Thermo-Lag 330-1 Flame Spread Test ResultsML031060314 |
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 |
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Issue date: |
08/10/1995 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
|
---|
References |
---|
IN-95-032, NUDOCS 9508040074 |
Download: ML031060314 (8) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
v1_
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 August 10, 1995 NRC INFORMATION NOTICE 95-32: THERMO-LAG 330-1 FLAME SPREAD TEST RESULTS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing thisspread information
notice to alert addressees to the results of the NRC flame tests of
will
Thermo-Lag 330-1 fire barrier panels. It is expected that recipientsand consider this
review the information for applicability to their facilities330-1 fire
information, as appropriate, in their review of Thermo-Lag notice are not
barriers. However, suggestions contained in this information
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
On January 12, 1995, the NRC Staff conducted two flame spread tests of
Thermo-Lag 330-1 panels at U.S. Testing, Fairfield, New Jersey. The National
The
Institute of Standards and Technology provided technical assistance. Materials
tests were conducted in accordance with American Society of Testing 1994, E84 (ASTM E84), Surface Burning Characteristics of Building Materials,"guidance
which is the test method referenced in the NRC fire protection
documents.
Both of the Thermo-Lag test specimens were constructed of 5/8-inch nominal
by 25-foot long
thickness Thermo-Lag 330-1 panels. A nominal 20-inch wide in a face-down
Thermo-Lag specimen was placed in the top of the tunnel furnace
position. The test specimen becomes the furnace ceiling. Athe gas burner at one
end of the furnace provided about 5,000 Btus per minute for 10-minute test
period. An inducted air flow pulled the gas flame downstream. Flame travel
in
along the surface of the Thermo-Lag specimen was observed the flamewindows
through
spread
the side of the furnace. The test laboratory calculated specimen
ratings on the basis of the distance the flame traveled down the test
and the elapsed time for maximum flame spread.
Texas
The Thermo-Lag panels for the first test specimen were purchased from Peak plant.
Utilities Electric Company from warehouse stock for the Comanche latex top coat
These panels were coated at the point of manufacture with a
and supplier
that was applied by Thermal Science, Inc. (TSI), the manufacturer
of Thermo-Lag fire barrier materials. The maximum flame spread measured was
about 2.4 meters [8 feet] at 1 minute and 23 seconds into the test.
PDdx :E 0-Pef - T5- 03, 9SOI&' D
9508040074 Q0ri
A'
K-2 K>/ IN 95-32 August 10, 1995 37. The Thermo-Lag
This measurement equated to a flame spread rating of from TSI, were not
panels for the second test specimen, which were purchased specimen was 2.4 meters
topcoated. The maximum flame spread measured for thisThis measurement equated
[8 feet] at 7 minutes and 20 seconds into the test.
to a flame spread rating of 25.
Discussion
burning characteristics
Flame spread tests are used to determine the surface test results are used
of materials when exposed to a test fire. Flame spread materials and are
to compare the surface burning characteristics of different
introduced when a material
one consideration in assessments of the fire hazard spread rating, the greater
is used in an area. The higher the numerical flame board and red oak
the flammability hazard. For example, cement-asbestos have flame spread
flooring, which are used to calibrate the test furnace, ratings of 0 and 100, respectively.
in several NRC
NRC staff guidelines regarding flame spread are,contained to fire
documents. For example, although it is not directly applicable
in part, that
barriers, Branch Technical Position APCSB 9.5-1 states, materials, and
insulation
"[i]nterior wall and structural components, thermal be non-combustible.
radiation shielding materials and sound-proofing shouldby a nationally
Interior finishes should be non-combustible or listed or less...." In
recognized testing laboratory...for a flame spread 25 spread in its definition
addition, Standard Review Plan 9.5.1 addresses flame a noncombustible
of noncombustible materials. It states, in part, that a surfacing
material has "a structural base of noncombustible material...with
rating not higher than 50...."
not over 1/8-inch thick that has a flame spread
written response. If
This information notice requires no specific action or please contact
notice, you have any questions about the information in this NRR project manager.
the technical contact listed below or the appropriate
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
164],J- gnC/
" achment
IN 95-32 August 10, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-31 Motor-Operated Valve 08/09/95 All holders of OLs or CPs
Failure Caused by Stem for nuclear power reactors.
