ML19263F364
| ML19263F364 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/09/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-26, NUDOCS 8001280026 | |
| Download: ML19263F364 (2) | |
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DAIRYLAND POWER COOPERATIVE Ba Groue, Ohconan S4601 January 9,1980 In reply, please refer to LAC-6726 DOCKET NO. 50-409 Mr. James G. Keppler Regional Director U. S. Nuclear Regulatory Comission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 IE BULLETIN NO. 79-26
Reference:
(1) NRC Letter, Keppler to Linder, enclosing IE Bulletin No. 79-26, dated November 20, 1979.
Dear Mr. Keppler:
The subject IE Bulletin discussed a potential failure mode which has been observed in General Electric Company (GE) control blades which can cause a loss of boron poison material through cracks in the stainless steel tubing containing the B C.
The IE Bulletin also stated four specific items requiring 4
certain actions and reports from all BWR power reactor facilities with an oper-ating license. The findings as to Items (1) and (2) for the LACBWR are reported below.
Item (1): The operating history of the LACBWR has been reviewed and a record of.the current B10 depletion averaged over the upper one-fourth of the blade has been established for every control blade. This record will be maintained on a continuing basis.
Item (2): No control blade in the LACBWR is predicted to have greater than 34 percent BIO depletion averaged over the upper one-fourth of the blade by the next refueling outage. The control blade with the greatest BIO depletion (29.7%) averaged over the upper one-fourth of the blade is presently in a core location where it is completely withdrawn during operation and therefore is experiencing'no sig-nificant additional B10 depletion.
It is standard operating procedure at the LACBWR to rotate control blades that have exper-1enced considerable exposure to core positions where their further 1816 323 0 M kk 8001280 O 2 6
Mr. James G. Keppler, Reg. Dir.
LAC-6726 U. S. Nuclear Regulatory Comission January 9, 1980 exposure will be negligible and thus limit their exposure to values significantly below the 34% BIO depletion criteria of the subject IE Bulletin.
Item (2a): Since none of the control blades in the LACBWR have experienced I
or are expected to experience greater than 34% B O depletion averaged over the upper one-fourth of the blade for several years, no plans for replacement of control blades are being formulated at the LACBWR.
Item (2b): Since no control blade in the LACBWR will experience 34% BIO depletion averaged over the upper one-fourth of the blade for several years, no justification of continued operations is necessary.
Authorization for this response to be submitted beyond the reporting period was granted to Dr. Seymour Raffety by Mr. Ken Ridgway on January 3, 1980.
If you have any questions concerning this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE M
b Frank Linder, General Manager FL:SJR:af cc:
U. S. Nuclear Regulatory Comission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.
20555 1816 324. n..
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