ML19281A146
| ML19281A146 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/08/1979 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| Shared Package | |
| ML19281A147 | List: |
| References | |
| NUDOCS 7903060605 | |
| Download: ML19281A146 (2) | |
Text
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UNITED STATES k
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON O. C. 20555 s r< L fg FEB 'O S 1979 Docket No.
STN 50-482 Mr. Glenn L. Koester Vice President - Operations Kansas Gas & Electric Company 201 North Market Street Wichita, Kansas 67201
Dear Mr. Koester:
SUBJECT:
INVESTIGATIONS OF 90-DAY BASE MAT CYLINDER REMNANTS FOR WOLF CREEK In your letter of January 16, 1979, you provided a description of a program for additional testing to be performed on concrete remnants of the 90-day test cylinders for the Wolf Creek reactor build'ng base mat. The program was described in a letter, dated Jarsary 12, 1979 from your consultant, Mr. William R. Waugh to you, wh,ch was attached to your letter.
You indicated that work on the program would be deferred until you had heard from us.
On January 17, 1979, your consultant, Mr. Waugh, and representatives of SNUPPS and Bechtel called to provide us with a more detailed discussion of the program outlined in the January 12, 1979 letter.
Your representatives also discussed this program with the Region IV Office of Inspection and Enforcement on the same date.
In these discussions on January 17, 1979, we informed your representatives that our approval is not required to proceed with your plans for additional testing. This letter confirms ; hat understanding.
During the above discussions, we suggested that consideration be given to including in the test program additional remnants of other 90-day concrete cylinders whose tests results indicated strengths below 5000 psi.
We also suggested that, for comparative purposes, consideration be given to including remnants of 28-day concrete cylinders from those concrete batches where there was an apparent drop in strength between 28 days and 90 days. We understand that the test program will include additional remnants in response to the above suggestions.
We consider that the program outlined can provide a better under-standing regarding the quality of the concrete and whether there is any degradation of concrete strength.
However, we consider it 7 9 0 3 0 6 0 6 of
Mr. Glenn L. Koester FEB 0 S 1979 somewhat problematical whether the results will be useful in modi-fying the 90-day strengh data resulting from the original tests performed with the cylinders.
Therefore, we request that you provide an assessment of the concrete strength of the reactor building base mat based on the strength data obtained with the 90-day test cylinders.
If any test data are excluded in making this assessment, provide the basis for this exclusion.
Using the strength resulting from the above assessment, we also request that you evaluate the load carrying capacity of the base mat to determine if this calculated strength for the concrete will satisfy the design criteria specified in the Preliminary Safety Analysis Report.
We would appreciate hearing from you within ten days after receipt of this letter regarding the date by when you plan to respond to the above request.
If you have any questions regarding this request, please advise us.
Sincerely, er S. Bo
, Directcc Division cf Project Management Office of Nuclear Reactor Regulation
Enclosure:
Letter f rom Glenn Koester, dated 1/16/79 cc: See next page
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