| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/10/2006 - 03/13/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42394 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: CARDINAL HEALTH - WAUWATOSA
Region: 3
City: WAUWATOSA State: WI
County:
License #: 079-1311-01
Agreement: Y
Docket:
NRC Notified By: CHERYL ROGERS
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/08/2006
Notification Time: 11:48 [ET]
Event Date: 02/24/2006
Event Time: 09:30 [CST]
Last Update Date: 03/08/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JULIO LARA (R3)
MICHELE BURGESS (NMSS)
| Event Text WISCONSIN AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION EVENT
The State provided the following information via facsimile:
"On Friday, February 24, 2006 at approximately 9:30 am [CST] a vial of Tc-99m broke in the nuclear pharmacy's dose preparation fume hood. The vial contained about 6 Curies of Tc-99m. The authorized nuclear pharmacist was performing the assay for molybdenum when the vial slipped out of the tongs and fell onto a metal frame that supports the L-block shield. She called over a pharmacy technician who brought absorbent papers to clean up the spill. The papers were placed in a secondary shield for a generator to decay. After clean-up radiation levels were 20 mR/hr in front of the fume hood. Lead sheets were placed on the floor in the immediate vicinity and covered over with cardboard that was taped down to hold the lead in place. The immediate area was posted and access restricted until February 27, 2006. Radiation levels were reduced to 3 mR/hr on February 25, 2006. On Monday, February 27, 2006 radiation levels were background, although a small amount of contamination remained in the hood. Use of the hood resumed on Monday. The lead sheets were taken up from the floor on Tuesday, February 28, 2006. The RSO for the local pharmacy contacted corporate Q & R on Monday, February 27, 2006 to inquire if this event was reportable. Corporate confirmed that a report was required according to HFS 157.13(17)(b)1.b. and also contacted DHFS. Additional information was obtained from the local RSO on March 8, 2006. This event will be followed up by DHFS on the next inspection."
WI Event Report ID #: 33 |
| Power Reactor | Event Number: 42403 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ANTHONY PETRELLI
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/10/2006
Notification Time: 00:58 [ET]
Event Date: 03/09/2006
Event Time: 22:14 [EST]
Last Update Date: 03/10/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JOHN WHITE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 85 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DUE TO LOSS OF CONDENSER VACUUM TURBINE TRIP
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) RPS Actuation (scram) for Nine Mile Point Unit 2 which states 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' On 03/09/2006 at 2214 while operating at approximately 85 % reactor power (coast down to refueling) a condenser low vacuum condition resulted in a turbine trip and a subsequent reactor scram. A loss of sealing steam most probably caused the loss of condenser vacuum and an investigation is in progress. Special Operating procedure N2-SOP-101 C was entered. All control rods inserted [fully] as expected. Condenser vacuum has been stabilized and the main steam isolation valves are open. The plant is stable and recovery actions are in progress."
Decay heat is being removed via the turbine bypass valves to the main condenser. The condensate and feedwater system is in operation maintaining reactor vessel level. The electric plant is in a normal shutdown lineup and there was no effect from this transient on Unit 1.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42404 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: KEITH DUNCAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/10/2006
Notification Time: 14:02 [ET]
Event Date: 03/10/2006
Event Time: 05:00 [CST]
Last Update Date: 03/10/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
CHUCK CAIN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FAILURE OF EMERGENCY EXHAUST SYSTEM DAMPERS
"At 1050 CST on 3/09/2006 the Auxiliary Building ventilation isolation damper, GKD0129, failed a preventive maintenance stroke test as the result of dirt buildup on the damper vanes. The associated Technical Specification action statement, T/S 3.7.13.a, was entered. At 0500 CST on 3/10/2006 mechanical maintenance personnel observed a similar buildup condition on the redundant train damper, GKD0128, which is in series with GKD0129. At 0838 CST on 3/10/2006 approval was given by the Shift Manager to stroke closed GKD0128 to verify Operability. At 0951 CST 3/10/2006 mechanical maintenance personnel observed that GKD0128 damper vanes remained approximately 45 percent open. T/S 3.7.13.b action for two inoperable emergency exhaust system trains inoperable due to inoperable auxiliary building boundary was entered and back dated to 0500 CST 3/10/2006.
"Having both trains of auxiliary building ventilation isolation dampers inoperable could prevent the ability to maintain the pressure boundary necessary to control the release of radioactive material.
