Event Notification Report for January 03, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/02/2003 - 01/03/2003
Power Reactor
Event Number: 39487
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: STEVE HENRY
HQ OPS Officer: JASON FLEMMING
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: STEVE HENRY
HQ OPS Officer: JASON FLEMMING
Notification Date: 01/03/2003
Notification Time: 15:14 [ET]
Event Date: 01/03/2003
Event Time: 11:01 [CST]
Last Update Date: 01/03/2003
Notification Time: 15:14 [ET]
Event Date: 01/03/2003
Event Time: 11:01 [CST]
Last Update Date: 01/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM JOHNSON (R4)
WILLIAM JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO POWER RANGE NEUTRON FLUX - HIGH NEGATIVE RATE TRIP
"On January 3, 2003, Wolf Creek Generating Station Unit 1 was operating at 100% reactor power when an automatic reactor trip occurred at 11:01 a.m. CST. Scheduled preventative maintenance had been completed on the control rod drive motor generator set, and the system was being placed back into service when an automatic reactor trip was received due to a Power Range Neutron Flux - High Negative Rate trip on all four power range channels.
"An Auxiliary Feedwater Actuation Signal was received and initiated the Auxiliary Feedwater System as expected. Plant equipment performed as expected.
"Investigation into the cause of the reactor trip is in progress. The plant is currently in MODE 3, Hot Standby. This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The Licensee has notified the NRC Resident inspector.
"On January 3, 2003, Wolf Creek Generating Station Unit 1 was operating at 100% reactor power when an automatic reactor trip occurred at 11:01 a.m. CST. Scheduled preventative maintenance had been completed on the control rod drive motor generator set, and the system was being placed back into service when an automatic reactor trip was received due to a Power Range Neutron Flux - High Negative Rate trip on all four power range channels.
"An Auxiliary Feedwater Actuation Signal was received and initiated the Auxiliary Feedwater System as expected. Plant equipment performed as expected.
"Investigation into the cause of the reactor trip is in progress. The plant is currently in MODE 3, Hot Standby. This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The Licensee has notified the NRC Resident inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39497
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: RICH LAURA
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: RICH LAURA
Notification Date: 01/09/2003
Notification Time: 13:55 [ET]
Event Date: 01/03/2003
Event Time: 10:00 [EST]
Last Update Date: 02/10/2003
Notification Time: 13:55 [ET]
Event Date: 01/03/2003
Event Time: 10:00 [EST]
Last Update Date: 02/10/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNCOMPENSATED SECURITY GUARD DEGRADATION FOR 1 HOUR
Immediate compensatory measures were taken upon discovery. The licensee notified the resident inspector. Refer to the HOO log for additional details.
* * * UPDATE ON 2/10/03 @ 1208 BY LYON TO GOULD * * * RETRACTION
The licensee is retracting this event
The NRC Resident Inspector was notified.
Notified Reis(EO) and Meyer(Reg 1 RDO)
Contact the HOO for further information.
* * * UPDATE ON 2/26/03 @ 1254 EST BY PRUSSMAN TO CROUCH * * *
Licensee corrected statements made during retraction. Contact the HOO for further information.
Notified Dennig (NRR EO) and Kinneman (R1DO).
Immediate compensatory measures were taken upon discovery. The licensee notified the resident inspector. Refer to the HOO log for additional details.
* * * UPDATE ON 2/10/03 @ 1208 BY LYON TO GOULD * * * RETRACTION
The licensee is retracting this event
The NRC Resident Inspector was notified.
Notified Reis(EO) and Meyer(Reg 1 RDO)
Contact the HOO for further information.
* * * UPDATE ON 2/26/03 @ 1254 EST BY PRUSSMAN TO CROUCH * * *
Licensee corrected statements made during retraction. Contact the HOO for further information.
Notified Dennig (NRR EO) and Kinneman (R1DO).
