Event Notification Report for April 04, 2012

INOPERABLE ACCIDENT MITIGATION EQUIPMENT

"On 4/4/2012 at 1517 EDT, the 'A' Emergency Diesel Generator (EDG) was declared inoperable for performance of a maintenance surveillance. At 1835 EDT on 4/4/2012 the 'B' Control Structure Chiller was declared inoperable due to an unrelated problem. [With] the 'B' Control Structure Chiller inoperable coincident with the 'A' EDG inoperable, the 'A' Control Structure Chiller would not be available to perform its design function on a loss of offsite power. This is a condition that, at the time of discovery, could have prevented fulfillment of a Safety Function and is reportable under 50.73(a)(2)(v) as an 8 hour notification. Note that Technical Specifications allows four hours to correct the condition before further actions are required, i.e. declare the features ('A' Control Structure Chiller) supported by the inoperable diesel inoperable. The 'A' EDG was restored to operable at 2200 which restored safety function capability for the 'A' Control Structure Chiller."


The licensee notified the NRC Resident Inspector.

AGREEMENT STATE REPORT - TC-99M GENERATOR INADVERTANTLY SENT TO NON-LICENSED RECIPIENT

The following information was received from the State of California by email:

"The hospital had sent a depleted Tc-99m generator to an incorrect recipient, a non-licensee. They had intended to return it to Mallinckrodt in St. Louis, [Missouri]. He [RSO] thought the generator still contained about 100 mCi. The package was shipped on 4/4/12, and was retrieved on 4/6/12 after the mistake was discovered."

The package was returned to Saint Joseph Hospital and the following week the hospital resent the package to the correct recipient, Mallinckrodt.

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE STATIC INVERTER

"Indian Point 2 commenced a Technical Specification required shutdown in accordance with Limiting Condition of Operation 3.8.7, Condition B at 0500 hours on 04/04/2012 due to the inoperability of '24' Static Inverter - a component in the 118VAC Distribution System. Indian Point 2 is required to be in Mode 3 by 0802 hours. Repair of the '24' Static Inverter is in progress.

"The NRC Resident Inspector has been notified."

The licensee also notified the NY State Public Service Commission.


* * * UPDATE FROM P. SCHOAN TO DONALD NORWOOD AT 1053 EDT ON 4/4/2012 * * *

At 0538 hours, the Technical Specification shutdown was stopped following the repair and return to service of the '24' Static Inverter.

The licensee notified the NRC Resident Inspector.

Notified R1DO (Caruso).

NOTICE OF UNUSUAL EVENT DUE TO DUAL UNIT LOSS OF OFFSITE POWER

At 2003 EDT on 4/4/12 Catawba Unit 1 automatically tripped due to a loss of offsite power. The licensee declared a Notice of Unusual Event due to entry into EAL 4.5.U.1, 'AC Electrical Power from All Offsite Sources Has Been Lost for Greater Than 15 Minutes.' Power is still available from onsite sources. All four Emergency Diesel Generators [EDG] started and powered their respective safety buses.

"The EAL poses no threat to the safety of the public."

The Unit 1 control rods fully inserted, there is no known primary to secondary leakage, and the auxiliary feedwater water system automatically started.

The licensee notified the NRC Resident Inspector

Notified: DHS SWO, FEMA, DHS NICC, USDA, HHS, DOE, EPA, and Nuclear SSA via email.


* * * UPDATE AT 0150 EDT ON 04/05/12 FROM DARRYL HELTON TO S. SANDIN * * *

Catawba Nuclear Generating Station exited the Unusual Event at 0137 EDT after restoring offsite power at 0135 EDT to the Unit 1A and Unit 2B essential busses. The EDGs powering these busses have been secured and returned to Standby.

The Unit 1B and Unit 2A essential busses remain energized by their respective EDGs. The licensee does not have an estimate as to when offsite power will be restored for these busses.

Additional information provided as follow-up includes:

4-hour notification per 10CFR50.72(b)(2)(iv)(B) due to the Unit 1 Reactor Protection System [RPS] actuation (Rx Trip),

4-hour notification per 10CFR50.72(b)(2)(xi) for offsite notifications to the States of North and South Carolina and the counties of York, Gaston and Mecklenburg,

8-hour notification per 10CFR50.72(b)(3)iv)(A) due to the Unit 1 Rx Trip, Unit 1 Auxiliary Feedwater automatic start, Unit 1A and 1B and Unit 2A and 2B EDG auto starts.

8-hour notification per 10CFR50.72(b)(3)(v)(B) due to the loss of Residual Heat Removal [RHR] cooling on the initial loss of power. Unit 2 RHR was restored in less than three (3) minutes when the essential busses were re-energized by the EDGs.

The licensee informed the NRC Resident Inspector.

Notified R2IRC, EO (Nelson), IRD (Gott) and FEDS (DHS SWO, DOE Ops Center, FEMA, HHS Ops Center, DHS NICC, USDA Ops Center, EPA EOC) and NuclearSSA via email.

DEGRADED CONDITION DUE TO IDENTIFIED REACTOR PRESSURE VESSEL TEST LEAKAGE

"On April 4, 2012, at 1716 [CDT], with Unit 2 shutdown for refueling, leakage was identified from a 2-inch vessel nozzle during a Reactor Pressure Vessel (RPV) pressure test. The leakage amount was approximately one drop per second. The penetration (N-11B) is a reference leg used for reactor vessel instrumentation. The leakage originates from the area where the nozzle penetrates the vessel wall. The nozzle is welded on the inside of the vessel, so the actual attachment weld could not be examined at the time of this report. The RPV pressure test has been stopped and the reactor vessel depressurized. The cause and resolution are under evaluation. The condition is being reported under 50.72(b)(3)(ii)(A) given the defect was associated with the primary coolant system pressure boundary."

The licensee notified the NRC Resident Inspector.