United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2008 > January 14

Event Notification Report for January 14, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/11/2008 - 01/14/2008

** EVENT NUMBERS **


43894 43895 43896 43897 43898 43899 43900 43901 43902

To top of page
Power Reactor Event Number: 43894
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG EVANS
HQ OPS Officer: PETE SNYDER
Notification Date: 01/11/2008
Notification Time: 15:46 [ET]
Event Date: 01/11/2008
Event Time: 15:10 [EST]
Last Update Date: 01/11/2008
Emergency Class: UNUSUAL EVENT
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
MALCOLM WIDMANN (R2)
MARY JANE ROSS-LEE (NRR)
JEFFREY CRUZ (IRD)

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

DISCOVERY OF AN AFTER THE FACT UNUSUAL EVENT

At 1510, "[Watts Bar Nuclear (WBN)] had identified RCS leakage in excess of 25 gallons per minute (gpm). The leakage was estimated at 105 gpm. This is a report notification only and not a declaration. The EAL that was exceeded was 2.6, RCS identified leakage. While placing a mixed bed demineralizer in service VCT level was observed to have dropped 10%. The demineralizer was immediately removed from service. This terminated the drop in VCT level. In accordance with WBN EPIP-1 Emergency Classification Flowchart, section 3.0 step 3.3.7, if an EAL was exceeded but the emergency has been totally resolved (prior to declaration), the emergency condition that was appropriate shall not be declared but reported only. The duration of the leakage was approximately 15 minutes. The unit remains at mode 1 and 100% power. The cause for the unexpected level decrease is under investigation at this time. There were no radiological releases associated."

The licensee will notify the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43895
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOE O'HARA
Notification Date: 01/11/2008
Notification Time: 17:53 [ET]
Event Date: 01/11/2008
Event Time: 16:22 [CST]
Last Update Date: 01/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
RUSSELL BYWATER (R4)

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

TECH. SPEC. REQUIRED SHUTDOWN DUE TO GAS VOIDING IN DISCHARGE PIPING

"Gas intrusion into ECCS piping required entry into Technical Specification (TS) 3.0.3.

"Wolf Creek was operating at 100% power when gas voiding was discovered in RHR discharge piping common to both trains of ECCS. Due to void reoccurring in excess of predetermined limits both trains of ECCS were declared inoperable at 1525 CST. A TS required shutdown was commenced at 1622.

"Engineering is researching the composition of the gas and possible sources."

The licensee must determine that the line is solid with fluid without any gas voiding before exiting the TS required shutdown. All normal and emergency power supplies are available. All EDG's are operable. Reactor power is being reduced one-half a percent per minute.

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43896
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DAVID FUNK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/12/2008
Notification Time: 07:37 [ET]
Event Date: 01/12/2008
Event Time: 05:41 [EST]
Last Update Date: 01/12/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 99 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO TWO ROD POSITION INDICATORS (RPIs) OUT IN ONE ROD BANK

"At 0451 [EST, the licensee] entered into [Technical Specification (TS)] 3.0.3 due to observed RPI B-10 erratic indication. This RPI is in the same bank as currently inoperable F-2 RPI. TS 3.1.3.2 has actions for a maximum of one RPI per bank inoperable. Since there are two [RPIs inoperable] in one bank, an entry into TS 3.0.3 is required.

"Power reduction was initiated at 0541.

"Repairs are currently in progress and [the licensee] anticipates correction prior to completion of the power reduction."

The licensee notified the NRC Resident Inspector.

See event notification #43888 for similar report.

* * * UPDATE FROM DAVID FUNK TO HOWIE CROUCH ON 01/12/08 AT 1049 EST * * *

Repairs have been completed and B-10 Rod Position Indicator has been returned to service. At 1010 EST, the licensee exited TS 3.0.3 and power ascension to 100% is in progress.

The licensee has notified the NRC Resident Inspector. Notified R2DO (Widmann).

