Information Notice 1997-59, Fire Endurance Test Results of Versawrap Fire Barriers

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Fire Endurance Test Results of Versawrap Fire Barriers
ML031050215
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  Entergy icon.png
Issue date: 08/01/1997
From: Slosson M
Office of Nuclear Reactor Regulation
To:
References
IN-97-059, NUDOCS 9707300061
Download: ML031050215 (6)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 August 1, 1997 NRC INFORMATION NOTICE 97-59: FIRE ENDURANCE TEST RESULTS OF

VERSAWRAFP FIRE BARRIERS

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 alert

addressees to the preliminary results of a recent fire endurance test of a new fire barrier

system. No specific action or written response is required.

DescriDtion of Circumstances

Transco Products, Incorporated, of Chicago, Illinois, is developing Versawrap as a

stand-alone fire barrier or as a potential upgrade for such existing raceway fire barriers as

Thermo-Lag 330-1 for use in nuclear power plants to meet NRC fire protection regulations.

On April 7, 1997, the NRC staff met with Entergy Operations, Incorporated, the licensee for

Arkansas Nuclear One, to discuss the use of Versawrap fire barriers to protect redundant

post-fire safe shutdown components. Subsequently, on April 10 and 11, 1997, the NRC staff

witnessed a full-scale fire endurance test of proposed 1-hour and 3-hour fire-rated Versawrap

fire barriers at Underwriters Laboratories, Incorporated (UL), of Northbrook, Illinois. The tests

were also witnessed by representatives of Entergy Operations, Incorporated, and Northern

States Power Company.

The following summary of the test results is taken from the staffs trip report:

Assuming that the thermocouples were working properly and on the basis of

the printed temperatures at the end of about 61 minutes, it appeared that test

articles A, B, C, D, L, 0, and R met the maximum single point temperature rise

acceptance criteria [of 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'] for a 1-hour fire

rating while test articles E and Q did not. Assuming that the thermocouples

were working properly and on the basis of the printed temperatures at the end

of about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 55 minutes (the temperatures at 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> were not

PPDk rJ-E aOTLD1- 9q -Aji07 7a

970 41,I'j!,

. 3

K>

IN 97-59 August 1, 1997 printed), it also appeared that test articles F, G, H, and I may meet the maximum

single point temperature rise acceptance criteria of GL 86-10, [Supplement 11, for a

3-hour fire rating, but test articles J, K, M, N, and P will not.

The observations made by the NRC staff during the fire endurance test are not sufficient in

and of themselves to determine whether or not Versawrap fire barriers will meet NRC criteria

for qualifying fire barriers. In Ks trip report, the staff also noted that UL would document the

results of the fire endurance test and that UL would base its conclusions regarding the

performance of the test articles on its observations during the fire endurance and hose

stream tests, analyses of electronically recorded thermocouple data, and consideration of

both the maximum single point temperatures and the average unexposed side temperatures.

Review and assessment of each of these factors are needed to determine whether the barrier

configurations that were tested meet the NRC acceptance criteria specified in GL 86-10,

Supplement 1. To date, no licensee has submitted the fire test results to the NRC for review.

The staffs meeting summary and trip report are available at the NRC Public Document Room

(Accession Numbers 9704188084 and 9705130324, respectively).

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.

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: K.S. West, NRR

301-415-1220

E-mail: kswenrc.gov

T.J. Carter, NRR

301-415-1153 E-mail: tjc@nrc.gov

Attachment: List of Recently Issued Information Notices

or +ie' )4ck~t,

I I

Attachment

IN 97-59 August 1, 1997 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

97-58 Mechanical Integrity of 07131/97 Holders of and Applicants

In-Situ Leach Injection for Licenses for In-Situ

Wells and Piping Leach Facilities

97-57 Leak Testing of Packaging 07/30/97 Suppliers and users of

Used in the Transport of packaging for the trans- Radioactive Material portation of radioactive

material required to per- form packaging leak tests

97-56 Possession Limits for 07/28/97 All licensees authorized

Special Nuclear Material to possess special nuclear

at the Environcare of material

Utah Low-Level Radioactive

Waste Disposal Facility

97-55 Calculation of Surface 07/23/97 All Uranium Recovery

Activity for Contaminated Licensees

Equipment and Materials

97-54 NRC Licensed Operators 07/18/97 All holders of OLs or CPs

at Six Non-Power Reactor for test and research

Facilities Allow their reactors and all licensed

Operator Licenses to operators at test and

Expire research reactor facilities

97-53 Circuit Breakers 07/18/97 All holders of OLs or CPs

Left Racked Out in for nuclear power reactors

Non-Seismically

Qualified Positions

97-52 Inadvertent Loss of 07/17/97 All holders of OLs or CPs

Capability for Emer- for nuclear power reactors

gency Core Cooling

System Motors

OL = Operating License

CP = Construction Permit

IN 97-59 August 1, 1997 printed), i also appeared that test articles F, G, H, and I may meet the maximum

single point temperature rise acceptance criteria of GL 86-10, [Supplement 11, for a

3-hour fire rating, but test articles J, K, M, N, and P will not.

