ML20084N422
| ML20084N422 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point, 05000000 |
| Issue date: | 12/15/1971 |
| From: | Kinsman G FLORIDA POWER & LIGHT CO. |
| To: | Jennifer Davis US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084N179 | List: |
| References | |
| NUDOCS 8306030207 | |
| Download: ML20084N422 (2) | |
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a FLORIDA FOWER & UGHT COMPA:n December 15, 1971 Mr.' John G. Davis,' Director U. S. Atomic Energy Commission Division of Compliance, Region 11 230 Feachtree Street, N. W.,
Suite 818 Atlanta, Georgia 30303 Rs:
Turkey Point Unit No. 3 Docket No. 50-250 Daar Mr. Davis:
This letter is'to answer your telegram received on December 4, 1971.
The answers below are in the order of your questions:
1 The failure occurred in two twelve-inch horizontal safety valve stub headers on opposite sides of main steam line 3A.
The subject headers were at 90 degrees to the main steam line and each was supported by two saddles.
Each header had two safety valve nozzles attached.
Each nozzle was made up of a weldolet and a weld end flange.
Failure of the headers was in the pipe metal just below and outside the nozzle to pipe weld.
The out-board valve on one stub completo with the no==lo left the stub and the pipe opened up.
Both valves complete with nozzles left the other header with little distortion of the pipe remaining.
The piping configuration and.the failure are shown in the photographs given to your Mr. Lewis on December 4, 1971.
At the time of the incident, the hot functional test was in progress but the unit was e,ssentially in hot standby waiting for turbine-generator work to be completed so it could be rolled on steam.
.Indicatod steam pressure was 990 psig.
2 The cause analysis and the materials investigation results will not be available within the deadline given for response to your telegram.
3.'
All stub headers have been removed and replacement headers are being designed.
8306030207 730604 "
gDRADOCK 05000250 PDR
'Mr. John G. Davis n
Deedmter 15, 1971 U
Page 2 A report of the incident, results of the analysis of the f'arture, and a description of the new design headers will be submitted to the Division of Reactor Licensing as soon as possible.
Very truly yours, d
I George Kinsman Senior Vice President GK:std O
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