ML19224D189
| ML19224D189 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/01/1979 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907110057 | |
| Download: ML19224D189 (2) | |
Text
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JijN 011979 Docket No. STN 50-482 MEMORANDUM FOR: Olan D. Parr, Chief, Light Water Reactors Branch No. 3, DPM FROM:
Emanuel a. Licitra, Project Manager, Light Water Reactors Branch No. 3, DPM
SUBJECT:
TELECON WITH GLENN K0ESTEE, ET AL. REGARDING WOLF CREEK BASE MAT REVIEW On 5/29/79, I received a call from Glenn '.oester (KG&E) in which hu asked about the status of our review of the Wolf Creek base mat matter.
With Franz Schauer (SEB) on the line, we told him that we were in the process of forwarding to him a request for additional information.
In order to enable him to expedite his responses to our forthcoming request, he
. requested a telecon later that day with Bechtel and KG&E representatives to determine what additional information was needed to complete our review.
The subsequent telecon included Glenn Koester and Earl Creel (KG&E),
William Waugh (KG&E consultant), Joe Shideler (PC., Bernie fleyers and Paul Divjak (Bechtel), Karl Seyfrit (Region IV), h o.2 Schauer and Henry Lee (SEB) and myself.
In this telecon,5.e discussed all of the areas where we would need additional information to complete our review of the base mat. These areas are: (1) the basis for selecting cylinder remnants for certain analyses, (2) the efficacy of the Windsor probe tests, (3) a comparative soil-structure interaction analysis which includes a half-space lumped parameter representation, (4) the effects of a reduced concrete strength on certain design parameters, (5) the effects of soil properties on the soil-structure interactinn analysis, (6) consideration of base mat uplift in the reanalysis, (7) consideration of heavy equipment anchored to the base mat in the reanalysis, (8) consideration of maximum principal stresses in the reanalysis, (9) the thermal stresses resulting from thermal loads for specific conditions, and (10) verification information on computer codes used in the reanalysis.
Continued discussion of the areas dealing with the Bechtel reanalysis (last eight items) was held between the NRR representatives and Bechtel in the Bechtel Gaithersburg office later that afternoon because of hearing difficulties encountered with a poor telephone connection.
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7907110o57 330 M
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Olan D. Parr JUN 011979 A request for the above additional information was transmitted to the applicant the following day by letter dated 5/30/79.
During the telecon, we informed the applicant that, based on our evaluation of all of the test data submitted, we conclude that the cylinder test results are valid and that the correction factor for the cube compressive strength test results, to correlate with the cylinder strength test results, may be less than the 0.8 factor suggested by the applicant.
After we discussed the areas that required additional information, the applicant stated that it wouldimake every effort to provide the requested information within the next few days.
d tank Emanuel A. Licitra, Project Manager Light Water Reactors Branch No. 3 Division of Project Management
.cc:
R. Boyd D. Vassallo F. Schauer H. Lee G
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