Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material: Difference between revisions
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| issue date = 05/26/1993 | | issue date = 05/26/1993 | ||
| title = Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material | | title = Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material | ||
| author name = Grimes B | | author name = Grimes B | ||
| author affiliation = NRC/NRR | | author affiliation = NRC/NRR | ||
| addressee name = | | addressee name = | ||
Line 14: | Line 14: | ||
| page count = 14 | | page count = 14 | ||
}} | }} | ||
{{#Wiki_filter:UNITED | {{#Wiki_filter:UNITED STATES | ||
NUCLEAR REGULATORY COMMISSION | |||
OFFICE OF NUCLEAR REACTOR REGULATION | |||
WASHINGTON, D.C. 20555 May 26, 1993 NRC INFORMATION NOTICE 93-40: FIRE ENDURANCE TEST RESULTS FOR THERMAL | |||
CERAMICS FP-60 FIRE BARRIER MATERIAL | |||
==Addressees== | ==Addressees== | ||
All holders of operating licenses or construction permits for nuclear | All holders of operating licenses or construction permits for nuclear power | ||
reactors. | |||
==Purpose== | ==Purpose== | ||
The U.S. Nuclear Regulatory Commission (NRC) is issuing this | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information | ||
notice to alert addressees to results of fire endurance and ampacity derating | |||
test reports submitted by Thermal Ceramics on the FireMaster FP-60 fire | |||
barrier system and the results of NRC staff reviews. 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 are not NRC requirements; | |||
therefore, no specific action or written response is required. | |||
===Descriotion of Circumstances=== | |||
In Generic Letter (GL) 92-08, wThermo-Lag 330-1 Fire Barriers," the staff | |||
stated it would evaluate other known fire barrier materials and systems that | |||
are used by licensees to fulfill NRC fire protection requirements. The staff | |||
is now evaluating fire barriers manufactured by other vendors to verify the | |||
ability of the barriers to adequately perform their 1-hour or 3-hour fire | |||
resistive functions and to meet stated ampacity derating values. Thermal | |||
Ceramics, Inc., formerly the Insulating Products Division of Babcock and | |||
Wilcox, Inc., of Augusta, Georgia, manufactures the FP-60 fire barrier system | |||
and submitted reports on two fire endurance tests and one ampacity derating | |||
test to the NRC in a letter of February 23, 1993. | |||
Discussion | |||
In its review of the Thermal Ceramics reports, the staff identified the | |||
following information. | |||
In its product literature, Thermal Ceramics states that the FP-60 product is | |||
manufactured for use on cable trays, conduits, junction boxes, and other cable | |||
raceways. The primary component, the FireMaster FP-60 blanket, is a ceramic | |||
fiber 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 the | |||
instructions, is qualified for up to a 13/4-hour fire rating using the American | |||
9305260385 ' P I)oktce. 93-o | |||
POR %'K | |||
P~ktcL93sI4 | |||
IN 93-40 | |||
May 26, 1993 Society for Testing and Materials (ASTM) Standard E-119, "Standard Test | |||
Methods for Fire Tests of Building Construction and Materials." | |||
FIRE ENDURANCE TESTS | |||
According to one report submitted by Thermal Ceramics, a.1-hour fire endurance | |||
test of the FP-60 fire barrier in various configurations was performed at | |||
Underwriters Laboratories, Inc. (UL File R11044-1, Project 84NK8356, March 22, 1985). The test followed UL Subject 1724, "Outline of | |||
Investigation, Fire Tests for Electrical Circuit Protective Systems," | |||
May 1984. According to the report, the furnace temperatures followed the | |||
ASTM E-119 standard time-temperature curve for fire exposure, and the barriers | |||
were subjected to a solid hose stream test. The report also states that | |||
circuit integrity was monitored. | |||
Documented test configurations included 91.4 cm [36 inch] wide open-ladder and | |||
solid-back steel cable trays, an air drop assembly, 12.7 cm [5 inch] diameter | |||
steel conduits, and a 30.5x15.2 cm (12x6 inch] steel Junction box. All | |||
configurations contained cables. Two hundred fifty thermocouples were | |||
reportedly used to measure temperatures of cables, cable trays, Junction | |||
* boxes, conduits and electrical circuit protective systdms on the unexposed | |||
1 side of the assembly. | |||
