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

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{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001November 14, 1995NRC INFORMATION NOTICE 95-52: FIRE ENDURANCE TEST RESULTS FOR ELECTRICALRACEWAY FIRE BARRIER SYSTEMS CONSTRUCTED FROM3M COMPANY INTERAM FIRE BARRIER MATERIALS
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY
 
COMMISSION
 
===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555-0001 November 14, 1995 NRC INFORMATION
 
NOTICE 95-52: FIRE ENDURANCE
 
===TEST RESULTS FOR ELECTRICAL===
RACEWAY FIRE BARRIER SYSTEMS CONSTRUCTED
 
FROM 3M COMPANY INTERAM FIRE BARRIER MATERIALS


==Addressees==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.
All holders of operating
 
licenses or construction
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
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.
The U.S. Nuclear Regulatory
 
Commission (NRC) is issuing this information
 
notice to inform addressees
 
of the results of recent fire endurance
 
tests for electrical
 
raceway fire barrier systems constructed
 
from 3M Company Interam fire barrier materials.
 
It is expected that recipients
 
will review the information
 
for applicability
 
to their facilities
 
and consider this information, as appropriate, in their review of Interam fire barriers.Backaround
 
On April 20, May 17, and July 7, 1995, the NRC staff visited Omega Point Laboratories (OPL), San Antonio, Texas, to witness full-scale
 
fire endurance tests for electrical
 
raceway fire barrier systems constructed
 
from 3M Company Interam fire barrier materials.
 
These tests were sponsored
 
by Peak Seals Corporation (Peak Seals). Peak Seals informed the NRC staff that the test specimens
 
included in this test program were intended to represent
 
generic Interam fire barrier systems and that these test programs were conducted
 
in accordance
 
with Generic Letter (GL) 86-10, Supplement
 
1, 'Fire Endurance
 
Test Acceptance
 
Criteria for Fire Barrier Systems Used To Separate Redundant
 
Safe Shutdown Trains Within the Same Fire Area." The following
 
information
 
is based 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
 
Tests The first test assembly included nominal 24-inch and 6-inch-wide
 
steel cable trays; 1-inch, 2-inch, 3-inch, and 5-inch-diameter
 
steel conduits;
a 2-inch diameter air drop; each was arranged in a U-shaped configuration;
and a 12-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 vertical runs and the 2-inch diameter air drop was installed
 
in the other. These test specimens
 
did not include cable fill and were supported
 
by a common trapeze 9511080324- K4 //6t~zEzt-0
t f51(14 IN 95-52 November 14, 1995 support. They were protected
 
with three layers of Interam E53A fire barrier mat material.
 
Each layer was 7.6 mm [0.3 inch] thick.On April 20, 1995, OPL subjected
 
the test assembly to the test fire specified in American Society for Testing and Materials (ASTM) Standard E-119, "Fire Test of Building Construction
 
and Materials," for 1 hour. After the fire exposure, 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-diameter
 
conduits;
and the air drop exceeded the temperature
 
rise acceptance
 
criteria of GL 86-10, Supplement
 
1, near the end of the 1-hour fire exposure.
 
None of the barriers burned through during the fire exposure nor were they breached by the hose stream. Table 1 (see Attachment
 
1) summarizes
 
the test specimen and fire 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- and 5-inch-diameter
 
steel conduits, and a 2-inch-diameter
 
air drop. These test specimens
 
did not contain cables and were protected
 
with three layers of Interam 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
 
in ASTM Standard E-119 for 1 hour. After the fire exposure, it subjected
 
the test specimens
 
to a fog-nozzle
 
hose stream test. These 1-hour test specimens met the acceptance
 
criteria of Supplement
 
1 to GL 86-10. Table 2 (see Attachment
 
1) summarizes
 
the test specimen and fire barrier configurations
 
and the results of the May 17, 1995, test.3-Hour Fire Endurance
 
Test The third test assembly included nominal 24-inch- and 6-inch-wide
 
steel cable trays; 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 a nominal 12-inch by 12-inch by 8-inch steel junction box. The cable trays were filled with a single layer of mix cables. The cable trays, the 1-inch- and 3-inch-diameter
 
steel conduits, and the air drop were protected
 
with five layers of Interam E54A fire barrier mat material.
 
