| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/29/2016 - 03/30/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51813 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: HCA HEALTH SERVICES OF OKLAHOMA
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: OK-21035-01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: VINCE KLCO | Notification Date: 03/22/2016
Notification Time: 11:07 [ET]
Event Date: 01/22/2016
Event Time: 12:00 [CDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - CONTAMINATION FOUND ON SHIPMENT
The following report was excerpted from an Oklahoma Department of Environmental Quality via email:
"On January 22, 2016 the RSO [Radiation Safety Officer] reported that a package received by the University of Oklahoma Health Science Center pharmacy (OK-03176-04MD) was found to have 2,118,858 cpm of removable contamination. The outside of the package was surveyed at 30 mR/hr, the reading at 1 meter was 0.12 mR/hr. The contaminant was identified as Tc-99m and was confined to the outside of the package. The package contained a number of empty unit dose syringes in lead pigs and had been returned from HCA Health Services of Oklahoma which administers the University of Oklahoma Medical Center. The package was transported by the pharmacy."
Refer to NRC Event #51661. |
| Power Reactor | Event Number: 51827 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: PAUL SALGADO
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/29/2016
Notification Time: 14:06 [ET]
Event Date: 03/29/2016
Event Time: 11:23 [CDT]
Last Update Date: 03/29/2016 | 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):
VINCENT GADDY (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 35 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM DUE TO TURBINE TRIP
"A Reactor Scram occurred at 1123 CDT on 03/29/2016 from 35% CTP [core thermal power]. The cause of the Scram appears to be a Turbine Generator trip. The station's procedures, '05-S-01-EP-2 RPV [Reactor Pressure Vessel] Control, 05-1-02-I-1 Reactor Scram ONEP [Off Normal Event Procedure] and 05-1-02-l-2 Turbine Generator Trip ONEP,' were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF [engineered safety feature] power occurred. No ECCS [emergency core cooling systems] initiation signals were reached and no ESF or Diesel Generator initiations occurred. All control rods fully inserted. MSIVs [main steam isolation valves] remained open, no SRVs [safety relief valves] lifted, and no containment isolation signals were generated.
"Currently, reactor water level is being maintained by the Condensate and Feedwater System in normal band and reactor pressure and temperature are being maintained by the Reactor Water Cleanup System. The main condenser is available. There are no challenges to Primary or Secondary Containment at this time.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 51828 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MASON
HQ OPS Officer: RICHARD SMITH | Notification Date: 03/29/2016
Notification Time: 16:31 [ET]
Event Date: 03/28/2016
Event Time: 19:00 [EDT]
Last Update Date: 03/29/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVID AYRES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Defueled | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF POWER TO METEOROLOGICAL TOWER
"At approximately 1900 EDT on March 28, 2016, an unplanned loss of retail power to the McGuire Meteorological tower occurred. This loss of power impacted communication between the Meteorological tower and the control room, which resulted in a major loss of emergency assessment capability. Compensatory measures existed within the site's emergency planning procedures to obtain meteorological data from the National Weather Service. Meteorological information could have been provided via the emergency notification system to the NRC operations center.
"Power was restored at 2245 EDT on March 28, 2016.
"The NRC Resident Inspector has been notified. There was no impact to the public." |
| Power Reactor | Event Number: 51829 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: OVIDIO RAMIREZ
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/29/2016
Notification Time: 17:04 [ET]
Event Date: 03/29/2016
Event Time: 16:45 [EDT]
Last Update Date: 03/29/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JAMES DWYER (R1DO)
SCOTT MORRIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Defueled | 0 | Defueled | Event Text BAFFLE BOLT INDICATIONS IDENTIFIED DURING INSERVICE INSPECTION
"This is a non-emergency report. Indian Point Unit 2 is shut down for a scheduled refueling outage and is performing an industry required MRP-227-A inspection of the reactor vessel internals. During this inspection, Entergy identified baffle/former bolts with either visual anomalies or ultrasonic indications. All vessel internal examinations have been successfully completed with no anomalies other than the baffle/former bolts. Entergy will be developing a repair plan that will be implemented prior to startup. The unit is in a safe and stable condition. No leakage was detected as a result of this condition.
"On March 29, 2016, this event was determined to be reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B), since the as-found conditions were not previously analyzed.
"Entergy is planning a press release to communicate this condition to our stakeholders. Therefore this is also being reported under 10 CFR 50.72(b)(2)(xi) since a news release is planned.
"The NRC Resident Inspector has been informed."
The licensee will notify State and local government agencies as appropriate. |
| Power Reactor | Event Number: 51830 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/30/2016
Notification Time: 02:13 [ET]
Event Date: 03/29/2016
Event Time: 22:56 [EDT]
Last Update Date: 03/30/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JAMES DWYER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE
"On March 29, 2016 at 2256 [EDT], Secondary Containment Zone 2 (Unit 2 Reactor Building) differential pressure lowered to 0.0 [inches] WG [water gauge] due to a failed closed discharge damper on the in service Zone 2 exhaust fan. Required differential pressure per SR 3.6.4.1.1 could not be maintained. Zone 2 ventilation was restored by starting the standby Zone 2 exhaust fan. Zone 2 differential pressure recovered to [greater than] 0.25 [inches] WG at 2321 hours. Zone 3 (Unit 1&2 Reactor Buildings) ventilation remained in service and stable. Zone 1(Unit 1 Reactor Building) ventilation remained in service however it is not required in this mode of Operation.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."
The licensee has notified the NRC Resident Inspector. | |