Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables

Potential Deficiency of Certain Class Ie Instrumental and Control Cables

ML031070494
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:	04/28/1993
Revision:	0
From:	Grimes B K Office of Nuclear Reactor Regulation
To:
References
IN-93-033, NUDOCS 9304230163
Download: ML031070494 (12)

I ..K)-UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 28, 1993NRC INFORMATION NOTICE 93-33: POTENTIAL DEFICIENCY OF CERTAIN CLASS IEINSTRUMENTATION AND CONTROL CABLES

Addressees

All holders of operating licenses or construction permits for nuclear powerreactors.PurDoseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to a potential deficiency in the environmentalqualification of certain Class 1E instrumentation and control cables. It isexpected that recipients will review the information for applicability totheir facilities and consider actions, as appropriate to avoid similarproblems. However, suggestions contained in this information notice are notNRC requirements; therefore, no specific action or written response to thisnotice is required.

Description of Circumstances

Sandia National Laboratories, under contract to the NRC, tested cables todetermine the long-term aging degradation behavior of typical instrumentationand control cables used in nuclear power plants and to determine the potentialfor using condition monitoring for assessing residual life. The results ofthis testing are described in NUREG/CR-5772, "Aging, Condition Monitoring, andLoss-of-Coolant Accident (LOCA) Tests of Class IE Electrical Cables," Volumes1, 2, and 3. The tests were conducted on cross-linked polyolefin/poly-ethylene, ethylene propylene rubber, and miscellaneous Class lE cable types.The test program generally followed the guidance of Institute of Electricaland Electronics Engineers (IEEE) Standard 323-1974, "IEEE Standard forQualifying Class IE Equipment for Nuclear Power Generating Stations," and IEEEStandard 383-1974, "IEEE Standard for Type Test of Class IE Electric Cables,Field Splices, and Connections." IEEE Standard 323-1974 is an industry-established standard endorsed by the NRC for qualifying Class 1E equipment fornuclear power generating stations, and IEEE Standard 383-1974 is an industry-established standard for type test of Class IE electric cables, field splices,and connections for nuclear power generating stations.The test program consisted of two phases; both phases used the same testspecimens. Phase 1 consisted of simultaneous thermal and radiation aging ofthe cables at approximately 100 *C (212 *F) and 0.10 kGy per hour (10 kiloradsper hour), respectively. Three different sets of cable specimens were testedin this phase: one was aged to a nominal lifetime of 20 years, a second to40 years, and a third to 60 years. Phase II was a sequential accidentexposure consisting of 1100 kGy (110 megarads) of high-dose-rate irradiation9304230163 LPk. t / 3 °LAoq aark a 1(002098 -J24-&iU e*!~~~~~ `;;1 ; :.tf,-;-., 'E t>., \