The 5-inch-diameter
 
conduit and the Junction box were protected
 
with six layers of Interam E54A fire barrier 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
 
in ASTM Standard E-119 for 3 hours. After the fire exposure, it subjected
 
the test specimens
 
to a fog-nozzle
 
hose stream test. The barriers did not burn through 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 the test specimens
 
exceeded the temperature
 
rise acceptance
 
criteria of GL 86-10, Supplement
 
1. Table 3 (see Attachment
 
1) summarizes
 
the test specimen and fire barrier configurations
 
and the results of the July 7, 1995 test.Discussion
 
Section 50.48 of Title 10 of the Code of Federal Regulations
 
requires that each operating
 
nuclear power plant must have a fire protection
 
plan that
 
IN 95-52 November 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 ensure that one train of systems necessary
 
to achieve and maintain shutdown conditions
 
is free of fire damage. One means of satisfying
 
this requirement
 
is 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 hour or 3 hours, depends on the other fire protection
 
features in the fire area.The NRC issued guidance on acceptable
 
methods of satisfying
 
the regulatory
 
requirements
 
of GDC 3 in Branch Technical
 
Position (BTP) Auxiliary
 
and Power Conversion
 
Systems Branch (APCSB) 9.5-1, 'Guidelines
 
for Fire Protection
 
for Nuclear Power Plants"; Appendix A to BTP APCSB 9.5-1; BTP Chemical Engineering
 
Branch (CMEB) 9.5-1, "Fire Protection
 
for Nuclear Power Plants"; and GL 86-10,"Implementation
 
of Fire Protection
 
Requirements." These guidance documents state that the fire resistance
 
ratings of fire barriers should be established
 
in 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 fire exposure.On March 25, 1994, the NRC issued Supplement
 
1 to GL 86-10 to (1) clarify the applicability
 
of the test acceptance
 
criteria in GL 86-10 to raceway fire barrier systems, (2) specify a set of fire endurance
 
test acceptance
 
criteria that are acceptable
 
for demonstrating
 
that fire barrier systems can perform the required fire-resistive
 
function and maintain the protected
 
safe shutdown train free of fire damage, (3) specify acceptable
 
options for hose stream testing, and (4) specify criteria for cable functionality
 
testing when a deviation
 
is necessary, such as when the fire barrier temperature
 
rise criteria are exceeded or the test specimen cables sustain visible damage.These positions
 
are incorporated
 
by the NRC staff in its review and evaluation
 
of the adequacy of fire endurance
 
tests and fire barrier systems proposed by licensees
 
or applicants
 
to satisfy existing NRC fire protection
 
rules and regulations.
 
Some temperatures
 
observed during the tests exceeded the maximum allowable temperature
 
acceptance
 
criteria of Supplement
 
1 to GL 86-10. In accordance
 
with this supplement, an engineering
 
evaluation
 
could be performed
 
to determine
 
the acceptability
 
of an in-plant Interam fire barrier that was bounded by a deviating
 
test specimen configuration.
 
Information
 
about such evaluations
 
can be found in Enclosure
 
2 of Supplement
 
1 to GL 86-10. By letter dated August 7, 1995 [accession
 
number 9509050173
], Peak Seals submitted
 
to the NRC staff additional
 
documentation
 
relating to the thermal performance
 
of the 3-hour fire barrier test specimens
 
for information.
 
