ML19338G152: Difference between revisions

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Public service company ce c elle m ure 16805 ROAD 19%
Public service company ce c elle m ure 16805 ROAD 19%
                   =a      PLATTEVILLE, COLOR ADO 80651 October 24, 1980 Fort St. Vrain Unit No. 1 P-80378
                   =a      PLATTEVILLE, COLOR ADO 80651 October 24, 1980 Fort St. Vrain Unit No. 1 P-80378 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Cocuission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000                                                                                    ,
                                                                                                      .
Mr. Karl V. Seyfrit, Director Nuclear Regulatory Cocuission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000                                                                                    ,
Arlington, Texas 76012
Arlington, Texas 76012


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REPORT DATE:            October 24, 1980              REPORTABLE OCCURRENCE 80-54 ISSUE O OCCURRENCE DATE:        September 26, 1980            Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CQiPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATIEVILLE, COLORADO 80651 REPORT No. 50-267/80-54/03-L-0 Final IDENTIFICATION OF OCCURRENCE:
REPORT DATE:            October 24, 1980              REPORTABLE OCCURRENCE 80-54 ISSUE O OCCURRENCE DATE:        September 26, 1980            Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CQiPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATIEVILLE, COLORADO 80651 REPORT No. 50-267/80-54/03-L-0 Final IDENTIFICATION OF OCCURRENCE:
During the performance of the hydraulic snubber suveillance test, eight snub-bers were found to be inoperable. Since reactor operation had occurred during the surve111ance interval, this is interpreted as a degraded mode of LCO 4.3.10 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
During the performance of the hydraulic snubber suveillance test, eight snub-bers were found to be inoperable. Since reactor operation had occurred during the surve111ance interval, this is interpreted as a degraded mode of LCO 4.3.10 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
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1 1
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[    ,
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l
l REPORTA3LE OCCURRENCE 80-54 ISSUE O Page 2 of 4 CAUSE DESCRIPTION:
  ,
    .
REPORTA3LE OCCURRENCE 80-54 ISSUE O Page 2 of 4 CAUSE DESCRIPTION:
The reasons for the inoperable snubbers were as follows:
The reasons for the inoperable snubbers were as follows:
BFS-405E    Reservoir empty.
BFS-405E    Reservoir empty.
BFS-412      Stroke out of tolerance.
BFS-412      Stroke out of tolerance.
                              .
HOS-10        Stroke out of tolerance.
HOS-10        Stroke out of tolerance.
HOS-36        Interf erence with mounting bracket.
HOS-36        Interf erence with mounting bracket.
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Surveillance interval has been adjusted to 31 days.
Surveillance interval has been adjusted to 31 days.
No further corrective action is anticipated or required.
No further corrective action is anticipated or required.
,


-
I REPORTABLE OCCURRENCE 80-54 ISSUE O Page 3 of 4 INTERNAL SEAL 011 Reserioir                                  -Snubber Valve In:ake O                                                      Snubber Valve
I
  .        ..                ..
REPORTABLE OCCURRENCE 80-54 ISSUE O Page 3 of 4 INTERNAL SEAL 011 Reserioir                                  -Snubber Valve In:ake O                                                      Snubber Valve
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EXTERNAL SEAL 011 Reserioir                                  -Snubber valve Istake O                                                      Scubber 7alve
EXTERNAL SEAL 011 Reserioir                                  -Snubber valve Istake O                                                      Scubber 7alve
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Cylinder l
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External Seal Housing FIGURE 1
External Seal Housing FIGURE 1


___
  *
.
REPORTABLE OCCURRENCE 80-54 ISSUE O Page 4 of 4 Prepared By:                A Asa B. Re<A Technical Services Technician                                                  O Reviewed 3y:                .
REPORTABLE OCCURRENCE 80-54 ISSUE O Page 4 of 4 Prepared By:                A Asa B. Re<A Technical Services Technician                                                  O Reviewed 3y:                .
                               .u.sa.
                               .u.sa.
Line 146: Line 107:
Frank M. Mathie Operations Manager Approved By:              'JI" D. Warembourg        /
Frank M. Mathie Operations Manager Approved By:              'JI" D. Warembourg        /
Manager, Nuclear Production
Manager, Nuclear Production
_ _ . . . . . . . _ _ . __
__ _ _ . . _.    --. _      __.
                                                                   . _ _ _ _ _ _ . . _ __ _ _ _ _ . _ _ .}}
                                                                   . _ _ _ _ _ _ . . _ __ _ _ _ _ . _ _ .}}

