05000409/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted

ML20054J609
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/18/1982
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20054J610	List: 05000409/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted 05000409/LER-1982-012-03, /03L-0:on 820526,during Refueling Outage, Containment Bldg Fire Suppression Header Removed from Svc to Repair High Pressure Svc Water Containment Isolation Valve.Header Returned to Svc Upon Completion of Repairs
References
LAC-8356, NUDOCS 8206290342
Download: ML20054J609 (2)

LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
4091982012R00 - NRC Website

text

_

D DA/RYLAND COOPERAT/VE

• PO BOX 817 2615 EAST AV SOUTH

• 1.A CROSSE. VASCONSIN S4601 (608) 788-4000 June 18, 1982 In reply, please refer to LAC-8356 DOCKET NO. 50-409 Mr. James G.

Keppler, Regional Administrator 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 N0. OPR-45 REPORTABLE OCCURRENCE NO. 82-12

REFERENCES:

(1)

LACBWR Technical Specifications, Section 6.9.1.9.b.

(2)

LACBWR Technical Speci fi cati ons,

Section 4.2.18.4.

(3)

DPC Letter, Linder to Keppler, LAC-8304, dated May 24, 1982

Dear Mr. Keppler:

In accordance with Reference 1, this is to inform you of ent ry into a degraded mode permitted by a limiting condition for operation.

Reference 2 requires, in part, that the fire hose station in the Containment Building Basement be operable at all times.

At 0845 on May 26, 1982, during a refueling outage, the Containment Building fire suppression header was removed f rom service to repai r the High Pressure Service Water Containment Isolation Valve (75-26-003).

During a recent periodic Type C leakage test, leakage greater than the acceptance criteria had been measured through this valve (See Reference 3).

A firehose was connected to an outside fire hydrant near the entrance to the Containment Building to provide compensatory fi re fighting capability while the Containment Building fire suppression header was removed from service.

The header was returned to operable status at 2230 on May 26, 1982.

A Licensee Event Report (Reference: Regulatory Guide 1.16, Revision

4) is enclosed.

j% M 8206290342 8206iB PDR ADOCK 05000409 s

PDR WP1 gyN 2 4 102

Mr. James G. Keppler, Regional Administrator June 18, 1982 U. S. Nuclear Regulatory Commission LAC-8356 If there are any questions, please contact us.

Very truly yours, DAIRYLAND P0 R COOPERATIVE h

Frank Linder, General Manager FL:LSG:eme Attachment cc:

Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.

C.

20555 NRC Resident Inspector-INP0 i!

WP1 _ _____