ML20096D435
| ML20096D435 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 01/12/1996 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-08, GL-92-8, NUDOCS 9601190130 | |
| Download: ML20096D435 (2) | |
Text
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m Tennessee Vahey Authonty Post Off6ce Box 2000. Soddy Daisy Tennessee 37379 January 12,'1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SON) - UPDATE OF TVA'S JUNE 15,1995, FOLLOW-UP INFORMATION REGARDING GENERIC LETTER (GL) 92-08, THERMO-LAG 330-1 FIRE BARRIERS
References:
- 1. TVA letter to NRC dated March 22,1995, "Sequoyah Nuclear Plant (SON)- Response to the Follow-up Request for Additional Information (RAl) Regarding Generic Letter (GL) 92-08,'Thermo-Lag 330-1 Fire Barriers'"
- 2. TVA letter to NRC dated June 15,1995,"Sequoyah (SON) and Watts Bar (WBN) Nuclear Plants - Update of TVA's March 22,1995, Response to NRC Request for Additional information Regarding Generic Letter (GL) 92-08,'Thermo-Lag 330-1 Fire Barriers'"
The purpose of this letter is to confirm the telephone conversation on December 22, 1995, between TVA and NRC staff pertaining to additional Thermo-Lag 330-1 testing being performed by TVA.
In Reference 1, SON committed to perform chemical testing on removed Thermo-Lag 330-1 material and evaluate the results against Thermo-Lag 330-1 materials used in TVA's WBN fire testing program.
During the Thermo-Lag 330-1 installation at WBN, TVA discovered a discrepancy between the Thermo-Lag 330-1 used in the qualification testing and the circa 1985 Thermo-Lag 330-1 materials that are stored in the TVA Hartsville warehouse. TVA also identified that some of the discrepant material was installed at SON. TVA informed NRC of this issue on June 15,1995 (Reference 2).
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1 January 12,1996 In or' er to determine the performance of the older Thermo-Lag 330-1 and demonstrate -
d that the Thermo-Lag 330-1 installed at SON is representative of tested materials, TVAL will be conducting a full scale one-hour. fire test.' The test assembly was constructed =
using New Old Stolck (NOS) Thermo-Lag 330-1 that produced the differing results Lwhen tested by Thermogravimetric Analysis'(TGA).L Thermo-Lag 330-1 material that -
4 has demonstrated acceptable.TGA results are included in the test assembly as contro'.
samples. In addition to testing representative SON materials, (the materialis of the
. same vintage, in some cases the same lots as that currently installed at SON) the test z
assembly was also designed to expand TVA's knowledge on the effects of cable fillin three-inch conduit protected with a single layer of nominal 5/8-inch Thermo Lag 330-1 and the effects of 0.5-inch stainless steel banding. In order for the test to be.
3 representative of installed SON configurations, the assembly was constructed by the '
same SON insulator craftsmen that installed the original SON installations.
The test is scheduled to be conducted on January 17,1996, at Omega Point Laboratories, San Antonio Texas. NRC is welcome to attend this testing. The results i
of this test will be used to develop SON's final plan for implementation of the subject
~ GL as described in Reference 1 of this letter.
f Please direct questions concerning this issue to W. C. Ludwig at (423) 843-7460.
Sincerely, e
R. H. Shell
[
Manager j
SON Site Licensing cc: Mr. D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident inspector U
Sequoyah Nuclear Plant-2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission i
Region 11 101 Marietta Street, NW, Suite 2900
' Atlanta, Georgia 30323-2711 i
.