Event Notification Report for December 11, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/10/2019 - 12/11/2019

** EVENT NUMBERS **

Power Reactor	Event Number: 54367
Facility: COMANCHE PEAK Region: 4 State: TX Unit: [] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MATT KARL HQ OPS Officer: CATY NOLAN	Notification Date: 11/03/2019 Notification Time: 09:23 [ET] Event Date: 11/03/2019 Event Time: 08:00 [CST] Last Update Date: 12/10/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JOHN DIXON (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Event Text

EN Revision Imported Date : 12/11/2019

EN Revision Text: PLANNED LOSS OF EMERGENCY RESPONSE FACILITIES AND EQUIPMENT

"At 0800 CST on November 3, 2019, Comanche Peak began a planned modification on the Unit 2 Plant Computer System. During this modification, the ability to perform emergency assessment in the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) will be impacted. Since the ability to perform emergency assessment is not expected to be restored within 72 hours, this is reportable per 10 CFR 50.72(b)(3)(xiii) as an event that results in a loss of emergency assessment capability.

"During this modification, the Control Room will continue to have the ability to perform emergency assessment. If an Alert, Site Area Emergency, or General Emergency is declared during this modification, communicators dedicated to performing emergency assessment will be stationed in the Control Room, TSC, and EOF. The Plant Computer System modification is scheduled to be completed on November 24, 2019 and a follow-up ENS notification will be made once the Unit 2 Plant Computer System is declared functional.

"The NRC Resident Inspector has been informed."

* * * UPDATE FROM MATT KARL TO HOWIE CROUCH AT 1104 EST ON 12/10/19 * * *

Unit 2 Plant Computer System has returned to service at 0756 CST on 12/10/19.

The NRC Resident Inspector has been notified. Notified R4DO (Groom).

Power Reactor	Event Number: 54430
Facility: COMANCHE PEAK Region: 4 State: TX Unit: [1] [] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: DAMON SCHROEDER HQ OPS Officer: BRIAN LIN	Notification Date: 12/10/2019 Notification Time: 00:03 [ET] Event Date: 12/09/2019 Event Time: 21:26 [CST] Last Update Date: 12/10/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JEREMY GROOM (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Event Text

MAIN STEAM LINE (MSL) RADIATION MONITOR TO BE NON-FUNCTIONAL

"1-RE-2328 Main Steam Line #1-04 MSL181 received an operate failure on loss of counts. At time 2126 [CDT], the radiation monitor was declared non-functional.

"With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 1-04 could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10 CFR 50.72(b)(3)(xiii).

"Comanche Peak Nuclear Power Plant (CPNPP) has assurance of steam generator integrity and fuel cladding integrity. There is a negligible safety significance to the current condition from a public health and safety perspective.

"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding. The N16 radiation monitor serves as a backup with alarm function and additionally Radiation Protection technicians have been briefed on taking local readings with a Geiger-Mueller tube on MSL 1-04.

"Corrective actions are being pursued to restore 1-RE-2328 to functional status.

"The NRC Resident Inspector has been notified."

Power Reactor	Event Number: 54431
Facility: COMANCHE PEAK Region: 4 State: TX Unit: [] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: GARY MERKA HQ OPS Officer: BRIAN LIN	Notification Date: 12/10/2019 Notification Time: 09:52 [ET] Event Date: 10/31/2019 Event Time: 19:19 [CDT] Last Update Date: 12/10/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION	Person (Organization): JEREMY GROOM (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Event Text

INVALID ACTUATION OF THE UNIT 2 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP (TDAFWP)

"This report describes an invalid actuation of the Unit 2 Turbine Driven Auxiliary Feedwater Pump that occurred on October 31, 2019. This report is being made in accordance with 10CFR50.73(a)(1), which states, in part, 'In the case of an invalid actuation reported under 10CFR50.73(a)(2)(iv), other than actuation of the Reactor Protection System (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER.'

"On October 31, 2019, Comanche Peak Nuclear Power Plant Unit 2 was in Mode 1 operating at 100% power. At 1919 CDT, the Main Steam Line 2-01 steam supply valve to the TDAFWP opened due to a loss of continuity between the fuse supplying control power to the valve positioner and the fuse clips. Operators initiated a 50MW load reduction to maintain power less than 100%. The steam supply to the TDAFWP was closed, the TDAFWP was stopped, and the fuse clips were tightened. Unit 2 was returned to full power at 2055 CDT.

