05000334/LER-2015-001, Regarding Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation Due to Condensate Pump Motor Failure
| ML15166A088 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/11/2015 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-15-189 LER 15-001-00 | |
| Download: ML15166A088 (4) | |
| 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)(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 10 CFR 50.73(a)(2)(iv)(B)(1) 10 CFR 50.73(a)(2)(iv)(B)(6) |
| 3342015001R00 - NRC Website | |
text
FENOC" Beaver Valley Power Station
-"-.%P.O.
Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 June 11, 2015 L-15-189 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 2015-001-00 Enclosed is Licensee Event Report (LER) 2015-001-00, "Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation due to Condensate Pump Motor 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. William C. Cothen, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, Eric A. Larson Enclosure - LER 2015-001-00 cc:
Mr. D. H. Dorman, NRC Region I Administrator Mr. J. A. Krafty, NRC Resident Inspector Ms. T. A. Lamb, NRR Project Manager INPO Records Center (via INPO Consolidated Event System)
Mr. L. J. Winker (BRP/DEP)
Ci2
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 01/31/2017 (02-2014)
, the NRC may not conduct or
_asponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Beaver Valley Power Station Unit Number 1 05000334 1 OF 3
- 4. TITLE Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation due to Condensate Pump Motor Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEUNUMBAL REV MONTH DAY YEAR N
AME NOUDAYRYEAR None FACILITY NAME DOCKET NUMBER 04 15 2015 2015 - 001 - 00 06 11 2015 None
- 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)
EZ 50.73(a)(2)(vii)
Mode 1 E 20.2201(d)
EZ 20.2203(a)(3)(ii)
[: 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)
[L 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
[] 50.73(a)(2)(iii)
[El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[] 20.2203(a)(2)(ii)
[_ 50.36(c)(1)(ii)(A)
Z 50.73(a)(2)(iv)(A)
LI 50.73(a)(2)(x)
EI 20.2203(a)(2)(iii)
[] 50.36(c)(2)
[L 50.73(a)(2)(v)(A)
LI 73.71(a)(4) 085 LI 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
LI 73.71(a)(5)
LI 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[L 50.73(a)(2)(v)(C)
LI OTHER Specify in Abstract below or in NRC
_El 20.2203(a)(2)(vi) 0I 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
ANALYSIS OF EVENT
The plant risk associated with the BVPS Unit 1 manual reactor trip and auxiliary feedwater actuation system on April 15, 2015, due to the "A" Condensate Pump trip is considered to be very low. This is based on the change in average core damage frequency derived using the conditional core damage probability, and change in average large early release frequency derived using the conditional large early release probability for the event. Based on the above, the safety significance of the manual reactor trip and auxiliary feedwater actuation event on April 15, 2015, was very low.
The condensate system is not credited to mitigate the consequences of an accident described in the BVPS Updated Final Safety Analysis Report. The condensate system cannot compromise the availability of safety-related equipment.
This event was reported on 4/15/2015, at 0732 EDT, EN 50985, as an event or condition that results in the actuation of the Reactor Protection System (RPS) when the reactor is critical, 10 CFR 50.72(b)(2)(iv)(B) and specified system actuation, 10 CFR 50.72(b)(2)(iv)(A). This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) as a condition that resulted in the manual actuation of the Reactor Protection System (RPS) 10 CFR 50.73(a)(2)(iv)(B)(1), and the automatic actuation of the auxiliary feedwater system 10 CFR 50.73(a)(2)(iv)(B)(6).
CORRECTIVE ACTIONS
- 1. Replacement of the condensate pump motor. (Complete)
- 2. Perform a review to ensure that all 4KV and single point vulnerability motors have the proper formal technical requirement for bearing reservoir oil level.
- 3. Evaluate training for the appropriate departments on the lessons learned from this event.
Completion of the above and other corrective actions are being tracked through the BVPS Corrective Action Program.
PREVIOUS SIMILAR EVENTS
A review of the previous three years has found that there were no similar events involving a reactor trip due to the failure of a large motor.
CR-2015-05256, 05262