1 NFPA adopted ASTM Standard E-119 as NFPA Standard 251.
 
IN 95-52 November 14, 1995 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Regulation (NRR) project manager.fiel rector Division of Reactor Pr ram Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts:
Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 3, Summaries
 
of Endurance
 
Tests 2. List of Recently Issued NRC Information
 
Notices
 
K>_Att__Lament
 
1 IN 9-5-52 November 14, 1995 Tnhla 1 mnrmarv nf Anril 20. 1995 Fire Endurance
 
Test Peak Seals -3M Company 1-Hour Interam Fire Barriers Allowable
 
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 REMARKS ILOCATIONS (OF)(F)}6" Cable tray Front side rail 262 338 Protected
 
with three layers of Interam E53A.Rear side rail J 262 337 Copper conductor Ila Met acceptance
 
criteria.24" Cable tray Front side rail Rear side rail Copper conductor Protected
 
with four layers of Interam E53A.Exceeded the maximum single point temperature
 
criterion
 
at 50X minutes and the average temperature
 
rise criterion
 
at 54X minutes.______________
.4 5" Conduit Conduit surface Copper conductor 1 277 1 370 I 217 275 3" Conduit Conduit surface Copper conductor 2" Conduit Conduit surface Copper conductor 1- Conduit Conduit surface Copper conductor 2" air drop Copper conductor Protected
 
with three layers of Interam E53A.Met acceptance
 
criteria.Protected
 
with three layers of Interarn E53A.Exceeded the maximum single point temperature
 
criterion
 
at 59 X minutes and the average temperature
 
rise criterion
 
at 53 X minutes.Protected
 
with three layers of Interam E54A.Exceeded the maximum single point temperature
 
criterion
 
at 55X minutes and the average temperature
 
rise criterion
 
at 55 minutes.Protected
 
with two layers of Interam E53A and an outer layer of Interam E54A.Exceeded maximum single point temperature
 
criterion
 
at 49X minutes and the average temperature
 
rise criterion
 
at 52 minutes._________________________________
I Protected
 
with three layers of Interam E54A.Exceeded average temperature
 
rise criterion
 
at 59 minutes._______ .-Junction box 2S7 311 Protected
 
with three layers of Interam E54A.Met acceptance
 
criteria.'Temperatures
 
measured during testing and the acceptance
 
temperatures
 
are presented
 
in aF in all Tables of this attachment
 
to minimize error and confusion.
 
Att.,,_ment
 
1 IN 95;-52 November 14, 1995 Table 2. Summary of May 17, 1995 Fire Endurance
 
Test Peak Seals -3M Company 1-Hour Interam Fire Barrier Allowable
 
single point unexposed-side
 
temperature
 
criterion
 
.405 OF Allowable
 
average unexposed-side
 
temperature
 
criterion
 
-330 OF TEST SPECIMEN THERMOCOUPLE
 
AVERAGE MAXIMUM REMARKS LOCATIONS (OF) (OF'24" Cable tray Front side rail 290 389 Protected
 
with three layers of 3M Interam E54A Rear side rail 301 354 Met 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 of Interam E54A.Met acceptance
 
criteria.
 
At lament 1 IN 95-52 November 14, 1995 Table 3. Summary of July 7. 1995 Fire Endurance
 
Test Peak Sea Allowable
 
single ;Allowable
 
averal (Shading shows temperature
 
===TEST SPECIMEN THERMOCOUPLE===
LOCATIONS 6" Cable tray Front side rail Rear side rail Copper conductor 24" Cable tray Front side rail Rear side rail Copper conductor 5" Conduit Conduit surface Copper conductor 3' Conduit Conduit surface Copper conductor 1" Conduit Conduit surface Copper conductor 2" Air drop Copper conductor Junction box Metal surface Is- 3M Company 3-Hour Interam Fire Barrier piInt unexposed-side
 
temperature
 
criterion
 
-407 OF ge unexposed-side
 
temperature
 
criterloon
 
-332 OF a that exceeded acceptance
 
criteria of GL 86-10. Supplement
 
1).AVERAGE ([F)I MAXIMUM (1F)I REMARKS Protected
 
with five layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
at 158 minutes and the average temperature
 
rise criterion
 
at 166 minutes.301 343 406 243 334 Protected
 
with five layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
at 176 minutes and the average temperature
 
rise criterion
 
at 167 minutes.Protected
 
with five layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
at 161 minutes and the average temperature
 
rise criterion
 
at 178 minutes..Protected
 
with five layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
at 148 minutes and the average temperature
 
rise criterion
 
at 152 minutes.Protected
 
with six layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
at 126 minutes and the sversge temperature
 
rise criterion
 
at 167 minutes..Protected
 
with five layers of Interam E54A. Exceeded the maximum single point temperature
 
criterion
 
and the average temperature
 
rise criterion
 
at 152 minutes..Protected
 
with six layers of Interam E54A. Exceeded the average temperature
 
rise criterion
 
at 165 minutes.
 