Latest revision as of 11:52, 31 January 2020

Forwards LER 80-054/03L-0
ML19338G152
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 10/24/1980
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19338G153 List:
References
P-80378, NUDOCS 8010280516
Download: ML19338G152 (5)


Text

. - _ - - - _ - - _ - - - -

r*

Public service company ce c elle m ure 16805 ROAD 19%

=a PLATTEVILLE, COLOR ADO 80651 October 24, 1980 Fort St. Vrain Unit No. 1 P-80378 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Cocuission 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/

80-54, 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. 50-267/30-54.

Very truly yours, W

Don Warembourg Manager, Nuclear Production DW/cis Enclosure ec: Director, MIPC S

//

8 01028 0 {\b

REPORT DATE: October 24, 1980 REPORTABLE OCCURRENCE 80-54 ISSUE O OCCURRENCE DATE: September 26, 1980 Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CQiPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATIEVILLE, COLORADO 80651 REPORT No. 50-267/80-54/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the performance of the hydraulic snubber suveillance test, eight snub-bers were found to be inoperable. Since reactor operation had occurred during the surve111ance interval, this is interpreted as 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:

On September 26, 1980, with the reactor shutdown for a maintenance period, maintenance personnel performing a scheduled hydraulic snubber surveillance identified eight inoperable snubbers.

These snubbers were last tested between August 25, 1980, and August 28, 1980.

The reactor was at power at that time and reactor operation continued until 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> August 29, 1980, at which time a maintenance shutdown period began.

3 The eight inoperable snubbers were as follows:

BFS-405E BFS-412 HOS-10 HOS-36 HOS-86 HRS-205 HRS-428 VSS-123 l

l l

1 1

I i

v 1

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l REPORTA3LE OCCURRENCE 80-54 ISSUE O Page 2 of 4 CAUSE DESCRIPTION:

The reasons for the inoperable snubbers were as follows:

BFS-405E Reservoir empty.

BFS-412 Stroke out of tolerance.

HOS-10 Stroke out of tolerance.

HOS-36 Interf erence with mounting bracket.

HOS-86 Stroke out of tolerance.

ERS-205 Stroke out of tolerance.

HRS-428 Stroke out of tolerance.

VSS-123 Interference with structural steel.

BFS-412 and HRS-428 vere subsequently examined by the Engineering Department and determined to be operable. (See Figure 1.) The original measurement was from point ($)to($)as most of the snubbers in use have internal seals.

These two snubbers have external seals and the measurements should have been made from($)to($) The correct measurement showed the snubbers to be operable.

CORRECTIVE ACTION:

The snubbers were corrected in the following manner:

BFS-405E Refilled reservoir.

BFS-412 None required - Test procedure revised to clarify measurement.

HOS-10 Installed new pipe stanchion.

H05-36 Rotated snubber 180* and changed reservoir position.

HOS-86 Repositioned pipe clamp.

HRS-205 Re-adjusted snubber stroke and extended stanchien.

HRS-428 None required - Test procedure revised to clarify measurement.

VSS-123 Repositioned mounting bracket and moved pipe clamp 1/2 inch.

Surveillance interval has been adjusted to 31 days.

No further corrective action is anticipated or required.

I REPORTABLE OCCURRENCE 80-54 ISSUE O Page 3 of 4 INTERNAL SEAL 011 Reserioir -Snubber Valve In:ake O Snubber Valve

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EXTERNAL SEAL 011 Reserioir -Snubber valve Istake O Scubber 7alve

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REPORTABLE OCCURRENCE 80-54 ISSUE O Page 4 of 4 Prepared By: A Asa B. Re<A Technical Services Technician O Reviewed 3y: .

.u.sa.

gTechnical Services Supervisor Reviewed By: 4'E \

Frank M. Mathie Operations Manager Approved By: 'JI" D. Warembourg /

Manager, Nuclear Production

. _ _ _ _ _ _ . . _ __ _ _ _ _ . _ _ .