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

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
Issue date:	11/14/1995
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
References
GL-86-010 IN-95-052, NUDOCS 9511080324
Download: ML031060151 (11)

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

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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

Att__Lament 1 K>_ 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

Rear side rail J 262 337 Interam E53A.

Met acceptance criteria.

Copper conductor Ila

24" Cable tray Front side rail Protected with four layers of

Interam E53A.

Rear side rail Exceeded the maximum single point

temperature criterion at 50X minutes

and the average temperature rise

Copper conductor

______________ .4 criterion at 54X minutes.

5" Conduit Conduit surface 1 277 1 370 Protected with three layers of

Interam E53A.

Copper conductor I 217 275 Met acceptance criteria.

3" Conduit Conduit surface Protected with three layers of

Interarn E53A.

Exceeded the maximum single point

Copper conductor temperature criterion at 59 X minutes

and the average temperature rise

criterion at 53 X minutes.

2" Conduit Conduit surface Protected with three layers of

Interam E54A.

Exceeded the maximum single point

Copper conductor temperature criterion at 55X minutes

and the average temperature rise

criterion at 55 minutes.

1- Conduit Conduit surface Protected with two layers of

Interam E53A and an outer layer of

Interam E54A.

Exceeded maximum single point

Copper conductor temperature criterion at 49X minutes

and the average temperature rise

I criterion at 52 minutes.

_________________________________

2" air drop Copper conductor 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 IN95-52 November 14, 1995 Table 3. Summary of July 7. 1995 Fire Endurance Test

Peak Sea Is- 3M Company 3-Hour Interam Fire Barrier

Allowable single ; piInt unexposed-side temperature criterion - 407 OF

Allowable averal ge unexposed-side temperature criterloon - 332 OF

(Shading shows temperature a that exceeded acceptance criteria of GL 86-10. Supplement 1) .

TEST SPECIMEN THERMOCOUPLE AVERAGE MAXIMUM REMARKS

LOCATIONS ([F) I (1F) I

6" Cable tray Front side rail Protected with five layers of

Interam E54A. Exceeded the

Rear side rail maximum single point temperature

criterion at 158 minutes and the

average temperature rise criterion at

Copper conductor 301 343 166 minutes.

24" Cable tray Front side rail Protected with five layers of

Interam E54A. Exceeded the

Rear side rail 406 maximum single point temperature

criterion at 176 minutes and the

average temperature rise criterion at

Copper conductor 243 334 167 minutes.

5" Conduit Conduit surface Protected with five layers of

Interam E54A. Exceeded the

maximum single point temperature

criterion at 161 minutes and the

Copper conductor

average temperature rise criterion at

178 minutes. .

3' Conduit Conduit surface Protected with five layers of

Interam E54A. Exceeded the

maximum single point temperature

criterion at 148 minutes and the

Copper conductor

average temperature rise criterion at

152 minutes.

1" Conduit Conduit surface Protected with six layers of

Interam E54A. Exceeded the

maximum single point temperature

criterion at 126 minutes and the

Copper conductor sversge temperature rise criterion at

167 minutes. .

2" Air drop Copper conductor Protected with five layers of

Interam E54A. Exceeded the

maximum single point temperature

criterion and the average temperature

rise criterion at 152 minutes.

.

Junction box Metal surface 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 Recent Incidents Involving 10/27/95 All material and fuel

Potential Loss of Control cycle licensees.

of Licensed Material

95-50 Safety Defect in Gammamed 10/30/95 All High Dose Rate

12i Bronchial Catheter Afterloader (HDR) Adapters.

Clamping Adapters

95-49 Seismic Adequacy of 10/27/95 All holders of OLs or CPs

Thermo-Lag Panels for nuclear power reactors.

95-48 Results of Shift Staffing 10/10/95 All holders of OLs or CPs

Study for nuclear power reactors.

95-47 Unexpected Opening of a 10/04/95 All holders of OLs or CPs

Safety/Relief Valve and for nuclear power reactors.

Complications Involving

Suppression Pool Cooling

Strainer Blockage

95-46 Unplanned, Undetected 10/06/95 All holders of OLs or CPs

Release of Radioactivity for nuclear power reactors.

from the Exhaust Ventilation

System of a Boiling Water

Reactor

95-12, Potentially Nonconforming 10/05/95 All holders of OLs or CPs

Supp. 1 Fasteners Supplied by for nuclear power reactors.

A&G Engineering II, Inc.

95-45 American Power Service 10/04/95 All holders of OLs or CPs

Falsification of American for nuclear power reactors.

Society for Nondestructive

Testing (ASNT) Certificates

95-44 Ensuring Compatible Use of 09/26/95 All Radiography Licensees.

Drive Cables Incorporating

Industrial Nuclear Company

Ball-Type Male Connectors

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 3, Summaries of Endurance Tests

2. List of Recentl, Issued NRC Information Notices

AWAS4 6'zp "' Ilke4- &&I--

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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

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OFFICIAL RECORD COPY

IN95-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 3, Summaries of Endurance Tests

2. List of Recently Issued NRC Information Notices

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OFFICE SPLB:DSS\A1, '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/ /__

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