05000424/LER-2012-002, Regarding Manual Reactor Trip Due to Circuit Board Failure
| ML12163A244 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/05/2012 |
| From: | Tynan T Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-12-1109 LER 12-002-00 | |
| Download: ML12163A244 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(8) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(8) 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 4242012002R00 - NRC Website | |
text
Southern Nuclear Operating Company. Inc.
Vogtle Electric Generating Plant 7821 River Road Waynesboro. Georgia 30B30 Tel 706.724.1562 or 706.554.9961 June 5, 2012 SOUTHERN COMPANY Docket Nos.:
50-424 NL~12-1109 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Unit 1 Licensee Event Report 2012-002-00 Manual Reactor Trip Due to Circuit Board Failure Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73(a)(2)(iv)(A), Southern Nuclear Operating Company hereby submits the enclosed Licensee Event Report concerning an event of the unplanned manual actuation of the Reactor Protection System and the automatic actuation of the Auxiliary Feedwater System following the failure of a circuit board in the feedwater control system.
This letter contains no NRC commitments. If you have any questions, please contact Mr. B. D. McKinney at (205) 992-5982.
Respectfully submitted, T. E. Tynan Vice President - Vogtle TETIWEB Enclosure: LER 1-2012-002, Revision 0 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President &Chief Nuclear Officer Mr. B. L Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations Mr. A. J. Ajluni, Nuclear Licensing Director RType: CVC7000
U. S. Nuclear Regulatory Commission I\\JL-12-1109 Page 2 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. P. G. Boyle, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle
Enclosure NL-12-1109 Vogtle Electric Generating Plant - Unit 1 Licensee Event Report 1-2012-002-00 Manual Reactor Trip Due to Circuit Board Failure
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150'()1 04 EXPIRES: 1013112013 (1(J.2010l Esllmated burden per response to comply with this mandatory coltecUon request: eo hours. Reported lessons leamed are Incorporated Into the licenslng process and fed back 10 Indust~ Send comments regarding burden estimate to the FOlAlPrivacy Section ( *5 F53l, U.S. Nuclear Regulatory LICENSEE EVENT REPORT (LER)
Commission. Washington, DC 20555-0001, or by Inlemet e-maH to Infocollects.resourceonrc'go\\l, and to the Desk Officer, Olfloe of Information and Regulatory Affairs, NE 6*10202, (3150-0104), Office of Management and 6udget. Washington. DC 20503. If a means used to impose an information colleCtIon does not display acurrently valid OM6 control number. the NRC may not conduct or sponsor, and iii person Is not required to respond to, the Information colleclion.
- 13. PAGE 1 Vogtle Electric Generating Plant-Unit 1 05000424 OF 3
~. nTLE Manual Reactor Trip Due to Circuit Board Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEOUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACIl.1TY NAME DOCKET NUMBER 05000 FAC1UTY NAME OOCKET NUMBER 04 14 2012 2012
- 002 -
00 06 13 2012 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201 (b) o 20.2203(a){3)(i) o 5O.73(a)(2)(I)(C) o 50.73(a)(2)(vil) 1 o 20.2201 (d) o 20.2203(a)(3)(ii) o 5O.73(a)(2)(II)(A) o 50.73(a)(2)(viil)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(8) o 20.2203(a)(2)(0 o 5O.36(c)(1)(i)(A) o 50.73(a)(2)(III) o 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(1I) o 50.36(o)(1)(ii)(A) t8I 50.73(a)(2)(Iv)(A) o 50.73(a)(2){x) o 20.2203(a)(2)(1II) o 50.36(0)(2) o 50.73(a)(2)(v)(A) o 73.71(a){4) o 20.2203(a)(2)(iv) o 50.46(a)(3)(10 o 50.73(a)(2)(v)(8) o 73.71(a)(5) 100 o 20.2203(a)(2)(v) o 5O.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vl) o 50.73(a)(2)(I)(8) o 5O.73(a)(2)(v)(O)
Specify In Abstract below or in inventory is not relieved from the pressurizer relief or safety valves. Based upon these considerations, there was no adverse effect on plant safety or on the health and safety of the public as a result of this event.
F. CORRECTIVE ACTION
The prompt corrective action was to replace the subject "Position 5" circuit board. In addition, the failure of the circuit board was entered into the Corrective Action Program in order to track a longer term solution.
G. ADDITIONAL INFORMATION
- 1) Failed Components:
Component: MDT-20 Control System Manufacturer: GE
- 2) Previous Similar Events:
A review of Licensee Event Reports for the past three years did not identify another instance in which there was a manual reactor trip following the loss of feedwater pump at VogUe Electric Generating Plant due to a failure of a circuit board in the feedwater control system.
- 3) Energy Industry Identification System Code:
Plant Protection System - JC Solid State Protection System - JG Auxiliary Feedwater System - BA Feedwater System - SJ
- 4) Commitment Information:
This report does not create any new permanent licensing commitments.