Information Notice 1991-83, Solenoid-Operated Valve Failures Resulted in Turbine Overspeed

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Solenoid-Operated Valve Failures Resulted in Turbine Overspeed
ML031190391
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  Entergy icon.png
Issue date: 12/20/1991
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-91-083, NUDOCS 9112160318
Download: ML031190391 (11)


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UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

December 20, 1991

NRC INFORMATION NOTICE 91-83: SOLENOID-OPERATED VALVE FAILURES RESULTED

IN TURBINE OVERSPEED

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice

to alert addressees to turbine overspeed problems and turbine trip failures

resulting from the failures of multiple solenoid-operated valves (SOVs). It is

expected that recipients will review the information for applicability to their

facilities and consider actions, as appropriate, to avoid similar problems.

However, suggestions contained in this information notice are not NRC require- ments; therefore, no specific action or written response is required.

Background

Westinghouse turbines are tripped using a combination of electro-hydraulic

control (EHC) fluid and auto-stop oil (Attachment 1).

In the electro-hydraulic

portion, SOVs dump the fluid to the EHC sump, causing the throttle valves, reheat stop valves, intercept valves, and the governor valves to shut, stopping

the flow of steam to the turbine.

Failure of the SOVs in the EHC system to

open could lead to the turbine overspeeding. Several events have occurred in

the industry that involved the failure of SOVs that must operate for turbine

emergency trip and overspeed protection.

The consequences of these failures

have varied according to the initiating event and the type of SOV failure.

These failures suggest that there are weaknesses in the preventive maintenance

and testing of these SOVs.

Description of Circumstances

On November 9, 1991, Unit 2 of the Salem Nuclear Generating'Station sustained

severe damage to its turbine and generator. The event occurred while'the

Public Service Electric and Gas Company (the licensee) was conducting routine

turbine testing at 100-percent power. The licensee bypassed the turbine's

auto-stop oil trip mechanism in accordance with the test procedure. During the

test, an oil pressure perturbation occurred in the auto-stop trip system, the

exact cause of which is yet to be determined.

This caused the interface valve

to open and thereby depressurized the EHC fluid.

Both the turbine and the

reactor tripped and, as expected, all turbine stop valves closed.

However, the

emergency trip solenoid valve failed to open upon receiving the trip signal.

9112160318

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,IN 91-83

-,December 20, 1991 When the auto-stop oil repressurized, the interface valve closed, and all

turbine stop valves reopened allowing steam flow into the turbine.

As

designed, the generator output breakers had opened upon receiving the reactor

trip signal, so the steam flow through the unloaded turbine caused the turbine

to overspeed.

Both overspeed protection controller (OPC) solenoid valves

failed to open preventing the governor valves and intercept valves from closing

properly. The turbine continued to overspeed to an estimated 160-percent of

rated speed.

Operators observed increasing noise and vibration from the

turbine and a fire at the generator.

The low pressure turbine blades penetra- ted the turbine shroud.

The overspeed resulted in severe damage to the low

pressure turbine, the generator exciter unit, the condenser, and associated

support structures, systems, and components.

Discussion

The staff sent an augmented inspection team (AIT)

to the site to investigate

the event.

The AIT concluded that the proximate cause of the event was the

failure of the emergency trip solenoid valve and both overspeed protection

controller solenoid valves to open when energized. The specific failure

mechanisms of the Parker-Hannifin SOVs are yet to be determined, but prelimi- nary analysis indicated that the pilot valve assembly in each solenoid unit was

mechanically bound sufficiently to prevent movement. Other previous failures

of these valves in the industry have also been attributed to mechanical bind- ing, corrosion, and worn or pinched elastomeric parts.

Several precursory factors contributed to the event. The licensee for the

Salem Nuclear Generating Station has no preventive maintenance program for any

of these three SOVs.

The surveillance and operational testing of the turbine

trip and overspeed circuits does not specifically verify the proper hydraulic

functioning of each SOY independently.

Further, information concerning previ- ous SOV failures has not been well disseminated.

The licensee had two earlier indications of problems with these SOVs.

Similar

valves on Salem Unit 1 required replacement, yet the licensee had not effec- tively verified the operability of the SOYs in Unit 2. Another indication

occurred during a startup in October 1991.

The OPC solenoid valves failed to

open when a test of the system was performed.

