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Event Notification Report for April 9, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/08/2010 - 04/09/2010

** EVENT NUMBERS **


45821 45822 45823 45824 45827 45828

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Power Reactor Event Number: 45821
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW MOG
HQ OPS Officer: PETE SNYDER
Notification Date: 04/07/2010
Notification Time: 21:11 [ET]
Event Date: 04/06/2010
Event Time: 08:30 [EDT]
Last Update Date: 04/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
JAMES TRAPP (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 86 Power Operation 86 Power Operation

Event Text

STORM DRAIN SYSTEM TESTED POSITIVE FOR TRITIUM

"On 4/06/10, Salem management was notified that samples taken from the Salem Unit 2 north storm drain system were positive for tritium. Two storm drain catch basin sample results were confirmed above 1 million pico Curies per liter. The affected area of the north storm drain system has been isolated. Samples upstream of the river outfall were less than the minimum detectable level for tritium.

"NRC reporting criteria were reviewed and, although no direct reportable criteria were met, based on the public sensitivity to tritium issues, it was determined that a voluntary notification to the NRC was prudent.

"Salem is taking action to mitigate, locate, and remediate the source of the tritium. In addition to isolating the affected portion of the system, the station has increased the sample frequency for the storm drain system and ground water wells in the affected area.

"A voluntary notification has been made to the appropriate State agency and the NRC Resident Inspector."

* * * UPDATE FROM TOM BYYKKONEN TO PETE SNYDER ON 4/8/10 AT 2025 * * *

"Based on further evaluation, Salem officially notified the New Jersey Department of Environmental Protection of the above tritium spill on 4/8/10 at 2003. This notification to New Jersey is reportable in accordance with 10 CFR 50.72(b)(2)(xi)."

The licensee notified the NRC Resident Inspector.

Notified R1DO (Trapp).

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Power Reactor Event Number: 45822
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/08/2010
Notification Time: 11:51 [ET]
Event Date: 04/08/2010
Event Time: 08:30 [CDT]
Last Update Date: 04/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID PROULX (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

PAGING SYSTEM OUTAGE

"At about 0830 CDT on 4/8/2010, it was discovered that the station paging system was not operating. Repair efforts were initiated. The Control Room and station personnel were notified of the pager outage. The automated callout system is available to notify the emergency response organization during the pager outage if needed.

"That pager system was returned to service at about 1005 CDT 4/8/10."

The NRC Resident Inspector has been informed.

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Power Reactor Event Number: 45823
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JIM BLAZEK
HQ OPS Officer: PETE SNYDER
Notification Date: 04/08/2010
Notification Time: 14:07 [ET]
Event Date: 04/08/2010
Event Time: 10:15 [MST]
Last Update Date: 04/08/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
DAVID PROULX (R4DO)
BRIAN McDERMOTT (IRD)
ART HOWELL (R4)
BRUCE BOGER (NRR)
NINA MCDONALD (DHS)
DORA HEYMAN (FEMA)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

EARTHQUAKE

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under reporting requirements of 10 CFR 50.73.

"An Event Classification of Unusual Event (HU1.1) was declared at 10:15 MST for the Palo Verde Nuclear Generating Station because of an earthquake that originated in Baja California location 32.220 N, 115.276 W at 09:44 MST. Per the USGS website and via phone conversation at 10:03, the magnitude of the earthquake was preliminarily 5.5 on the Richter scale.

"Initial walk downs of plant equipment and review of plant parameters have found no unusual conditions or damage to plant equipment. No abnormalities caused by the seismic event were observed. No reactor protection system (RPS) or engineered safety feature (ESF) actuations occurred and none were required.

"Palo Verde Unit 1 is in mode 6 for a scheduled refueling outage and Units 2 & 3 are at 100 percent power with all offsite power supplies available. Seismic Monitoring Instrumentation system is currently functional and did not indicate a seismic event. Currently based on the Modified Mercalli scale the seismic event was below the magnitude of the 0.10g spectra Operating Basis Earthquake (OBE) and the 0.20g spectra Safe Shutdown Earthquake (SSE)."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM JIM BLAZEK TO PETE SNYDER AT 1606 ON 4/8/10 * * *

"Emergency classification termination was declared at 4/08/10, 12:54 MST. All required power block inspections were completed with no deficiencies noted. No other conditions required an emergency classification, there are no challenges to fission product barriers or radiological release, and plant conditions offer no possibility of adverse impact on health and safety of the public.

"The NRC Resident Inspector has been notified of NUE termination."

Notified R4DO (Proulx), NRR EO (Thorp), DPR (McDermott), DHS (McDonald), and FEMA (Hollis).

