Event Notification Report for November 16, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/15/2021 - 11/16/2021
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: 11/14/2021
Notification Time: 08:50 [ET]
Event Date: 11/14/2021
Event Time: 05:25 [EST]
Last Update Date: 11/14/2021
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: 11/16/2021
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 (process control and instrumentation 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 (process control and instrumentation 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: 11/16/2021
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."
Power Reactor
Event Number: 55580
Facility: Summer
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Leon Smith
HQ OPS Officer: Donald Norwood
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Leon Smith
HQ OPS Officer: Donald Norwood
Notification Date: 11/15/2021
Notification Time: 21:00 [ET]
Event Date: 11/15/2021
Event Time: 17:28 [EST]
Last Update Date: 11/16/2021
Notification Time: 21:00 [ET]
Event Date: 11/15/2021
Event Time: 17:28 [EST]
Last Update Date: 11/16/2021
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Miller, Mark (R2)
Miller, Mark (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 47 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 11/17/2021
EN Revision Text: MANUAL REACTOR TRIP DUE TO MAIN TRANSFORMER FAULT
"At 1728 EST on 11/15/2021, with Unit 1 in Mode 1 at 47 percent power, the reactor was manually tripped due to a main transformer fault. The trip was not complex, with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system through the main condenser.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"Additionally, due to the valid actuation of the emergency feedwater system, this event is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified."
* * * UPDATE ON 11/16/21 AT 1649 EST FROM BRUCE BENNETT TO KERBY SCALES * * *
"At approximately 0900 [EST] on 11/16/2021, it was identified that mineral oil from the faulted main transformer had surpassed the capability of the oil containment system and discharged into Lake Monticello. It is estimated that less than 50 gallons of mineral oil entered the Lake. The oil is contained with booms and cleanup is ongoing. The EPA National Response Center and the South Carolina Department of Health and Environmental Control have been notified. This is considered a news release or notification to other government agencies; therefore, this event is reportable under 10 CFR 50.72(b)(2)(xi).
"The NRC Senior Resident Inspector has been notified."
Notified R2DO (Miller).
EN Revision Text: MANUAL REACTOR TRIP DUE TO MAIN TRANSFORMER FAULT
"At 1728 EST on 11/15/2021, with Unit 1 in Mode 1 at 47 percent power, the reactor was manually tripped due to a main transformer fault. The trip was not complex, with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system through the main condenser.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"Additionally, due to the valid actuation of the emergency feedwater system, this event is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified."
* * * UPDATE ON 11/16/21 AT 1649 EST FROM BRUCE BENNETT TO KERBY SCALES * * *
"At approximately 0900 [EST] on 11/16/2021, it was identified that mineral oil from the faulted main transformer had surpassed the capability of the oil containment system and discharged into Lake Monticello. It is estimated that less than 50 gallons of mineral oil entered the Lake. The oil is contained with booms and cleanup is ongoing. The EPA National Response Center and the South Carolina Department of Health and Environmental Control have been notified. This is considered a news release or notification to other government agencies; therefore, this event is reportable under 10 CFR 50.72(b)(2)(xi).
"The NRC Senior Resident Inspector has been notified."
Notified R2DO (Miller).
