ML20101H141
| ML20101H141 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/16/1992 |
| From: | Feldman R THERMAL SCIENCE, INC. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20101H139 | List: |
| References | |
| NUDOCS 9206290166 | |
| Download: ML20101H141 (25) | |
Text
1 5
4 16 June 1992 RUBW f rLDMAN. P.E.
Pres Wehl U S Nuclear Regulatory Commission Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20S52 Attention:
Mr. Ashok C. Thadani, Director Division of Systems Technology Office of Nuclear Reactor Regulaticn
Dear Mr. Thadani:
The NRC has previously received communications from Thermal Science, Inc.
relating to fire resistive testing of the THERMO-LAG 330 Fire Barrier System applied to 36 inch wide, open top, ladder back cable trays and 3/4 inch diameter conduits.
We are pleased to inform you that on Tuesday, June 9,1992, a very successful one hour fire resistive and water hose stream test was completed at the independent fire test facilities of Omega Point Laboratory in San Antonio, Texas. The one hour ASTM E119 fire simulation was followed by a 21/2 minute water hose stream exposure. Only generic cables were used. The cable tray contained one row of randomly spaced #12/7, #16/2 and 300 MCM cables. This was the first of several planned formal tests.
The following fire barrier n.aterials were used:
For the Cable Trav, lunction Boxes and Condulets:
- THERMO-LAG 330 Prefabricated Panels 0.625" t 0.125" nominal thickness
- THERMO LAG 330-1 Subliming Trowel Grade Material
- Stainless Steel Banding Material
- Stainless Steel Tie Wire For Conduits:
- THERMO LAG 330 Preshaped Conduit Sections 0.625" 0.125" nominal thickness
- THERMO-LAG 330-1 Subliming Trowel Grade Material-
- Stainless Steel Banding Material THERMAL SCIENCE, INC.
- 2200 CASSENS DR.
- ST. LOUIS, MO 63026 * (314) 349-1233 Telec Domestic 44 2384
- Overseas 209901
- Telecopier ( 314 ) 349-1207 9206290166 920622 PDR ADOCK 05000445 F
t
...___._...__m.-_.
Mr. Ashok C. Thadant 16 June 1992 Nuclear Regulatory Comission Page 2 The following are the highlights of this test:
- Electrical integrity was maintained throughout the fire endurance and water hose stream exposures.
- Cable Tray Test Assembly The maximum and average temperatures are shmvn in Figures 1 through 4 enclosed herein.
' Conduit Assembly - The maximum and average temperatures are shown in Figure 5. This is a 131 plot of the Omega. oint developed and provided data.
We have eliminated c,ne malfunctioning *.hermoccuple from this plot.
- Following the completion of the fire endurance and water hose stream test, portions of the THERMO-LAG wrap were removed from the test articles, with the following results:
- *The cables exhibited no damage whatsoever and were intact and flexible.
- *The nylon ties exhibited no damage and were flexible.
- *The paint on the junction boxes was intact and retained its gloss.
- A definable thickness of THERMO LAG 330 was present on the stress skin which was not damaged The test program, which is currently continuing with other planned tests,is under
'he total control of Omega Point Laboratory and includes:
- The construction of the test articles,
- The installation of the fire barrier system materials,
- Test article instrumentation,
- The performance of the fire endurance and water hose stre m tests.
- The performance electrical circuitry integrity monitoring,
- All pertinent Quality Control Documentation Omega Point Laboratory will publish the test reports.
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Mr. Ashok C. Thadani 16 June 1992 Nuclear Regulatory Comission Page 3 The tests are being conducted in accordance with the applicable prerequisites of:
Test Plan No. 31192 A Engineering Test Plan to Perfonn One llour Fire Endurance Tests Followed by Water Hose Stream Tests On a 36 Inch Wide Steel Open Top, Ladder Back Cable Tray GVith One Layer Of Generic Cables) and Steel Conduit Test Articles Protected With The THERMO. LAG 330 Fire Barrier System AN1's Bulletin B.7.2,11/87 "ANI/MAERP RA Guidelines For Fire Stop and Wrap Systems At Nuclear Facilities - Attachment B, Standard Fire Endurance Test Method To Qualify A Protective Envelope For Class IEEE Electrical Circuits",
Revision I, dated November 1987, as applicable U S Nuclear Regulatory Commission's Generic Letter 86-10 To All Power Reactor Licensees And Applicants For Power Reactor Licenses, dahd 24 April 1986 " Implementation Of Fire Protection Requirements", as applicable ASTM E119_(88)" Standard Methods of Fire Tests of Building Construciton and Materials", as applicable The planned details of construction are contained in the above referenced test plan.
The finallaboratory report, of course, is expected to provide the step by step details of what and how it was done.
The information presented herein is preliminary. It may be modified by the
-laboratory in its final report. - Please contact this office if you have any questions.
We Ic4 forward to a continuing association.
Yours truly,
~ ]{ f e-py p~
[_ j
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/)Q Rubin Feldnian i
President
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