| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/29/2011 - 05/02/2011 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46782 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: LUKE HEDGES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/25/2011
Notification Time: 16:06 [ET]
Event Date: 04/25/2011
Event Time: 09:50 [EDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
WAYNE SCHMIDT (R1DO)
|
| 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 SINGLE TRAIN CHARGING PUMP DECLARED INOPERABLE
"During normal operation with 23 Charging pump in service, an unusual sound was noticed by Operations. All other parameters were normal for the pump, but 21 Charging pump was placed in service as a precaution. Subsequent investigation was unable to conclusively identify the source of the unusual sound and a lower-than-expected crankcase oil pressure was observed on a maintenance run. Therefore, 23 Charging Pump was declared inoperable. This is the alternate safe shutdown pump responsible for inventory control for remote shutdown. NRC guidance indicates that a loss of a single train system not credited in accident analysis is reportable when identified in LCD 3.3.4 'Remote Shutdown.'"
The licensee notified the NRC Resident Inspector and the New York Public Service Commission.
* * * UPDATE AT 1408 EDT ON 04/29/11 FROM MIKE BURNEY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"Indian Point Unit 2 is retracting the 8-hour non-emergency notification made on April 25, 2011, at 1606 EDT (EN #46782). The notification on April 25, 2011, reported a loss of a single train system identified in LCO 3.3.4 'Remote Shutdown' (SSFF [safety system functional failure]) as a result of declaring the 23 Charging Pump (CP) inoperable. The 23 CP exhibited unusual sound during operation. Because the 23 CP is credited in Technical Specification (TS) 3.3.4 for Remote Shutdown, the inoperable condition was determined to be a loss of safety function. The TS 3.3.4 Allowed Outage Time (AOT) for inoperable conditions is 30 days. In accordance with recent NRC guidance provided to Indian Point for loss of single train systems, although not credited in the accident analysis and specified in Technical Specification 3.3.4, this condition is reportable as a SSFF.
"Subsequent investigations determined that the documented condition does not pose a challenge to the operability of the 23 CP. The noise was associated with the normal operation of the charging pump internal check valves. This condition is a long term issue that does not affect the current operation of the pump. The pump was in operation with no abnormal parameters noted at the time the noise was noted. No SSFF occurred."
The licensee will inform the NRC Resident Inspector. Notified R1DO (Schmidt). |
| Agreement State | Event Number: 46787 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: STORK TESTING AND METALLURGICAL CONSULTING
Region: 4
City: HOUSTON State: TX
County:
License #: 00299
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: PETE SNYDER | Notification Date: 04/26/2011
Notification Time: 09:58 [ET]
Event Date: 04/26/2011
Event Time: [CDT]
Last Update Date: 04/26/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - DAMAGED RADIOGRAPHY CAMERA GUIDE TUBE
The following information was provided via email:
"On April 20, 2011 the Agency was notified that a radiography source had failed to retract to the shielded position because the material being radiographed had fallen on the guide tube and crimped it. Following company procedures, the Radiation Safety Officer was notified and the area was restricted to avoid public or excessive employee exposures.
"Several entries were made to shield the source and allow an authorized individual to straighten the crimped portion of the tube within tolerable radiation fields. After several other trips to place lead shot on the source, four additional trips were required before the crimp in the source tube was straightened and the source was retracted into the shielded position.
"The source retriever and his assistance received nominal radiation exposures during the procedure and no public exposures reportedly occurred. No violations were cited."
