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Event Notification Report for November 22, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/21/2019 - 11/22/2019

** EVENT NUMBERS **


54293 54385 54401 54403

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 54293
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: OSSY FONT
Notification Date: 09/25/2019
Notification Time: 15:30 [ET]
Event Date: 09/25/2019
Event Time: 12:03 [EDT]
Last Update Date: 11/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text



EN Revision Imported Date : 11/22/2019

EN Revision Text: HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE

"At 1203 EDT, on September 25, 2019, during a Division 2 Emergency Equipment Service Water (EESW) pump and valve surveillance test, the Division 2 Emergency Equipment Cooling Water (EECW) Temperature Control Valve was found to be approximately 80 percent open rather than in its required full open position during fail safe testing. The Division 2 EESW system is required to support operability of the Division 2 EECW system. The Division 2 EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. An investigation is underway into the cause of the failure. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability.

"The NRC Senior Resident Inspector has been notified."

The licensee is in 72-hour shutdown action statement.

* * * RETRACTION ON 11/21/19 AT 1547 EST FROM PAUL ANGOVE TO BRIAN LIN * * *

"Subsequent engineering evaluation has determined that the EECW TCV was capable of passing sufficient flow to perform its design basis functions, including supporting the HPCI room cooler, while approximately 80% open. Therefore, HPCI remained operable and there was no loss of safety function. The event did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D).

"EN 54293 is retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted.

"The NRC Resident Inspector has been notified. "

Notified R3DO (Cameron).

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Agreement State Event Number: 54385
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: WEST PENN ALLEGHENY HEALTH SYSTEM INC
Region: 1
City: PITTSBURG   State: PA
County:
License #: PA-0031
Agreement: Y
Docket:
NRC Notified By: JOHN CHIPPO
HQ OPS Officer: OSSY FONT
Notification Date: 11/14/2019
Notification Time: 10:40 [ET]
Event Date: 11/08/2019
Event Time: 00:00 [EST]
Last Update Date: 11/15/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DOSE DELIVERED DIFFERS BY MORE THAN 20 PERCENT

The following was received from the Pennsylvania Department of Environmental Protection (DEP; the Department) via email:

"The Department received initial verbal notification from a licensee on November 8, 2019 of a possible reportable event with a detailed report on November 13, 2019 that on November 8, 2019 a reportable event occurred during an eye plaque implant (Theragenics model AgX100) containing 13 lodine-125 seeds. The seed activity was 3.728 mCi per seed for a total activity of 48.46 mCi. The prescribed dose was 8,500 rad with a planned treatment time of 101 hours. The implant was placed at 0745 [EDT] on 11/8/19. At approximately 0815 the patient complained of excessive pain. It is believed that the eye plaque had become dislodged from its proper position. It was removed at 1731 the same day. The licensee initial worst-case dose estimate to the normal sclera, conjunctiva and cornea is 1,899 rad at a depth of 1 mm for an 8.5 hour exposure. The dose at 2mm for this same time period is 1,425 rad. Both the patient and surgeon were notified. The effects on the patient are currently being evaluated. The DEP will update this event as soon as more information is provided."

Event Report ID No: PA190027

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Power Reactor Event Number: 54401
Facility: SURRY
Region: 2     State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOE POLLARD
HQ OPS Officer: BETHANY CECERE
Notification Date: 11/21/2019
Notification Time: 04:02 [ET]
Event Date: 11/20/2019
Event Time: 21:44 [EST]
Last Update Date: 11/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BINOY DESAI (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

UNIT 2 AUXILIARY FEED PUMPS INOPERABLE

"At 2144 EST, on 11/20/2019, all three auxiliary feedwater pumps for Unit 2 were declared Inoperable due to check valve leakage causing the turbine driven auxiliary feedwater pump to rotate backwards and subsequently trip. At this time, two of the Unit 1 motor driven auxiliary feedwater pumps were still able to provide cross-tied feedwater in the event of a design basis accident.

"At 2203 EST, the two motor driven auxiliary feedwater pumps on Unit 2 were declared operable once the discharge isolation valves for the turbine driven auxiliary feedwater pump were closed, thus preventing backflow through the turbine driven auxiliary feedwater pump and ensuring forward flow of the motor driven auxiliary feedwater pumps.

"This condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented the fulfillment of a safety function.

"There is no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

Unit 2 is in a 72-hour LCO 3.6.F.1 for turbine driven auxiliary feedwater pump inoperability.

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Power Reactor Event Number: 54403
Facility: CLINTON
Region: 3     State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ALLEN BRAND
HQ OPS Officer: BRIAN LIN
Notification Date: 11/21/2019
Notification Time: 21:11 [ET]
Event Date: 11/21/2019
Event Time: 12:25 [CST]
Last Update Date: 11/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

UNIT 1 HIGH PRESSURE CORE SPRAY INOPERABLE

"On 11/21/2019, at 1225 CST, as a result of Division 4 DC bus voltage oscillations, bus voltage lowered to less than the required improved technical specification (ITS) voltage of 127.6 VDC. This resulted in declaring High Pressure Core Spray (HPCS) system inoperable per technical specification LCO 3.8.4 and 3.8.9 actions. Division 4 DC bus voltage was restored to greater than 127.6 VDC at 1227 CST. The HPCS system remains inoperable due to Division 4 DC battery charger inoperability.

"Since HPCS is an emergency core cooling system and is a single train safety system, this condition is reportable under 10 CFR 50.72(b)(3)(v)(D) .

"The NRC Resident Inspector has been notified."

Clinton Power Station has implemented required compensatory actions due to the Division 4 DC battery charger and HPCS remaining inoperable.


Page Last Reviewed/Updated Friday, November 22, 2019
Friday, November 22, 2019