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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/18/2009 - 05/19/2009
** EVENT NUMBERS **
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| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! |
| Power Reactor |
Event Number: 44929 |
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: ANDREW SMOLINSKI
HQ OPS Officer: VINCE KLCO |
Notification Date: 03/23/2009
Notification Time: 10:56 [ET]
Event Date: 03/23/2009
Event Time: 07:31 [CDT]
Last Update Date: 05/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL |
Person (Organization):
HIRONORI PETERSON (R3) |
| 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
NON-FUNCTIONAL STEAM EXCLUSION BARRIER
"On 3/23/09 at 0731 an I&C Supervisor transiting though a steam exclusion double door found the door sweep misaligned causing one side to catch and stick open. This prevented the door from closing automatically until the sweep was readjusted back to its original position. The door was then closed and monitored while permanent repairs took place. While the door was open and could not close automatically, the barrier was Non-Functional for Steam Exclusion. In accordance with TRM 3.0.9 Section A.1 all equipment supported by that steam exclusion barrier was immediately declared inoperable. This zone includes both trains of ECCS and support equipment (i.e., SI, RFIR, ICS, CCW, etc ). TS 3.0.c was entered and exited during the time the door could have stuck open (6 minutes) with both trains of ECCS inoperable. Permanent repairs were completed on the door at 0809 on 3/23/09.
"Therefore, this is reportable under 10 CFR 50.72 (b)(3)(v), 'Any event or condition that at the time of discovery could have prevented the fulfillment of a safety function, and under 10 CFR 50.72(b)(3)(ii)(B) 'any event or condition that results in the nuclear plant being in an unanalyzed condition that significantly degrades plant safety.'
The licensee is also reporting this event under 10 CFR 50.72 (b)(3)(v)(D), Accident Mitigation.
"The licensee notified the NRC Resident Inspector."
* * * UPDATE FROM STEVE TAYLOR TO JOE O'HARA AT 1443 ON 05/18/09 * * *
"05/18/2009 - Retraction of EN # 44929. NonÀFunctional Steam Exclusion Barrier.
"EN # 44929 provided notification that both trains of ESF equipment (e.g. SI, RHR, CCW, etc ) were inoperable due to degradation of a steam exclusion boundary door in the auxiliary building on March 23, 2009.
"Subsequent engineering evaluation determined that the degraded door remained capable of fulfilling its steam exclusion function during the brief (eight minute) period when it was degraded. The door had become degraded while being used for routine transit when the lower door sweep became misaligned, thereby preventing the door from completely closing. However, an engineering evaluation determined that the resulting gap was sufficiently small such that the total allowed leak path criteria were not exceeded. Additionally, the door swing was in the direction of postulated steam flow, such that the door would have been held in the closed direction by any steam overpressure postulated under accident conditions.
"Therefore, the door remained functional and the supported ESF equipment in the auxiliary building remained operable. Consequently, this condition did not meet the reportability criteria in 10 CFR 50.72.
"As a result, the notification made on 03/23/2009 is hereby retracted."
The licensee notified the NRC Resident Inspector.
Notified the R3DO(R. Skokowski). |
| Power Reactor |
Event Number: 45028 |
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: CURT STEFFES
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 04/28/2009
Notification Time: 19:34 [ET]
Event Date: 04/28/2009
Event Time: 18:34 [CDT]
Last Update Date: 05/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
DAVID HILLS (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Refueling |
0 |
Refueling |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
PROCESS COMPUTER REPLACEMENT IMPACTING ERDS AND SPDS
"During the current Unit 1 refueling outage, the plant process computer system will be taken out of service for approximately three weeks to support a planned modification which will install a new (upgraded) plant process computer system. During this timeframe, ERDS [Emergency Response Data System] and SPDS [Safety Parameter Display System] will be unavailable on Unit 1 which will remain in a shutdown condition. The computer outage will also render ERDS and SPDS unavailable on Unit 2 for approximately eight hours. Should the need arise, plant status information will be communicated to the NRC, [State, and local responders] using other available communication systems. The computer outage is expected to commence at 2200 CDT on 4/28/2009, and the process computer will be restored prior to Unit 1 startup currently scheduled for 05/21/2009.
"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a Major Loss of Assessment Capability."
The licensee will update this report when ERDS and SPDS is restored to Unit 2.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM C. STEFFES TO JOE O'HARA AT 0558 ON 4/29/09 * * *
"Follow-up notification - U2 ERDS and SPDS is restored as of 0315 CDT 4/29/09."
The licensee notified the NRC Resident Inspector.
Notified R3DO(Hills)
* * * UPDATE FROM BRIAN MAGNUSON TO JOE O'HARA AT 1509 EDT ON 5/18/09 * * *
"Follow-up notification - U1 ERDS and SPDS have been restored. Acceptance testing was completed on 5/15/09."
The licensee notified the NRC Resident Inspector.
