Information Notice 1995-52, Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001
November 14, 1995
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
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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--
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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
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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
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