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Event Notification Report for September 20, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/19/2006 - 09/20/2006

** EVENT NUMBERS **


42842 42847 42848 42849

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General Information or Other Event Number: 42842
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: METAL PROCESSORS, INC.
Region: 4
City:  State: MS
County: HINDS COUNTY
License #: GL-384
Agreement: Y
Docket:
NRC Notified By: JEFF ALGEE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/15/2006
Notification Time: 09:33 [ET]
Event Date: 01/18/2006
Event Time: [CDT]
Last Update Date: 09/15/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CLAUDE JOHNSON (R4)
SANDRA WASTLER (NMSS)

Event Text

AGREEMENT STATE REPORT OF DAMAGED ALLOY ANALYZER CONTAINING A CADMIUM-109 SOURCE

The State provided the following information via email:

"DRH [Mississippi Division of Radiological Health] received notification on 8-7-06 from Metal Processors, Inc. that on 1-18-06 a Niton XL 309 Alloy Analyzer containing a 10mCi Cadmium-109 source (Serial # U3278NR6620) was accidentally run over by a company vehicle. Metal Processors personnel collected the device and contacted the manufacturer. The gauge was subsequently leak tested and showed no leakage. The device was sent back to the manufacturer for disposal."

Mississippi Report # MS-06010

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Power Reactor Event Number: 42847
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRAD EKLUND
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/19/2006
Notification Time: 04:08 [ET]
Event Date: 09/19/2006
Event Time: 01:05 [MST]
Last Update Date: 09/19/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BLAIR SPITZBERG (R4)

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

PRESSURIZER HEATER CAPACITY LESS THAN TECH SPEC LIMIT

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"On September 19, 2006, at approximately 01:05 hours Mountain Standard Time (MST), Palo Verde Nuclear Generating Station (PVNGS) Unit 1 commenced a reactor shutdown required by Technical Specification 3.0.3.

"Limiting Condition for Operability (LCO) 3.0.3 requires the unit shall be placed in a Mode or other specified condition in which the LCO is not applicable when an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS.

"LCO 3.4.9 Pressurizer, requires two groups of pressurizer heaters OPERABLE with the capacity of each group > [greater than] 125 Kw and capable of being powered from an emergency power supply. TS LCO 3.0.3 and 3.4.9.B were entered at 22:35 hours an 09/18/06 when the Pressurizer Class Heaters were declared INOPERABLE. Engineering personnel with input from the heater manufacturer informed the Unit 1 SM [Shift Manager] and STA that reasonable assurance of OPERABILITY no longer exists. Prompt Operability Determination research to date concludes that the Heaters will not perform their design function for the specified mission time."

The heaters were meggered and showed low resistance. There is no affect on Units 2 and 3. LCO 3.4.9.B is in affect for modes 1-3. The licensee intends to go to mode 3 and will evaluate continuing to mode 5.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42848
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JOHN YADUSKY
HQ OPS Officer: BILL GOTT
Notification Date: 09/19/2006
Notification Time: 13:09 [ET]
Event Date: 09/19/2006
Event Time: 10:00 [EDT]
Last Update Date: 09/19/2006
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):
JAMES MOORMAN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO GENERATOR LOCKOUT SIGNAL

"At approximately 1000 EDT on September 19, 2006, with the reactor at 100 percent power in Mode 1, the reactor was automatically tripped from a turbine trip due to a generator lockout signal. The cause of this signal is under investigation. The auxiliary feedwater system actuated as expected to stabilize steam generator levels. All systems functioned as required and no other safety systems were actuated. All control rods inserted [fully] on the reactor trip. The operations staff responded to the event in accordance with applicable plant procedures. The plant stabilized at normal operating no-load reactor coolant system temperature and pressure following the reactor trip. Steam generator water levels are being maintained using normal feedwater. All emergency core cooling system equipment is available. The plant electrical system is available and in a normal configuration.

"This condition is being reported as an unplanned reactor protection system actuation and specified system actuation in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."

The MSIVs are open with the steam generators discharging steam to the main condenser using the steam dump valves.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42849
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: BRIAN ROKES
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/19/2006
Notification Time: 16:08 [ET]
Event Date: 09/19/2006
Event Time: 12:08 [EDT]
Last Update Date: 09/19/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
EUGENE COBEY (R1)

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

Event Text

LOSS OF ALL EMERGENCY SIRENS FOR GREATER THAN ONE HOUR

"On September 19, 2006, at approximately 1208 hours, the Emergency Planning Department in conjunction with the Indian Point Energy Center (IPEC) Information Technology (IT) Department determined that all of the 156 sirens in the IPEC Emergency Planning Zone were unavailable due to an inability to activate the sirens through the siren computer operating system. The siren computer operating system was unavailable due to its Oracle Database not responding to a restart command during a routine bi-weekly reboot and preventive maintenance activity. Actions were initiated to recover the siren computer operating system and at approximately 1310 hours, the system was determined to be recovered and a test verified that all 156 sirens could be activated. In accordance with the IPEC reporting procedure, the loss of 16 or more sirens that can not be returned to service in one hour, constitutes a major loss of the offsite notification capability that requires an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(xiii). The Emergency plan has route alerting and public radio announcement available as necessary to notify the public during the time the sirens were not capable of being activated. The condition was recorded in the IPEC corrective action program and actions initiated to investigate and correct the condition. The cause of the failure of the Oracle Database not responding is unknown at this time."

The licensee notified the NRC Resident Inspector and the State and Local Emergency Planning organizations.

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Friday, March 30, 2012