Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves

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Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves
ML031060064
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: 05/21/1996
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-96-030, NUDOCS 9605160311
Download: ML031060064 (6)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

May 21, 1996

NRC INFORMATION NOTICE 96-30:

INACCURACY OF DIAGNOSTIC EQUIPMENT FOR

MOTOR-OPERATED BUTTERFLY VALVES

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 the increased inaccuracy of certain diagnostic

equipment for measuring torque when operating butterfly valves.

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 requirements; therefore, no specific action or written response is

required.

Background

In Generic Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and

Surveillance," the NRC staff requested that nuclear power plant licensees and

construction permit holders verify the design-basis capability of their

safety-related motor-operated valves (MOVs). As an integral part of their MOV

programs, most licensees rely on diagnostic equipment to provide information

on the torque and thrust required to open and close valves, and the amount of

torque and thrust delivered by the motor actuator.

Various types of MOV

diagnostic equipment are available to estimate torque and thrust for gate, globe, and butterfly valves.

Because some licensees make decisions regarding

the operability of safety-related MOVs on the basis of diagnostic equipment

readings, inaccuracies in MOV diagnostic equipment can adversely affect the

safe operation of a nuclear power plant.

On June 28, 1993, the NRC staff issued Supplement 5 to GL 89-10, "Inaccuracy

of Motor-Operated Valve Diagnostic Equipment," which discussed then-recent

information on the inaccuracy of MOV diagnostic equipment that raised a

generic concern regarding the reliability of data provided by certain MOV

diagnostic equipment. In Supplement 5 to GL 89-10, the staff stated that the

MOV Users' Group of nuclear power plant licensees had released a report

indicating that the MOV diagnostic equipment that relied on spring pack

displacement to estimate stem thrust in gate and globe valves was less

accurate than its vendors claimed.

The staff also discussed greater-than- assumed inaccuracy of MOV diagnostic equipment that relies on valve yoke

strain to estimate stem thrust in gate and globe valves. As a result of the

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IN 96-30

May 21, 1996 inaccuracy concerns for MOV diagnostic equipment used with gate and globe

valves, the staff (in Supplement 5 to GL 89-10) asked licensees to reexamine

their MOV programs and to report measures taken or planned to account for

uncertainties in properly setting valve operating thrust to ensure

operability. The staff stated that licensees should not limit their

evaluations to only the specific examples of increased inaccuracy of MOY

diagnostic equipment discussed in Supplement 5, but should consider any

information reasonably available to them.

The staff reviewed the licensees'

responses to Supplement 5 to GL 89-10 and conducted additional evaluations

during GL 89-10 inspections.

DescriDtion of Circumstances

ITI MOVATS Incorporated developed the Butterfly Analysis and Review Test

(BART) System as a method for determining the torque output of Limitorque HBC

gear boxes equipped with Limitorque motor actuators on butterfly valves. In

the BART System, a load cell is mounted between the HBC gearbox housing and

the HBC worm gear. Actuator torque is determined by multiplying the force

resisted in the load cell by the length of the moment arm.

In MOVATS Users

Technical Notice (MUTN) 96-01 (dated April 1996), ITI MOVATS stated that the

inaccuracy of the BART System had been considered to be equal to the

inaccuracy of the load cell (plus or minus the sum of 2 percent of reading and

0.4 percent of full scale).

However, recent observations and questions

concerning the performance of the BART System under field conditions led ITI

MOVATS to perform testing to determine the inaccuracy of the system.

In MUTN

96-01, ITI MOVATS reports that its test program revealed the inaccuracy of the

various fixture sizes of the BART System to be as follows:

Fixture Size

Inaccuracy

HOBC, HIBC, H2BC

+(14.0% of reading + 5.2% of full scale)

-( 4.0% of reading + 1.0% of full scale)

H3BC

+(14.0% of reading + 746 foot-pounds)

-(14.0% of reading + 311 foot-pounds)

ITI MOVATS notes that the effects of both torque switch repeatability and HBC

gear box repeatability are included in the new inaccuracy values.

The vendor

also states that these inaccuracy values are only valid for torque loads

between 20 percent and 100 percent of the full-load rating of the HBC gear

box.

ITI MOVATS offers no guidance in MUTN 96-01 for predicting inaccuracy

outside of this load range.

Discussion

The BART System is typically used to determine torque output at torque switch

trip when operating motor-operated butterfly valves under static (no flow)

conditions.

Overprediction of actual torque at the torque switch trip could

result in the motor actuator failing to fully stroke the valve under dynamic

flow conditions.

Underprediction of actual torque at the torque switch trip

could result in exceeding actuator or valve structural limits, or degraded-

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IN 96-30

May 21, 1996 voltage motor capability. Depending on the use of the diagnostic system and

the control circuitry of the motor actuator, the operation of limit-switch- controlled butterfly valves might also be adversely affected by the increased

inaccuracy of the BART System.

In MUTN 96-01, ITI MOVATS recommends that all quarter-turn valves that have

been set up using the BART System be reevaluated using the revised values for

inaccuracy. The vendor also suggests that, when using the BART System of

sizes HOBC, HIBC, and H2BC, the open and close strokes should begin with the

load cell in the relaxed position to simplify determination of zero load.

This information notice is being issued because valves that were marginally

operable assuming the old inaccuracy may be inoperable based on the new

inaccuracy.

