ML19253C404

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Forwards IE Bulletin 79-26, Boron Loss from BWR Control Blades. Response Required
ML19253C404
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 11/20/1979
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Linder F
DAIRYLAND POWER COOPERATIVE
References
NUDOCS 7912050372
Download: ML19253C404 (1)


Text

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NUCLEAR REGULATORY COMMISSION 3'

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ss GLEN ELLYN,ILLINOls 60137 Docket No. 50-409 Dairyland Power Cooperative y fl[j tj,

ATTN:

Mr. F. W. Linder General Manager 2615 East Avenue - South La Crosse, WI 54601 Gentlemen:

The enclos-d IE Bulletin No. 79-26 is forwarded to you for action. A written response is required.

If you desire additional information regarding this matter, please contact this office.

Sincerely,

, h~(b James G. Keppler Director

Enclosure:

IE Bulletin No. 79-26 cc w/ encl:

Mr. R. E. Shinshak, Plant Superintendent Central Files Director, NRR/DPM Director, h7R/ DOR PDR Local PDR NSIC TIC Anthony Roisman, Esq.,

Attorney 1504 170 7912050 37>

UNITED STATES SSINS:

6820 NUCLEAR REGULATORY COMMISSION Accession No.-

0FFICE OF INSPECTION AND ENFORCEMENT 7910250475 WASHINGTON, D.C.

20555 November 20, 1979 IE Bulletin No. 79-26 BORON LOSS FROM BWR CONTROL BLADES Description of Circumstances:

The General Electric Company (GE) has informed us of a failure mode for control blades which can cause a loss of boron poison material.

Hot cell examinations of both foreign and domestic blades have revealed cracks near the upper end of stainless steel tubing and loss of boron from the tubes.

The cracks and boron loss have so far been confined to locations in the poison tubes with ruore than 50 percent Boron-10 (B10) local depletion.

Observed crack sizes range from a ouarter to a half inch in length and frrm one to two mils in width.

GE has postulated that the cracking is due to stress corrosion induced by solidification of boron carbide (B C) particles and swelling of the compacted 4

B C as helium and lithium concentrations grow.

Once primary coolant penetrates 4

the cladding (i.e., the cracking has progressed through the cladding wall and the helium-lithium pressures are sufficient to open the crack), boron is leached out 10 of the tube at locations wi'.5 more than 50 percent B local depletion (local depletion is considered to oe twice the average depletion).

It was further found 10 with similar cracking but with less than 50 percent local depletion of B

, that leaching did not occur even though primary coolant had penetrated the cladding.

The cracking and boron loss shorten the design life of the control blade.

According to the GE criteria the end of design life is reached when the reactivity 10 worth of the blade is reduced by 10 percent, which corresponds to 42 percent B depletion averaged over the top quarter of

'le control blade.

Because of the 10 leaching mechanism, GE has reduced the the top quarter of the control blade f DUPLICATE DOCUMENT The safety significance of boron loss Entire document previously scram reactivity.

Although shutdown c entered into system under:

7h O

ANO 1504 171 No. of pages:

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