05000387/LER-2015-013, Regarding Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure

From kanterella
(Redirected from 05000387/LER-2015-013)
Jump to navigation Jump to search
Regarding Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure
ML16034A124
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 02/02/2016
From: Franke J
Susquehanna, Talen Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7437 LER 15-013-00
Download: ML16034A124 (5)
v • d • e


LER-2015-013, Regarding Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3872015013R00 - NRC Website
v • d • e

text

~EB 0 2 Z016 Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon.Franke@TalenEnergy.com U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2015-013-00 UNIT 1 LICENSE NO. NPF-14 PLA-7437 TALEN ~

ENERGY 10 CFR 50.73 Docket No. 50-387 Attached is Licensee Event Report (LER) 50-387/2015-013-00. This LER reports an event involving Secondary Containment being declared Inoperable due to loss of differential pressure. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as a condition which at the time of discovery could have prevented fulfilment of a safety function.

There were no actual consequences to the health and safety of the public as a result of this event.

no new regulatory commitments.

. A. Franke.

Attachment: LER 50-387/2015-013-00 Copy:

NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

2. DOCKET NUMBER YEAR 05000387 2015
3. LER NUMBER I

SEQUENTIAL NUMBER

- 013 I

REV NO.

- 00 The actual consequence was a brief entry into LCO 3.6.4.1 and an eight hour notification of the event to the Nuclear Regulatory Commission (NRC).

An engineering evaluation was performed and concluded that secondary containment could have performed its safety function of isolating and remaining leak tight as assumed in the accident analysis. Therefore, this event did not result in a loss of safety function. This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the engineering analysis that shows there was no loss of ability to fulfill the safety function.

CORRECTIVE ACTIONS

COMPLETED

  • The failed solenoid valve was examined and tested by station personnel
  • The failed solenoid valve was sent to Exelon Labs for failure analysis PLANNED
  • Results from the failure analysis will be reviewed
  • Corrective actions will be generated to address any issues identified from the review COMPONENT INFORMATION The failed solenoid is internally referenced as SV17521A, Reactor Building Zone I Equipment Compartment Exhaust Solenoid (SOL). The device properties are listed in the table below.

Property Value Manufacturer Name ASCO Valve Co.

Model No.

83200 003 Pmts 3

Operating Voltage 120 VAC Max Fluid dP 30 psid Max Fluid Temp 180 F Procured on 06/19/2014 Installed on 10/14/2015 NRC FORM 366 (11-2015)

PREVIOUS SIMILAR EVENTS

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

2. DOCKET NUMBER
3. LER NUMBER YEAR I

SEQUENTIAL I

REV NUMBER NO.

05000387 2015

- 013
- 00 The following are recent LERs involving a loss of secondary containment dP due to solenoid valve failures:

~EB 0 2 Z016 Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon.Franke@TalenEnergy.com U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2015-013-00 UNIT 1 LICENSE NO. NPF-14 PLA-7437 TALEN ~

ENERGY 10 CFR 50.73 Docket No. 50-387 Attached is Licensee Event Report (LER) 50-387/2015-013-00. This LER reports an event involving Secondary Containment being declared Inoperable due to loss of differential pressure. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as a condition which at the time of discovery could have prevented fulfilment of a safety function.

There were no actual consequences to the health and safety of the public as a result of this event.

no new regulatory commitments.

. A. Franke.

Attachment: LER 50-387/2015-013-00 Copy:

NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the infomnation collection.

2. DOCKET NUMBER
3. LER NUMBER YEAR I

SEQUENTIAL I REV NUMBER NQ 05000387 2015

- 013
- 00 On December 6, 2015 at 0107 hrs, the control room received an alarm which indicated possible icing of the inlet air dampers (DMP). Shortly after the Zone I supply fans (FAN) tripped on low flow, which tripped the Zone I filtered and non-filtered exhaust fans (FAN). At 0350, operations entered Condition A of LCO 3.6.4. 1 for failure to meet SR 3.6.4.1.1 on Unit 1. After removing ice accumulated on the inlet air dampers, dP was restored. LCO 3.6.4.1 was cleared at 0434 hrs. This event immediately preceded the event subject of this LER and is being reported under LER-2015-012-00, PLA 7435.

