United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for September 21, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/20/2012 - 09/21/2012

** EVENT NUMBERS **


48277 48302 48303 48318 48323 48325 48327 48328

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48277
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT BRINKLEY
HQ OPS Officer: PETE SNYDER
Notification Date: 09/05/2012
Notification Time: 16:35 [ET]
Event Date: 08/22/2012
Event Time: 12:36 [CDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
VINCENT GADDY (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

MISSING FLOOD SEAL

"During flooding walkdowns being performed on August 22, 2012, with the unit at 100 percent power, South Texas Project Unit 2 discovered the potential for water intrusion into the 10' Elevation Electrical Auxiliary Building (EAB) via a 2-inch underground conduit that was found to be missing its flood seal. It has been determined that the missing flood seal compromised the external flood design controls for the EAB. If flooding of the 10 [foot] EAB were to occur as a result of the missing flood seal, the operability of the Train A Engineered Safety Features (ESF) switchgear and the ESF Sequencers for all three Standby Diesel Generators could have been affected. Additionally, the Qualified Display Parameter System process cabinets (which control Auxiliary Feedwater flow and Steam Generator PORVs) and the Auxiliary Shutdown Panel are also located on the 10' Elevation.

"Repairs have been made and the 2-inch conduit is sealed.

"The event is being reported under 10 CFR 50.72(b)(3)(ii)(B) for Unit 2 being in an unanalyzed condition that significantly degraded plant safety, and under 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

* * * RETRACTION FROM JAMES MORRIS TO JOHN KNOKE AT 1658 EDT ON 09/20/12 * * *

"The purpose of this call is to retract the notification made on 09/05/2012, Event Number 48277. Further analysis indicates that water intrusion resulting from the missing 2-inch conduit seal would not have been sufficient to affect the operability of the equipment located on the 10-foot elevation of the Unit 2 Electrical Auxiliary Building. It has been determined that the maximum water depth would not have exceeded 2 inches in depth and all safety related equipment on the 10-foot elevation is greater than 2 inches above the floor, therefore there would be no impact to any safety-related equipment. Accordingly, this event notification is being retracted."

The licensee will notify the NRC Resident Inspector. Notified the R4DO (Geoffrey Miller).

To top of page
Agreement State Event Number: 48302
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: FLINT HILLS RESOURCES CHEMICAL INTERMEDIATES
Region: 3
City: JOLIET State: IL
County:
License #: IL-01337-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/12/2012
Notification Time: 16:26 [ET]
Event Date: 09/11/2012
Event Time: [CDT]
Last Update Date: 09/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE FOUND WITH STUCK SHUTTER

The following information was received from the State of Illinois via email:

"On Tuesday afternoon, the Agency [Illinois Emergency Management Agency] received a call from the RSO for Flint Hills Resources Chemical Intermediates, LLC (IL-01337-01). He called to report a shutter failure of a fixed gauge which he cannot close. The device manufacturer, Ronan Engineering, has been contacted and arrangements are pending for repair of the device. The RSO has isolated the area, posted warning signs and instituted a lock out/tag out procedure for the manway entrance to the vessel in order to prevent exposures which might occur from someone attempting to perform work within the tank that the gauge is located. Area surveys performed show no variations above normal (i.e., less than 1 milliR/h at 1 foot) for when the shutter is open and the unit is in operation. The shutter had last been tested in March with no abnormalities noted. The gauge has not been subjected to any corrosives or solvents or other conditions which exceed the gauge's prototype test conditions.

"The RSO was reminded of the requirement to provide a written report within 30 days of the event and to contact the Agency when the manufacturer was able to perform the site visit to evaluate/repair the device. The Agency considers this matter open pending those additional actions."

The Ronan gauge is model X90-SA1, S/N M7389, contains 24.5 mCi Cs-137.

To top of page
Agreement State Event Number: 48303
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSITY OF PENNSYLVANIA
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0131
Agreement: Y
Docket:
NRC Notified By: JOSEPH M. MELNIC
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/13/2012
Notification Time: 12:05 [ET]
Event Date: 09/11/2012
Event Time: [EDT]
Last Update Date: 09/13/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER NEWPORT (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - PATIENT UNDEREXPOSURE USING YTTRIUM-90 SIR-SPHERES TREATMENT

The following event was received from the Commonwealth of Pennsylvania via facsimile:

"Event type: A medical event (ME) involving the administration of yttrium-90 SIR-Spheres which is reportable under 10 CFR 35.3045(a)(1)(i).

"Notifications: On September 12, 2012, an inspector was performing a reactive inspection for a recent event (PA120026) that occurred on August 23, 2012. During the inspection the licensee reported another similar Sir-Sphere event.

"Event Description: A patient was being treated for disease of the liver with 33.04 millicuries (mCi) of Y-90 and received 25.6 mCi resulting in 77.5% of the intended dose. The treating physician, who also is the referring physician, notified the patient.

"Cause of the Event: Currently under investigation and unknown at this time.

"Actions: No harm to the patient is expected. The Department's reactive inspection occurring on September 11, 2012 incorporated this new event and therefore no new inspection is planned."

PA Report Number: 120030

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

To top of page
Power Reactor Event Number: 48318
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DANIELS
HQ OPS Officer: PETE SNYDER
Notification Date: 09/18/2012
Notification Time: 11:58 [ET]
Event Date: 09/18/2012
Event Time: 10:55 [CDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GEOFFREY MILLER (R4DO)

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

OUTAGE OF PLANT RADIATION MONITORING SYSTEM REMOTE READOUT DUE TO PLANNED MODIFICATION

"On September 18, 2012, power was removed from SCADA A of the Radiation Monitoring System (RMS) to perform a planned system modification. During this period, data for most Unit 1 radiation monitors will not be electronically available in the emergency response facilities and will not be supplied to the Emergency Response Data System (ERDS), if activated. System alarms and data displays will still be available to the plant operators in the Control Room. The expected duration of RMS remote data partial inoperability is approximately 72 hours. The loss of Unit 1 remote readout capability requires compensatory measures to be used for the acquisition of radiological data in the emergency response facilities. These compensatory measures have been communicated to the emergency response organization, Therefore, it is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the portions of the RMS are inoperable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update message will be provided when the RMS is restored."