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Power Reactor Event Number: 45824
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: GARY FLESHER
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/08/2010
Notification Time: 15:35 [ET]
Event Date: 04/08/2010
Event Time: [EDT]
Last Update Date: 04/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES TRAPP (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

STACK SAMPLE LINE SEPARATED AT FITTING

"During the routine replacement of the stack sample flow transmitter technicians in the area discovered the stack sample line had become separated at a SWAGELOK union at the 150 foot elevation. The sample line was reconnected and a visible count change was observed. At the time of discovery, the stack radioactive gas effluent monitoring system (RAGEMS) had been removed from service in accordance with the plant procedures and declared inoperable for performance of Surveillance Procedure 621.3.023 'Stack RAGEMS Sample and Effluent Flow Calibration.' Plant chemistry personnel are currently taking compensatory grab samples.

"Engineering has determined that functionality of the stack radiation monitoring capability was degraded and therefore this notification is being made in accordance with 50.72(b)(3)(xii) as a condition that resulted in a loss of monitoring capability. Backup assessment capabilities were available for Reactor Building Ventilation Radiation Monitoring and the Off-Gas Sample Monitor."

The NRC Resident Inspector will be informed.

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Power Reactor Event Number: 45827
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NEWTON LACY
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/08/2010
Notification Time: 17:26 [ET]
Event Date: 04/08/2010
Event Time: [EDT]
Last Update Date: 04/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JAY HENSON (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

DIESEL GENERATORS WIRED INCORRECTLY

"Action F of LCO 3.8.1, 'AC Sources - Operating,' was entered at 20:57 EDT April 7, 2010 for the 2A-A and the 2B-B diesel generators (DGs) being inoperable. Action F has a two hour allowed outage time (AOT). The DGs were determined to be inoperable due to incorrectly implemented wiring changes made by personnel performing construction work on Watts Bar Unit 2. The impact of the change is that during [an] actual or simulated ESF actuation signal, if the diesel is in test mode, and the output breaker is closed in parallel with the board supply breakers, the DG would not return to a 'ready to load' state meaning the output breaker would not have opened as designed for this condition. This function is tested as required on an 18 month frequency as a part of Surveillance Requirement (SR) 3.8.1.17.

"The wiring changes which affected the DGs were made in accordance with Unit 2 Work Order (WO) 09-954447 and 09-954448. The WOs as developed would not have an impact on Unit 1 operations. A review of the Unit 1 Operator Logs from January 1, 2010 to present, did not find any entries establishing the Unit 2 work had been authorized by Unit 1. The proper technical specification entry would have been Action 8 of LCO 3.8.1 for this activity. Entry into Action B of LCO 3.8.1 requires the implementation of several actions including a verification of the operability of the offsite circuits. Since these Technical Specification required actions were not complied with, WBN is providing this 24-hour notification in accordance with Section 2.G of the Watts Bar Unit 1 Facility Operating License.

"During the review of work performed by Unit 2 it was identified that the wiring was initially lifted on January 6. 2010. At the time of this report, actions have been taken to restore the wiring to its appropriate configuration on both of the DG circuits. 2B-B DG wiring was restored at 22:18 on April 7, 2010 and the 2B-B DG was declared operable. Action F of LCO 3.8.1 was exited at this time and Action B was entered for the 2A-A DG (14 day AOT). 2A-A DG circuitry was restored at 00:37 on April 8, 2010, and all LCO actions were exited. This event has been entered into TVA's corrective action program and actions are being initiated to establish the reason the leads were incorrectly lifted and to verify that no other similar wiring issues exist."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 45828
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: PETE SNYDER
Notification Date: 04/08/2010
Notification Time: 20:34 [ET]
Event Date: 04/08/2010
Event Time: 16:22 [CDT]
Last Update Date: 04/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DAVID PROULX (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 75 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE STEAM GENERATOR INLET ISOLATION VALVE

"At 1622 hours CDT, an electrical ground on 480 Volt Bus 1B3A was determined to be from a supply cable to Motor Control Center (MCC)-3A1. Isolating loads on this MCC required securing power to HCV-1385, Steam Generator RC-2B Inlet Isolation Valve. This condition results in the valve being unable to close on a Steam Generator Isolation Signal (SGIS), which requires entry into Technical Specification 2.0.1(1). This Technical Specification requires the plant to be placed in a Hot Shutdown condition within 6 hours. A plant shutdown to Mode 3 was commenced at 1740 hours CDT."

The licensee notified the NRC Resident Inspector.


* * * UPDATE FROM DAVID SPARGO TO DONALD NORWOOD AT 0036 EDT ON 4/9/2010 * * *

"At 2123 hours CDT, the Reactor was manually tripped from 22% Reactor Power in order to meet the requirements of Technical Specification 2.0.1(1) and have the reactor in a hot shutdown condition. All systems functioned properly.

"At 2124 CDT, the plant entered Mode 3 Shutdown Condition. AT 2235 CDT, HCV-1385, Steam Generator RC-2B Inlet Isolation Valve has been manually closed. Technical Specification 2.0.1(1) has been exited."

The licensee is reporting the manual scram under 10CFR50.72(b)(2)(iv)(B). The licensee notified the NRC Resident Inspector.

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