Texas Incident #: I-8838. |
| Agreement State | Event Number: 46789 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: IRISNDT INC MATRIX
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: L04769
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 04/27/2011
Notification Time: 09:30 [ET]
Event Date: 04/25/2011
Event Time: 22:00 [CDT]
Last Update Date: 04/27/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - INABILITY TO RETRACT SOURCE INTO RADIOGRAPHY CAMERA
"On April 26, 2011, the Agency [Texas Department of State Health Services] was informed by a licensee that on April 25, 2011, at 2200 [CDT] hours a QSA model 880D radiography camera containing 92 curies of Iridium (Ir) 192 fell from a 16 inch pipe it was sitting on. The camera landed on the guide tube side of the camera crimping the guide tube near the connection of the guide tube to the camera. This prevented the radiographer from retracting the source into the camera. The radiographers used a hammer and were able to remove the crimp from the guide tube enough to retract the source. No individual involved with the event exceeded an exposure limit based on their electronic dosimetry readings. The radiographer doing most of the source retraction work, radiographer 'A', had an electronic dosimeter reading of 1.5 Rem. The second radiographer, radiographer 'B', received 200 milliRem. The licensee stated that the exposure to the radiographer 'A' was high due to the inability to place shielding over the source due to the crimp being so close to the camera. The personnel dosimetry of the two individuals involved have been sent to the licensee's dosimetry processor for reading. The licensee stated that the camera would be leak tested on April, 26, 2011. The licensee is investigating the event. Additional information will be provided as it is received in accordance with Reporting Material Events SA-300."
Texas Incident Report # I-8839 |
| Power Reactor | Event Number: 46790 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM REED
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/27/2011
Notification Time: 13:06 [ET]
Event Date: 04/27/2011
Event Time: 10:30 [EDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DEBORAH SEYMOUR (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 | 92 | Power Operation | 92 | Power Operation | Event Text LOSS OF EMERGENCY SIRENS DUE TO LOSS OF ELECTRIC POWER
"At approximately 1030 EDT on April 27, 2011, [Sequoyah Nuclear Plant] received notification from TVAs Operations Duty Specialist that >30% of offsite sirens are not functional resulting in a 'major loss' of offsite [automatic] public notification [capabilities]. The loss of offsite sirens is due to loss of electrical power caused by severe thunderstorms and high winds in the area. Thirty five sirens are not functioning (32 sirens are considered 30%). Efforts are in place to restore offsite sirens to service.
"At 1044 EDT on April 27, 2011, power was restored to 2 offsite sirens leaving 33 offsite sirens not functional.
"At 1050 EDT on April 27, 2011, TVA's Operations Duty Specialist made a notification to Tennessee Emergency Management Agency (TEMA) and Hamilton County Emergency Response."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JEFF EPPERSON TO DONG PARK ON 4/29/11 AT 0514 EDT * * *
Sequoyah Nuclear Plant reported that 28 of 108 sirens are not functional (26%) which is below the 'major loss' of offsite automatic public notification capabilities threshold.
The licensee has notified the Tennessee Emergency Management Agency (TEMA) and Hamilton County Emergency Response. The licensee will notify the NRC Resident Inspector.
Notified R2DO (Seymour). |
| Agreement State | Event Number: 46792 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: NORTHWESTERN MEMORIAL HOSPITAL
Region: 3
City: CHICAGO State: IL
County:
License #: IL-01037-02
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/27/2011
Notification Time: 17:30 [ET]
Event Date: 04/27/2011
Event Time: [CDT]
Last Update Date: 04/27/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANN MARIE STONE (R3DO)
JOSEPHINE PICCONE (FSME)
| Event Text AGREEMENT STATE REPORT - UNDERDOSE DUE TO CLUMPING IN THE DELIVERY DEVICE
The following information was obtained from the State of Illinois via email:
"The Radiation Safety Officer at Northwestern Memorial Hospital contacted the Illinois Emergency Management Agency on April 26th and reported that a medical event involving radiolabled Theraspheres had occurred. The treating physician attempted to perform radioembolization by placing the Y-90 microspheres in the treatment site using the appropriate Nordion Microsphere Delivery Device. However, increased resistance was felt in the administration syringe and a clump of microspheres developed between the needle injector assembly and the microcatheter connection during the initial bolus flush. Administration was halted as soon as the microsphere flow was slowed and a clump was visualized. Following a second attempt to complete the flush, the microspheres began layering within the outlet tubing. Further flushing of the system with saline did not alter the position of the remaining microspheres. The procedure was halted. Analysis of the system showed that a significant amount of the original dose had not been delivered as intended to the right hepatic lobe of the liver. Approximately 80 percent of the dose was not administered as a result of the failure. The primary cause of this incident is due to the clumping of the microspheres. However, the reason for the clumping is unknown."