To top of page
Fuel Cycle Facility Event Number: 43897
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/12/2008
Notification Time: 11:10 [ET]
Event Date: 01/12/2008
Event Time: [EST]
Last Update Date: 01/12/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
RESPONSE-BULLETIN
Person (Organization):
MALCOLM WIDMANN (R2)

Event Text

BULLETIN 91-01 LOSS OF DOUBLE CONTINGENCY CRITICALITY SAFETY CONTROLS

"During a project review for the recovery of uranium generated by the chemical laboratory in the Fuel Manufacturing/Operations (FMO) complex, it was discovered that ten (10) laboratory generated cans of material had been improperly stored on a conveyor system. The cans of material came from the FMO chemical laboratory that generated them from its process. The material consisted of both dry uranium powder/pellets and wet ammonium diurinate (ADU). Each can contained approximately 16kg of uranium.

"After the material was placed in the cans, it was given an incorrect material type indicating it contained only dry material. When the material was moved from the chemical lab to a storage area in preparation for processing, it was improperly stored on a conveyor which was only authorized for dry material. The second controlled parameter (mass of uranium in each can) was maintained at all times.

"Upon discovery of this condition, the ten (10) cans were immediately placed on skids on the conveyor to provide the necessary spacing between each can.

"While this did not result in an unsafe condition, this event is being reported pursuant to NRC Bulletin 91-01 within 24 hours of discovery.

"NUMBER AND TYPES OF CONTROLS NECESSARY UNDER NORMAL OPERAIING CONDITIONS:

"The basis of criticality safety relies on spacing of cans (geometry) and mass as independent criticality safety controls.

"NUMBER AND TYPES OF CONTROLS WHICH FUNCTIONED PROPERLY UNDER UPSET CONDITIONS:

"1 - Mass control remained intact, thus no unsafe condition existed.

"NUMBER AND TYPES OF CONTROLS NECESSARY TO RESTORE A SAFE SITUATION:

"1 - Control on can spacing was lost since skids were not used to separate moderated cans on the conveyor.

"SAFETY SIGNIFICANCE OF EVENTS:

"Low Safety Significance - independent control on mass remained intact - additional failure
modes required before a criticality accident could occur. The as-found condition was analyzed and demonstrated to be safe.

"SAFETY EOUIPMENT STATUS:

"All ten (10) cans were placed on skids on the conveyor system and will await further processing.

"STATUS OF CORRECTIVE ACTIONS:

"Corrective and preventative actions will be identified as part of the incident investigation."

The cans were improperly stored for several weeks. The licensee will be making notifications to NRC Region 2, the State of North Carolina and the New Hanover County Emergency Management Agency.

To top of page
Power Reactor Event Number: 43898
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRANDON SHULTZ
HQ OPS Officer: JOE O'HARA
Notification Date: 01/12/2008
Notification Time: 19:09 [ET]
Event Date: 01/12/2008
Event Time: 09:04 [EST]
Last Update Date: 01/12/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANTHONY DIMITRIADIS (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

Event Text

VALID SPECIFIED SYSTEM ACTUATION DURING EDG GOVERNOR TESTING

"An overvoltage condition occurred on the D23 Safeguards 4kv bus during planned system outage window EDG governor testing. The EDG output breaker was immediately opened and the engine secured per test direction. Due to the output breaker being opened, the D23 bus then experienced an undervoltage condition. Bus voltage monitoring instrumentation automatically initiated automatic closure of the 201-D23 Bus Offsite Supply Feed Breaker after a 1 second time delay and re-energized the D23 Safeguards Bus per design.

"The remaining three 4kv buses and Emergency Diesel Generators were unaffected and remain operable."

The voltage regulation circuit is being investigated at this time to assist in determining the cause of the overvoltage condition. The EDG was out of service and inoperable during the testing. The EDG governor was replaced during the outage window and was being fine tuned when the event occurred. The licensee is currently in day 6 of a 30 day LCO (3.8.1.1).