Non-Power Reactor
Event Number: 55583
Rep Org: Univ Of Missouri-Columbia (MISC)
Licensee: University Of Missouri
Region: 0
City: Columbia State: MO
County: Boone
License #: R-103
Agreement: N
Docket: 05000186
NRC Notified By: Bruce Meffert
HQ OPS Officer: Kerby Scales
Licensee: University Of Missouri
Region: 0
City: Columbia State: MO
County: Boone
License #: R-103
Agreement: N
Docket: 05000186
NRC Notified By: Bruce Meffert
HQ OPS Officer: Kerby Scales
Notification Date: 11/16/2021
Notification Time: 15:59 [ET]
Event Date: 11/15/2021
Event Time: 00:00 [CST]
Last Update Date: 11/16/2021
Notification Time: 15:59 [ET]
Event Date: 11/15/2021
Event Time: 00:00 [CST]
Last Update Date: 11/16/2021
Emergency Class: Non Emergency
10 CFR Section:
10 CFR Section:
Person (Organization):
Geoff Wertz (NRR PM)
Mike Takacs (NRR ENC)
Geoff Wertz (NRR PM)
Mike Takacs (NRR ENC)
ABNORMAL OCCURRENCE
"University Of Missouri Research Reactor (MURR) Technical Specification (TS) 6.6.c(1) requires notification to the NRC Operations Center that an Abnormal Occurrence, as defined by MURR TS 1.1, has occurred. MURR was not in compliance with one (1) of the TS Limiting Conditions of Operations. TS 3.2.g states, 'The reactor safety system and the number (N) of associated instrument channels necessary to provide the following scrams shall be operable whenever the reactor is in operation.' Specifically, the reactor safety scram function that occurs when the differential pressure across the reactor pool reflector (PT-917) instrument channel decreases below 2.52 psi minimum in Mode 1 operation was not operable as required by TS 3.2.g.10.
"On 11/15/21 while the reactor was shut down, Control Room operators shut down the pool coolant system and noticed that the `Reflector Hi-Low Diff Pressure Scram' annunciator alarm did not initiate as pool coolant flow rate decreased to zero. The Control Room operators contacted reactor management, and an investigation was initiated to prove whether or not the safety scram function from the PT-917 instrument channel actuated correctly. Further testing revealed the safety scram signal from the PT-917 instrument channel did not occur due to a failed alarm-meter unit. The alarm-meter unit was replaced with an exact spare, the PT-917 instrument channel was calibrated, and the reactor safety scram functions of the PT-917 instrument channel were retested satisfactorily.
"In accordance with TS 6.6.c(4), the Reactor Facility Director was briefed and gave permission to restart the reactor prior to the reactor returning to operation later on 11/15/21. Currently, MURR is operating at 10 MW. A detailed event report will follow within 14 days as required by MURR TS 6.6.c(3)."
The NRC Project manager was notified.
"University Of Missouri Research Reactor (MURR) Technical Specification (TS) 6.6.c(1) requires notification to the NRC Operations Center that an Abnormal Occurrence, as defined by MURR TS 1.1, has occurred. MURR was not in compliance with one (1) of the TS Limiting Conditions of Operations. TS 3.2.g states, 'The reactor safety system and the number (N) of associated instrument channels necessary to provide the following scrams shall be operable whenever the reactor is in operation.' Specifically, the reactor safety scram function that occurs when the differential pressure across the reactor pool reflector (PT-917) instrument channel decreases below 2.52 psi minimum in Mode 1 operation was not operable as required by TS 3.2.g.10.
"On 11/15/21 while the reactor was shut down, Control Room operators shut down the pool coolant system and noticed that the `Reflector Hi-Low Diff Pressure Scram' annunciator alarm did not initiate as pool coolant flow rate decreased to zero. The Control Room operators contacted reactor management, and an investigation was initiated to prove whether or not the safety scram function from the PT-917 instrument channel actuated correctly. Further testing revealed the safety scram signal from the PT-917 instrument channel did not occur due to a failed alarm-meter unit. The alarm-meter unit was replaced with an exact spare, the PT-917 instrument channel was calibrated, and the reactor safety scram functions of the PT-917 instrument channel were retested satisfactorily.
"In accordance with TS 6.6.c(4), the Reactor Facility Director was briefed and gave permission to restart the reactor prior to the reactor returning to operation later on 11/15/21. Currently, MURR is operating at 10 MW. A detailed event report will follow within 14 days as required by MURR TS 6.6.c(3)."
The NRC Project manager was notified.
