TXX-4275, Informs That Steam Generator Tube Rupture Reevaluation Will Include Calculations to Determine Margin to Overfill & Equilibrium Breakflow Showing Time to Overfill Is Greater than Time to Equalization,Per NRC 840409 Request
| ML20095E983 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/22/1984 |
| From: | Schmidt H TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TXX-4275, NUDOCS 8408270132 | |
| Download: ML20095E983 (2) | |
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TEXAS UTILITIES GENERATING COMPANY Log # TXX-4275 File # 915.6
, MKYWAY TOWEft
- 400 NORTil OLIVE MTHEET, L.II. M1
- DALLAM, TEXAM 73201 August-22, 1984 Mr. B. J. Youngblood, Chief Division of Licensing Licensing Branch No. 1 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 RESPONSE TO STEAM GENERATOR TUBE RUPTURE CONCERN
Dear Mr. Youngblood:
Texas Utilities Generating Company (TUGC0) has been working (WOG) on with the NRC and Westinghouse through the Westinghouse Owners Group the reevaluation of the accident senario for Steam Generator Tube Ruption (SGTR).
As part of the WOG we have participated in the -
meetings and discussions on SGTR referd to in your letter dated August 9, 1984.
TUGCO, Westinghouse and the WOG as part of the scope of the ongoing SGTR study (reviewed and commented on the NRC) are working on the questions sent to us by your letter of April 9,1984.
It is now planned that the SGTR reevaluation will include (but will not necessarily be limed to) the following:
- 1) Calculations to determine the margin to overfill and the equilibrium breakflow showing the time to overfill is greater than the time to equalization.
- 2) Op'erator action times used in the analysis will be' verified.
- 3) Plant sp,ecific justification for use of certain non-safety grade equipment in recovery from a SGTR event.
- 4) Rational and justification that the analysis is conservative from the standpoint of radiological releases.
- 5) An analysis of the effects of steam line overfill on the integrity of steam line piping and supports.
From the information developed to date and the favorable response l
received from the NRC on the WOG-SGTR program, we believe that this I
issue will be resolved with minimal impact on Comanche Peak and that 1
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.. Log # TXX-4275 operation in the interim is justified. This interim operation is inhat.ced by_the fact that Comanche Peak is a new plant and TUGC0 is an active participant-in the WOG-SGTR Subgroup.
We believe that the above information is responsive to your reguest for additional information.
If you have any_ additional questions, please let us know.
Sincerely, H. C. Schmidt RAW:tls c - J. J. Stefano 9
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