The licensee was required to

verify proper OPC operation by closing the intercept valves when the OPC test

switch was activated. The intercept valves did not close, indicating a possi- ble malfunction of both of the OPC solenoid valves. The results were

apparently misinterpreted, leading management to believe a procedure problem

existed, rather than an equipment problem.

The licensee continued the startup

without further diagnosis and resolution.

The staff will include more details

of this event in NRC Inspection Report 50-311/91-81 when issued.

Previous Events

The following previous events involved failures of SOVs in the turbine trip

system during reactor trip events:

On April 6, 1985, at the R. E. Ginna Nuclear Power Plant, the turbine failed to

trip automatically following a reactor trip because of mechanical binding of

the emergency trip solenoid valve.

-

IN 91-83 December 20, 1991 On February 28, 1988, at the Crystal River Plant, Unit 3, the turbine failed to

trip automatically following a reactor trip because of a faulty emergency trip

solenoid valve.

On September 10, 1990, at Salem, Unit 1, the reactor tripped because of a steam

generator water level transient caused by a spurious overspeed signal.

Mechan- ical binding prevented the OPC solenoid valves from functioning.

On September 29, 1990, at Ginna, the reactor tripped because of personnel

error, but mechanical binding prevented the turbine emergency trip solenoid

valve from functioning.

These events indicate that proper maintenance and operability testing of both

the emergency trip solenoid valve and the OPC solenoid valves is prudent.

Related Generic Communications

The staff issued Generic Letter 91-15, "Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors," to distribute NUREG-1275, Volume 6, to industry. This document provided the staff's analysis of recent

U.S. light water reactor experience (primarily 1984-1989) with SOYs.

Appendix A of NUREG-1275, Volume 6, cited similar SOV failures at four other

plants. The staff noted the susceptibility of SOVs to common-mode failures.

The staff found that most SOVs cannot tolerate contaminants, need preventative

maintenance or periodic replacement, and have a propensity for rapid aging and

deterioration when subjected to elevated temperatures. The staff provided

recommendations to aid in preventing common-mode SOV failures.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact one

of the technical contacts listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Charles E. Rossi, Dir

or

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical contacts:

John White, Region I

(215) 337-5114

David Gamberoni, NRR

(301) 504-1171 Attachments:

1. Westinghouse Electro-Hydraulic Control System

2. List of Recently Issued NRC Information Notices

II

EMERGENCY TRIP

SOLENOID VALVE

TO EHC

SUMP

C

...... I................

AUTO-STOP OIL SYSTEM

TO En-IC

SUIMP

INTERFA'

VALVE

c

ELECTRO-HYORAULIC CONTROL FLUID

................

AUTO-STOP OIL

TO EHC

SUAJP

OVERSPEED PROTECTION

CONTROLLER SOLENOID

VALVES

WESTINGHOUSE ELECTRO-HYDRAULIC CONTROL SYSTEM

(D Z r'

Gm

n rt

(D 9 I'

03 oD

co B a

0 11 LO (D

Ft M

o

o_

_

'\\Attachment 2 IN 91-83

December 20, 1991 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

91-18, Supp. 1

91-82

91-81

91-80

91-79 High-Energy Piping Failures

Caused by Wall Thinning

Problems with Diaphragms

in Safety-Related Tanks

Switchyard Problems that

Contribute to Loss of

Offsite Power

Failure of Anchor

Head Threads on Post-

Tensioning System During

Surveillance Inspection

Deficiencies in the

Procedures for Instal- ling Thermo-Lag Fire

Barrier Materials

Potential for Spent

Fuel Pool Draindown

Status Indication of

Control Power for

Circuit Breakers Used

in Safety-Related Appli- cations

Substandard, Refur- bished Potter & Brum- field Relays Repre- sented as New

Shift Staffing at

Nuclear Power Plants

12/18/91

All holders of OLs or CPs

for nuclear power reactors.

12/18/91

All holders of OLs or CPs

for nuclear power reactors.

12/16/91

All holders of OLs or CPs

for nuclear power reactors.

12/11/91

All holders of OLs or CPs

for nuclear power reactors.

12/06/91

All holders of OLs or CPs

for nuclear power reactors.

11/29/91

All holders of OLs or CPs

for nuclear power reactors.

