05000267/LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl

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Forwards LER 83-004/03L-0.Detailed Event Analysis Encl
ML20071E457
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/04/1983
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20071E462 List:
References
P-83090, NUDOCS 8303150247
Download: ML20071E457 (5)


LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2671983004R00 - NRC Website

text

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4 public Senice Company

& Cdlondo 16805 Road 19 1/2, Platteville, Colorado 80651-9298 March 4, 1983 Fort St. Vrain

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P-83090 lM MAR-91983 qU)!

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Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/83-004, 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. 50-267/83-004.

Very truly yours, Don Warembourg Manager, Nuclear Pr uction DW/cls Enclosure cc: Director, MIPC b

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l 8303150247 830304 DRADOCK05000g i

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REPORT DATE:

March 4, 1983 REPORTABLE OCCURRENCE 83-004 ISSUE O OCCURRENCE DATE:

February 3, 1983 Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/83-004/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the period from February 3,1983, to February 4,1983, five Class 1 hydraulic shock suppressors (snubbers) were found to be inoperable.

This is reported as a degraded mode of LCO 4.3.10 per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

All of the events occurred while the reactor was in a shutdown mode, but the reactor had been operated at power prior to the occurrences and subsequent to the most recent check for operability. Therefore, the associated shock suppressors are assumed to have been inoperable during power operation.

Each event is described in the following table:

Out Of Snubber Event No.

Service Time Date Identification

Event Description

1 1100 2-3-83 CRS-556-1 Reservoir out of oil.

2 1100 2-3-83 HRS-422 Reservoir out of oil.

3 1357 2-3-83 MSS-184 Reservoir out of oil.

l 4

1030 2-4-83 BFS-614 Reservoir out of

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oil.

5 1030 2-4-83 MSS-204 Reservoir out of oil.

CRS-556-1, HRS-422, and MSS-184 are ITT Grinnell, type 200 snubbers.

BFS-614 and MSS-204 are ITT Grinnell, type 201 snubbers.

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REPORTABLE OCCURRENCE 83-004 ISSUE O Page 2 of 4

CAUSE

DESCRIPTION:

The cause of each event is described in the following table:

Event No.

Date Snubber Identification Cause Description 1

2-3-83 CRS-556-1 Loss of oil due to seal leakage.

2 2-3-83 HRS-422 Loss of oil due to broken reservoir.

3 2-3-83 MSS-184 Loss of oil due to seal leakage.

4 2-4-83 BFS-614 Loss of oil due to seal leakage.

5 2-4-83 MSS-204 Loss of oil due to seal leakage.

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4 REPORTABLE OCCURRENCE 83-004 ISSUE O Page 3 of 4 CORRECTIVE ACTION:

The corrective action taken for each event is described in the following table:

In Snubber Event No.

Service Time Date Idantification

Corrective Action

1 1355 2-3-83 CRS-556-1 Replaced with quali-fied spare, in-stalled in the sys-tem.

2 1030 2-4-83 HRS-422 Replaced broken reservoir, rebuilt cylinder and valve block, tested on Bergen-Patterson test stand, and re-installed in the system.

3 1030 2-4-83 MSS-184 Rebuilt cylinder and valve assembly, tested on Bergen-Patterson test stand, and re-installed in the system.

4 1415 2-4-83 BFS-614 Rebuilt cylinder and valve assembly, tested on Bergen-Patterson test stand, and re-installed in the system.

5 1415 2-4-83 MSS-204 Rebuilt cylinder and valve assembly, tested on Bergen-Patterson test stand and re-installed in the system.

In each event, the snubbers were returned to service within the 72-hour period specified allowed by LCO 4.3.10.

o REPORTABLE OCCURRENCE 83-004 ISSUE O Page 4 of 4 Prepared By:

  1. 1,t/

b Robert A. Dickerson Senior Technical Services Technician l

Reviewed By:

6 4[

Charles Fuller Technical Services Engin ering Supervisor

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Reviewed By:

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Ecwin D. Hilllr-Station Manager l

Approvec By:

Wmm f Don Warembourg

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ff Manager, Nuclear Production l

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