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Event Notification Report for December 29, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/28/2004 - 12/29/2004

** EVENT NUMBERS **


41284 41287 41297 41298

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General Information or Other Event Number: 41284
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: MAFI ASSOCIATES CONSULTANT ENGINEERING
Region: 1
City: BETHESDA State: MD
County:
License #: MD-31-270-01
Agreement: Y
Docket:
NRC Notified By: BOB NELSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/23/2004
Notification Time: 08:52 [ET]
Event Date: 12/22/2004
Event Time: 11:00 [EST]
Last Update Date: 12/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1)
TOM ESSIG (NMSS)

Event Text

AGREEMENT STATE REPORT OF TROXLER GAUGE RUN OVER BY A TRUCK

The Maryland Department of Environment Radiological Health Program reported that a Troxler moisture density gauge (Model 3430) was run over by a dump truck at a construction site in Prince Georges county (near the intersection of highway 410 and 295). The gauge contained an 8 milliCurie Cs-137 and 40 milliCurie Am-241/Be source. A representative of the Maryland Radiological Health Program responded to the scene and conducted a test for leakage and contamination. The gauge source was determined to be undamaged and in the shielded position. The gauge was packaged for transport and will be sent to the Troxler repair facility.

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General Information or Other Event Number: 41287
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GLOBAL PROCESS DIAGNOSTICS INC
Region: 4
City: CARSON State: CA
County:
License #: L05155
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/23/2004
Notification Time: 17:05 [ET]
Event Date: 12/21/2004
Event Time: [PST]
Last Update Date: 12/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4)
SCOTT FLANDERS (NMSS)

Event Text

AGREEMENT STATE REPORT

"It was reported to Radiological Health Branch (RHB), Granada Hills that a Texas licensee, Gamma Surveys, a Division of Global Process Diagnostics, Inc. ( Gamma Surveys) , was conducting density level measurements using sealed sources under reciprocity at the Conoco Phillips Corporation refinery in Carson, CA, the evening of 12/21/04. Special form sealed sources containing radioactive material are employed for "gamma scanning," diagnostic evaluation, typically density or level measurements, of industrial processes or equipment. At about 1900 one such source, 287 mCi, Co-60, contained in a collimating device at the end of a stainless-steel, stranded cable, was being lowered down the outside of a large, cylindrical "distillation vessel, " designated FR-1 Flasher Column, 200 ft. high and 28 ft. in diameter. Stiffening rings which protrude about 18 inches externally encircle the vessel at various heights. As the source is being lowered down the side of the vessel, the operator located at the top of the vessel must manually "shake" the cable to get the source over the protruding stiffening rings. On this occasion, the collimating device with the Co-60 source broke at the cable during this shaking to get it over a stiffening ring 20 feet from the top. The source came to rest on the stiffening ring, in the " unshielded" condition, where it remained overnight. However, Gamma Surveys indicated that the area was cleared of personnel and cordoned off. Radiation surveys were taken at the ground level showing no appreciable dose rates, approximately 0.04 mR/hr.

"The next day, 12/22/04, Gamma Surveys proposed a recovery plan to lower an operator in a man-basket down to the source to manually put the source back in its shielded condition ( normal practice) and then attach a replacement cable to the collimating device so that it may be reeled back into its shielded container at the top of the vessel for subsequent evaluation and repair of the damaged system. After consultation with RHB staff and the RSO for Gamma Surveys, this plan was effected. By about 5 PM, 12/22/04, the source recovery was completed without problems.

An investigation has been initiated to follow-up."

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Power Reactor Event Number: 41297
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOONG KO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/27/2004
Notification Time: 18:49 [ET]
Event Date: 12/27/2004
Event Time: 17:20 [EST]
Last Update Date: 12/28/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
CAUDLE JULIAN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 10 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP FOLLOWING PROBLEM WITH STEAM GENERATOR WATER LEVEL CONTROL

The licensee reported a "manual reactor trip due to low steam generator level caused by feedwater control system malfunction." The licensee stated that it manually tripped the reactor with steam generator water level at approximately 40% and decreasing. Steam generator water level control was restored following the trip using auxiliary feedwater.

All rods fully inserted on the trip. No safety or relief valves lifted. Auxiliary feedwater was manually actuated and decay heat is currently being discharged via the atmospheric dump valves. Unit 1 is at full power and unaffected and the grid is stable. The plant was in no major LCOs at the time. All systems functioned as required. The licensee is still investigating the feedwater control system malfunction.

The NRC Resident Inspector has been notified.

* * * UPDATE FROM LICENSEE (WILLIAMS) TO NRC (HUFFMAN) AT 1818 ON 12/28/04 * * *

"The original notification stated that decay heat was being discharged via the atmospheric dump valves post-trip when the decay heat removal mechanism being used was steam dump to the condenser via the steam bypass control system. Additionally, although the auxiliary feedwater system was used to deliver water to the steam generators post-trip, the main feedwater system was available for this function. The investigation into the feedwater malfunction is still in progress."

The NRC Resident Inspector has been informed. R2DO (Moorman) notified.

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Power Reactor Event Number: 41298
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/28/2004
Notification Time: 23:51 [ET]
Event Date: 12/28/2004
Event Time: 22:46 [EST]
Last Update Date: 12/29/2004
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):
JAMES MOORMAN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 M/R Y 70 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO GENERATOR EXCITER COOLING WATER LEAK

"Unit 3 unplanned Manual Reactor trip from 70% due to Generator Exciter cooling water leak. Leak caused voltage regulator transfer to manual. Cooling water leak was isolated after the manual reactor trip. Water was noted in the 3B 4kv safety related bus room affecting 3B Residual Heat Removal Pump breaker. This component is considered inoperable pending corrective action. Plant is stable in mode 3.

"Auxiliary Feed Water actuated automatically, as expected, and operated normally following the reactor trip."

All control rods fully inserted. The MSIV's were manually closed to prevent excessive RCS cooldown and decay heat is being removed via the atmospheric steam dumps. Unit 4 was unaffected. The licensee will notify the NRC Resident Inspector.

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Friday, March 30, 2012