LER-2014-001, Regarding Beaver Valley Unit 1 Automatic Reactor Trip Due to Main Unit Transformer Failure |
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| Report date: |
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| 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)(iii)
10 CFR 50.73(a)(2)(ix)(A)
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 |
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| 3342014001R00 - NRC Website |
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text
" FENOC"~
Beaver Valley Power Station P.O. Box 4 ft*
Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 March 7, 2014 L-14-108 10 CFR 50.73 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 2014-001-00 Enclosed is Licensee Event Report (LER) 2014-001-00, "Beaver Valley Unit 1 Reactor Trip due to Main Unit Transformer Failure." This event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A).
There are no regulatory commitments contained in this submittal. Any actions discussed in this document that represent intended or planned actions are described for the NRC's information, and are not regulatory commitments.
If there are any questions or if additional information is required, please contact Mr. Brian F. Sepelak, Supervisor, Regulatory Compliance at 724-682-4282.
Sincerely, Eric A. Larson Enclosure - LER 2014-001-00 cc:
Mr. W. M. Dean, NRC Region I Administrator Mr. J. H. Nadel, NRC Acting Resident Inspector Mr. J. A. Whited, NRR Project Manager INPO Records Center (via INPO Consolidated Event System)
Mr. L. E. Ryan (BRP/DEP)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 01/31/2017 (01-2014)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
T
- 3. PAGE Beaver Valley Power Station Unit Number 1 05000334I 1 OF 3
- 4. TITLE Beaver Valley Unit 1 Automatic Reactor Trip due to Main Unit Transformer Failure
- 6. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED R
SEQUENTIAL IREVY NA DOCKETNUMBER MONTH DAY YEAR YEAMONR NO ONTH DAY YEAR None
_ _I IFA CIFACNTYMNAME DOCKET NUMBER 01 06 2014 2014 - 001 - 00 03 07 2014 None
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
[3 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
Mode 1 [Z 20.2201(d).
EZ 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[] 50.73(a)(2)(viii)(A)
[] 20.2203(a)(1)
Z 20.2203(a)(4)
ED 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
LI 50.36(c)(1)(i)(A)
[L 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [j 20.2203(a)(2)(ii)
LI 50.36(c)(1)(ii)(A)
E 50.73(a)(2)(iv)(A)
E] 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
LI 50.36(c)(2)
[1 50.73(a)(2)(v)(A)
[L 73.71 (a)(4) 100 20.2203(a)(2)(iv)
LI 50.46(a)(3)(ii)
LI 50.73(a)(2)(v)(B)
El] 73.71(a)(5)
El 20.2203(a)(2)(v)
LI 50.73(a)(2)(i)(A)
LI 50.73(a)(2)(v)(C)
.I OTHER Specify in Abstract below or in NRC
__ 20.2203(a)(2)(vi)
[I 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
The plant risk associated with the BVPS Unit 1 automatic reactor trip and an Auxiliary Feedwater actuation, on January 6, 2014, due to a main unit transformer differential trip is considered to be very low.
This is based on the conditional core damage probability and conditional large early release probability for the event when considering the actual plant conditions that were present at the time of the event.
Based on the above, the safety Significance of the automatic reactor trip and Auxiliary Feedwater actuation event on January 6, 2014, was very low.
CORRECTIVE ACTIONS
- 1. Replacement of the Main Unit Transformer.
(Complete)
- 2. Establish a sequence of operation, for both Units' transformers, that minimizes the potential for static electrification.
- 3. Evaluate training for the appropriate departments on lessons learned from this event.
Completion of the above and other corrective actions is being tracked through the BVPS Corrective Action Program.
PREVIOUS SIMILAR EVENTS
A review identified the following historical BVPS Unit 1 events involving a failure of the main unit transformer.
BVPS LER 94-005 Main Transformer Bushing Failure Results In Electrical Grid Disturbance and Dual Unit Reactor Trip.
BVPS LER 78-043 Main Transformer Failure and Inadvertent SI CR 2014-00175
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| 05000412/LER-2014-001, Regarding Unacceptable Indication Identified During Reactor Vessel Head Inspection | Regarding Unacceptable Indication Identified During Reactor Vessel Head Inspection | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000334/LER-2014-001, Regarding Beaver Valley Unit 1 Automatic Reactor Trip Due to Main Unit Transformer Failure | Regarding Beaver Valley Unit 1 Automatic Reactor Trip Due to Main Unit Transformer Failure | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000412/LER-2014-002, Unit Number 2 Regarding Manual Reactor Trip Due to High Steam Generator Water Level During Plant Startup | Unit Number 2 Regarding Manual Reactor Trip Due to High Steam Generator Water Level During Plant Startup | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000334/LER-2014-002, Regarding Turbine Driven Auxiliary Feedwater Pump Governor Oscillations Result in Pump Trip | Regarding Turbine Driven Auxiliary Feedwater Pump Governor Oscillations Result in Pump Trip | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000334/LER-2014-003, Regarding Operation Outside of the Pressure and Temperature Limits Report During Isolated RCS Loop Vacuum Fill | Regarding Operation Outside of the Pressure and Temperature Limits Report During Isolated RCS Loop Vacuum Fill | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000334/LER-2014-004, Unit Number 1 Regarding Unanalyzed Condition Resulting from Unfused Direct Current Control Circuits | Unit Number 1 Regarding Unanalyzed Condition Resulting from Unfused Direct Current Control Circuits | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000412/LER-2014-006, Re Unplanned Automatic Actuation of Both Standby Service Water Pumps | Re Unplanned Automatic Actuation of Both Standby Service Water Pumps | 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iv)(B)(9) |
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