Information Notice 1989-88, Recent NRC-Sponsored Testing of Motor-Operated Valves

Recent NRC-Sponsored Testing of Motor-Operated Valves

ML031190060
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, Three Mile Island, 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	12/26/1989
From:	Rossi C Office of Nuclear Reactor Regulation
To:
References
IN-89-088, NUDOCS 8912190063
Download: ML031190060 (6)

• ' -*

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 December 26, 1989 NRC INFORMATION NOTICE NO. 89-88: RECENT NRC-SPONSORED TESTING OF

MOTOR-OPERATED VALVES

Addressees

.

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is intended to alert addressees to potential problems

identified as a result of recent NRC-sponsored testing of motor-operated valves

(MOVs). It is expected that recipients will review the information for appli- cability to their facilities and consider actions, as appropriate, to avoid

similar problems. However, suggestions contained in this information notice

do not constitute NRC requirements; therefore, no specific action or written

response is required.

Description of Circumstances

The NRC-sponsored blowdown testing of six motor-operated, flexible wedge gate

valves was recently completed. The test results are generally applicable to

any MOV that must open or close in a high flow, a high differential pressure, or a low subcooling situation.

The tests were sponsored by the NRC and conducted by the Idaho National Engi- neering Laboratory (INEL) at the Kraftwerk Union (KWU) facility in the Federal

Republic of Germany. The test results substantiated and expanded the concerns

that were previously identified with the operational capability of MOYs in high

flow, high differential, or low subcooling applications. These previous con- cerns were identified by INEL testing of two MOYs at the Wyle Labs facility in

.Huntsville, Alabama, and were reported in NUREG/CR-5406, "BWR Reactor Water

Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High

Energy Flow Interruption Test.' The expanded concerns now include(l) valves

supplied by four different manufacturers; (2)valves of two different sizes

(i.e., 6- and 10-inch valves); (3)water conditions, including several dif- ferent subcoolings and pressures; and (4) saturated steam conditions at several

different pressures.

Using experience gained from the Wyle tests, INEL adjusted the torque switches

to dbtain higher stem thrust values than would have been required using the

standard industry design formula. This was done to assure isolation of the

8912190063 z$- j

`1 I

IN 89-88 December 26, 1989 vast majority of flow through each valve during each blowdown. However, these

adjustments may have resulted in the stem thrust available during the blowdown

tests being above that currently being used (and possibly also above the me- chanical and electrical capabilities) for some currently installed valve and

motor operator assemblies. Even with the high settings used during the KWU

tests, several blowdowns resulted in closure of the flow area but did not

achieve full seating of the valve. During one such test, there was consider- able leakage through the valve after the valve stopped its closure stroke.

The KWU test results confirm the concern raised by the Wyle testing. The KWU

test data has not been fully evaluated at this time, but preliminary review

indicates that

1. The valves required stem thrusts well in excess of those predicted by the

industry design formula in use at the time of their design and manufacture.

2. The required stem thrust of the valves was not linearly dependent on the

differential pressure across the valve at the time of closure. This cir- cumstance precludes determination of the required stem thrust from data

that could be obtained under normal plant operating conditions.

3. The thrust at which torque switch trip occurs was not constant with respect

to the loading history of the valve. Many within the industry refer to

this as the 'rate of loading" phenomenon. However, the testing indicates

tha-ttheiremay be more involed than varifafons of the torque switch spring

pack's response time.

4. The stem factor (i.e., the ratio of the motor operator's output torque

to the valve's stem thrust) appears to be dependent on direction and

magnitude of the load being applied to the stem.

5. Several of the valves significantly damaged themselves during closure.

NRC plans to hold arinformation meeting to present the KWU test results for

Industry peer review. The meeting and a data report are planned for the early

part of 1990.

Related Generic Communications:

The general concern about the ability of MOYs to function properly when sub- jected to design-basis loadings has been previously addressed in NRC Bulletins

81-02, "Failure of Gate-Type Valves to Close Against Differential Pressure,"

and 85-03, "Motor-Operated Valve Common Mode Failures During Plant Transients

Due to Improper Switch Settings"; NRC Circular 77-01, "Malfunctions of

Limitorque Valve Operators"; and NRC Information Notices 81-31, "Failure

of Safety Injection Valves to Operate Against Differential Pressure," 85-50,

"Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock

& Wilcox,' and 89-61, "Failure of Borg-Warner Gate Valves to Close Against

Differential Pressure.n

, . IN 89-88'

December 26, 1989 In addition, Generic Letter 89-10, "Safely-Related Motor-Operated Valve Testing

and Surveillance," requested all addressees to develop a program for the testing, inspection, and maintenance of MOVs so as to provide the necessary assurance

that the MOYs will function when subjected to the design-basis conditions that

are to be considered during both normal operation and abnormal events In the

design basis of the plant.