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43899
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: JOE O'HARA
Notification Date: 01/12/2008
Notification Time: 20:57 [ET]
Event Date: 01/12/2008
Event Time: 16:26 [CST]
Last Update Date: 01/12/2008
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):
RUSSELL BYWATER (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 98 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM DUE TO DEGRADED COOLING TO MAIN TRANSFORMERS

"On 1/12/08 at 1626 hours a manual scram was inserted due to degraded cooling on the main transformers. All control rods fully inserted and all systems actuated and/or operated as designed. No safety relief valves opened during the event and reactor pressure is currently being controlled within normal bands with bypass valves. Reactor water level is also being controlled within normal bands with the condensate and feedwater system. Group 2 and 3 isolation signals were received however, no valve movement occurred since these valves are normally closed."

The licensee is investigating a potential electrical fault which may have caused the event, but it appears that there was an electrical fault in the transformer cooling system. The grid is normal with no transmission system warnings in effect. All feeds are available. Reactor vessel level is 32.6 inches stable with normal condensate system feeding the vessel. Primary plant pressure is 815 psig. All safety and BOP electrical buses are energized normally. No bus power was lost. Decay heat path is via bypass valves to the main condenser.

The licensee will notify the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43900
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: MIKE MLYNAREK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/13/2008
Notification Time: 09:11 [ET]
Event Date: 01/13/2008
Event Time: 05:21 [EST]
Last Update Date: 01/13/2008
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):
DAVID HILLS (R3)

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

Event Text

MANUAL REACTOR TRIP AFTER LOSS OF MAIN FEEDWATER PUMP

Palisades Operations staff manually tripped the reactor in accordance with their station's Off-Normal Operating Procedure, after an automatic trip of the "B" Main Feedwater Pump (MFP). The cause of the MFP auto-trip is unknown and being investigated. During the trip, all systems performed as designed.

During the transient resulting from the trip, the atmospheric steam dump valves did open momentarily and properly reseated. There is no known primary-to-secondary leakage therefore no release was known to have occurred. All control rods inserted fully as a result of the trip. Auxiliary feedwater pump [AFW] 8A started, as expected, in response to low steam generator water levels experienced during the transient and supplied both steam generators. Decay heat is being removed via the main steam isolation valves to the condenser with the 8A AFW pump supplying feedwater to the steam generators. The plant is at normal temperatures and pressures for this mode. The electrical grid is stable with the station start-up transformer supplying station loads.

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43901
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: GARY HUSTON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/13/2008
Notification Time: 11:36 [ET]
Event Date: 01/13/2008
Event Time: 10:36 [CST]
Last Update Date: 01/13/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RUSSELL BYWATER (R4)

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

Event Text

LOSS OF EMERGENCY ASSESSMENT CAPABILITIES DUE TO PLANNED MAINTENANCE ACTIVITIES

"Planned Maintenance on Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS).

"At 1036 CST hours, on 1/13/2008, the SPDS and ERDS system will be removed from service to support activities for a planned maintenance outage at River Bend Station. The duration of work is expected to be approximately 8 hours.

"During this time, Control Room indications and alternate methods will be available to implement the Emergency Plan. Since the SPDS computer system will be unavailable for greater than 2 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10CFR50.72(b)(3)(xiii).

"A follow-up notification will be made to the NRC after the SPDS and ERDS are returned to service.

"The licensee notified the NRC Resident Inspector."

* * * UPDATE AT 1844 ON 1/13/08 FROM HUSTON TO SNYDER * * *

"The SPDS and ERDS systems have been returned to service at 1745."

The licensee will notify the NRC Resident Inspector.

Notified R4DO (Bywater).

To top of page
Power Reactor Event Number: 43902
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ED BERTRAM
HQ OPS Officer: PETE SNYDER
Notification Date: 01/13/2008
Notification Time: 13:56 [ET]
Event Date: 01/13/2008
Event Time: 09:44 [EST]
Last Update Date: 01/13/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 N Y 100 Power Operation 100 Power Operation

Event Text

INTERMITTENT PLANT COMPUTER FAILURES

"At 09:44, the Plant Computer (ERDADS) failed. Investigation revealed the ERDS link was also INOPERABLE due to the failure of the plant computer due [to] data corruption due to train failovers. Engineering has restored the plant computer by 13:00. Called the plant computer and ERDS link OPERABLE at time 13:30."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012