IN 93-33April 28, 1993 at the rate of 6 kGy per hour (600 kilorads per hour) followed by a simulatedexposure to LOCA steam. The test profile was similar to the one given in IEEEStandard 323-1974 for "generic' qualification. The cables were energized at110 V dc during the accident simulation. Insulation resistance was measuredon line throughout the test. No chemical spray was used during the steamexposure, but a post-LOCA submergence test was performed on the cables thatwere aged to a nominal equivalent of 40 years.Cable types that failed during the accident tests or that exhibited marginalinsulation resistances were Rockbestos Firewall III, BIW Bostrad 7E, Okonite-Okolon, Samuel Moore Dekoron Dekorad Type 1952, Kerite 1977, RockbestosRSS-6-104/LE Coaxial, and Champlain Kapton. The list of cables included inthe test program and a summary of the test results from NUREG/CR-5772 areshown in Attachments 1 and 2, respectively.In addition, the Sandia National Laboratories (under contract to NRC) has alsotested cables in a separate program to determine the minimum insulationthickness necessary for installed cable to perform its intended functionshould the insulation be damaged during installation, maintenance, or otheractivities. During LOCA testing, all 10 of the Okonite-Okolon cable samplesfailed. The results of this test program are summarized in NRC InformationNotice 92-81, "Potential Deficiency of Electrical Cables With Bonded HypalonJackets," issued on December 11, 1992.DiscussionThe Sandia National Laboratories test results from NRC-sponsored programsraise questions with respect to the environmental qualification (EQ) ofcertain cables that either failed or exhibited marginal insulation resistancevalues. The staff reviewed the test data and noted that cable typesidentified as Firewall III, Okonite, Dekorad, and Kapton failed during thesimulated accident exposure, while BIW Bostrad, Rockbestos Coaxial, and Keriteexhibited marginal insulation resistances. It should be noted that theinsulation resistance of the Rockbestos coaxial cables may be too low to meetspecifications for use in General Atomics radiation monitor circuits,depending on the environment to which the cable will be exposed. The lowinsulation resistance of these Rockbestos coaxial cables was the subject of a10 CFR Part 21, "Reporting of Defects and Noncompliance," notification byGeneral Atomics dated March 28, 1989.As part of the NRC-sponsored aging research program, the Sandia NationalLaboratories searched licensee event reports (LERs) to find LERs that might berelated to cable aging. In NUREG/CR-5461, "Aging of Cables, Connections, andElectrical Penetrations Assemblies Used in Nuclear Power Plants," the SandiaNational Laboratories concluded that although cables are highly reliable IN 93-33April 28, 1993 devices under normal plant operating conditions, with no evidence ofsignificant increases in failure rate with aging, the performance experiencewith these components under actual accident conditions is small. The currentLER data provide a very limited database for this purpose. The onlysignificant data for cables subjected to design-basis events comes from EQtesting.Depending on the application, failure of these cables during or followingdesign-basis events could affect the performance of safety functions innuclear power plants. NRC Generic Letter 88-07, "Modified Enforcement PolicyRelating to 10 CFR 50.49, 'Environmental Qualification of Electric EquipmentImportant to Safety for Nuclear Power Plants'," provides relevant informationon dealing with potential EQ deficiencies. In Generic Letter 88-07, the NRCstated, in part:When a potential deficiency has been identified by the NRC orlicensee in the equipment (i.e., a licensee does not have anadequate basis to establish qualification), the licensee isexpected to make a prompt determination of operability (i.e., thesystem or component is capable of performing its intended designfunction), take immediate steps to establish a plan with areasonable schedule to correct the deficiency, and have writtenjustification for continued operation, which will be available forNRC review.The licensee may be able to make a finding of operability usinganalysis and partial test data to provide reasonable assurancethat the equipment will perform its safety function when called .upon. In this connection, it must also be shown that subsequentfailure of the equipment, if likely under accident conditions,will not result in significant degradation of any safety functionor provide misleading information to the operato l IE 7U .IN 93-33April 28, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Paul Shemanski, NRR(301) 504-1377Ann Dummer, NRR(301) 504-2831Satish Aggarwal, RES(301) 492-3829

Attachments:

