Information Notice 1995-52, Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials

Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials

ML031060151
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:	11/14/1995
Revision:	0
From:	Crutchfield D M Office of Nuclear Reactor Regulation
To:
References
GL-86-010 IN-95-052, NUDOCS 9511080324
Download: ML031060151 (11)

November 14, 1995

NRC INFORMATION NOTICE 95-52: FIRE ENDURANCE TEST RESULTS FOR ELECTRICALRACEWAY FIRE BARRIER SYSTEMS CONSTRUCTED FROM3M COMPANY INTERAM FIRE BARRIER MATERIALS

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 inform addressees of the results of recent fire endurance tests forelectrical raceway fire barrier systems constructed from 3M Company Interamfire barrier materials. It is expected that recipients will review theinformation for applicability to their facilities and consider thisinformation, as appropriate, in their review of Interam fire barriers.BackaroundOn April 20, May 17, and July 7, 1995, the NRC staff visited Omega PointLaboratories (OPL), San Antonio, Texas, to witness full-scale fire endurancetests for electrical raceway fire barrier systems constructed from 3M CompanyInteram fire barrier materials. These tests were sponsored by Peak SealsCorporation (Peak Seals). Peak Seals informed the NRC staff that the testspecimens included in this test program were intended to represent genericInteram fire barrier systems and that these test programs were conducted inaccordance with Generic Letter (GL) 86-10, Supplement 1, 'Fire Endurance TestAcceptance Criteria for Fire Barrier Systems Used To Separate Redundant SafeShutdown Trains Within the Same Fire Area." The following information isbased on observations made by the NRC staff who witnessed these fire tests.The NRC staff has not reviewed the test reports.

