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Event Notification Report for August 8, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/05/2005 - 08/08/2005

** EVENT NUMBERS **


41852 41854 41859 41890 41895 41896 41897 41898 41899 41900

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41852
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARK SHAFFER
HQ OPS Officer: PETE SNYDER
Notification Date: 07/19/2005
Notification Time: 10:53 [ET]
Event Date: 07/19/2005
Event Time: 03:45 [EDT]
Last Update Date: 08/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD CONTE (R1)

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

HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE

"On 7/19/05 at 0345, maintenance technicians were performing a voltage check during an I&C surveillance when a lead slipped, making inadvertent contact within the panel. This resulted in shorting of a power connection and blowing a fuse. This fuse supplied initiation and trip logic components associated with the High Pressure Coolant Injection (HPCI) system, the 'A' Core Spray system, and the 'A' Residual Heat Removal (RHR) system. Loss of the HPCI system is reportable under 10 CFR 50.72(b)(3)(v) as a loss of a single train safety system required to mitigate the consequences of an accident.

"Hope Creek entered Technical Specification (TS) 3.0.3 for HPCI inoperability with one Core Spray and one RHR system inoperable. Actions to replace the fuse and restore operability of the HPCI system were completed at 0909 on 7/19/05, allowing exit from TS 3.0.3. Actions to commence staffing for a shutdown and implement required procedures were implemented, however a power reduction was not initiated based on successful restoration.

"The remaining retest activities associated with fuse restoration were completed for the 'A' Core Spray Loop and the 'A' RHR system at 0923 on 7/19/05, clearing the remaining Limiting Conditions for Operation associated with the fuse failure. No additional Emergency Core Cooling Systems or safety related equipment was inoperable during this time period."

The licensee notified the NRC Resident Inspector and Lower Alloways Creek Township.

* * * UPDATE PROVIDED BY DARON ZAKARIAN TO JEFF ROTTON AT 1331 EDT ON 08/05/05 * * *

"Event # 41852, which was made by Hope Creek on July 19, 2005, at 1053, is being retracted.

"Although HPCI was declared inoperable in accordance with the instrumentation Technical Specification due to the instrumentation that was inoperable as a result of the blown fuse, a subsequent review of the HPCI control circuitry determined that HPCI remained capable of automatically performing its safety function in response to any event for which it is credited. Since HPCI was able to perform its safety function, it is not reportable in accordance with 10 CFR 50.72(b)(3)(v) and this notification can be retracted."

The licensee will notify the NRC Resident Inspector.

Notified the R1DO (Gray).

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General Information or Other Event Number: 41854
Rep Org: ALABAMA RADIATION CONTROL
Licensee: INLAND DREDGING
Region: 1
City: JACKSON State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID WALTER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 07/19/2005
Notification Time: 10:04 [ET]
Event Date: 07/18/2005
Event Time: [CDT]
Last Update Date: 08/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1)
MICHELE BURGESS (NMSS)

Event Text

ALABAMA AGREEMENT STATE REPORT - IMPROPER USE AND SHIPMENT OF NUCLEAR GAUGE

The State provided the following information via facsimile:

"Description of Event: A dredging company using GL devices in Alabama illegally, removed and shipped a device containing a 200 milliCuries cesium 137 source to Ronan Engineering Company in Kentucky for repair. The shutter was not locked in the closed position. The owner had painted over the marking and labeling on the source holder so that they were illegible. The dredging company has hired a consultant to reconstruct the incident and try to determine any possible exposures received.

"Additional information will be submitted after the investigation is completed."

The following, additional information was obtained from the State via telephone:

Dredging Company: Inland Dredging, Co. based in Dyersberg, TN, doing work in the vicinity of Jackson, AL
The gauge is currently at Ronan Engineering Co., Florence, KY
Event date is unknown, but the State was notified on the evening of 7/18/05.

* * * UPDATE PROVIDED BY DAVID WALTER (STATE OF ALABAMA) TO JEFF ROTTON VIA FAX AT 1623 EDT ON 08/05/05 * * *

The State provided the following information via facsimile:

"The general licensee stated that they had closed the shutter and placed a bolt through the mechanism to lock it closed. [The general licensee] then removed the device and prepared it for delivery to Ronan Engineering Company via truck. [The general licensee] contends that the shutter handle was broken during shipping. [The general licensee] further states that they had removed the paint from the identification placard on the source head. When [the general licensee] prepared the unit, they stated they bolted the source head to the detector head. This resulted in minimal access to the beam port. Ronan performed a survey of the device, and found maximum exposure readings of 1.5 mrem/hour at 1 meter.

"During shipping, the device went through five transport terminals, and appears to have been transferred to different trucks in each terminal.