x According to the report, within 30 seconds of the start of the test, the | |||
j filament tape around the blanket wrap ignited. At 5 minutes, flames | |||
# reportedly issued from seams and butt joints. The report also states that at | |||
20 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 the | |||
barrier. 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 cable | |||
jackets were melted and blistered. The hose stream eroded the bottom surface | |||
of the cable tray barrier so that the tray was exposed. | |||
The UL report concluded that the tested fire barrier had a 1-hour fire rating | |||
because circuit integrity was maintained during the fire exposure and hose | |||
stream test. However, it appears that the UL approval is limited to minimum | |||
91.4 cm [36 inch] wide cable trays and 12.7 cm [5 inch] or larger-diameter | |||
conduits with minimum No. 16 AWG jacketed multi-conductor cables or minimum | |||
No. 300 MCM jacketed copper single conductor power cables with polyvinyl | |||
chloride jackets. | |||
The second fire endurance test report submitted by Thermal Ceramics documented | |||
a Southwest Research Institute small-scale test, "One Hour Fire Qualification | |||
Test of a Protective Envelope for Class 1E Electrical Conduit Circuits," (SwRI | |||
Project 01-8305-053, February 1986). According to this report, the test | |||
employed the ASTM E-119 standard time-temperature curve for fire exposure and | |||
a subsequent solid hose stream test. The report also states that circuit | |||
integrity was monitored. SwRI documented the use of a small-scale furnace | |||
(maximum test specimen of 425.8 square cm (66 square inches]) to test a | |||
2.5 cm [1 inch] diameter conduit with a pull box, a 5.1 cm [2 inch] diameter | |||
conduit with a junction box, and an air drop. According to the report,. these | |||
IN 93-40 | |||
May 26, 1993 test assemblies each contained a single-conductor power cable and two control | |||
cables, all with PVC jackets. | |||
Recorded cable temperatures (measured at the cable jackets) at the end of the | |||
fire exposure ranged from 146.5 'C (296 *F] to 164 C (327 OF]. According hoseto | |||
the report, circuit integrity was maintained during the fire exposure and | |||
stream 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. SwRI | |||
did not report a conclusion as to the acceptability of the fire barrier | |||
system. | |||
In a letter of April 27, 1993 to Thermal Ceramics, Inc., the staff expressed | |||
concerns regarding the ability of the FP-60 system to meet existing NRC fire | |||
barrier acceptance criteria. | |||
===AMPACITY DERATING TEST=== | |||
The ampacity derating test report submitted by Thermal Ceramics was SwRI | |||
Project 01-8818-210, "Ampacity Derating of Fire-Protected Cables in Conduit | |||
and Cable Trays Using Babcock & Wilcox, Incorporated's Passive Fire Protection | |||
System," issued by SwRI on July 8, 1986. According to the report, a 1-hour | |||
fire barrier was used in the test. Three-conductor XLPE-insulated 6 AWG | |||
cables with Hypalon protective wraps were reportedly installed in a | |||
61 cm (24 inch] wide by 10.2 cm [4 inch] deep cable tray, and 3-conductor | |||
XLPE-insulated 3 AWG cables with Hypalon protective wraps were installed in a | |||
10.2 cm [4 inch] diameter conduit. Both assemblies were reported to be | |||
3.7 m [12 feet] long and completely filled. The report stated that | |||
thermocouples were installed in slits' in the cable insulation. | |||
According to the report, a steady-state temperature of 90 eC (194 *F) at the | |||
hottest single thermocouple was monitored. Equilibrium temperature was | |||
reportedly established when a steady-state condition (+/-1 eC per hour (+/-1.8 OF | |||
per hour]) was achieved for 3 hours without any perturbation to the system. | |||
The ampacity derating for the cable tray and conduit was estimated to be 62.4 and 41.4 percent, respectively, based on the test results. | |||
Some licensees use the FP-60 fire barrier system to achieve physical | |||
independence of electrical systems in accordance with Regulatory Guide 1.75, Physical Independence of Electrical Systems." Ampacity derating in fire | |||
barrier systems installed to achieve physical independence of electric systems | |||
is a consideration in the design of such systems as well as in those installed | |||
to protect safe shutdown capability from a fire. | |||
