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| | issue date = 06/29/1990 | | | issue date = 06/29/1990 |
| | title = Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers | | | title = Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers |
| | author name = Rossi C E | | | author name = Rossi C |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555June 29, 1990NRC INFORMATION NOTICE NO. 90-43: MECHANICAL INTERFERENCE WITH THERMAL TRIPFUNCTION IN GE MOLDED-CASE CIRCUIT BREAKERS | | {{#Wiki_filter:UNITED STATES |
| | |
| | NUCLEAR REGULATORY COMMISSION |
| | |
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| | |
| | WASHINGTON, D.C. 20555 June 29, 1990 |
| | NRC INFORMATION NOTICE NO. 90-43: MECHANICAL INTERFERENCE WITH THERMAL TRIP |
| | |
| | FUNCTION IN GE MOLDED-CASE CIRCUIT BREAKERS |
|
| |
|
| ==Addressees== | | ==Addressees== |
| :All holders of operating licenses or construction permits for nuclear powerreactors. | | : |
| | All holders of operating licenses or construction permits for nuclear power |
| | |
| | reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| :This information notice is Intended to-alert addressees of a manufacturingdeviation in certain General Electric (GE) molded-case circuit breakers (MCCBs)which may result in mechanical interference with the thermal overcurrent tripfunction when internal accessory undervoltage release (UVR) devices are in-stalled. In addition, the information contained herein is intended to empha-size the importance of conducting thorough pre-installation testing to verifythat plant components meet the functional performance requirements of theirsafety-related applications. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained in thisinformation notice do not constitute NRC requirements; therefore, no specificaction or written response is required. | | : |
| | This information notice is Intended to-alert addressees of a manufacturing |
| | |
| | deviation in certain General Electric (GE) molded-case circuit breakers (MCCBs) |
| | which may result in mechanical interference with the thermal overcurrent trip |
| | |
| | function when internal accessory undervoltage release (UVR) devices are in- stalled. In addition, the information contained herein is intended to empha- size the importance of conducting thorough pre-installation testing to verify |
| | |
| | that plant components meet the functional performance requirements of their |
| | |
| | safety-related applications. 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 do not constitute NRC requirements; therefore, no specific |
| | |
| | action or written response is required. |
|
| |
|
| ==Description of Circumstances== | | ==Description of Circumstances== |
| :In 1989, General Public Utilities-Nuclear (GPUN), the licensee for the OysterCreek Nuclear Power Plant (Oyster Creek), purchased 170 TED-type and THED-typeMCCBs from GE Nuclear Energy in San Jose, California. The MCCBs were purchasedas safety-related items and were supplied with GE Nuclear Energy productquality certificates (PQCs). GE Nuclear Energy purchased the MCCBs as commer-cial grade items (CGIs) from the GE Electrical Distribution and Control Depart-ment in Plainville, Connecticut (GE-ED&C), who manufactured the MCCBs at theirHumacao, Puerto Rico, factory and installed UVRs at their accessory installa-tion facility in Mascot (Knoxville), Tennessee." The MCCBs were dedicated by GENuclear Energy for use in safety-related applications at Oyster Creek, inpart, on the basis of testing performed at the Puerto Rico factory.In November 1989, one 15-ampere TED-type MCCB from this order was bench-testedat Oyster Creek prior to installation. This MCCB had a UVR installed in thestandard location by phase IC" (right-hand side). The MCCB failed to trip when300-percent of rated current was applied to phase C of the MCCB (a time-overcurrent test of the thermal trip function), whereas on phases A and B,9006250069 Z IN 90-43June 29, 1990 the thermal trips operated'satisfactorily. The licensee returned the MCCB toGE Nuclear Energy for failure and root cause analysis. The results of the.analysis have not yet been reported. .;In May 1990, according to GPUN reports, Oyster Creek technicians bench-testedseven more UYR-equipped MCCBs from the same'order. Five of the seven, failed topass the overcurrent trip test (also at 300 percent of rated current) onphase C only. In addition, GPUN reported opening one of the failed MCCBs,.removing'the UYR, and retesting the MCCB with satisfactory results for thethermal overcurrent trip test on phase C. These experimental results suggestedthat the UVR had been interfering with the operation of the phase-C thermalovercurrent trip element because of its close proximity to the phase-C element.However, it should be noted that the UVR is not intended to act on the thermalelement, but rather on the common tripper bar that trips all three phases orpoles.Discussion:On May 24, 1990, an NRC representative observed the GE ED&C testing of the fiveGE TED-type MCCBs with UYRs installed (GE catalog number TED136100UY4RS) whichhad failed pre-installation testing at Oyster Creek.