There were no structures, systems, or components inoperable at the start of the event that contributed to the event.

EVENT DESCRIPTION

On December 6, 2015 at 0546 hours0.00632 days <br />0.152 hours <br />9.027778e-4 weeks <br />2.07753e-4 months <br />, LCO 3.6.4.1 was entered after operations personnel received alarms in the control room indicating the loss of Zone 1 differential pressure (dP). Operations personnel in the field reported the Zone 1 Division 1 Filtered Exhaust Fan (1V206A)(FAN) had failed and the other division fan (1V206B) had auto-started. 1V206B was able to maintain differential pressure in Zone I and at 0745 on December 6, 2015, operations exited LCO 3.6.4.1.

This event was reported to the NRC on December 6, 2015 at 0958 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.64519e-4 months <br /> in accordance with 10 CFR 50.72(b)(3)(v)(c) under Emergency Notification (EN) 51588. This Licensee Event Report (LER) is being submitted in accordance with 10 CFR 50.73(a)(2)(v)(c).

CAUSE OF EVENT

Further investigation revealed the solenoid valve responsible for providing air to the 1 V206A fan logic had failed. As a result, the fan was unable to exhaust enough air from Zone I which led to the degradation of Zone I dP. The direct cause of the event was determined to be solenoid valve failure.

The apparent cause of the event was unable to be determined. The failed solenoid was sent to Exelon Labs for failure analysis. Contingent upon the results of the failure analysis, a cause will be determined and additional corrective actions will be generated. When the apparent cause is determined, a supplement will be issued to update this LER.

NRC FORM 366 (11 -2015)

ANALYSIS/SAFETY SIGNIFICANCE

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

2. DOCKET NUMBER YEAR 05000387 2015
3. LER NUMBER I

SEQUENTIAL NUMBER

- 013 I

REV NO.

- 00 The actual consequence was a brief entry into LCO 3.6.4.1 and an eight hour notification of the event to the Nuclear Regulatory Commission (NRC).

An engineering evaluation was performed and concluded that secondary containment could have performed its safety function of isolating and remaining leak tight as assumed in the accident analysis. Therefore, this event did not result in a loss of safety function. This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the engineering analysis that shows there was no loss of ability to fulfill the safety function.

CORRECTIVE ACTIONS

COMPLETED

  • The failed solenoid valve was examined and tested by station personnel
  • The failed solenoid valve was sent to Exelon Labs for failure analysis PLANNED
  • Results from the failure analysis will be reviewed
  • Corrective actions will be generated to address any issues identified from the review COMPONENT INFORMATION The failed solenoid is internally referenced as SV17521A, Reactor Building Zone I Equipment Compartment Exhaust Solenoid (SOL). The device properties are listed in the table below.

Property Value Manufacturer Name ASCO Valve Co.

Model No.

83200 003 Pmts 3

Operating Voltage 120 VAC Max Fluid dP 30 psid Max Fluid Temp 180 F Procured on 06/19/2014 Installed on 10/14/2015 NRC FORM 366 (11-2015)

PREVIOUS SIMILAR EVENTS

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

2. DOCKET NUMBER
3. LER NUMBER YEAR I

SEQUENTIAL I

REV NUMBER NO.

05000387 2015

- 013
- 00 The following are recent LERs involving a loss of secondary containment dP due to solenoid valve failures:

Retrieved from "https://kanterella.com/w/index.php?title=05000387/LER-2015-013,_Regarding_Loss_of_Differential_Pressure_in_Zone_I_of_Secondary_Containment_Due_to_Solenoid_Valve_Failure&oldid=5176950"