The intended dose of Y-90 was 59.4 mCi (2198.8 Mbq) for an exposure of 9750 rad (97.5 Gy).
The administered dose was 22.7 mCi (839.9 Mbq) for an exposure of 3760 rad (37.6 Gy).
Illinois Report Number: IL11049 |
| Power Reactor | Event Number: 46795 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/27/2011
Notification Time: 19:05 [ET]
Event Date: 04/27/2011
Event Time: 18:00 [CDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DALE POWERS (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text EMERGENCY SIRENS INTERMITTENTLY INOPERABLE DUE TO UPGRADING
"Fort Calhoun Station is improving (upgrading) the emergency siren system. This evening during the upgrade the sirens will be inoperable for a short period between 1830 and 2400 today. Fort Calhoun will inform the HOO when the sirens are returned to operation following this evenings maintenance."
The licensee notified the states of Nebraska and Iowa and local authorities in both states of the siren outage.
* * * UPDATE FROM JOHN FICKLE TO DONG PARK AT 0210 EDT ON 4/28/11 * * *
The emergency siren system maintenance was complete and all sirens were restored to service at 0010 CDT on 4/28/11. The licensee notified the states and local authorities.
Notified R4DO (Powers).
* * * UPDATE FROM ERIK MATZKE TO CHARLES TEAL AT 1236 EDT ON 4/28/11 * * *
"Fort Calhoun Station is improving (upgrading) the emergency siren system. Today during the upgrade, the sirens will be inoperable for a short period between 1130 CDT and 1210 CDT today. Fort Calhoun will inform the HOO when the sirens are returned to operation following this maintenance."
Notified R4DO (Powers), State and local government.
* * * UPDATE FROM ERIK MATZKE TO CHARLES TEAL AT 1251 EDT ON 4/28/11 * * *
The emergency siren system maintenance was complete and all sirens were restored to service at 1150 CDT on 4/28/11. The licensee notified the states and local authorities.
* * * UPDATE FROM ERIK MATZKE TO CHARLES TEAL AT 1415 EDT ON 4/28/11 * * *
"Continuing maintenance on the sirens determined that they are not responding correctly. Troubleshooting is in progress. There is not an estimated time to return the sirens to service at this time. Emergency planning personnel have been contacted and contingency actions are in place. The station will contact the HOO when the issue is resolved."
Notified R4DO (Powers).
* * * UPDATE FROM ERIK MATZKE TO CHARLES TEAL AT 1529 EDT ON 4/28/11 * * *
The emergency siren system maintenance was complete and all sirens were restored to service at 1529 CDT on 4/28/11. The licensee notified the states and local authorities.
Notified R4DO (Powers).
* * * UPDATE FROM ERIK MATZKE TO DONG PARK AT 0848 EDT ON 4/29/11 * * *
"Fort Calhoun Station is improving (upgrading) the emergency siren system. Today during the upgrade, the sirens are anticipated to be inoperable for an hour or two during the period between 0755 [CDT] and 1000 [CDT] today. The emergency planning staff has been informed and compensatory measures are in place. Fort Calhoun will inform the HOO when the sirens are returned to operation following this maintenance."
The licensee notified the states and local authorities, as well as the NRC Resident Inspector.
Notified R4DO (Powers).
* * * UPDATE FROM ERIK MATZKE TO CHARLES TEAL AT 1201 EDT ON 4/29/11 * * *
The emergency siren system maintenance was complete and all sirens were restored to service at 1030 CDT on 4/29/11. The licensee notified the states and local authorities.