Agreement State
Event Number: 55584
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: British Petroleum
Region: 3
City: Lemont State: IL
County:
License #: 9152422
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Kerby Scales
Licensee: British Petroleum
Region: 3
City: Lemont State: IL
County:
License #: 9152422
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Kerby Scales
Notification Date: 11/16/2021
Notification Time: 16:09 [ET]
Event Date: 11/10/2021
Event Time: 00:00 [CST]
Last Update Date: 11/16/2021
Notification Time: 16:09 [ET]
Event Date: 11/10/2021
Event Time: 00:00 [CST]
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)
AGREEMENT STATE REPORT - STUCK SHUTTER
The following was received from the state of Illinois (the Agency) via email:
"The Agency was notified by British Petroleum [BP] (registered as a general licensee under the name CHICAP Pipe Line Company (9152422)), that they had discovered a stuck shutter on a generally licensed fixed gauge at their Lemont, IL location. The shutter, which is normally open, has apparently been broken for many years and was only discovered during removal last week. No personnel exposures resulted and the gauge has been secured pending disposal.
"A specifically licensed service provider was removing a generally licensed fixed gauge on 11/10/21 for planned disposal through a waste broker when it was discovered to have an inoperable shutter. The gauge was a Ronan Engineering Company model SA-1, containing 50 milliCi of Cs-137 (s/n 8333GG). While the shutter was reportedly routinely tested, the arm that moves the shutter was severely corroded. It was only during removal that the registrant discovered the shutter itself was broken. The gauge has been in service for 24 years and was installed at a 12' height with the beam projecting into the process equipment. As the shutter remains in the open position and personnel are not in the beam path, personnel exposure is not a concern. No reported exposures during removal. The gauge has been double locked with the beam facing down into the concrete floor. The shutter is being repaired so it may be properly transported and disposed of through Bionomics (waste broker). A written report detailing remedial action is required within 30 days under 32 Ill. Adm. Code 330.220(a)(3)(E).
"This incident is reportable under 32 Ill. Adm. Code 340.1220. At this time, it does not appear a response to the site by Agency staff will be required. BP's consultant indicated that the gauge manufacturer reports 3-4 of these gauges per year are returned. The issue is reportedly a seal that leaks and gives rise to corrosion - despite being used within the environmental conditions specified in the SSDR [Seal Source Device Registry]. This information is anecdotal but included for NRC's evaluation and trending analysis. This matter will remain open until confirmation of shipping for disposal is received."
Illinois Item Number: IL210037
The following was received from the state of Illinois (the Agency) via email:
"The Agency was notified by British Petroleum [BP] (registered as a general licensee under the name CHICAP Pipe Line Company (9152422)), that they had discovered a stuck shutter on a generally licensed fixed gauge at their Lemont, IL location. The shutter, which is normally open, has apparently been broken for many years and was only discovered during removal last week. No personnel exposures resulted and the gauge has been secured pending disposal.
"A specifically licensed service provider was removing a generally licensed fixed gauge on 11/10/21 for planned disposal through a waste broker when it was discovered to have an inoperable shutter. The gauge was a Ronan Engineering Company model SA-1, containing 50 milliCi of Cs-137 (s/n 8333GG). While the shutter was reportedly routinely tested, the arm that moves the shutter was severely corroded. It was only during removal that the registrant discovered the shutter itself was broken. The gauge has been in service for 24 years and was installed at a 12' height with the beam projecting into the process equipment. As the shutter remains in the open position and personnel are not in the beam path, personnel exposure is not a concern. No reported exposures during removal. The gauge has been double locked with the beam facing down into the concrete floor. The shutter is being repaired so it may be properly transported and disposed of through Bionomics (waste broker). A written report detailing remedial action is required within 30 days under 32 Ill. Adm. Code 330.220(a)(3)(E).
"This incident is reportable under 32 Ill. Adm. Code 340.1220. At this time, it does not appear a response to the site by Agency staff will be required. BP's consultant indicated that the gauge manufacturer reports 3-4 of these gauges per year are returned. The issue is reportedly a seal that leaks and gives rise to corrosion - despite being used within the environmental conditions specified in the SSDR [Seal Source Device Registry]. This information is anecdotal but included for NRC's evaluation and trending analysis. This matter will remain open until confirmation of shipping for disposal is received."
Illinois Item Number: IL210037