Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation

Problems with General Electric Type Cr124 Overload Relay Ambient Compensation

ML031070040
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	06/07/1994
Revision:	0
From:	Grimes B K Office of Nuclear Reactor Regulation
To:
References
IN-94-041, NUDOCS 9406010125
Download: ML031070040 (10)

UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555June 7, 1994NRC INFORMATION NOTICE 94-41: PROBLEMS WITH GENERAL ELECTRIC TYPE CR124OVERLOAD RELAY AMBIENT COMPENSATION

Addressees

All holders of operating licenses or construction permits for nuclear powerreactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the potential for out-of-tolerance ambientcompensation in certain configurations of General Electric (GE) Type CR124overload relays. It is expected that recipients will review the informationfor applicability to their facilities and consider actions, as appropriate, toavoid similai'--problems. However, suggestions contained in this informationnotice are not NRC requirements; therefore, no specific action or writtenresponse is required.

Description of Circumstances

After some field test failures, in which several Type CR124 overload relaysexhibited out-of-tolerance trip times, the relays were returned to themanufacturer, GE Electrical Distribution and Control (ED&C). GE ED&Cdiscovered that on relay models CR124K028, K128, L028, and L128, manufacturedbefore October 1990, many of the ambient temperature-compensating bimetalelements (sometimes called ambient compensating springs) had been installedupside down because of a problem with the marking of the elements. In thiscondition, the incorrectly installed element can adversely affect the triptiming of the relay. These overload relays are typically used in conjunctionwith starters or motor controllers, many of which may serve safety-relatedloads. In April 1991, GE Nuclear Energy (GE NE) issued a "Germane to Safety"letter to all boiling water reactor customers and certain other customersconcerning the relays. However, the NRC has learned that other licensees mayalso be affected.DiscussionThe ambient temperature compensating bimetal element or spring is intended toadjust the trip forces inside the relay so that the trip time as a function ofoverload current is consistent with the design characteristic curves over awide range of ambient temperatures. According to GE, the improperly installedambient compensating bimetals will permit the overload relays to workcorrectly within a temperature range of 15-200C [59-68*F]. However, at lowertemperatures, i.e., 0-15'C [32-59°F], the ambient compensation would cause9406010125 PC tE No '("C- e CT q -ot q Lslot sha 'M A IN 94-41June 7, 1994 trip times above published specifications (time-current curves). At highertemperatures, i.e., 20-40'C [68-1040F], which is more typical of nuclear plantinstallations, the ambient compensations would cause trip times belowpublished specifications. GE ED&C did not have data on the magnitude ofdeviations from the published time-current curves.GE NE indicated that the above identified models made before October 1990 maybe affected by this problem. To identify when the relays were built, they aremarked with date codes consisting of two letters. The first letter, "N"through "Z" (skipping IQ"), indicates month of manufacture. The second letterindicates the year with "D" meaning 1989, NER meaning 1990, etc. Hence relaysof the affected models built before October 1990, i.e., in September 1990 andearlier (date codes "WE" and earlier), are affected. ED&C has issued noservice advice letters (SALs), nor has GE NE issued any service informationletters (SILs), on this issue. Since late 1991, ED&C has used 5-character,alphanumeric, in lieu of 2-letter date codes for the relays and similarcomponents.Because the affected relays are reported to work properly within thetemperature range of 15-20*C [59-68*F], ED&C recommended evaluating individualapplications in terms of actual service conditions and performancerequirements to determine the potential impact on operability of the overloadrelays with defective ambient compensation. In addition, because some of thepotentially affected relays may not be defective, GE ED&C provided a testprocedure that may be used as an alternative to wholesale replacement toidentify those relays that actually have the improperly installed ambientcompensation bimetal. The procedure is to test the relays at a nominaloverload current (e.g., 300 percent) at room temperature (e.g., 25°C [770F])and then repeating the test after thermal soaking at 40*C [104°F] andverifying that the cool and warm trip times at the same overload level arewithin 10 percent of each other. If these relays fail this test and thecondition cannot be tolerated because of requirements of the application, ED&Cstated that these relays would need to be replaced because they cannot berepaired. ED&C also recommended the test procedure described above forgeneral use on ambient compensated thermal overload relays, installed or instorage, which ED&C recommended testing at least every five year IN 94-41June 7, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office NuclearReactor Regulation (NRR) project manager.Bran K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Stephen D. Alexander, NRR(301) 504-2995

