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Event Notification Report for May 11, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/10/2011 - 05/11/2011

** EVENT NUMBERS **


46766 46826 46833 46837 46839

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Power Reactor Event Number: 46766
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDALL RAHRIG
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/19/2011
Notification Time: 00:44 [ET]
Event Date: 04/18/2011
Event Time: 23:09 [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MONTE PHILLIPS (R3DO)

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

Event Text

PLANT PROCESS COMPUTER REMOVED FROM SERVICE FOR PLANNED REPLACEMENT

"At 2309 [CDT] on April 18, 2011, the Unit 2 Plant Process Computer (PPC) was removed from service for planned replacement in the current Unit 2 refueling outage. The Unit 2 PPC feeds the Safety Parameter Display System (SPDS) used in the Main Control Room (MCR) and the Technical Support Center (TSC). The Unit 2 PPC also feeds the Emergency Response Data System (ERDS). The Unit 1 and Unit 2 PPCs also feed the Plant Parameter Display System (PPDS) used in the MCR, TSC and Emergency Operations Facility (EOF). Meteorological data will remain available. The dose assessment program will remain functional as the Unit 1 Plant Process computer will be capable of providing the necessary data through PPDS to run the program. The dose assessment program is not affected by the Unit 2 PPC being out of service. As compensatory measures, the backup method to fax or communicate via a phone circuit applicable data to the NRC, TSC and EOF exists. There is no impact to the Emergency Notification System (ENS) or Health Physics Network (HPN) communications systems.

"The new Unit 2 PPC is scheduled to be functional on April 23, 2011. However, based on the mode Unit 2 will be in, this will limit the number of points that would provide usable data. The Unit 2 PPC will be tested as mode changes occur. The Unit 2 PPC is planned to be declared functional by Mode 2. A follow-up ENS call will be made once the Unit 2 PPC is declared functional.

"The loss of SPDS and ERDS is a 'major loss of assessment capability' and is reportable under 10CFR50.72(b)(3)(xiii).

"The NRC Senior Resident Inspector and the State of Illinois (through the Illinois Emergency Management Agency Resident Inspector) have been notified of this ENS call."

* * * UPDATE FROM SCOTT BUTLER TO JOE O'HARA AT 0932 ON 5/10/11 * * *

"As of 0815 CT on May 10, 2011, the Unit PPC is considered operational with respect to the Safety Parameter Display System (SPDS), Plant Parameter Display System (PPDS) and Emergency Response Data System (ERDS). Therefore, a Major Loss of Assessment Capability no longer exists on Unit 2. The EP Manager will contact the NRC Computer Center today to conduct an ERDS test for Unit 2 to ensure the data is being satisfactorily sent to the NRC.

"The NRC Resident Inspector and the State of Illinois (through the Illinois Emergency Management Agency Resident Inspector) have been notified of this ENS update.


Notified R3DO(Passehl)

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Agreement State Event Number: 46826
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SHELL OIL
Region: 4
City: HOUSTON State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB FREE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/06/2011
Notification Time: 13:05 [ET]
Event Date: 06/15/2010
Event Time: [CDT]
Last Update Date: 05/06/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK LEVEL GAUGE SHUTTER

In June 2010, Shell identified a stuck level gauge shutter during scheduled maintenance testing. The licensee removed the gauge from service.

"The licensee intends to leave the gauge secured in storage until an undetermined future date when it is needed. This facility is a research facility and uses the gauge in its research and testing operations."

The gauge was a Berthold Model LB-440 with a 50 milliCurie Cs-137 source.

Texas Report Number: I-8842

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Power Reactor Event Number: 46833
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DUANE BISTODEAU
HQ OPS Officer: JOE O'HARA
Notification Date: 05/10/2011
Notification Time: 09:10 [ET]
Event Date: 05/10/2011
Event Time: 09:15 [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVE PASSEHL (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

LOSS OF EMERGENCY ASSESSMENT CAPABILITY

"Dose assessment cannot be performed onsite.