Description of Circumstances

1-Hour Fire Endurance TestsThe first test assembly included nominal 24-inch and 6-inch-wide steel cabletrays; 1-inch, 2-inch, 3-inch, and 5-inch-diameter steel conduits; a 2-inchdiameter air drop; each was arranged in a U-shaped configuration; and a12-inch by 12-inch by 8-inch steel junction box. With regard to the 2-inch-diameter steel conduit, the Junction box was installed in one of its verticalruns and the 2-inch diameter air drop was installed in the other. These testspecimens did not include cable fill and were supported by a common trapeze9511080324- K4 //6t~zEzt-0 t f51(14 IN 95-52November 14, 1995 support. They were protected with three layers of Interam E53A fire barriermat material. Each layer was 7.6 mm [0.3 inch] thick.On April 20, 1995, OPL subjected the test assembly to the test fire specifiedin American Society for Testing and Materials (ASTM) Standard E-119, "FireTest of Building Construction and Materials," for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After the fireexposure, the test specimens were subjected to a fog-nozzle hose stream test.The 24-inch-wide cable tray; the 3-inch-, 2-inch-, and 1-inch-diameterconduits; and the air drop exceeded the temperature rise acceptance criteriaof GL 86-10, Supplement 1, near the end of the 1-hour fire exposure. None ofthe barriers burned through during the fire exposure nor were they breached bythe hose stream. Table 1 (see Attachment 1) summarizes the test specimen andfire barrier configurations and the results of the April 20, 1995, test.The second test assembly included a 24-inch-wide steel cable tray, 1-inch- and5-inch-diameter steel conduits, and a 2-inch-diameter air drop. These testspecimens did not contain cables and were protected with three layers ofInteram E54A fire barrier mat material. Each layer was 10 mm [0.4 inch]thick.On May 17, 1995, OPL subjected the test assembly to the test fire specified inASTM Standard E-119 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After the fire exposure, it subjected thetest specimens to a fog-nozzle hose stream test. These 1-hour test specimensmet the acceptance criteria of Supplement 1 to GL 86-10. Table 2 (seeAttachment 1) summarizes the test specimen and fire barrier configurations andthe results of the May 17, 1995, test.3-Hour Fire Endurance TestThe third test assembly included nominal 24-inch- and 6-inch-wide steel cabletrays; nominal 1-inch-, 3-inch-, and 5-inch-diameter steel conduits; a 2-inch-diameter air drop; each was arranged in a U-shaped configuration; and anominal 12-inch by 12-inch by 8-inch steel junction box. The cable trays werefilled with a single layer of mix cables. The cable trays, the 1-inch- and3-inch-diameter steel conduits, and the air drop were protected with fivelayers of Interam E54A fire barrier mat material. The 5-inch-diameter conduitand the Junction box were protected with six layers of Interam E54A firebarrier mat material. Each layer was 10 mm [0.4 inch] thick.On July 7, 1995, OPL subjected the test assembly to the test fire specified inASTM Standard E-119 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. After the fire exposure, it subjected thetest specimens to a fog-nozzle hose stream test. The barriers did not burnthrough during the fire exposure, nor were they breached by the hose stream.There was no visible damage to the test specimen cables. However, all of thetest specimens exceeded the temperature rise acceptance criteria of GL 86-10,Supplement 1. Table 3 (see Attachment 1) summarizes the test specimen andfire barrier configurations and the results of the July 7, 1995 test.DiscussionSection 50.48 of Title 10 of the Code of Federal Regulations requires thateach operating nuclear power plant must have a fire protection plan that IN 95-52November 14, 1995 satisfies General Design Criterion (GDC) 3 of Appendix A to 10 CFR Part 50.Fire protection features required to satisfy GDC 3 include features to ensurethat one train of systems necessary to achieve and maintain shutdownconditions is free of fire damage. One means of satisfying this requirementis to separate one safe shutdown train from its redundant train with a fire-rated barrier. The level of fire resistance required of the barrier, 1 houror 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, depends on the other fire protection features in the fire area.The NRC issued guidance on acceptable methods of satisfying the regulatoryrequirements of GDC 3 in Branch Technical Position (BTP) Auxiliary and PowerConversion Systems Branch (APCSB) 9.5-1, 'Guidelines for Fire Protection forNuclear Power Plants"; Appendix A to BTP APCSB 9.5-1; BTP Chemical EngineeringBranch (CMEB) 9.5-1, "Fire Protection for Nuclear Power Plants"; and GL 86-10,"Implementation of Fire Protection Requirements." These guidance documentsstate that the fire resistance ratings of fire barriers should be establishedin accordance with National Fire Protection Association (NFPA) Standard 251,"Standard Methods of Fire Tests of Building Construction and Materials"(1975), by subjecting a representative test specimen to a standard fireexposure.On March 25, 1994, the NRC issued Supplement 1 to GL 86-10 to (1) clarify theapplicability of the test acceptance criteria in GL 86-10 to raceway firebarrier systems, (2) specify a set of fire endurance test acceptance criteriathat are acceptable for demonstrating that fire barrier systems can performthe required fire-resistive function and maintain the protected safe shutdowntrain free of fire damage, (3) specify acceptable options for hose streamtesting, and (4) specify criteria for cable functionality testing when adeviation is necessary, such as when the fire barrier temperature risecriteria are exceeded or the test specimen cables sustain visible damage.These positions are incorporated by the NRC staff in its review and evaluationof the adequacy of fire endurance tests and fire barrier systems proposed bylicensees or applicants to satisfy existing NRC fire protection rules andregulations.Some temperatures observed during the tests exceeded the maximum allowabletemperature acceptance criteria of Supplement 1 to GL 86-10. In accordancewith this supplement, an engineering evaluation could be performed todetermine the acceptability of an in-plant Interam fire barrier that wasbounded by a deviating test specimen configuration. Information about suchevaluations can be found in Enclosure 2 of Supplement 1 to GL 86-10. Byletter dated August 7, 1995 [accession number 9509050173 ], Peak Sealssubmitted to the NRC staff additional documentation relating to the thermalperformance of the 3-hour fire barrier test specimens for information.1 NFPA adopted ASTM Standard E-119 as NFPA Standard 25 IN 95-52November 14, 1995 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 Regulation (NRR) project manager.fiel rectorDivision of Reactor Pr ram ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Patrick M. Madden, NRR(301) 415-2854Amarjit Singh, NRR(301) 415-1237

