Event Notification Report for October 23, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/22/2017 - 10/23/2017
Non-Agreement State
Event Number: 53030
Rep Org: WEST BRANCH REGIONAL MEDICAL CENTER
Licensee: WEST BRANCH REGIONAL MEDICAL CENTER
Region: 3
City: WEST BRANCH State: MI
County:
License #: 09-32781-03MD
Agreement: N
Docket:
NRC Notified By: DAVID BARRATT
HQ OPS Officer: JEFF HERRERA
Licensee: WEST BRANCH REGIONAL MEDICAL CENTER
Region: 3
City: WEST BRANCH State: MI
County:
License #: 09-32781-03MD
Agreement: N
Docket:
NRC Notified By: DAVID BARRATT
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/23/2017
Notification Time: 09:11 [ET]
Event Date: 10/23/2017
Event Time: 07:40 [EDT]
Last Update Date: 10/23/2017
Notification Time: 09:11 [ET]
Event Date: 10/23/2017
Event Time: 07:40 [EDT]
Last Update Date: 10/23/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
ERIC DUNCAN (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ERIC DUNCAN (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
DELIVERY OF TC-99 SHOWED INCREASED RADIATION LEVEL ON CONTACT WITH PACKAGE
At 0740 EDT on 10/23/2017, while performing equipment quality control, the nuclear medical technician identified that the incoming case containing less than 100 milliCuries of Tc-99 measured from 190-220 mR/hr on contact. The technician performed a surface wipe to identify contamination and determined that there was no leakage or spill of contamination. At 0850 the radiation safety officer was notified of the event. The case was then placed into a waste decay storage area away from other personnel. The company that shipped the package was also contacted regarding the situation.
The type of isotopes provided were provided based on the ordered quantity, however, the technician reported that there might be other isotopes in the container, however could not verify without opening the container to look inside.
At 0740 EDT on 10/23/2017, while performing equipment quality control, the nuclear medical technician identified that the incoming case containing less than 100 milliCuries of Tc-99 measured from 190-220 mR/hr on contact. The technician performed a surface wipe to identify contamination and determined that there was no leakage or spill of contamination. At 0850 the radiation safety officer was notified of the event. The case was then placed into a waste decay storage area away from other personnel. The company that shipped the package was also contacted regarding the situation.
The type of isotopes provided were provided based on the ordered quantity, however, the technician reported that there might be other isotopes in the container, however could not verify without opening the container to look inside.
Power Reactor
Event Number: 53031
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JOSH SMITH
HQ OPS Officer: JEFF HERRERA
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JOSH SMITH
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/23/2017
Notification Time: 09:35 [ET]
Event Date: 10/23/2017
Event Time: 04:00 [EDT]
Last Update Date: 10/23/2017
Notification Time: 09:35 [ET]
Event Date: 10/23/2017
Event Time: 04:00 [EDT]
Last Update Date: 10/23/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BRICE BICKETT (R1DO)
BRICE BICKETT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
LEAKAGE IDENTIFIED ON ONE INCH LINE SOCKET WELD FOR THE B RECIRCULATION PUMP
"On Monday, October 23, 2017, with PBAPS [Peach Bottom Atomic Power Station] Unit 3 in Mode 3 at the beginning of a refueling outage, personnel entered the drywell to perform an inspection. At approximately 0400 [EDT], leakage was identified on a one-inch diameter instrument line socket weld for the 'B' recirculation pump. Because the leak was misting, the leakage rate could not be quantified. However, Unit 3 reactor coolant unidentified leakage prior to plant shutdown was 0.18 gpm. This line is considered part of the primary coolant pressure boundary.
"This event is being reported as an occurrence of an event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded under 10 CFR 50.72(b)(3)(ii).
"The Station is preparing an evaluation and repair plan at this time.
"The NRC Resident Inspector has been notified."
"On Monday, October 23, 2017, with PBAPS [Peach Bottom Atomic Power Station] Unit 3 in Mode 3 at the beginning of a refueling outage, personnel entered the drywell to perform an inspection. At approximately 0400 [EDT], leakage was identified on a one-inch diameter instrument line socket weld for the 'B' recirculation pump. Because the leak was misting, the leakage rate could not be quantified. However, Unit 3 reactor coolant unidentified leakage prior to plant shutdown was 0.18 gpm. This line is considered part of the primary coolant pressure boundary.
"This event is being reported as an occurrence of an event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded under 10 CFR 50.72(b)(3)(ii).
"The Station is preparing an evaluation and repair plan at this time.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 53134
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ALEX THORNBURG
HQ OPS Officer: STEVEN VITTO
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ALEX THORNBURG
HQ OPS Officer: STEVEN VITTO
Notification Date: 12/22/2017
Notification Time: 11:09 [ET]
Event Date: 10/23/2017
Event Time: 08:56 [CDT]
Last Update Date: 12/22/2017
Notification Time: 11:09 [ET]
Event Date: 10/23/2017
Event Time: 08:56 [CDT]
Last Update Date: 12/22/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BILLY DICKSON (R3DO)
BILLY DICKSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Defueled | 0 | Defueled |
INVALID ACTUATION OF EMERGENCY DIESEL GENERATOR
"At 0856 [CDT] on October 23, 2017, during the Unit 2 refueling outage, with no fuel in the Reactor Vessel, an unexpected auto start of the Unit 2 Train B Emergency Diesel Generator (D6) occurred when construction electricians inadvertently bumped the plunger for relay 2Sl-20X while working in the relay rack. Relay 2Sl-20X is a slave relay that actuates a light on the control board, starts D6, and starts 22 Residual Heat Removal (RHR) pump on a Safety Injection signal. In this instance, the RHR pump did not start as its control switch was in pull-out. It is expected that the control board light lit for the brief time the relay plunger was depressed, but this could not be confirmed. The D6 actuation resulted in an unexpected annunciator for D6 EMERGENCY GENERATOR SI SIGNAL EMERGENCY START. Operators responded per the alarm response procedure, performed a walk down of running D6 and then performed a shutdown of D6. D6 started and functioned as expected.
"There was no impact on public health and safety.
"This event is being reported as a 60-day telephone notification in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an invalid actuation of an emergency diesel generator."
The NRC Resident Inspector has been notified.
"At 0856 [CDT] on October 23, 2017, during the Unit 2 refueling outage, with no fuel in the Reactor Vessel, an unexpected auto start of the Unit 2 Train B Emergency Diesel Generator (D6) occurred when construction electricians inadvertently bumped the plunger for relay 2Sl-20X while working in the relay rack. Relay 2Sl-20X is a slave relay that actuates a light on the control board, starts D6, and starts 22 Residual Heat Removal (RHR) pump on a Safety Injection signal. In this instance, the RHR pump did not start as its control switch was in pull-out. It is expected that the control board light lit for the brief time the relay plunger was depressed, but this could not be confirmed. The D6 actuation resulted in an unexpected annunciator for D6 EMERGENCY GENERATOR SI SIGNAL EMERGENCY START. Operators responded per the alarm response procedure, performed a walk down of running D6 and then performed a shutdown of D6. D6 started and functioned as expected.
"There was no impact on public health and safety.
"This event is being reported as a 60-day telephone notification in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an invalid actuation of an emergency diesel generator."
The NRC Resident Inspector has been notified.