Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier MaterialML031080040 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
05/26/1993 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-93-040, NUDOCS 9305260385 |
Download: ML031080040 (14) |
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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 STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555May 26, 1993NRC INFORMATION NOTICE 93-40: FIRE ENDURANCE TEST RESULTS FOR THERMALCERAMICS FP-60 FIRE BARRIER MATERIAL
Addressees
All holders of operating licenses or construction permits for nuclear powerreactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to results of fire endurance and ampacity deratingtest reports submitted by Thermal Ceramics on the FireMaster FP-60 firebarrier system and the results of NRC staff reviews. It is expected thatrecipients will review the information for applicability to their facilitiesand consider actions as appropriate, to avoid similar problems. However,suggestions contained in this information notice are not NRC requirements;therefore, no specific action or written response is required.Descriotion of CircumstancesIn Generic Letter (GL) 92-08, wThermo-Lag 330-1 Fire Barriers," the staffstated it would evaluate other known fire barrier materials and systems thatare used by licensees to fulfill NRC fire protection requirements. The staffis now evaluating fire barriers manufactured by other vendors to verify theability of the barriers to adequately perform their 1-hour or 3-hour fireresistive functions and to meet stated ampacity derating values. ThermalCeramics, Inc., formerly the Insulating Products Division of Babcock andWilcox, Inc., of Augusta, Georgia, manufactures the FP-60 fire barrier systemand submitted reports on two fire endurance tests and one ampacity deratingtest to the NRC in a letter of February 23, 1993.DiscussionIn its review of the Thermal Ceramics reports, the staff identified thefollowing information.In its product literature, Thermal Ceramics states that the FP-60 product ismanufactured for use on cable trays, conduits, junction boxes, and other cableraceways. The primary component, the FireMaster FP-60 blanket, is a ceramicfiber blanket with thicknesses varying from 2.5 cm [1 inch] to 7.6 cm[3 inches]. Optional aluminum or stainless steel foil, Kao-Tex (woven cloth),or other cloth facings are provided for physical protection of the blanket.The vendor claims that the material, when installed according to theinstructions, is qualified for up to a 13/4-hour fire rating using the American9305260385 ' P I)oktce. 93-oPOR %'KP~ktcL93sI4 IN 93-40May 26, 1993 Society for Testing and Materials (ASTM) Standard E-119, "Standard TestMethods for Fire Tests of Building Construction and Materials."FIRE ENDURANCE TESTSAccording to one report submitted by Thermal Ceramics, a. 1-hour fire endurancetest of the FP-60 fire barrier in various configurations was performed atUnderwriters Laboratories, Inc. (UL File R11044-1, Project 84NK8356,March 22, 1985). The test followed UL Subject 1724, "Outline ofInvestigation, Fire Tests for Electrical Circuit Protective Systems,"May 1984. According to the report, the furnace temperatures followed theASTM E-119 standard time-temperature curve for fire exposure, and the barrierswere subjected to a solid hose stream test. The report also states thatcircuit integrity was monitored.Documented test configurations included 91.4 cm [36 inch] wide open-ladder andsolid-back steel cable trays, an air drop assembly, 12.7 cm [5 inch] diametersteel conduits, and a 30.5x15.2 cm (12x6 inch] steel Junction box. Allconfigurations contained cables. Two hundred fifty thermocouples werereportedly used to measure temperatures of cables, cable trays, Junction* boxes, conduits and electrical circuit protective systdms on the unexposed1 side of the assembly.x According to the report, within 30 seconds of the start of the test, thej filament tape around the blanket wrap ignited. At 5 minutes, flames# reportedly issued from seams and butt joints. The report also states that at20 minutes, some of the wrap slipped out of position resulting in an opening^ in the barrier, and at 60 minutes, there was a 8.9 cm [3X inch] opening in thebarrier. Some thermocouple measurements reportedly ranged from 204 'C[400 OF] to 260 eC [500 OF] at the end of the fire test.After the test, some cables were documented to be fused together, and cablejackets were melted and blistered. The hose stream eroded the bottom surfaceof the cable tray barrier so that the tray was exposed.The UL report concluded that the tested fire barrier had a 1-hour fire ratingbecause circuit integrity was maintained during the fire exposure and hosestream test. However, it appears that the UL approval is limited to minimum91.4 cm [36 inch] wide cable trays and 12.7 cm [5 inch] or larger-diameterconduits with minimum No. 16 AWG jacketed multi-conductor cables or minimumNo. 