ML20066D075
| ML20066D075 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/07/1991 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-91-2001, NUDOCS 9101140107 | |
| Download: ML20066D075 (2) | |
Text
- - -
GPU Nuclear CorporaHon G;
tuclear
- , ors:r388 Forked River, New Jersey 0873bO388 609 97b4000 Writer's Direct Dial Number:
January 7,1991 C321-91-2001 U.
S.
Nuclear Regulatory Commission Att Document Control Desk Washington, DC 20555 Gentlemen Subjects Oyeter Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Technical Specification Change Request No. 196 Supplementary
'Information 24-Month Cycle Surveillance Extensions This letter confirms our discussion on December 31, 1990 between G.
Sadauskas and D. Distel.(GPUN) and C.
Doutt (NRC), regarding additional information to support a 24-month surveillance interval.for the Primary and Safety Valve Position Indicator (Acoustic Monitoring System)-calibration.
Technical Specification Change Request No. 196,-submitted on December 17, 1990, stated that evaluation of the most recent refueling' outage calibration results for the-Acoustic Valve Monitoring System showed no deviations.
This surveillance was conducted on March 15 and 22, 1989.
The Acoustic Valve Monitoring System instrument channels have been-subjected to five (5) previous refueling outage interval calibrations since their installation in 1980.
These additional calibration surveillances were
~
performed in 1981, 1982, 1984, 1996 and;1987.
Each surveillance checks 21 instrument channels of the Acoustic System for the Electromagnetic Relief Valves (EMRV) and the Code Safety Valves.
This calibration data has also been1, evaluated and indicates the following results.
The EMRV's had expe.rter.cwd Ewo I,g (2) channel surveillance failures due to defective cahic api 1cos located in the
~
QQ@
drywell.
The defective cable splice was redesigned and no similar failuren-wuD have been experienced since 1987.
The Code Safety' Valves have experienced 3b four (4) channel surveillance deviations due to degradation of the preamplifier 0"D and the hardline cable, and four'(4) channel surveillance discrepancies due to bM preamplifier bias voltage alarm setpoint drift (diagnostic alarme).
These bo eight (8) deviations for the Code safety Valves were corrected by replacement j{@
of logic modules located in the control room or setpoint adjustments, also made from the control room, or replacement.of hardline cable and preamplifier in the-w 8g drywell.
No other deviations have been indicated by-the refueling outage
,-< O I
Os Q. Q.
GPU Nuclear Corporation is a subsidiary of General Pubke UtAties CCrporation.
lig L$: dol $
',C371-91-2001 Pago 2 i
surveillance channel calibrations from 1981 to 1989.
The Technical Specification required monthly channel check purveillances would also have identified the eight (8) deviations indicatuc' for the Code Safety Valve Acoustic Monitoring System.
The monthly surveillance essentially overlaps the refueling outage surveillance.
In addition, review of the above surveillance data indicates that the accolorometer has not been a contributor to channel failure of the Acoustic Monitoring System.
This information provides additional technical justification that the proposed surveillance interval change from 18-months to 24-months (TSCR No. 196) has no effect on the safety function of the Relief and Safety Valve Position Indicator Accident Monitoring Instrumentation.
Very truly yours, 9
E.
E.
Fitz a rick Vice President and Director Oyster Creek EE7/DJD/ pip ect Administrator, Region 1 NRC Resident Inspector Mr. Alex Dromerick, Jr.
l l
l l
sO" i
W' l
.gm.
C3212001
_ _. _ _. _ _ _ _ _.