"An Alabama licensee authorized to service industrial gauges has been contracted to investigate the incident. This company is traveling to Ronan to obtain further information, and has set up interviews with personnel at the transport terminals."

Notified the R1DO (Gray) and NMSS EO (Moore).

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General Information or Other Event Number: 41859
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: PORT OF OAKLAND
Region: 4
City: OAKLAND State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARK GOTTLIEB
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/20/2005
Notification Time: 16:00 [ET]
Event Date: 07/07/2005
Event Time: [PDT]
Last Update Date: 08/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA SMITH (R4)
TOM ESSIG (NMSS)

Event Text

AGREEMENT STATE REPORT - SCRAP METAL CONTAMINATION

State of California provided the following information via email:
"[The] US Customs Service, Port of Oakland contacted RHB-Berkeley on the morning of 07-07-2005, reporting that a load of scrap metal bound for China had set off a radiation alarm. Mr. Kent Prendergast and Mr. Mark Gottlieb of RHB-Berkeley responded. Measurements were made of the trailer and the following readings were obtained using a Bicron FieldSPEC-N, sn 02f3/777, portable MCA:

"Dose Rates: Surface = 260 R (microR)/hr; 1 foot from surface = 38 R/hr; 1 foot to the left = 35 R/hr; 1 foot to the right = 45 R/hr; 1 foot above = 19 R/hr. The radionuclide was identified as Am-241.

"On 07-08-2005, the Pleasant Hill Recycling Center was visited. The Port of Oakland determined that the load of scrap metal had originated there. [The Recycling Center] President and the Manager were interviewed. They stated that the load was lead scrap which had been accumulating for several years. They said that it would be very difficult to identify the source of the Am-241 if possible at all. They were uncertain if the scrap would be returned to them or handled by the Port of Oakland. [The Recycling Center President had] made contact with a health physics consultant as directed by the Port of Oakland to dispose of the Am-241. The area where the lead was stored was surveyed with both a Ludlum Model 3-98 survey meter with an external thin window, thin crystal Nal probe Mode 44-3, and a Ludlum Model 19 R meter. The results of the survey were negative.

"Based on measurements and calculations performed on 7-19-05 and 7-20-05, the activity of the Am-241/ Be source at the Port of Oakland is from 50 mCi to 150 mCi."

* * * UPDATE FROM K. PRENDERGAST TO W. GOTT AT 1630 ON 08/05/05 * * *

California Radiation Control Program personnel with the assistance of U.S Customs, inspected the scrap metal and found 9 Am-241 sources. They have taken custody of the sources and will conduct analysis to identify and determine where the sources originated.

Notified R4DO (D. Powers) and NMSS EO (S. Moore) and emailed TAS (R. Warren)

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General Information or Other Event Number: 41890
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: GEOSCIENCE GROUP INC
Region: 1
City: CHARLOTTE State: NC
County:
License #: 060-0909-1
Agreement: Y
Docket:
NRC Notified By: GEORGE ACCATTIATO
HQ OPS Officer: BILL GOTT
Notification Date: 08/03/2005
Notification Time: 16:44 [ET]
Event Date: 08/03/2005
Event Time: 14:50 [EDT]
Last Update Date: 08/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HAROLD GRAY (R1)
TRISH HOLAHAN (NMSS)
BEN SANDLER (email) (TAS)

Event Text

MISSING TROXLER GAUGE

After leaving the construction site at the intersection of Highway 74 and Unionville Indian Trail Road, the workers discovered that their Troxler Moisture Density gauge was missing. They returned to the construction site and the gauge was not there. The gauge was a Model 3450 Troxler (s/n 885) with 40 milliCuries Am/Be (s/n 78-515) and 8 milliCuries Cs-137 (s/n 77-261-0). The RSO is investigating. The Troxler was in the "Safe Position" but was not locked.

NC Report number: 05-29.


* * * UPDATE ON 8/5/05 @ 1056 BY ACCATTIATO TO GOULD * * *

The missing Troxler gauge was found (08/05/05 @ 0900) on the highway by a member of the public in Rock Hill, SC just over the boarder between NC and SC. The case of the device was damaged, however, the source was not in the exposed position. It is currently in the possession of the licensee and State inspectors are at the site to inspect the gauge.

Informed Reg 1 RDO (Harold Gray), NMSS EO (Trish Holahan), and TAS (Roberta Warren) by fax.

