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Event Notification Report for April 21, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/20/2010 - 04/21/2010

** EVENT NUMBERS **


45837 45846 45859 45860

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45837
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: RAY OLDFATHER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/13/2010
Notification Time: 13:17 [ET]
Event Date: 04/13/2010
Event Time: 12:00 [CDT]
Last Update Date: 04/20/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BLAIR SPITZBERG (R4DO)
JANE MARSHALL (IRD)
BRUCE BOGER (NRR)
ELMO COLLINS (R4RA)
KETTLES (DHS)
BISCO (FEMA)

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

UNUSUAL EVENT DECLARED DUE TO AN IDENTIFIED LEAKAGE EXCEEDING 25 GALLONS PER MINUTE

On April 13, 2010 at 1200 CDT, Callaway Unit 1 declared an Unusual Event due to identified leakage of greater than 25 gallons per minute (EAL SU6.1). During the flushing of the 'A' Chemical and Volume Control System mixed bed demineralizer, a leak occurred from the vent valve exceeding 25 gallons per minute for approximately 5 minutes. The leak was isolated and the Unusual Event was terminated at 1223 CDT. No personnel contamination or outside release occurred.

The licensee has notified the State and local authorities and the NRC Resident Inspector.

* * * UPDATE FROM WALTER GRUER TO DONG PARK AT 1614 EDT on 04/13/2010 * * *

"Callaway Plant declared an Unusual Event at 1200 CDT on 4/13/2010. The cause of the event was Emergency Action Level (EAL) SU6.1, identified leakage greater than 25 gallons per minute (gpm).

"When attempting to place the 'A' Chemical and Volume Control System (CVCS) mixed bed demineralizers in service, a drop in the Volume Control Tank (VCT) level was noted by the Reactor Operator (RO). Technical Specification (TS) 3.4.13 Condition A was entered at 1033 CDT upon identification of identified leakage of the Reactor Coolant System (RCS) greater than 10 gpm.

"TS 3.4.13 Condition A requires reduction of leakage to limits within 4 hours. The leakage was verified to be stopped at 1038 CDT, at which time TS 3.4.13.A was exited. The system was restored to a normal alignment.

"Upon review, it was determined that the VCT level dropped approximately 125 gallons in 5 minutes. EAL SU6.1 was declared at 1200 CDT and closed at 1223 CDT.

"The state and local counties (Callaway, Gasconade, Montgomery, and Osage) were notified of the event at 1210 CDT and of the event closeout at 1227 CDT.

"The NRC Resident Inspector was notified of the event. A news release will be made by Ameren Corporate Communications."

Notified R4DO (Spitzberg), NRR EO (Nelson), and IRD (Marshall).

* * * RETRACTION ON 4/20/10 AT 1417 EDT FROM DAVID HURT TO R. ALEXANDER * * *

"The declaration of Unusual Event SU6.1, RCS leakage, on 4/13/10 is being retracted, because the declaration was inaccurate. The leak was an isolable intersystem leak of the CVCS, not RCS leakage, and the leak was stopped within the 15 minute time period allowed to determine EAL applicability. Therefore, the leakage did not meet the Initiating Condition for the EAL.

"The NRC Resident Inspectors have been notified."

Notified R4DO (J. Whitten).

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General Information or Other Event Number: 45846
Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: GEORGIA INSTITUTE OF TECHNOLOGY
Region: 1
City: ATLANTA State: GA
County:
License #: GA-147-1
Agreement: Y
Docket:
NRC Notified By: IRENE BENNETT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/16/2010
Notification Time: 17:02 [ET]
Event Date: 04/13/2010
Event Time: [EDT]
Last Update Date: 04/16/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1DO)
JACK FOSTER (FSME)

Event Text

AGREEMENT STATE REPORT - UNCONTROLLED CONTAMINATION EVENT

On April 13, 2010, a student at the Georgia Institute of Technology (the licensee), under the supervision of an authorized user, was conducting an electroplating experiment, using Ni-63, under a fume hood in one of the licensee's RAM (Radioactive Material) rooms. During the experiment, the student noticed fumes outside the hood and ceased the experiment. She took a swipe outside the hood and found no contamination.