11/28/91

All holders of OLs or CPs

for nuclear power reactors.

11/27/91

All holders of OLs or CPs

for nuclear power reactors.

11/26/91

All holders of OLs or CPs

for nuclear power reactors.

88-92, Supp. 1

91-78

90-57, Supp. 1

91-77 OL = Operating License

CP = Construction Permit

HE

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

FIRST CLASS MAIL

POSTAGE 6 FEES PAID

USNRC

PERMIT No 0-57 I

II

IN 91-83 December 20, 1991 On February 28, 1988, at the Crystal River Plant, Unit 3, the turbine failed to

trip automatically following a reactor trip because of a faulty emergency trip

solenoid valve.

On September 10, 1990, at Salem, Unit 1, the reactor tripped because of a steam

generator water level transient caused by a spurious overspeed signal. Mechan- ical binding prevented the OPC solenoid valves from functioning.

On September 29, 1990, at Ginna, the reactor tripped because of personnel

error, but mechanical binding prevented the turbine emergency trip solenoid

valve from functioning.

These events indicate that proper maintenance and operability testing of both

the emergency trip solenoid valve and the OPC solenoid valves is prudent.

Related Generic Communications

The staff issued Generic Letter 91-15, "Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors," to distribute NUREG-1275, Volume 6, to industry. This document provided the staff's analysis of recent

U.S. light water reactor experience (primarily 1984-1989) with SOVs.

Appendix A of NUREG-1275, Volume 6, cited similar SOV failures at four other

plants. The staff noted the susceptibility of SOVs to common-mode failures.

The staff found that most SOVs cannot tolerate contaminants, need preventative

maintenance or periodic replacement, and have a propensity for rapid aging and

deterioration when subjected to elevated temperatures. The staff provided

recommendations to aid in preventing common-mode SOV failures.

This information notice requires no specific action or written response.

If

you have any questions about the information in this notice, please contact one

of the technical contacts listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Charles E. Rossi, Direc r

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical contacts:

John White, Region I

(215) 337-5114

David Gamberoni, NRR

(301) 504-1171 Attachments:

1. Westinghouse Electro-Hydraulic Control System

2. List of Recently Issued NRC Information Notices

Document Name: IN 91-83

  • SEE PREVIOUS CONCURRENCES
  • REGION I
  • EAB:DOEA:NRR
  • SC:REGION I
  • SC:EAB:DOEA:NRR

IMoghissi

DGamberoni

JWhite

DFischer

12/05/91

12/09/91

12/10/91

12/13/91

  • C.-AB DOEA:NRR *Tech Ed
  • C:OGCB:DOEA:NRR D:DOEA:NR eI4 g

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12/13/91

12/10/91

12/13/91

12,y4,91

IN 91-XX

December xx, 1991 On September 10, 1990, at Salem, Unit 1, the reactor tripped because of a steam

generator water level transient caused by a spurious overspeed signal.

Mechanical

binding prevented the OPC solenoid valves from functioning.

On September 29, 1990, at Ginna, the reactor tripped because of personnel

error, but mechanical binding prevented the turbine emergency trip solenoid

valve from functioning.

These events indicate that proper maintenance and operability testing of both

the emergency trip solenoid valve and the OPC solenoid valves is prudent.

Related Generic Communications

The staff issued Generic Letter 91-15, "Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors," to distribute NUREG-1275 to

industry. This document provided the staff's analysis of recent U.S. light

water reactor experience (primarily 1984-1989) with SOVs. The staff found that

most SOVs cannot tolerate contaminants, need preventative maintenance or

periodic replacement, and have a propensity for rapid aging and deterioration

when subjected to elevated temperatures. The staff provided recommendations to

aid in preventing further SOV problems.

This information notice requires no specific action or written response.

If

you have any questions about the information in this notice, please contact one

of the technical contacts listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical contacts: John White, Region I

(215) 337-5114

David Gamberoni, NRR

(301) 504-1171 Attachments:

1. Westinghouse Electro-Hydraulic Control System

2. List of Recently Issued NRC Information Notices

OFC : *REGION I

*EAB:DOEA:NRR
  • SC:REGION I
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DATE : 1d /i3/91

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  • SEE PREVIOUS CONCURRENCES

Document Name IN91/SALEM

-3-

9/10/90 At Salem, Unit 1, the reactor tripped due to a steam generator water

level transient caused by a spurious overspeed signal.