- Inspection and testingrevealed that the cause of the failure of the overcurrent trip function wasimproper installation of the calibration screw spring clips by the Puerto Rico-factory 4nstead-of-iniproper installation of the UVRs by the Knoxville faci-lity, as previously believed by GE Nuclear -YEnGy.-GE-ED&C-stated-that--the-misoriented calibration screw spring clips have no effect on the operability ofthe MCCBs unless internal UYRs are installed. The Oyster Creek-MCCBs passedthe thermal overcurrent trip tests at the GE Puerto Rico factory because theUYRs had not yet been installed. After the UYRs were installed at the GE ED&CKnoxville facility, the presence of the misoriented calibration screw springclips caused mechanical interference between the UVR and the thermal over-current trip function. This was not detected at the GE ED&C Knoxville faci-lity, because testing of all MCCBs normal functions was not performed.Deficiencies in manufacturing quality control and in the program for dedicationof CGIs for safety-related applications were exhibited by the undetectedmisorientation of the calibration screw spring clips and the lack of adequateretesting following installation of the UVRs. GE ED&C has indicated thataction will be taken, including design changes if necessary, to prevent inter-ference between the calibration screw spring clips and the UYRs. In addition,GE ED&C has now instituted overcurrent trip testing of MCCBs following theinstallation of UYRs at their Knoxville facility.Although GE ED&C's failure analysis was demonstrated by testing, it has notbeen firmly established that this condition is isolated to the MCCB shipment inquestion. However, GE ED&C has stated that the problem is limited only to thethermal overcurrent trip functions on phase C of their 3-pole, E-frame MCCBs(types TED13XXXX and THED13XXXX), and only those equipped with UVRs. This is aresult of this model's unique, integral overcurrent trip mechanisms and theproximity of the phase C thermal trip mechanism to the tripping arm of aninstalled UVR..9 IIN 90-43June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre-vented the use of the faulty MCCBs. Although the MCCBs were procured assafety-related components through GE Nuclear Energy and were supplied with thevendor'-s 10 CFR Part 50 Appendix B quality assurance certifications, thistesting was performed by the licensee in addition to the normal quality assur.-ance receipt inspection.This information notice requiresyou have any questions about 'theof the technical contacts listedno specific action or written response. Ifinformation in this notice, please contact onebelow or the appropriate NRR project manager.Char Rossi DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:K. R.(301)Naidu, NRR492-0980S. D. Alexander, NRR(301) 492-0995%ase-Cut " t.. .,. Em : lsr; -r. M | | : |
| | In 1989, General Public Utilities-Nuclear (GPUN), the licensee for the Oyster |
| | |
| | Creek Nuclear Power Plant (Oyster Creek), purchased 170 TED-type and THED-type |
| | |
| | MCCBs from GE Nuclear Energy in San Jose, California. The MCCBs were purchased |
| | |
| | as safety-related items and were supplied with GE Nuclear Energy product |
| | |
| | quality certificates (PQCs). GE Nuclear Energy purchased the MCCBs as commer- cial grade items (CGIs) from the GE Electrical Distribution and Control Depart- ment in Plainville, Connecticut (GE-ED&C), who manufactured the MCCBs at their |
| | |
| | Humacao, Puerto Rico, factory and installed UVRs at their accessory installa- tion facility in Mascot (Knoxville), Tennessee." The MCCBs were dedicated by GE |
| | |
| | Nuclear Energy for use in safety-related applications at Oyster Creek, in |
| | |
| | part, on the basis of testing performed at the Puerto Rico factory. |
| | |
| | In November 1989, one 15-ampere TED-type MCCB from this order was bench-tested |
| | |
| | at Oyster Creek prior to installation. This MCCB had a UVR installed in the |
| | |
| | standard location by phase IC" (right-hand side). The MCCB failed to trip when |
| | |
| | 300-percent of rated current was applied to phase C of the MCCB (a time- overcurrent test of the thermal trip function), whereas on phases A and B, |
| | 9006250069 Z |
| | |
| | IN 90-43 June 29, 1990 the thermal trips operated'satisfactorily. The licensee returned the MCCB to |
| | |
| | GE Nuclear Energy for failure and root cause analysis. The results of the. |