300 MCM jacketed copper single conductor power cables with polyvinylchloride jackets.The second fire endurance test report submitted by Thermal Ceramics documenteda Southwest Research Institute small-scale test, "One Hour Fire QualificationTest of a Protective Envelope for Class 1E Electrical Conduit Circuits," (SwRIProject 01-8305-053, February 1986). According to this report, the testemployed the ASTM E-119 standard time-temperature curve for fire exposure anda subsequent solid hose stream test. The report also states that circuitintegrity was monitored. SwRI documented the use of a small-scale furnace(maximum test specimen of 425.8 square cm (66 square inches]) to test a2.5 cm [1 inch] diameter conduit with a pull box, a 5.1 cm [2 inch] diameterconduit with a junction box, and an air drop. According to the report,. these
IN 93-40May 26, 1993 test assemblies each contained a single-conductor power cable and two controlcables, all with PVC jackets.Recorded cable temperatures (measured at the cable jackets) at the end of thefire exposure ranged from 146.5 'C (296 *F] to 164 C (327 OF]. According tothe report, circuit integrity was maintained during the fire exposure and hosestream tests.The barrier and cable conditions after the fire exposure were not reported.The test report suggests that the hose stream test caused some barrier damage,although the test report did not clearly report the extent of damage. SwRIdid not report a conclusion as to the acceptability of the fire barriersystem.In a letter of April 27, 1993 to Thermal Ceramics, Inc., the staff expressedconcerns regarding the ability of the FP-60 system to meet existing NRC firebarrier acceptance criteria.AMPACITY DERATING TESTThe ampacity derating test report submitted by Thermal Ceramics was SwRIProject 01-8818-210, "Ampacity Derating of Fire-Protected Cables in Conduitand Cable Trays Using Babcock & Wilcox, Incorporated's Passive Fire ProtectionSystem," issued by SwRI on July 8, 1986. According to the report, a 1-hourfire barrier was used in the test. Three-conductor XLPE-insulated 6 AWGcables with Hypalon protective wraps were reportedly installed in a61 cm (24 inch] wide by 10.2 cm [4 inch] deep cable tray, and 3-conductorXLPE-insulated 3 AWG cables with Hypalon protective wraps were installed in a10.2 cm [4 inch] diameter conduit. Both assemblies were reported to be3.7 m [12 feet] long and completely filled. The report stated thatthermocouples were installed in slits' in the cable insulation.According to the report, a steady-state temperature of 90 eC (194 *F) at thehottest single thermocouple was monitored. Equilibrium temperature wasreportedly established when a steady-state condition (+/-1 eC per hour (+/-1.8 OFper hour]) was achieved for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> without any perturbation to the system.The ampacity derating for the cable tray and conduit was estimated to be 62.4and 41.4 percent, respectively, based on the test results.Some licensees use the FP-60 fire barrier system to achieve physicalindependence of electrical systems in accordance with Regulatory Guide 1.75,Physical Independence of Electrical Systems." Ampacity derating in firebarrier systems installed to achieve physical independence of electric systemsis a consideration in the design of such systems as well as in those installedto protect safe shutdown capability from a fire.Cables enclosed in electrical raceways protected with fire barrier materialsare derated to ensure that systems have sufficient capacity and capability toperform their intended safety functions. These cables are derated because ofthe insulating effect of the fire barrier material. Other factors that affectampacity derating include cable fill, cable loading, cable type, racewayconstruction, and ambient temperature.