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

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

technical contacts listed below or the appropriate NRR project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Hugh W. Woods, RES

(301) 492-3908 Richard J. Kiessel, NRR

(301) 492-1154 Attachment: List of Recently Issued NRC Information Notices

- - X

IN 89-88 December 26, 1989 In addition, Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing

and Surveillance," requested all addressees to develop a program for the testing, inspection, and maintenance of MOVs so as to provide the necessary assurance

that the MOVs will function when subjected to the design-basis conditions that

are to be considered during both normal operation and abnormal events in the

design basis of the plant.

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

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

technical contacts listed below or the appropriate NRR project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Hugh W. Woods, RES

(301) 492-3908 Richard J. Kiessel, NRR

(301) 492-1154 Attachment: List of Recently Issued NRC Information Notices

• Draft IN forwarded to OGCB by WMinners memo 11/20/89 Document Name: NRC SPONSORED MOV TEST RESULTS

• SEE PREVIOUS CONCURRENCES

• C/OGCB:DOEA:NRR

CHBerlinger

'-12 //9 12/18/89

• OGCB:DOEA:NRR *D/DSIR:RES *C/EMEB:DET:NRR*D/DET:NRR *RPB:ARM

RJKiessel IMI nners LBMarsh JERichardson TechEd

11/30/89 11/20/89 12/06/89 12/06/89 12/11/89

IN 89-xx

December xx, 1989 In addition, Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing

and Surveillance," requested all addressees to develop a program for the

testing, Inspection, and maintenance of MOYs so as to provide the necessary

assurance that the MOVs will function when subjected to the design-basis

conditions that are to be considered during both normal operation and abnormal

events in the design basis of the plant.

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

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

technical contacts listed below or the appropriate NRR project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Hugh W. Woods, RES

(301) 492-3908 Richard J. Kiessel, NRR

(301) 492-1154 Attachment: List of Recently Issued NRC Information Notices

• Draft IN forwarded to OGCB by WMinners memo 11/20/89 Document Name: NRC SPONSORED MOV TEST RESULTS

• SEE PREVIOUS CONCURRENCES

D/DOEA:NRR

cX 3 C/OGCB:DOEA:NRR

CERossi CHBerjinger

12/ /89 12/1 '/89

• OGCB:DOEA:NRR *D/DSIR:RES *C/EMEB:DET:NRR*D/DET:NRR *RPB:ARM

RJKiessel WMinners LBMarsh JERichardson TechEd

11/30/89 11/20/89 12/06/89 12/06/89 12/1//89

IN 89-xx

December xx, 1989 Related Generic Communications:

The general concern of the ability of MOYs to function properly when subjected

to design basis loadings has been previously addressed in NRC Bulletins 81-02,

"Failure of Gate Type Valves to Close Against Differential Pressure," and

85-03, "Motor-Operated Valve Common Mode Failures During Plant Transients Due

to improper Switch Settings;" NRC Circular 77-01, *Malfunctions of Limltorque

Valve Operators;" and NRC Information Notices 81-31, 'Failure of Safety Injec- tion Valves to Operate Against Ditterentia ressure," 85-50, *Complete Loss of

Main and Auxiliary Feedwater at a PWR Designed by Babco-k rWilcox," and 89-61,

"Failure of Borg-Warner Gate Valves to Close Against Differential Pressure."

In addition, Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing

and Surveillance," requested all addressees to develop a program to provide for

the testing, inspection, and maintenance of MOVs so as to provide the necessary

assurance that they will function when subjected to the design basis conditions

that are to be considered during both normal operation and abnormal events

within the design basis of the plant.

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

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

technical contacts listed below or the appropriate NRR project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Hugh W. Woods, RES

(301) 492-3908 Richard J. Kiessel, NRR

(301) 492-1154 Attachment: List of Recently Issued NRC Information Notices

• Draft IN forwarded to OGCB by WMinners memo 11/20/89 Document Name: NRC SPONSORED MOV TEST RESULTS

D/DOEA:NRR C/OGCB:DOEA:NRR

CERossi CHBerlinger

11/ /89 11/ /89 OGCB E -N R *D/DSIR:RES /E'MEB:DET:NRR D/DET:NRR.pV RPB:ARM

RJKiessel WMinners LBMarsh JERichard~on TechEd

11/je /89 11/20/89 11l(e /89 IZ////89

1>//89 d1 MNA5 f~