"The licensee will notify the Resident Inspector." |
| Power Reactor | Event Number: 42405 | Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TERRY NANCE
HQ OPS Officer: BILL GOTT | Notification Date: 03/11/2006
Notification Time: 06:36 [ET]
Event Date: 03/11/2006
Event Time: 00:30 [CST]
Last Update Date: 03/11/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JAMNES CAMERON (R3)
|
| 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 UNANALYZED CONDITION
"This report is being made pursuant to 10CFR50.72(b)(3)(ii)(B), Degraded or Unanalyzed Condition. During Division 1 Core Standby Cooling System (CSCS) valve replacement work, it was discovered that temporary seismic supports required to maintain this piping within the Safe Shutdown Earthquake (SSE) design envelope were not installed. This condition was discovered during the restoration phase of the maintenance and the requirements for the temporary supports no longer exist. At the time of discovery, the required permanent seismic qualified support system had been re-established. The Division 1 CSCS System is common to both units and circulates lake water from the Ultimate Heat Sink (UHS) to the Division 1 Residual Heat Removal (RHR) heat exchangers, Division 1 Diesel Generator cooler, Division 1 Emergency Core Cooling System (ECCS) area room coolers, Division 1 RHR Pump seal coolers, and the Low Pressure Core Spray (LPCS) motor coolers. During the period with the required seismic supports not installed, both Unit 1 and Unit 2 were in an unanalyzed condition due to the inability of the Division 1 CSCS piping to meet its seismic qualification. A postulated structural failure of the Division 1 CSCS piping during an SSE could affect areas containing redundant equipment due to flooding."
The licensee is investigating the failure to install the supports. The supports were only needed during the maintenance.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42406 | 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: GEORGE HERNEISEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/11/2006
Notification Time: 08:35 [ET]
Event Date: 03/11/2006
Event Time: 01:00 [EST]
Last Update Date: 03/11/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
JOHN WHITE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNIT ENTERED A T.S. REQUIRED SHUTDOWN AFTER DECLARING BOTH CONDENSER OFFGAS RADIATION MONITORS INOPERABLE
"Condenser offgas radiation monitor flow was blocked. Both Offgas Radiation Monitors were affected and out of service. We entered T.S. 3.0.1 - When a Limiting Condition for Operation is not met, within 1 hour action shall be initiated to place the unit in a condition in which the specification does not apply:
"1. Hot Standby within 6 hours.
"2. Hot Shutdown with following 6 hours.
"3. Cold Shutdown with subsequent 24 hours.
"We started to shutdown the Unit at 0100 [hours] on 11 March 2006. Removed blockage from condenser offgas radiation monitors common exhaust and evaluated operability of the condenser offgas radiation monitors. At 0315 [hours] on 11 March 2006, we returned RM-A-5 and RM-A-15 [Condenser Offgas Radiation Monitors] to service and exited T.S. 3.0.1.
"We stopped the power reduction at 0251 [hours] on 11 March 2006 while performing the evaluation on the condenser offgas radiation monitors. We stopped the power reduction at 73% reactor power. We started power escalation to 100% at 0338 [hours] on 11 March 2006."
The blockage was discovered at 2125 hours on 3/10/2006 during rounds by Secondary Plant Operator who noted that the normal 1 SCFM exhaust flow was reading zero flow. During troubleshooting to discover the cause of the blockage, a bluish foreign material was found in the common exhaust piping. An investigation is underway to identify the source of the foreign material.
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 42407 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM HUFFORD
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/12/2006
Notification Time: 09:12 [ET]
Event Date: 03/12/2006
Event Time: 02:17 [EST]
Last Update Date: 03/12/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JOHN WHITE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LLRT TEST IDENTIFIED PIPING PENETRATION WITH EXCESSIVE LEAKAGE
"While performing local leak rate testing [LLRT] during a planned refueling outage, Susquehanna discovered a Type C penetration on Unit 1 with a leak rate of 12,700 sccm. The limit for this penetration, which can bypass secondary containment, is 4,247 sccm or 9 scfh. Even with this leak rate, the combined leak rate for all penetrations and valves subject to Type B and C tests meets the acceptance criteria of 10CFR50 Appendix J, which is 190,744.7 sccm. This condition seriously degrades the condition of the nuclear power plant, including its principal safety barriers, and is reportable in accordance with 10CFR50.72(b)(3)(ii)."
The licensee informed the NRC Resident Inspector. | |