Event Notification Report for February 03, 2020

U.S. Nuclear Regulatory Commission Operations Center Event Reports For 1/31/2020 - 2/3/2020 ** EVENT NUMBERS **

 

54379

54380

54382

54493

54494

54503

54506

54507

54508

Power Reactor	Event Number: 54379
Facility: WATTS BAR Region: 2     State: TN Unit: [1] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: DEAN BAKER HQ OPS Officer: BRIAN P. SMITH	Notification Date: 11/12/2019 Notification Time: 07:57 [ET] Event Date: 11/12/2019 Event Time: 07:00 [EST] Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): ERIC MICHEL (R2DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

100

Power Operation

2

N

Y

100

Power Operation

100

Power Operation

Event Text

EMERGENCY OPERATIONS FACILITY OUT OF SERVICE "On November 12, 2019, the Central Emergency Control Center (CECC) was removed from service for a planned facility upgrade project. The CECC is a common Emergency Operations Facility (EOF) for the TVA Nuclear sites (Browns Ferry / Sequoyah / Watts Bar). The duration of the upgrade project is approximately 75 days. "If an emergency is declared requiring CECC activation during this period, an alternate CECC will be used. During this period, the alternate CECC will be staffed and activated using existing emergency procedures. "This is an eight-hour, non-emergency notification for a Loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the CECC will be unavailable for more than 72 hours. "The Emergency Response Organization has been notified that the CECC will be unavailable during the upgrade project and to report to the alternate CECC in the event of an emergency. There is no impact on the health and safety of the public or plant employees. "The NRC Resident Inspector has been notified." * * * UPDATE FROM JUSTIN GALLAGHER TO KERBY SCALES AT 1620 EST ON 1/31/2020 * * * "The CECC facility upgrade project is sufficiently complete such that the CECC was returned to a functional status at 1400 EST on January 31, 2020. "The NRC Resident Inspector has been notified." Notified R2DO (Baptist)

Power Reactor	Event Number: 54380
Facility: SEQUOYAH Region: 2     State: TN Unit: [1] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: LESLIE MOREY HQ OPS Officer: THOMAS KENDZIA	Notification Date: 11/12/2019 Notification Time: 08:28 [ET] Event Date: 11/12/2019 Event Time: 07:00 [EST] Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): ERIC MICHEL (R2DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

N

0

Cold Shutdown

0

Cold Shutdown

2

N

Y

100

Power Operation

100

Power Operation

Event Text

EMERGENCY OPERATIONS FACILITY OUT OF SERVICE "On November 12, 2019, the Central Emergency Control Center (CECC) was removed from service for a planned facility upgrade project. The CECC is a common Emergency Operations Facility (EOF) for the TVA Nuclear sites (Browns Ferry / Sequoyah / Watts Bar). The duration of the upgrade project is approximately 75 days. "If an emergency is declared requiring CECC activation during this period, an alternate CECC will be used. During this period, the alternate CECC will be staffed and activated using existing emergency procedures. "This is an eight-hour, non-emergency notification for a Loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the CECC will be unavailable for more than 72 hours. "The Emergency Response Organization has been notified that the CECC will be unavailable during the upgrade project and to report to the alternate CECC in the event of an emergency. There is no impact on the health and safety of the public or plant employees. "The NRC Resident Inspector has been notified." * * * UPDATE FROM BRYAN KLEIN TO DONALD NORWOOD AT 1450 EST ON 1/31/2020 * * * "The CECC facility upgrade project is sufficiently complete such that the CECC was returned to a functional status at 1400 EDT on January 31, 2020. "The NRC Resident Inspector has been notified." Notified R2DO (Baptist).

Power Reactor	Event Number: 54382
Facility: BROWNS FERRY Region: 2     State: AL Unit: [1] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: ANGEL YARBROUGH HQ OPS Officer: THOMAS KENDZIA	Notification Date: 11/12/2019 Notification Time: 10:32 [ET] Event Date: 11/12/2019 Event Time: 06:00 [CST] Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): ERIC MICHEL (R2DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