Attachments:

1. Tables 1, 2, and 3, Summaries of Endurance Tests2. List of Recently Issued NRC Information Notices K>_Att__Lament 1IN 9-5-52November 14, 1995 Tnhla 1 mnrmarv nf Anril 20. 1995 Fire Endurance TestPeak Seals -3M Company 1-Hour Interam Fire BarriersAllowable single point unexposed-side temperature criterion -399 F'Allowable average unexposed-side temperature criterion -324 OF(Shading shows temperatures that exceeded, acceptance criteria of GL 86-10 Supplement 1)TEST SPECIMEN THERMOCOUPLE AVERAGE MAXIMUM REMARKSILOCATIONS (OF)(F)}6" Cable trayFront side rail262338Protected with three layers ofInteram E53A.Rear side rail J 262 337Copper conductorIlaMet acceptance criteria.24" Cable tray Front side railRear side railCopper conductorProtected with four layers ofInteram E53A.Exceeded the maximum single pointtemperature criterion at 50X minutesand the average temperature risecriterion at 54X minutes.______________ .45" ConduitConduit surfaceCopper conductor1 277 1 370I2172753" Conduit Conduit surfaceCopper conductor2" Conduit Conduit surfaceCopper conductor1- Conduit Conduit surfaceCopper conductor2" air drop Copper conductorProtected with three layers ofInteram E53A.Met acceptance criteria.Protected with three layers ofInterarn E53A.Exceeded the maximum single pointtemperature criterion at 59 X minutesand the average temperature risecriterion at 53 X minutes.Protected with three layers ofInteram E54A.Exceeded the maximum single pointtemperature criterion at 55X minutesand the average temperature risecriterion at 55 minutes.Protected with two layers ofInteram E53A and an outer layer ofInteram E54A.Exceeded maximum single pointtemperature criterion at 49X minutesand the average temperature risecriterion at 52 minutes._________________________________ IProtected with three layers ofInteram E54A.Exceeded average temperature risecriterion at 59 minutes._______ .-Junction box2S7311Protected with three layers ofInteram E54A.Met acceptance criteria.'Temperatures measured during testing and the acceptance temperatures are presented in aF inall Tables of this attachment to minimize error and confusio Att.,,_ment 1IN 95;-52November 14, 1995 Table 2. Summary of May 17, 1995 Fire Endurance TestPeak Seals -3M Company 1-Hour Interam Fire BarrierAllowable single point unexposed-side temperature criterion .405 OFAllowable average unexposed-side temperature criterion -330 OFTEST SPECIMEN THERMOCOUPLE AVERAGE MAXIMUM REMARKSLOCATIONS (OF) (OF'24" Cable tray Front side rail 290 389 Protected with three layers of 3MInteram E54ARear side rail 301 354Met acceptance criteria.Copper conductor 22265 l_______________5' Conduit Conduit surface 224 251 Protected with three layers of E54A.Copper conductor 217 244 Met acceptance criteria.1" Conduit Conduit surface 308 374 Protected with three layers of E54A.Copper conductor 286 346 Met acceptance criteria.2" Air drop Copper conductor 242 279 Protected with three layers ofInteram E54A.Met acceptance criteri At lament 1IN 95-52November 14, 1995 Table 3. Summary of July 7. 1995 Fire Endurance TestPeak SeaAllowable single ;Allowable averal(Shading shows temperatureTEST SPECIMEN THERMOCOUPLELOCATIONS6" Cable tray Front side railRear side railCopper conductor24" Cable tray Front side railRear side railCopper conductor5" Conduit Conduit surfaceCopper conductor3' Conduit Conduit surfaceCopper conductor1" Conduit Conduit surfaceCopper conductor2" Air drop Copper conductorJunction box Metal surfaceIs- 3M Company 3-Hour Interam Fire BarrierpiInt unexposed-side temperature criterion -407 OFge unexposed-side temperature criterloon -332 OFa that exceeded acceptance criteria of GL 86-10. Supplement 1).AVERAGE([F)IMAXIMUM(1F)IREMARKSProtected with five layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion at 158 minutes and theaverage temperature rise criterion at166 minutes.301 343406243 334Protected with five layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion at 176 minutes and theaverage temperature rise criterion at167 minutes.Protected with five layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion at 161 minutes and theaverage temperature rise criterion at178 minutes..Protected with five layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion at 148 minutes and theaverage temperature rise criterion at152 minutes.Protected with six layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion at 126 minutes and thesversge temperature rise criterion at167 minutes..Protected with five layers ofInteram E54A. Exceeded themaximum single point temperaturecriterion and the average temperaturerise criterion at 152 minutes..Protected with six layers ofInteram E54A. Exceeded the averagetemperature rise criterion at 165minute < ~tachment 2IN 95-52November 14, 1995 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-5195-5095-4995-4895-4795-4695-12,Supp. 195-4595-44Recent Incidents InvolvingPotential Loss of Controlof Licensed MaterialSafety Defect in Gammamed12i Bronchial CatheterClamping AdaptersSeismic Adequacy ofThermo-Lag PanelsResults of Shift StaffingStudyUnexpected Opening of aSafety/Relief Valve andComplications InvolvingSuppression Pool CoolingStrainer BlockageUnplanned, UndetectedRelease of Radioactivityfrom the Exhaust VentilationSystem of a Boiling WaterReactorPotentially NonconformingFasteners Supplied byA&G Engineering II, Inc.American Power ServiceFalsification of AmericanSociety for NondestructiveTesting (ASNT) CertificatesEnsuring Compatible Use ofDrive Cables IncorporatingIndustrial Nuclear CompanyBall-Type Male Connectors10/27/9510/30/9510/27/9510/10/9510/04/9510/06/9510/05/9510/04/9509/26/95All material and fuelcycle licensees.All High Dose RateAfterloader (HDR) Adapters.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.All holders of OLs or CPsfor nuclear power reactors.All Radiography Licensees.OL = Operating LicenseCP = Construction Permit IN 95-52November 14, 1995 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 Regulation (NRR) project manager.orig /s/'d by DNCrutchfieldDennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Patrick M. Madden, NRR(301) 415-2854Amarjit Singh, NRR(301) 415-1237

