05000333/LER-1988-001, :on 880310,HPCI Turbine Steam Supply Valve Failed to Open in Response to Open Signal.Caused by Procedures Not Including Evaluation of Relubrication of Threads of Valve Stem & Stem Nut

:on 880310,HPCI Turbine Steam Supply Valve Failed to Open in Response to Open Signal.Caused by Procedures Not Including Evaluation of Relubrication of Threads of Valve Stem & Stem Nut

ML20154L327
Person / Time
Site:	FitzPatrick
Issue date:	05/13/1988
From:	W. Verne Childs, Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
JAFP-88-0455, JAFP-88-455, LER-88-001, LER-88-1, NUDOCS 8805310252
Download: ML20154L327 (5)

LER-1988-001, on 880310,HPCI Turbine Steam Supply Valve Failed to Open in Response to Open Signal.Caused by Procedures Not Including Evaluation of Relubrication of Threads of Valve Stem & Stem Nut

Event date:
Report date:
3331988001R00 - NRC Website

text

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During normal operation at 100% rated power on 3/10/88 when required to be operable by Technical Specification 3.5.C, High Pressure Coolant Injection (HPCI) [BJ) was made inoperable when steam supply valve 23-MOV-14 failed to open during surveillance testing.

Automatic Depressurization System [AD], Low Pressure Coolant Injection [B0], Low Pressure Core Spray [BM), and Reactor Core Isolation Cooling [BN] systems were demonstrated operable.

These systems are redundart to or back up HPCI, resulting in operat ion of the plant within the rang, of accident analyses in the Final Safety Analysis Report.

The motor on 23-MOV-14 was destroyed by excessive current as a result of a procedure deficiency which did not require inspection and lubrication of the threads of the valve stem and stem nut when valves are repacked.

l Immediate corrective action was to replace the failed motor and return HPCI to service on 3/11/88 within approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.

Long-term corrective action is to revise the valve repacking procedure to require inspection, cleaning, and lubrication of the threads of the valve stem and stem nut.

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LER-85-025,86-014, 86-011, and 86-003 are related events in which

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safety-related valve motors failed tue to procedure deficiencies.

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Event Description

During normal full power (100% rated) operation at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on 3/10/88, High Pressure Coolant Injection (HPCI) [BJ] turbine steam supply valve 23-MOV-14 failed to open in response to an open signal.

The HPCI [BJ] system automatic initiation logic was being tested by performance of Surveillance Test ST-4E, titled "HPCI Subsystem Logic Functional Test".

Failure of valve 23-MOV-14 to open resulted in HPCI [EJ] being declared inoperable when the system was required to be operable by Technical Specification 3.5.C.

Surveillance to demonstrate the operability of Automatic Depressurization System (ADS) [AD],

Low Pressure Coolant Injection (LPCI) (BO), Low Pressure Core Spray (LPCS) (BM], and Reactor Core Isolation Cooling (RCIC) [BN]

as required by Technical Specification 4.5.C.1.a was initiated.

At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> on 3/10/88 during the surveillance testing required by Technical Specification 4.5.C.1.a. RCIC [BN] was also made inoperable for approximately one minute due to a personnel error which resulted in isolation of the RCIC [BN] steam supply (refer to LER-88-002 for details of this event).

Personnel performing the surveillance recognized the RCIC [BN] isolation as a personnel error, immediately corrected the error, and restored RCIC [BN] to service.

Following repair of valve 23-MOV-14 and testing to demonstrate operability of HPCI [BJ), the system was returned to service at 1131 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.303455e-4 months <br /> on 3/11/88, approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> after failure.

Cause of Event

Valve 23-MOV-14 failed to open when an open signal was provided by the logic system due to motor failure.

Examination of the DC motor revealed destruction of the commutator due to excessive i

current.

As part of post-work testing following replacement of the motor on valve 23-MOV-14, it was found that peak motor current for unseating the valve in the open direction with a differential pressure of approximately 1,000 psi was unacceptably high.

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Investigation of the high current revealed that the valve stem threads and stem nut threads did not have adequate lubrication.

l Following lubrication, the valve motor current tests were repeated during opening of the valve with a differential pressure of 1,000 psi.

A comparison of pre-lubrication and post-lubrication data revealed a peak valve motor unseating current reduction of approximately 50%.

Examination of maintenance records and maintenance procedures reveals that the valve stem of 23-MOV-14 had been repacked to correct a packing leak on 2/24/88.

The valve was tested on 2/25/88 with satisfactory results.

Review of Maintenance Procedure MP-59.9, titled "Valve Repacking", revealed that the procedure did not include instructions to determine if the valve stem threads and stem nut threads were adequately lubricated, i

Packing leaks can wash the lubricants off of the valve stem threads and stem nut thread surfaces.

l In consideration of the above, the cause of the event was determined to be a result of a procedural inadequacy which did not include evaluation of relubrication of the threads of the I

valve stem and stem nut.

Analysis of Event

HPCI [BJ] is designed to provide makeup water to the reactor in the event of a small Loss of Coolant Accident (LOCA) at a rate of 4,250 gpm with reactor pressure between 150 and 1,120 psig.

In the event of failure of the system (or the system being made unavailable for maintenance), the Automatic Depressurization System (ADS) [AD) provides protection for a small break LOCA.

ADS is designed to depressurice the reactor so that Low Pressure Coolant Injection (LPCI) [B0] and/or Low Pressure Core Spray (LPCS) [BM] can provide flow to the core for adequate core cooling.

LPCI [B0], LPCS [BM], and ADS [AD] were demonstrated to be fully operable as required by Technical Specification 4.5.C.1.a.

RCIC [BN] was also demonstrated to be fully operable except for the short time period noted in the event description above and in LER-88-002.

Accordingly, operation of the plant was within the limits of the Technical Specifications and Final Safety Analysis Report.

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Corrective Action

Immediate corrective action was to replace the failed motor and lubricate the valve stem and stem nut threads.

Long-term corrective action is to revise Maintenance Procedure MP-59.9 to require inspection, cleaning, and lubrication of the threads of the valve stem and stem nut during repacking of manual and power operated valves.

Additional Information

Failed component identification:

- Valve Motor Manufacturer:

Peerless-Porter

- Motor Model Number:

DS224B

- Manufacturer NPRD Code:

P269 LER-85-025,86-014, 86-011, and 86-003 are related events in which safety-related valve motors failed due to procedure deficiencies.

Revision 1 is submitted to provide clarification that the lubrication discussed refers to the threads of the valve stem and stem nut rather than the stem packing.

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1. > NewYorkPower 1st Authority May 13, 1988 JAFP-88-0455 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

REFERENCE:

DOCKET NO. 50-333 LICENSEE EVENT REPORT:

88-001-01

Dear Sir:

Enclosed please find referenced Licensee Event Report in accordance with 10 CFR 50.73, If there are any questions concerning this report, please contact Mr. W. Verne Childs at (315) 349-6305.

Very truly yours,

/

b C NVERSE 0

RADF RD RJC:WVC:lar cc:

USNRC, Region I (1)

INP0 Records Center, Atlanta, GA (1)

American Nuclear Insurers (1)

Internal Power Authority Distribution NRC Resident Inspector Document Control Center LER/0R File s