United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2010 > April 30

Event Notification Report for April 30, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/29/2010 - 04/30/2010

** EVENT NUMBERS **


45745 45816 45880 45882 45883

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45745
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/05/2010
Notification Time: 03:25 [ET]
Event Date: 03/05/2010
Event Time: 00:07 [CST]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHUCK CAIN (R4DO)

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

SPECIFIED SYSTEM ACTUATION - FEEDWATER ISOLATION DUE TO HIGH STEAM GENERATOR WATER LEVEL

"A Turbine trip and Feedwater Isolation Signal was generated as a result of high level in 'A' Steam Generator. At approximately 0007 CST, a turbine trip and Feedwater Isolation Signal was generated when the level in the 'A' Steam Generator exceeded the initiation set point of 78%. Steam Generator level returned below the initiation setpoint at approximately 0008 CST. Steam Generator 'A' high level resulted from swell of the Steam Generator after opening the 'A' Main Steam Isolation Valve. Level was approximately 50% prior to the event and returned to approximately 50% within one minute.

"The turbine was already in the tripped condition due to the plant trip that occurred at 1458 CST on 03/02/2010 (Reference EN# 45739).

"Steam Generators are being fed with the motor driven startup Feedwater pump. Decay heat removal is via the Steam Generator Atmospheric Relief Valves and steam dumps. The plant is in Mode 4 with Reactor Coolant System pressure at approximately 500 psig and temperature at approximately 332 degrees F.


"Two Main Feedwater isolation valves did not fully close but the actuators were being supplied with auxiliary medium (air) at the time of the actuation. Feedwater isolation valves are not required to be operable in Mode 4."

The licensee will notify the NRC Resident Inspector.

* * * RETRACTION FROM RICK HUBBARD TO PETE SNYDER AT 1456 ON 4/29/2010 * * *

"This event (Event Number 45745) is being retracted. A valid actuation of any systems listed in paragraph 50.72 (b)(3)(iv)(B) did not occur. The plant was in Mode 4 and neither a reactor trip nor an auxiliary feedwater system actuation signal occurred. Additional evaluation determined that the turbine trip and feedwater isolation signal are a function of the ESFAS [Engineered Safety Features Actuation System] instrumentation and does not result in an actuation of the RPS [Reactor Protection System] or other systems listed in paragraph 50.72 (b)(3)(iv)(B)."

The licensee notified the NRC Resident Inspector.

Notified R4DO(Clark).

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45816
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: ERIC FRANKE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/07/2010
Notification Time: 00:33 [ET]
Event Date: 04/06/2010
Event Time: 17:47 [PDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID PROULX (R4DO)

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

INITIATION OF TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO CONTROL ROOM EMERGENCY FILTRATION SYSTEM BEING DECLARED INOPERABLE

"At 1650 PDT Columbia Generating Station entered LCO 3.0.3 as required by LCO 3.7.3 for both divisions of Control Room Emergency Filtration (CREF) [being] inoperable. Entry into LCO 3.0.3 was required by Condition E of LCO 3.7.3, 'Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B' and has a Required Action to enter LCO 3.0.3 with an immediate Completion Time. Columbia commenced a plant shutdown at 1747 as required by LCO 3.0.3.

"[Columbia Generating Station] entered into Condition E of LCO 3.7.3 when it was determined that Radwaste Building Outside Air Smoke Detectors WOA-SMD-1A and WOA-SMD-1B did not meet seismic qualifications. Actuation of these smoke detectors would cause Radwaste Building Mixed Air Fire Dampers WMA-FD-1 and WMA-FD-2 to close. These fire dampers shutting would cause all CREF airflow to cease, preventing the control room from achieving a positive pressure. Both divisions of CREF [being] inoperable is an unanalyzed condition requiring immediate entry into LCO 3.0.3.

"This event is reportable under 50.72(b)(2)(i) due to the initiation of a plant shutdown as required by Columbia's Technical Specifications. This event is also reportable under 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"WMA-FD-1 and WMA-FD-2 have been deactivated in the open position for the smoke actuation function. [Columbia Generating Station] entered RFOLCS (Requirements for Operability of Licensee Controlled Specifications) 1.10.6 for these fire dampers [being] nonfunctional. [Columbia Generating Station] completed the required actions of LCS 1.10.6.

"The CREF system remains inoperable pending completion of a TMR (Temporary Modification Request)."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM QUOC VO TO CHARLES TEAL ON 4/7/10 AT 1957 * * *

"Question posed by NRC at time of initial report: Have these smoke detectors been installed since startup?

"Response: These smoke detectors have been installed since initial plant startup.