| | |
| | analysis have not yet been reported. . ; |
| | In May 1990, according to GPUN reports, Oyster Creek technicians bench-tested |
| | |
| | seven more UYR-equipped MCCBs from the same'order. Five of the seven, failed to |
| | |
| | pass the overcurrent trip test (also at 300 percent of rated current) on |
| | |
| | phase C only. In addition, GPUN reported opening one of the failed MCCBs,. |
| | |
| | removing'the UYR, and retesting the MCCB with satisfactory results for the |
| | |
| | thermal overcurrent trip test on phase C. These experimental results suggested |
| | |
| | that the UVR had been interfering with the operation of the phase-C thermal |
| | |
| | overcurrent trip element because of its close proximity to the phase-C element. |
| | |
| | However, it should be noted that the UVR is not intended to act on the thermal |
| | |
| | element, but rather on the common tripper bar that trips all three phases or |
| | |
| | poles. |
| | |
| | Discussion: |
| | On May 24, 1990, an NRC representative observed the GE ED&C testing of the five |
| | |
| | GE TED-type MCCBs with UYRs installed (GE catalog number TED136100UY4RS) which |
| | |
| | had failed pre-installation testing at Oyster Creek.- Inspection and testing |
| | |
| | revealed that the cause of the failure of the overcurrent trip function was |
| | |
| | improper installation of the calibration screw spring clips by the Puerto Rico |
| | |
| | -factory 4nstead-of-iniproper installation of the UVRs by the Knoxville faci- lity, as previously believed by GE Nuclear- YEnGy.-GE-ED&C-stated-that--the- misoriented calibration screw spring clips have no effect on the operability of |
| | |
| | the MCCBs unless internal UYRs are installed. The Oyster Creek-MCCBs passed |
| | |
| | the thermal overcurrent trip tests at the GE Puerto Rico factory because the |
| | |
| | UYRs had not yet been installed. After the UYRs were installed at the GE ED&C |
| | |
| | Knoxville facility, the presence of the misoriented calibration screw spring |
| | |
| | clips caused mechanical interference between the UVR and the thermal over- current trip function. This was not detected at the GE ED&C Knoxville faci- lity, because testing of all MCCBs normal functions was not performed. |
| | |
| | Deficiencies in manufacturing quality control and in the program for dedication |
| | |
| | of CGIs for safety-related applications were exhibited by the undetected |
| | |
| | misorientation of the calibration screw spring clips and the lack of adequate |
| | |
| | retesting following installation of the UVRs. GE ED&C has indicated that |
| | |
| | action will be taken, including design changes if necessary, to prevent inter- ference between the calibration screw spring clips and the UYRs. In addition, GE ED&C has now instituted overcurrent trip testing of MCCBs following the |
| | |
| | installation of UYRs at their Knoxville facility. |
| | |
| | Although GE ED&C's failure analysis was demonstrated by testing, it has not |
| | |
| | been firmly established that this condition is isolated to the MCCB shipment in |
| | |
| | question. However, GE ED&C has stated that the problem is limited only to the |
| | |
| | thermal overcurrent trip functions on phase C of their 3-pole, E-frame MCCBs |
| | |
| | (types TED13XXXX and THED13XXXX), and only those equipped with UVRs. This is a |
| | |
| | result of this model's unique, integral overcurrent trip mechanisms and the |
| | |
| | proximity of the phase C thermal trip mechanism to the tripping arm of an |
| | |
| | installed UVR. |
| | |
| | .9 |
| | |
| | I |
| | |
| | IN 90-43 June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre- vented the use of the faulty MCCBs. Although the MCCBs were procured as |
| | |
| | safety-related components through GE Nuclear Energy and were supplied with the |
| | |
| | vendor'-s 10 CFR Part 50 Appendix B quality assurance certifications, this |
| | |
| | testing was performed by the licensee in addition to the normal quality assur.- |
| | ance receipt inspection. |
| | |
| | This information notice requires no specific action or written response. If |
| | |
| | you have any questions about 'the information inthis notice, please contact one |
| | |
| | of the technical contacts listed below or the appropriate NRR project manager. |
| | |
| | Char Rossi Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: K. R. Naidu, NRR |
| | |
| | (301) 492-0980 |
| | S. D. Alexander, NRR |
| | |
| | (301) 492-0995 |
| | " |
| | %ase-Cut t.. . ,. Em : lsr; -r. M |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Attachut |
| | |
| | June 29. 19 Pap I of 1 LisT OF RECOMT issU£1 IRC IRFUOTION INOTICES |
| | |
| | mrformuoe Sit, er |
| | |
| | CUoti o Subject Isunc Issued to |