< ~tachment
 
2 IN 95-52 November 14, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
 
NOTICES Information
 
Date of Notice No. Subject Issuance Issued to 95-51 95-50 95-49 95-48 95-47 95-46 95-12, Supp. 1 95-45 95-44 Recent Incidents
 
Involving Potential
 
Loss of Control of Licensed Material Safety Defect in Gammamed 12i Bronchial
 
Catheter Clamping Adapters Seismic Adequacy of Thermo-Lag
 
Panels Results of Shift Staffing Study Unexpected
 
Opening of a Safety/Relief
 
Valve and Complications
 
Involving Suppression
 
===Pool Cooling Strainer Blockage Unplanned, Undetected===
Release of Radioactivity
 
from the Exhaust Ventilation
 
System of a Boiling Water Reactor Potentially
 
===Nonconforming===
Fasteners
 
Supplied by A&G Engineering
 
II, Inc.American Power Service Falsification
 
of American Society for Nondestructive
 
Testing (ASNT) Certificates
 
Ensuring Compatible
 
===Use of Drive Cables Incorporating===
Industrial
 
Nuclear Company Ball-Type
 
===Male Connectors===
10/27/95 10/30/95 10/27/95 10/10/95 10/04/95 10/06/95 10/05/95 10/04/95 09/26/95 All material and fuel cycle licensees.
 
All High Dose Rate Afterloader (HDR) Adapters.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All Radiography
 
Licensees.
 
OL = Operating
 
License CP = Construction
 
Permit
 
IN 95-52 November 14, 1995 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Regulation (NRR) project manager.orig /s/'d by DNCrutchfield
 
Dennis M. Crutchfield, Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, anm 2. List of Recentl, AWAS4 3, Summaries
 
of Endurance
 
Tests Issued NRC Information
 
Notices&&I--6'zp "'Ilke4-TechEd reviewed this document on 9/11/95 DOCUMENT NAME: 95-52.IN To ,eceive a copy of this document, Indicate In the box: *C' a Copy Without attachientenctoSurM
 
IE -Copy with attachmentlwclosure
 
IN' -No copy iOFFICE PECB:DRPM*
l C:PECB/DRPM*
I D/DRPV1J-n,1 A i NAME IJCarter IAEChaffee
 
DMCruVif!el
 
d DATE 09/28/95 11/02/95 111/ /95 OFFICIAL RECORD COPY
 
IN 95-xx November xx, 1995 This Information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts:
Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 3, Summaries
 
of Endurance
 
Tests 2. List of Recently Issued NRC Information
 
Notices DOCUMENT NAME: G:\IN\3MIN
 
To mcev. a copy of Weh docunnt. inducate I the box: IC' -Copy without attachment/encloss
 
'Ew
 
* Copy with attachmentoneloesure
 
OFFICE SPLB:DSSA*
I ADM:PUB* PECB:DRPM*
I C:PER RRPM NAME ASingh Tech Editor JCarter/RLD
 
A~hOW DATE 09/28/95 109/11/95 l09/28/95 ti/2/g&sect;PL3 OFFICE ID:DRPM/NRR
 
I II.N. .No copy!NAME 1DPMCrutchfield
 
JDATE I1 4 ! !J5I~~OFFICIAL RECORD COPY
 
IN 95-xx September
 
xx, 1995 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 2. List of Recently 3, Summaries
 
of Endurance


==Description of Circumstances==
Tests Issued NRC Information
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 hour. 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 hour. 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 hours. 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 hours, 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 251.
Notices.or DOCUMENT NAME: G:\IN\3M I.I ( 'ff-To rete a copy o o docunwra j2 box: 'C' -Copy wfthout anachmnten


