ML20207T423

From kanterella
Jump to navigation Jump to search
Deficiency Rept Re Potential for Hydraulic Pressure in MSIV Actuators to Exceed Design Pressure.Initially Reported on 870123.Util Evaluating Design Mod to Install Pressure Relief Valve on Hydraulic Sys.Final Rept to Be Submitted by 870424
ML20207T423
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/19/1987
From: Rice P
GEORGIA POWER CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
GN-1348, NUDOCS 8703230571
Download: ML20207T423 (2)


Text

'

/

)

b Georgia Ibwer Company Post Offico Box 282 Waynesborn Georgia 30830 Telephone 404 554 9961. Ext:nsion 3413 404 724 8114, Extension 3413 y gg 24 A 7 ; d 9 Georgia Pbwer p, g, VgPr s ent, tre se;orwn vectnc system February 19, 1987 United States Nuclear Regulatory Commission Region.II, Suite 2900 File: X78G03-M138 101 Marietta Street, Northwest Log: GN-1348 Atlanta, Georgia 30323

Reference:

'logtle Electric Generating Plant - Unit 2; 50-425; MSIV Overpressure Attention: Mr. J. Nelson' Grace On January 23, 1987, Mr. C. W. Hayes, Vogtle Quality Assurance Manager, notified tir. E. F. Christnot of the USNRC-Region II of a potentially reportable condition concerning the potential for hydraulic pressure in the MfIV actuators exceeding design pressure.

Rockwell, the valve manufacturer, has indicated that when fully retracted, the MSIV actuator can only accept a 12*F increase in temperature before the hydraulic pressure exceeds the rated operating pressure of the Keane solenoid valves.

Ex:rcising the valve will relieve the overpressure, but when taken to the extreme, assuming a leaktight hydraulic system, this overpressure could prevent the Keane solenoid from operating which would result in a failure of the MSIV to close.

Georgia Power Company is evaluating a design modification to install a pressure relief valve on the hydraulic system to prevent the overpressure condition.

The overpressure condition and the required corrective action are currently being evaluated.

The final report informing the NRC of the evaluation results is scheduled to be sent on or before April 24, 1987.

Unit 1 LER 1-87-002 also addresses this condition.

This response contains no proprietary information and may be placed in the NRC Public Document Room.

I n4 w P. D. Rice M

B703230571 870219 PDR ADOCK 05000425 S

PDR 4

000 TEA 1

. ),'

t o February 19, 1987 File: X78G03-M138 Log:

GN-1348 Page two CWH/PDR/wkl xc:

U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.

20555 H. G. Baker D. R. Altman L. T. Gucwa J. P. O'Reilly J. A. Bailey C. W. Hayes G. F. Head O. Batum G. A. McCarley R. E. Conway G. Bockhold R. W. McManus R. H. Pinson C. E. Belflower Sr. Resident (NRC)

R. M. Guthrie J. F. D'Amico C. C. Garrett (OPC)

R. A. Thomas W. D. Drinkard J. E. Joiner (TSLA)

W. D. Drinkard E. D. Groover D. Feig (GANE)

NORMS t

l l

l l

l

-