ML20248B030
| ML20248B030 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 09/28/1989 |
| From: | William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89725, NUDOCS 8910030076 | |
| Download: ML20248B030 (2) | |
Text
l l
l
= = ::
1 1
Log # TXX-89725
{
g File # 903.8 lilELFCTRIC September 28, 1989 W. J. Cahill Decutive Mce President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555.
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 CLARIFICATION OF PREVIOUS RESPONSE TO THE-REQUEST FOR ADDITIONAL INFORMATION ON FSAR SECTION 3.8 Gentlemen:
On July 31, 1989, a public meeting was held in Bethesda, Maryland, to discuss the NRC's Request for Additional. Information (RAI) on the amended FSAR-Sections 3.7 and 3.8.
TU Electric's le+ter TXX-89569 dated August 16, 1989, provided a response to the RAI items discussed in.the public meeting.
During September 6-7, 1989, the NRC conducted a. structural audit at CPSES.
As a result of discussions during and after the audit, TU Electric is providing a revised respoitse to RAI Item No.14 (see enclosure).
If you have any questions regarding this submittal, please contact Carl Corbin at (214) 812-8859.
J Sincerely, h*-
[.
William J. Cahill, Jr.
By:
0t784 Roge d. Walker Manager, Nuclear Licensing CBC/cbc Enclosure c - Mr. R. D. Martin, Region IV i
Resident' Inspectors, CPSES (3)
,(a6k.
8910030076 890928 i
/r i
PDR ADOCK 05000445 A
PDC J
l I
' 400 North Olive Street LR 81 Dallas, Texas 75201
Enclosure to TXX 89725 Page 1 of 1 RESPONSE TO REVIEW OF AMENDED FSAR SECTION 3.8
- 14. Provide the results of your determination of the ultimate capacity of the containment structure and discuss the analytical procedures as per the requirements.of USNRC f,RP NUREG-0800, Section 3.8.
Also specify the extent of plastic deformation allowed in the structural evaluation of CPSES components.
Response
The previous issue of SRP 3.8.1 (NUREG-75-087) did not address ultimate containment capacity.
However, TU Electric will provide the ultimate capacity of the Unit 1 concrete containment by October 31, 1989. Thi s..
response will include an evaluation of the concrete containment building and a comparison of the typical penetration conditions at CPSES to other similar containments.
1 i
l
- - - - _ = _ _ _
.