05000348/LER-2012-004, Regarding Unplanned B Train LOSP During Switchyard Breaker Testing
| ML12152A375 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/31/2012 |
| From: | Lynch T Southern Nuclear Operating Co, Southern Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-12-0906 LER 12-004-00 | |
| Download: ML12152A375 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) |
| 3482012004R00 - NRC Website | |
text
Thomas A. Lynch Southern Nuclear Vice President* Farley Operating Company, Inc.
Farley Nuclear Plant Post Office 0rawer 470 Ashford. Alabama 36312 Tel 334.814.4511 Fax 334.814.4728 SOUTHERN'\\'
COMPANY May31,2012 Docket No.:
50-348 NL-12-0906 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2012-004-00 Unplanned B Train LOSP during Switchyard Breaker Testing Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73 (a)(2)(iv)(A), Southern Nuclear Operating Company (SNC) is submitting the enclosed Licensee Event Report. This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Sincerely.
T. A. Lynch Vice President - Farley TALlWDO Enclosure: Unit 1 Licensee Event Report 2012-004-00
U. S. Nuclear Regulatory Commission NL-12-0906 Page 2 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. M. J. Ajluni, Director - Nuclear Licensing RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2012-004-00 Unplanned B Train LOSP during Switchyard Breaker Testing Enclosure Unit 1 Licensee Event Report 2012-004-00
!NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (1(1-2010)
Estimated burden per response to comply with this mandatory collection request: BO hours. Reported lessons leamed are incorporated into the licensing process and led back to rndUSI(f Send comments regarding burden estimate to !he FOIAlPrivaCb Seelion
- 5 F53), U.S. Nuclear Regulatory LICENSEE EVENT REPORT (LER)
Commission, Washington, C 20555*0001, or by Inlernel e-mail to infocouects.resource@nrc'g:, and to the Desk Officer, Office of Information and Regulatory Affairs, NE 6-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a curren6y valid OMS control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000348 1 OF 4
- 14. TITLE Unplanned B Train LOSP during Switchyard Breaker Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY I YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACllfTY NAME DOCKET NUMBER FACIUTY NAME DOCKET NUMBER 04 I 06 12012 2012 - 004 -
00 05 31 2012
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) 6 o 20.2201 (d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1)(i)(A) o 50.73(a)(2)(lil) o 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(ii) o 5O.36(c)(1 )(ii)(A) 181 5O.73(a)(2)(lv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) o 5O.36(c)(2) o 50.73(a}(2)(v)(A) o 73.71(a)(4) o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71 (a)(5) 000 o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(1)(8) o 50.73(a)(2)(v)(O)
Specify in Abstract belOW or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER
--~-"..
FACILITY NAME ITElEPHONE NUMBER (Include Alea COOe)
J.M. Farley Nuclear Plant, W. D. Oldfield - Principal Licensing Engineer (334) 814-4765 MANU*
REPORTABLE MANU*
REPORTABLE I
CAUSE
SYSTEM COMPONENT
CAUSE
SYSTEM COMPONENT FACTURER
_.~O>_~
I I
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 181 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On April 6, 2012 at approximately 14:44, with Unit 1 in mode 6, an unplanned loss of power on B-train 4160 volt emergency bus 1 G occurred during scheduled high voltage switchyard breaker testing activities. The 1 G bus was powered from the 1 B startup transformer (SUT) that lost power when power circuit breaker (PCB) 820 unexpectedly opened. A second PCB, 924, to the 1 B SUT was out of service for breaker testing. During that fault circuitry testing, an unanticipated trip of the adjacent PCB 820 occurred due to an inadequate test procedure, When power was lost to the 1 B SUT an undervoltage condition was sensed on the 1G bus and the B1G Sequencer caused the DG-15 feeder breaker to open and initiated a load shed on the 1 G bus. Due to B-train outage conditions, the 1 B Emergency Diesel Generator (EDG) was tagged out and did not automatically start and therefore no Loss of Offsite Power (LOSP) loads started. All systems functioned as designed for this condition.
Since core cooling was aligned to the A-train prior to the event, the A-train, 1 A Residual Heat Removal (RHR) pump remained in service for shutdown cooling. Unit 2 was unaffected and remained at 100 percent power during the event.
The 1 G bus was restored to service on April 6, 2012 at 15:42. Investigation revealed that the test procedure did not contain a step to isolate one of the fault protection relay schemes for PCB 820. The test procedure was corrected and the test was successfully completed on April 7, 2012.
NRC FORM 366 (10*2010)
4
Additional Information
Similar Events:
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