| | |
| | 30-. Surface Crack and Subsurfete 6/19se All wders of Ke |
| | |
| | Suav. 1 Indicatious Is the laid of or ChPfor nuclear |
| | |
| | a Reactor vessel Head powr reactors. |
| | |
| | 90.4 Failure of Electrical Pur 6/19/30 All holden of au |
| | |
| | Eqi.pnt Due to Solar or Chafor Wueagr |
| | |
| | Slgnotlc Distorbancee powe r . |
| | |
| | 90-41 Potential Fallen oft General /12/90 All holders of OLa |
| | |
| | Electric Nagne-Blast or CPa for nuclear. |
| | |
| | Circuit 5peakers and At powr reactors., |
| | Circuit Breakers |
| | |
| | :3J40 Results of IRC-Sponsorad 6/1/90 All holders of D14 Testing of 1etor-Operatad or Cha for ncler |
| | |
| | Talves pr nreactors. |
| | |
| | ct RroelasmIH1it |
| | |
| | c-39 Service UV1/90 All holders of OLs |
| | |
| | water Systauc or CPa for nuolear |
| | |
| | poaur reactors. |
| | |
| | 95>-3 Reirments for Processing 5/29/90 All fuel facility |
| | |
| | Financial Assurace Submittals VA matarlala |
| | |
| | for Decomissioeing licensus. |
| | |
| | 90.37 Sheared Pinaio Gear-to-Saft 1/24/90 All holders of a6e |
| | |
| | em Is Liaitorque aotor or CPa for nuclear |
| | |
| | Actuators pool reactors. |
| | |
| | 0-36 Apsresnt falsification of 1/24/90 All holders of Os |
| | |
| | State Of Connecticut or Chs for nuclear |
| | |
| | H1eigt Certificates powe reactors and |
| | |
| | 10 CFP73 11cauen. |
| | |
| | 90-31 Transportatios of Type A /24/90 All U.S. N1Clc a. |
| | |
| | Quantities of Non-Fissile |
| | |
| | Radioactive Matertals |
| | |
| | (R |
| | |
| | * Oerti, Liconse |
| | |
| | CP* ConItDt10n Permit |
| | |
| | UNITED STATES |
| | |
| | NUCLEAR REGULATORY COMMISSION PIPT LASAIL1 WASHINGTON, D.C. 206 IPOSTAGE & FEES PAIDI |
| | |
| | 1 USNRC 1 OFFICIAL BUSINESS |
| | |
| | PENALTY FOR PRIVATE USE. $300 |
| | |
| | IN 90-43 June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre- vented the use of the faulty MCCBs. Although the MCCBs were procured as |
| | |
| | safety-related components through GE Nuclear Energy and were supplied with the |
| | |
| | vendor's 10 CFR Part 50 Appendix B quality assurance certifications, this |
| | |
| | testing was performed by the licensee in addition to the normal quality assur- ance receipt inspection. |
| | |
| | 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 NRR project manager. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: K. R. Naidu, NRR |
| | |
| | (301) 492-0980 |
| | S. D. Alexander, NRR |
| | |
| | (301) 492-0995 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Document Name: INFO NOTICE ALEXANDER/2 |
| | *SEE PREVIOUS CONCU |
| | |
| | *C/OGCB:DOEA:NRR*RPB:ADM *D/DRIS:NRR |
| | |
| | CHBerlinger TechEd BKGrimes |
| | |
| | O6/>'90 06/19/90 06/05/90 06/07/90 |
| | *OGCB:DOEA:NRR*VIB:DRIS:NRR *VIB:DRIS:NRR *VIB:DRIS:NRR *C/VIB:DRIS:NRR |
| | |
| | NCampbell SAlexander:sdal KNaidu UPotapovs EWBrach |
| | |
| | 06/22/90 6/06/90 6/06/90 6/06/90 6/06/90 |
| | |
| | IN 90-XX |
| | |
| | June X, 1990 The failure of the Oyster Creek MCCBs in safety-related applications could have |
| | |
| | jeopardized the safety of the plant. Oyster Creek's routine pre-installation |
| | |
| | testing procedures detected and prevented the use of the faulty MCCBs. Al- though the MCCBs were procured as safety-related components through GENE and |
| | |
| | were supplied with the vendor's 10 CFR Part 50 Appendix B quality assurance |
| | |
| | certifications, this testing was performed by the licensee in addition to the |
| | |
| | normal quality assurance receipt inspection. |
| | |
| | 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 NRR project manager. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: K. R. Naidu, NRR |
| | |
| | (301) 492-0980 |
| | S. D. Alexander, NRR |
| | |
| | (301) 492-0995 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Document Nlame: INFO NOTICE ALEXANDER/@F |
| | |
| | *SEE PREVIOUS CONCURRENCES I |
| | |
| | D/DOEA:NRR B RR B:ADM *D/DRIS:NRR |
| | |
| | CERossi CHB~~ ih TechEd BKGrimes |
| | |
| | 06/ /90 06/1j/90 06/05/90 06/07/90 |
| | :NRR rVIB:DRIS:NRR *VIB:IDRIS:NRR *VIB:DRIS:NRR *C/VIB:DRIS:NRR |
| | |
| | NCampbell SAlexander:sda KNaidu UPotapovs EWBrach |
| | |
| | 06 /JVJ/90 6/06/90 6/06/90 6/06/90 6/06/90 |
| | |
| | IN 90-XX |
| | |
| | June X, 1990 Oyster Creek's routine preinstallation testing procedures detected and |
| | |
| | prevented the use of faulty MCCBs in safety-related applications which could |
| | |
| | have jeopardized s t the plant. It should be noted that this testing |
| | |
| | was conducted tow w c that these components were procured as safety- related and came with vendor 10 CFR Part 50 Appendix B quality assurance |
| | |
| | certifications. |
| | |
