| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/16/2006 - 10/17/2006 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42888 | Facility: SURRY
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ROBERT PORTLOCK
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/07/2006
Notification Time: 18:27 [ET]
Event Date: 10/07/2006
Event Time: 18:01 [EDT]
Last Update Date: 10/16/2006 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
THOMAS DECKER (R2DO)
THEODORE QUAY (NRR)
PETER WILSON (IRD)
MIKE WEBER (NRR)
V. MCREE (R2)
T. BARNES (DHS)
G. KANUPP (FEMA)
R. TURNER (DOE)
N. PYLES (HHS)
CREWS (EPA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL SCRAM DUE TO UNUSUAL NOISE IN TURBINE BUILDING
The main turbine cross-under safety relief valves lifted for no known reason and blew siding off the side of the Unit 2 Turbine building. This siding hit the feeder lines to the A & C Reserve Station Service Transformers (RSSTs). The operator manually scrammed the plant due to swings in steam generator level and unusual noise coming from the turbine building . Unit 2 shutdown currently de-energized A & C Reserve Station Transformers, which effects D & E transfer buses. This also effects 1J bus, which is de-energized, and 1H & 2J buses which are energized with #1 diesel and #3 diesel.
Decay heat removal is being performed thru the SG PORV's and auxiliary feedwater system, with forced cooling from the "B" RCP. Safety related systems are available if required.
Notified USDA (A. Jimenez) in addition to the other agencies already identified.
The licensee notified the NRC Resident Inspector, as well as State and local agencies.
* * * UPDATE ON 10/8/2006 AT 05:45 FROM MIKE CHRIS TO ABRAMOVITZ * * *
The site terminated the Alert at 05:40 due to having the "A" RSST in service with bus 1J being powered from its normal power supply. No damage was found from the displaced siding with the exception of the "C" RSST (which should be repaired around noon). The "C" RSST is currently tagged out for maintenance.
The licensee notified the NRC Resident Inspector, state, and local governments.
Notified: R2DO (Decker), R4DO (Pick), NRR (Dyer, Weber, Quay), IRD (Blount, Wilson), R2 (McCree), DHS (Gray), FEMA (Dunker), DOE (Steve Bailey), EPA (Allison), USDA (Dean Giles), and HHS (Lt. Smith).
* * * RETRACTION ON 10/16/06 AT 1724 FROM L. WHEELER TO M. ABRAMOVITZ * * *
"At 1827 hours on 10/07/06, an Emergency Notification System (ENS) notification was made for an Alert declaration at Surry Power station. The steam discharge from the turbine system safety valves that had lifted caused pieces of siding from the turbine building to dislodge and come in contact with two phases of the overhead bus for the 'A' and 'C' reserve station service transformers (RSST). The basis for the declaration was the Emergency Action Level (EAL) Tab K-11: 'Notification of missile impact causing damage to safety-related equipment or structures'. Upon further review, the RSSTs were determined not to be safely-related equipment. Therefore, the conditions for an Alert emergency did not exist and the notification is being retracted. A notification will be made to the Virginia Department of Emergency Management. This is being reported In accordance with 10 CFR50.72, (b) (2) (xi).
"As noted in EN# 42890, conditions for a Notification of Unusual Event (NOUE) did exist at the time of the Alert notification."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Henson). |
| Power Reactor | Event Number: 42908 | Facility: LACROSSE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] AC (ALLIS CHAMBERS)
NRC Notified By: DAN TESAR
HQ OPS Officer: BILL GOTT | Notification Date: 10/16/2006
Notification Time: 09:13 [ET]
Event Date: 10/16/2006
Event Time: 07:16 [CDT]
Last Update Date: 10/16/2006 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
DAVE PASSEHL (R3)
MICHELE BURGESS (NMSS)
TOM BLOUNT (IRD)
G GRAY (DHS)
M EACHES (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Decommissioned | 0 | Decommissioned | Event Text UNUSUAL EVENT - HIGH AIRBORN PARTICULATE IN THE REACTOR BUILDING
Even though there have been no operations on going over the weekend, airborne activities have increased to above ten times the normal levels. Activity levels were increasing during work processes last week but did not reach abnormally high levels. The licensee is taking air samples and swipe surveys to determine the source. The element of interest is Americium. Workers entering the building are required to wear filter masks.
* * * UPDATE VIA FAX FROM LICENSEE AT 1250 ON 10/16/06 TO M. ABRAMOVITZ * * *
"Conditions at time of incident: SAFSTOR, decommissioning work in progress involving saw-cutting of Upper Control Rod Drive Mechanism (UCRDM) seal inject supply and effluent lines, plasma arc cutting of metal in Reactor Vessel upper cavity, and welding of lifting lugs on Reactor Vessel upper cavity expansion joint structure.