Notified R4DO (Powers). |
| Power Reactor | Event Number: 46801 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/29/2011
Notification Time: 07:26 [ET]
Event Date: 04/28/2011
Event Time: 23:38 [CDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO LOSS OF POWER FROM A DIESEL GENERATOR
"At 2338 [CDT] on 04/28/2011, with Browns Ferry Nuclear Unit 1 and Unit 2 in Mode 4, Browns Ferry Nuclear Plant, performed a shutdown of the Unit 1/2 Emergency Diesel Generator 'C,' due to an oil leak coming from its governor causing voltage and frequency fluctuations. Following securing of the Unit 1/2 Diesel Generator 'C,' the 4kV Shutdown Board 'C,' which was being powered by DG 'C,' de-energized. This resulted in a loss of power to the 1B RPS, causing a Primary Containment Isolation System (PCIS) actuation and the automatic initiation of the three trains of Standby Gas and 1 train of CREV [Control Room Emergency Ventilation System]. The PCIS isolation (Group 2) also caused a loss of Shutdown Cooling on Unit 1 which was restored at 0025 [CDT] 04/29/2011 .
"In addition, the loss of power to the 4kV Shutdown Board 'C.' also caused the loss of 2B RHR Pump, leading to a momentary suspension of shutdown cooling to Unit 2. Shutdown cooling was immediately restored to Unit 2 using the 2D RHR Pump at 2342 [CDT].
"The general containment isolation signals affecting containment isolation valves in more than one system is reportable as an 8 hour notification to the NRC IAW 10CFR50.72(b)(3)(iv)(A), as 'Any event or condition that results in a valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'
"There were no new Technical Specification LCO's entered as a result of this event.
"This is also reportable as 60 day written report lAW 10CFR50.73(a)(2)(iv).
"The NRC Resident [Inspector] has been notified of this event.
"This event was entered into the licensee's Corrective Action Program as SR# 361382." |
| Power Reactor | Event Number: 46802 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/29/2011
Notification Time: 12:42 [ET]
Event Date: 04/29/2011
Event Time: 08:52 [CDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DALE POWERS (R4DO)
JOHN THORP (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text TRITIUM DETECTED IN UNIT 2 TURBINE BUILDING SUMP
"On 4/28/2011, Grand Gulf Nuclear Station Unit 2 turbine building sump samples indicated tritium presence. The Unit 2 turbine building is an abandoned, partially constructed building. Follow-up review and investigation confirmed that water from Unit 2 turbine building sump had been pumped to the environment through installed sump pumps and piping connected between the sumps and roof drains on the Unit 2 turbine building. The release has been terminated by turning off the sump pumps located in the Unit 2 turbine building. Site procedures require notification of off-site agencies, therefore the NRC is being notified in accordance with 10 CFR 50.72(b)(2)(xi)."
The NRC Resident Inspector has been informed. The state will be informed. |
| Power Reactor | Event Number: 46803 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/29/2011
Notification Time: 13:29 [ET]
Event Date: 04/29/2011
Event Time: 11:00 [EDT]
Last Update Date: 04/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANN MARIE STONE (R3DO)
JOHN THORP (NRR)
JEFFERY GRANT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION DUE TO FATALITY OF A CONTRACT EMPLOYEE
"On April 29, 2011, at approximately 1100 hours, a contract employee was found unresponsive in a vehicle, off the road, inside the Perry Nuclear Power Plant owner controlled area. At 1120 hours, it was confirmed by the Perry Fire Department that the individual was deceased. Notification has been made to the Lake County Sheriffs department and the Lake County Coroner. The death does not appear to be work related or the result of an accident. A preliminary diagnosis by the coroner is the individual suffered a heart attack. The Lake County Coroner is conducting a routine investigation into the death.
"A press release is not planned at this time. The individuals name has not yet been released pending notification of next-of-kin. A notification to OSHA per 29CFR1904.39 will be made for this event.
"The plant is currently in MODE 5 (Refuel) for a refueling outage. This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as an event or situation, related to the health and safety of the public or on-site personnel, for which notification to other government agencies has been or will be made. Such an event may include an on-site fatality. The NRC Senior Resident Inspector has been notified." | |