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) 415-1237Attachments:1. Tables 1, 2, and 3, Summaries of Endurance Tests2. List of Recently Issued NRC Information Notices
cosL 'E' -Copy with atchmentlenciosure


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 confusion.
'' -No copy OFFICE SPLB:DSS\A


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 criteria.
1, ] 'I ADM:PUB* I IP fTRPM I PECB/DRPM


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 165minutes.
Z I I C:PECB/DRPM


< ~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
I NAME ASingh ) A Tech Editor IJZarter RJKi I.fT AChaffee DATE m 95 109/11/95
/95 O&5 OFFICE D:DRPM/NRR


IN 95-52November 14, 1995 IN 95-xxNovember xx, IN 95-xxSeptember xx, 1995 
===I I NAME DMCrutchfleld===
}}
DATE 09/ /__ 95_I OFFICIAL RECORD COPY}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Revision as of 14:05, 31 August 2018

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  Entergy icon.png
Issue date: 11/14/1995
From: Crutchfield D M
Office of Nuclear Reactor Regulation
To:
References
GL-86-010 IN-95-052, NUDOCS 9511080324
Download: ML031060151 (11)
v • d • e


UNITED STATES NUCLEAR REGULATORY

COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 November 14, 1995 NRC INFORMATION

NOTICE 95-52: FIRE ENDURANCE

TEST RESULTS FOR ELECTRICAL

RACEWAY FIRE BARRIER SYSTEMS CONSTRUCTED

FROM 3M COMPANY INTERAM FIRE BARRIER MATERIALS

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 inform addressees

of the results of recent fire endurance

tests for electrical

raceway fire barrier systems constructed

from 3M Company Interam fire barrier materials.

It is expected that recipients

will review the information

for applicability

to their facilities

and consider this information, as appropriate, in their review of Interam fire barriers.Backaround

On April 20, May 17, and July 7, 1995, the NRC staff visited Omega Point Laboratories (OPL), San Antonio, Texas, to witness full-scale

fire endurance tests for electrical

raceway fire barrier systems constructed

from 3M Company Interam fire barrier materials.

These tests were sponsored

by Peak Seals Corporation (Peak Seals). Peak Seals informed the NRC staff that the test specimens

included in this test program were intended to represent

generic Interam fire barrier systems and that these test programs were conducted

in accordance

with Generic Letter (GL) 86-10, Supplement

1, 'Fire Endurance

Test Acceptance

Criteria for Fire Barrier Systems Used To Separate Redundant

Safe Shutdown Trains Within the Same Fire Area." The following

information

is based 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

Tests The first test assembly included nominal 24-inch and 6-inch-wide

steel cable trays; 1-inch, 2-inch, 3-inch, and 5-inch-diameter

steel conduits;

a 2-inch diameter air drop; each was arranged in a U-shaped configuration;

and a 12-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 vertical runs and the 2-inch diameter air drop was installed

in the other. These test specimens

did not include cable fill and were supported

by a common trapeze 9511080324- K4 //6t~zEzt-0

t f51(14 IN 95-52 November 14, 1995 support. They were protected

with three layers of Interam E53A fire barrier mat material.

Each layer was 7.6 mm [0.3 inch] thick.On April 20, 1995, OPL subjected

the test assembly to the test fire specified in American Society for Testing and Materials (ASTM) Standard E-119, "Fire Test 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 fire exposure, 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-diameter

conduits;

and the air drop exceeded the temperature

rise acceptance

criteria of GL 86-10, Supplement

1, near the end of the 1-hour fire exposure.