1. "Cables Included in the Test Program"2. "Summary of Tested, Failed, and Marginal InsulationResistance Cables"3. List of Recently Issued NRC Information Notices Attachment 1IN 93-33April 28, 1993 CABLES INCLUDED IN THE TEST PROGRAMSupplier1. Brand Rex2. Rockbestos3. Raychem4. SamuelMoore5. Anaconda5a. Anaconda*6. Okonite7. SamuelMoore8. Kerite8a. Kerite9. Rockbestos10. Rockbestos11. Champlain12. BIW**Description30 mil XLPE Insulation, 60 mil CSPE Jacket, 12 AWG, 3/C,600 VFirewall III, 30 mil XLPE Insulation, 45 mil NeopreneJacket, 12 AWG, 3/C, 600 VFlamtrol, 30 mil XLPE Insulation, 12 AWG, 1/C, 600 VDekoron Polyset, 30 mil XLPO Insulation, 45 mil CSPE Jacket,12 AWG, 3/C and Drain, 600 VAnaconda Y Flame-Guard FR-EP, 30 mil EPR Insulation, 45 milCPE Jacket, 12 AWG, 3/C, 600 VAnaconda Flame-Guard EP, 30 mil EPR Insulation, 15 milIndividual CSPE Jackets, 45 mil Overall CSPE Jacket, 12 AWG,3/C, 1000 VOkonite-Okolon, 30 mil EPR Insulation, 15 mil CSPE Jacket,12 AWG, 1/C, 600 VDekoron Dekorad Type 1952, 20 mil EPDM Insulation, 10 milIndividual CSPE Jackets, 45 mil Overall CSPE Jacket, 16 AWG,2/C TSP, 600 VKerite 1977, 70 mil FR Insulation, 40 mil FR Jacket, 12 AWG,1/C, 600 VKerite 1977, 50 mil FR Insulation, 60 mil FR Jacket, 12 AWG,1/C, 600 VRSS-6-104/LE Coaxial Cable, 22 AWG, 1/C Shielded30 mil Firewall Silicone Rubber Insulation, FiberglassBraided Jacket, 16 AWG, 1/C, 600 V5 mil Polyimide (Kapton) Insulation, Unjacketed, 12 AWG, 1/CBostrad 7E, 30 mil EPR Insulation, 15 mil Individual CSPEJackets, 60 mil Overall CSPE Jacket, 16 AWG, 2/C TSP, 600 V* This cable was only used for the multiconductor samples in the 3-monthchamber.** The IR values in BIW Report B915 are approximately one order ofmagnitude higher than the values observed during the Sandia NationalLaboratories testin ;Attachment 2IN 93-33April 28, 1993 Summary of Tested (T), Failed (F),and Marginal Insulation Resistance (IR)* CablesCable TypeFirewall IIIBrand RexPolysetRaychemAnacondaAnacondaBIW BostradBIW BostradOkoniteDekoradDekoradKeriteCoaxialSiliconeKapton**TotalsPre-aged 20 yearsT--F/IRM 3--0/0M 3--0/0M 3--0/0S 2--0/0M 6--0/0S 1--0/0M 2--0/2S 2--O/lS 3--0/0M 4--1/0S 2--0/0S 2--O/oS 2--0/2S 2--0/0S 2--1/039--2/540 yearsT--F/IR3--0/03--0/03--0/02--0/06--0/01--O/O2--0/22--0/23--0/04--0/02--0/02--0/22--0/22--0/02--i/?39--1/860 yearsT--F/IR6--1/03--0/06--0/03--0/06--0/01--O/O4--0/42--0/24--1/04--2/02--0/03--0/32--0/22--0/02--1/050--5/11* Minimum IR lower than 2500 ohm-1900 ft for instrument cable, 500 ohm-1000 ft for control cable, or 10 ohm-1000 ft for coaxial cable.** Failed cables that were pre-aged to 40 and 60 years were damaged priorto accident test.? No IR measurements were possible.S Single conductor cablesM Multiconductor cables i-Attachment 3IN 93-33April 28, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-3293-3193-3093-2993-2893-2793-2693-25Nonconservative Inputsfor Boron DilutionEvent AnalysisTraining of NursesResponsible for theCare of Patients withBrachytherapy ImplantsNRC Requirements forEvaluation of WipeTest Results; Cali-bration of Count RateSurvey InstrumentsProblems with the Useof Unshielded Test Leadsin Reactor ProtectionSystem CircuitryFailure to ConsiderLoss of DC Bus in theEmergency Core CoolingSystem Evaluation MayLead to NonconservativeAnalysisLevel InstrumentationInaccuracies Observedduring Normal PlantDepressurizationGrease SolidificationCauses Molded CaseCircuit BreakerFailure to CloseElectrical PenetrationAssembly Degradation4/21/9304/13/9304/12/9304/12/9304/09/9304/08/9304/07/9304/01/93All holders of OLs or CPsfor pressurized waterreactors (PWRs).All U.S. Nuclear RegulatoryCommission medicallicensees.All U.S. Nuclear RegulatoryCommission medicallicensees.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.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.OL -Operating LicenseCP = Construction Permit

..44IN 93-33?ril 28, 1993Sage 4 of 4If you have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Original signed 6yBrian K. GrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Paul Shemanski, NRR(301) 504-1377Ann Dummer, NRR(301) 504-2831Satish Aggarwal,(301) 492-3829RES

Attachments:

1. "Cables Included in the Test Program"2. "Summary of Tested, Failed, and MarginalResistance Cables3. List of Recently Issued NRC InformationInsulationNotices*SEE PREVIOUS CONCURRENCESPDLR*PShemanski4/21/93OGCB:DORS*GMarcus4/23/93DSSA: SPLB*GHubbard4D,1DSSA: SPLB*CMcCracken4/21/93Tech Ed.*RSanders4/12/93OGCB: DORS*TJKlim4/21/93DE: RES*LShao4/22/93DSSA:NRR*AThadanli4/23/93Document Name: 93-33.IN AttL.,%ent 3IN 93-33April 28, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-3293-3193-3093-29Nonconservative Inputsfor Boron DilutionEvent AnalysisTraining of NursesResponsible for theCare of Patients withBrachytherapy ImplantsNRC Requirements forEvaluation of WipeTest Results; Cali-bration of Count RateSurvey InstrumentsProblems with the Useof Unshielded Test Leadsin Reactor ProtectionSystem CircuitryFailure to ConsiderLoss of DC Bus in theEmergency Core CoolingSystem Evaluation MayLead to NonconservativeAnalysisLevel InstrumentationInaccuracies Observedduring Normal PlantDepressurization4/21/9304/13/9304/12/9304/12/9304/09/9304/08/9304/07/9304/01/93All holders of OLs or CPsfor pressurized waterreactors (PWRs).All U.S. Nuclear RegulatoryCommission medicallicensees.All U.S. Nuclear RegulatoryCommission medicallicensees.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.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.93-2893-27Grease SolidificationCauses Molded CaseCircuit BreakerFailure to CloseElectrical PenetrationAssembly DegradationOL -Operating LicenseCP = Construction Permit IN 93-xxApril , 1993 If you have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Paul Shemanski, NRR(301) 504-1377Ann Dummer, NRR(301) 504-2831Satish Aggarwal, RES(301) 492-3829

