ML19274D959
| ML19274D959 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/15/1979 |
| From: | Wessman G GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Gammill W Office of Nuclear Reactor Regulation |
| References | |
| FOIA-81-127 NUDOCS 7902270292 | |
| Download: ML19274D959 (3) | |
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g.,wy,-,.ir.....,n..,w GENERAL ATOMIC COMPANY PO BOX 81608 SAN DIEGO. CALIFORNIA 92138 (714) 455-3000 February 15, 1979 Mr. William Gamill Assistant Director for Advanced Reactors Division of Project Management U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Gammill:
Enclosed are fifty (50) copies of General Atomic Company's response to your Additional Information Request on H-451 graphite of February 5, 1979. We trust that this response, in conjunction with our previous respenses to your requests for additional information, will provide you with sufficient information to complete your review by your comnitted date of March 31, 1979.
Sincerely, A&nw G. L. Wessman, Director Plant Licensing Division GLW:mk 7 9 0 2 2 7 0 2 9a
STATE OF CALIFORNIA ss.
COUNTY OF SAN DIEGO )
After being duly sworn, the person known to me to Le G. L. Wessman of General Atomic Company, signed the within document this 16* day of February 1979.
WITNESS my hand and official seal.
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Notary Public
RESPONSE TO NRC QUESTION 130.2(b) ON H-451 GRAPHITE QUESTION 130.2(b)
In your response to 130.(b), you indicated that the seismic analysis of FSV H-327 reactor internals was conducted as a dynamic analysis, treating the core as a monolithic beam.
Since the reactor core is basically a three-dimensional structure and can be subjected to multi-directional earth-quakes, provide a discussion on the validity of using such a simplified mathematical model and procedure of analysis.
The discussion should be based on the state-of-the-art infomation available on the subject matter.
RESPONS E The seismic analysis of the Fort St. Vrain H-327 reactor internals has been accepted by the NRC (AEC) as a satisfactory basis for determining the acceptability of the core mechanical design. No evidence is available to indicate that use of more complex mathematical models and analysis pro-cedures would obtain inadequate margins for the protection of public health and safety.
Furthemore, none of the state-of-the-art information and procedures referred to have been validated, approved by NRC, or accepted by NRC for detemining core seismic safety margins on the Fort St. Vrain project. Accordingly, their use would not be appropriate.