| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/11/2009 - 12/14/2009 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 45464 | Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: KEVIN COUGHLIN
HQ OPS Officer: VINCE KLCO | Notification Date: 10/23/2009
Notification Time: 22:23 [ET]
Event Date: 10/23/2009
Event Time: 17:41 [EDT]
Last Update Date: 12/11/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 83 | Power Operation | 60 | Power Operation | Event Text STEAM GENERATOR SAFETY RELIEF VALVES DID NOT OPEN AT REQUIRED SETPOINT
"Online testing of the secondary side pressure relief valves revealed that 3 valves did not open at the required pressure set point on the initial tests. All valves did open on subsequent tests at a higher pressure and have been restored to operable status. These 3 valves and 3 other similar valves were installed during the last refueling outage and it is concluded that all 6 valves have the same set point drift failure mechanism. All 6 valves are assumed to have been inoperable at some time during the last operating cycle. The steam generator design analysis specifies a minimum pressure relief capability to prevent a failure of the steam generator and subsequent potential loss of decay heat removal capability. This condition could have prevented the fulfillment of the safety function needed to remove residual heat. An engineering analysis is in progress to determine the actual impact on the safety function.
"Per Technical Specifications 3.4.1.2.3, reactor power was reduced to below 66.3% due to the remaining 3 inoperable relief valves."
The licensee notified the NRC Resident Inspector.
* * * EVENT RETRACTION FROM ADAM MILLER TO DONALD NORWOOD AT 1130 EST ON 12/11/2009 * * *
"In addition to the 6 valves discussed in EN 45464, an additional valve was found to be inoperable. Thus, it is assumed that 7 of the 18 secondary side pressure relief valves were inoperable at some time during the last operating cycle. An engineering analysis has determined that the inoperable secondary side pressure relief valves did not result in a condition that could have prevented the fulfillment of the safety function needed to remove residual heat. The impact of the inoperable secondary side pressure relief valves on the steam generators and associated secondary side piping integrity was assessed by comparison to an existing analysis. A qualitative assessment of that analysis indicates that with the reduced steam relief capacity, the pressure in the steam generators and associated secondary side piping would remain below the ASME code allowable. Thus, there would have been no failure of the steam generators and no subsequent potential loss of decay heat removal capability. Therefore, this event does not meet the criteria of 50.72(b)(3)(v)(B) and is being retracted. This event will be reported as a 60 day LER in accordance with 10CFR50.73(a)(2)(i)(B)."
The licensee notified the NRC Resident Inspector.
Notified R1DO (Holody). |
| Power Reactor | Event Number: 45564 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [ ] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: STEVE NELSON
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/12/2009
Notification Time: 04:48 [ET]
Event Date: 12/12/2009
Event Time: 01:26 [PST]
Last Update Date: 12/12/2009 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
BLAIR SPITZBERG (R4DO)
TIM McGINTY (NRR)
JACK GROBE (NRR)
ELMO COLLINS (R4 E)
JEFFERY GRANT (IRD)
JEROME KETTLES (DHS)
DENNIS VIA (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 90 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING INOPERABLE
A declaration of Unusual Event per EAL D.1-1 was made at 0126 PST on 12/12/09 due to both EDGs being inoperable. This condition places the Unit in a required Technical Specification Shutdown condition and the Unit is proceeding to shutdown.
Train "B" EDG was declared inoperable at 0025 PST on 12/11/09 due to annunciator issues associated with the EDG. The cause of the annunciator issues has still not been identified. This placed the licensee into the Action Statement for LCO 3.8.1 that required verification of operability of the Train "A" EDG within 24 hours. During the operability test of the Train "A" EDG, the diesel failed to reach voltage and frequency (the EDG tripped on startup) and it was also declared inoperable. As a result, the licensee entered Action F of LCO 3.8.1 and is required to be in Mode 3 within 6 hours and Mode 5 within 36 hours.
The licensee declared the UE at 0126 and commenced power reduction. Mode 3 must be reached by 0625 PST on 12/12/09 and Mode 5 must be reached by 1225 on 12/13/09.
Besides the EDGs, all other safety related systems are operable.
The licensee has notified State and local authorities and the NRC Resident Inspector.