Attachments:

1. "Cables Included in the Test Program"2. "Summary of Tested, Failed, and Marginal InsulationResistance Cables"3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCESPDLR*PShemanski4/21/93DSSA:SPLB*GHubbard4/21/93DSSA:SPLB*CMcCracken4/21/93Tech Ed.*RSanders4/12/93OGCB:DORS*TJKim4/2.1/93DE:RES R*LShaQ" AThadani4/2z52 ' 4/z3/93OGCB:DORSGMarcup~yd4/.z3/9W='DORS:NRRBGrimes >4/ /93w1Document Name: \EQ1.INF

--1k_,A 93-xxApril , 1993 data provide a very limited database for this purpose.data for cables subjected to design-basis events comesThe only significantfrom EQ testing.Depending on the application, failure of these cables during or followingdesign-basis events could affect the performance of safety functions innuclear power plants. NRC Generic Letter 88-07, "Modified Enforcement PolicyRelating to 10 CFR 50.49, 'Environmental Qualification of Electric EquipmentImportant to Safety for Nuclear Power Plants,'" provides relevant informationon dealing with potential EQ deficiencies. In Generic Letter 88-07, the NRCstated, in part:"When a potential deficiency has been identified by the NRC orlicensee in the equipment (i.e., a licensee does not have anadequate basis to establish qualification), the licensee isexpected to make a prompt determination of operability (i.e., thesystem or component is capable of performing its intended designfunction), take immediate steps to establish a plan with areasonable schedule to correct the deficiency, and have writtenJustification for continued operation, which will be available forNRC review.The licensee may be able to make a finding of operability usinganalysis and partial test data to provide reasonable assurancethat the equipment will perform its safety function when calledupon. In this connection, it must also be shown that subsequentfailure of the equipment, if likely under accident conditions,will not result in significant degradation of any safety functionor provide misleading information to the operator."If you have any questions about the information in this notice, please contactthe technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Paul Shemanski, NRR(301) 504-1377Ann Dummer, NRR(301) 504-2831Satish Aggarwal, RES(301) 492-3829

Attachments:

1. "Cables Included2. List of Recently*SEE PREVIOUS CONCURRENCESPDLR DSSA:SPLB DSSA:SPLBPShemanski GHubbard CMcCracken4/21/93 4/21/93 4/21/93TecRSa4/1in the Test Program"Issued NRC Information Notices:h Ed. OGCB!DORS D X 'tnders TJKim LShao12/93 4/12/93 4/z J93ss \hsDSSA:NRRAThadani4/ /93OGCB:DORS DORS:NRRGMarcus BGrimes4/ /93 4/ /93Document Name: \EQ1.INF

.- <_> q93-xx4D~r I ,1993 data provide a very limited database for this purpose. The only significantdata for cables subjected to design-basis events comes from EQ testing.Depending on the application, failure of these cables during or followingdesign-basis events could affect the performance of safety functions innuclear power plants. NRC Generic Letter 88-07, "Modified Enforcement PolicyRelating to 10 CFR 50.49, 'Environmental Qualification of Electric EquipmentImportant to Safety for Nuclear Power Plants," provides relevant informationon dealing with potential EQ deficiencies. In Generic Letter 88-07, the NRCstated, in part:"When a potential deficiency has been identified by the NRC orlicensee in the equipment (i.e., a licensee does not have anadequate basis to establish qualification), the licensee isexpected to make a prompt determination of operability (i.e., thesystem or component is capable of performing its intended designfunction), take immediate steps to establish a plan with areasonable schedule to correct the deficiency, and have writtenJustification for continued operation, which will be available forNRC review.The licensee may be able to make a finding of operability usinganalysis and partial test data to provide reasonable assurancethat the equipment will perform its safety function when calledupon. In this connection, it must also be shown that subsequentfailure of the equipment, if likely under accident conditions,will not result in significant degradation of any safety functionor provide misleading information to the operator."If you have any questions about the information in this notice, please contactthe technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Paul Shemanski, NRR(301) 504-1377Ann Dummer, NRR(301) 504-2831Satish Aggarwal, RES(301) 492-3829

Attachments:

1. "Cables Included in the Test Program"2. List of Recently Issued NRC Information NoticesPDLR'4 r'l DSS A: (B S SA PLB Tech Ed. OGCB:DORS OGCB:DORS DORS:NRRPShemawski GHubbard CMcCracken RSanders TJKim GMarcus BGrimes4/21/93 4/21/93 412.//93 4/ /93 4/ /93 4/ /93 4/ /93Document Name: G:\IN-PAUL.CJF