Event Notification Report for December 17, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/16/2001 - 12/17/2001
EVENT NUMBERS
38578385793858038615
Power Reactor
Event Number: 38578
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG BAKER
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG BAKER
HQ OPS Officer: LEIGH TROCINE
Notification Date: 12/17/2001
Notification Time: 10:39 [ET]
Event Date: 12/17/2001
Event Time: 08:00 [CST]
Last Update Date: 12/17/2001
Notification Time: 10:39 [ET]
Event Date: 12/17/2001
Event Time: 08:00 [CST]
Last Update Date: 12/17/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MONTE PHILLIPS (R3)
MONTE PHILLIPS (R3)
| 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 | 95 | Power Operation | 95 | Power Operation |
SIGNIFICANT FITNESS-FOR-DUTY EVENT UNDER BRAIDWOOD PROGRAM SEC-1.10
A non-licensed supervisor tested positive based on a for-cause test due to the odor of alcohol. The individual was immediately escorted out of the Protected Area, and the individual's access has been suspended. (Call the NRC operations officer for additional details and for the Security Manager's telephone number.)
The licensee notified the NRC resident inspector.
A non-licensed supervisor tested positive based on a for-cause test due to the odor of alcohol. The individual was immediately escorted out of the Protected Area, and the individual's access has been suspended. (Call the NRC operations officer for additional details and for the Security Manager's telephone number.)
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 38579
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/17/2001
Notification Time: 16:17 [ET]
Event Date: 12/17/2001
Event Time: 15:30 [EST]
Last Update Date: 12/17/2001
Notification Time: 16:17 [ET]
Event Date: 12/17/2001
Event Time: 15:30 [EST]
Last Update Date: 12/17/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 10 | Power Operation |
24-HOUR REPORT DUE TO POTENTIAL OPERATION IN EXCESS OF OPERATING LICENSE CONDITION 2.C(1)
"After restart of Hope Creek from RF10, analysis of plant parameters indicated that changes occurred in the final feedwater temperature since the previous operating cycle. The temperatures as indicated by temperature loops 1AETE-N041A/B/C/D, were approximately 3 degrees lower than when operating at 100 percent power prior to the outage. This indicates that actual power may have been below 100 percent of last cycle operation. Other parameters, such as First Stage pressure, main turbine control valve position, #6 Feedwater Heater shell pressure, feed pump discharge flow, condensate pump flow, were also lower, substantiating that power was lower than previous cycle. Performance Engineering notified Design Engineering of this condition. Design Engineering then initiated a complete review of related documentation.
"During Hope Creek RF9 (May 2000), the main feedwater temperature loops required recalibration to support power up-rate. The traditional method to determine the RTD curve introduced a +1 degree F bias. This was non-conservative, in that power level was higher than calculated by the plant computer. In January of 2001, crossflow was implemented to correct for fouling of the venturis. In October 2001, a non-conservative moisture carryover fraction was used in the core thermal power calculation as reported in Hope Creek Special Report 354/2001-003-00. As a result of these conditions, Hope Creek Generating Station has potentially operated at power levels in excess of Operating License Condition 2.C(1), which requires that the facility be operated at reactor core power levels not in excess of 3339 MWt. The upper limit may have been exceeded by significantly less than 0.1%. This potential overpower condition existed between the time of crossflow implementation and RF10.
"This notification is being made in accordance with Hope Creek Operating License Condition 2.F, as a potential violation of Hope Creek Operating License Condition 2.C(1).
"The moisture carryover fraction was corrected during RF10. During the recent forced outage, the 4 RTDs were checked and all four loops were calibrated, therefore, eliminating the potential for operating above 100% power."
The period of time during which the unit may have operated in this condition occurred between August 1, 2001, and October 10, 2001. The corrective action involving calibration of the 4 RTDs was completed last week.
The licensee informed the NRC Resident Inspector.
"After restart of Hope Creek from RF10, analysis of plant parameters indicated that changes occurred in the final feedwater temperature since the previous operating cycle. The temperatures as indicated by temperature loops 1AETE-N041A/B/C/D, were approximately 3 degrees lower than when operating at 100 percent power prior to the outage. This indicates that actual power may have been below 100 percent of last cycle operation. Other parameters, such as First Stage pressure, main turbine control valve position, #6 Feedwater Heater shell pressure, feed pump discharge flow, condensate pump flow, were also lower, substantiating that power was lower than previous cycle. Performance Engineering notified Design Engineering of this condition. Design Engineering then initiated a complete review of related documentation.
"During Hope Creek RF9 (May 2000), the main feedwater temperature loops required recalibration to support power up-rate. The traditional method to determine the RTD curve introduced a +1 degree F bias. This was non-conservative, in that power level was higher than calculated by the plant computer. In January of 2001, crossflow was implemented to correct for fouling of the venturis. In October 2001, a non-conservative moisture carryover fraction was used in the core thermal power calculation as reported in Hope Creek Special Report 354/2001-003-00. As a result of these conditions, Hope Creek Generating Station has potentially operated at power levels in excess of Operating License Condition 2.C(1), which requires that the facility be operated at reactor core power levels not in excess of 3339 MWt. The upper limit may have been exceeded by significantly less than 0.1%. This potential overpower condition existed between the time of crossflow implementation and RF10.
"This notification is being made in accordance with Hope Creek Operating License Condition 2.F, as a potential violation of Hope Creek Operating License Condition 2.C(1).