The OPC solenoid valves

did not function due to mechanical binding.

9/29/90 At Ginna, the reactor tripped due to personnel error, but the turbine

emergency trip solenoid valve failed to function due to mechanical binding.

It is apparent from these events that proper maintenance and operability

testing of both the ET solenoid valve and the OPC solenoid valves is prudent.

Related Generic Communications

NUREG-1275, Operating Experience Feedback Report - Solenoid-Operated Valve

Problems, which was distributed to industry via Generic Letter 91-15, analyzed

recent U.S. light-water reactor experience (primarily 1984-1989) with solenoid- operated valves (SOVs). It was found that most SOVs cannot tolerate contaminants, need preventative maintenance or periodic replacement, and have a propensity

for rapid aging and deterioration when subjected to elevated temperatures.

Various recommendations were provided to aid in the prevention of further SOV

problems.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact one

of the technical contacts listed below or the appropriate Office of Nuclear

Reactor Regulation project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical contacts: John White, Region I

(215) 337-5114

David Gamberoni, NRR

(301) 492-1171 Attachments:

1. List of Recently Issued NRC Information Notices

OFC :

REGION I

EAB:DOEA:NRR

SC:REGION I : SC:EAB:DOEA:NRR

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DATE:

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/ /91

/ /91 OFC : C:EAB:DOEA:NRR :

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C:OGCB:DOEA:NRR : D:DOEA:NRR

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9/1/g10 At Salem, Unit 1, the reactor tripped due to a

levtI transient caused by A spurious overspeed signal.

did not function due to mechanical binding, The:OPC $07eno

atves

9/29/90 At ronnh

the reactor tripped due to personnel error, but

emgen"y trip So50nojd V8lve failed to function due to mechanical the turbine

bindinn.

It Is apparent from thes *vents that proper maintenance and operability

testing of both the ET solenoid valve and the OPC Solenoid valves Is prudent&

Related Generic Commnunicctiong

NORO-1275 ,perating Ex erieng Feedback eportave

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wh c was

strbuzec onustry via gener

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recent US. light-water reactor experience (primarily 1984.198g) WitY solenoid.

operated vatves (SOVi)t It WAs found that most SOYs cannot tolerate contaminants, need preventativ maintenance or periodic replacement

and have a propensity

for rapid aging and deterioration when subjected to elevated tomPeratures.

Various raconmendatlons were provided to aid in the prevention of further $01 problems.

This Information notice requires no 8pecfic Action or written response.

If

you have any questions about the Information in

this notice please contact one

of the technical contacts listed below or the appropriate Of ice of Nuclear

Reactor Regulition project manager, Charl'es £, Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical contacts:

John White

Region I

(215) 337-1114 n

' (ba\\id Gamberoni, NRR

(301) 492-1171

Attachmentst

1. List of Recently Issued NRC Information Notices

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At Salem, Unit 1, the reactor tripped due to a steam enerator water

level transient caused by a spurious overspeed signal. The DPC solenoid valves

did not function due to mechanical binding.

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At Ginna the reactor tripped due to personnel error, but the turbine

emergency trip soienoid valve failed to function due to mechanical binding.

It is apparent from these events that proper maintenance and operability

testing of both the ET solenoid valve and the OPC solenoid valves is prudent.

Related Generic Communications

NUREG-1275, OperatingExperience Feedback Report -

lenoid-Operated Valve

Problems, wh-lc

was d1strlbuteto industry

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recent US. light-water reactor experience (primarily 1984-1989) with solenoid- operated valves (SOYs), It was found that most $0SY

cannot tolerate contaminants, need preventative maintenance or periodic replacement and have 4 propensity

for rapid aging and deterioration when subjected to *e1vated temnperatures.

Various recommendations were provided to aid in the prevention of further SOY

problems.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice please contact one

of the technical contacts listed below or the appropriate Office of Nuclear

Reactor Regulation project manager.

Charles E. Rossi, Director

Division of 0 eratlonal Events Assessment

Office of Nuc ear Reactor Regulation

Technical contacts: 4ohn White

Region I

(215) 337.h114

David Gamberoni, NRA

(301) 492-1171

Attachmentss

1. List of Recently Issued NRC Informatlon Notices

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