05000278/LER-2015-001, Regarding Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter
| ML16057A011 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/26/2016 |
| From: | Pat Navin Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 15-001-00 | |
| Download: ML16057A011 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 2782015001R00 - NRC Website | |
text
Exelon Generation ~,
February 26, 2016 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001
Subject:
Peach Bottom Atomic Power Station (PBAPS) Unit 3 Renewed Facility Operating License No. DPR-56 NRC Docket No. 50-278 Licensee Event Report (LER) 3-15-001 10CFR 50.73 Enclosed is a Licensee Event Report concerning a loss of function of the High Pressure Coolant Injection System due to a failed signal converter associated with the system's flow controller.
In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that have been planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact us.
Sincef#-!J ~
Patrick D. Navin Plant Manager Peach Bottom Atomic Power Station PDN/dnd/IR 2606215 Attachment cc:
US NRC, Administrator, Region I US NRC, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-owner Affairs CCN: 16-17
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
(~) LICENSEE EVENT REPORT (LER)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Peach Bottom Atomic Power Station, Unit 3 05000278 1 OF 3
- 4. TITLE Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 12 31 2015 2015 - 001 0
02 26 2016
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201(bl D 20.2203(a)(3)(il 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 1 D 20.2201(ctl D 20.2203(a)(3)(iil 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
D 20.2203(a)(1 l D 20.2203(a)(4l D 50.13(a)(2)(iiil 0 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(il 0 50.36(c)(1 )(i)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(iil 0 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4l D 20.2203(a)(2)(iiil D 5o.3e(c)(2)
D 50.73(a)(2)(v)(B)
D 13.11(a)(5l D 20.2203(a)(2)(iv)
D 5o.4e(a)(3)(iil D 50.73(a)(2)(v)(C)
D 13.11(a)(1) 100%
0 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
~ 50.73(a)(2)(v)(D)
D 73.77(a)(2)(il 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii)
D 73.77(a)(2)(iil D so.73(a)(2)(i)(C)
~ OTHER Specify in Abstract below or in responded to a design basis event to maintain the plant in a safe condition. The Reactor Core Isolation Cooling (RCIC) system (EllS: BN) was also operable during this time period. This event is not considered to be risk significant. There were no actual safety consequences associated with this event.
This event is being reported in accordance with 10CFR 50.73(a)(2)(v)(D), as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. This LER also satisfies the reporting obligations of 1 OCFR Part 21, as stated in 10CFR 21.2(c).
Cause of the Event
Troubleshooting of the HPCI system determined that a signal converter in the HPCI control circuitry had failed. The signal converter converts the HPCI Flow Controller 4-20 mA output to a 10-50 mA signal that is required by the HPCI Electronic Governor Module.
The signal converter is manufactured by Moore Industries, Model #SCT/4-20MA/10-50MA and supplied by Nutherm International. The signal converter had been installed and tested in October 2015 during the recent refueling outage.
Following its failure on 12/31/15, it was sent off site for failure analysis. A failed transistor in the signal converter was identified. When replaced with a new transistor, the new transistor also failed during functional tests, suggesting it was the result of another sub-component within the signal converter.
Additional testing and analysis could not determine what other sub-component had failed.
Corrective Actions
The signal converter was replaced. HPCI was satisfactorily tested and returned to an operable status on 12/31/15 at approximately 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />.
The failure has been classified as a latent manufacturing issue resulting in an infant mortality of the device.
Similar installed equipment has been in operation for a period of time adequate for identifying this type of failure. The replacement signal converter has been in-service since 12/31/15 with satisfactory performance. Additional corrective actions are being evaluated in accordance with the corrective action program.
Previous Similar Occurrences LERs 3-04-001 and 3-05-001 both reported a failure of a HPCI flow controller due to failure of an internal power supply. The corrective actions taken for the previous events would not have been expected to prevent this recent event.
Unit Conditions Prior to the Event Unit 3 was in Mode 1 and operating at approximately 100% rated thermal power when the event occurred. There were no structures, systems or components out of service that contributed to this event.