Protector Pipe Inter- ference
95-30 Susceptibility of Low- 08/03/95 All holders of OLs or CPs
Pressure Coolant Injection for nuclear power reactors.
and Core Spray Injection
Valves to Pressure Locking
94-66, Overspeed of Turbine- 06/16/95 All holders of OLs or CPs
Supp. 1 Driven Pumps Caused by for nuclear power reactors.
Binding in Stems of
Governor Valves
95-29 Oversight of Design and 06/07/95 All holders of OLs or CPs
Fabrication Activities for nuclear power reactors.
for Metal Components Used
in Spent Fuel Dry Storage
Systems
95-28 Emplacement of Support 06/05/95 All holders of OLs or CPs
Pads for Spent Fuel Dry for nuclear power reactors.
Storage Installations at
Reactor Sites
95-27 NRC Review of Nuclear 05/31/95 All holders of OLs or CPs
Energy Institute, for nuclear power plants.
NThermo-Lag 330-1 Combustibility Evaluation
Methodology Plant Screening
Guide'
95-26 Defect in Safety- 05/31/95 All holders of OLs or CPs
Related Pump Parts due for nuclear power reactors.
to Inadequate Heat
Treatment
94-61, Corrosion of William 05/25/95 All holders of OLs or CPs
Supp. 1 Power Gate Valve Disc for nuclear power reactors.
Holders
OL - Operating License
CP = Construction Permit
K>
IN 95-32 August 10, 1995 This measurement equated to a flame 5;pread rating of 37. The Thermo-Lag
panels for the second test specimen, which were purchased from TSI, were not
topcoated. The maximum flame spread measured for this specimen was 2.4 meters
[8 feet] at 7 minutes and 20 seconds into the test. This measurement equated
to a flame spread rating of 25.
Discussion
Flame spread tests are used to determine the surface burning characteristics
of materials when exposed to a test fire. Flame spread test results are used
to compare the surface burning characteristics of different materials and are
one consideration in assessments of the fire hazard introduced when a material
is used in an area. The higher the numerical flame spread rating, the greater
the flammability hazard. For example, cement-asbestos board and red oak
flooring, which are used to calibrate the test furnace, have flame spread
ratings of 0 and 100, respectively.
NRC staff guidelines regarding flame spread are contained in several NRC
documents. For example, although it is not directly applicable to fire
barriers, Branch Technical Position APCSB 9.5-1 states, in part, that
"[i]nterior wall and structural components, thermal insulation materials, and
radiation shielding materials and sound-proofing should be non-combustible.
Interior finishes should be non-combustible or listed by a nationally
recognized testing laboratory...for a flame spread 25 or less...." In
addition, Standard Review Plan 9.5.1 addresses flame spread in its definition
of noncombustible materials. It states, in part, that a noncombustible
material has "a structural base of noncombustible material...with a surfacing
not over 1/8-inch thick that has a flame spread rating not higher than 50...."
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 NRR project manager.
orig /s/'d by DMCrutchfield
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-32.IN
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IN 95-XX
July xx, 199 equated to a flame spread rating of 37. The Thermo-Lag panels for the second
test specimen, which were purchased from TSI, were not topcoated. The maximum
flame spread measured for this specimen was 2.4 meters [8 feet] at 7 minutes
and 20 seconds into the test. This measurement equated to a flame spread
rating of 25.
Discussion
Flame spread tests are used to determine the surface burning characteristics
of materials when exposed to a test fire. Flame spread test results are used
to compare the surface burning characteristics of different materials and are
one consideration in assessments of the fire hazard introduced when a material
is used in an area. The higher the numerical flame spread rating, the greater
the flammability hazard. For example, cement-asbestos board and red oak
flooring, which are used to calibrate the test furnace, have flame spread
ratings of 0 and 100, respectively.
NRC staff guidelines regarding flame spread are contained in several NRC
documents. For example, although it is not directly applicable to fire
barriers, Branch Technical Position APCSB 9.5-1 states, in part, that
1[i]nterior wall and structural components, thermal insulation materials, and
radiation shielding materials and sound-proofing should be non-combustible.
