Event Notification Report for December 09, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/08/2011 - 12/09/2011
Power Reactor
Event Number: 47514
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GREG ELKINS
HQ OPS Officer: JOHN KNOKE
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GREG ELKINS
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/09/2011
Notification Time: 13:45 [ET]
Event Date: 12/09/2011
Event Time: 10:46 [EST]
Last Update Date: 12/09/2011
Notification Time: 13:45 [ET]
Event Date: 12/09/2011
Event Time: 10:46 [EST]
Last Update Date: 12/09/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 50 | Power Operation |
UNIDENTIFIED RCS LEAKAGE GREATER THAN 2 GPM INCREASE WITHIN 24 HOURS
"At 0908 [EST] Nine Mile Point Unit 2 received alert alarms for containment monitoring particulate channels. These alarms were accompanied by a rise in drywell floor drain leakage and drywell pressure.
"At 0915 [EST] Nine Mile Point Unit 2 entered technical specification action statement (TS 3.4.5 B) due to unidentified leakage rise of greater than 2 gpm within 24 hours.
"At 1046 [EST] the control room commenced power reduction for shutdown of the plant.
"Peak drywell pressure was approximately 0.16 psig and is lowering since the commencement of plant shutdown. Peak drywell floor drain leakage was approximately 3.7 gpm and is also lowering since the commencement of the plant shutdown. The cause of the rise in unidentified drywell leakage is unknown at this time."
The licensee has notified the NRC Resident Inspector and the state.
"At 0908 [EST] Nine Mile Point Unit 2 received alert alarms for containment monitoring particulate channels. These alarms were accompanied by a rise in drywell floor drain leakage and drywell pressure.
"At 0915 [EST] Nine Mile Point Unit 2 entered technical specification action statement (TS 3.4.5 B) due to unidentified leakage rise of greater than 2 gpm within 24 hours.
"At 1046 [EST] the control room commenced power reduction for shutdown of the plant.
"Peak drywell pressure was approximately 0.16 psig and is lowering since the commencement of plant shutdown. Peak drywell floor drain leakage was approximately 3.7 gpm and is also lowering since the commencement of the plant shutdown. The cause of the rise in unidentified drywell leakage is unknown at this time."
The licensee has notified the NRC Resident Inspector and the state.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 47515
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JAMES PRY
HQ OPS Officer: JOHN KNOKE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JAMES PRY
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/09/2011
Notification Time: 22:41 [ET]
Event Date: 12/09/2011
Event Time: 18:35 [EST]
Last Update Date: 02/06/2012
Notification Time: 22:41 [ET]
Event Date: 12/09/2011
Event Time: 18:35 [EST]
Last Update Date: 02/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PART 21 ISSUE WITH SEISMIC CLIPS ON RCIC SYSTEM CONTROLLERS RESULTS IN SYSTEM INOPERABILITY
"On December 7, 2011, a 10 CFR 21 report (reference NRC EN No. 47498) was received from a vendor for a defect with NUS Controllers. The defect involves spring clips that form part of the seismic restraints for the controllers. The controllers referenced in the report are installed for the Reactor Core Isolation Cooling (RCIC) system in the control room and remote shutdown panel. Based on initial information provided by the vendor, it was determined that the RCIC system remained operable. On December 9, 2011, additional information provided by the vendor did not support the immediate operability determination and the RCIC system was declared inoperable for Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.3 Condition A at 1835 hours [EST]. At 1932 hours [EST], the High Pressure Core Spray system was verified operable per TS LCO 3.5.3 Required Action A.1. TS LCO 3.5.3 Required Action A2 requires restoration of the RCIC system to operable status within 14 days. Qualified spring clips have been obtained and will be installed on the controllers. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(v)(B) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to remove residual heat.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHARLES ELBERFELD TO JOHN KNOKE AT 1415 EST ON 12/10/11 * * *
"As a follow-up to the condition reported above, we have replaced the affected seismic clips on the controllers and the Reactor Core Isolation Cooling system is now operable as of 0734 on December 10, 2011.
"The NRC Resident Inspector has been notified." R3DO (Skokowski) notified.
* * * RETRACTION FROM LLOYD ZERR TO CHARLES TEAL ON 2/6/12 AT 1504 EST * * *
"The vendor provided a seismic report to the station. This report showed that the seismic clips holding the Reactor Core Isolation Cooling (RCIC) controller meet the Operating Basis Earthquake (OBE) test requirements and design requirements for a Safe Shutdown Earthquake (SSE) for Perry. Based on this review, it was determined that the spring clips would function properly during and OBE and SSE. Because the condition reported in Event Number 47515 would not have prevented the fulfillment of the safety function of a system needed to remove residual heat, the condition is not reportable, and this notification is being retracted. The evaluation for this condition is documented in condition report 2011-06531. The NRC Resident Inspector has been informed."
Notified R3DO (Giessner) and Part 21 Group via email.
