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Event Notification Report for April 23, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/22/2010 - 04/23/2010

** EVENT NUMBERS **


45782 45855 45857 45858 45866 45867 45868

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General Information or Other Event Number: 45782
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WEATHERFORD US LP
Region: 4
City: BENBROOK State: TX
County:
License #: L-00747
Agreement: Y
Docket:
NRC Notified By: BOB FREE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/22/2010
Notification Time: 17:36 [ET]
Event Date: 03/19/2010
Event Time: [CDT]
Last Update Date: 04/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICK DEESE (R4DO)
JIM LUEHMAN (FSME)

Event Text

AGREEMENT STATE REPORT - WELL LOGGING TOOL EJECTED DURING WELL BLOW-OUT

The following information was received from the State of Texas via e-mail:

"Weatherford personnel were logging a well in Howard County, Texas when a blow out occurred. The logging tool was at 3500 feet when the tool and wireline were ejected from the well bore. The blow out preventer did not stop the tool and wireline from being ejected onto the surface. The crew evacuated the drilling rig due to the hazards associated with the high downhole pressure. Initially it was unknown whether the logging tool was still in the hole. A logging company manager conducted radiation surveys and found the tool, with the sources still in place near the logging truck. The sources were secured in their transport shields and returned to the company office for leak testing. At this point, there is no estimate of exposures to personnel at the well site."

Texas Report # I-8726

* * * UPDATE ON 04/22/2010 AT 1524 EDT FROM A. TUCKER TO R. ALEXANDER * * *

The following update was received from the State of Texas via e-mail:

"The licensee notified the Agency [Texas Department of State Health Services] that leak test results on the cesium and the americium-beryllium sources were satisfactory. The licensee stated that a visual examination of the sources did not find any physical damage."

Notified R4DO (J. Whitten) and FSME EO (C. Einberg).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45855
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/19/2010
Notification Time: 03:12 [ET]
Event Date: 04/18/2010
Event Time: 22:25 [CDT]
Last Update Date: 04/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ORTH (R3DO)

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

LCO 3.0.3 ENTRY AND LOSS OF SAFETY FUNCTION DUE TO LOSS OF TURBINE BUILDING HIGH ENERGY LINE BREAK COMPENSATORY MEASURE

"At 2225 CDT on 4/18/2010, Operations discovered that the Unit 1 Turbine Building Truck Aisle Rollup Door Security Fence was closed. This fence was to be maintained open as the truck aisle is a required drainage path from the Unit 1 Turbine Building to outside in the event of flooding resulting from a High Energy Line Break (HELB). With the expanded metal mesh door [fence] closed, turbine building debris could clog the drainage path and result in a higher than calculated water level being reached for this event. As the final water level cannot be predicted, this represented an unanalyzed condition. The higher water levels would be reached at least one hour after the postulated turbine building HELB event. High water levels could result in a Loss of Safety Function for Unit 1 Emergency Diesel Generators. Auxiliary Feedwater (both units) and DC Electrical Power (both units) if water levels exceed critical heights in the associated rooms.

"The doors [fence] were reopened at 2227 CDT. Unit 1 entered LCO 3.0.3 for this two minute period. With the doors [fence] opened, Unit 1 and 2 LCO conditions were again satisfied.

"The Unit 2 truck aisle was in the assumed condition, and Unit 2 is in Mode 5 so loss of AFW or DC power would not result in an LCO 3.0.3 entry. Unit 2 Emergency Diesel Generators are not affected as the Unit 2 truck aisle drain path would prevent water levels from reaching critical heights.

"The initial investigation determined that a Security Officer had closed the gate at approximately 1855 CDT on 4/18/2010.

"The NRC Resident Inspector has been notified. A press release is not planned."

* * * RETRACTION AT 1454 ON 4/22/2010 FROM DARRELL LAPCINSKI TO MARK ABRAMOVITZ * * *

"In reference to the 4/18/2010 discovery of the security fences (screen door) closed on the Unit One Turbine Building truck aisle door and the Tech Spec LCO 3.0.3 entry on Unit One, further analysis of HELB flooding scenarios in the plant configuration known to be in effect at that time has shown that the LCO 3.0.3 entry was not warranted. Engineering analysis demonstrates that water levels in the Unit One Turbine Building from a postulated worst case HELB flooding event would only have rendered the 12 Motor Driven Auxiliary Feedwater Pump inoperable. Thus TS LCO 3.7.5 Condition B would have been the only LCO action statement required to be entered. No loss of safety function existed."

The licensee will notify the NRC Resident Inspector.

Notified the R3DO (Skokowski).

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General Information or Other Event Number: 45857
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: NORTH MIAMI BEACH SURGICAL
Region: 1
City: NORTH MIAMI BEACH State: FL
County:
License #: 3589-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/19/2010
Notification Time: 17:33 [ET]
Event Date: 04/19/2010
Event Time: [EDT]
Last Update Date: 04/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1DO)
JACK FOSTER (FSME)
LAURA PEARSON (ILTA)

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

Event Text

AGREEMENT STATE REPORT - LOST BRACHYTHERAPY SEEDS

The following information was received from the State of Florida Bureau of Radiation Control via facsimile:

"Licensee discovered 51 I-125 brachytherapy seeds missing on 13 April 2010. Initial notification to the state was on 16 April 2010, after working hours, to the [State of Florida] duty officer. A search of the premises and outside garbage containers was performed [with negative results]. The search is still on going. Investigation [of this incident has been] assigned to [the State of Florida Bureau of Radiation Control] Miami Office."