| | 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 NRC regional office. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assesment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: K. R. Naidu, NRR (301) 492-0980 |
| | S. D. Alexander, NRR (301) 492-0995 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | OFC :VIB:DRIS:NRR :VIB:DRIS:NRR :VIB:DXIS:NRR :C:VIB-DRIS:NRR:TECH ED :D:DR S:NRR |
| | |
| | ___________----_____ |
| | ______------ :--q___ ------- A- -- -------------- :dn -- |
| | NAME :SAlexander:sda :UPo povs |
| | |
| | :N+df CFc |
| | |
| | fE) -- :7tl :B^ yrimes |
|
| |
|
| ===Attachment:===
| | __ __ _ _ _._..:V:- |
| List of Recently Issued NRC Information Notices AttachutJune 29. 19Pap I of 1LisT OF RECOMT issU£1IRC IRFUOTION INOTICESmrformuoe Sit, erCUoti o Subject Isunc30-. Surface Crack and Subsurfete 6/19seSuav. 1 Indicatious Is the laid ofa Reactor vessel Head90.4 Failure of Electrical Pur 6/19/30Eqi.pnt Due to SolarSlgnotlc Distorbancee90-41 Potential Fallen of General t /12/90Electric Nagne-BlastCircuit 5peakers and AtCircuit Breakers:3J40 Results of IRC-Sponsorad 6/1/90Testing of 1etor-OperatadTalvesc-39 ct RroelasmI H1i t Service UV1/90water Systauc95>-3 Reirments for Processing 5/29/90Financial Assurace Submittalsfor Decomissioeing90.37 Sheared Pinaio Gear-to-Saft 1/24/90em Is Liaitorque aotorActuators0-36 Apsresnt falsification of 1/24/90State Of ConnecticutH1eigt Certificates90-31 Transportatios of Type A /24/90Quantities of Non-FissileRadioactive MatertalsIssued toAll wders of Keor ChP for nuclearpowr reactors.All holden of auor Cha for Wueagrpowe r .All holders of OLaor CPa for nuclear.powr reactors.,All holders of D14or Cha for nclerpr nreactors.All holders of OLsor CPa for nuolearpoaur reactors.All fuel facilityVA matarlalalicensus.All holders of a6eor CPa for nuclearpool reactors.All holders of Osor Chs for nuclearpowe reactors and10 CFP 73 11cauen.All U.S. N1C lc a.(R
| | :6/, /90:6 -----. -- __- _ ----- |
| | DATE :6/6 /90 :6/ 9 :6/ /90 :6/ 6/90 :6/F/90 .6 90 avO_ |
| | . . |
|
| |
|
| * Oerti, LiconseCP
| | OFC B:DOEA:NRR :GCB:DOEA:NRR G |
|
| |
|
| * ConItDt10n PermitUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 206OFFICIAL BUSINESSPENALTY FOR PRIVATE USE. $300PIPT LAS AIL1IPOSTAGE & FEES PAIDI1USNRC1 IN 90-43June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre-vented the use of the faulty MCCBs. Although the MCCBs were procured assafety-related components through GE Nuclear Energy and were supplied with thevendor's 10 CFR Part 50 Appendix B quality assurance certifications, thistesting was performed by the licensee in addition to the normal quality assur-ance receipt inspection.This information notice requiresyou have any questions about theof the technical contacts listedno specific action or written response. Ifinformation in this notice, please contact onebelow or the appropriate NRR project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:K. R.(301)Naidu, NRR492-0980S. D. Alexander, NRR(301) 492-0995
| | :C:GCB:DOEA:NRR:D:DOEA NRR : |
| | NAME :JJRam :ERossi : |
| | :CBerlinger |
|
| |
|
| ===Attachment:===
| | DATE :6 /90 :6/ /90 6/ /90 :6/ /90 |
| List of Recently Issued NRC Information NoticesDocument Name:INFO NOTICE ALEXANDER/2*SEE PREVIOUS CONCUO6/>'90*OGCB:DOEA:NRR*VIB:DRIS:NRRNCampbell SAlexander:sda06/22/90 6/06/90*C/OGCB:DOEA:NRR*RPB:ADMCHBerlinger TechEd06/19/90 06/05/90*VIB:DRIS:NRR *VIB:DRIS:NRRl KNaidu UPotapovs6/06/90 6/06/90*D/DRIS:NRRBKGrimes06/07/90*C/VIB:DRIS:NRREWBrach6/06/90 IN 90-XXJune X, 1990 The failure of the Oyster Creek MCCBs in safety-related applications could havejeopardized the safety of the plant. Oyster Creek's routine pre-installationtesting procedures detected and prevented the use of the faulty MCCBs. Al-though the MCCBs were procured as safety-related components through GENE andwere supplied with the vendor's 10 CFR Part 50 Appendix B quality assurancecertifications, this testing was performed by the licensee in addition to thenormal quality assurance receipt inspection.This information notice requiresyou have any questions about theof the technical contacts listedno specific action or written response. Ifinformation in this notice, please contact onebelow or the appropriate NRR project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:K. R.(301)Naidu, NRR492-0980S. D. Alexander, NRR(301) 492-0995
| | OFFICIAL RECORD COPY |
|
| |
|
| ===Attachment:===
| | Document Name: GE MCCB UVR INFO NOTICE |