Related Generic Communications

The staff has alerted the industry to concerns about inaccuracy regarding

other MOV diagnostic equipment.

For example, the staff issued Information

Notice (IN) 92-23, "Results of Validation Testing of Motor-Operated Valve

Diagnostic Equipment;" IN 93-01, "Accuracy of Motor-Operated Valve Diagnostic

Equipment Manufactured by Liberty Technologies;" and IN 94-18, "Accuracy of

Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to

GL 89-10)."

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.

~Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: T. Scarbrough, NRR

(301) 415-2794 Internet:tgs@nrc.gov

M. Runyan, RIV

(817) 860-8142 Internet:mfr@nrc.gov

Attachment:

List of Recently Issued NRC Information Notices

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Attachment

IN 96-30

May 21, 1996 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

96-29

96-28

96-27

96-26

96-25

96-24

96-23

96-22

Requirements in 10 CFR

Part 21 for Reporting and

Evaluating Software Errors

Suggested Guidance Relating

to Development and Imple- mentation of Corrective

Action

Potential Clogging of High

Pressure Safety Injection

Throttle Valves During

Recirculation

Recent Problems with Over- head Cranes

Transversing In-Core Probe

Overwithdrawn at LaSalle

County Station, Unit 1 Preconditioning of Molded-

Case Circuit Breakers

Before Surveillance Testing

Fires in Emergency Diesel

Generator Exciters During

Operation Following Unde- tected Fuse Blowing

Improper Equipment Set- tings Due to the Use of

Nontemperature-Compensated

Test Equipment

05/20/96

05/01/96

05/01/96

04/30/96

04/30/96

04/25/96

04/22/96

04/11/96

All holders of OLs or CPs

for nuclear power reactors

All material and fuel cycle

licensees

All holders of OLs or CPs

for pressurized water

reactors

All holders of OLs or CPs

for nuclear power reactors

All holders of OLs or CPs

for nuclear power reactors

All holders of OLs or CPs

for nuclear power reactors

All holders of OLs or CPs

for nuclear power reactors

All holders of OLs or CPs

for nuclear power reactors

OL = Operating License

CP - Construction Permit

i

IN 96-30

May 21, 1996 voltage motor capability. Depending on the use of the diagnostic system and

the control circuitry of the motor actuator, the operation of limit-switch- controlled butterfly valves might also be adversely affected by the increased

inaccuracy of the BART System.

In MUTN 96-01, ITI MOVATS recommends that all quarter-turn valves that have

been set up using the BART System be reevaluated using the revised values for

inaccuracy. The vendor also suggests that, when using the BART System of

sizes HOBC, HIBC, and H2BC, the open and close strokes should begin with the

load cell in the relaxed position to simplify determination of zero load.

This information notice is being issued because valves that were marginally

operable assuming the old inaccuracy may be inoperable based on the new

inaccuracy.

Related Generic Communications

The staff has alerted the industry to concerns about inaccuracy regarding

other MOV diagnostic equipment.

For example, the staff issued Information

Notice (IN) 92-23, "Results of Validation Testing of Motor-Operated Valve

Diagnostic Equipment;" IN 93-01, "Accuracy of Motor-Operated Valve Diagnostic

Equipment Manufactured by Liberty Technologies;" and IN 94-18, "Accuracy of

Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to

GL 89-10)."

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.

Oriinal signed by

W L GoWd

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: T. Scarbrough, NRR

(301) 415-2794 Internet:tgs@nrc.gov

M. Runyan, RIV

(817) 860-8142 Internet:mfr@nrc.gov

Attachment:

List of Recently Issued NRC Information Notices

Tech Editor has reviewed and concurred on 03/02/96 See previous concurrence

DOCUMENT NAME: 96-30.IN

OFC

RGN-IV/DRS

C/EMEB:DE

C/PECB:DRPM

NAME

MRunyan*

RWessman*

AChaffee*for

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DATE

05/06/96

05/06/96

05/06/96/RLD

_-//,6/96

[OFFICIAL RECORD COPY]

/

IN 96-XX

May XX, 1996

Page 3 of X

In MUTN 96-01, ITI MOVATS recommends that all quarter-turn valves that have

been set up using the BART System be reevaluated using the revised values for

inaccuracy.

The vendor also suggests that, when using the BART System of

sizes HOBC, HIBC, and H2BC, the open and close strokes should begin with the

load cell in the relaxed position to simplify determination of zero load.

Related Generic Communications

The staff has alerted the industry to concerns about inaccuracy regarding

other MOV diagnostic equipment.

For example, the staff issued Information

Notice (IN) 92-23, "Results of Validation Testing of Motor-Operated Valve

Diagnostic Equipment"; IN 93-01, "Accuracy of Motor-Operated Valve Diagnostic

Equipment Manufactured by Liberty Technologies"; and IN 94-18, 'Accuracy of

Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to

GL 89-10)."

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.

Brian K. Grimes, Acting Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: T. Scarbrough, NRR

(301) 415-2794 Internet:tgs@nrc.gov

M. Runyan, RIV

(817) 860-8142 Internet:mfr@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\\TAG\\MOVIN.TS3 A

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NAME MRunyan1

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DATE

(//96 /

5/9 /96

</C/96

[OFFICIAL RECORD COPY]