05000267/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

ML20040G935
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/05/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20040G936	List: 05000267/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl 05000267/LER-1982-001-03, /03L-0:on 820108,18 Snubbers Found Inoperable During Surveillance Testing,Indicating Inoperability During Reactor Operation.Caused by Seal Leakage & Deficiencies in Piston Position & Oil Level.Snubbers Repaired
References
P-82032, NUDOCS 8202160639
Download: ML20040G935 (7)

LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671982001R00 - NRC Website

text

. -.

puhtic servlee compimy of Cenomde ve i 16805 Road 19.1/2, Platteville, Colorado 80651-9298 February 5, 1982 Fort St. Vrain Unit No. 1.

P-82032

% R@ R MIR

• FEB 81982 Mr. John T. Collins, Regional Administrator j

Region IV Nuclear Regulatory Commission n

(;7[c ~Qf3 611 Ryan Plaza Drive i

Suite 1000 i

Arlington, Texas 76011

.a. a y g9 Reference: Facility Operating Li e se r/gg I982a I No. DPR-34 nm

- Lacua[#lft s

Docket No. 50-267 9,

Dec 7

/

t

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-001, 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. 50-267/82-01.

Very truly yours, W

Don Warembourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC h

82021'60639'820205

~

PDR ADOCK 05000267

/ l 0

PDR

REPORT DATE:

February 5,1982 REPORTABLE OCCURRENCE 82-001 ISSUE 0 OCCURRENCE DATE:

January 8, 1982 Page 1 of 6 FORT ST. VRAIN NUCLEAR GENERATING STATION

- PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298' REPORT NO. 50-267/82-001/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During Surveillance Testing by plant personnel, while the reactor was in a shutdown / cooled down condition, a total of eighteen Class I hydraulic shock suppressors (snubbers) were found to be inoperable.

Since the reactor had been operated since these snubbers were last successfully tested, the snubbers must be considered to have been inoperable when the reactor was at power.

This is a degraded mode of LC0~4.3.10 and is reportable per Fort'St.

Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

With the plant shutdown for a system modification outage, plant personnel conducted a routine Surveillance Test of all-hydraulic shock suppressors (snubbers) to verify their operability. A total of eighteen Class I snubbers were found to be inoperable for various reasons.

The tabulation which follows lists the snubbers by number and their associated event description.

EVENT NUMBER SNUBBER IDENTIFICATION

EVENT DESCRIPTION

1 HRS-281 No visual oil level.

2 HRS-357 No visual oil level.

3 HOS-74 Piston fully extended.

l l

4 H05-88 No visual oil level.

5 HOS-87 Piston fully inserted.

6 MSS-257 Piston fully extended.

t 7

HRS-413 Piston fully inserted.

i

REPORTABLE OCCURRENCE'82-001 ISSUE O Page 2 of 6

~

~

EVENT NUMBER ~ SNUBBER IDENTIFICATION

EVENT DESCRIPTION

8 CRS-297 Found disconnected and removed from system.

9

.VSS-116 Piston' fully' extended, no visual oil level 10 HRS-205 Rod shaft unscrewing from rod eye.

11 BFS-399E No visual oil level.

12 BFS-158E No visual oil level.

13 HRS-158 Piston fully extended, no visual oil level.

14 BFS-299E No visual oil level.

15 MSS-149 No visual oil level.

16 CRS-751' uNo visual-oil level.

17 BFS-228E No visual oil level.

18 BFS-534 No visual oil level.

CAUSE

DESCRIPTION:

The following is a listing of cause descriptions associated with each event number.

EVENT NUMBER SNUBBER IDENTIFICATION CAUSE DESCRIPTION 1

HRS-281 Seal / internal leakage caused a loss of reservoir oil.

2 HRS-357 Seal / internal leakage caused a loss of reservoir oil.

3 HOS-74 Thermal pipe contra tion caused snubber to be. fully extended.

4 H05-88 Seal / internal leakage aused a loss of reservoir oil.

5 HOS-87 Thermal pipe contraction caused snubber to be fully inserted.

REPORTABLE OCCURRENCE 82-001 ISSUE 0 Page 3 of 6 EVENT.-

NUMBER SNUBBER IDENTIFICATION-CAUSE DESCRIPTION 6

MSS-257 Thermal pipe contraction caused snubber to be fully inserted.

