Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems

One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems

ML031080038
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
Issue date:	05/28/1993
From:	Grimes B Office of Nuclear Reactor Regulation
To:
References
IN-93-041, NUDOCS 9305280011
Download: ML031080038 (8)

A~- I

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 May 28, 1993 NRC INFORMATION NOTICE 93-41: ONE HOUR FIRE ENDURANCE TEST RESULTS FOR

THERMAL CERAMICS KAOWOOL, 3M COMPANY FS-195 AND

3M4 COMPANY INTERAM E-50 FIRE BARRIER SYSTEMS

Addressees

for nuclear power

All holders of operating licenses or construction permits

reactors.

PurDose

information

The U.S. Nuclear Regulatory Commission (NRC) is issuing this tests for Thermal

notice to alert addressees to the results of fire endurance

(3M Company)

Ceramics Kaowool, Minnesota Mining and Manufacturing Company reviewed by

FS-195, and 3M Company Interam E-50 1-hour fire barrier systems

inspection. It is expected that

NRC inspectors during a reverification to their facilities

recipients will review the information for applicability

However, and consider actions as appropriate to avoid similar problems.requirements;

notice are not NRC

suggestions contained in this information

therefore, no specific action or written response is required.

Description of Circumstances

the staff stated it

In Generic Letter 92-08, "Thermo-Lag 330-1 Fire Barriers," that are used by

would evaluate other known fire barrier materials and systems to Appendix R

licensees to fulfill NRC fire protection requirements pursuant staff has started

to 10 CFR Part 50 of the Code of Fedefal Regulations. The Thermal

by vendors other than

its review of fire barriers manufactured barrier systems to

Science, Incorporated, to verify the capability of the fire

and to meet

adequately perform their 1-hour or 3-hour fire-resistive functions

stated ampacity derating values.

at the Salem

A reverification inspection was conducted by NRC inspectors Electric Company

Nuclear Generating Station, owned by Public Service Gas and fire

(the licensee), the week of May 17, 1993. NRC inspectors reviewed systems used by

endurance test results for the electrical raceway fire barrier same fire area.

the licensee to separate safe shutdown functions within the FS-195 and

The systems used were Thermal Ceramics Kaowool, 3M Company in the fire

3M Company Interam E-50. The fire test results, as documented summarized in

barrier qualification test reports, are discussed below and are

the attached table.

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IN 93-41 May 28, 1993 Kaowool Fire Barrier

Thermal Ceramics, Inc., was formerly the Insulating Products Division

of

Babcock and Wilcox, Inc., of Augusta, Georgia. The licensee fire endurance

testing basis for Kaowool is a Babcock and Wilcox fire test report

October 24, 1978. of

According to the report, five specimens of the Kaowool

barrier were tested on cable trays in a small-scale furnace. The maximum

length of the 45.7 cm [18 inch] wide cable trays was 61 cm [24 inches].

fill ranged from 33 percent to 35 percent. According to the report, Cable

test acceptance criterion was circuit integrity. The tests were not the fire

or controlled by an independent testing laboratory. conducted

The test report stated that the circuit integrity in one circuit was

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 1 minute. It also stated that cable temperatures exceeded lost at

[250 OF] above ambient air temperature in about 22 minutes. At 60 minutes 139 OC

into the test, the cable temperature was about 426.5 *C [800 OF]. Hose

tests were not performed. The results section of the test report stated stream

cables in all tests exhibited signs of fire damage, such as charring. that

3M Company FS-195 Fire Barrier

The licensee fire endurance qualification testing basis for the 3M Company

FS-195 fire.barrier system is a 3M Company test report of October 31, Test acceptance criteria were not reported. The report stated that 1980.

small-scale test at the 3M test facility. The figure in the report this was a

the test specimen was conceptual and did not give dimensions. According showing

the figure, the fire barrier was constructed by placing a cable tray to

metal air duct with the tray support in the middle of the duct. in a

The metal

duct was covered with FS-195, there was an air space- around the cable

and the tray contained 40 percent cable fill. tray, According to the test report, the metal duct temperature on the unexposed

of the fire barrier material exceeded 139 'C [250 OF] above ambient side

30 minutes. At 60 minutes the temperature was 326.5 °C [620 OF]. in about

specimen was not subjected to a hose stream test. The condition ofThe test

at the end of the test was not reported. the cables

3M Companv Interam E-50 Fire Barrier

The licensee fire endurance qualification testing basis for the 3M

Interam E-50 fire barrier system is a Twin City Testing Corporation Company

report of September 1986. The fire test acceptance criterion was test

circuit integrity as specified by American Nuclear Insurers. stated as

According to the test report, the cable tray test specimen was a 61

[24 inch] wide aluminum cable tray installed in the test slab in cm

configuration. The vertical drops into the furnace were 58.4 cm a horseshoe

[23 inches],

and the horizontal run'was 86.4 cm [34 inches]. The tray configuration

divided into four segments. A vertical run of solid bottom tray was

to a ladder-back 90o radial bend. This bend was connected to a was connected

tray segment, which was connected to a vertical ladder-back tray solid bottom

segment. The

IN 93-41 May 28, 1993 test specimen also included an air drop. One half of the tray had 14 percent

cable fill. The other half had 40 percent cable fill. A second test specimen

consisted of one 12.7 cm [5 inch] diameter steel conduit and one 12.7 cm

[5 inch] diameter aluminum conduit and a 25.4 cm [10 inch] by 25.4 cm

[10 inch] by 15.2 cm [6 inch] junction box.

