Event Notification Report for February 25, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/24/2011 - 02/25/2011
EVENT NUMBERS
4664146643466444771946655
Power Reactor
Event Number: 46641
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN WEISSINGER
HQ OPS Officer: JOE O'HARA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN WEISSINGER
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 11:48 [ET]
Event Date: 02/25/2011
Event Time: 09:10 [EST]
Last Update Date: 02/25/2011
Notification Time: 11:48 [ET]
Event Date: 02/25/2011
Event Time: 09:10 [EST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WILLIAM COOK (R1DO)
WILLIAM COOK (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL SCRAM DUE TO RECIRCULATION PUMP TRIP
"Limerick Unit 2 was manually scrammed from 100% power on 2/25/11 at 0910 EST in accordance with plant procedure OT-112 'Recirculation Pump Trip', when both the '2A' and '2B' recirculation pumps tripped. Preliminary indication of why the recirculation pumps tripped is due to main generator stator water coolant runback. The cause of the stator water coolant runback is currently under investigation at this time.
"All control rods inserted as required. No ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is currently in HOT SHUTDOWN maintaining normal Reactor Water Level with Feedwater in service."
Primary plant pressure and temperature is 600 psia and approximately 485 degrees F. All unit safety related equipment is operable and available, if needed. The decay heat path is via turbine bypass valves. There is no affect on Unit 1. The licensee informed Montgomery, Chester, Burks Counties and the Pennsylvania Emergency Management Agency (PEMA). The licensee intends to issue a press release.
The NRC Resident Inspector has been notified.
"Limerick Unit 2 was manually scrammed from 100% power on 2/25/11 at 0910 EST in accordance with plant procedure OT-112 'Recirculation Pump Trip', when both the '2A' and '2B' recirculation pumps tripped. Preliminary indication of why the recirculation pumps tripped is due to main generator stator water coolant runback. The cause of the stator water coolant runback is currently under investigation at this time.
"All control rods inserted as required. No ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is currently in HOT SHUTDOWN maintaining normal Reactor Water Level with Feedwater in service."
Primary plant pressure and temperature is 600 psia and approximately 485 degrees F. All unit safety related equipment is operable and available, if needed. The decay heat path is via turbine bypass valves. There is no affect on Unit 1. The licensee informed Montgomery, Chester, Burks Counties and the Pennsylvania Emergency Management Agency (PEMA). The licensee intends to issue a press release.
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 46643
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TRICAN WELL SERVICE
Region: 4
City: SPRINGTOWN State: TX
County:
License #: GLA G02259
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOE O'HARA
Licensee: TRICAN WELL SERVICE
Region: 4
City: SPRINGTOWN State: TX
County:
License #: GLA G02259
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 19:03 [ET]
Event Date: 02/25/2011
Event Time: 16:15 [CST]
Last Update Date: 02/25/2011
Notification Time: 19:03 [ET]
Event Date: 02/25/2011
Event Time: 16:15 [CST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
VIVIAN CAMPBELL (R4DO)
ROBERT LEWIS (FSME)
VIVIAN CAMPBELL (R4DO)
ROBERT LEWIS (FSME)
MISSING SHUTTER HANDLE ON BERTHOLD MODEL LB 8010 PORTABLE DENSITY GAUGE
On 2/22/11, Trican Well Service was preparing to use the portable gauge at a well jobsite in De Soto Parish, Louisiana when they discovered the gauge was missing its shutter handle. The crew stopped work, took surveys to ensure the shutter was fully closed, and placed the gauge out of service until a repair can be performed. The device is a Berthold Model LB 8010 serial number 10074 portable density gauge used in well servicing operations. The device contains 20 milliCuries of Cs-137, serial number 014808. The crew does not know when the handle became detached. They searched the jobsite for the handle but were unsuccessful in recovering it. The device is in the custody of the licensee. Berthold has been contacted and plans to repair the gauge on March 1, 2011.
Texas Incident No. I-8825
On 2/22/11, Trican Well Service was preparing to use the portable gauge at a well jobsite in De Soto Parish, Louisiana when they discovered the gauge was missing its shutter handle. The crew stopped work, took surveys to ensure the shutter was fully closed, and placed the gauge out of service until a repair can be performed. The device is a Berthold Model LB 8010 serial number 10074 portable density gauge used in well servicing operations. The device contains 20 milliCuries of Cs-137, serial number 014808. The crew does not know when the handle became detached. They searched the jobsite for the handle but were unsuccessful in recovering it. The device is in the custody of the licensee. Berthold has been contacted and plans to repair the gauge on March 1, 2011.