The observations made by the NRC staff during the fire endurance test are not sufficient in

and of themselves to determine whether or not Versawrap fire barriers will meet NRC criteria

for qualifying fire barriers. In its trip report, the staff also noted that UL would document the

results of the fire endurance test and that UL would base its conclusions regarding the

performance of the test articles on its observations during the fire endurance and hose

stream tests, analyses of electronically recorded thermocouple data, and consideration of

both the maximum single point temperatures and the average unexposed side temperatures.

Review and assessment of each of these factors are needed to determine whether the barrier

configurations that were tested meet the NRC acceptance criteria specified In GL 86-10,

Supplement 1. To date, no licensee has submitted the fire test results to the NRC for review.

The staffs meeting summary and trip report are available at the NRC Public Document Room

(Accession Numbers 9704188084 and 9705130324, respectively).

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.

original signed by S.H. Weiss for

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: K.S. West, NRR

301-415-1220

E-mail: kswenrc.gov

T.J. Carter, NRR

301-415-1153 E-mail: tjc@nrc.gov

Attachment: List of Recently Issued Information Notices

DOCUMENT NAME: 97-59.IN *SEE PREVIOUS CONCURRENCES

To receive a copy of this document, Indicate In the box: "C" - Copy without enclosures "" - Copy with enclosures "NP- No copy .

OFFICE Tech C:SPLB C:PECB (A)D:DRPM

Contact I ILI

NAME SWest* LMarsh* AChaffee* MSlosson<i7,)

JCarter* _ ____,',

DATE 07/14/97 07/15/97 07/17/97 0 7 V/ 07/ /97 OFFICIAL RECORD COPY

IN 97-xx

July xx, 1997 printed), it also appeared that test articles F, G, H, and I may meet the maximum

single point temperature rise acceptance criteria of GL 86-10, [Supplement 1], for a

3-hour fire rating, but test articles J, K, M, N, and P will not.

The observations made by the NRC staff during the fire endurance test are not sufficient in

and of themselves to determine whether or not Versawrap fire barriers will meet NRC criteria

for qualifying fire barriers. In its trip report, the staff also noted that UL would document the

results of the fire endurance test and that UL would base its conclusions regarding the

performance of the test articles on its observations during the fire endurance and hose

stream tests, analyses of electronically recorded thermocouple data, and consideration of

both the maximum single point temperatures and the average unexposed side temperatures.

Review and assessment of each of these factors are needed to determine whether the barrier

configurations that were tested meet the NRC acceptance criteria specified in GL 86-10,

Supplement 1. To date, no licensee has submitted the fire test results to the NRC for review.

The staffs meeting summary and trip report are available at the NRC Public Document Room

(Accession Numbers 9704188084 and 9705130324, respectively).

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.

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: K.S. West, NRR

301-415-1220

E-mail: ksw@nrc.gov

T.J. Carter, NRR

301-415-1153 E-mail: tjcenrc.gov

Attachment: List of Recently Issued Information Notices

DOCUMENT NAME: G:ITJCVERSWRAP.IN *SEE PREVIOUS CONCURRENCES

To receive a copy of this document, Indicate Inthe box: "C - Copy wfthout enclosures " = Copy with enclosures "W No copy

OFFICE Tct C:ZSPLB C:PECB (A)D:DRP M I ZI

Contact I I IlI

NAME SWest* LMarsh* AChaffee* MSlosson

JCarter*

DATE 107/14/97 07/15/97 07/17/97 07/ /97 07/ /97 OFFICIAL RECORD COPY4AA U 7

44 4 -7/i1f1

IN 97-xx

July xx, 1997 printed), it also appeared that test articles F, G, H, and I may meet the maximum

single point temperature rise acceptance criteria of GL 86-10, [Supplement 11, for a

3-hour fire rating, but test articles J, K, M, N, and P will not.

The observations made by the NRC staff during the fire endurance test are not sufficient in

and of themselves to determine whether or not Versawrap fire barriers will meet NRC criteria

for qualifying fire barriers. In its trip report, the staff also noted that UL would document the

results of the fire endurance test and that UL would base its conclusions regarding the

performance of the test articles on its observations during the fire endurance and hose

stream tests, analyses of electronically recorded thermocouple data, and consideration of

both the maximum single point temperatures and the average unexposed side temperatures.

Review and assessment of each of these factors are needed to determine whether the barrier

configurations that were tested meet the NRC acceptance criteria specified in GL 86-10,

Supplement 1. To date, no licensee has submitted the fire test results to the NRC for review.

The staffs meeting summary and trip report are available at the NRC Public Document Room

(Accession Numbers 9704188084 and 9705130324, respectively).

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.

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: K.S. West, NRR T.J. Carter

301-415-1220 301-415-1153 E-mail: ksw@nrc.gov E-mail: tjcenrc.gov

Attachment:

List of Recently Issued Information Notices

DOCUMENT NAME: G:%TJC\VERSWRAP.IN

To receive a copy of this document, Indicate In the box: "C' - Copy without enclosures "E"- Copy with enclosures "HN

' No copy

OFFICE Tech C: SPLB l C:PECB (A)D:DRPM

Contact G*I

NAME SWestA LMarsh AChaffee C-5 MSlosson

JCarterv',I"

D ATE 7/97/17 07/K /97 07/r)/9 07/ /97 07/ /97 OFFAICXL RECORD COPY


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