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 M 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 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

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IN' -No copy iOFFICE PECB:DRPM*

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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

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

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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

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