| List of Recently Issued NRC Information NoticesDocument N*SEE PREVIOUS:NRRNCampbell06 /JVJ/90Clame: INFO NOTICE ALEXANDER/@FONCURRENCES ID/DOEA:NRR B RR B:ADMCERossi CHB~~ ih TechEd06/ /90 06/1j/90 06/05/90rVIB:DRIS:NRR *VIB:IDRIS:NRR *VIB:DRIS:NRRSAlexander:sda KNaidu UPotapovs6/06/90 6/06/90 6/06/90*D/DRIS:NRRBKGrimes06/07/90*C/VIB:DRIS:NRREWBrach6/06/90 IN 90-XXJune X, 1990 Oyster Creek's routine preinstallation testing procedures detected andprevented the use of faulty MCCBs in safety-related applications which couldhave jeopardized s t the plant. It should be noted that this testingwas conducted tow w c that these components were procured as safety-related and came with vendor 10 CFR Part 50 Appendix B quality assurancecertifications.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate NRC regional office.Charles E. Rossi, DirectorDivision of Operational Events AssesmentOffice of Nuclear Reactor RegulationTechnical Contacts: K. R. Naidu, NRR (301) 492-0980S. D. Alexander, NRR (301) 492-0995
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| | 0004.0.0}} |
| List of Recently Issued NRC Information NoticesOFC :VIB:DRIS:NRR :VIB:DRIS:NRR :VIB:DXIS:NRR :C:VIB-DRIS:NRR:TECH ED :D:DR S:NRR______------ ___________----_____ :--q___ ------- A- -- --------------:dn --NAME :SAlexander:sda :N+df :UPo povs fE) C Fc -- :7tl :B^ yrimes__ __ _ _ _._..:V:- -----. -- __- _ ------:6/, /90:6DATE :6/6 /90 :6/ 9 :6/ /90 :6/ 6/90 :6/ F/90 .6 9 0 avO_..OFC G B:DOEA:NRR :GCB:DOEA:NRR :C:GCB:DOEA:NRR:D:DOEA NRR :NAME :JJRam :CBerlinger :ERossi :DATE :6 /90 :6/ /90 6/ /90 :6/ /90OFFICIAL RECORD COPYDocument Name: GE MCCB UVR INFO NOTICE0004.0.0}}
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Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit BreakersML031130291 |
Person / Time |
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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 |
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Issue date: |
06/29/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-90-043, NUDOCS 9006250069 |
Download: ML031130291 (7) |
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Similar Documents at 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 29, 1990
NRC INFORMATION NOTICE NO. 90-43: MECHANICAL INTERFERENCE WITH THERMAL TRIP
FUNCTION IN GE MOLDED-CASE CIRCUIT BREAKERS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is Intended to-alert addressees of a manufacturing
deviation in certain General Electric (GE) molded-case circuit breakers (MCCBs)
which may result in mechanical interference with the thermal overcurrent trip
function when internal accessory undervoltage release (UVR) devices are in- stalled. In addition, the information contained herein is intended to empha- size the importance of conducting thorough pre-installation testing to verify
that plant components meet the functional performance requirements of their
safety-related applications. 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 do not constitute NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
In 1989, General Public Utilities-Nuclear (GPUN), the licensee for the Oyster
Creek Nuclear Power Plant (Oyster Creek), purchased 170 TED-type and THED-type
MCCBs from GE Nuclear Energy in San Jose, California. The MCCBs were purchased
as safety-related items and were supplied with GE Nuclear Energy product
quality certificates (PQCs). GE Nuclear Energy purchased the MCCBs as commer- cial grade items (CGIs) from the GE Electrical Distribution and Control Depart- ment in Plainville, Connecticut (GE-ED&C), who manufactured the MCCBs at their
Humacao, Puerto Rico, factory and installed UVRs at their accessory installa- tion facility in Mascot (Knoxville), Tennessee." The MCCBs were dedicated by GE
Nuclear Energy for use in safety-related applications at Oyster Creek, in
part, on the basis of testing performed at the Puerto Rico factory.
In November 1989, one 15-ampere TED-type MCCB from this order was bench-tested
at Oyster Creek prior to installation. This MCCB had a UVR installed in the
standard location by phase IC" (right-hand side). The MCCB failed to trip when
300-percent of rated current was applied to phase C of the MCCB (a time- overcurrent test of the thermal trip function), whereas on phases A and B,
9006250069 Z
IN 90-43 June 29, 1990 the thermal trips operated'satisfactorily. The licensee returned the MCCB to
GE Nuclear Energy for failure and root cause analysis. The results of the.
analysis have not yet been reported. . ;
In May 1990, according to GPUN reports, Oyster Creek technicians bench-tested
seven more UYR-equipped MCCBs from the same'order. Five of the seven, failed to
pass the overcurrent trip test (also at 300 percent of rated current) on
phase C only. In addition, GPUN reported opening one of the failed MCCBs,.
removing'the UYR, and retesting the MCCB with satisfactory results for the
thermal overcurrent trip test on phase C. These experimental results suggested
that the UVR had been interfering with the operation of the phase-C thermal
overcurrent trip element because of its close proximity to the phase-C element.