Cables enclosed in electrical raceways protected with fire barrier materials | |||
are derated to ensure that systems have sufficient capacity and capability to | |||
perform their intended safety functions. These cables are derated because of | |||
the insulating effect of the fire barrier material. Other factors that affect | |||
ampacity derating include cable fill, cable loading, cable type, raceway | |||
construction, and ambient temperature. | |||
IN 93-40 | |||
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative | |||
derating factors could result in installation of undersized cables or raceway | |||
overfilling. This could cause operating temperatures to exceed design limits | |||
within the raceways thereby reducing the expected design life of the cables. | |||
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff | |||
requested additional information on ampacity derating. | |||
The National Electrical Code, Insulated Cable Engineers Association (ICEA) | |||
publications, and other industry standards provide general ampacity derating | |||
factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, "Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables," for use as an industry standard. The industry | |||
consensus standard development process may formulate an appropriate technical | |||
approach to the determination of ampacity derating factors for cables enclosed | |||
by fire barrier systems. | |||
The staff is continuing to review this product for its ability to perform its | |||
fire resistive function and will evaluate whether further generic | |||
communications are needed to address the issues discussed above. | |||
This information notice requires no specific action or written response. If | |||
you have any questions about the information in this notice, please contact | |||
the technical contact listed below or the appropriate Office of Nuclear | |||
Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
===List of Recently Issued Information Notices=== | |||
*2 IN 93-40 | |||
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative | |||
derating factors could result in installation of undersized cables or raceway | |||
overfilling. This could cause operating temperatures to exceed design limits | |||
within the raceways thereby reducing the expected design life of the cables. | |||
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff | |||
requested additional information on ampacity derating. | |||
The National Electrical Code, Insulated Cable Engineers Association (ICEA) | |||
publications, and other industry standards provide general ampacity derating | |||
factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, "Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables,' for use as an industry standard. The industry | |||
consensus standard development process may formulate an appropriate technical | |||
approach to the determination of ampacity derating factors for cables enclosed | |||
by fire barrier systems. | |||
The staff is continuing to review this product for its ability to perform its | |||
fire resistive function and will evaluate whether further generic | |||
communications are needed to address the issues discussed above. | |||
This information notice requires no specific action or written response. If | |||
you have any questions about the information in this notice, please contact | |||
the technical contact listed below or the appropriate Office of Nuclear | |||
Reactor Regulation (NRR) project manager. Orginal ignd y | |||
Brian K.Grimes | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
List of Recently Issued Information Notices | |||
*See previous concurrence | |||
*SPLB:DSSA *SPLB:DSSA *TechEd | |||
IMiller SWest DGable | |||
05/06/93 , 05/06/93 05/10/93 | |||
*SPLB:DSSA *OGC *DE:EELB | |||
CMcCracken JGoldberg CBerlinger | |||
5/20/93 5/20/93 05/25/93 | |||
*DD:DSSA *D:DSSA *OGCB:DORS | |||
MVirgilio AThadani GMarcus Grimes | |||
05/25/93 05/25/93 05/25/93 S g&493 DOCUMENT NAME: 93-40.IN | |||
IN 93-XX | |||
May xx, 1993 Cable derating calculations that are based on inaccurate or nonconservative | |||
derating factors could result in installation of undersized cables or raceway | |||
overfilling. This could cause operating temperatures to exceed design limits | |||
within the raceways thereby reducing the expected design life of the cables. | |||
In the letter to thermal ceramics of April 27, 1993, the staff requested | |||
