ML19269D142

From kanterella
Jump to navigation Jump to search
Responds to 790208 Ltr Requesting Addl Work Be Performed Re Investigation of 90-day Base Mat Concrete Cylinder Remnants. Forwards List of Representative Groups of Concrete Remnants from 28-day Cylinder Breaks Sent to Portland Cement
ML19269D142
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 02/21/1979
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Boyd R
Office of Nuclear Reactor Regulation
References
NUDOCS 7902270378
Download: ML19269D142 (3)


Text

\

KANSAS GAS AND ELECTRIC COMPANY THE ELECTRoC COM,mNY GLENN L MOESTER vsC E PAESIDE N f-OPE ma' EON S February 21, 1979 Mr. Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C. 20555 Re: Docket No. STN 50-482 Subj: Investigations of 90-Day Base Mat Cylinder Remnants for Wolf Creek

Dear Mr. Ocyd:

I have your letter of February 8, 1979, in which you requested certain additional work should be performed in regard to the investigations of 90-day base mat concrete cylinder remnants at Wolf Creek. The following information outlines our response to your letter.

The work to be performed by Portland Cement Association (PCA) as described in our Consultant's (Mr. Waugh) letter of January 12, 1979, which was transmitted to Mr. Licitra on January 16, 1979, is nearing completion and a final report is due shortly. In addition to the cylinder remnants listed in Mr. Waugh's letter, cylinder remnants #6527, #6534, #6648 and

  1. 6683 were also tested, as suggested by NRC Region IV.

As suggested in your February 8,1979 letter, we are preparing to send to Portland Cement Association a representative group of concrete remnants from the 28-day cylinder breaks for testing. A listing of these remnants is included as an attaciuaent.

The tests indicated above, together with a broad based program directed by Mr. Waugh, are designed to investigate all factors which mould con-ceivably affect the 90-day compressive strength of the base mat concrete.

Results available to date indicate that the compressive strength is in excess of 5000 PSI.

The fifth par'. graph of your letter requests an assessment of the concrete strength of the reactor building base mat based on the strength data obtained with the 90-day test cylinders. You further requested that an evaluation be made of 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 ReporL. The above work is g 7902276373 \

201 N. Market - Wichita, Kansas - Mail Address: P. O. Box 208 / Wichita, Kansas 67201 - Telephs se: Area Code (316) 264-1111

Mr. Boyd February 21, 1979 already underway. In fact, Kansas Gas and Electric Company authorized our AE, Bechtel Power Corporation, to begin this work on January 8, 1979, in response to comments by NRC Staff in our meeting on January 4, 1979.

A final report is tentatively scheduled for May 28, 1979.

We believe this covers the requests as outlined in your February 8,1979 letter. If you have any furcher comments or questions, please advise me.

Sincerely yours,

, .p 3 f, ' JL&LUO d

GLK:bb Attach cc: KSyefrit, Region IV Attach

GIS :bb 2/15/79

. 28 DAY BASEMAT CYI,IfJDER REMtJAtJTS TO BE TESTED AT PCA Cylinder Daniel 28 Daniel 96 Petro /Chenical Ilumber Day Test (PSI) Day Avg. (PSI) Analysis 6411 4611 5330 6424 4270 4810

  • 6448 4620 5190 6483 4650 5050
  • 6484 4560 5050 6490 4190 4990
  • 6496 5110 6106 6513 4760 4770 6514 4580 4770 6531 5020 4730
  • 6543 5570 4050
  • 6561 5680 4530
  • 6580 5780 5150 6586 5200 4820
  • 6604 4850 4340 6640 4530 5490
  • 6651 5130 5090
  • 6664 SE40 5420 6700 4790 4830
  • 6706 4530 5570 6717 4990 4800
  • 6718 4320 4800
  • 6735 4190 4410
  • 6752 4460 4830
  • 6771 5410 4880
  • 6794 4860 4530
  • Petrographic / chemical analysis to specifically include the following tests:

(c) Cement content (b) Water / cement ratio (c) Level of hydration in UPC's (0 to 10) plus a description of hydration products (d) Evidence of reactivity (c) Aggregate distribution and geologic classification

( f) Air content by linear tra'rerse method ( ASTM C-457)

(g) Amount of aggregate dust Prepare written report set'ing out the res"its ot' the above testing including to the extent possible evaluation of remnants to include:

'(a) Type of break (b) Condition of ends, i.e., amount of curvature (c) Any observed anomalies of end caps