Information Notice 1986-65, Malfunctions of ITT Barton Model 580 Series Switches During Requalification Testing

Malfunctions of ITT Barton Model 580 Series Switches During Requalification Testing

ML031250074
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, Skagit, Marble Hill
Issue date:	08/14/1986
Revision:	0
From:	Jordan E L NRC/IE
To:
References
IN-86-065, NUDOCS 8608120032
Download: ML031250074 (3)

u s SSINS, No.: 6835LE CALLIN 86-65UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555August 14, 1986IE INFORMATION NOTICE NO. 86-65: MALFUNCTIONS OF ITT BARTON MODEL 580 SERIESSWITCHES DURING REQUALIFICATION TESTING

Addressees

All nuclear power reactor facilities holding an operating license or aconstruction permit.

Purpose

This notice is provided to alert recipients to a potentially significant safetyproblem pertaining to malfunctions of ITT Barton Model 580 Series indicatingswitches under accident conditions. It is expected that recipients will reviewthe information for applicability to their facilities and consider actions, ifappropriate, to preclude malfunctions occurring at their facilities. However,suggestions contained in this notice do not constitute NRC requirements;therefore, no specific action or written response is required.Description of Problem:On April 14, 1986, NRC was notified by ITT Barton Instruments Company of thedefect in accordance with 10 CFR Part 21. According to the report, duringrequalification testing of ITT Barton Model 580 Series indicating switchesunder loss-of-coolant accident conditions, switch malfunctions occurred whenthe chamber temperature was raised to 3400F. The symptoms of the malfunctionswere:-In three of the five instruments tested, one or both of the switchesfailed to operate (no change in switch state) when input pressure tothe instrument was varied.-Switch set-point shift in excess of the allowable 10 percent occurredon two of the instruments.When the chamber temperature was lowered to room ambient, all of the switcheschanged state when input pressure was varied; however, the switch set-pointshifts which occurred at temperature were permanent.The initial report indicated that the failure was due to a specific componentused, a Honeywell Snap-Acting Switch, part number 11SM 403. A subsequentreport indicated that, as a result of additional testing, it was determinedthat there is also a deflection of the instrument case which affects theposition of the snap switch and the setpoint. Furthermore, the deflection canresult in failure of case seal integrity.8608120032

, .-.. v .IN 86-65August 14, 1986 ITT Barton has indicated that they are evaluating case/seal redesigns and arealistic date for completion of retesting would be April 15, 1987.In previous tests, the instruments performed successfully when subjected to 2200Fafter aging, irradiation, and seismic testing.This information notice is being issued to ensure that all nuclear power plantend-users have been notified of this problem.A contact at ITT Barton Instruments Company knowledgeable of this problem is:John P. DoyonManager, Sales and Service(818) 961-2547 extension 456No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.D corDivisio f Emergency Preparednessand Ehi neering ResponseOffice of Inspection and EnforcementTechnical Contacts: Eric Weiss, IE(301) 492-9005Pentti Koutaniemi, IE(301) 492-9428

Attachments:

List of Recently Issued IE Information Notices Attachment 1IN 86-65August 14, 1986LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue Issued to86-64Deficiencies In UpgradePrograms For Plant EmergencyOperating ProceduresLoss Of Safety InjectionCapability8/14/868/6/86All power reactorfacilities holdingan OL or CPAll PWR facilitiesholding an OL or CP86-6386-62Potential Problems In West-inghouse Molded Case CircuitBreakers Equipped With AShunt TripFailure Of Auxiliary Feed-water Manual Isolated Valve7i31/867/28/86All power reactorfacilities holdingan OL or CPAll power reactorfacilities holdinga CP086-6186-6086-31Sup. 186-5986-5886-57Unanalyzed Post-LOCA ReleasePathsUnauthorized Transfer AndLoss Of Control Of IndustrialNuclear GaugesIncreased Monitoring OfCertain Patients WithImplanted Coratomic, Inc.Model C-100 and C-101Nuclear-Powered CardiacPacemakersDropped Fuel AssemblyOperating Problems WithSolenoid Operated Valves AtNuclear Power PlantsReliability Of Main SteamSafety Valves7/28/867/14/867/14/867/11/867/11/867/10/86All power reactorfacilities holdingan OL or CPAll NRC generallicensees that possessand use industrialnuclear gaugesAll NRC licenseesauthorized to usenuclear-poweredcardiac pacemakersAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll PWR facilitiesholding an OL or CP86-56OL = Operating LicenseCP = Construction Permit