additional information on ampacity derating. | |||
The National Electrical Code, Insulated Cable Engineers Association (ICEA) | |||
publications, and other industry standards provide general ampacity derating | |||
factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, "Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables," for use as an industry standard. The industry | |||
consensus standard development process may formulate an appropriate technical | |||
approach to the determination of ampacity derating factors for cables enclosed | |||
by fire barrier systems. | |||
The staff is continuing to review this product for its ability to perform its | |||
fire resistive function and will evaluate whether further generic | |||
communications are needed to address the issues discussed above. | |||
This information notice requires no specific action or written response. If | |||
you have any questions about the information in this notice, please contact | |||
the technical contact listed below or the appropriate Office of Nuclear | |||
Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
List of Recently Issued Information Notices | List of Recently Issued Information Notices | ||
* | *See previous concurrence | ||
SPLB:DSSA SPLB:DSSA TechEd | |||
*IMiller *SWest *DGable | |||
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC *DE:EELB | |||
CMcCracken* JGoldberg* CBerlinger | |||
5/20/93 5/20/93 05/25/93 | |||
*DD:DSSA *D:DSSA *OGCB:DORS D:DORS | |||
MVirgilio AThadani GMarcus BGrimes | |||
05/25/93 05/25/93 05/25/93 / /93 DOCUMENT NAME: INPSB.1 | |||
--------------- | |||
4 factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables,' for use as an industry standard. The staff encourages | |||
licensees to participate in the industry consensus standard development | |||
process to formulate an appropriate technical approach to the determination of | |||
ampacity derating factors for cables enclosed by fire barrier systems. | |||
The staff is continuing to review this product for its ability to perform its | |||
fire 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 contact | |||
the technical contact listed below or the appropriate Office of Nuclear | |||
Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
List of Recently Issued Information Notices | |||
*See previous concurrence | |||
SPLB:DSSA SPLB:DSSA TechEd | |||
*IMiller *SWest *DGable | |||
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EELB | |||
CMcCracken* JGoldberg* CBerlinger* | |||
5/20/93 5/20/93/ / /93 DD:DSSA D:DSSA M OGCBD;ORS D: DORS | |||
MVirgilio* AThadani &M GMar~ BGrimes | |||
/ /93 5 f1;93 1-/ (/93 AlS / /93 | |||
[G:\THERMOLA\OTHERVEN\IN FP60.R3] | |||
Originator: Isabel Miller | |||
_L | |||
factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, "Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables," for use as an industry standard. The staff encourages | |||
licensees to participate in the industry consensus standard development | |||
process to formulate an appropriate technical approach to the determination of | |||
ampacity 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 its | |||
fire resistive function and will take further action if appropriate. If you | |||
have any questions about the information in this notice, please contact the | |||
technical contact listed below or the appropriate Office of Nuclear Reactor | |||
Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
List of Recently Issued Information Notices | |||
*See previous concurrence | |||
SPLB:DSSA SPLB:DSSA TechEd | |||
*IMiller *SWest *DGable | |||
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EE | |||
CMcCracken* JGoldberg* CBerltTrg r | |||
5/20/93 5/20/93 -jstk093 DD:DSSA,~ D:DSSA OGCB:DORS D:DORS | |||
M9irgil9 AThadani GMarcus BGrimes | |||
/ /93 / /93 / /93 | |||
[G:\THERMOLA\OTHERVEN\IN FP60.R3] | |||
Originator: Isabel Miller | |||
1__ . '\1 factors for open-air installations but do not include derating factors for | |||
fire barrier systems. The Insulated Conductors Committee of the IEEE Power | |||
Engineering Society, Task Force 12-45, has been developing IEEE Standard | |||
Procedure P848, "Procedure for the Determination of the Ampacity Derating of | |||
Fire Protected Cables," for use as an industry standard. The staff encourages | |||
licensees to participate in the industry consensus standard development | |||
process to formulate an appropriate technical approach to the determination of | |||
