United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2004 > January 12

Event Notification Report for January 12, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/09/2004 - 01/12/2004

** EVENT NUMBERS **


40378 40427 40430 40432 40434 40435 40436

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40378
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/06/2003
Notification Time: 04:44 [ET]
Event Date: 12/05/2003
Event Time: 23:49 [EST]
Last Update Date: 01/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD CONTE (R1)

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

Event Text

A LEVEL 3 LOW REACTOR WATER LEVEL WAS REACHED DURING A REACTOR WATER LEVEL TRANSIENT

The reactor was being shutdown as part of a planned evolution to allow repairs on the Reactor Water Cleanup flange leak. After the Reactor Protection System Mode Select Switch had been placed in shutdown, the resulting reactor level transient caused the Level 3 low reactor level set point to be reached. The Reactor Protection System had already been de-energized and the lowest level reached during the transient was +2 inches. This level transient is a normal occurrence on a reactor shutdown, and level was restored to the normal operating band. There was no effect on the plant due to reaching the low level set point. No other abnormal plant response was noted.

The licensee will notify the NRC Resident Inspector

* * * RETRACTION ON 1/9/04 AT 1310 FROM CLYDE BAUER TO E. THOMAS * * *

"Upon further review of this event, the resulting Level 3 low reactor water level signal following the manual scram is considered part of the pre-planned sequence in accordance with the guidance of NUREG-1022. Therefore, this event is not reportable under 10 CFR50.72(b)(3)(iv)(A) and is being retracted."

Notified R1DO (J. Noggle)

To top of page
General Information or Other Event Number: 40427
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: VULCAN CHEMICALS
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2848-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/06/2004
Notification Time: 11:40 [ET]
Event Date: 12/02/2003
Event Time: [CST]
Last Update Date: 01/06/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MIKE RUNYAN (R4)
DOUG BROADDUS (NMSS)

Event Text

AGREEMENT STATE REPORT CONCERNING LOST GAUGE

"A Kay-Ray Model 7063P gauge with serial number 12349 and a 500 milliCurie source of Cs-137 was not accounted for during the last Radiation Source Survey. The device has been stored in a locked warehouse with limited access since 1984. It was stored in a secured wooden crate with proper labeling. A search was conducted and interviews performed. As of December 2, 2003 the device has not been found. An email from Thermo Electron Corporation states that the source has decayed to 316.366 milliCurie. Vulcan also notified all of its scrap metal contractors to be on alert for the device."

To top of page
General Information or Other Event Number: 40430
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE METHODIST HOSPITAL
Region: 4
City: HOUSTON State: TX
County:
License #: L00457-000
Agreement: Y
Docket:
NRC Notified By: JAMES H. OGDEN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/07/2004
Notification Time: 16:43 [ET]
Event Date: 01/05/2004
Event Time: 08:16 [CST]
Last Update Date: 01/07/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MIKE RUNYAN (R4)
JOSEPH GIITTER (NMSS)

Event Text

AGREEMENT STATE REPORT: NOVOSTE STRONTIUM-90 INTRAVASULAR BRACHYTHERAPY (IVB) SOURCE DISCOVERED MISSING.

"Novoste Strontium-90 Intravascular brachytherapy (IVB) source (remote afterloader) was discovered missing on January 5, 2004. Source was last seen but not used on December 17, 2003. Reported by phone by RSO. Source is a small handlheld device - Manufacturer: Novoste, Model: BethCath, Serial No. 92607; Source train Serial No. ZB-520; Original Activity 55.62 millicuries; current activity (date of discovery) 54.64 millicuries; Calibration date: 04/11/2003; Last leak test 10/29/2003. Received at the hospital on November 4, 2003. Last used in a patient on December 5, 2003 (first and last use). Last seen on during a functional test on December 17, 2003 in the Fondren Building, Room F1099 (near cath lab) at the Licensee's main site 6565 Fannin Street, Houston, Texas. The source was not used that day. Two other sources of different activity and length remain in storage. The room and cath lab have been search 4 times by the Licensee's staff. Trash has been surveyed. Hospital staff has been notified of the missing equipment.."

Texas Incident No.: I-8089.

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40432
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DENNIS BEAMIS
HQ OPS Officer: RICH LAURA
Notification Date: 01/08/2004
Notification Time: 18:45 [ET]
Event Date: 01/08/2004
Event Time: 17:58 [EST]
Last Update Date: 01/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES NOGGLE (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

OFFSITE NOTIFICATION AT SEABROOK

The licensee reported that the upper lights on the meteorological tower were not working. The licensee made an offsite notification to the FAA and will initiate corrective actions.

The licensee notified the NRC resident inspector.


* * * UPDATE ON 01/09/04 @ 0859 BY RITTER TO GOULD * * * RETRACTION

The licensee is retracting this notification after a further review of the reporting requirements determined that the notification was unnecessary. The condition reported to other government agencies was not related to the radiological health and safety of the public or onsite personnel or the protection of the environment.

