05000316/LER-2012-002, Regarding Unit 2 Reactor Trip from Generator Trip Due to Incorrect Relay Setting
| ML12193A088 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/26/2012 |
| From: | Gebbie J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2012-45 LER 12-002-00 | |
| Download: ML12193A088 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3162012002R00 - NRC Website | |
text
INDIANA MICHIGAN POWER A unit of American Electric Power Indiana Michigan Power One Cook Place Bridgman, MI 49106 Indiana Michigan Power.com AEP-NRC-2012-45 10 CFR 50.73 June 26, 2012 Docket No. 50-316 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 LICENSEE EVENT REPORT 316/2012-002-00 UNIT 2 REACTOR TRIP FROM GENERATOR TRIP DUE TO INCORRECT RELAY SETTING In accordance with the criteria established by 10 CFR 50.73, Licensee Event Report System, the following report is being submitted:
LER 316/2012-002-00: "Unit 2 Reactor Trip From Generator Trip Due to Incorrect Relay Setting" There are no commitments contained in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President SJM/kmh Enclosure c:
LERevents@lNPO.org (e-mail only)
C. A. Casto - NRC Region III J. T. King - MPSC, w/o enclosure S. M. Krawec - AEP Ft. Wayne, w/o enclosure MDEQ - RMD/RPS, w/o enclosure NRC Resident Inspector P. S. Tam - NRC Washington DC ptLA
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB:
NO. 3150-0104 EXPIRES 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Donald C. Cook Nuclear Plant Unit 2 05000-316 1 of 3
- 4. TITLE Unit 2 Reactor Trip from Generator Trip Due to Incorrect Relay Setting
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEDENIA RVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 04 30 2012 2012 002 00 06 26 2012 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
E]
50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
E]
50.36(c)(1)(ii)(A)
E 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
E]
50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4) 91 El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
H 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
OTHER Specify in Abstract below El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D) or in
Analysis of Event
The event, is not considered to be risk significant as there were no risk significant equipment failures to pose elevated risk. It is recognized that there was an actuation of a main generator protective circuit and all systems responded as designed.
Based on review of the control room logs and the post-trip review, all plant systems performed as designed to shut down the unit and remove decay heat. No risk-significant equipment functions were affected or failed and no significant operator actions outside those required for normal trips were required.
Corrective Actions
Completed Corrective Actions The overall differential relay setting changes were implemented and monitored during the restart evolution as load was increased to 100%.
Planned Corrective Actions
Planning and modification procedures will be revised to address task verification of modification implementation.
Previous Similar Events
LERs for CNP Unit 1 and Unit 2 for the past three years were reviewed for similar events. The following was identified:
05000315-2011-001-00, Unit 1 Reactor Trip Due To Main Turbine Trip On September 07, 2011, at 0854 hours0.00988 days <br />0.237 hours <br />0.00141 weeks <br />3.24947e-4 months <br />, Donald C. Cook Nuclear Plant (CNP) Unit 1 Reactor tripped automatically due to a trip of the main turbine. All control rods fully inserted and the auxiliary feedwater system (AFW) started and performed as designed.
The cause of the event above, Unit 1 Main Turbine trip, was an incorrectly installed thrust probe, which was due to an over reliance on field engineering guidance for maintenance activities in lieu of detailed planning instruction. Corrective actions included revising project guidance to improve the quality of work order instructions.
The cause of the event, for this LER, was that the modification process did not require a formal verification of activities required to implement the modification.
The causes are different in each event and the corrective actions taken in the prior event would not have precluded this event.
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