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Event Notification Report for July 10, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/07/2006 - 07/10/2006

** EVENT NUMBERS **


42690 42691 42692 42693

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Power Reactor Event Number: 42690
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE MAYO
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/07/2006
Notification Time: 15:43 [ET]
Event Date: 07/07/2006
Event Time: 14:45 [EDT]
Last Update Date: 07/07/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
PAUL FREDRICKSON (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

ALTERNATIVE REPORT FOR NON-DECLARED EMERGENCY CONDITION IN ACCORDANCE WITH NUREG-1022

"On July 7, 2006, at 1445 hours with Watts Bar Unit 1 at 100% power, operations were underway to prepare to sluice resin to the spent resin storage tank. Due to a suspected valve alignment anomaly, approximately 60 gpm from the CVCS volume control tank transferred thru the cation vessel to the tritiated drain collector tank. This is considered identified leakage in accordance with EAL 2.6 RCS Leakage greater than 25 gpm.

"This condition was immediately corrected within about 3.5 minutes but could have met the conditions for a NOUE had the event continued. Accordingly a NOUE was not declared, but this NRC ENS notification is being made in accordance with NUREG-1022 as an acceptable alternative to the immediate notification requirement of 50.72(a)(1)(i)."

The licensee informed the NRC Resident Inspector.

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Other Nuclear Material Event Number: 42691
Rep Org: SOUTHEAST MISSOURI STATE UNIVERSITY
Licensee: SOUTHEAST MISSOURI STATE UNIVERSITY
Region: 3
City: CAPE GIRARDEAU State: MO
County: CAPE GIRARDEAU
License #: 24-09296-02
Agreement: N
Docket:
NRC Notified By: WALT LILLY
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/07/2006
Notification Time: 16:31 [ET]
Event Date: 07/07/2006
Event Time: 10:00 [CDT]
Last Update Date: 07/07/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(1) - UNPLANNED CONTAMINATION
Person (Organization):
KENNETH RIEMER (R3)
E. WILLIAM BRACH (NMSS)

Event Text

DISCOVERY OF ADDITIONAL CONTAMINATION ASSOCIATED WITH AM-241 SPILL

At 1000 CDT on 7/7/06, additional Am-241 contamination was discovered in Magill Hall Room 215. An area of approximately 10-12 sq. ft. was identified having gross contamination levels of approximately 10 nanocuries with 0.05 nanocuries removable (alpha emitters) underneath cabinets being moved . The room has been posted as a contaminated area with access controls in place. A Radiation Work Permit will address decontamination on Monday morning, 7/10. A cabinet was taken from Room 215 by two (2) movers and loaded onto a truck. A radiation survey found contamination on the truck lift gate and the truck bed which have been decontaminated. The truck will be rechecked for contamination before being released.

The source of the contamination is an Am-241 spill referenced in previous Event Notifications #'s 37282 and 37298.

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Power Reactor Event Number: 42692
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/07/2006
Notification Time: 19:56 [ET]
Event Date: 07/07/2006
Event Time: 17:00 [CDT]
Last Update Date: 07/07/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
GREG PICK (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

AUXILIARY FEEDWATER PUMP RECIRCULATION VALVE INOPERABLE

"At 1700 CDT, Fort Calhoun Station determined that one of the two safety related auxiliary feedwater pumps may not provide sufficient flow to the steam generators during certain design basis events. The circuitry for the minimum flow recirculation valve for the electric motor driven auxiliary feedwater pump contains some components which were not designed as critical quality components. Since these components are not critical quality components, they are assumed to fail in a manner such that the minimum flow recirculation valve would fail open during a design basis event. If this valve should fail open, flow to the steam generators from the electric motor driven auxiliary feedwater pump may not provide adequate flow to cool the steam generators. The station has entered the appropriate technical specification action statement which requires the plant to be in Mode 2 (hot standby) within 30 hours of declaring the pump inoperable. The electric motor driven auxiliary feedwater pump was declared inoperable at 1700 CDT today."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42693
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: BILL GOTT
Notification Date: 07/08/2006
Notification Time: 09:22 [ET]
Event Date: 07/08/2006
Event Time: 09:18 [EDT]
Last Update Date: 07/08/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
KENNETH RIEMER (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 66 Power Operation 66 Power Operation

Event Text

OFFSITE NOTIFICATION - EXCEEDED LIMIT FOR SUSPENDED SOLIDS IN DISCHARGE

"On 6/29/06 at 1630 Neutralization Basin A was pumped to Lake Erie. On 7/7/06 the analysis of suspended solids for this discharge was completed with results outside of the daily limit. Results for the suspended solids for the basin discharge was 142 ppm with a limit of 100 ppm. State of Ohio EPA was notified for this non-compliance. This 4 hour notification is being made due to the notification to the State of Ohio EPA. Notification to the Ohio EPA was made at 0918 on 7/08/06. Specific. Reporting details required by Part 12.A are as follows:

"Discharge occurred- 6/29/06 at 16:30; Discovered 7/7/06 at 14:38 (analysis reported by First Energy Beta Drive Lab)
Approximate amount 18,300 gallons; 7.94 pH; 142 ppm Total Suspended Solids [backup sample 148 ppm]"

The licensee notified the NRC Resident Inspector.

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Friday, March 30, 2012