Attachments:

1. Tables 1, 2, anm2. List of Recentl,AWAS43, Summaries of Endurance TestsIssued NRC Information Notices&&I--6'zp "'Ilke4-TechEd reviewed this document on 9/11/95DOCUMENT NAME: 95-52.INTo ,eceive a copy of this document, Indicate In the box: *C' a Copy Without attachientenctoSurM IE -Copy with attachmentlwclosure IN' -No copyiOFFICE PECB:DRPM* l C:PECB/DRPM* I D/DRPV1J-n,1 A iNAME IJCarter IAEChaffee DMCruVif!el dDATE 09/28/95 11/02/95 111/ /95OFFICIAL RECORD COPY IN 95-xxNovember xx, 995This 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 Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Patrick M. Madden, NRR(301) 415-2854Amarjit Singh, NRR(301) 415-1237

Attachments:

1. Tables 1, 2, and 3, Summaries of Endurance Tests2. List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\IN\3MINTo mcev. a copy of Weh docunnt. inducate I the box: IC' -Copy without attachment/encloss 'Ew

• Copy with attachmentoneloesureOFFICE SPLB:DSSA* I ADM:PUB* PECB:DRPM* I C:PER RRPMNAME ASingh Tech Editor JCarter/RLD A~hOWDATE 09/28/95 109/11/95 l09/28/95 ti/2/g§PL3OFFICE ID:DRPM/NRR I II.N. .No copy!NAME 1DPMCrutchfieldJDATE I1 4 ! !J5I~~OFFICIAL RECORD COPY IN 95-xxSeptember xx, 1995 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 Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Patrick M. Madden, NRR(301) 415-2854Amarjit Singh, NRR(301) 415-1237

Attachments:

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