ML20002A934

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RO 80-15:on 801129,while Performing Periodic Type C Leak Tests on Retention Tank Pump Discharge Valve,Leak Flow Rates from Condensate Exceeded Tech Specs.Repairs & Adjustments to Valve Will Be Accomplished & Retest Performed
ML20002A934
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 12/01/1980
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-7257, RO-80-15, NUDOCS 8012090206
Download: ML20002A934 (2)


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Ti December 1, 1980 E?T W

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  • C In reply, please refer to LAC-7257 c:

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[j DOCKET NO. 50-409 i

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M'r. Jamek G.

Keppler Regional Director U.

S. Nuclear Regulatory Commissicn Directorate of Regulatory Operations Region III 799 "oosevelt Road Glea Ellyn, Illinois 60137

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 REPORTABLE OCCURRENCE NO. 80-15

Reference:

(1)

LACBWR Technical Specifications, Section 3. 9. 2. a. (3).

(2)

LACBWR Technical Specifications, Secticn 5. 2.1. 3. (b).

Dear Mr. Keppler:

In accordance with Reference 1, this is to inform you of abnormal degradation discovered in the primary reactor containment during periodic Type C surveillance leakage rate testing while in a shut-down condition.

As a result of conducting periodic Type C leak tests on the Retention Tank Pump Discharge Valve, the leak flow rates determined from the Condensate Valve exceeded the permissible leak flow rates as defined in Technical Specifications (Reference 2).

The test leakage rate was determined to be between 0.56 and 4.0 SCFH.

The Acceptance Criteria is 0.375 SCFH.*

The test was performed on November 29, 1980.

Prompt notification of test results to the U.

S.

Nuclear Regulatory Commission was accom-plished at 1645 on November 29, 1980, by R.

J.

Cota, LACBWR Duty Shift Supervisor.

  • Shall not exceed 1% of leakage rate L where L is 37.5 SCFH.

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0012000goQ Ib

s Mr. James G.fKeppler,. Regional _ Director LAC-7257 U.fS. Nuclear = Regulatory. Commission

. December'1,l1980 Repairs.or-adjustments.to the Petention' Tank Pump Discharge Valve-

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will be accomplished-and~a' retest will.be performed.:

-If there are anyLquestions concerning,this report, please contact.

us.

Very.truly yours, DAIRYLAND POWER COOPERATIVE'

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-a, SY Frank Linder, General Manager FL: LEG:af cc:

Director, Office of Management Information and (3)

' Program Control U. S. Nuclear Regulatory Commission Washington, D.

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