"Pursuant to 10CFR50.72 (b)(3)(xiii), Monticello Nuclear Generating Plant is reporting a planned loss of emergency assessment capability scheduled for 0915 hours on May 10, 2011 for system maintenance. Dose assessment in the control room, TSC, and EOF are non-functional. Main meteorological tower data is unavailable. Projected outage duration is approximately 7 hours. Control room and local instrumentation/annunciation remain available for accident assessment. Telephone lines remain available between site emergency response facilities and offsite agencies for communication of plant status information. Dose assessment capabilities will exist at the backup EOF. Backup meteorological data will be available in the control room, TSC, and EOF. "

The licensee will not be in any Technical Specification action statements as a result of this evolution.

The NRC Resident Inspector has been notified.

* * * UPDATE FROM JEFF OLSON TO PETE SNYDER ON 5/10/11 AT 1650 EDT * * *

The licensee has restored their dose assessment capability.

Notified R3DO (Passehl).

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Power Reactor Event Number: 46837
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN MACDONALD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/10/2011
Notification Time: 16:15 [ET]
Event Date: 05/10/2011
Event Time: 13:15 [EDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ANNE DEFRANCISCO (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 4 Startup 0 Hot Shutdown

Event Text

REACTOR PROTECTION SYSTEM ACTUATION DURING START-UP

"At 1315 hours on Tuesday, May 10, 2011, with the Reactor Mode Select Switch in Startup, the Reactor Protection System (RPS) actuated due to a valid Hi-Hi trip signal from the Intermediate Range Monitors (IRMs) of the Neutron Monitoring System. At the time of the RPS actuation, reactor thermal power was four (4)% and control rods were being withdrawn as part of a planned reactor startup from a refueling outage. The RPS actuation signal resulted in a reactor scram. The IRMs were in range 7 when the scram occurred.

"All control rods automatically inserted in accordance with design. No other ESF actuation signals were generated. The reactor scram was not part of pre-planned test or reactor operation. The cause of the Hi-Hi IRM trip signal is under investigation.

"This event had no impact on the health and/or safety of the public.

"The licensee has notified the NRC Senior Resident Inspector.

"This 4-hour notification is being made in accordance with 10CFR50.72(b)(2)(iv)(B)."

The unit is in a normal post trip electrical alignment. Decay heat is being removed via the main steam line drains to the main condenser.

The licensee will notify the Massachusetts Emergency Management Agency.

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Power Reactor Event Number: 46839
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: JOE O'HARA
Notification Date: 05/11/2011
Notification Time: 01:21 [ET]
Event Date: 05/09/2011
Event Time: 15:18 [EDT]
Last Update Date: 05/11/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
EUGENE GUTHRIE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

POTENTIAL VALVE MISPOSITIONING LED TO A CONDITION PROHIBITED BY TECHNICAL SPECIFICATIONS

"On May 9, 2011, at 1518 Eastern Daylight Saving Time (EDT), WBN [Watts Bar Nuclear] started a Safety Injection Pump and began to inject into the Reactor Coolant System contrary to Technical Specification Limiting Condition for Operation 3.4.12, which requires in part for Mode 5 that a Cold Overpressure Mitigation System (COMS) shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated.

"The RCS pressure rise was recognized immediately, and the pump was secured within 27 seconds. The pressure reached a maximum of 328 psig. which is below the relief valve setpoint, so no structure, system, or component pressure limit was exceeded at any time. LCO 3.4.12 Condition A was entered immediately. At 1521, the pump breaker was directed to be racked out, and the breaker was reported racked out and verified by 1600, at which time LCO 3.4.12 was exited.

"This event was determined to be reportable as a condition prohibited by Technical Specifications in accordance with 10 CFR 50.73(a) (2)(i)(b). This notification is made in accordance with Watts Bar License condition 2.G.

"The NRC Resident Inspector has been notified of this event and event notification."

The licensee is investigating the likelihood of a valve mispositioning.

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Thursday, March 29, 2012