On April 14, the licensee's Radiation Safety Officer took swipes of the room and found 22,000 DPM of contamination on the fume hood lip, 11,000 DPM on the RAM room floor, 1,200 DPM on a public hallway floor outside the RAM room, and contamination in an adjacent RAM room. All areas have been cordoned off to control access and cleanup is in progress.

It is unknown whether the student had any uptake, was overexposed, or was contaminated during the event.

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Power Reactor Event Number: 45859
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/20/2010
Notification Time: 15:55 [ET]
Event Date: 04/20/2010
Event Time: 13:07 [CDT]
Last Update Date: 04/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JACK WHITTEN (R4DO)

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

FIVE POTENTIAL ISSUES DISCOVERED DURING POST-FIRE SAFE SHUTDOWN REVIEW

"While performing a post-fire safe shutdown (PFSSD) review per Enforcement Guidance Memorandum (EGM) 09-002, 'Enforcement Discretion for Fire Induced Circuit Faults', and Regulatory Guide (RG) 1.189, Revision 2, five issues were identified that could be potentially reportable. EGM 09-002 provides enforcement discretion for non-compliances related to fire-induced multiple spurious operations (MSOs). The enforcement discretion period allows 6 months from the date of issuance of RG 1.189, Rev. 2 to perform the following:

- Identify noncompliances related to multiple fire induced circuit failures
- Implement compensatory measures for the noncompliances, and
- Place the noncompliances in the licensees' corrective action program

"The five fire-induced issues that were identified are:

- Three issues which could potentially prevent operation of the Residual Heat Removal Pump(s),
- An issue where all four Reactor Coolant Pumps may not stop from the Control Room, and
- An issue where a Centrifugal Charging Pump could spuriously start and fill the pressurizer solid.

"RG 1.189 was issued on November 2, 2009. Therefore, the 6-month identification period ends on May 2, 2010. For issues identified during the 6-month identification period, enforcement discretion continues for an additional 30 months to resolve identified issues.

"The 10 CFR 50, Appendix R Fire is not a Design Basis Accident. While Appendix R fires are postulated to cause a Technical Specification (TS) inoperability of a [System, Structure or Component] SSC, the failure to previously identify these issues does not constitute an actual TS inoperability. Rather, the issues identified during this MSO are noncompliances with the Current Licensing Basis (CLB). Therefore, the affected systems are considered operable but degraded or non-conforming as defined in Regulatory Issue Summary (RIS) 2005-20."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45860
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CLAY WILLIAMS
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/20/2010
Notification Time: 18:39 [ET]
Event Date: 04/20/2010
Event Time: 11:03 [PDT]
Last Update Date: 04/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JACK WHITTEN (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 98 Power Operation 98 Power Operation
3 N Y 50 Power Operation 50 Power Operation

Event Text

OFFSITE NOTIFICATION - SODIUM HYDROXIDE RELEASED INTO BERM

"At about 0755 (PDT) on April 20, 2010, approximately 200 gallons of sodium hydroxide (caustic) was released into the SONGS Caustic Skid Berm. The release was fully contained within the bermed area and there was no release to the environment. The release is believed to have occurred from a Unit 2 caustic pump pressure safety valve (PSV) during the performance of condensate polishing demineralizer regeneration. The release has been secured and SONGS personnel have pumped the caustic to poly drums.

"Between 1103 and 1125 (PDT) SONGS notified the San Diego Department of Environmental Health (DEH), the State of California Emergency Management Agency (CalEMA), and the National Response Center of the contained non-radioactive caustic spill within the protected area of the facility. Therefore, Southern California Edison is reporting this occurrence to the Nuclear Regulatory Commission in accordance with 10 CFR 50.72(b)(2)(xi).

"SONGS Unit 2 is in Mode 1 at approximately 98% power and Unit 3 is in Mode 1 at approximately 50% power. The NRC Resident Inspector will be notified of this occurrence and will be provided a copy of this report.

"Additional information regarding this event will be provided to one of the Resident Inspectors at the site."

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Thursday, March 29, 2012