ML19340D330
| ML19340D330 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 12/18/1980 |
| From: | Moon C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340D319 | List: |
| References | |
| NUDOCS 8012300283 | |
| Download: ML19340D330 (3) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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HOUSTON LIGHTING & POWER COMPANY Docket No. 50-466 l
(Allens Creek Nuclear Generating
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Station, Unit 1)
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NRC STAFF SUPPLEMENTAL TESTIMONY OF CALVIN W. MOON IN RESPONSE TO BOARD QUESTION 7 ON ON-SITE TRANSPORTATION ACCIDENT Q.
Will the witness please state his name, place of employment, and duties he performs.
A.
My name is Calvin W. Moon.
I am a senior licensing project manager, Licensing Branch No.1, Division of Licensing, Office of Nuclear Reactor Regulation, Nuclear Regulatory Conmission. Since July,1975 I have been assigned to the Allens Creek construction permit stage of the health and safety review. Since April, 1980 my Allens Creek assignment has been broadened to include project management of environmental aspects of the review.
Q.
Is a statement of educational and professional qualifications attached to this testimony?
A.
Yes.
Q.
What is the purpose of your testimony?
A._
The purpose of _ this testimony is to respond to the following Board question as it relates to Allens Creek:
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n Is there an opportunity for the permissible site boundary radiation level to be exceeded by virtue of a gap in NRC and/or EPA regulations, whereby an on-site transportation accident gives rise to a radiation field which, when added to the ambient radiation level from normal plant operation (in-cluding radiation from stored spent fuel), might then result in a higher than permissible site boundary radiation level?. If not, why not? If so, does this constitute an oversight in the Staff's FES analysis?
Q.
Has the staff postulated and analyzed transportation accidents on the proposed Allens Creek site?
A.
No. The staff's review has not identified a concern that such an accident with significant radiological consequences is likely enough to warrant an accident analysis.
Q.
Why is this so?
A.
In part, this is because of the, rigorous design criteria for~ shipping containers which are sufficient to permit transportation over public highways. Also, the staff has not perceived that potential initiating events are likely enough to be of concern.
Q.
If such an accident were identified for some site and analyzed could the resulting radiation fields cause permissible site boundary radiation levels to be exceeded?
A.
No. The strdf would view such an event as facility or site accident and consider _ Part 100 guidelines, or lower guidelines depending on the probability of occurrence, as being applicable to the determination of the acceptability of the consequences.
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CALVIN W. MOON PROFESSIONAL QUALIFICATIONS LICENSING BRANCH NO. 1 DIVISION OF LICENSING I am a Senior Project Manager in Licensing Branch No.1 Division of Licensing, U. S. Nuclear Regulatory Commission.
In my present position, I have overall responsibility for conducting the safety and environmental reviews of power reactor license applications assigned to me. This includes the responsibility for planning and coordinating the efforts of other tech-nical personnel involved in the review.
I hold a Bachelor of Science degree in Mechanical Engineering from Iowa State University and a Master of Science degree from Stanford University.
I am a registered professional engineer in the State of Iowa.
I have a total of 29 years of professional experience. For three years I was employed by the University of California at the Los Alamos Scientific Laboratory with responsibilities for the design and development of mechanical systems.
For fourteen years I was employed by private industry in various staff and supervisory enginee. ring positions working on the design and
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development of gas cooled reactors for application to military propulsion, marine prop,ulsion, space propulsion and space auxiliary power systems.
In 1968. I accepted a position as Reactor Engineer with the Regulatory Staff of the Atomic Energy Commission.
In this capacity, I participated in
'the development.of reactor safety criteria..In my present position I have participated in the safety reviews of several power reactors by the Atomic Energy Commission and the Nuclear Regulatcry Commission.
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