| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
5/8/2018 - 5/9/2018 ** EVENT NUMBERS ** |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53355 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN GALLAGHER
HQ OPS Officer: DAVID AIRD | Notification Date: 04/22/2018
Notification Time: 02:34 [ET]
Event Date: 04/21/2018
Event Time: 21:52 [EDT]
Last Update Date: 05/09/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| 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 | Event Text BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE
"On April 21, 2018 at 2152 EDT, Watts Bar Nuclear Plant (WBN) Unit 1 entered TS [Technical Specifications] LCO [Limiting Condition for Operation] 3.0.3 due to both trains of the Residual Heat Removal System (RHRS) becoming inoperable. During surveillance testing, the gas void values on Emergency Core Cooling System (ECCS) piping common to both trains did not meet acceptance criteria. This caused both RHRS trains to become inoperable. Operations subsequently vented the RHRS to meet the acceptance criteria and exited TS LCO 3.0.3 at 2222 EDT. More frequent surveillances will be conducted to monitor gas void volumes while additional analysis is being performed to determine corrective actions."
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM ANTHONY PATE TO DONALD NORWOOD AT 1310 EDT ON 5/9/2018 * * *
"This event is being retracted. The initial report was based on a conservative acceptance criteria for gas accumulation adopted on April 19, 2018 when it was determined that the previously used acceptance criteria for gas accumulation in the ECCS was non-conservative. Additional analysis has subsequently been performed and determined that a higher gas accumulation acceptance criteria does not challenge operability. With a void of less than the acceptance criteria, in the event of ECCS actuation, the system piping support loads will remain within structural limits and the piping system will remain operable. Therefore, both trains of Unit 1 RHRS were operable and the previously reported 10 CFR 50.72(b)(3)(v)(B) event is being retracted.
"The NRC Resident Inspector has been informed of this event retraction."
Notified R2DO (Ehrhardt). |
| Agreement State | Event Number: 53369 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SLIDELL MEMORIAL HOSPITAL
Region: 4
City: SLIDELL State: LA
County:
License #: LA-0783-L02, AI 2970
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/30/2018
Notification Time: 12:34 [ET]
Event Date: 04/12/2018
Event Time: 00:00 [CDT]
Last Update Date: 04/30/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - WRONG RADIOPHARMACEUTICAL USED
The following is information received via e-mail:
"April 19, 2018, [the licensee] called to inquire if one of his facilities had a 'Recordable Event' or if the facility had a 'Reportable Medical Event.' The report and attachments were left in a voice mail at 8:18 pm [CDT]. The event occurred under the [Slidell Memorial Hospital] SMH Therapeutic and Diagnostic Radioactive Material License, LA-0783-L02. The event involved 5.4 mCi Tc-99m-Myoview administered to a patient who was scheduled for a lung scan utilizing [approximately] 5.4 mCi Tc-99m-MAA. The technologist depended on the unit dose for 'STAT' used to be MAA and did not verify the unit dose label. This medical event occurred on 04/12/2018.
"The technologist states that a Myoview cardiac dose was in a pig labelled MAA for a lung scan. The pharmacy pulled the dose records, verified the bar coding and determined the technologist was at error.
"[The licensee] provided dose calculations for the heart scan dose utilizing 5.4 mCi Tc-99m-Myoview as 0.224 rad effective dose equivalent and highest organ dose of 0.972 rad to the wall of the gallbladder.
"There were corrective actions [to] retrain the technologist in patient dose verification prior to injection and request their pharmacy change their label fonts to magnification and bolding the unit dose labels. The referring physician and the patient were notified of the error.
"LDEQ [Louisiana Department of Environmental Quality] considers this incident still open and subject to investigation to determine if this event was caused by the facility personnel or if it is an error caused by the pharmacy personnel."
Louisiana Event Report ID No.: LA-180007, T 184299 |
| Agreement State | Event Number: 53370 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ALPHA TESTING INCORPORATED
Region: 4
City: DALLAS State: TX
County:
License #: L 03411
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/30/2018
Notification Time: 14:18 [ET]
Event Date: 04/29/2018
Event Time: 05:30 [CDT]
Last Update Date: 05/02/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
ILTAB (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL)
CNSNS (MEXICO) (FAX) | | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the state of Texas via email:
"On April 30, 2018, the licensee reported that sometime during the overnight hours of April 28-29, 2018, a Humboldt model 5001 moisture density gauge had been stolen from the back of a company vehicle. The licensee's technician had taken the vehicle with gauge home [to Arlington, TX], contrary to company policy, and had left the gauge chained with locks in the truck. The source rod handle was locked with a padlock. At 0530 [CDT] on April 29th, he discovered the chains had been cut and the gauge stolen. Local law enforcement was notified and the licensee has checked the surrounding area. The licensee will begin checking local pawn shops. More information will be provided as it is obtained in accordance with SA-300.
"Device: Humboldt Model 5001 - SN: 2821
Sources: Americium-241 - 40 milliCuries - SN: 0379CX; Cesium-137 - 10 milliCuries - SN: NJ-04061"
TX Incident #: 9566
* * * UPDATE ON 5/2/2018 AT 1452 EDT FROM KAREN BLANCHARD TO DONG PARK * * *
The following was received via e-mail:
"This gauge was recovered today and is being returned to the licensee."