Interior finishes should be non-combustible or listed by a nationally
recognized testing laboratory...for a flame spread 25 or less...." In
addition, Standard Review Plan 9.5.1 addresses flame spread in its definition
of noncombustible materials. It states, in part, that a noncombustible
material has "a structural base of noncombustible material...with a surfacing
not over 1/8-inch thick that has a flame spread rating not higher than 50...."
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 NRR project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN T_LAG.FST
- See previous concurrence ANT a No copy
To receive a copy of this document. Indicate In the box: 'C
- Copy without attachment/enclosure 'E' - Copy with attachment/enclosure
l
OFFICE SPLB:DSSA I OECB:DOPS _ ADM:PUB N SC/SPLB:DSSA C/SPLB:DSSA
NAME PMadden* JCarter* Tech Editor* SWest* CMcCracken*
DATE 07/07/95 07/07/95 [07/06/95 07/07/95 07/07/95
- . .a a1.
- a HI
AfFTrr irtPErR-flRPM I IPECB:DRPM I IC/PECB:DRPM I IU/UKVM I I
NAME RDennig* _ RKiessel* _AChaffee* DCrutchfie
DATE 07/27/95 07/27/95 07/27/95 I // 9 5 I
V . - nrr^ r%%fl
"lfl
UttpLbLAL KtLUUKU 6urT
IN 95-XX
July xx, 199 equated to a flame spread rating of 37. The Thermo-Lag panels for the second
test specimen, which were purchased from TSI, were not topcoated. The maximum
flame spread measured for this specimen was 2.4 meters [8 feet] at 7 minutes
and 20 seconds into the test. This measurement equated to a flame spread
rating of 25.
Discussion
Flame spread tests are used to determine the surface burning characteristics
of materials when exposed to a test fire. Flame spread test results are used
to compare the surface burning characteristics of different materials and are
one consideration in assessments of the fire hazard introduced when a material
is used in an area. The higher the numerical flame spread rating, the greater
the flammability hazard. For example, cement-asbestos board and red oak
flooring, which are used to calibrate the test furnace, have flame spread
ratings of 0 and 100, respectively.
NRC staff guidelines regarding flame spread are contained in several NRC
documents. For example, although it is not directly applicable to fire
barriers, Branch Technical Position APCSB 9.5-1 states, in part, that
"[i]nterior wall and structural components, thermal insulation materials, and
radiation shielding materials and sound-proofing should be non-combustible.
Interior finishes should be non-combustible or listed by a nationally
recognized testing laboratory...for a flame spread 25 or less...." In
addition, Standard Review Plan 9.5.1 addresses flame spread in its definition
of noncombustible materials. It states, in part, that a noncombustible
material has "a structural base of noncombustible material...with a surfacing
not over 1/8-inch thick that has a flame spread rating not higher than 50...."
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 NRR project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN T LAG.FST
- See previous concurrence - "N" - No copy
To receive a copy of this document, Indicate In the box: TC' - Copy without attachment/onclosure 'E' - Copy with attachmentienclosure d
OFFICE SPLB:DSSA I OECB:DOPS lI ADM:PUB I N SC/SPLB:DSSA I C/SPLB:DSSA I
NAME PMadden* JCarter* Tech Editor* SWest*CMcCracken*
DATE 07/07/95 07/07/95 07/06/95 07/07/95 07/07/95
. - - . I-- I I if
_,._.___i
nlFF1F 1I=/PFciP.fFwM
RD s7 I IPECB:DRPM
r-isel I IC/PkS$:UKF'M
________ I D*uchil
I/UKPM I I
II
NAME ReWY\ RKiessel* ACHE fe DCrutchfield
DATE _ _ _ _ __/95_ __
_07/27_7 ___/95 1_ /95 /
_ - -. 1-v~~nf IIfnlV
UVrriL4AL KtLUKU Wri
K)
IN 95-XX
July xx, 199 equated to a flame spread rating of 37. The Thermo-Laig panels for the maximum second
test specimen, which were purchased from TSI, were not topcoated. The
flame spread measured for this specimen was 2.4 meters [8 feet] at 7 minutes
and 20 seconds into the test. This measurement equated to a flame spread
rating of 25.
Discussion
Flame spread tests are used to determine the surface burning characteristics
of materials when exposed to a test fire. Flame spread test results are used
to compare the surface burning characteristics of different materials and are
one consideration in assessments of the fire hazard introduced when a material
is used in an area. The higher the numerical flame spread rating, the greater
the flammability hazard. For example, cement-asbestos board and red oak
flooring, which are used to calibrate the test furnace, have flame spread
ratings of 0 and 100, respectively.