IN 93-40May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservativederating factors could result in installation of undersized cables or racewayoverfilling. This could cause operating temperatures to exceed design limitswithin the raceways thereby reducing the expected design life of the cables.In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staffrequested additional information on ampacity derating.The National Electrical Code, Insulated Cable Engineers Association (ICEA)publications, and other industry standards provide general ampacity deratingfactors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, "Procedure for the Determination of the Ampacity Derating ofFire Protected Cables," for use as an industry standard. The industryconsensus standard development process may formulate an appropriate technicalapproach to the determination of ampacity derating factors for cables enclosedby fire barrier systems.The staff is continuing to review this product for its ability to perform itsfire resistive function and will evaluate whether further genericcommunications are needed to address the issues discussed above.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices
- 2 IN 93-40May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservativederating factors could result in installation of undersized cables or racewayoverfilling. This could cause operating temperatures to exceed design limitswithin the raceways thereby reducing the expected design life of the cables.In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staffrequested additional information on ampacity derating.The National Electrical Code, Insulated Cable Engineers Association (ICEA)publications, and other industry standards provide general ampacity deratingfactors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, "Procedure for the Determination of the Ampacity Derating ofFire Protected Cables,' for use as an industry standard. The industryconsensus standard development process may formulate an appropriate technicalapproach to the determination of ampacity derating factors for cables enclosedby fire barrier systems.The staff is continuing to review this product for its ability to perform itsfire resistive function and will evaluate whether further genericcommunications are needed to address the issues discussed above.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager. Orginal ignd yBrian K. GrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices*See previous concurrence*SPLB:DSSA *SPLB:DSSA *TechEdIMiller SWest DGable05/06/93 , 05/06/93 05/10/93*SPLB:DSSA *OGC *DE:EELBCMcCracken JGoldberg CBerlinger5/20/93 5/20/93 05/25/93*DD:DSSA *D:DSSA *OGCB:DORSMVirgilio AThadani GMarcus Grimes05/25/93 05/25/93 05/25/93 S g&493DOCUMENT NAME: 93-40.IN
IN 93-XXMay xx, 1993 Cable derating calculations that are based on inaccurate or nonconservativederating factors could result in installation of undersized cables or racewayoverfilling. This could cause operating temperatures to exceed design limitswithin the raceways thereby reducing the expected design life of the cables.In the letter to thermal ceramics of April 27, 1993, the staff requestedadditional information on ampacity derating.The National Electrical Code, Insulated Cable Engineers Association (ICEA)publications, and other industry standards provide general ampacity deratingfactors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, "Procedure for the Determination of the Ampacity Derating ofFire Protected Cables," for use as an industry standard. The industryconsensus standard development process may formulate an appropriate technicalapproach to the determination of ampacity derating factors for cables enclosedby fire barrier systems.The staff is continuing to review this product for its ability to perform itsfire resistive function and will evaluate whether further genericcommunications are needed to address the issues discussed above.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices*See previous concurrenceSPLB:DSSA SPLB:DSSA TechEd*IMiller *SWest *DGable05/06/93 05/06/93 05/10/93SPLB:DSSA OGC *DE:EELBCMcCracken* JGoldberg* CBerlinger5/20/93 5/20/93 05/25/93*DD:DSSA *D:DSSA *OGCB:DORS D:DORSMVirgilio AThadani GMarcus BGrimes05/25/93 05/25/93 05/25/93 / /93DOCUMENT NAME: INPSB.1
-- -------------4factors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, Procedure for the Determination of the Ampacity Derating ofFire Protected Cables,' for use as an industry standard. The staff encourageslicensees to participate in the industry consensus standard developmentprocess to formulate an appropriate technical approach to the determination ofampacity derating factors for cables enclosed by fire barrier systems.The staff is continuing to review this product for its ability to perform itsfire resistive function and will take further action if appropriate.This information notice requires no specific action or written response.If you have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices*See previous concurrenceSPLB:DSSA*IMiller05/06/93SPLB:DSSA*SWest05/06/93TechEd*DGable05/10/93SPLB:DSSACMcCracken*5/20/93DD:DSSAMVirgilio*/ /93OGCJGoldberg*5/20/93/D :DSSA MAThadani5 f1;93DE:EELBCBerlinger*/ /93OGCBD;ORS&M GMar~1-/ (/93 AlSD: DORSBGrimes/ /93[G:\THERMOLA\OTHERVEN\IN FP60.R3]Originator: Isabel Miller
