| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/11/2009 - 06/12/2009 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 45103 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/29/2009
Notification Time: 03:37 [ET]
Event Date: 05/28/2009
Event Time: 22:06 [CDT]
Last Update Date: 06/11/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MICHAEL SHANNON (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 CONTROL ROOM EMERGENCY FILTRATION SYSTEM EXCESSIVE LEAKAGE
"On 28 May 2009 the Control Room Emergency Filtration System (CREFS) was declared inoperable due to a degraded Control Room Envelope (CRE). Two CRE boundary doors were found with excessive leakage. Based on the identified leakage, reasonable assurance that CREFS would fulfill its safety function could not be established.
"The CRE boundary doors support CREFS at CNS. CREFS is a single train system and per 10CFR50.72(b)(3)(v)(D) an 8 hour report is required due to the fact that at the time of discovery this condition could have prevented the fulfillment of the safety function of an SSC [system, structure or component] that is required to mitigate the consequences of an accident.
"Actions to implement mitigating actions have been initiated in accordance with plant Technical Specifications.
"The NRC Senior Resident Inspector has been notified of the condition."
* * * UPDATE FROM KIRKPATRICK TO PARK AT 16:50 EDT ON 06/11/09 * * *
The licensee is retracting this report based on the following:
"This notification is being made to retract Event Notification EN# 45103 which reported a loss of safety function due to the unplanned inoperability of the Control Room Emergency Filtration (CREF) system. The CREF system was declared inoperable on May 28, 2009, due to a degraded Control Room Envelope (CRE). Two CRE boundary doors were found with excessive leakage and reasonable assurance that the CREF system would fulfill its safety function could not be established at that time. Cooper Nuclear Station (CNS) has subsequently determined through further testing that while the CREF system was procedurally required to be declared inoperable, the ability of the CREF system to perform its safety function was not lost. CREF system safety function is to maintain the habitability of the CRE following a loss of coolant accident or fuel handling accident involving handling lately irradiated fuel.
"CNS performed testing on June 5, 2009. CRE adjacent building pressures were raised to create harsh conditions and one CRE door was cracked open to simulate a boundary leaking at about four times the CRE leakage of May 28, 2009. Testing results showed the CRE remained considerably more positive, in comparison to previous tracer gas testing performed in July 2004, and it is not credible the CRE unfiltered in-leakage exceeded maximum allowable limits. Thus, CNS determined the CREF system was still capable of performing its safety function during the timeframe when the two CRE boundary doors were identified leaking excessively.
"The NRC Resident Inspector was notified of this retraction."
Notified R4DO (Geoffrey Miller) |
| General Information or Other | Event Number: 45117 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: IROQUOIS PAVING CORP.
Region: 3
City: WATSEKA State: IL
County:
License #: IL-01909-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/08/2009
Notification Time: 12:17 [ET]
Event Date: 06/05/2009
Event Time: 15:30 [CDT]
Last Update Date: 06/08/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PATTY PELKE (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text ILLINOIS AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
"On Friday June 5, the licensee's Radiation Safety Officer, called the Agency [Illinois Emergency Management Agency] to report a traffic accident involving their portable moisture density gauge that afternoon around 15:30. Apparently, a drunk driver entered the north bound construction zone on IL Rt. 49 at a speed in excess of 70 miles per hour and struck the gauge. The gauge was drug [approximately] 350 to 500 feet from the site of the impact. The car backed up to dislodge the gauge from under the vehicle and sped off. The license plate and identity of the vehicle was noted by a member of the road crew. The driver later crashed his vehicle and was apprehended by local law enforcement.
"The gauge source rod was in a shallow test position at the time of impact which separated the handle with indexing rod and source rod from the base of the gauge. The licensee attempted to recover all the pieces but some fragments of the source rod appeared to be missing. Radiation measurements taken at the scene by the RSO using a hand held instrument suggested both the Cs-137 and Am-241 sources were present. Digital pictures forwarded from the site to the Agency seemed to corroborate that finding however, after the gauge was returned to the storage location approximately one hour later, readings from the source rod definitely showed the source was no longer attached to the bottom of the rod.
"The Agency immediately dispatched an individual to investigate the matter.
"[The investigator, using] direct measurements and observation confirmed that although the Am-241:Be source was intact and in the shielded base of the destroyed gauge, the Cs-137 was no longer present with the other remaining pieces of the gauge and that the source rod tip had been cleanly severed from the source rod. Arrangements were made with the RSO and QA/QC Manager for the licensee to acquire additional safety equipment and begin a search of the section of pavement where the accident occurred. The nighttime scanning of the 1 mile section of roadway from the point of impact with a rate meter and scintillation probe produced elevated readings along the roadside off of the shoulder of the new asphalt. The readings were used to pinpoint the area where the source was located. Additional lighting eventually lead to the discovery of the source capsule within a grassy area of the shoulder some 5 feet from the road bed. The source was subsequently collected by the Agency investigator and placed into a shielded transport container. Gross monitoring of wipe tests collected at the scene showed no signs of contamination from the source or any equipment used to handle the source. The source was subsequently secured and isolated at the licensee's storage facility pending transfer to the manufacturer. Interviews with staff and assessment of radiation readings from the source indicated that no individual received a notable exposure from the actual event nor did any one handle a piece of the gauge that would result in an extremity exposure. Pocket dosimeter readings from those involved in the recovery showed no measured exposures.
"This item remains open pending transfer of the source and submission of the required report from the licensee."
The gauge contained a 8 mCi Cs-137 source and a 40 mCi Am/Be-241 source.
Illinois Event No. IL0900046 |
| Power Reactor | Event Number: 45124 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM TAYLOR
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/11/2009
Notification Time: 18:24 [ET]
Event Date: 06/11/2009
Event Time: 15:55 [CDT]
Last Update Date: 06/11/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
GERALD MCCOY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 12 | Power Operation | 0 | Hot Shutdown | Event Text UNIT 2 INITIATED A TECH SPEC REQUIRED SHUTDOWN DUE TO A RISE IN UNIDENTIFIED DRYWELL LEAKAGE
"At noon on 06/11/2009 Browns Ferry Unit 2 experienced a rise in drywell leakage during reactor startup. The 4 hour unidentified leak rate from 0800 to 1200 on 6/10/2009 was 0 GPM, while the 4 hour unidentified leak rate from 0800 to 1200 on 6/11/2009 was 3.88 GPM. This increase in leak rate exceeded the allowable limit of a 2 GPM increase in unidentified leakage in a 24 hour period per Technical Specification 3.4.4. At 1555 [CDT] on 06/11/2009, Unit 2 inserted a manual reactor SCRAM to comply with Technical Specification 3.4.4 Condition C to be in Mode 3 in 12 hours and Mode 4 within 36 hours.
"All systems responded as required except that when reset of the SCRAM was attempted after all control rods had inserted, a portion of the 'B' RPS channel (B2/B3) failed to reset. The 'A' RPS channel was then actuated by a spike on the Intermediate Range Monitors while they were being driven into the core resulting in a full RPS SCRAM actuation.
"The licensee notified the NRC Resident Inspector."
Unit 2 is currently removing decay heat using normal feedwater with bypass steam to the main condenser. The electrical system is in a normal shutdown configuration. The licensee has not identified the source of the unidentified leakage and anticipates taking Unit 2 to Cold Shutdown (Mode 4). | |