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Event Notification Report for October 31, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/30/2006 - 10/31/2006

** EVENT NUMBERS **


42946 42947 42948 42949

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Power Reactor Event Number: 42946
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARK FIOCCO
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/30/2006
Notification Time: 01:10 [ET]
Event Date: 10/29/2006
Event Time: 20:11 [EST]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAMES NOGGLE (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

AUTOMATIC START OF AUXILIARY FEEDWATER DURING MSIV TESTING

"This is an 8 hour notification being made to report that a valid ESF auxiliary feed actuation occurred. Salem Unit 2 is in Mode 4 with RHR providing shutdown cooling. 21, 22, and 23 reactor coolant pumps are in service providing forced circulation.

"While performing a main steam isolation valve stroke test for maintenance concurrent with main turbine valve surveillance testing, 22 steam generator narrow range level indication shrunk to 7%, which is below the low level trip setpoint of 14%, causing an automatic start of 21 and 22 auxiliary feedwater pumps. There was no other testing or evolutions in progress at the time of the event that contributed to the automatic start of the auxiliary feedwater pumps.

"Steam generator parameters at the time of the event where 0 psig and 223 degrees (T-cold). Main condenser vacuum was established.

"23 auxiliary feedwater pump was tagged for maintenance and did not start.

"22 steam generator level was restored to normal level and the 21 and 22 auxiliary feedwater pumps secured.

"There were no personnel injured."

During this event, the main turbine governor valves were off their closed seats when the MSIVs were stroked.

The licensee notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY STRAUBMULLER TO KOZAL ON 10/31/2006 AT 0146 * * *

"Subsequent to the initial notification, it has been determined that in addition to reporting the auxiliary feedwater pumps starting on low steam generator level, it is required to report that the reactor protection system opened the reactor trip breakers as designed. The reactor trip breakers were closed for surveillance testing of the main turbine. Actuation of the reactor trip breakers is reportable under [10 CFR] 50.72 (b)(3)(iv)(A) for this event."

The licensee notified the NRC Resident Inspector.

Informed R2DO (GRAY)

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Power Reactor Event Number: 42947
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JERRY RISTE
HQ OPS Officer: BILL GOTT
Notification Date: 10/30/2006
Notification Time: 11:56 [ET]
Event Date: 10/30/2006
Event Time: 08:48 [CST]
Last Update Date: 10/30/2006
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):
MARK RING (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 92 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP

"During power operation, at 92% rated power, an automatic reactor trip occurred. The reactor protection signal that caused the reactor trip was steam generator 'B' steam flow greater than feedwater flow coincident with low water level on steam generator 'B.' The cause of the plant transient that led to the reactor trip was a loss of Instrument Bus 1 (Red Channel). Instrument Bus 1 unexpectedly deenergized during the performance of maintenance on the inverter (BRA-111) that feeds Instrument Bus 1.

"Following the reactor trip, the auxiliary feedwater pumps automatically started, as designed, due to a low level in the steam generators.

"After the trip, non-safety related 4160 Volt AC Bus 4 de-energized and secondary plant feedwater heater 15B relief valve lifted. The cause of the loss of Bus 4 and 158 feedwater heater relief lifting Is under Investigation.

"The plant is currently stable and in the hot shutdown (HSD) mode. Power was restored to Instrument Bus 1 at 1018.

"This event is reportable under 10 CFR 50.72(b)(2)(iv)(B) as any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical because of the automatic reactor trip and under 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed below because of the actions of the RPS and the automatic start of the AFW pumps."

All control rods fully inserted. Decay heat is being removed by feeding the steam generators with AFW and steaming to the Condenser Dump.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM T. BUNKELMAN TO W. GOTT AT 1332 EST ON 10/30/06 * * *

"Due to the loss of Bus 4, the running Circulating Water Pump was lost resulting in a loss of normal heat sink to the condenser. The standby Circulating Water Pump was started at 1002 CST and the condenser heat sink was restored."

Until the condenser steam dump was restored, the plant was steaming through the steam generator PORVs (atmospheric steam dumps). There is no steam generator tube leakage.

The licensee notified the NRC Resident Inspector.