Attachment:

List of Recently Issued NRC Information Notices A tachment 1IN 94-41June 7, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to94-4094-3994-3894-3794-3691-81,Supp. 194-35Failure of a Rod ControlCluster Assembly to FullyInsert Following a ReactorTrip at Braidwood Unit 2Identified Problems inGamma StereotacticRadiosurgeryResults of a Special NRCInspection at DresdenNuclear Power StationUnit 1 Following a Ruptureof Service Water InsideContainmentMisadministration Causedby a Bent InterstitialNeedle during Brachy-therapy ProcedureUndetected Accumulationof Gas in ReactorCoolant SystemSwitchyard Problems thatContribute to Loss ofOffsite PowerNIOSH Respirator UserNotices, "InadvertentSeparation of the Mask-Mounted Regulator (MMR)from the Facepiece on theMine Safety Appliances (MSA)Company MMR Self-ContainedBreathing Apparatus (SCBA)and Status Update"05/26/9405/31/9405/27/9405/27/9405/24/9405/19/9405/16/94All holders of OLs or CPsfor pressurized-waterreactors (PWRs).All U.S. Nuclear RegulatoryCommission TeletherapyMedical Licensees.All holders of OLs or CPsfor NPRs and all fuel cycleand materials licenseesauthorized to possess spentfuel.All U.S. Nuclear RegulatoryCommission Medical Licenseesauthorized to use brachy-therapy sources in high-,medium-, and pulsed-dose-rate remote afterloaders.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors,and all licensed fuelfacilities.OL = Operating LicenseCP = Construction Permit IN 94-41June 7, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager. oWginalsigned DIBrian IL 1rneSBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Stephen D. Alexander, NRR(301) 504-2995

Attachment:

List of Recently Issued NRC Information Notices*See previous concurrence.OFFICE VIB/DRIL SC/VIB/DRIL TECH ED BC/VIB/DRIL D/DRILNAME SAlexander* GCwalina* RSanders* LNorrholm* CERossi*DATE 1 01/07/94 01/13/94 02/02/94 01/24/94 Ad I'7 01/31/94OFFICEEELB/DEOGCB/DORSI ABC/OGCB/DORSD /M< ND .AE 0 9 0 -20NAME CBerlinger* PWen* AKug ler *{/DATE 02/22/94 03/08/94 03/16/94 06/1 /94DOCUMENT NAME: 94-41.IN IN 94-XXMarch xx, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Stephen D. Alexander, NRR(301) 504-2995

Attachment:

List of Recently Issued NRC Information Notices*See previous concurrence.OFFICE I VIB/DRIL SC/VIB/DRIL TECH ED BC/VIB/DRIL D/DRILNAME SAlexander* GCwalina* RSanders* LNorrholm* CERossi*DATE 01/07/94 01/13/94 02/02/94 01/24/94 01/31/94OFFICE EELB/DE OGCB/DORS ABC/OGCB/DORS D/DORS/NRRNAME CBerlinger* PWen* AKugler B_ __KGrimesDATE 02/22/94 03/ /94 03/08/94 03/1K/9403/ /94DOCUMENT NAME: CR124AC.PCW ,tJt1e)

V .-' IN 94-XXMarch xx, 1994 No specific action or written response is required by this information notice.If you have any questions regarding this matter, please contact the technicalcontact listed below or the appropriate Office of Nuclear Reactor Regulation(NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Stephen D. Alexander, NRR(301) 504-2995