Notified R4DO (Azua), ILTAB, NMSS Events Notification, and Mexico via 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 |
| Agreement State | Event Number: 53372 | Rep Org: WA OFFICE OF RADIATION PROTECTION
Licensee: INTERMOUNTAIN MATERIAL TESTING
Region: 4
City: RICHLAND State: WA
County:
License #: I0578
Agreement: Y
Docket:
NRC Notified By: JON NAPIER
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/30/2018
Notification Time: 19:21 [ET]
Event Date: 04/27/2018
Event Time: 16:30 [PDT]
Last Update Date: 04/30/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
CNSC (CANADA) (FAX) | | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST PORTABLE GAUGE
The following information was obtained from the state of Washington via email:
"Today, April 30, 2018, the Washington State Department of Health Radioactive Materials Section was notified of a lost portable gauge. The gauge owner, Intermountain Materials Testing (WA RadMat licensee I0578), notified the Emergency Response Duty Officer at 10:15 am [PDT] about the lost gauge. The company RSO was notified of the incident by an employee earlier today. The employee determined the gauge (CPN MC3 S/N M300405776) was missing at approximately 2:35 pm [PDT] Friday, April 27, 2018. This gauge has a 10 mCi (370MBq) Cs-137 source and 50 mCi (1.85 GBq) Am-241 source. The employee searched for the gauge until 4:30 pm [PDT] before he notified the local Richland, WA Police Department. The gauge was presumed to be left on the ground at a job site near the intersection of Queensgate Dr. and Gala Way in Richland, WA, because it was determined to not be in its storage location at a different job site. This incident has been given the Incident ID WA-18-015 and is reportable under 10 CFR 20.2201(a)(1)(ii) and is a 30 day reportable event. Follow up will be supplied as needed."
Washington State Incident Number WA-18-015
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 |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53392 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: STEVEN VITTO | Notification Date: 05/08/2018
Notification Time: 01:39 [ET]
Event Date: 05/07/2018
Event Time: 23:00 [CDT]
Last Update Date: 06/27/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
BINOY DESAI (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNANALYZED CONDITION
"On May 7, 2018 at 1041 CDT, Unit 1 performed an RCS (reactor coolant system) leakrate procedure that calculated an unidentified RCS leakrate of 0.202 gpm. The leak source investigation concluded at 2150 that the packing for the charging flow control valve (FCV) was the source of the RCS leakage when it was bypassed, which isolated the leakage. A second RCS leakrate calculation was performed after the charging flow control valve was isolated which calculated an acceptable leakrate of 0.00 gpm.
"The packing leakage from the charging flow control valve represented leakage external to containment which would result in a greater that 5 Rem dose projection to control room personnel during accident conditions which does not satisfy the GDC19 criteria described in Technical Specification Bases 3.7.10. Therefore the control room emergency filtration system would not be able to fulfill its design function resulting in an unanalyzed condition.
"This condition is being reported pursuant to 10CFR50.72(b)(3)(ii) for a 'condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety'.
"The packing leak from the charging flow control valve will remain isolated until repaired under work order SNC944374."
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/2018 * * *
"Retraction - There was sufficient margin in the analysis of record to account for the increased leakage in the charging flow control valve that was not known at the time of reporting. Doses at the site boundary and in the Main Control Room would have remained less than the legal limits had a Loss of Coolant Accident occurred based on plant conditions at the time."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Michel). |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53393 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DOUGLAS HOBSON
HQ OPS Officer: DAN LIVERMORE | Notification Date: 05/08/2018
Notification Time: 10:38 [ET]
Event Date: 05/08/2018
Event Time: 01:39 [CDT]
Last Update Date: 06/27/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
BINOY DESAI (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text CONTAINMENT LEAK RATE GREATER THAN TECH SPEC
"On May 8, 2018 at 0139 Central Daylight Time, Farley Nuclear Plant Unit 1 declared containment inoperable due to total containment leak rate greater than technical specifications. The 1B containment cooler had seat leakage of approximately 30 gallons per minute from a service water drain valve.
"Though the containment cooler service water supply is not tested per the Appendix J program, a loss of the containment barrier is possible under accident conditions.
"The service water flow path to the 1B containment cooler has been isolated to exit the condition."
The licensee will notify the NRC resident inspector.
* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/18 * * *
"During the time of the leakage reported in event notification 53393 the system was under administrative control. The containment isolation valves for the 1B containment cooler were closed as restoration of the containment cooler was still in progress following the outage. With the system isolated, operations had identified a 50 drop per minute (dpm) leak downstream of a service water drain valve to the 1B containment cooler. To quantify the leak, operations removed the downstream pipe cap and piping to better measure the leak under system pressure. Upon opening the service water containment isolation valves the leak rate was measured at 30 gpm. Operations re-closed the service water containment isolation valves per the pre-briefed contingency actions. It was determined that the service water drain valve (a ball valve) was not properly seated. This was all performed with operations personnel on station in the containment and in the Main Control Room. At no time were the containment isolation valves degraded. Following closure of the containment isolation valves they were also powered down to prevent inadvertent opening."
The licensee notified the NRC Resident Inspector.
Notified R2DO (Michel). | |