7 HRS-413 Thermal-pipe contraction caused isnubber to be fully inserted.

8 CRS-297 Exact cause is unknown. May have been disconnected due to mainte-nance in immediate area.

9 VSS-116 Thermal pipe contraction caused snubber to be fully extended, using all available oil in reser-voir.

10 HRS-205 Vibration caused the shaft to ro-tate loose from the rod eye end.

11 BFS-399E Seal / internal leakage caused a loss of reservoir oil.

12 BFS-158E Seal / internal leakage caused a loss of reservoir oil.

13 HRS-158 Thermal pipe contraction and seal leakage caused the snubber to be fully extended, using all remaining oil in reservoir.

14 BFS-229E

- Seal / internal leakage caused a loss of reservoir oil.

15 MSS-149 Seal / internal-leakage caused a loss of reservoir oil.

16 CRS-751 Seal / internal leakage caused a loss of reservoir oil.

17 BFS-228E Seal / internal leakage caused a loss of reservoir oil.

18 BFS-534 Seal / internal leakege caused a loss l

of reservoir oil, i

~

REPORTABLE OGCURRENCE 82-001 ISSUE O Page 4 of 6 CORRECTIVE ACTION:

The following is a listing of corrective actions taken associated with each event number.

EVENT NUMBER SNUBBER IDENTIFICATION

CORRECTIVE ACTION

1 HRS-281 Cylinder and valve block rebuilt, filled, purged, and tested.

Reser-voir repositioned to ensure maximum oil availability.

Re-installed in system.

2 HRS-357 Filled, purged, and tested.

Re-inst &? led in system.

3 H05-74 Cylinder and valve block rebuilt, filled, purged, and tested.

Re-installed in system.

4 HOS-88 Cylinder and valve block rebuilt, filled, purged, and tested.

Re-installed in system.

5 HOS-87 Filled, purged, and tested.

New bracket made to prevent piston from bottoming out. 'Re-installed in system.

6 MSS-257 Filled, purged, and tested. Ad-justed extension tube. Re-installed in system.

7 HRS-413 Filled, purged, and tested.

'Re-installed in system.

8 CRS-297 Filled, purged, and tested.

Re-installed in system.

9 VSS-116 Adjusted reach rod, filled, purged, and tested.

Re-installed in system.

10 HRS-205 Screwed rod eye tight onto piston rod, filled, purged, and tested.

Re-installed in system.

11 BFS-399E Rebuilt cylinder and valve assembly.

Filled, purged, and tested.

Re-installed in system.

I REPORTABLE OCCURRENCE 82-001 ISSUE O Page 5 of 6 EVENT NUMBER SNUBBER IDENTIFICATION

CORRECTIVE ACTION

12 BFS-158E

- Rebuilt cylinder and valve block.

Filled, purged, and tested.

Re-installed in system.

13 HRS-158 Rebuilt cylinder and valve block.

Filled, purged, and tested.

Re-installed in system.

Added shim to-end.

14 BFS-299E Rebuilt cylinder and valve block.

Filled, purged, and tested.

Re-installed in system.

15 MSS-149 Rebuilt cylinder.and valve block.

Filled, purged, and tested.

Re-stalled in system.

16 CRS-751 Rebuilt cylinder and valve block.

j Filled, purged,.and tested.

Re-t installed in system.

17 BFS-228E Filled, purged, and tested.

Re-installed in system.

18.

BFS-534 Rebuilt cylinder and orifice block.

Filled, purged, and tested.

Re-installed in system.

In accordance with Surveillance Requirement 5.3.8, the surveillance interval has been adjusted to 31 days + 25%.

No further corrective action is anticipated or required.

m.._

~

REPORTABLE OCCURRENCE 82-001' ISSUE 0.

.Page 6 of 6-t r

C Prepared By: (!)'toevti ' hh d2 Owen J. C.1tyton-

//

Technical ervices Technician.

C/d M /r % u Reviewed By:

Charles Fuller Technical-Services Engineering Supervisor

[

s Reviewed By:

/

/

Edw1/(O'. Hill * '

Station Manager Approved By:

Ma,u4 Don Warembourg Manager, Nuclear Production e.