Event Notification Report for September 22, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/21/2000 - 09/22/2000
EVENT NUMBERS
37364373653736637367373683736937370
Power Reactor
Event Number: 37364
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: HAMM/SCHALL
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: HAMM/SCHALL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/22/2000
Notification Time: 04:26 [ET]
Event Date: 09/22/2000
Event Time: 04:00 [EDT]
Last Update Date: 09/22/2000
Notification Time: 04:26 [ET]
Event Date: 09/22/2000
Event Time: 04:00 [EDT]
Last Update Date: 09/22/2000
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION 50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION 50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS DECKER (R2)
BILL BATEMAN (NRR)
JOSEPH GIITTER (IRO)
LUIS REYES (R2)
HEYMAN (FEMA)
THOMAS DECKER (R2)
BILL BATEMAN (NRR)
JOSEPH GIITTER (IRO)
LUIS REYES (R2)
HEYMAN (FEMA)
| 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 |
FIRE IN THE PROTECTED AREA LASTING GREATER THAN 10 MINUTES RESULTING IN A REACTOR SCRAM.
AN UNUSUAL EVENT WAS DECLARED @ 0400 DUE TO A FIRE IN THE MAIN TRANSFORMER THAT LASTED >10 MINUTES. OFF SITE FIRE DEPARTMENT WAS CALLED IN TO RESPOND AND THE FIRE WAS EXTINGUISHED WITHIN 14 MINUTES, HOWEVER THE PLANT STILL REMAINS IN THE UNUSUAL EVENT. A REACTOR SCRAM FROM 100% POWER OCCURRED FOLLOWING A MAIN TURBINE GENERATOR LOCKOUT WHICH RESULTED FROM THE TRANSFORMER FAILURE. THERE WERE SOME ERRONEOUS INDICATIONS OF CONTROL ROD POSITION, BUT ALL RODS APPEAR TO BE FULLY INSERTED. THERE WAS NO ECCS ACTUATION AND NO SAFETY RELIEF VALVES LIFTED DURING THIS EVENT. THE PLANT DID NOT LOSE OFFSITE POWER DUE TO THE AUTO TRANSFER FROM THE MAIN TRANSFORMER TO THE STARTUP AUXILIARY TRANSFORMER. THE DIESELS AUTOMATICALLY STARTED AND WERE STILL RUNNING AT THE TIME OF THIS REPORT. GROUP 2,6 AND 8 ISOLATIONS WERE ALSO RECEIVED. THERE WAS A PROBLEM WITH THE STARTUP LEVEL CONTROL VALVE WHEN THEY REESTABLISHED REACTOR FEED PUMP, VALVE DID NOT OPEN PROPERLY SO THEY HAD TO USE THE BACKUP PATH IN THE FEED SYSTEM. AS A RESULT OF THIS THE LEVEL WENT LOW ENOUGH TO RECEIVE A SECOND REACTOR SCRAM SIGNAL. THE CONDENSER IS BEING USED AS THE HEAT SINK AND THE PLANT IS STABLE. THE CAUSES FOR THE TRANSFORMER FIRE AND THE ERRONEOUS CONTROL ROD INDICATIONS ARE BEING INVESTIGATED. THERE HAVE BEEN NO INJURIES REPORTED AND IT IS NOT KNOWN AT THIS TIME IF A PRESS RELEASE WILL BE ISSUED.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED.
* * * UPDATE ON 9/22/00 @ 0528 BY HAMM TO GOULD * * *
THE NOUE WAS TERMINATED AT 0512 DUE TO THE FIRE BEING COMPLETELY EXTINGUISHED.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.
THE EO(BATEMAN), RDO(DECKER), FEMA (HEYMAN) AND IRO(GIITTER) WERE NOTIFIED.
SEE EVENT # 37365.
* * * UPDATE AT 1313 EDT ON 9/22/00 BY KEN CHISM TO FANGIE JONES * * *
The licensee, after further review, has determined that the fire was extinguished in 16 minutes versus the 14 minutes originally reported.
The licensee has issued a press release concerning the declaration of Unusual Event.
The licensee intends to notify the NRC Resident Inspector. The R2DO (Thomas Decker), NRR (Ed Goodwin), IRO (Joseph Giitter) have been notified.
* * * UPDATE AT 1653 EDT ON 9/22/00 BY KEITH REQUARD TO FANGIE JONES * * *
The licensee notified the State of North Carolina due to an oil spill resulting from the event. On September 22, 2000, at approximately 1350 hours, a notification was made to Mr. Jim Bushard, of the North Carolina Division of Water Quality, Wilmington Regional Office.
The incident began when a transformer overheated. The overheated transformer developed a leak at an oil flange, and caught fire. The transformer deluge system activated and, as a result, a mixture of water and transformer oil escaped the concrete containment structure surrounding the transformer. It is estimated that greater than 25 gallons and less than 100 gallons of transformer oil is outside of the containment structure. The oil is contained onsite and poses no environmental hazard. The oil is a mineral oil and contains no PCBs. Clark Environmental Services Inc. is performing the cleanup.
The licensee notified the NRC Resident. The R2DO (Thomas Decker), IRO (Joseph Giitter), and NRR EO (Bill Bateman) have been notified.
AN UNUSUAL EVENT WAS DECLARED @ 0400 DUE TO A FIRE IN THE MAIN TRANSFORMER THAT LASTED >10 MINUTES. OFF SITE FIRE DEPARTMENT WAS CALLED IN TO RESPOND AND THE FIRE WAS EXTINGUISHED WITHIN 14 MINUTES, HOWEVER THE PLANT STILL REMAINS IN THE UNUSUAL EVENT. A REACTOR SCRAM FROM 100% POWER OCCURRED FOLLOWING A MAIN TURBINE GENERATOR LOCKOUT WHICH RESULTED FROM THE TRANSFORMER FAILURE. THERE WERE SOME ERRONEOUS INDICATIONS OF CONTROL ROD POSITION, BUT ALL RODS APPEAR TO BE FULLY INSERTED. THERE WAS NO ECCS ACTUATION AND NO SAFETY RELIEF VALVES LIFTED DURING THIS EVENT. THE PLANT DID NOT LOSE OFFSITE POWER DUE TO THE AUTO TRANSFER FROM THE MAIN TRANSFORMER TO THE STARTUP AUXILIARY TRANSFORMER. THE DIESELS AUTOMATICALLY STARTED AND WERE STILL RUNNING AT THE TIME OF THIS REPORT. GROUP 2,6 AND 8 ISOLATIONS WERE ALSO RECEIVED. THERE WAS A PROBLEM WITH THE STARTUP LEVEL CONTROL VALVE WHEN THEY REESTABLISHED REACTOR FEED PUMP, VALVE DID NOT OPEN PROPERLY SO THEY HAD TO USE THE BACKUP PATH IN THE FEED SYSTEM. AS A RESULT OF THIS THE LEVEL WENT LOW ENOUGH TO RECEIVE A SECOND REACTOR SCRAM SIGNAL. THE CONDENSER IS BEING USED AS THE HEAT SINK AND THE PLANT IS STABLE. THE CAUSES FOR THE TRANSFORMER FIRE AND THE ERRONEOUS CONTROL ROD INDICATIONS ARE BEING INVESTIGATED. THERE HAVE BEEN NO INJURIES REPORTED AND IT IS NOT KNOWN AT THIS TIME IF A PRESS RELEASE WILL BE ISSUED.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED.
* * * UPDATE ON 9/22/00 @ 0528 BY HAMM TO GOULD * * *
THE NOUE WAS TERMINATED AT 0512 DUE TO THE FIRE BEING COMPLETELY EXTINGUISHED.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.
THE EO(BATEMAN), RDO(DECKER), FEMA (HEYMAN) AND IRO(GIITTER) WERE NOTIFIED.
SEE EVENT # 37365.
* * * UPDATE AT 1313 EDT ON 9/22/00 BY KEN CHISM TO FANGIE JONES * * *
The licensee, after further review, has determined that the fire was extinguished in 16 minutes versus the 14 minutes originally reported.
The licensee has issued a press release concerning the declaration of Unusual Event.
The licensee intends to notify the NRC Resident Inspector. The R2DO (Thomas Decker), NRR (Ed Goodwin), IRO (Joseph Giitter) have been notified.
* * * UPDATE AT 1653 EDT ON 9/22/00 BY KEITH REQUARD TO FANGIE JONES * * *
The licensee notified the State of North Carolina due to an oil spill resulting from the event. On September 22, 2000, at approximately 1350 hours, a notification was made to Mr. Jim Bushard, of the North Carolina Division of Water Quality, Wilmington Regional Office.
The incident began when a transformer overheated. The overheated transformer developed a leak at an oil flange, and caught fire. The transformer deluge system activated and, as a result, a mixture of water and transformer oil escaped the concrete containment structure surrounding the transformer. It is estimated that greater than 25 gallons and less than 100 gallons of transformer oil is outside of the containment structure. The oil is contained onsite and poses no environmental hazard. The oil is a mineral oil and contains no PCBs. Clark Environmental Services Inc. is performing the cleanup.
The licensee notified the NRC Resident. The R2DO (Thomas Decker), IRO (Joseph Giitter), and NRR EO (Bill Bateman) have been notified.
Power Reactor
Event Number: 37365
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SCHALL
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SCHALL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/22/2000
Notification Time: 06:37 [ET]
Event Date: 09/22/2000
Event Time: 03:40 [EDT]
Last Update Date: 09/22/2000
Notification Time: 06:37 [ET]
Event Date: 09/22/2000
Event Time: 03:40 [EDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (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 |
PLANT HAD ESF ACTUATIONS DURING A REACTOR SCRAM
A main turbine trip resulted in a reactor scram. As expected following the scram, reactor water level dropped to the actuation setpoint for Groups 2, 6 and 8 isolations. The main turbine trip apparently resulted from a fire in B main power transformer. The fire was reported to the control room at 0346. The site fire brigade responded and the fire was extinguished at 0402 using the automatic deluge system and fire hoses. Offsite fire department assistance was requested but was not needed to extinguish the fire. An Unusual Event was declared at 0400 in accordance with the plant's emergency procedures. The Unusual Event was terminated at 0512 based on the plant being in a stable condition. During the transient the startup level control did not control level in the automatic mode. Reactor level was controlled using a feedwater bypass valve. A second reactor scram signal was generated due a low reactor water level signal received while manual level control was being established, however all rods were already fully inserted. The plant emergency diesels started but did not load. Offsite power remained available throughout the event. The NRC Resident Inspector was notified.
HOO Note: see event # 37364
A main turbine trip resulted in a reactor scram. As expected following the scram, reactor water level dropped to the actuation setpoint for Groups 2, 6 and 8 isolations. The main turbine trip apparently resulted from a fire in B main power transformer. The fire was reported to the control room at 0346. The site fire brigade responded and the fire was extinguished at 0402 using the automatic deluge system and fire hoses. Offsite fire department assistance was requested but was not needed to extinguish the fire. An Unusual Event was declared at 0400 in accordance with the plant's emergency procedures. The Unusual Event was terminated at 0512 based on the plant being in a stable condition. During the transient the startup level control did not control level in the automatic mode. Reactor level was controlled using a feedwater bypass valve. A second reactor scram signal was generated due a low reactor water level signal received while manual level control was being established, however all rods were already fully inserted. The plant emergency diesels started but did not load. Offsite power remained available throughout the event. The NRC Resident Inspector was notified.
HOO Note: see event # 37364
Power Reactor
Event Number: 37366
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: A. DALL'AU
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: A. DALL'AU
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/22/2000
Notification Time: 11:49 [ET]
Event Date: 09/22/2000
Event Time: 11:10 [EDT]
Last Update Date: 09/22/2000
Notification Time: 11:49 [ET]
Event Date: 09/22/2000
Event Time: 11:10 [EDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 4 | N | Y | 88 | Power Operation | 88 | Power Operation |
SEVERAL PIECES OF SCAFFOLDING KNUCKLES AND ELBOWS RECEIVED FROM VENDOR FOUND TO HAVE LOW LEVELS OF RADIOACTIVITY. OFFSITE NOTIFICATION MADE TO THE STATE OF FLORIDA
While performing routine surveys, Turkey Point Health Physics personnel discovered low levels of radioactivity on several pieces of scaffolding knuckles and elbows received from a vendor. The knuckles never entered the site's radiation controlled area. These items were counted in a Small Articles Monitor (SAM) and indicated low level contamination was present. In total 3 out of approximately 700 item's surveyed indicted the presence of low level fixed activity. The highest level measured was 15,000 disintegration's per minute (dpm) using a standard HP-210 (pancake GM) probe. Isotope analysis indicated Cobalt-60 and Cesium-137. No loose surface contamination was found. The items identified with low level fixed contamination are now being held inside the Turkey Point radiation controlled area. The state of Florida was notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
While performing routine surveys, Turkey Point Health Physics personnel discovered low levels of radioactivity on several pieces of scaffolding knuckles and elbows received from a vendor. The knuckles never entered the site's radiation controlled area. These items were counted in a Small Articles Monitor (SAM) and indicated low level contamination was present. In total 3 out of approximately 700 item's surveyed indicted the presence of low level fixed activity. The highest level measured was 15,000 disintegration's per minute (dpm) using a standard HP-210 (pancake GM) probe. Isotope analysis indicated Cobalt-60 and Cesium-137. No loose surface contamination was found. The items identified with low level fixed contamination are now being held inside the Turkey Point radiation controlled area. The state of Florida was notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 37367
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVID FRYE
HQ OPS Officer: FANGIE JONES
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVID FRYE
HQ OPS Officer: FANGIE JONES
Notification Date: 09/22/2000
Notification Time: 12:17 [ET]
Event Date: 09/22/2000
Event Time: 09:40 [EDT]
Last Update Date: 09/22/2000
Notification Time: 12:17 [ET]
Event Date: 09/22/2000
Event Time: 09:40 [EDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LICENSEE TECHNICAL REQUIREMENTS 24 HOUR REPORT
The licensee, in accordance with their technical requirements, reported that the diesel fire pump was removed from service for approximately 2 hours. The pump was removed from service as part of ongoing maintenance of the pretreatment water storage tank. The pump being out-of-service and having one of two sources of water out-of-service prompted the 24 hour report. The pump has been restored to service.
The licensee informed the NRC Resident Inspector.
See similar event #37376 reported on 09/25/00.
The licensee, in accordance with their technical requirements, reported that the diesel fire pump was removed from service for approximately 2 hours. The pump was removed from service as part of ongoing maintenance of the pretreatment water storage tank. The pump being out-of-service and having one of two sources of water out-of-service prompted the 24 hour report. The pump has been restored to service.
The licensee informed the NRC Resident Inspector.
See similar event #37376 reported on 09/25/00.
General Information or Other
Event Number: 37368
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONSTRUCTION TESTING ENGINEERING
Region: 4
City: CONCORD State: CA
County:
License #: 2952-07
Agreement: Y
Docket:
NRC Notified By: MARK M. GOTTLIEB
HQ OPS Officer: JOHN MacKINNON
Licensee: CONSTRUCTION TESTING ENGINEERING
Region: 4
City: CONCORD State: CA
County:
License #: 2952-07
Agreement: Y
Docket:
NRC Notified By: MARK M. GOTTLIEB
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/22/2000
Notification Time: 13:07 [ET]
Event Date: 09/22/2000
Event Time: 06:00 [PDT]
Last Update Date: 09/22/2000
Notification Time: 13:07 [ET]
Event Date: 09/22/2000
Event Time: 06:00 [PDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JEFF SHACKELFORD (R4)
BRIAN SMITH (NMSS)
JEFF SHACKELFORD (R4)
BRIAN SMITH (NMSS)
TROXLER MOISTURE DENSITY GAUGE STOLEN FROM THE BACK OF A PICKUP TRUCK
AGREEMENT STATE REPORT
A Troxler Moisture Density gauge, Model # 3411-B (serial (12622) was stolen from the back of a pickup truck in Concord, California this morning around 0600 PT. The gauge was locked in the back of the licensee's pickup truck with a hasp lock going through the handle of the Troxler gauge case. The hasp lock cable was cut with a chain cutter. The person driving the pickup truck drove the truck home and was away from the truck approximately 15 minutes. The Concord police department was notified of the theft.
Troxler Model # 3411-B: 9 mCi of Cs-137 and 44 mCi of Americium-241. State of California report number is 092200.
AGREEMENT STATE REPORT
A Troxler Moisture Density gauge, Model # 3411-B (serial (12622) was stolen from the back of a pickup truck in Concord, California this morning around 0600 PT. The gauge was locked in the back of the licensee's pickup truck with a hasp lock going through the handle of the Troxler gauge case. The hasp lock cable was cut with a chain cutter. The person driving the pickup truck drove the truck home and was away from the truck approximately 15 minutes. The Concord police department was notified of the theft.
Troxler Model # 3411-B: 9 mCi of Cs-137 and 44 mCi of Americium-241. State of California report number is 092200.
Hospital
Event Number: 37369
Rep Org: SIBLEY MEMORIAL HOSPITAL
Licensee: SIBLEY MEMORIAL HOSPITAL
Region: 1
City: WASHINGTON State: DC
County:
License #:
Agreement: N
Docket:
NRC Notified By: GREGORY SIBLEY
HQ OPS Officer: FANGIE JONES
Licensee: SIBLEY MEMORIAL HOSPITAL
Region: 1
City: WASHINGTON State: DC
County:
License #:
Agreement: N
Docket:
NRC Notified By: GREGORY SIBLEY
HQ OPS Officer: FANGIE JONES
Notification Date: 09/22/2000
Notification Time: 16:15 [ET]
Event Date: 09/22/2000
Event Time: 13:00 [EDT]
Last Update Date: 09/22/2000
Notification Time: 16:15 [ET]
Event Date: 09/22/2000
Event Time: 13:00 [EDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
35.33 - MED MISADMINISTRATION
10 CFR Section:
35.33 - MED MISADMINISTRATION
Person (Organization):
RICHARD BARKLEY (R1)
JOHN HICKEY (NMSS)
RICHARD BARKLEY (R1)
JOHN HICKEY (NMSS)
2 PATIENTS RECEIVED MEDICAL MISADMINISTRATION DUE TO CALCULATION ERROR
The hospital discovered today that a mistake was made in ordering sources for medical procedures, a change had been made to order sources in 'air kerma strength' instead of millicuries (mCi). The conversion is suppose to be mCi divided by 1.2 instead they multiplied by 1.2. Two patients received I-125 plaques to the eye for melanoma and were suppose to receive 7000 rads, instead received 10,866 and 11,470 rads. There is not expected to be any consequences beyond what was expected with the prescribed dose. The procedure was a try at preserving the eye as it would have been removed otherwise. The prescribing physician has been contacted and the patient will be counseled.
The hospital has determined that no other sources were ordered with the wrong calculation and is taking steps to insure this mistake is not repeated.
The hospital has contacted NRC Region 1 (Teresa Darden).
The hospital discovered today that a mistake was made in ordering sources for medical procedures, a change had been made to order sources in 'air kerma strength' instead of millicuries (mCi). The conversion is suppose to be mCi divided by 1.2 instead they multiplied by 1.2. Two patients received I-125 plaques to the eye for melanoma and were suppose to receive 7000 rads, instead received 10,866 and 11,470 rads. There is not expected to be any consequences beyond what was expected with the prescribed dose. The procedure was a try at preserving the eye as it would have been removed otherwise. The prescribing physician has been contacted and the patient will be counseled.
The hospital has determined that no other sources were ordered with the wrong calculation and is taking steps to insure this mistake is not repeated.
The hospital has contacted NRC Region 1 (Teresa Darden).
Power Reactor
Event Number: 37370
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: THOMAS DOUGHERTY
HQ OPS Officer: FANGIE JONES
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: THOMAS DOUGHERTY
HQ OPS Officer: FANGIE JONES
Notification Date: 09/22/2000
Notification Time: 20:04 [ET]
Event Date: 09/22/2000
Event Time: 19:15 [EDT]
Last Update Date: 09/22/2000
Notification Time: 20:04 [ET]
Event Date: 09/22/2000
Event Time: 19:15 [EDT]
Last Update Date: 09/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
Person (Organization):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TESTING FOUND 20 OF 165 OFFSITE EMERGENCY SIRENS DETERMINED TO BE INOPERABLE
"On September 22, 2000 at 19:15, it was determined that 20 of Limerick Generating Station's 165 Emergency Offsite Sirens were inoperable. The exact cause of the inoperable sirens is not known at this time, but the ability of the licensee and counties to detect the inoperable sirens has been compromised. A plan is being developed to repair the degraded sirens, and appropriate interim compensatory measures are being implemented to compensate for the degraded condition."
This was the result of routine testing, there was no cluster of inoperable sirens, the inoperable sirens reported appeared operable from remote testing at the county, and an investigation will continue. These sirens have been maintained by the same contractor as mentioned in NRC report #37361 of 9/21/00.
The licensee has notified the NRC Resident Inspector and contacted the local authorities as part of the interim compensatory measures.
"On September 22, 2000 at 19:15, it was determined that 20 of Limerick Generating Station's 165 Emergency Offsite Sirens were inoperable. The exact cause of the inoperable sirens is not known at this time, but the ability of the licensee and counties to detect the inoperable sirens has been compromised. A plan is being developed to repair the degraded sirens, and appropriate interim compensatory measures are being implemented to compensate for the degraded condition."
This was the result of routine testing, there was no cluster of inoperable sirens, the inoperable sirens reported appeared operable from remote testing at the county, and an investigation will continue. These sirens have been maintained by the same contractor as mentioned in NRC report #37361 of 9/21/00.
The licensee has notified the NRC Resident Inspector and contacted the local authorities as part of the interim compensatory measures.