ML20248B030

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Forwards Clarification to Util 890816 Response to NRC 890731 Request for Addl Info Re Amended FSAR Sections 3.7 & 3.8. Rev to Response Provided Per Discussions During & After NRC 890906-07 Structural Audit at Facility
ML20248B030
Person / Time
Site: Comanche Peak Luminant icon.png
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)


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Log # TXX-89725

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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)

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8910030076 890928 i

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' 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.

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