05000409/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted

ML20050A985
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/23/1982
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20050A986	List: 05000409/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted 05000409/LER-1982-003-03, /03L-0:on 820313,during Type B Leakage Test on Personnel Airlock,Manometer Read Incorrectly.Caused by Inadequate Tightening of Strongbacks on Inner Door.Need for Tight Installation Emphasized & Procedure Revised
References
LAC-8167, NUDOCS 8204020472
Download: ML20050A985 (2)

LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
4091982003R00 - NRC Website

text

I

~

9 D

DA/RYLAND

~

h [k

COOPERAT/VE e.O box 8i7 2615 EAST AV SOUTH

• LA CROSSE. WISCONSIN 54601 (608) 788-4000 March 23, 1982 In reply, please refer to LAC-8167 DOCKET N0. 50-409 Mr. James G. Keppler, Regional 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

?J '. c'!,g

~'

REPORTABLE OCCURRENCE NO. 82-03

,. *2

'g

.y

REFERENCES:

(1) LACBWR Technical Specifications,

!Y

• O M W gr:ncg g 10

'P l Jg Sections 6.9.1.9.b and c (2) LACBWR Technical Specifications, ng Section 5.2.1.2

" Q oma 77 (3) LACBWR Technical Specifications, yq Section 3.0.3 N' Q, / -

p

Dear Mr. Keppler:

In accordance with Reference 1, this report is notification of observed inadequacies in the implementation of a procedure which led to commencement of a plant shutdown required by a limiting condition for operation.

On March 12-13, 1982, a Type B leakage test of the personnel air lock was conducted. The test method used involves placing an airtight reference chamber inside the airlock. Both the reference chamber and the air space between the inner and outer personnel air lock doors are pressurized to at least 52 psig. The difference in pressure between the reference chamber and the airlock is measured with a manometer. Any change in dif ferential pressure is assumed to be due to leakage from the airlock. The acceptance criteria is 3.75 SCFH.*

On March 13, the leakage rate was calculated to be 3.23 SCFH, which is within the acceptance. criteria. A small amount of leakage was found using the soap bubble techniqu'e on the inner door gasket. No leakage was detected through the outer door. The test was detennined satisfactory.

• Shall not exceed 10% of leakage rate Lpo, where Lpo is 37.5 SCFH (Reference 2).

WP-6 -

0204020472 820323

@R 2 9 g82

[

PDR ADDCK 05000409

/

,S PDR

i i

3 Mr. James G. Keppler, Regional Director March 23, 1982 U. S. Nuclear Regulatory Commission LAC-8167 At 0750 on March 14, it was determined that the auxiliary operator hoc not l

read the manameter correctly when conducting the Type B test on the personnel ai rl ock. Also, the operators who removed the strongbacks, which are installed

{

on the inner airlock door for the test, found them to be not as secure as noma 1 The strongbacks are needed because the force on the inner door during the Type B test is from the opposite direction than would be the case in a containment pressurization accident. A reactor shutdown commenced in l

accordance with Reference 3.

f The Mechanical Maintenance Supervisor and the Operations Supervisor were I

called in to supervise their departments in conducting a retest.

A successful retest was concluded at 2000 on March 14. The calculated leakage rate was i

1.503 SCFH, which is within the acceptance criteria of Reference 2.

The l

lowest reactor power reached was 40% Rated Thermal Power (18 MWe-Net).

[

The Type B test procedure for the personnel airlock will be modified to include instructions for reading the manometer.

The importance of secure instrllation of the strongbacks has been emphasized to the Maintenance Department.

The Nuclear Regulatory Commission Resident Inspector for LACBWR, M. Branch, was notified of the event at approximately 0830 on March 14, 1982. The NRC Operations Center was notified at 0850 on March 14, 1982.

A Licensee Event Report (Reference: Appendix A, Regulatory Guide 1.16, Revision 4) is enclosed.

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

Very truly yours, l

DAIRYLAND POWER COOPERATIVE WENS AVFrank Linder, General Manager P

FL:LSG:eme Enclosures cc:

Director, Office of Inspection and Enforcement (30)

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Director, Office of Management Infomation (3) and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 NRC Resident Inspector INPO 4

WP-6