"Description: Thursday afternoon October 12, 2006, air samples of Reactor Building indicated higher levels of Americium-241 (Am-241) than normal. As of Monday morning October 16, 2006, Reactor Building ventilation through HEPA filters had not reduced the level of Am-241 as expected. Unusual Event was declared and investigations commenced to identify source of contamination.
"Immediate evaluation/corrective actions: Upper cavity work was halted Thursday afternoon following the air sample results. It was believed that welding or plasma arc cutting in the upper cavity had created the airborne problem. Air sampling on Friday October 13, 2006, indicated Am-241 levels still remained higher than normal. At that time, all personnel entering the Reactor Building were required to wear respirators. Air sampling continued through the weekend. When Am-241 levels had not decreased to acceptable levels by Monday morning, October 16, 2006, an Unusual Event was declared due to the unexpected nature of the airborne activity, lack of identification of the source of the activity, and activity level being greater than 10 times normal for the nuclide Am-241. Following declaration, the Operations Review Committee (ORC) was convened. Various strategies for identifying the source of the contamination were discussed and established. Surveys were conducted in the Reactor Building basement and the source of the contamination was tentatively identified as effluent from the UCRDM draining that occurred on Thursday morning October 12, 2006. Further analysis and clean-up is in progress."
Notified the R3DO (Skokowski). |
| Power Reactor | Event Number: 42909 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: KEVIN MCLAUGHLIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/16/2006
Notification Time: 11:00 [ET]
Event Date: 10/16/2006
Event Time: 05:20 [EDT]
Last Update Date: 10/16/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
RICHARD BARKLEY (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 FAILURE OF CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION
"At 0520 hours on 10/16/06 with the plant in Mode 6, with containment shutdown purge system in operation and core alterations in progress, a Control Room Operator noted that Main Control Board annunciator L-4 'Safeguard DC Failure [Containment Isolation] CI and [Containment Ventilation Isolation] CVI Logic' was illuminated.
"ITS LCO 3.9.3 c. 2. requires that 'Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either (1) closed by a manual or automatic isolation valve, blind flange, or equivalent, or (2) capable of being closed by an operable Containment Ventilation Isolation System.'
"ITS LCO 3.3.5 Containment Ventilation Isolation Instrumentation Table 3.3.5-1 requires that Function 1, 'Automatic Actuation Logic and Actuation Relays' be operable during core alterations and movement of irradiated fuel assemblies within containment.
"Contrary to the requirements DC power was removed from the Containment Ventilation Logic and Actuation Relays on Friday 10/13/06. On Saturday 10/14/06 reactor vessel head lift was performed. Between Sunday 10/15/06 from 1559 until Monday at 0514 the movement of fuel and core alterations in containment were conducted. All fuel movement and core alterations were stopped at 0514 on 10/16/06."
The licensee notified the NRC Resident Inspector. |
| Hospital | Event Number: 42910 | Rep Org: PETOSKEY CARDIOLOGY
Licensee: PETOSKEY CARDIOLOGY
Region: 3
City: PETOSKEY State: MI
County:
License #: 21-32345-01
Agreement: N
Docket:
NRC Notified By: JAMES CARSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/16/2006
Notification Time: 14:38 [ET]
Event Date: 10/16/2006
Event Time: 08:30 [EDT]
Last Update Date: 10/16/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
RICHARD SKOKOWSKI (R3)
MICHELE BURGESS (NMSS)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text Tc-99m MEDICAL SOURCE LOST PRIOR TO USE
Seven pairs of Tc-99m sources were received in syringes in lead shielding, placed in their holders, and inventoried at 0800. At 0830 one source (15 milliCuries) was found missing. A search was conducted visually and with a radiac. The missing source was not found.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Power Reactor | Event Number: 42912 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RICKY ROBBINS
HQ OPS Officer: JOE O'HARA | Notification Date: 10/16/2006
Notification Time: 23:15 [ET]
Event Date: 10/16/2006
Event Time: 21:26 [CDT]
Last Update Date: 10/16/2006 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
RICHARD SKOKOWSKI (R3)
FREDERICK BROWN (NRR)
THOMAS BLOUNT (IRD)
HOLZ (DHS)
JIM DUNKER (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text UNUSUAL EVENT - IDENTIFIED LEAKAGE GREATER THAN 25 GPM
"At 2126, PBNP Unit 2 had a inadvertent PORV (431C) lift. This was a momentary event, however, a PRT level change of 60 gallons was notified. This event is classifiable per C.U. 1.2 identified leakage greater than 25 GPM on Unit 2."
"This event has been terminated at 2139.
"This event was caused by a momentary loss of power to the PORV controller. Power was immediately restored."
The event was caused when a manually operated breaker (MOB) was inadvertently operated while the licensee was working inside the panels on the "B" train RHR system.
The licensee notified the NRC Resident Inspector, State and local officials. | |