Attachment:

List of Recently Issued NRC Information Notices*See previous concurrence.OFFICE VIB/DRIL SC/VIB/DRIL TECH ED BC/VIB/DRIL D/DRILNAME SAlexander* GCwalina* RSanders* LNorrholm* CERossi*DATE 01/07/94 j01/13/94 J02/02/94 101/24/94 101/31/94OFFICE EELB/DE OGCB/DORS ABC/OGCB/DORS D/DORS/NRRNAME CBerlinger* PWen T IC__ AKugler BKGrimesDATE 02/22/94 03___94 __03/ /94 03/ /94 103/ /94OCUMENT N AME: CR124AC.PCW 1-.%IN 94-XXFebruary XX, 1994 GE NE stated that annf the affected models made before October 1990 shouldbe considered suspect a should be replaced. To identify when the relayswere built, they are markel with date codes consisting of two letters. Thefirst letter, "NO through " " (skipping "Qu), indicates month of manufacture.The second letter indicates t year with "E" meaning 1990, OF" meaning 1991,etc. Hence relays of the affec d models stated above built before October1990, i.e., in September 1990 an earlier (date codes "WE" and earlier), areaffected. ED&C reportedly correct the problem on these models in September1990 so that date codes for October 90 and later, i.e., "XE" (October 1990),"YE" (November 1990), "ZE" (December 90), INF" (January 1991), etc., shouldnot be affected. ED&C has issued no se ice advice letters (SALs), nor has GENE issued any service information letters (SILs) on this issue.GE NE also reported that ED&C recommend , in addition to replacing suspectrelays, testing thermal overload relays that re installed and in storage atleast every 5 years. ED&C's procedure is to st the relays at a nominaloverload current (e.g., 300 percent) at room teperature (e.g., 25OC/77'F) andalso after thermal soaking at 40*C/104OF and ver ying that the cool and warmtrip times at the same overload level are within 1 percent of each other. Ifnot, ED&C recommended replacing the relays because ey cannot be repaired.No specific action or written response is require by this informationnotice. If you have any questions regarding this matt r, please contact oneof the technical contacts listed below or the appropria Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectoDivision of Operating Rea tor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Stephen D. Alexander, NRR (301) 504-2995

Attachments:

1. List of Recently Issued NRC Information Notices*See previous concurrence.OFFICE VIB/DRIL SC/VIB/DRIL TECHED BC/VIB/DRIL D/DRILNAME SAlexander* GCwalina* RSanders* LNorrholm* CERossi*DATE 01/07/94 01/13/94 02/02/94 01/24/94 01/31/94COPY YES YES NO NO NOOFFICE EELB______i__e__OGCB/DORS BC/OGCB/DORS D/DORS/NRRNAME CBerlfnger -Rliies4 BKGrimesDATE 02/22/94 02/ /94 02/ /94 02/ /94 02/ /94COPY YES NO YES NO YES NO YES NO YES NOOFFICIAL RECORD COPY DOCUMENT NAME: CR124AC.IN IN 94-XXJanuary XX, 1994 GE NE stated t t any of the affected models made before October 1990 shouldbe considered susp t and should be replaced. To identify when the relayswere built, they are arked with date codes consisting of two letters. Thefirst letter, "N" thro h HZ" (skipping "Q"), indicates month of manufacture.The second letter indic es the year with "E" meaning 1990, "F" meaning 1991,etc. Hence relays of the ffected models stated above built before October1990, i.e., in September 1 %0 and earlier (date codes "WE" and earlier), areaffected. ED&C reportedly c rrected the problem on these models in September1990 so that date codes for Octqber 1990 and later, i.e., "XE" (October 1990),"YE" (November 1990), "ZE" (Decei er 1990), "NF" (January 1991), etc., shouldnot be affected. ED&C has issued b Service Advice Letters (SALs), nor has GENE issued any Service Information Le ters (SILs) on this issue.GE NE reported also that ED&C recome nded, in addition to replacing suspectrelays, testing thermal overload relays at are installed and in storage atleast every 5 years. ED&C's procedure is o test the relays at a nominaloverload current (e.g., 300 percent) at roo temperature (e.g., 25OC/770F) andalso after thermal soaking at 40*C/104*F and erifying that the cool and warmtrip times at the same overload level are with 10 percent of each other. Ifnot, ED&C recommended replacement because these elays cannot be repaired.No specific action or written response is requ ed by this informationnotice. If you have any questions regarding this aitter, please contact oneof the technical contacts listed below or the approptate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Stephen D. Alexander, NRR (301) 504-2995

