05000364/LER-2003-001, Regarding Reactor Trip Due to Loss of Power to Reactor Coolant Pump Breaker Position Indication
| ML033580660 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/22/2003 |
| From: | Beasley J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-2581 LER 03-001-00 | |
| Download: ML033580660 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 3642003001R00 - NRC Website | |
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J. Barnie Beasley, Jr., P.E.
Vice President Southern Nuclear Operating Company. Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7110 Fax 205.992.0341 SOUTHERN A COMPANY Energy to Serve Your World' NL-03-2581 December 22, 2003 Docket No.: 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report 2003-001-00 Reactor Trip Due to Loss of Power to Reactor Coolant Pump Breaker Position Indication Ladies and Gentlemen:
Joseph M. Parley Nuclear Plant - Licensee Event Report (LER) No. 2003-001 -00 is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(A).
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, JBB/WAS/sdl Enclosure: Licensee Event Report 2003-001-00 cc:
Southern Nuclear Operating Company Mr. J. D. Woodard, Executive Vice President Mr. D. E. Grissette, General Manager - Plant Farley Document Services RTYPE: CFAO4.054; LC# 13894 U. S. Nuclear Regulatorv Commission Mr. L. A. Reyes, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. T. P. Johnson, Senior Resident Inspector - Farley APPROVED BY 0MB NO. 3150-0104 EXPIRES 7-31-2004 NRC FORM 366 U.S. NUCLEAR REGULATORY Estimated buaden per response to comply with this mandatory nformation collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
(7-2001)
COMMISSION Reported lessons learned are ncorporated Into the licensing process and fed back to ndustry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6). U.S. Nuclear Regulatory Commission. Washington, DC 20555-0001, or by Internet e-mail to bjs1 nrcgov. and to the LICENSEE EVENT REPORT (LER)
Desk Officer. Office of Information end Regulatory Affairs. NEOB-10202 (3150-0104). Office of Management and Budget, Washington, DC 20503. If a means used to Impose information collection (See reverse afr required number of does not display a currently valid OMB control number, the NRC may not conduct or sponsor. and a digits/characters for each block) person is not required to respond to the Information collection.
FACIUTY NAME (1)
DOCKET NUMBER 2)
PAGE (3)
Joseph M. Farley Nuclear Plant - Unit 2 05000 364 1 OF 4
TITLE (4)
Reactor Trip Due to Loss of Power to Reactor Coolant Pump Breaker Position Indication EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REV FACILITY NAME DOCKET NUMBER SEQUENTIAL REV MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 05000 1 1 10 2003 2003 001
- - 00 12 22 2003 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (1)
MODE (9) 1
=
20.2201 (b)
_ 20.2203(a)(3)(ii)
_ 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 100 20.2203(a)(1) 50.36(c)(1)(i)(A)
X 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A)
X 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii)
_ 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or in
=
20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
(If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
Corrective Action
The Unit 2 RCP breaker position reactor trip circuits have been realigned from the inverters to independent dedicated regulated 120 VAC power supplies.
Additional Information
The Unit I RCP breaker position reactor trip circuits will be realigned to the 120 VAC regulated power supplies at the next opportunity.
A Technical Specification change to remove the RCP breaker position trip is being pursued. This trip function is anticipatory and is not required by accident analysis. Appropriate design change packages to remove this function will be prepared and implemented following approval of the Technical Specification change.
The following information, although not believed to represent a direct cause of the event, is related to the function of the inverters:
A 10CFR21 report filed by Ametek Solidstate Controls Inc., dated January 26, 2000, identified that a static switch board contained a "UJT 1" transistor of a type which can initiate spurious transfer of the inverter to bypass mode.
Farley was not identified as an affected plant by the report. The spurious initiation of transfer to bypass does not affect the time required to complete the transfer to bypass mode and therefore is not the cause of the event reported in this LER. Prior to this event, FNP had planned inspections and repairs related to the "UJTI" issue for the next refueling outage.
The following LER has been submitted in the past two years concerning a reactor trip associated with loss of vital instrument power:
LER 2002-001-00 Unit 1, Reactor Trip Due to Inadvertent Electrical Contact During Recorder Maintenance.