NRC staff guidelines regarding flame spread are contained in several NRC
documents. For example, although it is not directly applicable to fire
barriers, Branch Technical Position A PCSB 9.5-1 states, in part, that X
N[i]nterior wall and structural components, thermal insulation materials, and
radiation shielding materials and sound-proofing should be non-combustible.
Interior finishes should be non-combustible or listed by a nationally
recognized testing laboratory.. foa flame spread 25 or less...." In xl
addition, Standard Review Plan SR .5.1 addresses flame spread in its
definition of noncombustible materials. It states, in part, that a
noncombustible material has "a structural base of noncombustible
material...with a surfacing not over 1/8-inch thick that has a flame spread
rating not higher than 50...."
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 NRR project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN T LAG.FST
- See previous concurrence - -
FE nwnVwith &ttachnent/onclosure 'N' = No copy
I *.eceive a copy of tls documem Incaacto. inthN doX %. *py
- W
OFFICE SPLB:DSSA I OECB:DOPS I ADM:PUB I N SC/SPLB:DSSA I C/SPLB:DSSA L
NAME PMadden* JCarter* Tech Editor* SWest*CMcCracken*
DATE 07/07/95 07/07/95 107/06/95 107/07/95 07/07/95 nFrrFl IqC/PFrRCBRPM I
-.IPECB:DRPM.
___
l
I -I
L/PtLb:UKFM I
I &r~ff~ffi
I U/UKrr
_ I-]1 l -l
NAME __ _iessel
RDennig Y fibAChaffee DCrutchfield U
DATE / /95 I I/2 /95 1//._ rflfV
/ /95
_________ -,~rrvo-Tivs 1117Plnn
OFFMIv L KC%,UKU vUr 1
-4 IN 95-XX
July xx, 199 purchased from TSI, were not topcoated. The maximum flame spread measured for
this specimen was 8 feet at 7 minutes and 20 seconds into the test. This
equated to a flame spread rating of 25.
Discussion
Flame spread tests are used to determine the surface burning characteristics
of materials when exposed to a test fire. Flame spread test results are used
to compare the surface burning characteristics of different materials and are
one consideration in assessments of the fire hazard introduced when a material
is used in an area. The higher the numerical flame spread rating, the greater
the flammability hazard. For example, cement-asbestos board and red oak
flooring, which are used to calibrate the test furnace, have flame spread
ratings of 0 and 100, respectively.
NRC staff guidelines regarding flame spread are contained in several NRC
documents. For example, although it is not directly applicable to fire
barriers, Branch Technical Position (BTP) APCSB 9.5-1 states, in part, that
"(interior wall and structural components, thermal insulation materials, and
radiation shielding materials and sound-proofing should be non-combustible.
Interior finishes should be non-combustible or listed by nationally recognized
testing laboratory...for a flame spread 25 or less...' In addition, Standard
Review Plan (SRP) 9.5.1, addresses flame spread in its definition of
noncombustible materials. It states, in part, that a noncombustible material
has "a structural base of noncombustible materiaJ...with a surfacing not over
1/8-inch thick that has a flame spread rating not higher than 50..."
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 NRR project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contact: Patrick M. Madden, NRR
(301) 415-2854 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\INTLAG.FST
To receive a copy of this docuent, Indicate in the box: 'C"a Copy without attachmenthnclosure ET = Copy whh attachment/enclosure W - No copy
OFFICE SPLB:DSSA OPS ADM:PUB ISC/SPLBDSSP
NAME PMadde rrTech Editor ICMcCracke
DATE I/ 7 5 0"( / / /95 1L7E!~. 4' / 7 /95 OFFICE SCIOECB:DOPS OECB:DOPS C/OECB:DOPS D/DOPS
NAME RDennig RKiessel 1 AChaffee BGrimes s
DATE / 195 / /95 / /95 / /95 OFFICIAL RECORD COPY
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak, Water hammer)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995, Topic: Hardened grease)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves, Overspeed)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Overspeed)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request, Overspeed, Manual Operator Action)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy, Underdose)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Commercial Grade, Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
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