ampacity 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 its fire | |||
resistive function and will take further action if appropriate. Licensees are | |||
advised to consider this information when contemplating any changes to their | |||
current fire protection program. If you have any questions about the | |||
information in this notice, please contact the technical contact listed below | |||
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: Isabel M. Miller, NRR | |||
(301) 504-2852 Attachment: | |||
===List of Recently Issued Information Notices=== | |||
*See previous concurrence | |||
SPLB:DSSA SPLB:DSSA TechEd | |||
*IMiller *SWest *DGabl e | |||
05/06/93 05/06/v 05/10/93 SPLB:DSSP( ' L DE:EELB | |||
CMcCrackelr CBerlinger | |||
_.5/P/93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS | |||
MVirgilio AThadani GMarcus BGrimes | |||
/ /93 / /93 / /93 / /93 | |||
[G:\THERMOLA\OTHERVEN\IN FP60.R2] | |||
Originator: Isabel Miller | |||
This information notice required 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 Office of | |||
Nuclear Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contact: K. Steven West, NRR | |||
(301) 504-1220 | |||
Attachment: | |||
List of Recently Issued Information Notices | |||
SPLB:DSSA SPLB:DSSA | |||
IMiller SWest | |||
/ /93 / /93 6:7/0/93 OGC SPLB:DSSA DE:EELB | |||
JGoldberg CMcCracken CBerlinger | |||
/ /93 / /93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS | |||
GHolahan AThadani GMarcus BGrimes | |||
04/ /93 04/ /93 04/ /93 / /93 | |||
. ,- -. 1 | |||
; l * | |||
consider actions as appropriate. | |||
This information notice required 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 Office of | |||
Nuclear Reactor Regulation (NRR) project manager. | |||
Brian K. Grimes, Director | |||
Division of Operating Reactor Support | |||
Office of Nuclear Reactor Regulation | |||
Technical contai K. Steven West, NRR | |||
(301) 504-1220 | |||
Attachment: | |||
List of Recentl2 ssued Information Notices | |||
SPLB:DSSA,. TechEd | |||
IMilletgfYL SIest RiStnde-e | |||
5f/6 /93 t576 /93 / /93 OGC SPLB:DSSA DE: EELB | |||
JGoldberg CMcCracken CBerlinger | |||
/ /93 / /93 / /93 DD: DSSA D: DSSA OGCB:DORS D: DORS | |||
GHolahan AThadani GMarcus BGrimes | |||
04/ /93 04/ /93 04/ /93 / /93 | |||
[G:\THERMOLA\FP-60 IN.R1] | |||
Originator: IsabeT Miller | |||
I -1 Attachment | |||
IN 93-40 | |||
May 26, 1993 LIST OF RECENTLY ISSUED | |||
NRC INFORMATION NOTICES | |||
Information Date of | |||
Notice No. Subject Issuance Issued to | |||
93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs | |||
Power Reactor Biolog- for nuclear power reactors. | |||
ical Shields | |||
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs | |||
Engineered Safety for nuclear power reactors. | |||
Features Actuation | |||
System | |||
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs | |||
minate Properties In- for nuclear power reactors. | |||
stalled in Limitorque | |||
Valve Operator Housing | |||
Covers | |||
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory | |||
and Records of Misadmin- Commission medical | |||
istrations licensees. | |||
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs | |||
Cause Failure Events for nuclear power plants | |||
(NPPs). | |||
93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs | |||
Supp. 1 Emergency Cooling for nuclear power reactors. | |||
Function Due to A | |||
Combination of | |||
Operational and Post- Loca Debris in Contain- ment | |||
93-34 Potential for Loss of 04/26/93 All holders of OLs or CPs | |||
Emergency Cooling for nuclear power reactors. | |||
Function Due to A | |||
Combination of | |||
Operational and Post- Loca Debris in Contain- ment | |||
= | OL = Operating License | ||
CP = Construction Permit}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} |
Latest revision as of 04:19, 24 November 2019
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 26, 1993 NRC INFORMATION NOTICE 93-40: FIRE ENDURANCE TEST RESULTS FOR THERMAL
CERAMICS FP-60 FIRE BARRIER MATERIAL
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to results of fire endurance and ampacity derating
test reports submitted by Thermal Ceramics on the FireMaster FP-60 fire
barrier system and the results of NRC staff reviews. 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 are not NRC requirements;
therefore, no specific action or written response is required.