General Information or Other
Event Number: 39639
Rep Org: HOLTEC INTERNATIONAL
Licensee: AALBORG
Region: 0
City: State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: HOLTEC (fax)
HQ OPS Officer: MIKE RIPLEY
Licensee: AALBORG
Region: 0
City: State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: HOLTEC (fax)
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/06/2003
Notification Time: 14:10 [ET]
Event Date: 01/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/06/2003
Notification Time: 14:10 [ET]
Event Date: 01/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/06/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MOHAMED SHANBAKY (R1)
CAROLYN EVANS (R2)
MONTE PHILLIPS (R3)
DALE POWERS (R4)
TERRY REIS (NRR)
MOHAMED SHANBAKY (R1)
CAROLYN EVANS (R2)
MONTE PHILLIPS (R3)
DALE POWERS (R4)
TERRY REIS (NRR)
PART 21 NOTIFICATION - AALBORG FLOW METERS
Holtec International reports a potential defect in Aalborg model GFM671S mass flow rate meters. The instruments are used to verify the correct amount of helium is backfilled into dry spent fuel storage canisters. These instruments were never used on a Holtec cask system containing spent nuclear fuel because the problem was discovered during the preparatory phase before fuel loading.
Four meters were purchased for use at the Trojan nuclear plant to measure the amount of helium gas injected into a loaded Holtec dry spent fuel Multipurpose Canister (MPC). It was determined that erroneous data was coming from the flow rate meters. It was determined by Aalborg that the published correction factors for helium/nitrogen were incorrect for this model flow meter. At the time the discrepant condition was identified, none of the flow meters had been used on an MPC loaded with spent fuel and they were subsequently removed from service until they could be correctly calibrated.
Four flow rate meters were procured and delivered to the Trojan nuclear power plant. Three were not used in actual fuel loading activities due to the discovery of the mis-calibration during dry run activities. The fourth flow rate meter has been removed from the site.
Aalborg is developing new helium correction factors. In the interim, they have committed to using helium to calibrate all flow meters destined for use in measuring helium.
Trojan plant was the first plant where flow rate meters and flow totalizers were to be used to confirm adequate helium backfill in Holtec MPCs loaded with spent fuel. Therefore, no other Holtec client is affected for past loading operations. For future MPC loading operations, Holtec users, as well as other purchasers and licensees are being notified via this report that Aalborg flow meters procured for use in important-to-safety activities may not be calibrated correctly and that certain catalogue correction factors have been determined to be incorrect. The calibration of Aalborg flow meters should be confirmed prior to use in important-to-safety activities.
Holtec International reports a potential defect in Aalborg model GFM671S mass flow rate meters. The instruments are used to verify the correct amount of helium is backfilled into dry spent fuel storage canisters. These instruments were never used on a Holtec cask system containing spent nuclear fuel because the problem was discovered during the preparatory phase before fuel loading.
Four meters were purchased for use at the Trojan nuclear plant to measure the amount of helium gas injected into a loaded Holtec dry spent fuel Multipurpose Canister (MPC). It was determined that erroneous data was coming from the flow rate meters. It was determined by Aalborg that the published correction factors for helium/nitrogen were incorrect for this model flow meter. At the time the discrepant condition was identified, none of the flow meters had been used on an MPC loaded with spent fuel and they were subsequently removed from service until they could be correctly calibrated.
Four flow rate meters were procured and delivered to the Trojan nuclear power plant. Three were not used in actual fuel loading activities due to the discovery of the mis-calibration during dry run activities. The fourth flow rate meter has been removed from the site.
Aalborg is developing new helium correction factors. In the interim, they have committed to using helium to calibrate all flow meters destined for use in measuring helium.
Trojan plant was the first plant where flow rate meters and flow totalizers were to be used to confirm adequate helium backfill in Holtec MPCs loaded with spent fuel. Therefore, no other Holtec client is affected for past loading operations. For future MPC loading operations, Holtec users, as well as other purchasers and licensees are being notified via this report that Aalborg flow meters procured for use in important-to-safety activities may not be calibrated correctly and that certain catalogue correction factors have been determined to be incorrect. The calibration of Aalborg flow meters should be confirmed prior to use in important-to-safety activities.