05000348/LER-2003-003, From Farley, Unit 1 Regarding Unplanned Auxiliary Feedwater Actuation Upon Trip of Steam Generator Feed Pump
| ML031830331 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/30/2003 |
| From: | Beasley J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-1397 LER 03-003-00 | |
| Download: ML031830331 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 3482003003R00 - NRC Website | |
text
J. Barnie Beasley. Jr., P.E.
Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7110 Fax 205.992.0341 SOUTHERINIAF COMPANY Energy to Serve Your Wo rid June 30, 2003 Docket No.:
50-348 NL-03-1397 U. S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2003-003-00 Unplanned Auxiliary Feedwater Actuation upon Trip of Steam Generator Feed Pump Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant - Licensee Event Report (LER) No. 2003-003-00 is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(A).
There are no NRC commitments in this letter. If you have any questions, please advise.
S'ncerely, B. Beasle
,Jr.
JBB/WAS/sdl
Enclosure:
Licensee Event Report 2003-003-00 cc:
Southern Nuclear Operating Company Mr. J. D. Woodard, Executive Vice President Mr. D. E. Grissette, General Manager - Plant Farley Document Services RTYPE: CFA04.054; LC# 13802 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. F. Rinaldi, NRR Project Manager - Farley Mr. T. P. Johnson, Senior Resident Inspector - Farley
APPROVED BY OMB NO. 3150.0104 EXPIRES 7-31-2004 NRC FORM 366 U.S. NUCLEAR REGULATORY
, the NRC may not conduct or sponsor, and a person is not required to respond to. the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Joseph M. Farley Nuclear Plant - Unit 1 05000348 I
1 OF 3
TITLE (4)
Unplanned Auxiliary Feedwater Actuation upon Trip of Steam Generator Feed Pump EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUBE MO DAY YEAR 05000 05 02 2003 2003 003 00 06 30 2003 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply) (11)
MODE (9) 2 20.2201 (b) 20.2203(aX3Xii) 50.73(a)(2Xii)(B) 50.73(a)(2Xix)(A)
POWER 20.2201(d) 20.2203(a)(4) 50.73(a)(2Xiii) 50.73(aX2)(x)
LEVEL (10) 3 20.2203(a)(1) 50.36(cX1XiXA)
X 50.73(aX2)(ivXA) 73.71(aX4) 20.2203(aX2Xi) 50.36(cX1 XilXA) 50.73(aX2XvXA) 73.71 (aX5) 20.2203(aX2)(ii) 50.c36 2
50.73(aX2XvXB)
OTHER
=
20.2203(aX2)(iii)
=
50.46(aX3Xii) 50.73(aX2XvXC)
Specify in Abstract below or in 20.2203(aX2xiv) 50.73(aX2XiXA) 50.73(aX2XvXD)
(ff more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
Safety Assessment
In neither the May 2 reportable event nor the May 9 subsequent equipment failure did the SGFP exceed its design overspeed trip setpoint of 5775 rpm. In both events, operator action was manually initiated to remove the lB SGFP from service as a conservative response to the loss of speed control.
All safeguards equipment functioned as designed. Therefore, the health and safety of the public were unaffected by this event.
Corrective Action
On May 9, the speed sensing circuit "Tach Pak" was replaced.
Additional Information
Due to its proximity to other SGFP control components, the faulted component was not physically removed from the cabinet during the repair on May 9. The failed component will be removed at the next outage of sufficient duration and the cause of failure investigated by December 17, 2004.
The calibration and maintenance history of the speed sensing circuits on the SGFPs on both units will be reviewed to determine the acceptability of current Periodic Maintenance (PM) practices. Reliability of new and refurbished Tach Paks from available sources will be evaluated. Based on these reviews and investigations, changes to the design, procurement and/or PM programs for this equipment will be made as appropriate. These actions will be complete by December 12,2003.
The following LER has been submitted in the past two years involving SGFP control issues:
LER 2002-004-00 Unit 1, Manual Reactor Trip on Loss of Both Steam Generator Feed Pumps NR CFORM 366A (7-2001)