Descriotion of Circumstances
In Generic Letter (GL) 92-08, wThermo-Lag 330-1 Fire Barriers," the staff
stated it would evaluate other known fire barrier materials and systems that
are used by licensees to fulfill NRC fire protection requirements. The staff
is now evaluating fire barriers manufactured by other vendors to verify the
ability of the barriers to adequately perform their 1-hour or 3-hour fire
resistive functions and to meet stated ampacity derating values. Thermal
Ceramics, Inc., formerly the Insulating Products Division of Babcock and
Wilcox, Inc., of Augusta, Georgia, manufactures the FP-60 fire barrier system
and submitted reports on two fire endurance tests and one ampacity derating
test to the NRC in a letter of February 23, 1993.
Discussion
In its review of the Thermal Ceramics reports, the staff identified the
following information.
In its product literature, Thermal Ceramics states that the FP-60 product is
manufactured for use on cable trays, conduits, junction boxes, and other cable
raceways. The primary component, the FireMaster FP-60 blanket, is a ceramic
fiber 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 the
instructions, is qualified for up to a 13/4-hour fire rating using the American
9305260385 ' P I)oktce. 93-o
POR %'K
P~ktcL93sI4
May 26, 1993 Society for Testing and Materials (ASTM) Standard E-119, "Standard Test
Methods for Fire Tests of Building Construction and Materials."
FIRE ENDURANCE TESTS
According to one report submitted by Thermal Ceramics, a.1-hour fire endurance
test of the FP-60 fire barrier in various configurations was performed at
Underwriters Laboratories, Inc. (UL File R11044-1, Project 84NK8356, March 22, 1985). The test followed UL Subject 1724, "Outline of
Investigation, Fire Tests for Electrical Circuit Protective Systems,"
May 1984. According to the report, the furnace temperatures followed the
ASTM E-119 standard time-temperature curve for fire exposure, and the barriers
were subjected to a solid hose stream test. The report also states that
circuit integrity was monitored.
Documented test configurations included 91.4 cm [36 inch] wide open-ladder and
solid-back steel cable trays, an air drop assembly, 12.7 cm [5 inch] diameter
steel conduits, and a 30.5x15.2 cm (12x6 inch] steel Junction box. All
configurations contained cables. Two hundred fifty thermocouples were
reportedly used to measure temperatures of cables, cable trays, Junction
- boxes, conduits and electrical circuit protective systdms on the unexposed
1 side of the assembly.
x According to the report, within 30 seconds of the start of the test, the
j filament tape around the blanket wrap ignited. At 5 minutes, flames
- reportedly issued from seams and butt joints. The report also states that at
20 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 the
barrier. 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 cable
jackets were melted and blistered. The hose stream eroded the bottom surface
of the cable tray barrier so that the tray was exposed.
The UL report concluded that the tested fire barrier had a 1-hour fire rating
because circuit integrity was maintained during the fire exposure and hose
stream test. However, it appears that the UL approval is limited to minimum
91.4 cm [36 inch] wide cable trays and 12.7 cm [5 inch] or larger-diameter
conduits with minimum No. 16 AWG jacketed multi-conductor cables or minimum
No. 300 MCM jacketed copper single conductor power cables with polyvinyl
chloride jackets.
