my position with the.Comission since September 1974.
I have' participated in numerous safety and environmental reviews of all types
. of comercial nuclear power plants, including testifying as an expert witness in the Trojan Spent Fuel Pool Expansion Hearing.
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