United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for June 11, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/08/2007 - 06/11/2007

** EVENT NUMBERS **


43411 43413 43414 43415 43416

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General Information or Other Event Number: 43411
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: METCO
Region: 4
City: LAKE CHARLES State: LA
County:
License #: LA-8043-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/06/2007
Notification Time: 12:36 [ET]
Event Date: 05/08/2007
Event Time: [CDT]
Last Update Date: 06/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4)
GREG MORELL (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING EQUIPMENT FAILURE OF RADIOGRAPHY CAMERA

The following report was received from the Louisiana Department of Environmental Quality (LA DEQ) via fax:

"[A] field inspection was performed on a field crew for METCO. [While] performing the inspection a misconnect test was performed. The crank outs had a serial number of MST 225 manufactured by AEA Technologies and the camera was an Amersham 880 Sigma with serial number S1712. This misconnect test failed. The crank outs were removed [from] operation and taken back to the shop. The problem was located on the crank out and was repaired. A misconnect test was then performed with the same camera and an additional camera and it passed the test. METCO stated that they will pay closer attention to damage and wear and tear on equipment."

LA Event Report ID No.: LA070014

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Power Reactor Event Number: 43413
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: D. MAY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 06/08/2007
Notification Time: 10:49 [ET]
Event Date: 06/08/2007
Event Time: 09:10 [EDT]
Last Update Date: 06/08/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD BARKLEY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 81 Power Operation 81 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.

"During the performance of quarterly HPCI valve testing in accordance with OP4120 one of the two injection valves, HPCI-19, did not stroke open as required. Prior to testing the HPCI system was in normal standby line up. HPCI-19 was stroke tested during the outage on 6-1-07 and operated normally. HPCI-19 was also tested and verified to open during the ECCS test on 6-1-07."

HPCI was declared inoperable per Technical Specification 3.5.E.2 (14 day Limiting Condition of Operation). All other ECCS systems and the EDGs are fully operable and the electrical grid is stable.

The licensee has initiated repair efforts.

The NRC Resident Inspector was notified of this event by the licensee.

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Power Reactor Event Number: 43414
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: JOE O'HARA
Notification Date: 06/09/2007
Notification Time: 15:53 [ET]
Event Date: 06/09/2007
Event Time: 11:00 [CDT]
Last Update Date: 06/09/2007
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):
PAUL FREDRICKSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 79 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TURBINE TRIP AS A RESULT OF HIGH MOISTURE SEPARATOR REHEATER TANK LEVEL

"On 06/09/2007 at 1100 CDT, Browns Ferry Unit 1 received an automatic SCRAM due to a Turbine Trip Signal caused by a Moisture Separator Drain Tank Level High. All control rods inserted and all systems responded as required to the automatic SCRAM signal. Two Main Steam Relief Valves (MSRVs) momentarily lifted in response to the pressure transient. No Emergency Core Cooling System (ECCS) initiations occurred as a result of the SCRAM. Reactor water level lowered below Level 3 (+2") as a result of the SCRAM and was recovered to the normal level band by the reactor feed pumps (RFPs). The expected Primary Containment Isolation System (PCIS) Groups 2, 3, 6, and 8 isolations were received due to reactor water level lowering below Level 3 (+2") with all systems isolating as required. Additionally, the expected initiation of the RPT breakers from the turbine trip was received which resulted in the trip of both reactor recirculation pumps. Reactor pressure is being controlled using Main Steam Bypass Valves. Reactor Level is being maintained in band using RFPs. Cooldown is in progress to Mode 4. Investigation into the event is proceeding.

"The NRC Senior Resident Inspector has been informed of this event.

"This event is reportable under 10CFR50.72(b)(2)(iv)(B) 'any event or condition that results in a valid actuation of the Reactor Protection System'; 10 CFR50.72(b)(3)(iv)(A), ' Any event that results in an actuation of the specified systems'. This event also requires a 60 day written report in accordance with 10CFR50.73(a)(2)(iv)(A)."

* * * UPDATE FROM BOLAND TO HUFFMAN AT 1850 EDT ON 6/9/07 * * *

Follow-up review of the reported reactor scram revealed that the Group 8 isolation did not function as required. Specifically, the licensee provided the update below concerning the function of one of the reactor's five Traversing Incore Probes (TIP) that had been used the previous day for flux mapping and were in the drywell (not fully retracted) to permit decay when the scram occurred.

"The Group 8 isolation signal received during Unit 1 Rx SCRAM on 06/09/2007 @ 1100 did not automatically go to completion as designed. The 'D' TIP failed to automatically withdraw as required. When the TIP was manually withdrawn, the TIP Ball valve closed as required. The local resident was notified. A work order and PER was written to correct the deficiency."

The other four TIPs did retract and the corresponding ball valves shut as expected. R2DO (Fredrickson) notified.

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Other Nuclear Material Event Number: 43415
Rep Org: B. JONES & SONS PAVING
Licensee: B. JONES & SONS PAVING
Region: 3
City: BROWNSBURG State: IN
County:
License #: GENERAL
Agreement: N
Docket:
NRC Notified By: BUCK JONES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/10/2007
Notification Time: 14:00 [ET]
Event Date: 06/10/2007
Event Time: [EDT]
Last Update Date: 06/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
MONTE PHILLIPS (R3)
SCOTT MOORE (FSME)
MICHAEL SHANNON (R4)

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

Event Text

STOLEN NITON METAL ANALYZER

The licensee possessed a Niton Metal Analyzer (believed to be a Model XRF but not certain). The analyzer is used for scrap metal alloy analysis. The analyzer was inadvertently left in the company truck which was being used for personal business. The truck was broken into while parked at a hotel in Humble, Texas (Country Heart Inn and Suites) and the Niton Analyzer was stolen. The licensee did not know the source in the analyzer. Based on information found on the internet it is believed to be a 40millicurie Cadmium-109 source. The licensee plans to file a police report.

R4DO (Shannon) will ensure that the State of Texas is notified.


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.

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Power Reactor Event Number: 43416
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MATT EVANS
HQ OPS Officer: JASON KOZAL
Notification Date: 06/11/2007
Notification Time: 01:17 [ET]
Event Date: 06/10/2007
Event Time: 20:03 [CDT]
Last Update Date: 06/11/2007
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 97 Power Operation 97 Power Operation

Event Text

HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE DUE TO FAILED INVERTER

"At 2003 on 6/10/07, the division 3 Nuclear System Protection System (NSPS) inverter power supply failed for unknown reasons. As a result of this failure, the High Pressure Core Spray (HPCS) system has been declared inoperable. This is a failure of a single train safety system and is reportable under 10 CFR 50.72(b)(3)(v)(D). Troubleshooting has been initiated to determine the cause of this failure."

The licensee notified the NRC Resident Inspector.

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