05000267/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl

Forwards LER 83-016/03L-0.Detailed Event Analysis Encl

ML20073S188
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/28/1983
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20073S190	List: 05000267/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl 05000267/LER-1983-016-03, /03L-0:on 830331,two Class 1 Hydraulic Shock Suppressors Found Inoperable.Caused by Fully Extended Snubbers,Due to Thermal Pipe Movement.One Snubber Adjusted & Other Replaced
References
P-83159, NUDOCS 8305060479
Download: ML20073S188 (5)

LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671983016R00 - NRC Website

text

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Public service company cf C&us2 16805 Road 19 1/2, Platteville, Colorado 80651-9298 April 28, 1983 Fort St. Vrain Unit No. 1 P-83159 gggg{gg3 s

MAY - 21983 Mr. John T. Collins, Regional Administrator J

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. 50-267/83-016, 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. 50-267/83-016.

Very truly yours, Do-us

, 4 mMwar Don Warembourg Manager, Nuclear Production DW/cls Enclosure cc: Director, MIPC yh 8305060479 830428 PDR ADOCK 05000267 S

PDR

REPORTABLE OCCURRENCE DISTRIBlilaN Numbe r of Copies De p a r tne n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter) 3an Francisco Operations Office ATTN: California Patent Group 1333 Broadway Oakland, California 94612 De p a r tra n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Mr. Glen A. Newby. Chief HTR Branch Division of Nuclear Power Development

iail Station 3-107 Washington, D.C.

20545 De p a r t men t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Project Mana ge r ATT';

Dr. Seighley P. O. Box 81608 San Diego. CA 92133 Mr. John T. Collins, Regional Administrator 1 Original of P Letter)

Region IV Nuclear Regulatory Cots.issica 611 Ryan Plaza Drive Suite 1000 Arlingt n. Texas 76011 Mr. Philip C. Wagner, Project Manager 1 (P Letter)

Region IV Nuclear Regulatory Cocunission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 Director - - - - - - - - - - - -

1 (P Le tte r>

Of fice of Management Information and Program Control Nuclear Regulatory Commission Washington, D.C.

20555 INPO Records Center 1 (P Le t te r)

Suite 1500 1100 Circle 75 Parkway Atlanta. Georgia 30339

.ir. Mike D,1 rhin, FS V. GA Technologies. Inc. Si te ReDresentative --------- 1 (P Letter)

General Atomic Technologies. Inc.

16864 Weld County Road 19 1/2 Platteville, Colorado 80651

';2C Resident Site Inspector 1 (P Letter)

REPORT DATE:

April 28,1983 REPORTABLE OCCURRENCE 83-016 Determined ISSUE O OCCURRENCE DATE:

March 31, 1983 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/83-016/03-L-0 Final d

IDENTIFICATION OF OCCURRENCE:

On March 31, 1983, with the reactor shut down, two Class I hydraulic shock suppressors (snubbers) were found inoperable.

This event constitutes operation in a degraded mode of LCO 4.3.10 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

Both events occurred while the reactor was shutdown, but the reactor had been operated at power prior to the occurrence and subsequent to the most recent check for operability.

Therefore, the shock suppressors are assumed to have been inoperable during power operation.

j Each event is described in the following table:

(

Out Of Snubber Event No.

Service Time Date Identification

Event Description

1 1145 4-1-83 MSS-258 Inadequate stroke l

length.

2 0945 4-2-83 VSS-117 Inadequate stroke length.

l MSS-258 is an ITT Grinnell. Type 201 snubber, and VSS-117 is an l

Atlanta, Type AE411-2.5-5 snubber.

l l

l

REPORTABLE OCCURRENCE 83-016 ISSUE O Page 2 of 3

CAUSE

DESCRIPTION:

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

Event No.

Snubber Identification Cause Description 1

MSS-258 Thermal pipe movement caused full extension.

2 VSS-117 Thermal pipe movement caused full extension.

CORRECTIVE ACTION:

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

In Snubber Event No.

Service Time Date Identification Corrective Action 1

1558 4-1-83 MSS-258 Replaced with a qualified spare.

Adjusted stanchion length.

2 1010 4-2-83 VSS-117 Disconnected snub-ber, and adjusted stanchion length.

In each event, the snubbers were returned to service prior to reactor operatioh at power.

No further corrective action is anticipated or required.

REPORTABLE OCCURRENCE 83-016 ISSUE O Page 3 of 3 Prepared By:

//>-fit M

Duane L. Frye 7

Senior Technical Services Technician L[f f)

Reviewed By:

FranE Jf. ovacnek Technical Services Engineering Supervisor Reviewed By:

77/d 64 _ 8, L. M. McB ri de f

Station Manager Approved By:

Do, ts t.,, L m._,_ l_,w M M Don.Warembourg

/

/

Manager, Nuclear Production