Event Notification Report for October 02, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/01/2001 - 10/02/2001
Power Reactor
Event Number: 38345
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: DAVE BROWN
HQ OPS Officer: LEIGH TROCINE
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: DAVE BROWN
HQ OPS Officer: LEIGH TROCINE
Notification Date: 10/03/2001
Notification Time: 18:50 [ET]
Event Date: 10/02/2001
Event Time: 16:37 [PDT]
Last Update Date: 10/03/2001
Notification Time: 18:50 [ET]
Event Date: 10/02/2001
Event Time: 16:37 [PDT]
Last Update Date: 10/03/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
24-HOUR REPORT REGARDING AN OPERATING LICENSE CONDITION VIOLATION (POTENTIAL MAXIMUM POWER LEVEL VIOLATION
The following text is a portion of a facsimile received from the licensee:
"General Electric (GE) report titled, 'Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculation, September 2001,' documents a non-conservative constant for moisture carryover fraction in the equation used to calculate plant heat balance. The report states that a number of later model GE BWR plants report carryover fractions of less than 0.003%. Currently, Columbia Generating Station uses 0.1% for the carryover term in the calculation as directed by the GE design specifications. Use of the 0.1% term in the heat balance calculation may have resulted in Columbia Generating Station exceeding the maximum core thermal power value of 3486 MWt specified in license condition 2.C(1) by approximately 2.83 MWt or 0.08% Rated Thermal Power. As a compensatory measure until this issue is resolved, Columbia Generating Station will adopt a conservative value of 0.0% for the moisture carryover term in the plant heat balance calculation. Consequently, the Plant Process Computer eight hour average core thermal power is currently being administratively controlled at less than or equal to 3482 MWt."
"The Columbia Generating Station Operating License (NPF-21) contains a requirement to report a violation of this license condition to the NRC Regional Administrator or the Administrators designee. The NRC Region IV Regional Administrator's designee, Mr. William Jones, has been informed of this condition."
The licensee notified the NRC resident inspector.
(Refer to event numbers 38330, 38337, 38340, 38344, 38347, 38349, 38356, and 38357 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Limerick 2, River Bend, Clinton, and Limerick 1.)
The following text is a portion of a facsimile received from the licensee:
"General Electric (GE) report titled, 'Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculation, September 2001,' documents a non-conservative constant for moisture carryover fraction in the equation used to calculate plant heat balance. The report states that a number of later model GE BWR plants report carryover fractions of less than 0.003%. Currently, Columbia Generating Station uses 0.1% for the carryover term in the calculation as directed by the GE design specifications. Use of the 0.1% term in the heat balance calculation may have resulted in Columbia Generating Station exceeding the maximum core thermal power value of 3486 MWt specified in license condition 2.C(1) by approximately 2.83 MWt or 0.08% Rated Thermal Power. As a compensatory measure until this issue is resolved, Columbia Generating Station will adopt a conservative value of 0.0% for the moisture carryover term in the plant heat balance calculation. Consequently, the Plant Process Computer eight hour average core thermal power is currently being administratively controlled at less than or equal to 3482 MWt."
"The Columbia Generating Station Operating License (NPF-21) contains a requirement to report a violation of this license condition to the NRC Regional Administrator or the Administrators designee. The NRC Region IV Regional Administrator's designee, Mr. William Jones, has been informed of this condition."
The licensee notified the NRC resident inspector.
(Refer to event numbers 38330, 38337, 38340, 38344, 38347, 38349, 38356, and 38357 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Limerick 2, River Bend, Clinton, and Limerick 1.)
Power Reactor
Event Number: 38340
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KENNETH KLASS
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KENNETH KLASS
HQ OPS Officer: LEIGH TROCINE
Notification Date: 10/02/2001
Notification Time: 16:20 [ET]
Event Date: 10/02/2001
Event Time: 15:57 [EDT]
Last Update Date: 10/02/2001
Notification Time: 16:20 [ET]
Event Date: 10/02/2001
Event Time: 15:57 [EDT]
Last Update Date: 10/02/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 95 | Power Operation | 95 | Power Operation |
24-HOUR REPORT REGARDING AN OPERATING LICENSE CONDITION VIOLATION (POTENTIAL MAXIMUM POWER LEVEL VIOLATION)
The following text is a portion of a facsimile received from the licensee.
"General Electric (GE) report titled, 'Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculations, September 2001,' documents a non-conservative assumption for moisture carryover used in the calculation of core thermal power. The assumed carryover fraction of 0.1% was discovered to be closer to 0.0% (non-conservative) in later model GE BWRs. Hope Creek Generating Station may be affected by the non-conservative core thermal power calculation with an estimated bias of less than 4 MWt. As a result, there is a potential that Hope Creek Generating Station has 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."
