| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/28/2005 - 10/31/2005 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41995 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BERNARD LITKETT
HQ OPS Officer: ARLON COSTA | Notification Date: 09/14/2005
Notification Time: 23:38 [ET]
Event Date: 09/14/2005
Event Time: 21:38 [EDT]
Last Update Date: 10/30/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JAMES TRAPP (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM FAILED SURVEILLANCE TESTING
"On 9/14/05 at 2138, the High Pressure Coolant Injection (HPCl) system was declared inoperable. The HPCI Pump In Service Surveillance Test was in progress with system flow and speed being adjusted to establish surveillance test conditions. Speed and flow oscillations were observed when turbine speed approached 3900 rpm. Since speed and flow oscillations prevented the establishment of surveillance test conditions, HPCI was declared inoperable. Evaluations of these speed and flow oscillations are ongoing.
"Loss of the HPCI is reportable under 10CFR50.72(b)(3)(v) as loss of a single train safety system required to mitigate the consequences of an accident. No additional Emergency Core Cooling Systems or Safety Related equipment was inoperable during this time period."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM LICENSEE (BREADY) TO NRC (HUFFMAN) AT 11:38 EST ON 10/30/05 * * *
"Evaluation of the HPCI system speed and flow oscillations concluded that the HPCI system was capable of mitigating the consequences of an accident. Therefore this event is not reportable under 10 CFR 50.72(b)(3)(v) as a loss of a single train safety function and is being retracted."
The licensee will notify the NRC Resident Inspector. R1DO (Silk) notified. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42072 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: ARLON COSTA | Notification Date: 10/24/2005
Notification Time: 12:41 [ET]
Event Date: 10/21/2005
Event Time: 09:00 [EDT]
Last Update Date: 10/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
CHRISTINE LIPA (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 | Event Text UNANALYZED CONDITION DUE TO RELOCATION OF A FIRE DOOR BOUNDARY
"This event is being reported as 10CFR50.72(b)(3)(ii)(B), an unanalyzed condition that significantly degrades plant safety. A postulated fire water system line break did not take into consideration the movement of a fire door boundary. Consequently, the break may affect safe shutdown of the plant. The door boundary was moved in May 1999.
"While assessing a calculation to update fire pump curves (CR 04-00422-04) it was found that the calculation does not appear to have been updated for the tornado depressurization event modifications (DCP 99-05014). Specifically, door DG-112 was moved to the control complex wall from the diesel generator wall. This door movement isolates the rattle space that was previously credited as a relief path for this internal flood.
"A full break is postulated for this line as the result of a safe shutdown earthquake. As the result of the postulated pipe break, both fire protection pumps are expected to auto start resulting in a break flow rate into the hallway of approximately 6,000 gpm. Standard Perry design practice is to assume a 30 minute duration for the pipe break flow isolation unless justified otherwise.
"The line in question was isolated at 2027 on 10/21/05. The valves are being maintained closed under administrative controls."
The licensee notified the NRC Resident Inspector.
**** RETRACTION ON 10/28/05 AT 1748 EDT FROM H. KELLY TO P. SNYDER ****
"An 8-hour notification was made on October 24, 2005 under 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades plant safety. The report was made due to a postulated break for a non-safety non-seismic fire water pipe that could possibly affect safe shutdown of the plant.
"An evaluation was completed on October 28, 2005. This evaluation confirmed that the current plant configuration is consistent with the design basis. The evaluation used for the original event notification assumed a full break of the involved piping. Perry design basis for this moderate energy system is a leakage crack. The postulated leakage from the crack in the piping remains within design basis and does not significantly degrade plant safety. Since Perry remains in compliance with design basis and there is no unanalyzed condition that significantly degrades plant safety, there is no reportable condition. Therefore, ENF 42072 is retracted."
