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Event Notification Report for April 27, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/26/2004 - 04/27/2004

** EVENT NUMBERS **


40686 40692 40704 40705

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Power Reactor Event Number: 40686
Facility: OCONEE
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: ARLON COSTA
Notification Date: 04/20/2004
Notification Time: 10:55 [ET]
Event Date: 03/20/2004
Event Time: 15:59 [EDT]
Last Update Date: 04/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
CAUDLE JULIAN (R2)

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

INVALID ACTUATION OF THE MOTOR DRIVEN EMERGENCY FEEDWATER PUMPS

"By design, the Steam Generator (SG) Dry-out Protection Circuit actuates whenever two level indications (two of two actuation logic) in either SG are lower than the setpoint for more than 30 seconds. This start circuit is not credited in any ONS safety analysis, therefore this signal is considered an INVALID signal with respect to 50.73 (a)(2)(iv)(A). Upon actuation, the circuit starts both Motor Driven Emergency Feedwater Pumps (MDEFWPs) on the affected unit. It does not send a start signal to the Turbine Driven Emergency Feedwater Pump.

"Shortly after entering Mode 4, a control operator stopped one of two operating Reactor Coolant Pumps per the Unit shutdown procedure. A second control operator was manually controlling Feedwater and reduced flow to control the system cooldown rate, without recognizing that the 2B SG had reached the low level setpoint for SG Dry-out Protection Circuit actuation.

"In this event, the 2B SG level trains A and B indicated lower than the setpoint value (-21 inches) for more than 30 seconds, so the SG Dry-out Protection Circuit started the 2A and 2B MDEFWPs. The actuation was considered complete and the system started and functioned successfully. Both MDEFWPs started. The 2B SG control valve, 2FDW-316, opened and fed the 2B SG from the 2B MDEFWP for approximately one minute until the SG level reached the EFDW control setpoint (30 inches). The 2A pump did not feed the 2A SG because 2A SG level remained well above the EFDW control setpoint so there was no demand for the 2A SG control valve, 2FDW-315, to open."

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 4/26/04 AT 16:23 FROM R. TODD TO A. COSTA * * *
This update is to clarify a typographic misspelling on the first sentence of the last paragraph of this event notification which should read (~[approximately] 21 inches) instead of (-21 inches). Notified R2DO(Julian).

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General Information or Other Event Number: 40692
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: CONAGRA FOODS
Region: 1
City: NEWPORT State: TN
County:
License #: 337
Agreement: Y
Docket:
NRC Notified By: BILLY FREEMAN
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/21/2004
Notification Time: 13:45 [ET]
Event Date: 04/21/2004
Event Time: [EDT]
Last Update Date: 04/21/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID SILK (R1)
JOSEPH GIITTER (NMSS)
TOM DECKER (R2)
JIM WHITNEY (TAS)

Event Text

AGREEMENT STATE REPORT INVOLVING LOST GENERAL LICENSE SOURCE MATERIAL

"The licensee called to report that a Filtec FT-50 fill level gauge, serial number, 112082, containing 100 millicuries of Am-241 in sealed source, serial number 4473, could not be located during inventory. The unit was removed from a manufacturing line in June, 1995 and stored in a building along with other idle equipment. During a recent project to clean this building and dispose of old equipment, the licensee was unable to locate this unit. An extensive search was conducted throughout the facility and the gauge could not be located. Personnel who may have had knowledge of the unit were interviewed. The last documented time that the gauge was seen in storage was in January 1998. The licensee believes that the unit was discarded with other idle equipment. The manufacturer's records indicate the source was not returned to them. Inspectors [Tennessee Division of Radiological Health] are enroute to the facility to investigate."

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Other Nuclear Material Event Number: 40704
Rep Org: STERIGENICS/IBA (Former RTI)
Licensee: STERIGENICS/IBA (Former RTI)
Region: 1
City: SALEM State: NJ
County:
License #: 29-20900-01
Agreement: N
Docket:
NRC Notified By: THOMAS DALFONSO
HQ OPS Officer: ARLON COSTA
Notification Date: 04/26/2004
Notification Time: 14:09 [ET]
Event Date: 04/22/2004
Event Time: 13:30 [EDT]
Last Update Date: 04/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
36.83(a)(10) - POOL COND HIGH
Person (Organization):
RICHARD BARKLEY (R1)
THOMAS ESSIG (NMSS)

Event Text

HIGH CONDUCTIVITY READINGS IN GAMMA POOL

On 4/22/04, around 13:30 EDT, after the irradiator shielding pool had been vacuumed, pool water conductivity exceeded 100 microsiemens per centimeter. The licensee initiated a change of the resin beds and observed pool water conductivity to decrease, as expected. On 4/23/04, the licensee noticed that pool water conductivity had increased to 110 microsiemens per centimeter. New resin beds are being placed in service today (4/26/04) by 18:00 and its is expected that pool water conductivity will decrease from 201 microsiemens to levels of less than 20 microsiemens per centimeter within 24 to 48 hours at the current recirculation rate through the resin beds. There are no personnel safety issues involved with this incident. The licensee will contact the Operations Center if the expected water pool conductivity does not return to normal operating levels.

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Power Reactor Event Number: 40705
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: BRUCE BREDEMAN
HQ OPS Officer: ARLON COSTA
Notification Date: 04/26/2004
Notification Time: 20:06 [ET]
Event Date: 04/26/2004
Event Time: 17:11 [CDT]
Last Update Date: 04/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
CHARLES MARSCHALL (R4)

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

Event Text

TECHNICAL SPECIFICATIONS REQUIRED REPORT OF STEAM GENERATOR DEFECTIVE TUBES

"During Refueling Outage RF13, interim results of 'A' Steam Generator (S/G) tube inspections indicate 59 tubes out of 5341 tubes (i.e., > 1 %) have been determined to be defective. This S/G tube inspection result for the 'A' S/G is classified as category C-3 in accordance with Technical Specification 5.5.9, Table 5.5.9-2. Per NUREG 1022, Section 3.2.4 Discussion (A)(3), the present C-3 classification of the 'A' S/G tubes does not meet the listed criteria for serious S/G tube degradation and thus is not a degraded or unanalyzed condition. Since this report is required by Administrative Technical Specification 5.5.9, this notification is being listed as an 'Other Unspecified Requirement'.

"All defective tubes will be removed from service before the S/G is returned to service. There were no adverse safety consequences or implications as a result of this event. This event did not adversely affect the safe operation of Callaway Plant or the health and safety of the public."

The licensee notified the NRC Resident Inspector.

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