Notified R3DO(Skokowski) |
| General Information or Other |
Event Number: 45061 |
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: THE UROLOGY CENTER, LLC
Region: 3
City: Cincinnati State: OH
County:
License #: 02200310002
Agreement: Y
Docket:
NRC Notified By: MARK LIGHT
HQ OPS Officer: DONALD NORWOOD |
Notification Date: 05/13/2009
Notification Time: 09:58 [ET]
Event Date: 05/13/2009
Event Time: [EDT]
Last Update Date: 05/14/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
ANGELA MCINTOSH (FSME) |
Event Text
AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING AN UNDERDOSAGE TO THE PROSTATE
"Ohio Department of Health (ODH) Bureau of Radiation Protection (BRP) was notified of a medical event that occurred at The Urology Center, LLC located at 4700 Smith Road, Suite M, Cincinnati, OH. 45212, Ohio license # 02200310002 at 12:30 PM 05/12/2009. The patient received a permanent implant of 64 I-125 seeds on 5-11-09. The total activity implanted was 28.422 mCi. (.444mCi/seed). The prescribed dose to the prostate was 144.0 Gy. The post-plan CT was evaluated 5-12-09 and determined that the prostate volume receiving the prescribed dose was 47% (i.e. V100%=47%) resulting in a 53 percent under dose of the prescribed dose. The patient and physician have been notified. ODH BRP will continue to evaluate this event. The licensee has initiated an internal evaluation."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| General Information or Other |
Event Number: 45062 |
Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: GEORGIA DEPT OF TRANSPORATION
Region: 1
City: ATLANTA State: GA
County:
License #: GA50-1
Agreement: Y
Docket:
NRC Notified By: ERIC JAMESON
HQ OPS Officer: JOHN KNOKE |
Notification Date: 05/13/2009
Notification Time: 16:45 [ET]
Event Date: 05/13/2009
Event Time: 16:00 [EDT]
Last Update Date: 05/13/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
DANIEL HOLODY (R1DO)
GREG SUBER (FSME) |
Event Text
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The licensee reported to the State that a vehicle transporting a Troxler gauge (Model 3430, s/n 38185) was involved in a traffic accident in Perry, GA along Highway 341, Mile Marker 3. The licensee's RSO is enroute to the site. The licensee indicated there was no harm to personnel. The gauge contained both a 40 mCi Am-241/Be source and a 8 mCi Cs-137 source. |
| Power Reactor |
Event Number: 45076 |
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: MITCHELL SAARE
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 05/18/2009
Notification Time: 05:06 [ET]
Event Date: 05/18/2009
Event Time: 04:50 [EDT]
Last Update Date: 05/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
DANIEL HOLODY (R1DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
| 3 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
TSC HVAC RENDERED NON-FUNCTIONAL DUE TO PLANNED MAINTENANCE
"At 0450 on Monday, May 18, 2009, power was removed to the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) ventilation system for planned preventative maintenance activities on the Unit 1 480VAC Load Center 10B014. During the 10B014 bus outage work activities, temporary power will be supplied to maintain all TSC facility equipment functional with the exception of TSC Normal and Emergency Ventilation. The TSC Supply, Exhaust and HEPA Filter fans will be de-energized, rendering the TSC HVAC non-functional while planned maintenance activities are in progress. This maintenance is scheduled to be worked continuously until completion to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed within 48 hours, including a total of 5 hours to establish and remove the clearances. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing EP procedures and checklists. It will take no more than 4 hours to return the Ventilation system back to an operable status, dependent on the stage of the work at the time the emergency occurs. If radiological conditions require TSC facility evacuation during ventilation system restoration, the Station Emergency Director will evacuate and relocate the TSC staff in accordance with, EP-AA-112-200-F-01.
"The NRC Resident Inspector has been notified." |
| Power Reactor |
Event Number: 45077 |
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DOUG SMITH
HQ OPS Officer: VINCE KLCO |
Notification Date: 05/18/2009
Notification Time: 14:41 [ET]
Event Date: 05/18/2009
Event Time: 13:05 [CDT]
Last Update Date: 05/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
RICHARD SKOKOWSKI (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Standby |
Event Text
TURBINE TRIP/REACTOR TRIP DUE TO CONDENSER VACUUM
"Prairie Island Unit 1 experienced an automatic turbine and reactor trip following a lockout trip of [the] 12 Circulating Water Pump. Lockout of the circulating water pump resulted in a condenser A/B differential pressure trip of the main turbine which in turn caused an automatic reactor trip. Auxiliary Feedwater Pumps automatically started on low steam generator level. All control rods fully inserted. Decay heat removal is via auxiliary feedwater and condenser steam dump. Offsite power was maintained to safeguards and non-safeguards AC buses. Operations are in progress per Reactor Trip Response emergency procedures to stabilize plant conditions, restore main feedwater flow to the steam generators, and then shut down auxiliary feedwater pumps. The plant will then be maintained per normal shutdown procedures until the cause of the trip is corrected."
No safety or relief valves lifted during the transient. There was no impact on Unit 2.
The licensee notified the NRC Resident Inspector. |
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