ML20086E166

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AO 50-267/74/6:on 740402,during Startup Testing,Reserve Shutdown Hopper Pressure Switch Failed to Indicate Pressure Buildup During Normal Surveillance.Caused by Check Valve Plugged W/Dirt & Iron Oxide.Valves Cleaned
ML20086E166
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 04/02/1974
From: Mathie F, Swart F
PUBLIC SERVICE CO. OF COLORADO
To: Anthony Giambusso
US ATOMIC ENERGY COMMISSION (AEC)
References
AO-50-267-74-6, NUDOCS 8312060216
Download: ML20086E166 (7)


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A ril 2, 1974 UNUSUAL OCCURRENCE O

P DATE:

ABNORMAL OCCURRENCE X FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 80651 g

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(o REPORT NO. 50-267/74/ 6 Ic

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Final IDENTIFICATION OF OCCURRENCE:

The Reserve Shutdown Hopper pressure switch failed to indicate a

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pressure buildup during normal surveillance.

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1 CONDITIONS PRIOR TO OCCURRENCE:

Steady State Power Routine Shutdown Hot Shutdown Routine Load Change Cold Shutdown X

Other (specify)

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Refueling Shutdown Reactor shutdown in air Routine Startup atmosphere during "A" series Start-up tests.

8312060216 740402 PDR ADOCK 05000267 S

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o-Pcg2 2 The major plant paramaters at the time of the event were.as follows:

Power'

PTR, N/A MWth

, ELECT, N/A gue Secondary Coolant Pressure N/A ig-ps Temperature N/A ep Flow N/A

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4 Primary Coolant Pressure' N/A psig Temperature N/A

  • F Core Inlet N/A i'

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Flow N/A

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P5ga 3 DESCRIPTION OF l

OCCURRENCE:

Routine testing of operability of the eserve Shutdown Hopper of Control Rod Drive No. 30, in Penetration 11, revealed the inability to cause operation of the pressure indicating swit,ch in the hopper. The testing was being done prior to installing the secondary closure.

The drive was removed from the reactor and the check valve removed from the discharge end of the Reserve Shutdown pressurizing line in the penetration wall.

The check valve was found to be plugged with dirt, iron oxide and pipe scale of a fairly fine consis'tency.

This material had plugged the v'alve rendering it inoperable in the closed position.

(See drawing No. PI-11-1 attached,'with check valves circled in red)

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ANALYSIS OF OCCURRENCE:

Mill scale, dirt, rust, etc., which had accumulated in the pipes during storage prior to construction, and during-construction, had-not been cleared from the lines. This foreign material was caught in the check. valve.

during normal testing and jammed the valve.

2 Normal testing uncovered the problem.

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N CORRECTIVE' u

ACTION:

Ch'ech valves were removed from the reserve shutdown pressurizing lines of a'11 control rod drive penetrations and the lines were, blown clear.

The checlevalves were cleaned and reinstalled.

The controldod purge lines and check valves were treated similarly since tha 24--

a th: :::: ::teridl cad.the check valvcs the sana design.

L renewed build-up of scale is not anticipated because the supply lines to the control rod drives will be filled with Helium in nomal use, e

as opposed to air during the construction phase.

FAILURE DATA /SEfILAR REPORTED OCCURRENCES:

4 No failures of a similar nature have previously occurred.

PROGRAIDIATIC IMPACT:

It is expected that this orablem vill va ='ilt in.: 3-5 day del /

_in c6mpletion of PCRV top head work.

l CODE DIPACT:

No codes involved.

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Prepared.by:

Appreved:

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F. if. Mathie t>

fredericE. Swart-Maintenance Engineer Guperintendent

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.O pubile service company oe conorado P. O. Box 361,-Platteville, Celorado 80651-l April 16, 1974 Q,.

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s f:n Mr. A. Ciambusso

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Deputy Directo,

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Directorate of Licensing

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S Iid zTh United States Atomic Energy Commission Washington, D. C.

20545 REF: Facility Operating License-No. DPR-34 Docket No. 50-267--

Dear Mr. Giambusso:

Attached please find 3 copies of Abnormal 0ccurrence Report,.No.'

50-267/74/6, submitted for your information.

Very truly yours, ff M uJ:w Frederic E. Swart Superintendent Fort St. Vrain Nuclear Generating Station FES:ll p

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