| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/19/2007 - 06/20/2007 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43324 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DAVE KARST
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/29/2007
Notification Time: 17:48 [ET]
Event Date: 04/29/2007
Event Time: 15:26 [CDT]
Last Update Date: 06/19/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
DAVE PASSEHL (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 89 | Power Operation | Event Text TECHNICAL SPECIFICATION SHUTDOWN DUE TO BOTH EMERGENCY DIESELS DECLARED INOPERABLE
"At 1453, [the licensee] declared D/G [Emergency Diesel Generator] - A inoperable due to outside air temperature exceeding 78.2 degrees Fahrenheit and entered Technical Specification 3.7.b.2 [which has a] 7-day LCO. At 1526, outside air temperature increased to greater than 81.4 degrees Fahrenheit and D/G - B was declared inoperable. With both D/Gs declared inoperable, Technical Specification 3.0.c , Standard Shutdown Sequence was entered. No other safety related components are inoperable at this time. Plant shutdown was initiated at 1624 on 4/29/07."
Based on recent findings by the licensee, the EDGs may not be capable of generating the minimum electrical power output needed to support a safety bus when outside air temperature exceeds certain limits (Operability Determination 151 dated April 26, 2007) The licensee is in the process of making ventilation modifications that will correct this condition. The licensee expects that the temperatures will drop below the EDG inoperability limits before the plant actually shuts down.
The licensee notified the NRC Resident Inspector.
* * * RETRACTION ON 06/19/07 AT 1515 ET FROM JACK BADZALA TO MACKINNON * * *
"EN 43324 provided notification of initiation of a unit shutdown due to both emergency diesel generators (EDGs) being declared inoperable due to outside air temperature exceeding allowable limits. Unit shutdown had been initiated per Technical Specification (TS) 3.0.c, Standard Shutdown Sequence, due to TS 3.7 not being met.
"A subsequent engineering evaluation allowed for increasing the allowable limit for outside ambient air temperature at which the EDGs are operable. The highest outside ambient air temperature recorded on 04/29/2007 (83.5 F) did not exceed the new allowable limit. Therefore, based on the new evaluation, both EDGs remained operable. TS 3.7 remained met and no TS shutdown was required. Consequently, this condition did not meet any reportability criteria in 10 CFR 50.72.
"As a result, the notification made on 4/29/07 (EN 43324) is hereby retracted." NRC R3DO (Patrick Louden) notified.
The NRC Resident Inspector was notified of this retraction by the licensee. |
| General Information or Other | Event Number: 43422 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: IOWA HEALTH - DES MOINES
Region: 3
City: DES MOINES State: IA
County:
License #: 0077-1-77-M1
Agreement: Y
Docket:
NRC Notified By: RANDY DAHLIN
HQ OPS Officer: JOE O'HARA | Notification Date: 06/14/2007
Notification Time: 14:54 [ET]
Event Date: 06/14/2007
Event Time: 10:30 [CDT]
Last Update Date: 06/14/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MONTE PHILLIPS (R3)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT - POTENTIAL PERSONNEL OVEREXPOSURE
The licensee's RSO received a phone call from Landauer at 1030 this morning to report a badge which had a deep dose reading of 6437 milliRem, an eye dose reading of 6437 milliRem, and a shallow dose reading of 6400 milliRem. The badge was assigned to the Chief of Surgery for the licensee for the month of January 2006. The RSO is investigating the cause for the fifteen month delay (January 2006 till June 2007) in processing the badge. Landauer told the RSO that this was a "dynamic" exposure to the badge meaning that the badge was moving during the time period of exposure.
Iowa Item Number IA-070001. |
| Power Reactor | Event Number: 43430 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RON FRANTZ
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/19/2007
Notification Time: 11:09 [ET]
Event Date: 06/19/2007
Event Time: 06:35 [CDT]
Last Update Date: 06/19/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 1 | Startup | 1 | Startup | Event Text TECH SPEC REQUIRED SHUTDOWN DUE TO INSTRUMENT LINE STEAM LEAK
"During performance of a plant shut down personnel entered the Drywell to investigate a steam leak. At 0635 hours, personnel identified steam leaking from a flexible hose instrument line (approximately 1" diameter) that is welded to an elbow tap on the C Main Steam line and concluded that the leak constitutes pressure boundary leakage. This required entry into TS 3.4.5, Condition C. This requires that the unit be in Mode 3 in 12 hours and Mode 4 in 36 hours, which is a TS required shutdown.
"The station has determined that this event is reportable under the provisions of: 10 CFR 50.72 (b)(2)(i) for the plant shutdown required by Technical Specifications, as a 4-hour notification; 10 CFR 50.72 (b)(3)(ii)(A) as an event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded, as an 8-hour notification.
"The NRC resident inspector has been notified."
The leaking line goes to a steam line flow instrument. The leak indication was first noticed yesterday and the licensee decided to shutdown to investigate before the leak was verified by the drywell entry. | |