"The moisture carryover fraction was corrected during RF10. During the recent forced outage, the 4 RTDs were checked and all four loops were calibrated, therefore, eliminating the potential for operating above 100% power."
The period of time during which the unit may have operated in this condition occurred between August 1, 2001, and October 10, 2001. The corrective action involving calibration of the 4 RTDs was completed last week.
The licensee informed the NRC Resident Inspector.
Fuel Cycle Facility
Event Number: 38580
Facility: HONEYWELL INTERNATIONAL, INC.
Region: 3 State: IL
Unit: [] [] []
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
NRC Notified By: HUGH ROBERTS
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: IL
Unit: [] [] []
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
NRC Notified By: HUGH ROBERTS
HQ OPS Officer: LEIGH TROCINE
Notification Date: 12/18/2001
Notification Time: 09:13 [ET]
Event Date: 12/17/2001
Event Time: 12:05 [CST]
Last Update Date: 12/18/2001
Notification Time: 09:13 [ET]
Event Date: 12/17/2001
Event Time: 12:05 [CST]
Last Update Date: 12/18/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MONTE PHILLIPS (R3)
FRED BROWN (NMSS)
MONTE PHILLIPS (R3)
FRED BROWN (NMSS)
FAILURE OF THE STANDBY GENERATOR TO START ON AUTOMATIC DUE TO A PARTIAL POWER OUTAGE AND RELAY FAILURE
Moisture in a substation resulted in a partial power outage, and a faulty relay resulted in a failure to switch over to an automatic start on the standby generator. The failure of the standby generator to start on automatic occurred at 1205 CST on 12/17/01. The facility was shut down until the generator was restored and the relay was fixed. The system was restored to service at approximately 1930 CST on 12/17/01.
The licensee reported that there was no loss of source material related to this event. In addition, there were no personnel radiation exposures or contaminations.
The licensee reported this event in accordance with 10CFR40.60(b)(2)(iii) because there was no redundant equipment available to operate and perform the required safety function.
The licensee notified the NRC resident inspector (Bruce Bartlett) for Paducah and plans to submit a written report.
(Call the NRC operations officer for a licensee contact telephone number.)
Moisture in a substation resulted in a partial power outage, and a faulty relay resulted in a failure to switch over to an automatic start on the standby generator. The failure of the standby generator to start on automatic occurred at 1205 CST on 12/17/01. The facility was shut down until the generator was restored and the relay was fixed. The system was restored to service at approximately 1930 CST on 12/17/01.
The licensee reported that there was no loss of source material related to this event. In addition, there were no personnel radiation exposures or contaminations.
The licensee reported this event in accordance with 10CFR40.60(b)(2)(iii) because there was no redundant equipment available to operate and perform the required safety function.
The licensee notified the NRC resident inspector (Bruce Bartlett) for Paducah and plans to submit a written report.
(Call the NRC operations officer for a licensee contact telephone number.)
General Information or Other
Event Number: 38615
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: HOLDEN X-RAY SERVICE
Region: 4
City: State: LA
County:
License #: LA-4440-L01
Agreement: Y
Docket:
NRC Notified By: BLACKWELL VIA FAX
HQ OPS Officer: BOB STRANSKY
Licensee: HOLDEN X-RAY SERVICE
Region: 4
City: State: LA
County:
License #: LA-4440-L01
Agreement: Y
Docket:
NRC Notified By: BLACKWELL VIA FAX
HQ OPS Officer: BOB STRANSKY
Notification Date: 01/08/2002
Notification Time: 12:10 [ET]
Event Date: 12/17/2001
Event Time: 00:00 [CST]
Last Update Date: 01/08/2002
Notification Time: 12:10 [ET]
Event Date: 12/17/2001
Event Time: 00:00 [CST]
Last Update Date: 01/08/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHUCK CAIN (R4)
FRED BROWN (NMSS)
CHUCK CAIN (R4)
FRED BROWN (NMSS)
AGREEMENT STATE REPORT
"Event Report ID No.; LA010019
"License No.: LA-4440-L01
"Licensee: Holden X-Ray Service
"Event date and Time: 12/17/01 at 14:27. Report faxed to Holden
"Event Location: NA
"Event type: Excessive-exposure to Industrial Radiographer
"Notifications: Holden X-Ray notified the Department. The letter is dated December 26, 2001. The Department received the letter on January 3, 2002. I received a copy of the letter on January 7, 2002.
"Event description; [individual] received a Deep dose of 6873 mrem, Lens dose of 6873 mrem, and a shallow dose of 6629 mrem as of November 9, 2001 for the 2001 year. He was using Iridium 192 with source strengths up to 93 Curies. [Individual] was working a lot towards the end of the year."
"Event Report ID No.; LA010019
"License No.: LA-4440-L01
"Licensee: Holden X-Ray Service
"Event date and Time: 12/17/01 at 14:27. Report faxed to Holden
"Event Location: NA
"Event type: Excessive-exposure to Industrial Radiographer
"Notifications: Holden X-Ray notified the Department. The letter is dated December 26, 2001. The Department received the letter on January 3, 2002. I received a copy of the letter on January 7, 2002.
"Event description; [individual] received a Deep dose of 6873 mrem, Lens dose of 6873 mrem, and a shallow dose of 6629 mrem as of November 9, 2001 for the 2001 year. He was using Iridium 192 with source strengths up to 93 Curies. [Individual] was working a lot towards the end of the year."