The second fire endurance test report submitted by Thermal Ceramics documented
a Southwest Research Institute small-scale test, "One Hour Fire Qualification
Test of a Protective Envelope for Class 1E Electrical Conduit Circuits," (SwRI
Project 01-8305-053, February 1986). According to this report, the test
employed the ASTM E-119 standard time-temperature curve for fire exposure and
a subsequent solid hose stream test. The report also states that circuit
integrity was monitored. SwRI documented the use of a small-scale furnace
(maximum test specimen of 425.8 square cm (66 square inches]) to test a
2.5 cm [1 inch] diameter conduit with a pull box, a 5.1 cm [2 inch] diameter
conduit with a junction box, and an air drop. According to the report,. these
May 26, 1993 test assemblies each contained a single-conductor power cable and two control
cables, all with PVC jackets.
Recorded cable temperatures (measured at the cable jackets) at the end of the
fire exposure ranged from 146.5 'C (296 *F] to 164 C (327 OF]. According hoseto
the report, circuit integrity was maintained during the fire exposure and
stream 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. SwRI
did not report a conclusion as to the acceptability of the fire barrier
system.
In a letter of April 27, 1993 to Thermal Ceramics, Inc., the staff expressed
concerns regarding the ability of the FP-60 system to meet existing NRC fire
barrier acceptance criteria.
AMPACITY DERATING TEST
The ampacity derating test report submitted by Thermal Ceramics was SwRI
Project 01-8818-210, "Ampacity Derating of Fire-Protected Cables in Conduit
and Cable Trays Using Babcock & Wilcox, Incorporated's Passive Fire Protection
System," issued by SwRI on July 8, 1986. According to the report, a 1-hour
fire barrier was used in the test. Three-conductor XLPE-insulated 6 AWG
cables with Hypalon protective wraps were reportedly installed in a
61 cm (24 inch] wide by 10.2 cm [4 inch] deep cable tray, and 3-conductor
XLPE-insulated 3 AWG cables with Hypalon protective wraps were installed in a
10.2 cm [4 inch] diameter conduit. Both assemblies were reported to be
3.7 m [12 feet] long and completely filled. The report stated that
thermocouples were installed in slits' in the cable insulation.
According to the report, a steady-state temperature of 90 eC (194 *F) at the
hottest single thermocouple was monitored. Equilibrium temperature was
reportedly established when a steady-state condition (+/-1 eC per hour (+/-1.8 OF
per 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 62.4 and 41.4 percent, respectively, based on the test results.
Some licensees use the FP-60 fire barrier system to achieve physical
independence of electrical systems in accordance with Regulatory Guide 1.75, Physical Independence of Electrical Systems." Ampacity derating in fire
barrier systems installed to achieve physical independence of electric systems
is a consideration in the design of such systems as well as in those installed
to protect safe shutdown capability from a fire.
Cables enclosed in electrical raceways protected with fire barrier materials
are derated to ensure that systems have sufficient capacity and capability to
perform their intended safety functions. These cables are derated because of
the insulating effect of the fire barrier material. Other factors that affect
ampacity derating include cable fill, cable loading, cable type, raceway
construction, and ambient temperature.
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff
requested additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
publications, and other industry standards provide general ampacity derating
factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, "Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables," for use as an industry standard. The industry
consensus standard development process may formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- 2 IN 93-40
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff
requested additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
publications, and other industry standards provide general ampacity derating
factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, "Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables,' for use as an industry standard. The industry
consensus standard development process may formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager. Orginal ignd y
Brian K.Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- See previous concurrence
- SPLB:DSSA *SPLB:DSSA *TechEd
IMiller SWest DGable
05/06/93 , 05/06/93 05/10/93
- SPLB:DSSA *OGC *DE:EELB
CMcCracken JGoldberg CBerlinger
5/20/93 5/20/93 05/25/93
- DD:DSSA *D:DSSA *OGCB:DORS
MVirgilio AThadani GMarcus Grimes
05/25/93 05/25/93 05/25/93 S g&493 DOCUMENT NAME: 93-40.IN
IN 93-XX
May xx, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to thermal ceramics of April 27, 1993, the staff requested
additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
publications, and other industry standards provide general ampacity derating
factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, "Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables," for use as an industry standard. The industry
consensus standard development process may formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- See previous concurrence
SPLB:DSSA SPLB:DSSA TechEd
- IMiller *SWest *DGable
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC *DE:EELB
CMcCracken* JGoldberg* CBerlinger
5/20/93 5/20/93 05/25/93
- DD:DSSA *D:DSSA *OGCB:DORS D:DORS
MVirgilio AThadani GMarcus BGrimes
05/25/93 05/25/93 05/25/93 / /93 DOCUMENT NAME: INPSB.1
4 factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables,' for use as an industry standard. The staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity derating factors for cables enclosed by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire 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 contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- See previous concurrence
SPLB:DSSA SPLB:DSSA TechEd
- IMiller *SWest *DGable
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EELB
CMcCracken* JGoldberg* CBerlinger*
5/20/93 5/20/93/ / /93 DD:DSSA D:DSSA M OGCBD;ORS D: DORS
MVirgilio* AThadani &M GMar~ BGrimes
/ /93 5 f1;93 1-/ (/93 AlS / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R3]
Originator: Isabel Miller
_L
factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, "Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables," for use as an industry standard. The staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity 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 its
fire resistive function and will take further action if appropriate. If you
have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- See previous concurrence
SPLB:DSSA SPLB:DSSA TechEd
- IMiller *SWest *DGable
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EE
CMcCracken* JGoldberg* CBerltTrg r
5/20/93 5/20/93 -jstk093 DD:DSSA,~ D:DSSA OGCB:DORS D:DORS
M9irgil9 AThadani GMarcus BGrimes
/ /93 / /93 / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R3]
Originator: Isabel Miller
1__ . '\1 factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the IEEE Power
Engineering Society, Task Force 12-45, has been developing IEEE Standard
Procedure P848, "Procedure for the Determination of the Ampacity Derating of
Fire Protected Cables," for use as an industry standard. The staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity 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 its fire
resistive function and will take further action if appropriate. Licensees are
advised to consider this information when contemplating any changes to their
current fire protection program. If you have any questions about the
information in this notice, please contact the technical contact listed below
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- See previous concurrence
SPLB:DSSA SPLB:DSSA TechEd
- IMiller *SWest *DGabl e
05/06/93 05/06/v 05/10/93 SPLB:DSSP( ' L DE:EELB
CMcCrackelr CBerlinger
_.5/P/93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS
MVirgilio AThadani GMarcus BGrimes
/ /93 / /93 / /93 / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R2]
Originator: Isabel Miller
This information notice required 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 Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: K. Steven West, NRR
(301) 504-1220
Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA
IMiller SWest
/ /93 / /93 6:7/0/93 OGC SPLB:DSSA DE:EELB
JGoldberg CMcCracken CBerlinger
/ /93 / /93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS
GHolahan AThadani GMarcus BGrimes
04/ /93 04/ /93 04/ /93 / /93
. ,- -. 1
- l *
consider actions as appropriate.
This information notice required 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 Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contai K. Steven West, NRR
(301) 504-1220
Attachment:
List of Recentl2 ssued Information Notices
SPLB:DSSA,. TechEd
IMilletgfYL SIest RiStnde-e
5f/6 /93 t576 /93 / /93 OGC SPLB:DSSA DE: EELB
JGoldberg CMcCracken CBerlinger
/ /93 / /93 / /93 DD: DSSA D: DSSA OGCB:DORS D: DORS
GHolahan AThadani GMarcus BGrimes
04/ /93 04/ /93 04/ /93 / /93
[G:\THERMOLA\FP-60 IN.R1]
Originator: IsabeT Miller
I -1 Attachment
May 26, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs
Power Reactor Biolog- for nuclear power reactors.
ical Shields
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs
Engineered Safety for nuclear power reactors.
Features Actuation
System
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
minate Properties In- for nuclear power reactors.
stalled in Limitorque
Valve Operator Housing
Covers
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs
Cause Failure Events for nuclear power plants
(NPPs).
93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs
Supp. 1 Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
93-34 Potential for Loss of 04/26/93 All holders of OLs or CPs
Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
OL = Operating License
CP = Construction Permit