ML20214P878
| ML20214P878 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/20/1986 |
| From: | Rice P GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GN-1163, NUDOCS 8612040408 | |
| Download: ML20214P878 (2) | |
Text
C Georgd Power Company -
' Post Offes Box 282
' Waynesborn Georgia 30830
- Mem 404 554-9sS1 Ext. N 3413 '
404 724-8114. Ext. 33ee '
i-l' GeorgiaPbwer P. D. Rice p
k &} }G A h l l f Ptos t
tM cumn entre system November 20,-1986
~ United States Nuclear Regulatory Commission Region II File: X7BG03-M78 Suite 2900 Log:
GN-1163 101 Marietta Street, Northwest
-Atlanta, Georgia 30323
Reference:
Vogtle Electric Generating Plant-Units 1 and 2; 50-424, 50-425; Safety Grade Core Exit Thermocouples Letter GN-654 dated July 2, 1985 Attention: Mr. J. Nelson Grace In previous correspondence on the above referenced subject, Georgia Power Company indicated the NRC would be informed of corrective actions-taken to resolve this concern.
The following corrective action has a
been taken:
'The temperature input required for temperature compensation of the Westinghouse RVLIS system was changed from core exit thermocouples to RCS wide range RTD's.
Train A of the RVLIS system was modified such that wide range hot leg RTD TE-443A is utilized as the temperature compensation input.
A dedicated wide range hot leg RTD was installed in loop 3 for use as the Train B temperature compensation input.
This modification was described in detail in the Plant Vogtle submittal on NUREG-0737r Item -II.F.2,^ " Instrumentation for Detection of Inadequate Core Cooling."
For additional information, please refer to Appendix 4A of the FSAR.
Georgia Power Company has also modified the core exit thermocouple E0P setpoints to reflect the plant specific core exit thermocouple monitoring system increased inaccuracy during post-accident operation.
With the implementation of the above corrective actions, the issue of increased core exit thermocouple monitoring system post-accident induced errors is resolved on Plant Vogtle.
8612040408 861120 PDR ADOCK 05000424-A PDR l
L____
'f a Page Two This response contains no proprietary information and may be placed in the USNRC Public Document Room.
Yours truly,
>"4 P. D. Rice REF/PDR/tdm xc:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
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