However, it should be noted that the UVR is not intended to act on the thermal
element, but rather on the common tripper bar that trips all three phases or
poles.
Discussion:
On May 24, 1990, an NRC representative observed the GE ED&C testing of the five
GE TED-type MCCBs with UYRs installed (GE catalog number TED136100UY4RS) which
had failed pre-installation testing at Oyster Creek.- Inspection and testing
revealed that the cause of the failure of the overcurrent trip function was
improper installation of the calibration screw spring clips by the Puerto Rico
-factory 4nstead-of-iniproper installation of the UVRs by the Knoxville faci- lity, as previously believed by GE Nuclear- YEnGy.-GE-ED&C-stated-that--the- misoriented calibration screw spring clips have no effect on the operability of
the MCCBs unless internal UYRs are installed. The Oyster Creek-MCCBs passed
the thermal overcurrent trip tests at the GE Puerto Rico factory because the
UYRs had not yet been installed. After the UYRs were installed at the GE ED&C
Knoxville facility, the presence of the misoriented calibration screw spring
clips caused mechanical interference between the UVR and the thermal over- current trip function. This was not detected at the GE ED&C Knoxville faci- lity, because testing of all MCCBs normal functions was not performed.
Deficiencies in manufacturing quality control and in the program for dedication
of CGIs for safety-related applications were exhibited by the undetected
misorientation of the calibration screw spring clips and the lack of adequate
retesting following installation of the UVRs. GE ED&C has indicated that
action will be taken, including design changes if necessary, to prevent inter- ference between the calibration screw spring clips and the UYRs. In addition, GE ED&C has now instituted overcurrent trip testing of MCCBs following the
installation of UYRs at their Knoxville facility.
Although GE ED&C's failure analysis was demonstrated by testing, it has not
been firmly established that this condition is isolated to the MCCB shipment in
question. However, GE ED&C has stated that the problem is limited only to the
thermal overcurrent trip functions on phase C of their 3-pole, E-frame MCCBs
(types TED13XXXX and THED13XXXX), and only those equipped with UVRs. This is a
result of this model's unique, integral overcurrent trip mechanisms and the
proximity of the phase C thermal trip mechanism to the tripping arm of an
installed UVR.
.9
I
IN 90-43 June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre- vented the use of the faulty MCCBs. Although the MCCBs were procured as
safety-related components through GE Nuclear Energy and were supplied with the
vendor'-s 10 CFR Part 50 Appendix B quality assurance certifications, this
testing was performed by the licensee in addition to the normal quality assur.-
ance receipt inspection.
This information notice requires no specific action or written response. If
you have any questions about 'the information inthis notice, please contact one
of the technical contacts listed below or the appropriate NRR project manager.
Char Rossi Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: K. R. Naidu, NRR
(301) 492-0980
S. D. Alexander, NRR
(301) 492-0995
"
%ase-Cut t.. . ,. Em : lsr; -r. M
Attachment: List of Recently Issued NRC Information Notices
Attachut
June 29. 19 Pap I of 1 LisT OF RECOMT issU£1 IRC IRFUOTION INOTICES
mrformuoe Sit, er
CUoti o Subject Isunc Issued to
30-. Surface Crack and Subsurfete 6/19se All wders of Ke
Suav. 1 Indicatious Is the laid of or ChPfor nuclear
a Reactor vessel Head powr reactors.
90.4 Failure of Electrical Pur 6/19/30 All holden of au
Eqi.pnt Due to Solar or Chafor Wueagr
Slgnotlc Distorbancee powe r .
90-41 Potential Fallen oft General /12/90 All holders of OLa
Electric Nagne-Blast or CPa for nuclear.
Circuit 5peakers and At powr reactors.,
Circuit Breakers
- 3J40 Results of IRC-Sponsorad 6/1/90 All holders of D14 Testing of 1etor-Operatad or Cha for ncler
Talves pr nreactors.
ct RroelasmIH1it
c-39 Service UV1/90 All holders of OLs
water Systauc or CPa for nuolear
poaur reactors.
95>-3 Reirments for Processing 5/29/90 All fuel facility
Financial Assurace Submittals VA matarlala
for Decomissioeing licensus.
90.37 Sheared Pinaio Gear-to-Saft 1/24/90 All holders of a6e
em Is Liaitorque aotor or CPa for nuclear
Actuators pool reactors.
