Event Notification Report for June 11, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/10/2009 - 06/11/2009
General Information or Other
Event Number: 45123
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: DOW CHEMICAL
Region: 4
City: HOUSTON State: TX
County:
License #: L00451
Agreement: Y
Docket:
NRC Notified By: DANNY JISHA
HQ OPS Officer: DONALD NORWOOD
Licensee: DOW CHEMICAL
Region: 4
City: HOUSTON State: TX
County:
License #: L00451
Agreement: Y
Docket:
NRC Notified By: DANNY JISHA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/11/2009
Notification Time: 14:45 [ET]
Event Date: 06/11/2009
Event Time: 00:00 [CDT]
Last Update Date: 06/11/2009
Notification Time: 14:45 [ET]
Event Date: 06/11/2009
Event Time: 00:00 [CDT]
Last Update Date: 06/11/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GEOFFREY MILLER (R4DO)
ANDREA KOCK (FSME)
GEOFFREY MILLER (R4DO)
ANDREA KOCK (FSME)
AGREEMENT STATE REPORT - STUCK SHUTTER
The following was received via E-mail:
"As we [the Texas Department of Health] understand it, a gauge, Ronan Eng. Co., Model SA-1 with 3Ci of Cs-137, has a broken handle and the shutter will not close. The serial number (S/N) is M7844 and I see that the source model could be 3M or QSA (AEA) so that will [be] determined later. It said that the external exposure rate is a nominal 1.5mR/hr and the gauge is 40' high on a vessel which is in process so no vessel entry is anticipated. They hope to keep operating until their next scheduled outage on July 15."
The following was received via E-mail:
"As we [the Texas Department of Health] understand it, a gauge, Ronan Eng. Co., Model SA-1 with 3Ci of Cs-137, has a broken handle and the shutter will not close. The serial number (S/N) is M7844 and I see that the source model could be 3M or QSA (AEA) so that will [be] determined later. It said that the external exposure rate is a nominal 1.5mR/hr and the gauge is 40' high on a vessel which is in process so no vessel entry is anticipated. They hope to keep operating until their next scheduled outage on July 15."
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
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: 06/15/2009
Notification Time: 18:24 [ET]
Event Date: 06/11/2009
Event Time: 15:55 [CDT]
Last Update Date: 06/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GERALD MCCOY (R2DO)
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 |
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).
* * * UPDATE AT 1730 EDT ON 6/15/09 FROM HUNTER TO SANDIN * * *
"Plant personnel entered the drywell after the reactor was shutdown. The resulting investigation revealed two sources of increased drywell leakage. One source of leakage was from 2-CKV-10-511 and 2-CKV-10-526, SRV Tailpipe Vacuum Breakers, which were apparently damaged by leakage past the pilot valve for 2-PCV-001-0023, Main Steam Safety Relief Valve. The combination of damaged vacuum breakers and a leaking pilot valve resulted in steam leakage into the drywell atmosphere. The other source of leakage was noted through the packing for 2-DRV-10-505, RPV Drain to RWCU. The vacuum breakers, pilot valve, and drain valve have been repaired.
"The 'B' RPS contactors were repaired and the scram reset.
"The NRC Resident Inspector has been notified."
R2DO (McCoy) notified.
"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).
* * * UPDATE AT 1730 EDT ON 6/15/09 FROM HUNTER TO SANDIN * * *
"Plant personnel entered the drywell after the reactor was shutdown. The resulting investigation revealed two sources of increased drywell leakage. One source of leakage was from 2-CKV-10-511 and 2-CKV-10-526, SRV Tailpipe Vacuum Breakers, which were apparently damaged by leakage past the pilot valve for 2-PCV-001-0023, Main Steam Safety Relief Valve. The combination of damaged vacuum breakers and a leaking pilot valve resulted in steam leakage into the drywell atmosphere. The other source of leakage was noted through the packing for 2-DRV-10-505, RPV Drain to RWCU. The vacuum breakers, pilot valve, and drain valve have been repaired.
"The 'B' RPS contactors were repaired and the scram reset.
"The NRC Resident Inspector has been notified."
R2DO (McCoy) notified.