Event Notification Report for August 18, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/17/2005 - 08/18/2005
Power Reactor
Event Number: 41927
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: QUENTIN HICKS
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: QUENTIN HICKS
HQ OPS Officer: PETE SNYDER
Notification Date: 08/18/2005
Notification Time: 11:10 [ET]
Event Date: 08/18/2005
Event Time: 09:49 [EDT]
Last Update Date: 08/18/2005
Notification Time: 11:10 [ET]
Event Date: 08/18/2005
Event Time: 09:49 [EDT]
Last Update Date: 08/18/2005
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAYMOND LORSON (R1)
RAYMOND LORSON (R1)
| 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 |
AUTOMATIC SCRAM DUE TO LOSS OF A POWER BOARD
"Unit 1 scrammed from 100% power due to a loss of power board 11 coincident with 1/2 scram present already on RPS channel 12 due to [instrumentation and control] (I&C) testing. A loss of power board 11 causes a loss of 11 RPS trip bus which in turn produces a 1/2 scram. Loss of power board 11 is currently under investigation. In addition during the scram, HPCI injected into the reactor vessel on a turbine trip signal to maintain reactor water level.
"Currently, the reactor is in hot shutdown with reactor water levels being maintained in the normal level band at 74 inches with feedwater in automatic. Reactor pressure is currently 920 psig and being maintained in automatic with turbine bypass valves.
"Plan is to stay in hot shutdown and complete scram recovery procedures."
All control rods fully inserted. No safety relief valves actuated. Electrical busses were being supplied by normal offsite power. Emergency diesel generators are available. The decay heat removal path is currently normal feedwater to the reactor vessel through the turbine bypass valves to the condenser. There was no impact on Unit 2. The licensee is going to suspend any high risk maintenance activities on Unit 2.
The licensee notified the NRC Resident Inspector.
"Unit 1 scrammed from 100% power due to a loss of power board 11 coincident with 1/2 scram present already on RPS channel 12 due to [instrumentation and control] (I&C) testing. A loss of power board 11 causes a loss of 11 RPS trip bus which in turn produces a 1/2 scram. Loss of power board 11 is currently under investigation. In addition during the scram, HPCI injected into the reactor vessel on a turbine trip signal to maintain reactor water level.
"Currently, the reactor is in hot shutdown with reactor water levels being maintained in the normal level band at 74 inches with feedwater in automatic. Reactor pressure is currently 920 psig and being maintained in automatic with turbine bypass valves.
"Plan is to stay in hot shutdown and complete scram recovery procedures."
All control rods fully inserted. No safety relief valves actuated. Electrical busses were being supplied by normal offsite power. Emergency diesel generators are available. The decay heat removal path is currently normal feedwater to the reactor vessel through the turbine bypass valves to the condenser. There was no impact on Unit 2. The licensee is going to suspend any high risk maintenance activities on Unit 2.
The licensee notified the NRC Resident Inspector.
Hospital
Event Number: 41928
Rep Org: LANCASTER GENERAL HOSPITAL
Licensee: LANCASTER GENERAL HOSPITAL
Region: 1
City: LANCASTER State: PA
County:
License #: 37-11866-04
Agreement: N
Docket:
NRC Notified By: TONY MONTAGNESE
HQ OPS Officer: BILL HUFFMAN
Licensee: LANCASTER GENERAL HOSPITAL
Region: 1
City: LANCASTER State: PA
County:
License #: 37-11866-04
Agreement: N
Docket:
NRC Notified By: TONY MONTAGNESE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/18/2005
Notification Time: 14:08 [ET]
Event Date: 08/18/2005
Event Time: 10:00 [EDT]
Last Update Date: 08/18/2005
Notification Time: 14:08 [ET]
Event Date: 08/18/2005
Event Time: 10:00 [EDT]
Last Update Date: 08/18/2005
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):
RAYMOND LORSON (R1)
TOM ESSIG (NMSS)
RAYMOND LORSON (R1)
TOM ESSIG (NMSS)
MEDICAL EVENT
The licensee reports that a patient was scheduled to receive five Gamma Knife treatments to a single tumor in the head. Two treatments were successfully administered. Prior to the third treatment, it was determined that the shield "jaws' on the Gamma Knife were stuck closed and the Knife was considered inoperable. Consequently, the patient did not receive the final three prescribed treatments.