Florida Incident #: FL10-056

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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General Information or Other Event Number: 45858
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SHERWIN ALUMINA, LLC
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: 00200
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/20/2010
Notification Time: 15:06 [ET]
Event Date: 04/19/2010
Event Time: [CDT]
Last Update Date: 04/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
CHRISTIAN EINBERG (FSME)

Event Text

TEXAS AGREEMENT STATE REPORT - NUCLEAR GAUGE SHUTTERS STUCK OPEN

The following information was obtained from the State of Texas via email:

"On April 20, 2010, the Agency [Texas Department of Health] was notified by the licensee that on April 19, 2010, while conducting calibrations on two continuous density measurement detectors, the associated nuclear gauge shutters were found to be stuck in the open position. Open is the normal position for these gauges. The gauges are Ohmart gauges containing 100 millicuries each of Cesium-137 (original activity). The gauges are model SR-A serial numbers 7613 GK and 8150 GK. The Radiation Safety Officer (RSO) has placed notification tags on the gauges to warn workers of the problem. The manufacturer has been contacted to provide repairs to the gauges."

Texas Incident # I-8732

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Power Reactor Event Number: 45866
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/22/2010
Notification Time: 13:20 [ET]
Event Date: 04/22/2010
Event Time: 10:51 [EDT]
Last Update Date: 04/22/2010
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):
RICHARD CONTE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 32 Power Operation 0 Hot Shutdown

Event Text

REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL DURING FEEDWATER INTEGRATED CONTROL SYSTEM TESTING

"At 10:51 on 4/22/10, Susquehanna Unit 1 experienced an automatic reactor SCRAM on reactor low level, +13", during the initial testing of the Feedwater Integrated Control System. Following the SCRAM, reactor water level dropped to approx. -30", and the Reactor Core Isolation Cooling system initiated and injected into the vessel. Level was recovered by the Feedwater System and the RCIC system. Division 2 Alternate Rod Insertion unexpectedly initiated during the level transient. Due to scheduled maintenance activities, the 11B Aux Bus did not transfer to the off site power supply post SCRAM. The 11B Aux bus was restored at 12:17. There were no ECCS initiations and no challenges to containment.

"This event is a Reactor Protection System (RPS) actuation when the reactor is critical, and is reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(iv)(B). This event is also an unplanned actuation of a system used to mitigate the consequences of a significant event and is reportable as an eight hour ENS notification under 10CFR50.72(b)(3)(iv)(A)."

The scram was described as uncomplicated. All rods fully inserted and all systems functioned as required. The initiation of the alternative rod insertion should not occur unless level drops below -38" but the initiation did not result in any complications. The offsite supply breaker to Aux bus 11B was under maintenance when the scram occurred and so the loss of power was expected. This bus supplies some balance of plant loads which were lost (recirculation pump, condensate pump, and circulating water pump) but the loss of these components had no impact on the transient.

The NRC Resident Inspector has been notified. The licensee will notify State authorities and also plans a press release.

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Power Reactor Event Number: 45867
Facility: BYRON
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BLAINE PETERS
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 04/22/2010
Notification Time: 15:17 [ET]
Event Date: 04/19/2010
Event Time: 05:03 [CDT]
Last Update Date: 04/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
MIKE CHEOK (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

RPS AND AFW ACTUATION SIGNALS WHILE SHUTDOWN IN MODE 4

"Unit 2 was in Hot Shutdown [Mode 4] for a Refueling Outage. At 0503 [CDT] on April 19, 2010, a valid Lo-Lo Steam Generator level condition occurred during restoration of feedwater system testing. The feedwater test was a planned activity and included isolation of feedwater to the steam generators. During performance of the test, steam generator levels decreased and the Lo-Lo level setpoint was reached on the 2D steam generator. This generated a reactor trip signal and auxiliary feedwater system start signal. Since the Unit was in Hot Shutdown, the reactor trip breakers were already open, and the auxiliary feedwater system was already removed from service when the steam generator water level unintentionally reached the Lo-Lo level setpoint. Additionally, the open steam generator blowdown isolation valves closed as expected at the Lo-Lo steam generator level setpoint. Steam generator level was promptly restored above the Lo-Lo steam generator setpoint. There was no impact on the reactor cooldown that was concurrently in progress as part of the preparation for refueling. Initial screening of the condition determined as not reportable in accordance with 10 CFR 50.72(b)(3)(iv), however, based upon further review it has been determined the condition is reportable."

At the time of the event, both trains of shutdown cooling were in service and there were no challenges to offsite power. The licensee was not required to enter any Technical Specification LCO action statements as a result of the event, and the licensee is still investigating the cause of the decrease in steam generator level below the Lo-Lo level setpoint.

The licensee has informed the NRC Resident Inspector.

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Power Reactor Event Number: 45868
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JEFF WILLIAMS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/22/2010
Notification Time: 15:57 [ET]
Event Date: 04/22/2010
Event Time: 10:01 [CDT]
Last Update Date: 04/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

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

FITNESS FOR DUTY TEST

A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations officer for additional details.

The licensee informed the NRC Resident Inspector.

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