Notified R3DO (M. Phillips)

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Power Reactor Event Number: 42948
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KELLI VOELSING
HQ OPS Officer: BILL GOTT
Notification Date: 10/30/2006
Notification Time: 13:47 [ET]
Event Date: 10/30/2006
Event Time: 07:21 [EST]
Last Update Date: 10/30/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MIKE ERNSTES (R2)

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

OFFSITE EMERGENCY SIRENS INOPERABLE

"At approximately 0721, Eastern Standard Time, the Harris Nuclear Plant (HNP) Control Room was informed that the offsite emergency sirens were inoperable. This event requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. The NRC Senior Resident Inspector was informed. The State of North Carolina and all four counties within the 10-mile emergency planning zone were notified and were standing by to implement mobile route alerting if needed, as detailed in the Emergency Plan. Tone Alert Radios for notification of residents within the 5-mile emergency planning zone were also available and operable.

"The most probable cause was a controller malfunction at the microwave tower. This controller was reset at 0600. A successful system interrogation was initiated and restored operability of all sirens following the controller reset. Operability of the offsite emergency sirens was restored at 0922 following two successful silent tests. The State of North Carolina and all four counties within the 10-mile emergency planning zone were notified of system restoration by 1035. The cause of the controller malfunction and required corrective action will be determined in accordance with HNP's Corrective Action Program."

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Power Reactor Event Number: 42949
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/30/2006
Notification Time: 14:25 [ET]
Event Date: 10/30/2006
Event Time: 13:04 [CST]
Last Update Date: 10/30/2006
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DALE POWERS (R4)
PETER WILSON (IRD)
M.J. ROSS-LEE (NRR)
JIM DYER (NRR)
BARNES (DHS)
EACHES (FEMA)
SMITH (DOE)
McCROSSEN (NRC)
BRZOSTEK (USDA)
HARRIS (HHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 67 Power Operation 67 Power Operation

Event Text

ALERT DECLARATION DUE TO ELECTRICAL FIRE AFFECTING ONE ESF TRAIN

At 1304 CT on 10/30/06, the licensee declared an Alert due to a fire in a breaker compartment in safety-related 480 VAC Bus 2B-53. The bus feeder breaker tripped open, resulting in the loss of some safety equipment, including one train of emergency feedwater. The fire was immediately extinguished.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM LICENSEE (D. HAWKINS) TO W. GOTT AT 1950 EST ON 10/30/06 * * *

"ANO-2 Technical Specification 3.6.3.1 action compliance is in progress which includes plans to commence plant shutdown starting at approximately 1908 hours [CT]. Parallel repair efforts are underway to restore the necessary portions of 2B-53 power to allow exiting the Technical Specification 3.6.3.1 LCO's."

The licensee notified the NRC Resident Inspector. Notified R4 DO (D. Powers) and R4 IRC (Kennedy).

* * * UPDATE FROM LICENSEE (D. HAWKINS) TO W. GOTT AT 2046 EST ON 10/30/06 * * *

"At 1925 hours [CT] on 10/30/06, Shutdown of Unit 2 to Hot Standby was commenced in accordance with Technical Specification 3.6.3.1 Action D. This notification satisfies the requirement of 10CFR50.72(b)(2)."

The licensee notified the NRC Resident Inspector. Notified R4 DO (D. Powers) and R4 IRC (Kennedy).

* * * UPDATE FROM LICENSEE (D. HAWKINS) TO W. GOTT AT 2110 EST ON 10/30/06 * * *

"At 1925 hours [CT], Shutdown of Unit 2 was commenced in accordance with Technical Specification 3.6.3.1. The termination criteria of OP-1903.010, Section 6.3 have been met and the Alert has been terminated [at 2000 CST].

The licensee will notify the NRC Resident Inspector. Notified R4 DO (D. Powers), R4 IRC (Kennedy), NRR EO (Lubinski), NSIR (Leach, Blount, Wilson), HQ PAO (Brenner), Comm TA's (Lee, Brown, Skeen, Hatchett, Piccone), EDO Staff (Lamb - message), DHS SWO (Bozzo), FEMA (Casto), DOE (Foote), NRC (McCrossen), USDA (Giles), HHS (Harris)

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