United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2007 > December 28

Event Notification Report for December 28, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/27/2007 - 12/28/2007

** EVENT NUMBERS **


43830 43862 43868 43870

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 43830
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KENT MILLS
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/08/2007
Notification Time: 07:54 [ET]
Event Date: 12/08/2007
Event Time: 00:50 [EST]
Last Update Date: 12/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RICHARD BARKLEY (R1)

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

REACTOR POWER INADVERTENTLY INCREASED ABOVE ACCIDENT ANALYSIS LIMIT

"On December 8, 2007 at 0050, during plant maneuvers to return Unit Two from 84% to 100% reactor power following main turbine control valve testing, the two-minute instantaneous thermal power was inadvertently increased above the accident analysis thermal power limit of 2735.1 thermal megawatts while adjusting main turbine load to maintain Reactor Coolant temperature on program. The maximum power level attained was 2741 thermal megawatts. This is a potentially unanalyzed condition. Prompt operator action was taken to restore reactor power to within limits. Reactor thermal power was restored to within limits [below 2735.1 thermal megawatts] eight minutes later at 0058."

The two-minute instantaneous thermal power was restored to below 2700 thermal megawatts (100% rated thermal power) at 0105.

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM DAVID SUPANICH TO HOWIE CROUCH ON 12/27/07 @ 1243 EST VIA EMAIL * * *

"Based on the results of an evaluation of the event, the licensee concluded that Unit 2 operated at a maximum power level of 2741 MWth [101.5 percent rated thermal power (RTP)]. The maximum analyzed steady-state reactor core power levels, including uncertainties, are 102 percent of RTP or 2754 MWth. The unit was not in an unanalyzed condition. Therefore, this event is not reportable.

"Based on this evaluation, the associated non-emergency notification made on December 8, 2007, is retracted."

Licensee has notified the NRC Resident Inspector. Notified R1DO (Perry).

To top of page
Other Nuclear Material Event Number: 43862
Rep Org: KEY TECH
Licensee: KEY TECH
Region: 1
City: KEYPORT State: NJ
County:
License #: 29-19282-01
Agreement: N
Docket:
NRC Notified By: FONG CHEN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/21/2007
Notification Time: 16:07 [ET]
Event Date: 12/19/2007
Event Time: 10:00 [EST]
Last Update Date: 12/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PAMELA HENDERSON (R1)
ABY MOHSENI (FSME)

Event Text

DAMAGED MOISTURE DENSITY GAUGE

The Troxler moisture density gauge was being used at a construction site in Newark, New Jersey near Jackson Street. The gauge was not in use and the source rod was in the safety position when a roller rolled over part of the gauge. The area around the gauge was cordoned off until the RSO performed radiation surveys and performed a wipe test. The survey indicated no contamination or leakage. The wipe test was shipped to Troxler and verified no radioactive material leakage. The gauge is currently in the licensee's gauge storage room awaiting disposition.

Troxler Moisture Density gauge Model 3440
Serial Number 16356
One Cs-137 source (typically 8 milliCuries)

* * * UPDATE FROM FONG CHEN TO HOWIE CROUCH @ 1430 EST ON 12/27/07 VIA TELEPHONE * * *

The licensee wanted to clarify some statements made in the original report. The gauge was in use at the time of the incident with the source rod in the testing position. After the gauge was hit, the licensee was able to retract the source into the shielded (safe) position. A leak test swipe was performed and the swipe was overnighted to Troxler. Troxler reported that sample results were negative for leakage.

Notified R1DO (Perry) and FSME (Wassler).

To top of page
Other Nuclear Material Event Number: 43868
Rep Org: R. M. WESTER CONSULTANTS
Licensee: JACOBI GEOTECHNICAL ENGINEERING
Region: 3
City: O'FALLON State: MO
County:
License #: 24-32231-01
Agreement: N
Docket:
NRC Notified By: KEVIN MCCAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/27/2007
Notification Time: 12:27 [ET]
Event Date: 12/26/2007
Event Time: 10:00 [CST]
Last Update Date: 12/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
STEVE ORTH (R3)
SANDRA WASTLER (FSME)

Event Text

DAMAGED MOISTURE DENSITY GAUGE

Radiation Health Physics consultants, R.M. Wester, notified the NRC of an event in the State of Missouri that resulted in damage to a Humboldt Soil Density Gauge (Model EZ 5001, S/N 693) containing 40 mCi Am-241/Be and 10 mCi Cs-137. The gauge is licensed to Jacobi Geotechnical Engineering. The consultant stated that the event took place at a construction site in Pezley, MO. The gauge was run over by a backhoe. There was some damage to the plastic housing of the gauge. The source rod was undamaged. The source rod was wipe tested with negative results. In addition, soil samples at the incident location also tested negative.

R.M. Wester has taken possession of the gauge and will ship it to Humboldt for repairs.

To top of page
Power Reactor Event Number: 43870
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ROBERT ALEXANDER
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/28/2007
Notification Time: 02:24 [ET]
Event Date: 12/27/2007
Event Time: 20:04 [CST]
Last Update Date: 12/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
TROY PRUETT (R4)

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

LOSS OF SPDS CAPABILITY FOR GREATER THAN ONE HOUR

"At 2004, while performing a routine surveillance (Manual Scram Functional Test) the operator performing the surveillance identified that the Plant Management Information System (PMIS) terminals in the control room did not respond as expected to the surveillance. The expected response would have displayed an 'RPS channel trip' message.

"PMIS is the computer system which implements the Safety Parameter Display System [SPDS] and dose determination. Dose determination was available using manual calculations. This system also supports the ERDS (Emergency Response Data System) and the core monitoring system.

"Additional investigation found that the PMIS displays had stopped updating at 1950. Attempts to cause the system to fail over to the backup computer (the 'A' computer) thus restoring functionality were unsuccessful. Information Technology (IT) personnel were called and responded to the plant. IT personnel manually restarted the 'A' computer and switched the input/output (I/O) devices to the 'A' computer. Personnel have verified the Technical Support Center and Emergency Offsite Facility systems are also functional. Functionality of the SPDS system and its related systems was verified to be restored at 2330. The backup system ('B') remains out of service and will be addressed tomorrow.

"This event is reported under 50.72(b)(3)xiii, Any event which results in a major loss of emergency assessment capability."

The licensee notified the NRC Resident Inspector.

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