0-36 Apsresnt falsification of 1/24/90 All holders of Os
State Of Connecticut or Chs for nuclear
H1eigt Certificates powe reactors and
10 CFP73 11cauen.
90-31 Transportatios of Type A /24/90 All U.S. N1Clc a.
Quantities of Non-Fissile
Radioactive Matertals
(R
CP* ConItDt10n Permit
UNITED STATES
NUCLEAR REGULATORY COMMISSION PIPT LASAIL1 WASHINGTON, D.C. 206 IPOSTAGE & FEES PAIDI
1 USNRC 1 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 90-43 June 29, 1990 Oyster Creek's routine pre-installation testing procedures detected and pre- vented the use of the faulty MCCBs. Although the MCCBs were procured as
safety-related components through GE Nuclear Energy and were supplied with the
vendor's 10 CFR Part 50 Appendix B quality assurance certifications, this
testing was performed by the licensee in addition to the normal quality assur- ance receipt inspection.
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 NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: K. R. Naidu, NRR
(301) 492-0980
S. D. Alexander, NRR
(301) 492-0995 Attachment: List of Recently Issued NRC Information Notices
Document Name: INFO NOTICE ALEXANDER/2
- C/OGCB:DOEA:NRR*RPB:ADM *D/DRIS:NRR
CHBerlinger TechEd BKGrimes
O6/>'90 06/19/90 06/05/90 06/07/90
- OGCB:DOEA:NRR*VIB:DRIS:NRR *VIB:DRIS:NRR *VIB:DRIS:NRR *C/VIB:DRIS:NRR
NCampbell SAlexander:sdal KNaidu UPotapovs EWBrach
06/22/90 6/06/90 6/06/90 6/06/90 6/06/90
IN 90-XX
June X, 1990 The failure of the Oyster Creek MCCBs in safety-related applications could have
jeopardized the safety of the plant. Oyster Creek's routine pre-installation
testing procedures detected and prevented the use of the faulty MCCBs. Al- though the MCCBs were procured as safety-related components through GENE and
were supplied with the vendor's 10 CFR Part 50 Appendix B quality assurance
certifications, this testing was performed by the licensee in addition to the
normal quality assurance receipt inspection.
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 NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: K. R. Naidu, NRR
(301) 492-0980
S. D. Alexander, NRR
(301) 492-0995 Attachment: List of Recently Issued NRC Information Notices
Document Nlame: INFO NOTICE ALEXANDER/@F
- SEE PREVIOUS CONCURRENCES I
D/DOEA:NRR B RR B:ADM *D/DRIS:NRR
CERossi CHB~~ ih TechEd BKGrimes
06/ /90 06/1j/90 06/05/90 06/07/90
- NRR rVIB:DRIS:NRR *VIB:IDRIS:NRR *VIB:DRIS:NRR *C/VIB:DRIS:NRR
NCampbell SAlexander:sda KNaidu UPotapovs EWBrach
06 /JVJ/90 6/06/90 6/06/90 6/06/90 6/06/90
IN 90-XX
June X, 1990 Oyster Creek's routine preinstallation testing procedures detected and
prevented the use of faulty MCCBs in safety-related applications which could
have jeopardized s t the plant. It should be noted that this testing
was conducted tow w c that these components were procured as safety- related and came with vendor 10 CFR Part 50 Appendix B quality assurance
certifications.
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 NRC regional office.
Charles E. Rossi, Director
Division of Operational Events Assesment
Office of Nuclear Reactor Regulation
Technical Contacts: K. R. Naidu, NRR (301) 492-0980
S. D. Alexander, NRR (301) 492-0995 Attachment: List of Recently Issued NRC Information Notices
OFC :VIB:DRIS:NRR :VIB:DRIS:NRR :VIB:DXIS:NRR :C:VIB-DRIS:NRR:TECH ED :D:DR S:NRR
___________----_____
______------ :--q___ ------- A- -- -------------- :dn --
NAME :SAlexander:sda :UPo povs
- N+df CFc
fE) -- :7tl :B^ yrimes
__ __ _ _ _._..:V:-
- 6/, /90:6 -----. -- __- _ -----
DATE :6/6 /90 :6/ 9 :6/ /90 :6/ 6/90 :6/F/90 .6 90 avO_
. .
OFC B:DOEA:NRR :GCB:DOEA:NRR G
- C:GCB:DOEA:NRR:D:DOEA NRR :
NAME :JJRam :ERossi :
- CBerlinger
DATE :6 /90 :6/ /90 6/ /90 :6/ /90
OFFICIAL RECORD COPY
Document Name: GE MCCB UVR INFO NOTICE
0004.0.0
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Intergranular Stress Corrosion Cracking, Dissimilar Metal Weld, Exclusive Use)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990, Topic: Siren)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits, Stress corrosion cracking)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link, Siren)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990, Topic: Siren)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990, Topic: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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