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Power Reactor Event Number: 41895
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE JESTER
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/05/2005
Notification Time: 21:24 [ET]
Event Date: 08/05/2005
Event Time: 18:40 [EDT]
Last Update Date: 08/06/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KERRY LANDIS (R2)
CATHERINE HANEY (NRR)
TIM MCGINTY (IRD)

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

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABILITY OF ALL EMERGENCY DIESEL GENERATORS

"Event reportability is in accordance with 10 CFR 50.72(b)(3)(v)(D), 'Accident Mitigation,' and 10 CFR 50.72(b)(2)(i), 'TS Required Shutdown,' due to potential COMMON CAUSE FAILURE of all four Emergency Diesel Generators. On 05 August 2005, at 14:31 hrs, DG2 was started for data gathering purposes, and it experienced a trip and lockout on differential current. Investigation revealed that set points for the installed DG differential current protective devices may be set too conservatively. Since each DG has the same relay with the same set point, all DGs were declared inoperable. Preparations are in progress to place both units in Cold Shutdown.

"The site has insufficient operable backup AC sources. The current effect on the plant is minimal due to all normal AC sources being available and operable. However, due to the potential for losing a normal AC source resulting in insufficient power being available to some emergency systems, both units will be placed in cold shutdown until all emergency diesel generators can be restored to operable.

"Corrective actions are in progress to correct differential current protective device problem in order to restore availability of DG2 and operability of all four DGs."

The licensee plans on commencing a down power on both units (Unit 2 first) within several hours. Technical Specifications require both units to be in Hot Shutdown within 12 hours (approximately 0700 on 08/06/05) and Cold Shutdown within 36 hours. Neither unit has any other significant systems LCOs.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM LICENSEE (BAIN) TO NRC (HUFFMAN) AT 10:38 EDT ON 8/06/05 * * *

"This is a follow up message to the initial event reported in accordance with 10 CFR 50.72(b)(3)(v)(D), 'Accident Mitigation' and 10 CFR 50.72(b)(2)(i), 'TS Required Shutdown' due to the potential COMMON CAUSE FAILURE of all four Emergency Diesel Generators. Unit 2 entered Mode 3 (Hot Shutdown) at 04:46. Unit 1 entered Mode 3 (Hot Shutdown) at 05:31. Both units are continuing to cool down in preparation for entering Mode 4 (Cold Shutdown)." The licensee notified the NRC Resident Inspector.

Notified R2DO(Landis), NRR EO (Haney), and IRD (McGinty).

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Power Reactor Event Number: 41896
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MICHAEL HUNTER
HQ OPS Officer: BILL GOTT
Notification Date: 08/05/2005
Notification Time: 21:50 [ET]
Event Date: 08/05/2005
Event Time: 17:08 [CDT]
Last Update Date: 08/06/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KERRY LANDIS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

RPS ACTUATION DUE TO LOW REACTOR WATER LEVEL CAUSED BY LOSS OF REACTOR FEED PUMPS

"At 1708 on 08/05/2005, Unit 2 reactor scrammed from 100% power when reactor water level reached Level 3 Reactor Scram setpoint due to loss of 2C and 2B Reactor Feed Pumps. All rods inserted [fully]. Unit 3 was also at 100% power and was unaffected by this event. Reactor water level reached level 2 (-45) HPCI & RCIC initiation setpoint and was recovered by HPCI and RCIC injection. All expected PCIS isolations, Group 2 (RHR S/D cooling), Group 3 (RWCU), Group 6 (ventilation), and Group 8 (TIP) were received along with the auto start of CREV, 3 SGT trains, HPCI and RCIC with injection into Reactor Vessel. Recirc Pumps tripped at -45" as expected. Four MSRVs lifted momentarily to stabilize reactor pressure.

"This event is reportable at 4 hour and 8 hour Non-Emergency Notification along with a 60 day written report in accordance with 10CFR50.72(b)(2)(iv)(A), 10CFR50.72(b)(2)(iv)(B), 10CFR50.72(b)(3)(iv)(A) and 10CFR50.73(a)(2)(iv)(A) as 'Any event or condition that results in a valid actuation of RPS and PCIS as described in (l) and (2) below.'"

Decay heat is being removed via steam to the main condenser using the bypass valves maintaining pressure at 895 psi. The licensee notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY HUNTER TO JEFF ROTTON AT 1524 ON 08/06/05 * * *

"Upon further evaluation by the trip investigation team, it has been determined that no MSRV's lifted during this event. Reactor pressure data indicated no increasing pressure spike during the transient. The post-scram pressure trends indicated the maximum reactor pressure was normal operating pressure at the start of the transient followed by a gradual decline. The initial report which stated that 4 MSRV's had lifted was in error."

The licensee will notify the NRC Resident Inspector.

Notified the R2DO (Landis).