The licensee notified the NRC Resident Inspector. Notified R3DO (Lipa). |
| Power Reactor | Event Number: 42093 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICH KLINEFELTER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/29/2005
Notification Time: 01:44 [ET]
Event Date: 10/28/2005
Event Time: 23:32 [EDT]
Last Update Date: 10/29/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
DAVID SILK (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 18 | Power Operation | 18 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE CONTROL RODS
"On 10/28/2005, Susquehanna Unit 1 operators began the process of shutting down the unit for a maintenance outage to address control cell friction. It was expected that during this evolution, "slow to settle" control rods would be encountered, and rather than delay the continuance of the shutdown to perform operability testing, it was determined that these control rods would conservatively be declared inoperable. Based on previous testing data and trending analysis of operability testing performed during the cycle, PPL [Pennsylvania Power and Light] believes that the subject control rods would have passed operability tests.
"Accordingly, at 2332 EDT, Technical Specification 3.1.3.f was entered which requires the unit to be taken to Mode 3 in 12 hours when nine or more control rods are inoperable. Entry into this specification was also required per 3.1.3.e when it was determined that four inoperable rods resided within one Banked Position Withdrawal Sequence (BPWS) group. The inoperable control rods are fully inserted and disarmed, shutdown margin requirements are met, and the control rod system was always fully capable of performing its safety function.
"At the time when the ninth control rod was declared inoperable, Unit One was operating at 18% power. Unit Two is continuing operation at 100% power.
"PPL is reporting this event as a Technical Specification required shutdown per 10CFR 50.72(b)(2)(i).
"The NRC Resident Inspector was notified by the licensee."
Unit 2 is not affected by this problem and will continue to operate at 100% power.
* * * UPDATE FROM LICENSEE (ILLIADIS) TO NRC HUFFMAN AT 1011 EDT ON 10/29/05 * * *
"At 0744 the plant reached All Rods In and at 0805 entered Mode 3 in accordance with plant procedures to fulfill the requirement of Technical Specification 3.1.3. As stated in the original EN# 42093, it was expected that during this evolution, "slow to settle"' control rods would be encountered, and rather than delay the continuance of the shutdown to perform operability testing, it was determined that these control rods would conservatively be declared inoperable. This action was taken on a total of 41 control rods that failed to settle at position 00 during the shutdown. There are 4 additional control rods that were declared inoperable previously during the cycle and subsequently settled to 00. Of the 41 control rods that failed to settle at the time of the shutdown, 6 have settled to 00 at the time of this update.
"Based on previous testing data and trending analysis of operability testing performed during the cycle, PPL continues to believe that the subject control rods would have passed operability tests. The inoperable control rods are fully inserted, shutdown margin requirements are met, and the control rod system was always fully capable of performing its safety function.
"There were no ECCS initiations and no challenges to containment."
The licensee notified the NRC Resident Inspector. R1DO (Silk) notified. |
| Power Reactor | Event Number: 42094 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: BILL BANDHAUER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/29/2005
Notification Time: 04:39 [ET]
Event Date: 10/29/2005
Event Time: 01:26 [EDT]
Last Update Date: 10/29/2005 | 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
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 16 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FOLLOWING LOSS OF FEEDWATER PUMPS
"This event is reportable under 10 CFR 50.72 (b)(2)(iv)(B) and 10 CFR 50.72 (b)(3)(iv)(B)(6). During a plant shutdown for a refueling outage at 0126 [EDT] on October 29, a manual reactor trip was initiated in anticipation of Critical Operation on Emergency Feedwater. CR3 [Crystal River Unit 3] experienced an automatic Emergency Feedwater Actuation based upon a loss of both Main Feedwater Pumps. Main Feedwater Pumps tripped on a loss of the running Main Feedwater Booster Pump, which was automatically tripped on low Feedwater De-aerator Tank level. The redundant Main Feedwater Booster Pump was shutdown as part of the plant shutdown sequence. The low Feedwater De-aerator Tank level occurred due to a loss of the operating Condensate Pump while the redundant Condensate Pump was tagged out of service for scheduled maintenance."