None of the barriers burned through during the fire exposure nor were they breached by the hose stream. Table 1 (see Attachment

1) summarizes

the test specimen and fire 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- and 5-inch-diameter

steel conduits, and a 2-inch-diameter

air drop. These test specimens

did not contain cables and were protected

with three layers of Interam 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

in ASTM 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

the test specimens

to a fog-nozzle

hose stream test. These 1-hour test specimens met the acceptance

criteria of Supplement

1 to GL 86-10. Table 2 (see Attachment

1) summarizes

the test specimen and fire barrier configurations

and the results of the May 17, 1995, test.3-Hour Fire Endurance

Test The third test assembly included nominal 24-inch- and 6-inch-wide

steel cable trays; 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 a nominal 12-inch by 12-inch by 8-inch steel junction box. The cable trays were filled with a single layer of mix cables. The cable trays, the 1-inch- and 3-inch-diameter

steel conduits, and the air drop were protected

with five layers of Interam E54A fire barrier mat material.

The 5-inch-diameter

conduit and the Junction box were protected

with six layers of Interam E54A fire barrier 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

in ASTM 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

the test specimens

to a fog-nozzle

hose stream test. The barriers did not burn through 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 the test specimens

exceeded the temperature

rise acceptance

criteria of GL 86-10, Supplement

1. Table 3 (see Attachment

1) summarizes

the test specimen and fire barrier configurations

and the results of the July 7, 1995 test.Discussion

Section 50.48 of Title 10 of the Code of Federal Regulations

requires that each operating

nuclear power plant must have a fire protection

plan that

IN 95-52 November 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 ensure that one train of systems necessary

to achieve and maintain shutdown conditions

is free of fire damage. One means of satisfying

this requirement

is 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 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 regulatory

requirements

of GDC 3 in Branch Technical

Position (BTP) Auxiliary

and Power Conversion

Systems Branch (APCSB) 9.5-1, 'Guidelines

for Fire Protection

for Nuclear Power Plants"; Appendix A to BTP APCSB 9.5-1; BTP Chemical Engineering

Branch (CMEB) 9.5-1, "Fire Protection

for Nuclear Power Plants"; and GL 86-10,"Implementation

of Fire Protection

Requirements." These guidance documents state that the fire resistance

ratings of fire barriers should be established

in 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 fire exposure.On March 25, 1994, the NRC issued Supplement

1 to GL 86-10 to (1) clarify the applicability

of the test acceptance

criteria in GL 86-10 to raceway fire barrier systems, (2) specify a set of fire endurance

test acceptance

criteria that are acceptable

for demonstrating

that fire barrier systems can perform the required fire-resistive

function and maintain the protected

safe shutdown train free of fire damage, (3) specify acceptable

options for hose stream testing, and (4) specify criteria for cable functionality

testing when a deviation

is necessary, such as when the fire barrier temperature

rise criteria are exceeded or the test specimen cables sustain visible damage.These positions

are incorporated

by the NRC staff in its review and evaluation

of the adequacy of fire endurance

tests and fire barrier systems proposed by licensees

or applicants

to satisfy existing NRC fire protection

rules and regulations.

Some temperatures

observed during the tests exceeded the maximum allowable temperature

acceptance

criteria of Supplement

1 to GL 86-10. In accordance

with this supplement, an engineering

evaluation

could be performed

to determine

the acceptability

of an in-plant Interam fire barrier that was bounded by a deviating

test specimen configuration.

Information

about such evaluations

can be found in Enclosure

2 of Supplement

1 to GL 86-10. By letter dated August 7, 1995 [accession

number 9509050173

], Peak Seals submitted

to the NRC staff additional

documentation

relating to the thermal performance

of the 3-hour fire barrier test specimens

for information.

1 NFPA adopted ASTM Standard E-119 as NFPA Standard 251.

IN 95-52 November 14, 1995 This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Regulation (NRR) project manager.fiel rector Division of Reactor Pr ram Management

Office of Nuclear Reactor Regulation

Technical

contacts:

Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:

1. Tables 1, 2, and 3, Summaries

of Endurance

Tests 2. List of Recently Issued NRC Information

Notices

K>_Att__Lament

1 IN 9-5-52 November 14, 1995 Tnhla 1 mnrmarv nf Anril 20. 1995 Fire Endurance

Test Peak Seals -3M Company 1-Hour Interam Fire Barriers Allowable

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 REMARKS ILOCATIONS (OF)(F)}6" Cable tray Front side rail 262 338 Protected

with three layers of Interam E53A.Rear side rail J 262 337 Copper conductor Ila Met acceptance

criteria.24" Cable tray Front side rail Rear side rail Copper conductor Protected

with four layers of Interam E53A.Exceeded the maximum single point temperature

criterion

at 50X minutes and the average temperature

rise criterion

at 54X minutes.______________

.4 5" Conduit Conduit surface Copper conductor 1 277 1 370 I 217 275 3" Conduit Conduit surface Copper conductor 2" Conduit Conduit surface Copper conductor 1- Conduit Conduit surface Copper conductor 2" air drop Copper conductor Protected

with three layers of Interam E53A.Met acceptance

criteria.Protected

with three layers of Interarn E53A.Exceeded the maximum single point temperature

criterion

at 59 X minutes and the average temperature

rise criterion

at 53 X minutes.Protected

with three layers of Interam E54A.Exceeded the maximum single point temperature

criterion

at 55X minutes and the average temperature

rise criterion

at 55 minutes.Protected

with two layers of Interam E53A and an outer layer of Interam E54A.Exceeded maximum single point temperature

criterion

at 49X minutes and the average temperature

rise criterion

at 52 minutes._________________________________

I Protected

with three layers of Interam E54A.Exceeded average temperature

rise criterion

at 59 minutes._______ .-Junction box 2S7 311 Protected

with three layers of Interam E54A.Met acceptance

criteria.'Temperatures

measured during testing and the acceptance

temperatures

are presented

in aF in all Tables of this attachment

to minimize error and confusion.

Att.,,_ment

1 IN 95;-52 November 14, 1995 Table 2. Summary of May 17, 1995 Fire Endurance

Test Peak Seals -3M Company 1-Hour Interam Fire Barrier Allowable

single point unexposed-side

temperature

criterion

.405 OF Allowable

average unexposed-side

temperature

criterion

-330 OF TEST SPECIMEN THERMOCOUPLE

AVERAGE MAXIMUM REMARKS LOCATIONS (OF) (OF'24" Cable tray Front side rail 290 389 Protected

with three layers of 3M Interam E54A Rear side rail 301 354 Met 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 of Interam E54A.Met acceptance

criteria.

At lament 1 IN 95-52 November 14, 1995 Table 3. Summary of July 7. 1995 Fire Endurance

Test Peak Sea Allowable

single ;Allowable

averal (Shading shows temperature

TEST SPECIMEN THERMOCOUPLE

LOCATIONS 6" Cable tray Front side rail Rear side rail Copper conductor 24" Cable tray Front side rail Rear side rail Copper conductor 5" Conduit Conduit surface Copper conductor 3' Conduit Conduit surface Copper conductor 1" Conduit Conduit surface Copper conductor 2" Air drop Copper conductor Junction box Metal surface Is- 3M Company 3-Hour Interam Fire Barrier piInt unexposed-side

temperature

criterion

-407 OF ge unexposed-side

temperature

criterloon

-332 OF a that exceeded acceptance

criteria of GL 86-10. Supplement

1).AVERAGE ([F)I MAXIMUM (1F)I REMARKS Protected

with five layers of Interam E54A. Exceeded the maximum single point temperature

criterion

at 158 minutes and the average temperature

rise criterion

at 166 minutes.301 343 406 243 334 Protected

with five layers of Interam E54A. Exceeded the maximum single point temperature

criterion

at 176 minutes and the average temperature

rise criterion

at 167 minutes.Protected

with five layers of Interam E54A. Exceeded the maximum single point temperature

criterion

at 161 minutes and the average temperature

rise criterion

at 178 minutes..Protected

with five layers of Interam E54A. Exceeded the maximum single point temperature

criterion

at 148 minutes and the average temperature

rise criterion

at 152 minutes.Protected

with six layers of Interam E54A. Exceeded the maximum single point temperature

criterion

at 126 minutes and the sversge temperature

rise criterion

at 167 minutes..Protected

with five layers of Interam E54A. Exceeded the maximum single point temperature

criterion

and the average temperature

rise criterion

at 152 minutes..Protected

with six layers of Interam E54A. Exceeded the average temperature

rise criterion

at 165 minutes.