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Power Reactor Event Number: 41897
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: ELLIS PFEFFER
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/05/2005
Notification Time: 22:46 [ET]
Event Date: 08/05/2005
Event Time: 17:54 [CDT]
Last Update Date: 08/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MONTE PHILLIPS (R3)

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 BOTH CONTROL ROOM EMERGENCY VENTILATION SYSTEMS DURING TESTING

During maintenance testing of the 'B' Control Room Emergency Ventilation system (CRV) the 'A' Air conditioning unit was running. The 'A' A/C unit (V-EAC-14A) tripped on a low service water flow condition while performing step 0255-11-III-4 which manipulated service water valves for the test. The 'B' loop of the CRV system was in a 30 day LCO due to the maintenance testing. When the 'A' A/C unit tripped and the 'B' unit inoperable due to testing, both CRV trains were inoperable and that placed the unit in a 24 hour Tech Spec LCO, 3.17.A.3.a. The compressor unit V-EAC-14A was reset following restart of the 13 Emergency Service Water pump 8 minutes after the trip and exited the 24 hour LCO.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41898
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/06/2005
Notification Time: 00:20 [ET]
Event Date: 08/05/2005
Event Time: 22:28 [EDT]
Last Update Date: 08/06/2005
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):
KERRY LANDIS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP APPARENTLY DUE TO LIGHTNING STRIKE

The Unit 2 reactor automatically tripped due to an overpower-delta temperature (OpDeltaT) trip signal. The licensee states that an actual OpDeltaT condition did not exist at the time of the trip. The trip signal is believed to have been generated by lightning strikes from an electrical storm that was passing through the area at the time. The trip was uncomplicated and all systems functioned as required. All control rods fully inserted; no safety relief valves lifted; decay heat is being discharged to the main condenser using normal feedwater to supply the steam generators; the reactor temperature and pressure are at normal hot standby range. No obvious grid disturbance was seen during the trip and Unit 1 was not impacted (Unit 1 was being ramped offline at the time for secondary side maintenance work). The licensee noted that Auxiliary Feedwater did auto-start as expected due to a trip from full power and was subsequently secured.

The licensee is still investigating the cause of the OpDeltaT trip signal but noted that other Unit 2 instrumentation was found failed after the transient including the Unit 2, A-loop, wide range T-hot and T-cold indications and the Unit 2, B-loop, T-cold indication. The licensee plans to remain in Mode 3 until the investigation is complete and instrument repairs completed.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41899
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: MARK BARATTA
HQ OPS Officer: MIKE RIPLEY
Notification Date: 08/06/2005
Notification Time: 04:42 [ET]
Event Date: 08/06/2005
Event Time: 04:03 [EDT]
Last Update Date: 08/06/2005
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
HAROLD GRAY (R1)
BRIAN HOLIAN (R1)
CATHERINE HANEY (NRR)
TIM MCGINTY (IRD)
K. SWEETSER (FEMA)
C. NOWAKI (EPA)
C. MCKENTRY (DHS)
J. PAULEY (DOE)
H. PEAGLER (HHS)
R. MAGNERS (USDA)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 43 Power Operation

Event Text

ALERT DECLARED DUE TO LOW INTAKE WATER LEVEL

The licensee declared an Alert (EAL HA3) at 0403 ET 08/06/05 due to low water level in the north half of the intake structure as a result of heavy grass accumulation due to a storm in the area. Intake level recovered to above the EAL value for an Alert, and the event was de-escalated to an Unusual Event (EAL HU3) at 0406 ET. One Circulating Water Pump associated with the north intake was immediately secured and reactor power was reduced to 43%. When the second Circulating Water Pump associated with the north intake was secured, intake water level returned to normal. As a result of the grassing, trash racks collapsed and traveling screen shear pins sheared at the north intake. The traveling screens were subsequently restored to service.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM E. DEMONCH TO M. RIPLEY AT 0800 ET 08/06/05 * * *

The licensee terminated the Unusual Event at 0755 ET 08/06/05. The licensee notified the NRC Resident Inspector. Notified R1 DO (H. Gray), NRR (J. Dyer, C. Haney), NSIR IRD (T. McGinty), R1 (Dapas, Holian, Bellamy, Bores), HHS (J. Tribble), USDA (J. Jones), DHS (M. Inzer), FEMA (Liggett), EPA/NRC (P. Layman), DOE (M. Wyatt).

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Power Reactor Event Number: 41900
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN PFFIFFER
HQ OPS Officer: BILL GOTT
Notification Date: 08/07/2005
Notification Time: 20:06 [ET]
Event Date: 08/07/2005
Event Time: [EDT]
Last Update Date: 08/07/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KERRY LANDIS (R2)

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

SPDS UNAVAILABLE FOR GREATER THAN ONE HOUR

"Unit SPDS was unavailable for greater than 60 minutes due to a plant computer system failure. SPDS was unavailable from 1507 on 08/07/05 until 1900 on 08/07/05."

The licensee notified the NRC Resident Inspector.

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