| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/07/2008 - 03/10/2008 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | General Information or Other | Event Number: 43857 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: KIMBERLY-CLARK, INC.
Region: 3
City: MARINETTE State: WI
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: CHERYL ROGERS
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/20/2007
Notification Time: 16:45 [ET]
Event Date: 12/05/2007
Event Time: [CST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ERIC DUNCAN (R3)
ABY MOHSENI (FSME)
| Event Text WISCONSIN AGREEMENT STATE REPORT - LEAKING TRITIUM EXIT SIGN
The State provided the following information via facsimile:
"The licensee reported the discovery of a broken tritium exit sign on December 5, 2007, during an inspection. The sign had been damaged at some unknown previous date. The licensee had collected exit signs for disposal. A worker recalled having difficulty removing a sign and prying it off the wall. The frame broke and pieces fell to the floor. He also recalls sweeping up the pieces, including broken tubes and placing in normal trash. The unbroken tubes were collected, and the sign reassembled. The sign is currently bagged and stored in a secured storage area, pending disposal by a contractor.
"DHFS intends to investigate. Staff will be present when the contractor arrives to wipe test and package all the exit signs for disposition."
The licensee notified the state on December 19, 2007 via telephone and facsimile.
WI Event Report ID No.: 070030
* * * UPDATE FROM RASHID SALIKHDJANOV TO HOWIE CROUCH @ 1637 EST ON 03/07/08 * * *
"On December 20, 2007, Kimberly-Clark Corporation notified the DHFS [Department of Health and Family Services] of a damaged tritium exit sign. According to the licensee, the damage occurred on an unknown previous date during a collection of exit signs with tritium and the damage was not discovered until December 05, 2007. All collected exit signs were placed in secure locked storage room pending disposal. Licensee arranged with a contracted waste disposal company for disposal of the signs.
"During an investigation of the event on January 15-16, 2008, a DHFS inspector reconstructed the event and interviewed the worker who damaged the tritium exit sign. The employee indicated that the damage happened in August 2006. He recalled having difficulty removing the sign and eventually had to pry it off the wall. When this was done the sign frame broke and various pieces fell to the ground. The pieces, including broken tubes, were swept up and placed in the normal trash. The broken tubes were collected and the sign reassembled. The damaged sign was placed in a plastic bag and turned in with the remaining signs that had been removed that day. The employee did not report the incident other than the frame was damaged during removal. A dose assessment performed by DHFS, indicated that the maximum uptake to the worker was 68 mCi of tritium (less than required 5 times the ALI of 80 mCi). DHFS wipe tests were performed at 3 points on the floor, where pieces of the exit sign, including broken tubes, would have fallen and one area ~20 feet above the floor. Results of the survey indicated that maximum contamination was 3970 dpm/100 cm [squared] on the floor.
"The contracted waste disposal company wipe tested all signs and storage area contamination prior to disposal. Results of survey indicated that maximum contamination did not exceed 40dpm/100 cm [squared]. All exit signs, including the broken item, were shipped out on January 16, 2008. Licensee intends to contract with a consultant company to perform additional wipe tests of the accident area and to clean up the area if it is necessary. DHFS will close this event once the area has been decontaminated. Since the dose estimate was less than the 5 times the ALI, DHFS retracts the report to NRC Operations Center."
Notified R3DO (Pelke) and FSME EO (Flanders). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43892 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES M. KURAS
HQ OPS Officer: KARL DIEDERICH | Notification Date: 01/10/2008
Notification Time: 20:34 [ET]
Event Date: 01/10/2008
Event Time: 18:12 [CST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RUSSELL BYWATER (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 VOIDING DISCOVERED IN HIGH HEAD AND INTERMEDIATE HEAD SI COMMON SUCTION
"Both centrifugal charging pumps and both safety injection pumps [were] declared inoperable due to 5% to 7% voiding identified in a portion of common suction piping. [The] pumps were inoperable for 27 minutes. [The] line was vented to remove [the] void and [the] pumps restored to operable. (These pumps are the High Head and Intermediate Head Emergency Core Cooling Pumps.)"
The source of the voiding is not understood and is under investigation. All systems functioned as required.
R4DO (Bywater) notified.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM PRESTON LAWSON TO P. SNYDER AT 1733 ON 3/7/08 * * *
Wolf Creek engineering evaluated the effects of the voids found in the common suction piping for the high head and the intermediate head emergency core cooling pumps. The pumps and their systems would have been able to perform their intended safety functions.
The licensee will notify the NRC Resident Inspector.
Notified R4DO (Cain). |
| General Information or Other | Event Number: 44029 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: IRON & METAL
Region: 1
City: GOLDSBORO State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RANDY CROWE
HQ OPS Officer: JOE O'HARA | Notification Date: 03/04/2008
Notification Time: 17:18 [ET]
Event Date: 02/18/2008
Event Time: 10:00 [EST]
Last Update Date: 03/04/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN CARUSO (R1)
PATRICE BUBAR (FSME)
| Event Text AGREEMENT STATE REPORT - DENSITY GAUGE CONTAINING CS-137 INADVERTENTLY THROWN AWAY AS SCRAP WAS LATER RECOVERED
"Brief Description of Incident
"Railroad [RR] car arrived at Nucor Steel [in South Carolina] at 10AM on February 18, 2008. The RR car set off the exploranium detection equipment, so to ensure accuracy the RR car was passed through 4 times. Radiation measurement of RR car #JOSX 1771 was 25 microR/hr [which is] five times background (5 microR/hr). Notified SC-DHEC -Radiation Waste [DELETED] who further contacted NC DENR. [DELETED] from SC Nucor Steel was given CRCPD approval (see SC-NC 08-01) for return trip of rail car to point of origin, Iron & Metal Goldsboro, N.C.
"The Rail Car numbered JOSX 1771 returned from Nucor Steel Darlington, SC on February 28, 2008. [NC-DENR] arrived at their location in Goldsboro on February 29, 2008 in the AM, as requested and took reading from the rail car and found only one hot spot (35 microR/hr - Ludlum 19) that was located on the left side of the railcar toward the upper middle portion of container. The item in question was located.
"I annotated what was legible and it is the following: Model number 7062 BP; Serial Number 18317; Manufacturing Date 1984; Type and Amount of Isotope Cs-137, 100 mCi. Highest Readings 10.5 mR/hr on contact with Ludlum 19 and Identifinder.
"Gauge SN 18317 was retrieved from Iron & Metal Goldsboro with chain of custody letter signed by all parties, then taken to storage room at the GAF Materials Corp. where three other gauges are now kept.
GAF Materials has custody of the damaged gauge and will package it and ship it to a suitable vendor for repair.
N.C. Incident Number 08-09.
The State of North Carolina informed Region 1(Jim Cotton). |
| General Information or Other | Event Number: 44031 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: MARSHFIELD CLINIC MINOCQUA CENTER
Region: 3
City: MINOCQUA State: WI
County:
License #: 141-1162-01
Agreement: Y
Docket:
NRC Notified By: LEONA DEKOCK
HQ OPS Officer: PETE SNYDER | Notification Date: 03/05/2008
Notification Time: 14:53 [ET]
Event Date: 01/10/2008
Event Time: [CST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PATTY PELKE (R3)
MICHELE BURGESS (FSME)
ILTAB (e-mail) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST IODINE-125 BRACHYTHERAPY SEEDS
"A permanent prostate seed implant was performed on 12/21/07. Following this case there were 18 unused seeds remaining. Unused seeds are kept in the original shielded container provided by the vendor and stored in the nuclear medicine hot lab until returned by the Radiation Safety Officer (RSO) to the vendor for ultimate storage and disposal. Unused seeds are normally returned once each quarter by the RSO.
"In this case, however, the nuclear medicine technologist transferred the 18 seeds from the shielded container to a lead-lined radioactive waster bin for the storage of dry-solid active waste such as gloves, absorbent pads, etc. potentially contaminated with Tc-99m. This waste bin is not used for medical waste such as syringes, sharps, etc.
"The dry-solid radioactive waste bins are held for decay-in-storage. Based on the preliminary information and a review of the radioactive waste disposal log, this particular bag was surveyed and disposed of on either 1/10/08 or 2/6/08. Since they use two bins and hold for radioactive decay until the other is full, it is not clear at this time as to which bag was disposed in the regular trash. Discovery of the lost material was through inquiries by the RSO concerning how many unused seeds were available this quarter for return. If the seeds were disposed of in the regular trash on 1/10/08, the activity lost would be 5.03 milliCuries; if disposed of in the regular trash on 2/6/08, the activity lost would be 3.68 milliCuries.
"The possible disposition of the licensed radioactive material at this time is the landfill. A detailed written description of the incident will be submitted within 30 days.
"The State of Wisconsin plans to investigate this incident on an upcoming inspection."
Wisconsin Event Report ID: WI080004
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. |
| General Information or Other | Event Number: 44032 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: INDUSTRIAL NUCLEAR COMPANY
Region: 1
City: NORTH ANDOVER State: MA
County:
License #: 27-9661
Agreement: Y
Docket:
NRC Notified By: ROBERT GALLAGHER
HQ OPS Officer: JOE O'HARA | Notification Date: 03/05/2008
Notification Time: 16:21 [ET]
Event Date: 03/05/2008
Event Time: [EST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN CARUSO (R1)
SCOTT FLANDERS (FSME)
| Event Text AGREEMENT STATE REPORT - ABANDONMENT OF MATERIALS MANUFACTURING FACILITY
The Commonwealth of Massachusetts called to report that one of their materials licensees has ceased business and terminated or dismissed a majority of their employees. The licensee is under an M&D order, and a review of an inventory of materials on the site indicates there are materials at the site which exceed the allowable quantities in Table 1 of the M&D order. Since the business is no longer staffed, the Commonwealth of Massachusetts has expressed concerns with security at the facility.
The issue was discussed in detail on a conference bridge with NRC Headquarters, Region 1, and Commonwealth of Massachusetts representatives. |
| General Information or Other | Event Number: 44033 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: SKYRIDGE MEDICAL CENTER
Region: 4
City: DENVER State: CO
County:
License #: 1053-01
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: JOE O'HARA | Notification Date: 03/05/2008
Notification Time: 16:14 [ET]
Event Date: 03/05/2008
Event Time: [MST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
SCOTT FLANDERS (FSME)
| Event Text AGREEMENT STATE REPORT - MISADMINISTRATION OF Y-90 MICROSPHERES
The State provided the following information via facsimile:
"A medical licensee notified the Department of a misadministration during a Y-90 microsphere procedure, The problem was identified at the conclusion of the procedure when staff noted that 50% of the Y-90 microspheres were still in the application kit, resulting in a 50% underdose to the patient. The licensee's medical physicist, who is investigating the incident, was unsure if the problem was caused by a faulty injection valve or human error (e.g.. The valve was turned to the wrong position during the procedure). The licensee is Skyridge Medical Center Denver, CO, License 1053-01.
"No other details are available at this time.
"The Department has initiated an investigation of this incident."
* * * UPDATE ON 03/08/2008 AT 0847 EST FROM FSME (FLANNERY) TO ALEXANDER * * *
The NRC has reviewed this event and determined it to be a reportable medical event.
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. |
| Power Reactor | Event Number: 44041 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GRZECK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/07/2008
Notification Time: 11:25 [ET]
Event Date: 03/07/2008
Event Time: 10:30 [EST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GEORGE HOPPER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 93 | Power Operation | 93 | Power Operation | | 2 | N | Y | 77 | Power Operation | 77 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO TRITIUM IN ONSITE WATER SAMPLES
"Brunswick previously reported detection of tritium in excess of Nuclear Energy Institute (NEI) reporting criteria on June 13, 2007, i.e., EN 43420, as a result of water samples taken from an onsite shallow groundwater well (i.e., ESS 1BC) near the Storm Drain Stabilization Pond (SDSP). As previously indicated in EN 43420, the storm drain system routes tritiated water into the SDSP. Overflow from the Turbine Building air-wash system was identified as the primary contributor to the effluent of the storm drain system. The air-wash is no longer routed into the storm drains, which eliminated the main source of the tritium into the storm drain system.
"On March 6, 2008, an ongoing investigation determined that tritium levels in excess of NEI voluntary reporting criteria present in an onsite shallow groundwater well (i.e., ESS-2C), resulted from a condition not previously reported. Though elevated levels of tritium for each incident are most likely a result of the same source (i.e., effluent routed in the storm drain system,) subsequent investigations indicate that the storm drain piping may allow an inadvertent pathway to groundwater in close proximity to ESS-2C.
"The monitoring well ESS-2C is well within the boundaries of the site owner controlled area and there is no indication that tritium has migrated into any drinking water.
"The following agencies will be updated on the status of the onsite tritium samples and informed of the pending press release: State Officials, City of Southport, Brunswick County, NEI, INPO, and ANI.
"The Licensee notified the NRC Senior Resident Inspector." |
| Power Reactor | Event Number: 44042 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES KRITZER
HQ OPS Officer: PETE SNYDER | Notification Date: 03/07/2008
Notification Time: 13:00 [ET]
Event Date: 03/07/2008
Event Time: 10:45 [EST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN CARUSO (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 TELEPHONE OUTAGE ONSITE
"On 3/7/08, at 1045, Vermont Yankee experienced a telephone service interruption that resulted in a loss of the dedicated phone line used to contact the NRC Operations Center via the Emergency Notification System (ENS) - FTS phone as well as a loss of the Nuclear Alert System (NAS) from the control room.
"Alternate phone communications remain available from the control room to both the NRC Operations Center as well as the states of Vermont, Massachusetts, and New Hampshire.
"The Emergency Planning organization has verified proper ENS - FTS and NAS communications from the Emergency Operations Facility (EOF)."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM KRITZER TO SNYDER ON 3/7/08 AT 1552 * * *
Vermont Yankee's ENS and other phone lines are back in service.
The licensee notified the NRC Resident Inspector.
Notified R1DO (Caruso). |
| Other Nuclear Material | Event Number: 44044 | Rep Org: KENNEDY HEALTH SYSTEM
Licensee: KENNEDY HEALTH SYSTEM
Region: 1
City: STRATFORD State: NJ
County:
License #: SNM-1690
Agreement: N
Docket: 07002427
NRC Notified By: LESTER TRIP
HQ OPS Officer: PETE SNYDER | Notification Date: 03/07/2008
Notification Time: 15:15 [ET]
Event Date: 03/07/2008
Event Time: [EST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
JOHN CARUSO (R1)
SCOTT FLANDERS (FSME)
ILTAB (E-MAIL) ()
|
| This material event contains a "Category 3" level of radioactive material. | Event Text NUCLEAR POWERED PACEMAKER POTENTIALLY UNACCOUNTED FOR
After recently determining that an individual with a nuclear powered pacemaker was due for a six month check-up, the licensee attempted to reach the individual on March 5, 2008. Later the licensee determined that the individual was deceased. The licensee contacted the funeral director in an attempt to recover the pacemaker. The licensee also contacted Medtronic Corp. in an attempt to determine if the funeral director had returned the pacemaker to Medtronic but the licensee has still been unable to account for the pacemaker.
On March 7, 2008, after attempts to locate the device, an official from Kennedy Health System determined that a Coreatomic Inc. nuclear powered pacemaker is missing and perhaps lost.
The pacemaker is a Coreatomic model C-101-P nuclear powered cardiac pacemaker serial number 1168. Typically these pacemakers contain 2 to 4 curies of Pu-238 which is about 250 milligrams of material or less.
THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL
Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example, level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. |
| Power Reactor | Event Number: 44046 | Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: AL DEES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/07/2008
Notification Time: 17:21 [ET]
Event Date: 03/07/2008
Event Time: 14:46 [EST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
GEORGE HOPPER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM WITH HPCI/RCIC ACTUATION DUE TO LOSS OF CONDENSATE FEEDWATER
"Unit 2 RPS actuation / unplanned scram with subsequent ECCS discharge to the RCS at 1446 hrs. on 3/07/08. Unit 2 scrammed on Low RPV water level of 3 inches above instrument zero as a result of a loss of condensate feedwater. Water level decreased to approximately 60 inches below instrument zero as a result of the loss of feedwater. [Top of active fuel is approximately 150 inches below instrument zero.] The cause of the loss of feedwater is presently under investigation. At 35 inches below instrument zero, HPCI and RCIC actuated and restored water level. HPCI oscillations were experienced and the system was taken to manual control, at which time the flow oscillations abated. All other systems functioned as required.
"A team has been assembled to investigate and determine the cause of the initiating event of the loss of feedwater."
During the scram, all rods inserted into the core. There were no safety relief valve actuations as a result of the transient. RPV level was restored and is being maintained using control rod drive flow. The electrical grid is stable with normal offsite power supplying safety loads. Decay heat is being removed using the turbine bypass valves to condenser.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44047 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MARK JONES
HQ OPS Officer: PETE SNYDER | Notification Date: 03/07/2008
Notification Time: 22:49 [ET]
Event Date: 03/07/2008
Event Time: 19:14 [EST]
Last Update Date: 03/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GEORGE HOPPER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INTERMITTENT OPERATION OF EMERGENCY RESPONSE DATA SYSTEM
"At 1914 on 3/07/08, the Unit 4 RCO noted that the ERDADS OPCON displays in control room and computer room stopped updating. This rendered the Unit 4 ERDS link to the Nuclear Regulatory Commission Operations Center (NRCOC) to be inoperable for greater than 30 minutes, as the link can not be initialized if required.
"Attempts to reboot the OPCON displays and the PEDS Computers were initially performed per plant procedure, but did not correct the issue. Troubleshooting is in progress at this time. No estimated return to service is available at this time.
"8-hour notification being performed to NRCOC under event classification 10 CFR 50.72 (b)(3)(xiii)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44048 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DON DEWEY
HQ OPS Officer: JOE O'HARA | Notification Date: 03/08/2008
Notification Time: 21:23 [ET]
Event Date: 03/08/2008
Event Time: 19:37 [EST]
Last Update Date: 03/08/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN CARUSO (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF POWER TO OFF-SITE EMERGENCY SIRENS
"On March 8, 2008, at 1937 hours, Emergency Planning determined that 17 of a total of 156 sirens were reported as unavailable due to weather related loss of power as a result of high winds. In accordance with the Indian Point reporting procedure, the loss of 16 or more sirens that can not be returned to service in one hour, constitutes a major loss of the offsite notification capability that requires an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(xiii). Actions are underway to restore all of the sirens to service.
"As of 2043 EST on 03/08/08 there were 16 of 156 sirens out of service.
"The licensee notified the NRC Resident Inspector, as well as the Counties of Westchester, Putnam, Rockland, and Orange."
The licensee also notified the Public Service Commission. | |