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Event Notification Report for May 11, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/08/2009 - 05/11/2009

** EVENT NUMBERS **


45047 45048 45049 45051 45052

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Power Reactor Event Number: 45047
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: JASON KOZAL
Notification Date: 05/08/2009
Notification Time: 08:02 [ET]
Event Date: 05/08/2009
Event Time: 10:00 [EDT]
Last Update Date: 05/08/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN CARUSO (R1DO)

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

SAFETY PARAMETER DISPLAY SYSTEM OUT OF SERVICE FOR MAINTENANCE

"On May 8, 2009, the Safety Parameter Display System (SPDS) will be removed from service at approximately 1000 hours for Salem Unit 1 to perform planned maintenance to the system. The maintenance consists of the replacement of the uninterruptable power source (UPS) to improve the reliability of the SPDS. The removal of SPDS will also affect the transmission of Salem Unit 1 data from the emergency response data system (ERDS). Appropriate compensatory measures will be in place while SPDS is out of service. SPDS capability is scheduled to be restored using a temporary power feed later today."

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 5/8/2009 AT 1541 FROM JACK OSBORNE TO MARK ABRAMOVITZ * * *

"The Salem Unit 1 Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were returned to service at 1530 hours."

The licensee will notify the NRC Resident Inspector.

Notified the R1DO (Caruso).

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Power Reactor Event Number: 45048
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: VINCE KLCO
Notification Date: 05/08/2009
Notification Time: 15:26 [ET]
Event Date: 05/08/2009
Event Time: 08:17 [EDT]
Last Update Date: 05/08/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
(R1)

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

PRIMARY CONTAINMENT ISOLATION VALVES DISCOVERED OPEN

"At 0817, 4 of the 5 ball valves associated with the Traversing Incore Probe (TIP) system were discovered to be open. In conjunction with explosive shear valves located on each line, these ball valves function to isolate the primary containment upon the receipt of a containment isolation signal. Further investigation revealed that the associated TIP detectors were in the drywell at the indexer. With the TIP detectors in the drywell the detector cable is passing through the ball valves and this condition renders the valves inoperable. This condition had existed for approximately 48hrs and was due to improper shutdown of the system on May 5, 2009.

"This is a violation of technical specification 3.6.3 and resulted in a condition which would have prevented the automatic safety function of the TIP system to control the release of radioactive material during an accident. The explosive shear valves are manually actuated per Operations abnormal procedures should a ball valve not close during accident conditions and remained operable throughout the time the ball valves were impaired.

"At 0937 the TIP detectors were withdrawn to their chamber shields, the ball valves closed and declared operable.

"This event was limited to the TIP system and its associated containment penetrations. Plant operation was not affected. Investigation is in progress and will be entered into the station's corrective action program. There was nothing unusual or not understood. All safety related equipment and systems are operable."

The licensee notified the NRC Resident Inspector.

Notified the R1DO(Caruso).

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Power Reactor Event Number: 45049
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: EDWEN URQUHART
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/08/2009
Notification Time: 17:29 [ET]
Event Date: 05/08/2009
Event Time: 15:15 [EDT]
Last Update Date: 05/08/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
EUGENE GUTHRIE (R2DO)

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

Event Text

INADVERTANT MAIN STEAM ISOLATION WHILE PERFORMING MAINTENANCE

"At 1515 on 5/8/09, a Group 1 isolation signal was received which resulted in all eight Main Steam Isolation Valves closing. The signal was received based upon a valid main condenser low vacuum signal coincident with a main turbine reset signal which opened the turbine stop valves. The reset of the turbine was an unanticipated result of ongoing Mark VI turbine control system processor repair work. The reactor was maintaining hot shutdown while conducting nuclear instrumentation repair. The Group 1 isolation was completed successfully with all MSlVs and small bore valves closing as designed. The condition causing the turbine reset has been cleared and the turbine tripped with all valves closed. The Group 1 isolation signal has been reset and the MSIVs have been re-opened.

"The cause of the turbine reset signal is being investigated by Station Engineering and the on-site GE representative."

The reactor is being taken to cold shutdown for intermediate range nuclear instrument maintenance.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 45051
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DAVID HOLICK
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/08/2009
Notification Time: 17:41 [ET]
Event Date: 05/08/2009
Event Time: 10:45 [PDT]
Last Update Date: 05/08/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
GREG PICK (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 87 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM AFTER LOSS OF GENERATOR SEAL OIL

"At 1045 hours, a manual scram was inserted due to a loss of main generator seal oil pressure and subsequent loss of hydrogen pressure in the Main Generator. Initial investigation revealed that a filter in the seal oil system became clogged during a system test. Even though the test was stopped and the system lineup restored, seal oil system pressure did not return to normal until the main turbine generator was secured. No indications of turbine or generator damage exist.

"All rods fully inserted, MSIVs remained open, no SRVs opened, and all other safety systems operated as designed. Reactor Water Level was restored and maintained with the Reactor Feedwater and Condensate systems during the post scram transient within normal operating bands. Reactor Pressure was controlled using the Main Turbine Bypass Valves in automatic control. Normal cool down to the Main Condenser is in progress. Offsite power is available. EDG-2 was inoperable but available due to surveillance testing, restoration is in progress. All other EDGs are operable and in standby status.

"This shutdown occurred 13 hours before a planned shutdown for the refueling outage, so the plant will not be restarted until after the outage."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 45052
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: EDWEN URQUHART
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/10/2009
Notification Time: 12:52 [ET]
Event Date: 05/10/2009
Event Time: 10:41 [EDT]
Last Update Date: 05/10/2009
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):
EUGENE GUTHRIE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 8 Power Operation 0 Hot Shutdown

Event Text

INTERMEDIATE RANGE REACTOR SCRAM DURING TRANSITION TO RUN

"During Startup of HNP-1, after reaching greater than or equal to 7% RTP [rated thermal power], the crew placed the Reactor MODE switch to 'RUN,' in accordance with the Startup Procedure 34GO-OPS-001-1. Upon placing the MODE switch to 'RUN,' a full RPS actuation occurred due to upscale trip signals on the Intermediate Range Nuclear Instrumentation (IRM) 1C51K601A, 1C51K601D and 1C51K601H. Placing the Reactor MODE switch to 'RUN' bypasses the IRM inputs to the RPS system, so actuation of the RPS from the IRMS was not expected. All withdrawn control rods inserted properly upon receipt of the full SCRAM signal. All equipment functioned as expected, with the exception of the unexpected upscale trips of IRMs 1C51K601A, 1C51K601D and 1C51K601H and the subsequent RPS actuation from the IRMs.

"No reactivity changes were in progress at the time to cause the upscale trip signals. At this time, investigation is in progress, but the investigation and corrective action have not yet been completed.

"The shift crew is progressing to Cold Shutdown, MODE 4 at this time."

The decay heat is being removed by main turbine sealing steam with makeup provided via the control rod drive system. Offsite power is provided by the normal shutdown electrical lineup.

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012