The fire barrier installation procedures appended to the test report specified

multiple installation methods. However, the fire barrier construction details

and methods of fire barrier application for the test specimens were not

documented in the test report.

The temperatures within the fire barrier and the condition of the cables at

the end of the test were not reported.

As a result of the issues raised during the inspection, the licensee posted

fire watches as compensatory measures in accordance with plant procedures.

Discussion

The staff is continuing its review of these fire barrier systems including a

reassessment of any previous staff reviews of these systems. The staff

previously requested additional information on Kaowool from Thermal Ceramics, Incorporated, in a letter of April 27, 1993, and on the 3M fire barrier

systems from 3M Company in a letter of May 4, 1993. The staff will evaluate

whether further generic communications are needed to address the issues

discussed above.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Pat Madden, NRR

301-504-2854 Attachments:

1. Summary of Test Results

2. List of Recently Issued Information Notices

Attachment 1 IN 93-41 May 28, 1993 Page l.of 1 Summary of Test Results

Scale of test Small-scale Small-scale Small-scale

Test laboratory Not independent Not independent Not independent, but witnessed by

Twin City

_ _Testing Corp.

Hose stream test Not performed Not performed Performed

Cable damage Charred Unknown Unknown

Tested Not Not Not

configuration representative of representative of representative

in-plant in-plant of in-plant

configurations configurations configurations2 Maximum -426.5 C 326.5 eC[620 OF] Unknown

temp rature at 1 [-800 OF]

hour

Comments Accepted by NRC Accepted by NRC Installed in

11/20/1979 3/18/1981 1991; not

submitted to NRC

1 In a letter of May 18, 1993, to the NRC, the 3M Company stated that the

FS-195 fire barrier system is used only at Salem.

2 3M Company provided additional test reports to the licensee on

May 20, 1993. The licensee is evaluating the applicability of these test

reports to the in-plant configurations.

3 NRC acceptance criteria is 139 eC [250 OF] above ambient.

KQ~

Attachment 2 IN 93-41 May 28, 1993 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Subject Issuance Issued to

Notice No.

Fire Endurance Test 05/26/93 All holders of OLs or CPs

93-40 for nuclear power reactors.

Results for Thermal

Ceramics FP-60 Fire

Barrier Material

93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs

Power Reactor Biolog- for nuclear power reactors.

ical Shields

Inadequate Testing of 05/24/93 All holders of OLs or CPs

93-38 for nuclear power reactors.

Engineered Safety

Features Actuation

System

Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs

93-37 for nuclear power reactors.

minate Properties In- stalled in Limitorque

Valve Operator Housing

Covers

Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory

93-36 Commission medical

and Records of Misadmin- istrations licensees.

Insights from Common- 05/12/93 All holders of OLs or CPs

93-35 for nuclear power plants

Cause Failure Events

(NPPs).

Potential for Loss of 05/06/93 All holders of OLs or CPs

93-34, for nuclear power reactors.

Supp. 1 Emergency Cooling

Function Due to A

Combination of

operational and Post- Loca Debris in Contain- ment

OL - Operating License

CP - Construction Permit

failiN

93-41 May 28, 1993 percent

test specimen also included an air drop. One half of the tray had 14 specimen

cable fill. The other half had 40 percent cable fill. A second test

cm

consisted of one 12.7 cm [5 inch] diameter steel conduit and one 12.7 cm [10 inch] by 25.4 cm

[5 inch] diameter aluminum conduit and a 25.4

[10 inch] by 15.2 cm [6 inch] junction box.

specified

The fire barrier installation procedures appended to the test report details

multiple installation methods. However, the fire barrier construction

for the test specimens were not

and methods of fire barrier application

documented in the test report.

at

The temperatures within the fire barrier and the condition of the cables

the end of the test were not reported.

As a result of the issues raised during the inspection, the licensee posted

fire watches as compensatory measures in accordance with plant procedures.

Discussion

a

The staff is continuing its review of these fire barrier systems including

reassessment of any previous staff reviews of these systems. The staff

previously requested additional information on Kaowool from Thermal Ceramics, Incorporated, in a letter of April 27, 1993, and on the 3M fire barrier

systems from 3M Company in a letter of May. 4, 1993. The staff will evaluate

whether further generic communications are needed to address the issues

discussed above.

If

This information notice requires no specific action or written response.

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager. Original signed by

Brian K. Grimes

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Pat Madden, NRR

301-504-2854 Attachments:

1. Summary of Test Results

2. List of Recently Issued Information Notices

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The temperatures within the fire barrier and the condition of the cables at

the end of the test were not reported.

The licensee opted to treat its fire barriers as indeterminate and posted fire

watches as compensatory measures in accordance with plant procedures after

discussing the reported fire test results with the NRC inspectors.

Discussion

The staff is continuing its review of these fire barrier systems including a

reassessment of any previous staff reviews of these systems. The staff

previously requested additional information on Kaowool from Thermal Ceramics, Incorporated in a letter of April 27, 1993, and on the 3M fire barrier systems

from 3M Company in a letter of May 4, 1993. The staff will evaluate if

further generic communications are needed to address the issues discussed

above.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Pat Madden, NRR

301-504-2854 Attachments:

1. Summary of Test Results

2. List of Recently Issued Information Notices

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Originator: Jeff Holmes-