100

Power Operation

2

N

Y

100

Power Operation

100

Power Operation

3

N

Y

100

Power Operation

100

Power Operation

Event Text

EMERGENCY OPERATIONS FACILITY OUT OF SERVICE "On November 12, 2019, the Central Emergency Control Center (CECC) was removed from service for a planned facility upgrade project. The CECC is a common Emergency Operations Facility (EOF) for the TVA Nuclear sites (Browns Ferry / Sequoyah / Watts Bar). The duration of the upgrade project is approximately 75 days. "If an emergency is declared requiring CECC activation during this period, an alternate CECC will be used. During this period, the alternate CECC will be staffed and activated using existing emergency procedures. "This is an eight-hour, non-emergency notification for a Loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the CECC will be unavailable for more than 72 hours. "The Emergency Response Organization has been notified that the CECC will be unavailable during the upgrade project and to report to the alternate CECC in the event of an emergency. There is no impact on the health and safety of the public or plant employees. "The NRC Resident Inspector has been notified." * * * UPDATE AT 1316 EST ON 11/14/19 FROM BARUCH CALKIN TO JEFF HERRERA * * * The event information was updated to indicate that the event occurred at 0700 EST. The NRC Resident Inspector has been notified. Notified the R2DO(Musser). * * * UPDATE FROM ALAN PRUCHA TO KERBY SCALES AT 1526 EST ON 1/31/2020 * * * "The CECC facility upgrade project is sufficiently complete such that the CECC was returned to a functional status at 1350 CST on January 31, 2020. "The NRC Resident Inspector has been notified." Notified R2DO (Baptist).

Agreement State	Event Number: 54493
Rep Org: UTAH DIVISION OF RADIATION CONTROL Licensee: Region: 4 City: SALT LAKE CITY   State: UT County: License #: Agreement: Y Docket: NRC Notified By: GWYN GALLOWAY HQ OPS Officer: THOMAS KENDZIA	Notification Date: 01/23/2020 Notification Time: 21:32 [ET] Event Date: 01/21/2020 Event Time: 10:15 [MST] Last Update Date: 01/23/2020
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): PATRICIA SILVA (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FOUND SOURCE The following is a synopses of a report received from the Utah Department of Environmental Quality (the Division) via email: On January 21, 2020, a licensee left a message for the Division that a source had been found lying outside of the locked gate of one of the licensee's facilities. The licensee reported that it was not their source, but they moved it inside of their facility in order to secure the source and keep a member of the public from finding it. The licensee did not have much information regarding the source when staff spoke with them, but sent a picture of the source that was found. The picture showed a small can labeled with a Beckman Instruments, Inc. label. The label stated that the can contained 40 microcuries of Cs-137 assayed on July 30, 1981. The label was consistent with a generally licensed source and appeared to have been manufactured in CA. The licensee did not know where the source came from or why it was deposited close to their entrance gate. A member of the Division's staff will go to the licensee's facility tomorrow to read the serial number and the full label from the can. Utah Event Report ID #: UT200001

Agreement State	Event Number: 54494
Rep Org: OR DEPT OF HEALTH RAD PROTECTION Licensee: PORTLAND GENERAL ELECTRIC Region: 4 City: BOARDMAN   State: OR County: License #: 90735 Agreement: Y Docket: NRC Notified By: HILLARY HASKINS HQ OPS Officer: OSSY FONT	Notification Date: 01/24/2020 Notification Time: 17:50 [ET] Event Date: 01/24/2020 Event Time: 13:24 [PST] Last Update Date: 01/24/2020
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): PATRICIA SILVA (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE DAMAGED The following summary was received from the Oregon Public Health Division via phone: The licensee reported that the handle of a fixed gauge used as a level indicator broke off. The device contains Cs-137 and the shutter is in the closed position. The device will not be used until it is repaired by an authorized party.

Power Reactor	Event Number: 54503
Facility: FITZPATRICK Region: 1     State: NY Unit: [1] [] [] RX Type: [1] GE-4 NRC Notified By: ROBERT GRAHAM HQ OPS Officer: THOMAS KENDZIA	Notification Date: 01/31/2020 Notification Time: 09:46 [ET] Event Date: 01/31/2020 Event Time: 05:55 [EST] Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): MARK HENRION (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

A/R

Y

38

Power Operation

0

Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP "At 0555 [EST], on January 31, 2020, James A. FitzPatrick was at 38 percent power when an automatic scram occurred as a result of a main turbine trip on high Reactor Pressure Vessel (RPV) water level. The plant was at reduced power in preparation for maintenance activities. The 'A' Reactor Feed Pump (RFP) was being removed from service when a perturbation in reactor water level reached the high RPV water level setpoint. This resulted in a main turbine trip and 'B' RFP trip. "The automatic scram inserted all control rods. A subsequent low water level resulted in a successful Group 2 isolation. The plant is stable in Mode 3 with the 'B' RFP maintaining RPV water level. The initiation of the reactor protection systems (RPS) due to the automatic scram signal at critical power is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The general containment Group 2 isolations are reportable per 10 CFR 50.72(b)(3)(iv)(A)." The licensee notified the NRC Resident Inspector, and the State and Local government for the scram. Decay heat is being removed via the main condenser.

