ML20217E262
| ML20217E262 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/24/1998 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.108, RTR-REGGD-1.108 NUDOCS 9803300428 | |
| Download: ML20217E262 (5) | |
Text
'l 0:ve Morey Southern Nuclear Vice Presidst Operating Company a
Farley Project P.O. Box 1295 Birmingham. Alabama 35201 l
Tel 205.992.5131 i
1 SOUTHERN h March 24,1998 COMFANY Energy to ServeYourWorld" Docket Nos.: 50-348 10 CFR 50.36 50-364 U.S. Nuclear Regulatory Commission
' ATfN: Document Control Desk Washington,DC 20555 Joseph M. Farley Nuclear Plant 1997 Annual Diesel Generator Reliability Data Report Ladies and Gentlemen: provides the Annual Diesel Generator (D/G) Reliability Data Report for 1997, which is submitted in accordance with Farley Nuclear Plant (FNP) Technical Specification 6.9.1.12.. This report provides the number of tests (valid or invalid) and the number of failures for the D/Gs at FNP for 1997. Attachment 2 provides the information identified in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977, for the failures.
If there are any questions, please advise.
Respectfully submitted, f
llyw Dave Morey EWC/ cit:dg-ar-97. doc Attachments:
- 1. 1997 Annual Diesel Generator Reliability Data Report
- 2. Information Identified in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977
. cc:. Mr. L. A. Reyes, Region II Administrator
- Mr. J. I. Zimmerman, NRR Project Manager f
N_.
L Mr. T. M. Ross, Plant Sr. Resident Inspector
-Q.I 9803300428 980324 PDR-ADOCK 05000348,'
R PDR
]
I ATTACIIMENT 1 ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT FOR 1997 i
' ATTACilMENT I ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT FOR 1997 M 6hW M WR: M i'5 " ? Q b; NA?%mQ MA) i M ?l W M bl e m awar?KI?!B 7%?166%W
's Valid Successful Tests 17 16 18 29-80 Invalid Tests 20 12 6
15 53 Valid Failures 1
0 0
0 1
Invalid Failures 0
0 0
0 0
i i
-)
- 6. -.
A1:1of1-
l e
1 ATTACIIMENT 2 INFORMATION IDENTIFIED IN REGULATORY POSITION C.3.b OF REGULATORY GUIDE 1.108, REVISION 1, AUGUST 1977 i
l i
1
A'ITACi! MENT 2 INFORMATION IDENTIFIED IN REGULATORY POSITION C.3.b OF REGULATORY GUIDE 1.108, REVISION 1, AUGUST 1977 The surveillance testing frequencies of the Technical Specifications diesel generators 1-2A,1B,2B and IC are scheduled in accordance with the Technical Specifications,4.8-1," Diesel Generator Test Schedule." Note that this table deviates from the test schedule contained in Regulatory Position C.2.d in Regulatory Guide 1.108, Revision 1, August 1977, 1-2A D/G Failure on 11-02-97 At 0641 on I l-02-97, while performing FNP-0-STP-80.1," Diesel Generator 1-2A Operability Test,"
the 1-2A D/G was secured aller the unit I output breaker QlR15BKRDF08 would not close.
During perfonnance of the test, the breaker would not close from the Emergency Power Board in the control room. During initial tro' bleshooting, an attempt to close the breaker was made with u
electricians at the breaker cubicle. Again, the breaker failed to close and the electricians did not hear the control circuit relay (52X) energizing, which indicated a problem with the breaker control circuit.
In addition, when the breaker was racked out for further troubleshooting, the springs did not automatically discharge as expected.
The breaker was removed and cycled successfully several times with a test set. Further inspection revealed the breaker close linkage was slightly out of adjustment. The breaker manufacturer concluded that the misadjustment was the cause of the breaker springs not discharging when racked
. out and possibly could have prevented the breaker from closing.
i The failure of personnel to hear the 52X relay energizing during initial troubleshooting indicated the breaker was not receiving a close signal. Ilowever, subsequent investigation of the breaker control circuit did not identify a problem anywhere in the control circuit. It was concluded that during initial troubleshooting, the diesel was placed in a mode in which it would not autostart and this manipulation possibly corrected the control circuit malfunction thus eliminating any evidence of the failure mechanism.
It was concluded that the probable root cause of the breaker not closing was the breaker not receiving a close signal due to a control circuit malfunction. For future failures a troubleshooting plan to identify the cause prior to control circuit manipulation has been developed to be utilized should this problem recur.
Another breaker was placed in cubicle DF08-1 and the diesel successfully completed a return-to-a service surveillance and was restored to operable status. The 1-2A D/G was unavailable for 9.2 hrs as a result of this failure. This failure was the first failure in the last 100 valid tests and the first failure in the last 20 valid tests.
After this failure, the surveillance schedule remained at once per thirty-one days, which is in conformance with the Technical Specifications, Table 4.8-1," Diesel Generator Test Schedule."
l A2: 1 of I