The NRC Resident Inspector was informed.

Notified Reg 1 RDO (Noggle)

To top of page
Power Reactor Event Number: 40434
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: AL HARTNER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 01/10/2004
Notification Time: 04:40 [ET]
Event Date: 01/10/2004
Event Time: 01:27 [EST]
Last Update Date: 01/10/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DANIEL HOLODY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 72 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN INITIATED AND SUBSEQUENTLY TERMINATED

"During a surveillance of the Beaver Valley Power Station Unit No. 1 Solid State Protection System (SSPS) train "B" on 01/09/2004, a master relay contact exhibited unacceptable high resistance and was declared inoperable at 2042 hours. Corrective action was initiated to replace the relay, which requires that the "B" train of the reactor trip system be transferred from the reactor trip breaker to the bypass reactor trip breaker and the "B" train of SSPS be de-energized. Action 40.b of Technical Specification 3.3.1.1, Table 3.3-1, Item 21 requires the Unit to be in at least Hot Standby within 6 hours with one reactor trip breaker inoperable as a result of something other than an inoperable diverse trip feature. Bypassing the reactor trip breaker in order to replace the SSPS master relay makes the reactor trip breaker inoperable as a result of something other than an inoperable diverse trip feature.

"The 'B' train Reactor Trip System reactor trip breaker was bypassed at 00:28 hours on 01/10/2004. Beaver Valley Power Station Unit No. 1 initiated a plant shutdown at 01:27 hours on 01/10/2004 in response to entering Action 40.b of Technical Specification 3.3.1.1, Table 3.3-1, Item 21.

"Action to replace the SSPS master relay was completed and the reactor trip breaker was returned to operability at 02:55 hours and the plant shutdown was terminated at 72% power. The Unit is scheduled to return to full power operation.

"Source Range N-31 re-energized when source range high voltage switch was restored to "Normal" position. Investigation is currently underway to determine the cause of this."

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 40435
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDREW OHRABLO
HQ OPS Officer: ERIC THOMAS
Notification Date: 01/10/2004
Notification Time: 13:48 [ET]
Event Date: 01/10/2004
Event Time: 05:00 [CST]
Last Update Date: 01/10/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MIKE RUNYAN (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

ACCIDENT MITIGATION - CREFS INOPERABLE

This Notification is being made pursuant to 10 CFR 50.72 (b)(3)(v)(D).

On January 8, 2004 at 17:35 CST with the Control Room Emergency Filtration System (CREFS) inoperable for planned maintenance, CREFS failed post work testing due to system flow being higher than that allowed by technical specifications. It was originally believed that the failure was connected with the planned maintenance because the system flow rate was initially within the specifications during surveillance testing the previous clay.

Following system troubleshooting, at 05:00 CST on January 10, 2004, it was determined that the cause of the high flow rates was indeterminate. Based on this evaluation, it could not be determined whether the CREFS failure was independent of planned maintenance or not. Additionally, it is not immediately clear if the high flow condition would result in a loss of safety function. It was therefore conservatively determined that the condition is reportable per 10 CFR 50.72 (b)(3)(v)(D) as a failure of a single train system which could have prevented the fulfillment of a safety function that is needed to mitigate the consequences of an accident.

CREFS flow rates are currently within specifications, but the system will remain inoperable until the proper surveillances have been completed.

The senior NRC Resident has been notified.

To top of page
Power Reactor Event Number: 40436
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: FRANK PAYNE
HQ OPS Officer: RICH LAURA
Notification Date: 01/10/2004
Notification Time: 15:22 [ET]
Event Date: 01/10/2004
Event Time: 13:00 [EST]
Last Update Date: 01/10/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DANIEL HOLODY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 1 Startup 1 Startup

Event Text

TS REQUIRED SHUTDOWN AT NMP1 DUE TO INOPERABLE MSIV

"During the performance of a normal orderly planned shutdown for maintenance a packing leak was discovered on Main Steam Inboard Isolation Valve 01-02 (01-02). Drywall inspection results revealed MSIV 01-02 operator gear housing degraded allowing grease to be lost. Engineering assessment of the condition of the limitorque operator of MSIV 01-02 is not able to provide enough information to support operability of MSIV 01-02. Declaring MSIV 01-02 inoperable. Entering T.S. 3.2.7(b and c). Action required to close one valve in the line having an inoperable valve or initiate a normal orderly shutdown with in one hour and be in cold shutdown within ten hours. Entering T.S. 3.3.4(b and c). Action required to close one valve in the line having an inoperable valve within four hours or reduce reactor coolant temperature to a value less than 215 degrees F within ten hours. Most limiting action required in current condition is 10 hours to be in cold shutdown. 01-02 will be closed as soon as all rods are in."

The NRC Resident Inspector was notified.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012