ML19253C419

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Forwards IE Bulletin 79-26, Boron Loss from BWR Control Blades. No Response Required
ML19253C419
Person / Time
Site: Point Beach  
Issue date: 11/20/1979
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Burstein S
WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 7912050414
Download: ML19253C419 (1)


Text

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f UNITED STATES y y,g j NUCLEAR REGULATORY COMMISSION

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REGION 111

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Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company r.

ATTN:

Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 Gentlemen:

The enclosed IE Bulletin No. 79-26 is forwarded to you for information.

No written response is required.

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

Sincerely, M-4s

,[tJamesG.Keppler U Director

Enclosure:

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

Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORB /hTR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore Citizens for Safe Energy 1502

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UNITED STATES SSINS:

6820 NUCLEAR REGULATORY COMMISSION Accession No.

OFFICE 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 failen 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 more than 50 percent Boron-10 (B10) local depletion.

Observed crack sizes range from a quarter to a half inch in length and from 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 with more than 50 percent B local depletion (local depletion is considered to be 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 thorten 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 the control blade.

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

Although shutdown ca entered into system under:

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1502 348 No. of pages: