Event Notification Report for December 04, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/03/2001 - 12/04/2001
EVENT NUMBERS
3853738538385393853538547
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38537
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: FANGIE JONES
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: FANGIE JONES
Notification Date: 12/04/2001
Notification Time: 16:03 [ET]
Event Date: 12/04/2001
Event Time: 12:00 [EST]
Last Update Date: 12/21/2001
Notification Time: 16:03 [ET]
Event Date: 12/04/2001
Event Time: 12:00 [EST]
Last Update Date: 12/21/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN ROGGE (R1)
JACK STROSNIDER (NRR)
JOHN ROGGE (R1)
JACK STROSNIDER (NRR)
| 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 |
FAILURE OF PART OF THE OFF-SITE NOTIFICATION SIRENS TO OPERATE WHEN TESTED
The licensee was performing their semi-annual off-site notification siren operational test and found that only 147 of 154 sirens operated properly. The remaining 7 sirens are being investigated for the cause of their failure. The licensee will use the Emergency Plan alternate means of informing the public, including route alerting and public announcements in the event of an accident.
The licensee notified the NRC Resident Inspector.
* * * UPDATE 1200EST ON 12/21/01 FROM JIM READY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"Indian Point Units 1,2 and 3 is retracting the eight (8) hour non-emergency notification made in accordance with 10 CFR 50.72(b)(3)(xiii) on December 4, 2001, at 1603 hours (EN # 38537). The notification reported the loss of a portion of the offsite communication capability due to a failure of 5 of 16 sirens in Orange County to actuate during the semi-annual siren test. The notification was a result of less than a 90% response rate of sirens in one county (Orange). At the time, 5 sirens in Orange County were being investigated for the cause of failure.
"Upon subsequent investigation and testing, which was completed on December 13, Entergy determined that this condition was not reportable because the 5 Orange County sirens were acceptable and operable and thereby did not exceed the threshold for notification. The cause of the sirens to appear to have failed was attributed to a discrepancy in test coordination which occurred during the conduct of the siren test.
The licensee informed the NRC Resident Inspector. Notified R1DO(Kinneman).
The licensee was performing their semi-annual off-site notification siren operational test and found that only 147 of 154 sirens operated properly. The remaining 7 sirens are being investigated for the cause of their failure. The licensee will use the Emergency Plan alternate means of informing the public, including route alerting and public announcements in the event of an accident.
The licensee notified the NRC Resident Inspector.
* * * UPDATE 1200EST ON 12/21/01 FROM JIM READY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"Indian Point Units 1,2 and 3 is retracting the eight (8) hour non-emergency notification made in accordance with 10 CFR 50.72(b)(3)(xiii) on December 4, 2001, at 1603 hours (EN # 38537). The notification reported the loss of a portion of the offsite communication capability due to a failure of 5 of 16 sirens in Orange County to actuate during the semi-annual siren test. The notification was a result of less than a 90% response rate of sirens in one county (Orange). At the time, 5 sirens in Orange County were being investigated for the cause of failure.
"Upon subsequent investigation and testing, which was completed on December 13, Entergy determined that this condition was not reportable because the 5 Orange County sirens were acceptable and operable and thereby did not exceed the threshold for notification. The cause of the sirens to appear to have failed was attributed to a discrepancy in test coordination which occurred during the conduct of the siren test.
The licensee informed the NRC Resident Inspector. Notified R1DO(Kinneman).
Power Reactor
Event Number: 38538
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FLOYD BATEY
HQ OPS Officer: FANGIE JONES
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FLOYD BATEY
HQ OPS Officer: FANGIE JONES
Notification Date: 12/04/2001
Notification Time: 17:18 [ET]
Event Date: 12/04/2001
Event Time: 16:30 [EST]
Last Update Date: 12/04/2001
Notification Time: 17:18 [ET]
Event Date: 12/04/2001
Event Time: 16:30 [EST]
Last Update Date: 12/04/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
| 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 NOTIFIED THE BETHAL FIRE DEPARTMENT
The licensee called on the Bethal Fire Department for help in clean-up of a lift station spill (sewage). Fire header water will be used to flush spill area to yard drains and catch basin for later release in accordance with procedures. No sewage reached the lake.
The licensee intends to notify the NRC Resident Inspector, the states of South Carolina and North Carolina, and local counties.
The licensee called on the Bethal Fire Department for help in clean-up of a lift station spill (sewage). Fire header water will be used to flush spill area to yard drains and catch basin for later release in accordance with procedures. No sewage reached the lake.
The licensee intends to notify the NRC Resident Inspector, the states of South Carolina and North Carolina, and local counties.
Power Reactor
Event Number: 38539
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MIKE BEARD
HQ OPS Officer: FANGIE JONES
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MIKE BEARD
HQ OPS Officer: FANGIE JONES
Notification Date: 12/04/2001
Notification Time: 21:58 [ET]
Event Date: 12/04/2001
Event Time: 18:24 [CST]
Last Update Date: 12/04/2001
Notification Time: 21:58 [ET]
Event Date: 12/04/2001
Event Time: 18:24 [CST]
Last Update Date: 12/04/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY GODY (R4)
ANTHONY GODY (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 |
24-HOUR REPORT REGARDING AN OPERATING LICENSE CONDITION VIOLATION (GGNS LICENSE CONDITION F)
The licensee discovered an error in the thermal power calculation during an ongoing review previously reported under LER 2001-004-00, Docket #50-416 Thermal Calculation Error. There is an additional error of 5.5 MWth in the calculation due to the original use of the 1936 Steam Tables versus the updated 1969 version. The licensee has reduced reactor thermal power by the 5.5 MWth and is maintaining 3827 MWth for an 8 hour average.
The licensee notified the NRC Resident Inspector.
See Event #38344 from Grand Gulf.
The licensee discovered an error in the thermal power calculation during an ongoing review previously reported under LER 2001-004-00, Docket #50-416 Thermal Calculation Error. There is an additional error of 5.5 MWth in the calculation due to the original use of the 1936 Steam Tables versus the updated 1969 version. The licensee has reduced reactor thermal power by the 5.5 MWth and is maintaining 3827 MWth for an 8 hour average.
The licensee notified the NRC Resident Inspector.
See Event #38344 from Grand Gulf.
Power Reactor
Event Number: 38535
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: RON FRIGO
HQ OPS Officer: FANGIE JONES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: RON FRIGO
HQ OPS Officer: FANGIE JONES
Notification Date: 12/04/2001
Notification Time: 14:57 [ET]
Event Date: 12/04/2001
Event Time: 11:00 [EST]
Last Update Date: 12/04/2001
Notification Time: 14:57 [ET]
Event Date: 12/04/2001
Event Time: 11:00 [EST]
Last Update Date: 12/04/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PATRICK HILAND (R3)
PATRICK HILAND (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
EMERGENCY RESPONSE DATA SYSTEM FOUND INOPERABLE
The licensee was conducting their quarterly functional test of the Emergency Response Data System (ERDS) and found it to be inoperable. The ERDS was restored to service at 1405 EST on 12/4/01.
The licensee notified the NRC Resident Inspector.
The licensee was conducting their quarterly functional test of the Emergency Response Data System (ERDS) and found it to be inoperable. The ERDS was restored to service at 1405 EST on 12/4/01.
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 38547
Rep Org: PHILLIP MORRIS USA
Licensee: PHILLIP MORRIS USA
Region: 2
City: RICHMOND State: VA
County:
License #: 45-00385-06
Agreement: N
Docket:
NRC Notified By: J. TENHET (VIA FACSIMILE)
HQ OPS Officer: BOB STRANSKY
Licensee: PHILLIP MORRIS USA
Region: 2
City: RICHMOND State: VA
County:
License #: 45-00385-06
Agreement: N
Docket:
NRC Notified By: J. TENHET (VIA FACSIMILE)
HQ OPS Officer: BOB STRANSKY
Notification Date: 12/07/2001
Notification Time: 14:26 [ET]
Event Date: 12/04/2001
Event Time: 09:10 [EST]
Last Update Date: 12/07/2001
Notification Time: 14:26 [ET]
Event Date: 12/04/2001
Event Time: 09:10 [EST]
Last Update Date: 12/07/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
INFORMATION REPORT
"Equipment:: Maid N Scanning Head (Beta Gauge)
"Equipment NRC Registration: # NR-462-D-1 02-B
"Equipment Registered to: Molins Richmond
3900 Carolina Avenue
P.O. Box 6159
Richmond, VA 23222-0159
"Radioactive Material: strontium-90, 0.025 curies, sealed source
"Nature of Failure: On Tuesday. December 4, 2001, an Authorized User was conducting routine leak-tests and shutter-checks. While conducting tests, he noticed cigarette maker machine 2A4, which was shutdown for routine maintenance, had a shutter indicator denoting the shutter in the open position. In this machine state, this shutter should have been closed. He used a survey meter to verify the shutter was open. He immediately inserted a cigarette rod in the pass tube to simulate normal operating conditions and radioed another Authorized User to bring another scanning head to the maker. Together they dismounted the scanning head and removed the source at 09:20 a.m. A beta shield was used during the source removal and the source was placed into a lead container. The other scanning head was placed on the maker and a survey was made. The source and malfunctioning scanning head were taken to the radiation shop and the source was placed into a locked storage sate.
"The Molins Maid N scanning head is a fixed gauge. During operation, it is bolted to a cigarette-making machine. The Maid N scanning head is used to measure the density of tobacco in a continuous, paper-wrapped. cylindrical rod that passes through this gauge en route to being sectioned into individual cigarette lengths in another part of the machine. The Maid N is shielded except for a 9-mm diameter pass tube through which the continuous tobacco rod passes. The Strontium 90 source is situated at the rear of the gauge and the detector tube at the front. The direct beam of radiation is wholly contained within the gauge and is aligned perpendicular to the pass tube. During normal operation, the pass tube is filled by a cigarette rod. When the gauge is turned off, the pass tube is clear and the shutter is closed.
"Date/Time of Event: Tuesday, December 4, 2001, 09:10 a.m..
"Date/Time Initially Reported to NRC: Tuesday, December 4, 2001 4:50 p.m..
"Name or Individual Reporting: Mr. Chuck L. Stiff, Safety Director
Mr. Joe Tenhet, RSO
"Location: Philip Morris USA
Richmond Manufacturing Center
3601 Commerce Road
P.O. Box 26603
Richmond, VA 23261
"License # 45-00385-06
"Corrective Actions: The scanning head was completely disassembled, checked and repaired. The repair technician found no reason for the shutter to fail to close and was not able to reproduce the problem. A new shutter assembly was installed in the scanning head as a precaution."
"Equipment:: Maid N Scanning Head (Beta Gauge)
"Equipment NRC Registration: # NR-462-D-1 02-B
"Equipment Registered to: Molins Richmond
3900 Carolina Avenue
P.O. Box 6159
Richmond, VA 23222-0159
"Radioactive Material: strontium-90, 0.025 curies, sealed source
"Nature of Failure: On Tuesday. December 4, 2001, an Authorized User was conducting routine leak-tests and shutter-checks. While conducting tests, he noticed cigarette maker machine 2A4, which was shutdown for routine maintenance, had a shutter indicator denoting the shutter in the open position. In this machine state, this shutter should have been closed. He used a survey meter to verify the shutter was open. He immediately inserted a cigarette rod in the pass tube to simulate normal operating conditions and radioed another Authorized User to bring another scanning head to the maker. Together they dismounted the scanning head and removed the source at 09:20 a.m. A beta shield was used during the source removal and the source was placed into a lead container. The other scanning head was placed on the maker and a survey was made. The source and malfunctioning scanning head were taken to the radiation shop and the source was placed into a locked storage sate.
"The Molins Maid N scanning head is a fixed gauge. During operation, it is bolted to a cigarette-making machine. The Maid N scanning head is used to measure the density of tobacco in a continuous, paper-wrapped. cylindrical rod that passes through this gauge en route to being sectioned into individual cigarette lengths in another part of the machine. The Maid N is shielded except for a 9-mm diameter pass tube through which the continuous tobacco rod passes. The Strontium 90 source is situated at the rear of the gauge and the detector tube at the front. The direct beam of radiation is wholly contained within the gauge and is aligned perpendicular to the pass tube. During normal operation, the pass tube is filled by a cigarette rod. When the gauge is turned off, the pass tube is clear and the shutter is closed.
"Date/Time of Event: Tuesday, December 4, 2001, 09:10 a.m..
"Date/Time Initially Reported to NRC: Tuesday, December 4, 2001 4:50 p.m..
"Name or Individual Reporting: Mr. Chuck L. Stiff, Safety Director
Mr. Joe Tenhet, RSO
"Location: Philip Morris USA
Richmond Manufacturing Center
3601 Commerce Road
P.O. Box 26603
Richmond, VA 23261
"License # 45-00385-06
"Corrective Actions: The scanning head was completely disassembled, checked and repaired. The repair technician found no reason for the shutter to fail to close and was not able to reproduce the problem. A new shutter assembly was installed in the scanning head as a precaution."