Texas Incident No. I-8825
Power Reactor
Event Number: 46644
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: JOE O'HARA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 23:12 [ET]
Event Date: 02/25/2011
Event Time: 20:27 [EST]
Last Update Date: 02/25/2011
Notification Time: 23:12 [ET]
Event Date: 02/25/2011
Event Time: 20:27 [EST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM COOK (R1DO)
WILLIAM COOK (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 99 | Power Operation |
UNIT 1 HPCI INOPERABLE DUE TO STEAM LEAK
"At 2027 EST, Unit 1 HPCI system was declared inoperable due to a steam leak on HV155F002, HPCI Steam Supply Inboard Isolation Valve. Engineering evaluation determined that the valve actuator will not close the valve fully under design basis conditions, due to the impingement of steam from the valve packing region on the valve stem. The penetration flow path has been isolated and the outboard isolation valve has been deactivated.
"HPCI is a single train ECCS safety system, This event results in the loss of an entire safety function which requires an 8 hour ENS notification in accordance with 10CFR50.72(b)(3)(v) and the guidance provided under NUREG-1022, rev. 2.
"There are no other ECCS systems presently out of service."
Unit 1 is in a 14 day LCO 3.5.1. EDG's are operable, and offsite power is normal. There is no increase in plant risk, and the licensee will notify the Pennsylvania Emergency Management Agency (PEMA).
The NRC Resident Inspector has been notified.
"At 2027 EST, Unit 1 HPCI system was declared inoperable due to a steam leak on HV155F002, HPCI Steam Supply Inboard Isolation Valve. Engineering evaluation determined that the valve actuator will not close the valve fully under design basis conditions, due to the impingement of steam from the valve packing region on the valve stem. The penetration flow path has been isolated and the outboard isolation valve has been deactivated.
"HPCI is a single train ECCS safety system, This event results in the loss of an entire safety function which requires an 8 hour ENS notification in accordance with 10CFR50.72(b)(3)(v) and the guidance provided under NUREG-1022, rev. 2.
"There are no other ECCS systems presently out of service."
Unit 1 is in a 14 day LCO 3.5.1. EDG's are operable, and offsite power is normal. There is no increase in plant risk, and the licensee will notify the Pennsylvania Emergency Management Agency (PEMA).
The NRC Resident Inspector has been notified.
Non-Agreement State
Event Number: 47719
Rep Org: CAMDEN CLARK MEMORIAL HOSPITAL
Licensee: CAMDEN CLARK MEMORIAL HOSPITAL
Region: 1
City: PARKERSBURG State: WV
County: WOOD
License #: 47-09772-02
Agreement: N
Docket:
NRC Notified By: DAN BERKLEY
HQ OPS Officer: ERIC SIMPSON
Licensee: CAMDEN CLARK MEMORIAL HOSPITAL
Region: 1
City: PARKERSBURG State: WV
County: WOOD
License #: 47-09772-02
Agreement: N
Docket:
NRC Notified By: DAN BERKLEY
HQ OPS Officer: ERIC SIMPSON
Notification Date: 03/05/2012
Notification Time: 16:17 [ET]
Event Date: 02/25/2011
Event Time: 12:00 [EST]
Last Update Date: 12/03/2012
Notification Time: 16:17 [ET]
Event Date: 02/25/2011
Event Time: 12:00 [EST]
Last Update Date: 12/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
KEVIN O'SULLIVAN (FSME)
LAWRENCE DOERFLEIN (R1DO)
KEVIN O'SULLIVAN (FSME)
DOSE RECEIVED BY PROSTATE LESS THAN PRESCRIBED
At the request of NRC Region I, Camden-Clark Memorial Hospital reassessed records from a prostate radioactive seed implantation procedure that had been performed on February 25, 2011. The record review indicated that the patient had received roughly 80 percent of the prescribed dose.
"The effect on the patient has been minimal as the desired response was achieved. The long term effect will be under constant follow-up.
"The entire implant process will be reviewed with special attention to real time seed placement and subsequent thirty day image evaluation with respect to NRC regulatory guidelines.
"The attending physician, based on medical judgment, felt that notifying the patient would be harmful. The patient is under the care of oncologic physicians and will be followed appropriately as per his disease type."
* * * UPDATE AT 1636 EST ON 12/03/12 FROM DAN BERKLEY TO S. SANDIN * * *
The licensee is updating the report with the following information:
"That (1) the dose received by the target was less than 80% of the prescribed dose and (2) a small volume of tissue outside of, and adjacent to, the treatment site received a dose that was greater than 10 Gy and more than 50% greater than the prescribed dose to that location."
The licensee discussed this update with R1 (Weidner). Notified R1DO (Jackson) and FSME Events Resource via email.
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.
At the request of NRC Region I, Camden-Clark Memorial Hospital reassessed records from a prostate radioactive seed implantation procedure that had been performed on February 25, 2011. The record review indicated that the patient had received roughly 80 percent of the prescribed dose.