Part 21	Event Number: 54506
Rep Org: FAIRBANKS MORSE Licensee: FAIRBANKS MORSE Region: 3 City: Beloit   State: WI County: License #: Agreement: Y Docket: NRC Notified By: MARTIN KURR HQ OPS Officer: KERBY SCALES	Notification Date: 01/31/2020 Notification Time: 16:32 [ET] Event Date: 01/31/2020 Event Time: 00:00 [CST] Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE	Person (Organization): MARK HENRION (R1DO) JAMES BAPTIST (R2DO) - PART 21/50.55 REACTORS (EMAIL)

Event Text

Part 21 - UNKNOWN TIGHTNESS OF CAM THRUST LOCK NUT ASSEMBLY The following information is a summary of information received via facsimile: On January 31, 2020, Fairbanks Morse (FM) submitted information of a defect or failure of the unknown tightness of the opposed piston (OP) diesel engine cam thrust lock washer and lock nut assembly for emergency diesel generators (EDGs). FM assembled and completed a factory acceptance test on a 1000 rpm new opposed piston diesel engine generator set. Upon post-test inspection it was discovered that the lock nut and lock washer had fallen off of the camshaft. The failure did not prevent the engine from starting, accelerating to rated speed as well as accepting and sustaining rated load. The failure does not result in an immediate engine shutdown or load rejection. The timing chain restrains the camshaft adequately for the engine to perform its emergency function. However, it cannot be concluded that the engine would continue to operate for the entire duration of its safety function. This Part 21 notification is being issued for subject engines with less than 98 hours of operation since the camshaft lock nut assembly was tightened. This Part 21 notification is being applied only to engines with less than 98 operating hours since the cam lock nut assembly was tightened for the following two reasons: 1) There are no known occurrences of cam lock nut assembly failures on any 900 rpm FM OP engines. All FM OP engines in service as EDGs in the United States are 900 rpm and 2) A laboratory analysis of the failed components conclusively shows this failure is an infant mortality. In the event the cam lock nut is loose, the lock washer will fail very quickly upon engine operation. FM has defined the appropriate tightening value to the cam lock nut assembly in Service Information Letter SIL-40 and has provided this guidance to all licensees that possess FM OP engines. FM has updated all internal engineering specifications and manufacturing instructions to include the newly specified tightening requirements. There are no 10 CFR 50 Appendix B FM OP engines being newly constructed. A list of affected customers are: Exelon - Peach Bottom Nuclear Generating Station and Southern Nuclear / Georgia Power - Hatch Nuclear Power Plant FM Notification Report Serial Number 20-01

Power Reactor	Event Number: 54507
Facility: PERRY Region: 3     State: OH Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: CLIFFORD JONES HQ OPS Officer: KERBY SCALES	Notification Date: 02/01/2020 Notification Time: 16:29 [ET] Event Date: 02/01/2020 Event Time: 11:50 [EST] Last Update Date: 02/01/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): LAURA KOZAK (R3DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

100

Power Operation

Event Text

LOW PRESSURE CORE SPRAY INOPERABLE "At 1150 EST on 2/1/2020, it was discovered that the Low Pressure Core Spray System was inoperable due to a divisional battery voltage being out of specification. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The Low Pressure Core Spray is a single train safety system in Modes 1, 2, and 3. Low Pressure Core Spray was restored to operable, restoring function at 1230 on 2/1/2020. "There was no impact on the health and safety of the public or plant personnel. "The NRC Resident Inspector has been notified."

Power Reactor	Event Number: 54508
Facility: WOLF CREEK Region: 4     State: KS Unit: [1] [] [] RX Type: [1] W-4-LP NRC Notified By: ERIC CARLSON HQ OPS Officer: DONALD NORWOOD	Notification Date: 02/01/2020 Notification Time: 23:06 [ET] Event Date: 02/01/2020 Event Time: 18:45 [CST] Last Update Date: 02/01/2020
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS	Person (Organization): RAY AZUA (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

0

Hot Standby

Event Text

TECHNICAL SPECIFICATION SHUTDOWN DUE TO CONTAINMENT PURGE VALVE EXCESSIVE LEAKAGE At 1845 CST on 2/1/2020, during surveillance testing (STS PE-015, Containment Purge Valve Leakage Test) containment leakage in excess of Technical Specification requirements was observed. A Technical Specification required shutdown was initiated at 2030 CST and Mode 3 was achieved at 2154 CST. All systems functioned as required during and following shutdown. The unit is proceeding to Mode 5. The licensee notified the NRC Resident Inspector.