"On December 7, 2011, a 10 CFR 21 report (reference NRC EN No. 47498) was received from a vendor for a defect with NUS Controllers. The defect involves spring clips that form part of the seismic restraints for the controllers. The controllers referenced in the report are installed for the Reactor Core Isolation Cooling (RCIC) system in the control room and remote shutdown panel. Based on initial information provided by the vendor, it was determined that the RCIC system remained operable. On December 9, 2011, additional information provided by the vendor did not support the immediate operability determination and the RCIC system was declared inoperable for Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.3 Condition A at 1835 hours [EST]. At 1932 hours [EST], the High Pressure Core Spray system was verified operable per TS LCO 3.5.3 Required Action A.1. TS LCO 3.5.3 Required Action A2 requires restoration of the RCIC system to operable status within 14 days. Qualified spring clips have been obtained and will be installed on the controllers. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(v)(B) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to remove residual heat.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHARLES ELBERFELD TO JOHN KNOKE AT 1415 EST ON 12/10/11 * * *
"As a follow-up to the condition reported above, we have replaced the affected seismic clips on the controllers and the Reactor Core Isolation Cooling system is now operable as of 0734 on December 10, 2011.
"The NRC Resident Inspector has been notified." R3DO (Skokowski) notified.
* * * RETRACTION FROM LLOYD ZERR TO CHARLES TEAL ON 2/6/12 AT 1504 EST * * *
"The vendor provided a seismic report to the station. This report showed that the seismic clips holding the Reactor Core Isolation Cooling (RCIC) controller meet the Operating Basis Earthquake (OBE) test requirements and design requirements for a Safe Shutdown Earthquake (SSE) for Perry. Based on this review, it was determined that the spring clips would function properly during and OBE and SSE. Because the condition reported in Event Number 47515 would not have prevented the fulfillment of the safety function of a system needed to remove residual heat, the condition is not reportable, and this notification is being retracted. The evaluation for this condition is documented in condition report 2011-06531. The NRC Resident Inspector has been informed."
Notified R3DO (Giessner) and Part 21 Group via email.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 47522
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: VINCE KLCO
Notification Date: 12/13/2011
Notification Time: 19:43 [ET]
Event Date: 12/09/2011
Event Time: 11:59 [CST]
Last Update Date: 01/26/2012
Notification Time: 19:43 [ET]
Event Date: 12/09/2011
Event Time: 11:59 [CST]
Last Update Date: 01/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BILLY DICKSON (R3DO)
BILLY DICKSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION- DEGRADED FIRE BARRIER BETWEEN FIRE AREAS
"A degraded fire barrier between Fire Area (FA) 118 (Bus 26 Room) and FA 128 (Bus 27 Room) has existed during the last three years. The top of the wall between the Bus 26 and Bus 27 room had a missing/degraded fire barrier. At the time of discovery on December 9, 2011 a fire watch was in place. However, it was determined that at various times during the last three years a fire watch was not established.
"Bus 27 has been conservatively aligned to Bus 26 to provide the required degree of separation for redundant safe shutdown trains (between Bus 26 and Bus 25). The fire watch will remain in place as a compensatory measure until the fire barrier is repaired.
"[The] NRC Resident [Inspector] has been informed."
* * * RETRACTION FROM BRIAN JOHNSON TO JOE O'HARA AT 1555 EST ON 1/26/12 * * *
"An eight hour report per 10 CFR 50.72(b)(3)(ii)(B) was reported on December 13, 2011 for a degraded fire barrier between Fire Area (FA) 118 (Bus 26 Room) and FA 128 (Bus 27 Room.)
'Subsequent engineering analysis determined that the degraded fire barrier maintained the required degree of separation for redundant safe shutdown trains and plant safety was not significantly degraded. The 10 CFR 50.72(b)(3)(ii)(B) report is retracted.
"The NRC Resident Inspector has been informed."
Notified R3DO (L. Kozak)
"A degraded fire barrier between Fire Area (FA) 118 (Bus 26 Room) and FA 128 (Bus 27 Room) has existed during the last three years. The top of the wall between the Bus 26 and Bus 27 room had a missing/degraded fire barrier. At the time of discovery on December 9, 2011 a fire watch was in place. However, it was determined that at various times during the last three years a fire watch was not established.
"Bus 27 has been conservatively aligned to Bus 26 to provide the required degree of separation for redundant safe shutdown trains (between Bus 26 and Bus 25). The fire watch will remain in place as a compensatory measure until the fire barrier is repaired.
"[The] NRC Resident [Inspector] has been informed."
* * * RETRACTION FROM BRIAN JOHNSON TO JOE O'HARA AT 1555 EST ON 1/26/12 * * *
"An eight hour report per 10 CFR 50.72(b)(3)(ii)(B) was reported on December 13, 2011 for a degraded fire barrier between Fire Area (FA) 118 (Bus 26 Room) and FA 128 (Bus 27 Room.)
'Subsequent engineering analysis determined that the degraded fire barrier maintained the required degree of separation for redundant safe shutdown trains and plant safety was not significantly degraded. The 10 CFR 50.72(b)(3)(ii)(B) report is retracted.
"The NRC Resident Inspector has been informed."
Notified R3DO (L. Kozak)