Attachments:

1. List of Recently Issued NRC Information Notices*See previous concurrence.-:- lOFFICE VIB/DRIL SC/VIB/DRIL TECHED BC/VIB/DRIL DDRINAME SAlexander* GCwalina* yiua.,k14 LNorrholm* CERossi*DATE 01/07/94 01/13/94 02/ V&/94 01/24/94 01/31/94COPY YES YES NO NO NOOFFICE EELB/DE OGCB/DORS BC/OGCB/DORS D/DORS/NRRNAME CBerlinger RKiesel BKGrimesDATE 01/ /94 01/ /94 01/ /94 01/ /94 01/ /94COPY YES NO YES NO YES NO YES NO YES NOa_&_hf 9 Al UNI4lA AP TEOFFICIAL RECORD COPYUULUMtNI N Li X1~t; IN 94-XXJanuary XX, 1994 GE NE stated that any of the a fected models made before October 1990 shouldbe considered suspect and should e replaced. To identify when the relayswere built, they are marked with ate codes consisting of two letters. Thefirst letter, IN' through "Z" (ski ping "Q"), indicates month of manufacture.The second letter indicates the yea with "E" meaning 1990, "F" meaning 1991,etc. Hence relays of the affected m dels stated above built before October1990, i.e., in September 1990 and ear ier (date codes "WE" and earlier), areaffected. ED&C reportedly corrected t problem on these models in September1990 so that date codes for October 199 and later, i.e., "XE" (October 1990),"YE" (November 1990), "ZE" (December 199 I, INFO (January 1991), etc., shouldnot be affected. ED&C has issued no Servi e Advice Letters (SALs), nor has GENE issued any Service Information Letters ( ILs) on this issue.GE NE reported also that ED&C recommended in addition to replacing suspectrelays, testing thermal overload relays that re installed and in storage atleast every 5 years. ED&C's procedure is to t st the relays at a nominaloverload current (e.g., 300 percent) at room te perature (e.g., 25OC/770F) andalso after thermal soaking at 40OC/104OF and ve *fying that the cool and warmtrip times at the same overload level are within 10 percent of each other. Ifnot, ED&C recommended replacement because these r lays cannot be repaired.No specific action or written response is requ red by this informationnotice. If you have any questions regarding this atter, please contact oneof the technical contacts listed below or the appr iate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Stephen D. Alexander, NRR (301) 504-2995

Attachments:

1. List of Recently Issued NRC Information NoticesOFFICE VIB/DRIL SC/ VW RIL TECHED BC/ I /DRIL D/DRILNAME SAlexand GC_ WiDATE 01/c1/94 0l13 94 01/ /94 01 94COPY Y YE NO NO YES YNOYES NOOFFICE EELB/DE OGCB/DORS BC/OGCB/DORS D/DORS/NRRNAME CBerlinger RKiesel BKGrimesDATE 01/ /94 01/ /94 01/ /94 01/ /94 01/ /94COPY YES NO YES NO YES NO YES NO YES NOncr~rTIAI nrrnnnr, rrl.hraI- AK ,.I ,^AM T&IUrr LUlRL ICUKU bUMUUUUMtNI NMMt: LK1z4qA%.1N