05000267/LER-1980-027, Forwards LER 80-027/03L-0

Forwards LER 80-027/03L-0

ML19318D218
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/01/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19318D219	List: 05000267/LER-1980-027, Forwards LER 80-027/03L-0 05000267/LER-1980-027-03, /03L-0:on 800603 to 11,three Separate Instances of Reactor Operation Took Place W/Inoperable Class 1 Shock Suppressors.Caused by Rotated Reservoir,Low Oil Level Due to Cracked Fitting & Piston Rod Seal Leak
References
P-80188, NUDOCS 8007080210
Download: ML19318D218 (5)

LER-1980-027, Forwards LER 80-027/03L-0

Event date:
Report date:
2671980027R00 - NRC Website

text

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Public service company ce cdemaTo l

16805 ROAD 19%

PLATTEVILLE, COLORADO 80651 July 1, 1980 Fort St. Vrain Unit No. 1 P-80188 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Reference: Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/

80-27, Final, submitted per the requirements of Technical Specification AC 7.5.2(b) 2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/80-27.

Very truly yours, 5

Don Warembourg

/

Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC 3 9h i

8007080 Sio

e REPORT DATE:

July 1, 1980 REPORTABLE OCCURRENCE 80-27 ISSUE O OCCURRENCE DATE:

June 3, 1980 Page 1 of 4 FORT ST. VRAIN NUCLEAR GENE 3ATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD County ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-27/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the period from June 3, 1980, through June 11, 1980, with the reactor operating at power, three separate instances of reactor operation ecok place with inoperable Class I shock suppressors (snubbers).

These events constitute operation in a degraded mode of LCO 4.3.10, and are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

Three instances of LCO 4.3.10 degraded mode operation occurred between June 3 and June 11, 1980, as outlined below.

Event #1 At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on June 3,1980, with the plant operating at approximately 62% thermal power and 179 !We, hydraulic oil snubber HOS-30 was determined to be impaired due to the snubber reservoir being rotated below the cylinder.

The snubber was repaired and returned to service at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on June 3, 1980.

Event #2 At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on June 3,1980, with the plant operating at approximately 69% thermal power and 200 MRe, main steam snubber 11SS-422 was removed from service to repair a cracked fitting.

A Plant Trouble Report had been initiated to indicate that the snubber was low op oil, but was still operative. However, investigation revealed that the low oil level was due to a broken fitting from the valve to the cylinder, so the snubber was removed from service for repair.

The faulty fitting was replaced, and the snubber filled wf th oil and returned to service at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on June 4,1980.

O REPORTABLE OCCURRENCE 80-27 ISSUE O Page 2 of 4 EVENT

DESCRIPTION

(Cont' d)

Event #3 At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on June 11, 1980, with the plant operating at approximately 697. thermal power and 202 NRe, main steam snubber MSS-149 was removed from service for repair of a piston rod seal.

A Plant Trouble Report was initiated on May 19, 1980, indicating that this snubber had a low oil level, but that it was still operable. This low oil level did not result in LCO 4.3.10 degraded mode operation; however, a decision to remove the snubber from operation for repair on June 11 resulted in operation in a degraded mode of LCO 4.3.10.

The enubber was rebuilt per approved procedure to rectify the rod seal leakage, and was returned to service at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on June 11, 1980.

No further instances of LCO 4.3.10 degraded mode operation were observed.

J

CAUSE

DESCRIPTION:

4 Event #1 Rotation of the reservoir of HOS-30 is being attributed to personnel working in the area using the snubber as a stepping platform.

Event #2 Cause of MSS-422 low oil level was a cracked fitting between the snubber valve and cylinder, which necessitated removing the snubber from service for repai,r.

Event #3 Cause of event #3 degraded mode operation was the removal of MSS-149 i

from service in order to repair a piston rod seal. Although the seal 1eakage resulted in the snubber having low oil level, it was not inoper-able prior to its removal from service.

CORRECTIVE l

ACTION:

Event #1 i

The snubber was returned to its proper position, its lock nut set, and the snubber returned to service.

Personnel were reminded that plant piping and installations are not to be used in place of ladders in order to gain access to equipment.

REPORTABLE OCCURRENCE 80-27 ISSUE O Page 3 of 4 CORRECTIVE ACTION:

(Cont'd)

Event #2 The broken fitting was replaced with a new fitting. The snubber was filled with oil and returned to service.

Event #3 T'e piston rod seal was replaced during rebuilding of the snubber cylinder and valve per approved procedure, and the snubber was returned to service.

In accordance with Surveillance Requirement 5.3.8, the surveillance interval has been adjusted to 124 days + 25%.

No further corrective action is anticipated or required.

REPORTABLE OCCURRENCE 80-27 ISSUE O Page 4 of 4 Prepared By:

,1r/M.

wI Cathy Cy Hirsch Technical Services Tecn ician Reviewed By:

T((), t /// 7?? [],

J. W. Gahm u

Technical Services Supervisor Reviewed By:

Frank M. Mathie Operations Manager Approved By:

Tw W

Don Warembourg Manager, Nuclear Production l

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