Event Notification Report for November 14, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/13/2021 - 11/14/2021
Agreement State
Event Number: 55581
Rep Org: Ohio Bureau of Radiation Protection
Licensee: The MetroHealth System
Region: 3
City: Cleveland State: OH
County:
License #: 02110180045
Agreement: Y
Docket:
NRC Notified By: Michael J Rubadue
HQ OPS Officer: Thomas Herrity
Licensee: The MetroHealth System
Region: 3
City: Cleveland State: OH
County:
License #: 02110180045
Agreement: Y
Docket:
NRC Notified By: Michael J Rubadue
HQ OPS Officer: Thomas Herrity
Notification Date: 11/16/2021
Notification Time: 11:45 [ET]
Event Date: 11/14/2021
Event Time: 00:00 [EST]
Last Update Date: 11/16/2021
Notification Time: 11:45 [ET]
Event Date: 11/14/2021
Event Time: 00:00 [EST]
Last Update Date: 11/16/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Orth, Steve (R3)
NMSS_Events_Notification, (EMAIL)
Orth, Steve (R3)
NMSS_Events_Notification, (EMAIL)
EN Revision Imported Date: 12/16/2021
EN Revision Text: AGREEMENT STATE REPORT - LEAKING CALIBRATION SOURCE
The following was received from the Ohio Department of Health Bureau of Radiation Protection via email:
"The licensee reported a sealed Cs-137 source (IPL Model SRV-137-200U) used to calibrate instruments was leaking. The leak test was taken on November 7, 2021 and the results were reported to the licensee on November 14, 2021. The leak test results were 338 Bq (0.009 microCi). Surveys of the lead pig and source storage area showed no contamination. The source will be returned to the manufacturer for disposal."
Ohio Item Number: OH210009
EN Revision Text: AGREEMENT STATE REPORT - LEAKING CALIBRATION SOURCE
The following was received from the Ohio Department of Health Bureau of Radiation Protection via email:
"The licensee reported a sealed Cs-137 source (IPL Model SRV-137-200U) used to calibrate instruments was leaking. The leak test was taken on November 7, 2021 and the results were reported to the licensee on November 14, 2021. The leak test results were 338 Bq (0.009 microCi). Surveys of the lead pig and source storage area showed no contamination. The source will be returned to the manufacturer for disposal."
Ohio Item Number: OH210009
Power Reactor
Event Number: 55575
Facility: Peach Bottom
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Chris Wainaina
HQ OPS Officer: Karen Cotton
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Chris Wainaina
HQ OPS Officer: Karen Cotton
Notification Date: 11/14/2021
Notification Time: 08:50 [ET]
Event Date: 11/14/2021
Event Time: 05:25 [EST]
Last Update Date: 01/30/2024
Notification Time: 08:50 [ET]
Event Date: 11/14/2021
Event Time: 05:25 [EST]
Last Update Date: 01/30/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Henrion, Mark (R1)
Henrion, Mark (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 1/31/2024
EN Revision Text: MANUAL TRIP DUE TO LOWERING MAIN CONDENSER VACUUM
At 0525 EST, November 14, 2021, "Unit 2 was manually scammed by operations due to lowering main condenser vacuum. This resulted in PCIS (primary containment Isolation system) Group II/III isolation signals. All control rods inserted, and all systems operated as designed."
Unit 3 is unaffected and remains at 100 percent power in Mode 1.
The Resident Inspector was notified.
EN Revision Text: MANUAL TRIP DUE TO LOWERING MAIN CONDENSER VACUUM
At 0525 EST, November 14, 2021, "Unit 2 was manually scammed by operations due to lowering main condenser vacuum. This resulted in PCIS (primary containment Isolation system) Group II/III isolation signals. All control rods inserted, and all systems operated as designed."
Unit 3 is unaffected and remains at 100 percent power in Mode 1.
The Resident Inspector was notified.
Power Reactor
Event Number: 55576
Facility: Millstone
Region: 1 State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Sunyoung Kwon
HQ OPS Officer: Donald Norwood
Region: 1 State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Sunyoung Kwon
HQ OPS Officer: Donald Norwood
Notification Date: 11/14/2021
Notification Time: 17:06 [ET]
Event Date: 11/14/2021
Event Time: 11:50 [EST]
Last Update Date: 11/14/2021
Notification Time: 17:06 [ET]
Event Date: 11/14/2021
Event Time: 11:50 [EST]
Last Update Date: 11/14/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Henrion, Mark (R1)
Henrion, Mark (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 12/14/2021
EN Revision Text: NON-FUNCTIONAL STEAM SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP
"On November 14, 2021, at 1150 EST, while operating in Mode 1 at 100 percent power, the supply check valve from the Number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the Number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.
"There has been no radioactive release to the environment. The steam lines from the steam generators to the turbine driven auxiliary feedwater pump have been isolated by use of a motor operated valve in the discharge line of the Number 2 steam generator. There has been no impact to Unit 3 which remains at 100 percent power.
"The NRC Senior Resident has been notified.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."
EN Revision Text: NON-FUNCTIONAL STEAM SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP
"On November 14, 2021, at 1150 EST, while operating in Mode 1 at 100 percent power, the supply check valve from the Number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the Number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.
"There has been no radioactive release to the environment. The steam lines from the steam generators to the turbine driven auxiliary feedwater pump have been isolated by use of a motor operated valve in the discharge line of the Number 2 steam generator. There has been no impact to Unit 3 which remains at 100 percent power.
"The NRC Senior Resident has been notified.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."