< ~tachment

2 IN 95-52 November 14, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION

NOTICES Information

Date of Notice No. Subject Issuance Issued to 95-51 95-50 95-49 95-48 95-47 95-46 95-12, Supp. 1 95-45 95-44 Recent Incidents

Involving Potential

Loss of Control of Licensed Material Safety Defect in Gammamed 12i Bronchial

Catheter Clamping Adapters Seismic Adequacy of Thermo-Lag

Panels Results of Shift Staffing Study Unexpected

Opening of a Safety/Relief

Valve and Complications

Involving Suppression

Pool Cooling Strainer Blockage Unplanned, Undetected

Release of Radioactivity

from the Exhaust Ventilation

System of a Boiling Water Reactor Potentially

Nonconforming

Fasteners

Supplied by A&G Engineering

II, Inc.American Power Service Falsification

of American Society for Nondestructive

Testing (ASNT) Certificates

Ensuring Compatible

Use of Drive Cables Incorporating

Industrial

Nuclear Company Ball-Type

Male Connectors

10/27/95 10/30/95 10/27/95 10/10/95 10/04/95 10/06/95 10/05/95 10/04/95 09/26/95 All material and fuel cycle licensees.

All High Dose Rate Afterloader (HDR) Adapters.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All Radiography

Licensees.

OL = Operating

License CP = Construction

Permit

IN 95-52 November 14, 1995 This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Regulation (NRR) project manager.orig /s/'d by DNCrutchfield

Dennis M. Crutchfield, Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:

1. Tables 1, 2, anm 2. List of Recentl, AWAS4 3, Summaries

of Endurance

Tests Issued NRC Information

Notices&&I--6'zp "'Ilke4-TechEd reviewed this document on 9/11/95 DOCUMENT NAME: 95-52.IN To ,eceive a copy of this document, Indicate In the box: *C' a Copy Without attachientenctoSurM

IE -Copy with attachmentlwclosure

IN' -No copy iOFFICE PECB:DRPM*

l C:PECB/DRPM*

I D/DRPV1J-n,1 A i NAME IJCarter IAEChaffee

DMCruVif!el

d DATE 09/28/95 11/02/95 111/ /95 OFFICIAL RECORD COPY

IN 95-xx November xx, 1995 This Information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

contacts:

Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:

1. Tables 1, 2, and 3, Summaries

of Endurance

Tests 2. List of Recently Issued NRC Information

Notices DOCUMENT NAME: G:\IN\3MIN

To mcev. a copy of Weh docunnt. inducate I the box: IC' -Copy without attachment/encloss

'Ew

  • Copy with attachmentoneloesure

OFFICE SPLB:DSSA*

I ADM:PUB* PECB:DRPM*

I C:PER RRPM NAME ASingh Tech Editor JCarter/RLD

A~hOW DATE 09/28/95 109/11/95 l09/28/95 ti/2/g§PL3 OFFICE ID:DRPM/NRR

I II.N. .No copy!NAME 1DPMCrutchfield

JDATE I1 4 ! !J5I~~OFFICIAL RECORD COPY

IN 95-xx September

xx, 1995 This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:

1. Tables 1, 2, and 2. List of Recently 3, Summaries

of Endurance

Tests Issued NRC Information

Notices.or DOCUMENT NAME: G:\IN\3M I.I ( 'ff-To rete a copy o o docunwra j2 box: 'C' -Copy wfthout anachmnten

cosL 'E' -Copy with atchmentlenciosure

-No copy OFFICE SPLB:DSS\A

1, ] 'I ADM:PUB* I IP fTRPM I PECB/DRPM

Z I I C:PECB/DRPM

I NAME ASingh ) A Tech Editor IJZarter RJKi I.fT AChaffee DATE m 95 109/11/95

/95 O&5 OFFICE D:DRPM/NRR

I I NAME DMCrutchfleld

DATE 09/ /__ 95_I OFFICIAL RECORD COPY


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