Event Notification Report for April 19, 2018

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Nebraska Department of Health via email:

"Eagle Distributing of Norfolk, LLC sold their building which contained tritium exit signs to Our Savior Lutheran Church on October 17, 2017. Eagle Distributing did not inform Our Savior Lutheran Church of the General License [GL] responsibility until March of 2018 when the Annual Renewal for GL0595 came overdue. After Our Savior Lutheran Church was informed of the exit signs and their GL responsibility, Our Savior Lutheran Church conducted a search to locate the signs within the building resulting in 3 missing signs. They have no information as to what could have happened or specific dates of their removal."

NE Item Number: NE180003

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

AGREEMENT STATE REPORT - DAMAGED PORTABLE GAUGE

The following was received from the State of Colorado via email:

"The Department [Colorado Department of Public Health and Environment] was notified via phone on 4/19/18 at approximately 1552 MDT. A G Wassenaar's RSO notified the Department that a portable gauge had been run over by a vehicle and the vehicle did not stop. At the time of the phone call, the gauge was broken into multiple pieces and the RSO was about to go out on-site to assess the damage.

"State inspectors are responding immediately as well."

Colorado Event Report ID No.: CO180008

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."

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.

AGREEMENT STATE REPORT - DAMAGED GAUGES

The following information was obtained by the State of Texas via email:

"On April 20, 2018, a consultant for the company called to inform the Agency [State of Texas] that a fire had damaged part of the refinery. The fire happened yesterday, April 19, 2018 around 1700 CDT. The radiation safety officer has been informed and the two are preparing an assessment of the damage. There are 19 gauges in the location of the fire. The fire was located in the allocation unit where phrase fractions are allocated into different hydrocarbon groups for refinement. All but two gauges have been assessed for damage. The two remaining gauges are 1 milliCurie or less in activity and cannot be checked at this time due to safety issues. Once the area is released for entry the gauges will be checked for damage. An update will be provided with gauge identification and correct activity. Updates will be provided in accordance with SA-300 guidelines."

Texas Incident No.: I-9562

AGREEMENT STATE REPORT - LEAKING SOURCE

The following report was received from the State of Florida:

"[The Florida Department of Health / Bureau of Radiation Control] received an email from Florida International University [FIU] reporting a leaking source. On April 19, the RSO [Radiation Safety Officer] opened a cabinet inside CP- 194 and did leak tests on stored sealed sources inside that cabinet. One Ni-63 source (9.4 milliCurie) was contained in a plastic vial with a screw top lid. The RSO removed the plastic vial from the radiation container for one minute to do a swab test, and sent the swab to an approved vendor for analysis. FIU EHS [Environmental Health and Safety] and the RSO were informed that the leak test associated with the Ni-63 source came back with a reading of 0.0119 microCuries (above the max. 0.005 microCurie limit) on May 18th. The RSO removed the radiation container containing the rad source from CP- 194 on May 22nd and moved it to the EHS vault in ACH 4 to await proper disposal. No other contamination was found."

Incident Number: FL18-070

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).