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Event Notification Report for December 3, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/02/2009 - 12/03/2009

** EVENT NUMBERS **


45526 45535 45536

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45526
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JOHN JARRELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/29/2009
Notification Time: 05:08 [ET]
Event Date: 11/28/2009
Event Time: 23:44 [CST]
Last Update Date: 12/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
NEIL OKEEFE (R4DO)

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

Event Text

CONTAINMENT MINIMUM PATHWAY LEAK RATE WAS EXCEEDED

"10CFR50 Appendix J Local Leak Rate Testing determined the total 'as-found' containment minimum pathway leak rate exceeded the maximum allowable containment leak rate per the Containment Leakage Rate Testing Program. This was primarily due to three penetrations that could not be pressurized to full test pressure. The maximum allowable leakage was assigned to both valves in each penetration since the valves can not be tested individually.

"This condition is reportable as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10CFR50.72(b)(3)(ii)(A). The condition was discovered with the plant in Mode 5. Corrective actions have already been completed and all penetrations, as well as total containment leakage, is well within limits established by the Containment Leakage Rate Testing Program."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM JIM POLLOCK TO PETE SNYDER AT 1711 EST ON 12/2/09 * * *

"On November 29, 2009, Waterford 3 reported that the total as-found containment minimum pathway leak rate exceeded the maximum allowable containment leak rate per the Containment Leakage Rate Testing Program. This was primarily due to three penetrations that could not be pressurized to full test pressure. The maximum allowable leakage was assigned to both valves in each penetration since the valves could not be tested individually. This condition was determined to be reportable as a condition of the nuclear power plant, including its principle safety barriers, being seriously degraded per 10CFR72(b)(3)(ii).

"Subsequently, Waterford 3 has evaluated the leak rates for all three penetrations and determined that as-found leakage rates assigned to the penetrations should not have been recorded at 630,000 sccm each, but should have been recorded at lower values.

"After one valve was re-worked in Penetration number 48, a Local Leak Rate Test (LLRT) was completed. With the new information from the second LLRT, a revised as-found leak rate of 97 sccm was assigned to the un-worked valve.

"For Penetration number 10, an Engineering evaluation of the test results was completed. The evaluation determined that the as-found leakage from this penetration was 191,000 sccm. This was based on calculating the maximum air flow capacity that could be obtained from the Leak Rate Monitor test equipment and using the first LLRT's penetration only reaching a test pressure of 43 psig instead of the 44 psig full test pressure.

"For Penetration number 11, troubleshooting activities determined that one of the valves had no detectable leakage; however, a leak rate of 9,100 sccm was assigned based on its previous as-left leakage value.

"With the lower leakage rates, the total as-found containment minimum pathway leak rate is calculated to be 230,682 sccm, which is within the limit of 630,000 SCCM. Since Waterford 3 had not exceeded the maximum allowable containment leak rate, EN #45526 is being retracted."

The licensee notified the NRC Resident Inspector.

Notified R4DO (Deese).

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Power Reactor Event Number: 45535
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARK JANKIN
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/02/2009
Notification Time: 17:09 [ET]
Event Date: 12/02/2009
Event Time: 13:45 [CST]
Last Update Date: 12/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICK DEESE (R4DO)

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

NOTIFICATION TO KANSAS DEPARTMENT OF HEALTH

"Notification to State agency due to sample exceeding limits.

"On 12/2/09, Wolf Creek received lab results for Wastewater Treatment Basin samples. The sample taken on 11/14/09 exceeded the National Pollutant Discharge Elimination System (NPDES) daily limit of 15 parts per million (ppm) for oil and grease. The result was 18.3 ppm. Exceeding this limit required notification to the State. The Kansas Department of Health and Environment, Bureau of Water was notified on 12/2/2009 that our NPDES limit was exceeded."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 45536
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID HALL
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/02/2009
Notification Time: 17:25 [ET]
Event Date: 12/02/2009
Event Time: 13:41 [EST]
Last Update Date: 12/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DANIEL HOLODY (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

POTENTIAL FIRE PREVENTING REDUNDANT CHILL WATER PUMP FROM OPERATING

"During reconstitution of the post fire safe shutdown analysis, it was noted that conditions exist whereby the requirements of the Hope Creek fire protection program (BTP CMEB 9.5-1) for the required degree of separation for redundant safe shutdown trains may not be met.

"A postulated fire in one of the reactor building fire zones (RB1 or RB2) may affect the ability to operate a required chilled water circulating pump due to the logic interrelationships between the cooling fans and their associated chilled water pump. Specifically, a fire in one area may affect cooling fans from each division and the fan failures could either trip or prevent the redundant chilled water pump from operating. This has the effect of removing the fire barrier between redundant safe shutdown trains. As such, this event is reportable under 10CFR50.72(b)(3)(ii)(B) for the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.

"Fire watches have been implemented in accordance with our approved fire protection program as an interim compensatory measure. All required safe shutdown systems remain operable. No systems or safety-related equipment actuations occurred or were required or expected as a result of this condition. All systems and safety-related equipment affected by this condition remain operable and functional. Nothing has been noted as unusual or not understood. The only system affected is the chill water system. There were no actuations or initiating signals, nor effects of the event on the plant. No personnel have been injured."

The NRC Resident Inspector will be notified.

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