Description of the Event On 12/31/15, at approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, during shift turnover panel walk-downs, a licensed operator identified that the High Pressure Coolant Injection (HPCI) (EllS:BJ) flow controller (EllS:FIC) output indication was showing zero percent. The controller was in automatic with the set point at 5000 gpm, which would typically result in a controller output value of 100%. This condition would have prevented the HPCI system from performing its design function in the event of an accident. The HPCI system was declared inoperable and the appropriate Technical Specification Action was entered. Other standby systems (Reactor Core Isolation Cooling and low pressure emergency core cooling systems) remained operable.
This condition was reported to the NRC on 12/31/15 at approximately 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br /> pursuant to the requirements of 10CFR 50.72(b)(3)(v)(D) (Event Notification 51630).
Subsequent troubleshooting of the HPCI system determined that a signal converter in the HPCI control circuitry had failed, resulting in the HPCI system not being capable of providing a sufficient flow rate if it had been required for a design basis event. The signal converter was replaced. HPCI was satisfactorily tested and returned to an operable status on 12/31 /15 at approximately 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />. The elapsed time from discovery to the time when the system was returned to service was approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and 40 minutes.
Analysis of the Event
The HPCI system is part of the Emergency Core Cooling System (ECCS) network that provides cooling water to the reactor vessel for certain design basis events. The HPCI system uses a turbine driven pump that is designed to provide core cooling for a wide range of reactor pressures. As a result of this failure, upon receipt of an initiation signal, the HPCI turbine would have started, but the flow controller would have provided a flow demand of 0%. This would cause the governor control valve to close, stopping the turbine shortly after receiving the initiation signal.
A documented walk down of this panel on 12/30/15 at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> shows that the flow controller indicated 100% at that time. In addition, the operator also observed the controller at 100% at approximately 0400 on 12/31/15. It was observed during shift turnover walk downs at approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> to be at 0%. Therefore, the duration of inoperability prior to discovering the condition was at most approximately 2-1/2 hours. During the inoperability time period, other core cooling systems (Automatic Depressurization System (ADS) {EllS: RV), Core Spray (EllS: BM) and Low Pressure Coolant Injection (EllS: BO)) were operable and could have adequately responded to a design basis event to maintain the plant in a safe condition. The Reactor Core Isolation Cooling (RCIC) system (EllS: BN) was also operable during this time period. This event is not considered to be risk significant. There were no actual safety consequences associated with this event.
This event is being reported in accordance with 10CFR 50.73(a)(2)(v)(D), as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. This LER also satisfies the reporting obligations of 1 OCFR Part 21, as stated in 10CFR 21.2(c).
Cause of the Event
Troubleshooting of the HPCI system determined that a signal converter in the HPCI control circuitry had failed. The signal converter converts the HPCI Flow Controller 4-20 mA output to a 10-50 mA signal that is required by the HPCI Electronic Governor Module.
The signal converter is manufactured by Moore Industries, Model #SCT/4-20MA/10-50MA and supplied by Nutherm International. The signal converter had been installed and tested in October 2015 during the recent refueling outage.
Following its failure on 12/31/15, it was sent off site for failure analysis. A failed transistor in the signal converter was identified. When replaced with a new transistor, the new transistor also failed during functional tests, suggesting it was the result of another sub-component within the signal converter.
Additional testing and analysis could not determine what other sub-component had failed.
Corrective Actions
The signal converter was replaced. HPCI was satisfactorily tested and returned to an operable status on 12/31/15 at approximately 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />.
The failure has been classified as a latent manufacturing issue resulting in an infant mortality of the device.
Similar installed equipment has been in operation for a period of time adequate for identifying this type of failure. The replacement signal converter has been in-service since 12/31/15 with satisfactory performance. Additional corrective actions are being evaluated in accordance with the corrective action program.
Previous Similar Occurrences LERs 3-04-001 and 3-05-001 both reported a failure of a HPCI flow controller due to failure of an internal power supply. The corrective actions taken for the previous events would not have been expected to prevent this recent event. 0