ML19324B715
| ML19324B715 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/24/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-88-008, IEB-88-8, TXX-89769, NUDOCS 8911080068 | |
| Download: ML19324B715 (1) | |
Text
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1 L
f TXX 89769 FNef903.6 P "".
E 10010 Ref. # 10CFR50 nlELECTRIC October 24, 1989 i
?NbD}l6 U. S. Nuclear Regulatory Commission i
Attn: Document Control Desk i
Washington, D. C.
20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) i DOCKET NOS. 50-445 AND 50 446 ADDITIONAL INFORMATION ON THERMAL STRESSES IN PIPING CONNECTED 10 REACTOR COOLANT SYSTEMS i
REF:
- 2) NRC Bulletin No. 88-08, Supplement 3:
Thermal Stresses in Piping Connected To Reactor Coolant Systems l
i Gentlemen:
Reference 1 provided TV Electric's response to NRC Bulletin No. 88 08, regarding thermal stresses in piping connected to reactor coolant systems l
l (RCS).
In a teiephone call on September 22, 1989, S. Lee of your staff asked whether the information in reference 1 required revision in light of the i
phenomena described by reference 2.
This letter provides the response to that question.
i The phenomena described in reference 2, involving thermal stratification of the Residual Heat Removal (RHR) suction line due to valve packing leakage has been evaluated and is encompassed by the analyses su) porting leak-before break i
qualification of the RHR suction line.
TV Electric 1as concluded that the l
response provided by reference 1 is correct and no change to reference 1 is l
L
- required, j
The information provided in this letter has been discussed with S. Lee of your staff.
If you have any questions, please contact H. A. Marvray at (214) 812 8296.
l Sincerely, i
e j *I 891100006e s91024
-- f:
45g ADOCK 0 gDR l
William J. Cahill, Jr.
I HAM /smp c - Mr. R. D. Martin, Region IV
- 7Ed, Resident Inspectors, CPSES (3)
M brth Olive Street LB 51 Dallas, Texas 73201 l
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