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Event Notification Report for April 28, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/27/2010 - 04/28/2010

** EVENT NUMBERS **


45870 45877

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General Information or Other Event Number: 45870
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: KEYTECH
Region: 1
City: MANCHESTER State: NJ
County:
License #: NJ-507394
Agreement: Y
Docket:
NRC Notified By: BILL CSASZAR
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 04/23/2010
Notification Time: 09:51 [ET]
Event Date: 04/19/2010
Event Time: 11:00 [EDT]
Last Update Date: 04/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1DO)
ANGELA MCINTOSH (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - POSSIBLE LOSS OF CONTROL/DAMAGE TO PORTABLE GAUGE

The following report was received from the State via e-mail:

"At approximately 11 a.m. [EDT] on Monday, April 19, 2010, one of KeyTech's portable moisture density gauges (Troxler Model 4640B, Serial No. 2008, containing 9 mCi of Cs-137 and 44 mCi of Am-241) was struck by a steam-roller. The incident occurred at the intersection of Manchester Boulevard and Manchester Road in Manchester, NJ. On Wednesday, April 21, 2010, the licensee filed a report with the Manchester Police. The Manchester Police then contacted the Trenton Dispatch. At about 11 a.m., RMP [New Jersey Dept. of Environmental Protection Radioactive Materials Program] personnel were notified by Trenton Dispatch.

"The RMP contacted Manchester Police and it was learned that KeyTech reported that while the gauge was damaged the radioactive material remained intact within the device. KeyTech's RSO [Radiation Safety Officer] and administrator were contacted. The RSO stated that only the keyboard portion of the gauge was hit and that there was no damage to the radioactive material within the gauge. When the gauge was hit, the source rod was extended. The technician was able to retract the source rod into the safe position. The gauge was moved to a safe location and away from the public. RMP personnel went to KeyTech on Thursday, 4/22/10, to speak with the licensee and to conduct an investigation. The investigation concluded that the material was intact within the gauge and determined the licensee took appropriate actions to protect personnel and the public."

New Jersey Report #C348104

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 45877
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/27/2010
Notification Time: 18:44 [ET]
Event Date: 04/27/2010
Event Time: 16:37 [EDT]
Last Update Date: 04/27/2010
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):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 74 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP FOLLOWING A GENERATOR LOCKOUT DURING AUTOMATIC VOLTAGE REGULATOR TESTING

"On 4/27/2010 at 1637 hours, during recovery from a refueling outage when the main turbines and exciter were replaced, Unit 2 experienced a generator lockout which caused a turbine trip. The turbine trip resulted in a reactor trip when the reactor was at 74% power. The generator lockout occurred while automatic voltage regulator testing was being performed. This event is reportable per 10CFR50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.

"The Auxiliary Feedwater Pumps (AFW) received an automatic start signal due to low/low level in the steam generators following the reactor trip. Steam Generator inventory was restored to normal operating level. The Steam Driven AFW pump experienced an issue with the lube oil system which resulted in some of the oil leaking onto the floor. An investigation into the oil leakage issue will be performed. The Steam Driven AFW pump was declared inoperable until this investigation is complete. The two motor driven AFW pumps automatically started and operated as designed. This event is reportable per 10CFR50.72(b)(3)(iv)(A) due to actuation of an ESF system.

"All control rods inserted into the core following the reactor trip and decay heat is being removed using the normal steam dump system. Several secondary (feedwater) relief valves lifted and resealed during the event. Unit 2 is stable in Mode 3 at normal operating temperature and pressure."

Unit 2 is in a normal shutdown electrical lineup and there was no impact on Unit 1. The NRC Resident Inspector has been notified by the licensee.

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