* * * UPDATE FROM GEOFF COOK TO DONALD NORWOOD AT 0918 EST ON 12/12/2009 * * *
"On December 12, 2009, at about 0025 PST, SONGS Unit 3 Emergency Diesel Generator (EDG) 3G002 was determined to be inoperable. EDG 3G003 had been declared inoperable prior to this, resulting in both Unit 3 EDGs being inoperable.
"At about 0025 on December 11, 2009, EDG 3G003 (Train 'B') was declared inoperable as a result of work being done on an annunciator power supply. SONGS Technical Specifications (TS), section 3.8.1.B, requires that the associated EDG, 3G002 (Train 'A') be tested within 24 hours to ensure that the EDG was also not inoperable due to a common cause. On December 12, 2009, at about 0025, EDG 3G002 was declared inoperable when it did not achieve required voltage and frequency during an attempted start.
"SCE is reporting this occurrence as a loss of safety function in accordance with 10 CFR 50.72(b)(3)(v).
"The loss of both EDGs on Unit 3, per TS 3.8.1.E, requires restoration of one EDG within 2 hours. This action was not met, and as a result TS 3.8.1.F required the unit to be shutdown to Mode 3 within 6 hours. This shutdown action began at 0126 PST. Also, pursuant to the SONGS Emergency Plan, the shutdown of Unit 3 under TS 3.8.1.F required declaration of an Unusual Event. Both the TS required shutdown action and the declaration of the Unusual Event were reported to the NRC pursuant to 10CFR50.72 in an earlier notification (same NRC Operations Log #45564).
"SCE is taking actions to restore one of the EDGs to operability. At the time of this occurrence, Unit 2 was in a Steam Generator Replacement Outage, and Unit 3 was at approximately 100% power proceeding to a Mode 3 shutdown.
"The NRC Resident Inspector has been notified of this occurrence and will be provided with a copy of this report."
Notified R4DO (Spitzberg).
* * * UPDATE FROM DOUG KNUDSON TO BILL HUFFMAN AT 1021 EST ON 12/12/2009 * * *
The licensee exited their Unusual Event [and TS required shutdown] at 0645 PST based on restoration of operability of the "B" Train EDG. The "B" Train EDG annunciator issue was repaired and the EDG started and load tested per Technical Specification requirements. The EDG was declared operable at 0511 PST. The licensee is currently holding at 40% and planning to return to full power. Investigation into the starting problem of the "A" Train EDG is still ongoing.
The licensee has notified the NRC Resident Inspector, State and local authorities.
R4DO(Spitzberg), NRR(McGinty), and IRD MOC (Grant) notified. Also notified DHS (Inzer) and FEMA (Via). |
| Power Reactor | Event Number: 45565 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BRANNON PAYNE
HQ OPS Officer: CHARLES TEAL | Notification Date: 12/12/2009
Notification Time: 20:44 [ET]
Event Date: 12/12/2009
Event Time: 18:45 [CST]
Last Update Date: 12/12/2009 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
REBECCA NEASE (R2DO)
LUIS REYES (R2 R)
VICTOR MCCREE (R2 D)
JEFFERY GRANT (IRD)
TIM McGINTY (NRR)
JAY KETTLES (DHS)
ERWIN CASTO (FEMA)
ERIC LEEDS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 97 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO A FIRE IN THE CCW HEAT EXCHANGER
The licensee declared an Unusual Event at 1845 CST due to a fire greater than 15 minutes in the CCW heat exchanger room. The fire suppression system actuated as designed and the site fire brigade responded . There were no injuries or equipment damage. The fire is out and the licensee is monitoring the area. The licensee reduced power per their plant response procedures. The plant is stable and remains in Mode 1.
The licensee has notified the State and local authorities and the NRC Resident Inspector.
* * * UPDATE FROM BRANNON PAYNE TO JOHN KNOKE AT 2243 EST ON 12/12/09 * * *
The licensee exited the Unusual Event at 2036 CST, based on the fact that no equipment was damaged. The fire was believed to be from some hot work in the area igniting combustible material.
The licensee will be notifying the NRC Resident Inspector.
Notified R2DO (Nease), NRR EO (McGinty) email only, DHS (Kettles), FEMA (Casto). | |