Event Notification Report for October 27, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/26/2010 - 10/27/2010
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 46368
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: AARON CHLADIL
HQ OPS Officer: STEVE SANDIN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: AARON CHLADIL
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/27/2010
Notification Time: 17:05 [ET]
Event Date: 10/27/2010
Event Time: 12:22 [CDT]
Last Update Date: 12/17/2010
Notification Time: 17:05 [ET]
Event Date: 10/27/2010
Event Time: 12:22 [CDT]
Last Update Date: 12/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 81 | Power Operation |
UNIT COMMENCED SHUTDOWN AFTER DECLARING CONTAINMENT SPRAY INOPERABLE
"During pressure drop testing of the backup nitrogen supply for HCV-345 (Containment Spray Header isolation valve) the accumulator failed its test. This renders HCV-345 inoperable. HCV-344 the opposite header isolation valve also has an air leak that appears to be of similar magnitude to the leak on HCV-345. Fort Calhoun Station is conservatively considering both valves inoperable and has entered technical specification 2.0.1 which requires shutting the plant down to hot standby within 6 hours. The plant shutdown began at 1513 CDT. Repair efforts are underway on HCV-345 and HCV-344."
The leakage on both valves was identified by systems engineering during testing.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1756 EDT ON 10/27/10 FROM AARON CHLADIL TO S. SANDIN * * *
At 1647 CDT, the licensee exited technical specification 2.0.1 after declaring HCV-344 operable. The Unit is currently at 74% power. The licensee will stabilize power at 70% and then commence power escalation.
The licensee informed the NRC Resident Inspector.
Notified R4DO (Proulx).
* * * RETRACTION FROM ERICK MATZKE TO HOWIE CROUCH AT 1155 EST ON 12/17/10 * * *
"Following the original notification, the Fort Calhoun Station reviewed and reanalyzed the acceptance criteria for the subject valve air accumulators. The analysis determined that the valves had been and were operable during the event. Therefore, the report under 10CFR50.72(b)(3)(v)(D) is being retracted."
The licensee has notified the NRC Resident Inspector. Notified R4D0 (Howell).
"During pressure drop testing of the backup nitrogen supply for HCV-345 (Containment Spray Header isolation valve) the accumulator failed its test. This renders HCV-345 inoperable. HCV-344 the opposite header isolation valve also has an air leak that appears to be of similar magnitude to the leak on HCV-345. Fort Calhoun Station is conservatively considering both valves inoperable and has entered technical specification 2.0.1 which requires shutting the plant down to hot standby within 6 hours. The plant shutdown began at 1513 CDT. Repair efforts are underway on HCV-345 and HCV-344."
The leakage on both valves was identified by systems engineering during testing.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1756 EDT ON 10/27/10 FROM AARON CHLADIL TO S. SANDIN * * *
At 1647 CDT, the licensee exited technical specification 2.0.1 after declaring HCV-344 operable. The Unit is currently at 74% power. The licensee will stabilize power at 70% and then commence power escalation.
The licensee informed the NRC Resident Inspector.
Notified R4DO (Proulx).
* * * RETRACTION FROM ERICK MATZKE TO HOWIE CROUCH AT 1155 EST ON 12/17/10 * * *
"Following the original notification, the Fort Calhoun Station reviewed and reanalyzed the acceptance criteria for the subject valve air accumulators. The analysis determined that the valves had been and were operable during the event. Therefore, the report under 10CFR50.72(b)(3)(v)(D) is being retracted."
The licensee has notified the NRC Resident Inspector. Notified R4D0 (Howell).
Power Reactor
Event Number: 46369
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: RANDY FLYNN
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: RANDY FLYNN
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/27/2010
Notification Time: 18:34 [ET]
Event Date: 10/27/2010
Event Time: 00:00 [EDT]
Last Update Date: 10/27/2010
Notification Time: 18:34 [ET]
Event Date: 10/27/2010
Event Time: 00:00 [EDT]
Last Update Date: 10/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
REBECCA NEASE (R2DO)
JOHN LUBINSKI (NRR)
REBECCA NEASE (R2DO)
JOHN LUBINSKI (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY REPORT INVOLVING A SUPERVISOR
A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been denied. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified.
A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been denied. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 46373
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JEREMY HITE
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JEREMY HITE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/27/2010
Notification Time: 16:25 [ET]
Event Date: 10/27/2010
Event Time: 11:07 [EDT]
Last Update Date: 10/28/2010
Notification Time: 16:25 [ET]
Event Date: 10/27/2010
Event Time: 11:07 [EDT]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(c )(2) - SPENT FUEL, HLW OR RX-REL GTCC RED. EFECT
10 CFR Section:
72.75(c )(2) - SPENT FUEL, HLW OR RX-REL GTCC RED. EFECT
Person (Organization):
JOHN CARUSO (R1DO)
JOHN THORP (NRR)
RAYMOND LORSON (NMSS)
JEFFERY GRANT (IRD)
JOHN CARUSO (R1DO)
JOHN THORP (NRR)
RAYMOND LORSON (NMSS)
JEFFERY GRANT (IRD)
| 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 |
SPENT FUEL STORAGE RELATED DEFECT - CASK LEAKAGE RATE GREATER THAN TECHNICAL SPECIFICATION
"On 10/27/10, at 1107 [EDT], troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-68-01 identified that a helium leak exists in the cask lid sealing area at a leak rate greater than allowed by ISFSI Cask Technical Specification Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-O5 ref-cc/sec. The cask was in LOADING OPERATIONS and is currently located within the [Peach Bottom Atomic Power Station] PBAPS Unit 2 containment building. Preliminary review indicates that a leak exists in the Cask Main Lid Outer Closure Seal. The cask will be repaired and tested prior to returning the cask to the Independent Spent Fuel Storage Installation (ISFSI). No release of radiation occurred as a result of this issue.
"This report is being submitted pursuant to 10CFR 72.75(c)(2) as a result of a reduction in the effectiveness of the cask confinement system.
"The Certificate of Compliance for this cask is 1027 (Amendment 0)."
The NRC Resident Inspector has been informed.
"On 10/27/10, at 1107 [EDT], troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-68-01 identified that a helium leak exists in the cask lid sealing area at a leak rate greater than allowed by ISFSI Cask Technical Specification Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-O5 ref-cc/sec. The cask was in LOADING OPERATIONS and is currently located within the [Peach Bottom Atomic Power Station] PBAPS Unit 2 containment building. Preliminary review indicates that a leak exists in the Cask Main Lid Outer Closure Seal. The cask will be repaired and tested prior to returning the cask to the Independent Spent Fuel Storage Installation (ISFSI). No release of radiation occurred as a result of this issue.
"This report is being submitted pursuant to 10CFR 72.75(c)(2) as a result of a reduction in the effectiveness of the cask confinement system.
"The Certificate of Compliance for this cask is 1027 (Amendment 0)."
The NRC Resident Inspector has been informed.