"The specific train and system that actuated was the third AFW train on Unit 2. The train actuation was complete and during the TDAFWP start the system started and functioned correctly.

"The NRC Resident Inspector was notified."

Power Reactor	Event Number: 54433
Facility: COMANCHE PEAK Region: 4 State: TX Unit: [1] [] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MATT KARL HQ OPS Officer: HOWIE CROUCH	Notification Date: 12/10/2019 Notification Time: 11:04 [ET] Event Date: 12/10/2019 Event Time: 09:20 [CST] Last Update Date: 12/10/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JEREMY GROOM (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Event Text

PLANNED LOSS OF EMERGENCY RESPONSE FACILITIES AND EQUIPMENT

"At 0920 CST on December 10, 2019, Comanche Peak began a planned modification on the Unit 1 Plant Computer System. During this modification, the ability to perform emergency assessment in the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) will be impacted. Since the ability to perform emergency assessment is not expected to be restored within 72 hours, this is reportable per 10CFR50.72(b)(3)(xiii) as an event that results in a loss of emergency assessment capability.

"During this modification, the Control Room will continue to have the ability to perform emergency assessment. If an Alert, Site Area Emergency, or General Emergency is declared during this modification, communicators dedicated to performing emergency assessment will be stationed in the Control Room, TSC, and EOF. The Plant Computer System modification is scheduled to be completed on December 22, 2019, and a follow-up ENS notification will be made once the Unit 1 Plant Computer System is declared functional.

"The NRC Resident Inspector has been informed."

Part 21	Event Number: 54435
Rep Org: GENERAL ATOMICS Licensee: GENERAL ATOMICS ELECTROMAGNETIC SYSTEMS Region: 4 City: SAN DIEGO State: CA County: License #: Agreement: Y Docket: NRC Notified By: MICHAEL GROGAN HQ OPS Officer: ANDREW WAUGH	Notification Date: 12/10/2019 Notification Time: 18:30 [ET] Event Date: 10/17/2019 Event Time: 00:00 [PST] Last Update Date: 12/10/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE	Person (Organization): CHRISTOPHER LALLY (R1DO) BRIAN BONSER (R2DO) BILLY DICKSON (R3DO) JEREMY GROOM (R4DO) - PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 - HARDWARE FAILURE IN RADIATION MONITORING SYSTEM

The following is a summary of information received from General Atomics via fax:

On October 17, 2019, General Atomics (GA) identified a hardware failure in GA's Model RP-2C radiation monitoring system, manufactured and supplied by GA's Electromagnetic Systems Group (GA-EMS). The RP-2C radiation monitoring systems are used for post-accident monitoring of the containment area.

The defect would prevent the RP-2C from sensing a high radiation condition. This could present a potential safety hazard to personnel by not indicating the actual radiation value and by not actuating the plant systems connected to the alarm relays. It is noted that there are typically redundant high range containment monitoring systems available to the control room operators, and the operators would be able to rely on the remaining operable channels during an accident.

GA-EMS will issue a Quality Bulleting to the affected sites that will include additional detail in identifying affected modules and what to do if a defect is found. Sites are advised to continue performing their normal surveillance testing of the RP-2C module by utilizing the front panel CHECK test feature.

If you have any questions or need additional information concerning this report please contact Michael Grogan, Senior Director of Licensing, at (858) 455-2809 or Michael.Grogan@ga.com. Technical questions can be directed to Arthur Evans at (858) 964-6948.

The following plants are affected: FitzPatrick, Millstone, Peach Bottom, Pilgrim, Susquehanna, Catawba, McGuire, Saint Lucie, Sequoyah, Turkey Point, Watts Bar, Fermi, LaSalle, Palisades, Point Beach, Prairie Island, Quad Cities, Arkansas Nuclear One, Columbia Generating Station, Crystal River, Kewaunee, San Onofre, Zion.

Page Last Reviewed/Updated Thursday, March 25, 2021