The licensee has requested repairs on the Gamma Knife from an authorized service representative. The licensee believes that a microphone clip, used to communicate with the patient while under treatment, may have fallen into the Gamma Knife and jammed the "jaws."
The licensee plans to continue treatment of the patient pending repair to the Gamma Knife.
The licensee also planned to notify the State of Pennsylvania.
The licensee reports that a patient was scheduled to receive five Gamma Knife treatments to a single tumor in the head. Two treatments were successfully administered. Prior to the third treatment, it was determined that the shield "jaws' on the Gamma Knife were stuck closed and the Knife was considered inoperable. Consequently, the patient did not receive the final three prescribed treatments.
The licensee has requested repairs on the Gamma Knife from an authorized service representative. The licensee believes that a microphone clip, used to communicate with the patient while under treatment, may have fallen into the Gamma Knife and jammed the "jaws."
The licensee plans to continue treatment of the patient pending repair to the Gamma Knife.
The licensee also planned to notify the State of Pennsylvania.
Power Reactor
Event Number: 41931
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/18/2005
Notification Time: 19:03 [ET]
Event Date: 08/18/2005
Event Time: 14:40 [CDT]
Last Update Date: 08/18/2005
Notification Time: 19:03 [ET]
Event Date: 08/18/2005
Event Time: 14:40 [CDT]
Last Update Date: 08/18/2005
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):
KENNETH RIEMER (R3)
KENNETH RIEMER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE CORE SPRAY SYSTEM INOPERABLE
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. During a scheduled 24 hour surveillance run of the 1B diesel generator, with the diesel generator paralleled to its associated Bus 143, an electrical fault occurred in the Division 3 AC system. This resulted in a trip of the normal System Auxiliary Feed breaker ACB 1432 to the bus. The diesel generator was manually tripped when it was subsequently identified that its associated cooling water pump was not running. With the 1B diesel generator tripped, the Division 3 AC system is de-energized. The consequence is a loss of the Unit 1 High Pressure Core Spray System. High Pressure Core Spray is a single train system that performs a safety function, and therefore, loss of the system is reportable as an 8 hour ENS notification under SAF 1.8.
"The required actions of Technical Specification 3.5.1 for the High Pressure Core Spray System were entered on 8/18/05 at 14:40 when the system was made inoperable. All other Emergency Core Cooling Systems are operable at this time. The High Pressure Core Spray system is also unavailable, and On Line Risk for Unit 1 is Yellow. The system has been quarantined, and an investigation is currently in progress to determine the cause of the electrical fault."
Unit 2 is not affected by this event, and Unit 1 is in a 14 day LCO to repair the EDG.
The licensee notified the NRC Resident Inspector.
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. During a scheduled 24 hour surveillance run of the 1B diesel generator, with the diesel generator paralleled to its associated Bus 143, an electrical fault occurred in the Division 3 AC system. This resulted in a trip of the normal System Auxiliary Feed breaker ACB 1432 to the bus. The diesel generator was manually tripped when it was subsequently identified that its associated cooling water pump was not running. With the 1B diesel generator tripped, the Division 3 AC system is de-energized. The consequence is a loss of the Unit 1 High Pressure Core Spray System. High Pressure Core Spray is a single train system that performs a safety function, and therefore, loss of the system is reportable as an 8 hour ENS notification under SAF 1.8.
"The required actions of Technical Specification 3.5.1 for the High Pressure Core Spray System were entered on 8/18/05 at 14:40 when the system was made inoperable. All other Emergency Core Cooling Systems are operable at this time. The High Pressure Core Spray system is also unavailable, and On Line Risk for Unit 1 is Yellow. The system has been quarantined, and an investigation is currently in progress to determine the cause of the electrical fault."
Unit 2 is not affected by this event, and Unit 1 is in a 14 day LCO to repair the EDG.
The licensee notified the NRC Resident Inspector.