ML20053C792

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RO 82-11:on 820523,during Type B & C Surveillance Leakage Testing,Degradation Discovered in Primary Reactor Containment High Pressure Svc Water Containment Isolation Valve.Repairs Will Be Accomplished & Retests Performed
ML20053C792
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 05/24/1982
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-8304, RO-82-11, NUDOCS 8206020566
Download: ML20053C792 (2)


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  • Po BOX 817 2615 EAST AV SOUTH
  • LA CROSSE. WISCONSIN 54601 (608) 788 4 000 May 24, 1982 In reply, please refer to LAC-8304 DOCKET NO. 50-409 Mr. James G.

Keppler, Director U.

S. Nuclear Regulatory Commission 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 REPORTABLE OCCURRENCE NO. 82-11

Reference:

(1)

LACBWR Technical Specifications, Section 6.9.1.8.c.

(2)

LACBWR Technical Specifications, Section 5. 2.1. 2. (b) and 5. 2.1. 3. (b).

Dear Mr. Keppler:

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

As a result of conducting a periodic Type C leak test on the High Pressure Service Water Conthinment Isolation Valve, the leak flow rate determined from the valve exceeded the permissible leak flow rate as defined in Technical Specifications (Reference 2).

During the conduct of Type B leakage tests, the leakage rate from Electrical Penetration Unit No. 5 exceeded the allowable leakage rate.

The test leakage rate from the HPSW Containment Isolation Valve was determined to be 2.39 SCFH.

The leakage rate from Electrical Pene-tration Unit 5 was 48.83 SCFH, the majority of which was through the test chamber boundary, of the Containment Building wall.

The Acceptance Criteria is 0.375 SCFH* for each penetration.

The tests were performed on May 23, 1982.

Prompt notification of

+

test results to Paul Pelke, Region III, U.

S. Nuclear Regulatory Commission, was accomplished at 0915 on May 24, 1982, by L. S.

Goodman, LACBWR Operations Engineer.

Notification of the HPSW Containment j

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

pg po g

82060206% S I l MAY 2 6 E02

i s

i Mr. James G.

Keppler, Director LAC-8304 U.

S. Nuclear Regulatory Commission May 24, 1982 Isolation Valve test results was also.nade to the NRC Operations Center at 0425 on May 23,-1982, by J.

Gallaher, LACBWR-Shift Supervisor.

Repairs or adjustments will be accomplished and retests will be performed.

If there are any questions concerning this report, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE l

Frank Linder, General Manager 1

FL:LSG:af cc:

NRC Resident Inspector i

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