The cause of the failed condensate pump that initiated the event sequence is still under investigation but the licensee indicated that it appears to be due to a mechanical failure.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42096 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: AL DEES
HQ OPS Officer: PETE SNYDER | Notification Date: 10/29/2005
Notification Time: 14:51 [ET]
Event Date: 10/29/2005
Event Time: 13:25 [EDT]
Last Update Date: 10/30/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
STEPHEN CAHILL (R2)
TOM BLOUNT (IRD)
JOHN HANNON (NRR)
VINNY GOMEZ (DHS)
JIM DUNKER (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text UNUSUAL EVENT - MAIN TRANSFORMER FIRE
"NUE declared on Hatch Unit 1 due to a fire on the main transformer lasting greater than 10 minutes. Unit 1 reactor scram on main turbine trip. Group 2 PCIV (Primary Containment Isolation Valves) isolation on low reactor water level (+3 inches). All group 2 valves closed as required. Fire extinguished at 1358 hours. Plant is stable."
All control rods fully inserted on the reactor scram. The plant is in hot shutdown steaming through the turbine bypass valves to the main condenser. No safety systems are affected. Emergency electrical buses are on normal offsite power and emergency diesel generators are available if required. The onsite fire brigade responded to the fire and the fire suppression system for the main transformer functioned as expected.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM E. BURKETT TO W. GOTT AT 1950 ON 10/29/05 * * *
The licensee is still in a NUE. The fire is out. The fire reflashed at 1603 when the deluge system was secured to inspect the transformer. The deluge system was restarted immediately. Offsite fire support have responded. Cleanup efforts are in progress.
The licensee notified the NRC Resident Inspector.
Notified IRD (Blount), R2DO (Cahill), and NRR EO (J. Hannon).
* * * UPDATE FROM E. BURKETT TO P. SNYDER AT 2010 ON 10/29/05 * * *
The licensee is still in a NUE. This call is to add an offsite notification per 10 CFR 72.75 (b)(2) to another government agency. The site chemistry department notified the National Response Center (Coast Guard) at 1636 that the site had discharged an unknown quantity of oil into the Altamaha River and was implementing site spill control and countermeasures procedures. The licensee also notified the Georgia Environmental Protection Division.
The licensee notified the NRC Resident Inspector.
Notified IRD (Blount), NRR EO (J. Hannon), and R2DO(Cahill).
* * * UPDATE FROM E. BURKETT TO W. HUFFMAN AT 0021 EDT ON 10/30/05 * * *
The licensee reports that the fire is confirmed extinguished (i.e., no risk of reflash) based on long term monitoring of the transformer including thermography measurements. The Unit remains in an Unusual Event until assessment activities related to the transformer fire have been completed.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM E. BURKETT TO W. HUFFMAN AT 0105 EDT ON 10/30/05 * * *
Based on the results of assessment activities related to the transformer fire, the licensee has exited the Unusual Event at 0050. The licensee notified the NRC Resident Inspector. The R2DO (Cahill), EO (Hannon), IRD (Blount), DHS (Doyle), and FEMA (Bisco) have been notified. |
| Power Reactor | Event Number: 42097 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/30/2005
Notification Time: 03:05 [ET]
Event Date: 10/30/2005
Event Time: 01:50 [EDT]
Last Update Date: 10/30/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text SPDS UNAVAILABLE FOR GREATER THAN ONE HOUR
The Unit 2 SPDS (Safety Parameter Display System) was unavailable from 0050 EDT to 0300 EST on 10/30/05. The cause of the unavailability is believe to have been related to software updates. The condition has been corrected and the system is back in service. This item is reportable per the licensee's procedures whenever SPDS is out of service for more than one hour.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42098 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: POUL CHRISTIANSEN
HQ OPS Officer: BILL GOTT | Notification Date: 10/30/2005
Notification Time: 23:28 [ET]
Event Date: 10/30/2005
Event Time: 19:50 [EST]
Last Update Date: 10/30/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
STEPHEN CAHILL (R2)
LANCE ENGLISH email (TAS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION
"On October 30, 2005, at 1950 an altercation occurred between two contract personnel. The event occurred inside the protected area, but outside the radiation controlled area. The event took place in a temporary building used as a dress out area for the Unit 1 refueling outage. One of the two people suffered a minor cut to his arm. There was no contamination related to this incident. FPL Security escorted the two individuals off site and revoked their plant access. The local St. Lucie County Sheriff department was called and is investigating the event. One person has been arrested for simple battery and is in custody of the St. Lucie County Sheriff Department. This NRC notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) due to the notification of the St. Lucie County Sheriff Department."
The licensee notified the NRC Resident Inspector. | |