| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
6/4/2018 - 6/5/2018 ** EVENT NUMBERS ** |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53349 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES BROESCHE
HQ OPS Officer: THOMAS KENDZIA | Notification Date: 04/20/2018
Notification Time: 00:55 [ET]
Event Date: 04/19/2018
Event Time: 19:44 [EDT]
Last Update Date: 06/05/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ALAN BLAMEY (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 UNANALYZED CONDITION RELATED TO EMERGENCY CORE COOLING GAS ACCUMULATION ACCEPTANCE CRITERIA
"On April 19, 2018 at 1944 EDT, Watts Bar Nuclear Plant (WBN) determined that a preliminary analysis shows current acceptance criteria for gas accumulation in the WBN Unit 1 and Unit 2 Safety Injection System (SIS) and Residual Heat Removal System (RHRS) discharge piping may be non-conservative. The surveillances that check void values and allow venting of the systems are to be performed utilizing conservative criteria at more frequent intervals to ensure gas void volumes remain under acceptable limits. Additional analysis is being performed to determine final actions.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 6/5/18 AT 0801 EDT FROM DEAN BAKER TO ANDREW WAUGH* * *
"This event is being retracted. The original report was made as a result of errors found in the gas accumulation analysis performed for WBN, such that the analysis in use might be non-conservative. WBN has performed additional analyses related to gas accumulation and determined that both the Safety Injection and Residual Heat Removal systems remained operable and would have been able to perform their safety functions during the past three years. Therefore, this event was not an unanalyzed condition that significantly degrades plant safety.
"The NRC Resident Inspector has been notified."
Notified the R2DO (Ernstes). |
| Agreement State | Event Number: 53427 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ALTER METAL RECYCLING
Region: 3
City: GREEN BAY State: WI
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: MEGAN SHOBER
HQ OPS Officer: OSSY FONT | Notification Date: 05/25/2018
Notification Time: 18:04 [ET]
Event Date: 05/23/2018
Event Time: 00:00 [CDT]
Last Update Date: 05/31/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - FOUND SOURCE
The following information was received via E-mail:
"On May 23, 2018, a scrap yard identified a radioactive source in an outgoing load of waste intended for a landfill. The radioactive source is one inch long and approximately one-half inch in diameter. The Wisconsin Department of Health Services responded to the scrap yard on May 25, 2018, and measured a maximum exposure rate of 210 mR/hr on contact with the source. The source was confirmed to not be leaking. There are no markings or numbers on the source, and isotope identification is pending. It is not known how long the scrap yard was in possession of the source. The source is now in secured storage at the scrap yard. Additional updates will be provided as information about the source and possible original device become available."
Wisconsin Event Report ID No.: WI180008
* * * UPDATE FROM KRISTA KUHLMAN TO DONALD NORWOOD AT 1524 EDT ON 5/31/2018 * * *
The following information was received via E-mail:
"On May 31, 2018, the department performed additional characterization of the source at the scrap yard with assistance from the EPA. It has been determined that it is a Ba-133 source, with an activity between 350 - 500 microCuries. The department has not been able to determine the origin of the source. It will continue to work with the scrap yard to determine the proper disposal path."
Notified R3DO (Cameron) and NMSS Events Notification E-mail group. |
| Power Reactor | Event Number: 53443 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACOB EILERTSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/04/2018
Notification Time: 14:00 [ET]
Event Date: 06/04/2018
Event Time: 09:20 [CDT]
Last Update Date: 06/04/2018 | 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):
RICHARD SKOKOWSKI (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP ON LOWERING STEAM GENERATOR WATER LEVEL
"At 0920 CDT, Braidwood Unit 1 reactor was manually tripped due to lowering steam generator water levels following a trip of the 1C main feedwater pump. The cause of the 1C main feedwater pump trip is unknown at this time and is under investigation.
"Both trains of Braidwood Unit 1 auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.
"All systems responded as expected. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in standby and all safety systems available. There is no impact to Unit 2.
"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8-hr. notification."
All rods inserted into the core during the trip. Concerning the relief valves momentarily lifting and reseating, there is no known primary-to-secondary leakage.
The licensee has notified the NRC Resident Inspector. | |