"The effect on the patient has been minimal as the desired response was achieved. The long term effect will be under constant follow-up.
"The entire implant process will be reviewed with special attention to real time seed placement and subsequent thirty day image evaluation with respect to NRC regulatory guidelines.
"The attending physician, based on medical judgment, felt that notifying the patient would be harmful. The patient is under the care of oncologic physicians and will be followed appropriately as per his disease type."
* * * UPDATE AT 1636 EST ON 12/03/12 FROM DAN BERKLEY TO S. SANDIN * * *
The licensee is updating the report with the following information:
"That (1) the dose received by the target was less than 80% of the prescribed dose and (2) a small volume of tissue outside of, and adjacent to, the treatment site received a dose that was greater than 10 Gy and more than 50% greater than the prescribed dose to that location."
The licensee discussed this update with R1 (Weidner). Notified R1DO (Jackson) and FSME Events Resource via email.
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.
Part 21
Event Number: 46655
Rep Org: FISHER CONTROLS INTERNATIONAL
Licensee: FISHER CONTROLS INTERNATIONAL
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DENNIS SWANSON
HQ OPS Officer: JOHN KNOKE
Licensee: FISHER CONTROLS INTERNATIONAL
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DENNIS SWANSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/04/2011
Notification Time: 12:53 [ET]
Event Date: 02/25/2011
Event Time: 00:00 [CST]
Last Update Date: 03/04/2011
Notification Time: 12:53 [ET]
Event Date: 02/25/2011
Event Time: 00:00 [CST]
Last Update Date: 03/04/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
KENNETH RIEMER (R3DO)
MALCOLM WIDMANN (R2DO)
PART 21 GROUP
KENNETH RIEMER (R3DO)
MALCOLM WIDMANN (R2DO)
PART 21 GROUP
PART 21 - ERROR IN VALVE BODY DRAWING
The purpose of this Fisher Information Notice (FIN) is to alert Duke Energy that as of February 25, 2011, Fisher Controls International LLC became aware of the possibility of a situation which may affect the performance of the applicable equipment provided to McGuire Nuclear Station. Specifically, an error was discovered on valve body drawing V112298, when, during a revision process on Revision B of the drawing, a dimension was omitted that set the depth of the valve shaft bearing bore. This error resulted in a greater possible variation of bearing position in the valve shaft bore. If the error was large, the valve could not be assembled which was not the case for these valves. The valves assembled without incident and passed the operational testing, including a seat leakage test, with no anomalies. In the case that the bearing position error was slight, it is possible that the seal and disc could experience more wear than normal and increased leakage would result. Because these valves are equipped with manual operators, Fisher expects that these valves will not be cycled enough to experience any of the potential problems described above.
This equipment included NPS 4, Class 150, Fisher Type A11 Butterfly Valve Assemblies equipped with Fisher Leverlock Manual Actuators. The NPS 4, A11 is a butterfly valve that uses internal bearings (located on either side of the disc) to provide a radial wear surface for shaft rotation and also serve as a centering system for the disc in the waterway. Centering of the disc is accomplished with a wear surface on the end of the bearings adjacent to the side of the disc. Lateral positioning of the disc is accomplished by controlling the length of the bearings and the depth of the bored holes in the body that accept the bearings.
Fisher has revised the drawings to ensure that this issue is corrected.
The purpose of this Fisher Information Notice (FIN) is to alert Duke Energy that as of February 25, 2011, Fisher Controls International LLC became aware of the possibility of a situation which may affect the performance of the applicable equipment provided to McGuire Nuclear Station. Specifically, an error was discovered on valve body drawing V112298, when, during a revision process on Revision B of the drawing, a dimension was omitted that set the depth of the valve shaft bearing bore. This error resulted in a greater possible variation of bearing position in the valve shaft bore. If the error was large, the valve could not be assembled which was not the case for these valves. The valves assembled without incident and passed the operational testing, including a seat leakage test, with no anomalies. In the case that the bearing position error was slight, it is possible that the seal and disc could experience more wear than normal and increased leakage would result. Because these valves are equipped with manual operators, Fisher expects that these valves will not be cycled enough to experience any of the potential problems described above.
This equipment included NPS 4, Class 150, Fisher Type A11 Butterfly Valve Assemblies equipped with Fisher Leverlock Manual Actuators. The NPS 4, A11 is a butterfly valve that uses internal bearings (located on either side of the disc) to provide a radial wear surface for shaft rotation and also serve as a centering system for the disc in the waterway. Centering of the disc is accomplished with a wear surface on the end of the bearings adjacent to the side of the disc. Lateral positioning of the disc is accomplished by controlling the length of the bearings and the depth of the bored holes in the body that accept the bearings.
Fisher has revised the drawings to ensure that this issue is corrected.