"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)."
"An administrative shift average power limit of 3335 MWt has been implemented when the Crossflow ultrasonic flow measurement system is available. If Crossflow is unavailable, shift average power will be administratively limited to 3289 MWt."
"PSEG Nuclear is continuing to evaluate the effect of the moisture carryover term on the heat balance calculation."
The licensee notified the NRC resident inspector.
(Refer to event numbers 38330, 38337, 38344, 38445, 38347, 38349, 38356, and 38357 for similar events at Fermi, Perry, Grand Gulf, Columbia Generating Station, Limerick 2, River Bend, Clinton, and Limerick 1.)
The following text is a portion of a facsimile received from the licensee.
"General Electric (GE) report titled, 'Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculations, September 2001,' documents a non-conservative assumption for moisture carryover used in the calculation of core thermal power. The assumed carryover fraction of 0.1% was discovered to be closer to 0.0% (non-conservative) in later model GE BWRs. Hope Creek Generating Station may be affected by the non-conservative core thermal power calculation with an estimated bias of less than 4 MWt. As a result, there is a potential that Hope Creek Generating Station has 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."
"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)."
"An administrative shift average power limit of 3335 MWt has been implemented when the Crossflow ultrasonic flow measurement system is available. If Crossflow is unavailable, shift average power will be administratively limited to 3289 MWt."
"PSEG Nuclear is continuing to evaluate the effect of the moisture carryover term on the heat balance calculation."
The licensee notified the NRC resident inspector.
(Refer to event numbers 38330, 38337, 38344, 38445, 38347, 38349, 38356, and 38357 for similar events at Fermi, Perry, Grand Gulf, Columbia Generating Station, Limerick 2, River Bend, Clinton, and Limerick 1.)
Other Nuclear Material
Event Number: 38342
Rep Org: STERIGENICS
Licensee: STERIGENICS
Region: 1
City: ROCKAWAY State: NJ
County: MORRIS
License #: 29-30308-01
Agreement: N
Docket:
NRC Notified By: STANLEY YAP
HQ OPS Officer: LEIGH TROCINE
Licensee: STERIGENICS
Region: 1
City: ROCKAWAY State: NJ
County: MORRIS
License #: 29-30308-01
Agreement: N
Docket:
NRC Notified By: STANLEY YAP
HQ OPS Officer: LEIGH TROCINE
Notification Date: 10/03/2001
Notification Time: 13:10 [ET]
Event Date: 10/02/2001
Event Time: 23:59 [EDT]
Last Update Date: 10/03/2001
Notification Time: 13:10 [ET]
Event Date: 10/02/2001
Event Time: 23:59 [EDT]
Last Update Date: 10/03/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
36.83(a)(1) - UNSHIELD STUCK SOURCE
10 CFR Section:
36.83(a)(1) - UNSHIELD STUCK SOURCE
Person (Organization):
RICHARD CONTE (R1)
FRED BROWN (NMSS)
JOSEPH HOLONICH (IRO)
RICHARD CONTE (R1)
FRED BROWN (NMSS)
JOSEPH HOLONICH (IRO)
COMMERCIAL IRRADIATOR FACILITY REPORT REGARDING A SOURCE HANG UP
Sterigenics is a panoramic, wet-source storage, commercial, irradiator facility. At approximately midnight on 10/02/01, a 2.6-megacurie cobalt-60 source got stuck in the unshielded position for approximately 1 hour. Because the source got stuck on the way down, the licensee lifted the source rack, freed it, and successfully returned it to the shielded position. The licensee is still investigating the cause of this event but stated that there were no obvious reasons at this time. There were no personnel radiation exposures or injuries as a result of this event, and there was no source leakage.
(Call the NRC operations officer for a site contact telephone number.)
(Refer to event #38363 for a similar event at Sterigenics on 10/07/01.)
Sterigenics is a panoramic, wet-source storage, commercial, irradiator facility. At approximately midnight on 10/02/01, a 2.6-megacurie cobalt-60 source got stuck in the unshielded position for approximately 1 hour. Because the source got stuck on the way down, the licensee lifted the source rack, freed it, and successfully returned it to the shielded position. The licensee is still investigating the cause of this event but stated that there were no obvious reasons at this time. There were no personnel radiation exposures or injuries as a result of this event, and there was no source leakage.
(Call the NRC operations officer for a site contact telephone number.)
(Refer to event #38363 for a similar event at Sterigenics on 10/07/01.)