_Lfactors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, "Procedure for the Determination of the Ampacity Derating ofFire Protected Cables," for use as an industry standard. The staff encourageslicensees to participate in the industry consensus standard developmentprocess to formulate an appropriate technical approach to the determination ofampacity derating factors for cables enclosed by fire barrier systems.This information notice requires no specific action or written response.The staff is continuing to review this product for its ability to perform itsfire resistive function and will take further action if appropriate. If youhave any questions about the information in this notice, please contact thetechnical contact listed below or the appropriate Office of Nuclear ReactorRegulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices*See previous concurrenceSPLB:DSSA*IMiller05/06/93SPLB:DSSACMcCracken*5/20/93DD:DSSA,~M9irgil 9SPLB:DSSA*SWest05/06/93OGCJGoldberg*5/20/93TechEd*DGable05/10/93DE:EECBerltTrg r-jstk093D:DSSAAThadani/ /93OGCB:DORSGMarcus/ /93D:DORSBGrimes/ /93[G:\THERMOLA\OTHERVEN\IN FP60.R3]Originator: Isabel Miller
.'\1factors for open-air installations but do not include derating factors forfire barrier systems. The Insulated Conductors Committee of the IEEE PowerEngineering Society, Task Force 12-45, has been developing IEEE StandardProcedure P848, "Procedure for the Determination of the Ampacity Derating ofFire Protected Cables," for use as an industry standard. The staff encourageslicensees to participate in the industry consensus standard developmentprocess to formulate an appropriate technical approach to the determination ofampacity derating factors for cables enclosed by fire barrier systems.This information notice requires no specific action or written response. Thestaff is continuing to review this product for its ability to perform its fireresistive function and will take further action if appropriate. Licensees areadvised to consider this information when contemplating any changes to theircurrent fire protection program. If you have any questions about theinformation in this notice, please contact the technical contact listed belowor the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Isabel M. Miller, NRR(301) 504-2852Attachment:List of Recently Issued Information Notices*See previous concurrenceSPLB:DSSA*IMiller05/06/93SPLB:DSSP( ' LCMcCrackelr_.5/P/93DD:DSSAMVirgilio/ /93SPLB:DSSA*SWest05/06/vD:DSSAAThadani/ /93TechEd*DGabl e05/10/93DE:EELBCBerlinger/ /93OGCB:DORSGMarcus/ /93D: DORSBGrimes/ /93[G:\THERMOLA\OTHERVEN\IN FP60.R2]Originator: Isabel Miller
This information notice required 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 RegulationK. Steven West, NRR(301) 504-1220Technical contact:Attachment:List of Recently Issued Information NoticesSPLB:DSSAIMiller/ /93OGCJGoldberg/ /93DD:DSSAGHolahan04/ /93SPLB:DSSASWest/ /93SPLB:DSSACMcCracken/ /93D:DSSAAThadani04/ /936:7/0/93DE:EELBCBerlinger/ /93OGCB:DORSGMarcus04/ /93D: DORSBGrimes/ /93
., --.1; l *consider actions as appropriate.This information notice required 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 contaiAttachment:List of Recentl2SPLB:DSSA,.IMilletgfYL5f/6 /93K. Steven West, NRR(301) 504-1220ssued Information NoticesSIestt576 /93TechEdRiStnde-e/ /93OGCJGoldberg/ /93SPLB:DSSACMcCracken/ /93DE: EELBCBerlinger/ /93DD: DSSAGHolahan04/ /93D: DSSAAThadani04/ /93OGCB:DORSGMarcus04/ /93D: DORSBGrimes/ /93[G:\THERMOLA\FP-60 IN.R1]Originator: IsabeT Miller
I -1AttachmentIN 93-40May 26, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-3993-38Radiation Beams fromPower Reactor Biolog-ical ShieldsInadequate Testing ofEngineered SafetyFeatures ActuationSystem05/25/9305/24/93All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.93-37Eyebolts with Indeter-minate Properties In-stalled in LimitorqueValve Operator HousingCovers05/19/93All holdersfor nuclearof OLs or CPspower reactors.93-36Notifications, Reports,and Records of Misadmin-istrations05/07/93All U.S. Nuclear RegulatoryCommission medicallicensees.93-35Insights from Common-Cause Failure Events05/12/93All holdersfor nuclear(NPPs).of OLs or CPspower plants93-34,Supp. 193-34Potential for Loss ofEmergency CoolingFunction Due to ACombination ofOperational and Post-Loca Debris in Contain-mentPotential for Loss ofEmergency CoolingFunction Due to ACombination ofOperational and Post-Loca Debris in Contain-ment05/06/9304/26/93All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.OL = Operating LicenseCP = Construction Permit
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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