| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/19/2018 - 04/20/2018 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 53325 | Rep Org: UNITED STATES NAVY
Licensee: UNITED STATES NAVY
Region: 1
City: State: VA
County:
License #: 45-23645-01NA
Agreement: Y
Docket:
NRC Notified By: LINO FRAGOSO
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/11/2018
Notification Time: 11:38 [ET]
Event Date: 04/05/2018
Event Time: 14:35 [EDT]
Last Update Date: 04/18/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
DON JACKSON (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text LOST RADIOACTIVE MATERIAL
"A Marine Corps CH-53 helicopter crashed around 1453 PDT on 5 April 2018 at the outlying landing field of Naval Air Facility El Centro, California. This helicopter carries seven in-blade-inspection-systems (IBIS), one per blade, and each one carries a strontium-90 source with an activity of 0.5 milliCuries. The U.S. Navy was able to retrieve five of the IBIS, but two of them were not located after several surveys of the aircraft and the surrounding area. The U.S. Navy is reporting those two sources as lost for a total 1 milliCurie of strontium-90."
The Licensee has notified NRC Region 1 (Seeley) and (Elliott).
* * * UPDATE FROM L.L. FRAGOSO (VIA EMAIL) TO HOWIE CROUCH AT 1242 EDT ON 4/12/18 * * *
"The sixth strontium-90 source has been found buried under the fuselage wreckage. That leaves only one strontium-90 source missing for a total of 0.5 mCi lost."
Notified R1DO (Jackson) and NMSS Events Notification (email).
* * * UPDATE FROM L.L. FRAGOSO (VIA EMAIL) TO ANDREW WAUGH AT 0902 EDT ON 4/18/18 * * *
"The last report was made in error. Upon evaluation of the sixth IBIS (buried underneath a gear box), they found no source pin, hence we still have two missing IBIS sources. Personnel will be surveying the area in the next couple of days in the hope of finding the two missing sources."
Notified R1DO (Lilliendahl) and NMSS Events Notification (email).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 53347 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICH ROWE
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/19/2018
Notification Time: 20:00 [ET]
Event Date: 04/19/2018
Event Time: 11:52 [CDT]
Last Update Date: 04/19/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH RIEMER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text UNDERVOLTAGE ACTUATION OF THE ENGINEERED SAFETY FEATURE BUS
"On Thursday, April 19, 2018 at 1152 CDT, a valid actuation of Engineered Safety Feature (ESF) Bus 141 Undervoltage (UV) Relay occurred. At the time, Braidwood Station Unit 1 was performing a pre-planned Bus 141 Undervoltage Actuation Surveillance, initiating the 1A Emergency Diesel Generator (EDG) to emergency start and sequence loads on the UV signal. Following the 1A EDG solely supplying electrical power to Bus 141, the EDG lost voltage resulting in an unplanned UV actuation of the ESF Bus 141. Subsequently, operators restored power to ESF Bus 141 via crosstie of the Unit 2 offsite power source. Shutdown cooling was maintained throughout the event as the 1B Residual Heat Removal train was unaffected by the actuation.
"This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) for 'Any event or condition that results in valid actuation of any of the systems listed...', specifically 10 CFR 50.72(b)(3)(iv)(B)(8) for the 'Emergency ac electrical power systems, including: emergency diesel generators (EDGs)...'.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 53348 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: KEVIN BROOKS
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/19/2018
Notification Time: 23:41 [ET]
Event Date: 04/19/2018
Event Time: 21:07 [EDT]
Last Update Date: 04/19/2018 | 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):
JON LILLIENDAHL (R1DO)
WILLIAM GOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 8 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO TURBINE ISSUE
"While performing a turbine startup, a turbine control anomaly caused a steam generator level transient. The rise in steam generator level above the setpoint caused the turbine to automatically trip. The high steam generator level of 73 percent caused a feedwater isolation signal at 2107 EDT, which also tripped both Main Boiler Feed Pumps. The tripping of the Main Boiler Feed Pumps auto started the motor driven Aux Boiler Feed Pumps 21 and 23.
"The reactor was manually tripped at 2108 EDT in accordance with AOP-FW-1 Loss of Main Feedwater. All control rods inserted. Electrical power is being provided from offsite via the Station Aux Transformer. Decay heat removal is being provided via the Atmospheric Dump Valves. An investigation into the cause of the turbine control anomaly is underway. The NRC Resident Inspector has been notified."
The event did not have an affect on Unit 3 and there is no primary to secondary leakage. |
| 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: 04/20/2018 | 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." | |