"A temporary modification request was installed to de-energize the non-seismic detector logic that causes automatic fire damper actuation for the two dampers identified above. The alarm function of the smoke detectors remains active with this temporary modification.

"Entry into this condition was made when it was determined that the smoke detectors were not seismically qualified and there is a possible failure mode that during an earthquake the detectors would actuate the electro-thermal link and cause the associated fire damper (WOA-FD-1 or WOA-FD-2) to close, hence impacting control room emergency filtration function.

"With implementation of the temporary modification at 2218 PDT on 4/6/10, the CREF system is now considered to be in an 'operable but non-conforming' status. As such, LCOs 3.7.3 and 3.0.3 were exited at 2218 PDT on 4/6/10.

"This event was initially reported pursuant to paragraph 50.72(b)(2)(i) as an initiation of a plant shutdown required by Columbia's Technical Specifications. Reporting pursuant to paragraph 50.72(b)(2)(i) is being retracted because negative reactivity was not inserted into the reactor prior to exiting the LCOs described above. Reporting pursuant to paragraph 50.72(b)(2)(i) would not be consistent with the guidance provided in NUREG-1022 in that no negative reactivity was inserted and the condition was corrected before exceeding the required action times."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM KYLE CHRISTIANSON TO PETE SNYDER AT 1550 EDT ON 4/29/2010 * * *

"Subsequent to the April 7, 2010, event report (EN #45816), an Energy Northwest engineering evaluation concluded that the identified smoke detectors would not inadvertently actuate during a design basis safe shutdown earthquake (SSE). This conclusion is based on a seismic response spectrum test report for the smoke detectors. Therefore, since the safety function of the CREF system needed to mitigate the consequences of an accident would not be affected by an SSE, the event notification made pursuant to 10 CFR 50.72 (b)(3)(iv)(D) is hereby retracted."

"The NRC Senior Resident Inspector (Cohen) has been notified."

Notified R4DO (Clark).

To top of page
Power Reactor Event Number: 45880
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DOUGLAS SHORTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/29/2010
Notification Time: 08:31 [ET]
Event Date: 04/29/2010
Event Time: 08:30 [EDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID HILLS (R3DO)

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

PLANT INTEGRATED COMPUTER SYSTEM OUTAGE DUE TO SCHEDULED MAINTENANCE

"Beginning at approximately 0830 hours EDT on April 29, 2010, Perry Plant personnel will be taking the plant Integrated Computer System (ICS) out of service for planned maintenance. During the time ICS is out of service, the Safety Parameter Display System (SPDS), the Emergency Response Data System (ERDS), and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable. The computer outage is scheduled for six hours.

"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off-Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."

The NRC Resident Inspector has been notified.

* * * UPDATE AT 1036 EDT ON 04/29/10 FROM DOUGLAS SHORTER TO CHARLES TEAL * * *

The plant ICS has been returned to service and the system is functioning normally. The NRC Resident Inspector has been notified.

Notified R3DO (Hills).

To top of page
Power Reactor Event Number: 45882
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/29/2010
Notification Time: 20:30 [ET]
Event Date: 04/29/2010
Event Time: 18:30 [EDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GERALD MCCOY (R2DO)

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

IDENTIFIED WIRING DISCREPANCY IN "B" EDG

"While performing a walkdown of the 'B' emergency diesel generator remote shutdown circuitry, a wiring discrepancy was identified that could have disabled the Appendix R function of the circuitry. The wiring discrepancy could have prevented complete isolation of the 'B' emergency diesel generator breaker closure circuitry from a postulated fire in the Control Building.

"This configuration causes the Appendix R function of the 'B' emergency diesel generator to be inoperable.

"A roving firewatch has been established and a 7 day action statement has been entered in accordance with the applicable fire protection procedure. Corrective actions are being evaluated to resolve this issue."

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 45883
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: CHRIS BUSH
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/30/2010
Notification Time: 05:26 [ET]
Event Date: 04/30/2010
Event Time: 03:00 [CDT]
Last Update Date: 04/30/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID HILLS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 65 Power Operation 65 Power Operation

Event Text

LOSS SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DUE TO COMPUTER PROBLEMS

"At 0300 [CDT] on 04/30/2010, the Plant Computer Group identified that the SPDS stalled and was not updating data points as required. The SPDS also supplies data to several Emergency Response Data System (ERDS) points. Redundant, normal control room indications are still available to the operators. This is considered a Loss of Emergency Assessment Capability and therefore, reportable under 10CFR50.72(b)(3)(xiii).

"SPDS was restored at 0356 [CDT] on 4/30/2010.

"The licensee has notified the NRC Resident Inspector."

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