The NRC Resident has been notified.

* * * UPDATE FROM TONY SIROIS TO JOHN KNOKE AT 1749 EDT ON 09/20/12 * * *

"The Radiation Monitoring System alarms and data displays have been restored to the Comanche Peak Emergency Response Facilities (ERFs) following completion of planned system modifications. The emergency assessment capability of the Comanche Peak ERF have been re-established.

The licensee has notified the NRC Resident Inspector. Notified the R4DO (Geoffrey Miller)

To top of page
Power Reactor Event Number: 48323
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: PHILIP M. NICHOLS
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/20/2012
Notification Time: 11:55 [ET]
Event Date: 09/20/2012
Event Time: 09:23 [EDT]
Last Update Date: 09/20/2012
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):
CHRISTOPHER CAHILL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC SCRAM AND HIGH PRESSURE COOLANT INJECTION SYSTEM INITIATION

"On September 20, 2012 at 0923 EDT, Nine Mile Point Unit 1 experienced an automatic reactor scram due to a turbine trip at power. The cause of the turbine trip is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram.

"Following the automatic scram, the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. At 0924 EDT, RPV level was restored above the HPCI System low level actuation set point and the HPCI System initiation signal was reset. Pressure control was established on the Turbine Bypass Valves, the preferred system. No Electromatic Relief Valves actuated due to this scram.

"Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. One 115kv off site power source (Line 4) is unavailable for planned maintenance at the James A Fitzpatrick Nuclear Power Plant. Both Reserve Station Transformers are in service and being supplied by the other 115kv offsite power source (Line 1). Both Emergency Diesel Generators are operable and in standby. The unit is currently implementing post scram recovery procedures."

The licensee has notified the NRC Resident Inspector. Licensee has notified the state.

To top of page
Power Reactor Event Number: 48325
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: DAVID LEWIS
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/20/2012
Notification Time: 16:15 [ET]
Event Date: 09/20/2012
Event Time: 14:16 [EDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR TRIP DUE TO REACTOR PROTECTION SYSTEM ACTUATION

"On September 20th at 1416 EDT, Three Mile Island automatically tripped due to a flux to flow imbalance as a result of a trip of the 'C' reactor coolant pump. The cause of the trip of the 'C' reactor coolant pump is still under investigation.

"The electrical grid is stable and unit 1 is being supplied by offsite power. All control rods have fully inserted. Decay heat is being removed by main feedwater flow to both steam generators that are exhausting via the normal main condenser cooling loop under manual control. Preliminary evaluation indicates that all plant systems functioned normally following the reactor trip, except for automatic operation of turbine bypass valve control due to failure of the automatic control function to control precisely at setpoint. Three Mile Island remains stable in hot shutdown mode while conducting the post trip review. No radioactive releases were experienced as a result of this event.

"This event is reportable under 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation, and under 10 CFR 50.72 (b)(2)(xi) due to an information release to local officials. Both are four hour reports.

"The licensee notified the NRC Resident Inspector."

The licensee has notified the state and local governments, and will be making a media release.

To top of page
Power Reactor Event Number: 48327
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BALL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/20/2012
Notification Time: 20:47 [ET]
Event Date: 09/20/2012
Event Time: 12:40 [CDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO INOPERABLE SEISMIC MONITORING INSTRUMENTATION

"At 1240 CDT on 9/20/2012, Operations personnel determined that Browns Ferry Nuclear Plant had experienced a loss of assessment capability. The loss of assessment capability identified was due to not having functional seismic monitoring instrumentation during performance of a modification. The loss of seismic monitoring capability was determined to have existed from 8/17/2012 until 9/15/2012.

"The ability to declare an Unusual Event per Emergency Action Level 7.1-U or an Alert per Emergency Action Level 7.1-A could potentially be hampered by the unavailability of the seismic monitoring instrumentation, because the declarations would be based on personnel feeling an earthquake. In addition, the unavailability of the seismic monitoring instrumentation could potentially hamper the operators in determining the magnitude of an earthquake in order to determine if it reached Operating Basis Earthquake levels or Safe Shutdown Earthquake levels. Therefore, this event is being considered reportable as it results in a loss of emergency assessment capability. Compensatory measures were established on 9/15/2012 which restored assessment capability.

"This condition is reportable per 10CFR50.72(b)(3)(xiii). The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 48328
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN LOGAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/21/2012
Notification Time: 01:20 [ET]
Event Date: 09/20/2012
Event Time: 20:35 [CDT]
Last Update Date: 09/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK RING (R3DO)

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

TECHNICAL SUPPORT CENTER VENTILATION INOPERABLE

"At 2035 CDT on 9/20/2012 power was removed from the Technical Support Center ventilation for planned maintenance on the supply breaker and the supply breaker cubicle. At 2109 CDTduring restoration, it was discovered that the breaker for the Technical Support Center ventilation could not be closed.

"The cause for not being able to close the supply breaker is unknown. Troubleshooting is currently in progress and the Technical Support Center ventilation is expected to be returned to service on 09/21/2012.

"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev.2 since this work activity affects an emergency response facility."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, September 21, 2012
Friday, September 21, 2012