United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for June 27, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/24/2011 - 06/27/2011

** EVENT NUMBERS **


46975 46982 46985 46986 46987 46988 46989 46990 46991 46992

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Agreement State Event Number: 46975
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ST. MARY'S HOSPITAL - RHINELANDER
Region: 3
City: RHINELANDER State: WI
County:
License #: 085-1296-01
Agreement: Y
Docket:
NRC Notified By: CHERYL K. ROGERS
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/21/2011
Notification Time: 12:37 [ET]
Event Date: 06/15/2011
Event Time: [CDT]
Last Update Date: 06/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KENNETH RIEMER (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - TWO I-125 INCIDENTS INVOLVING TOTAL DOSE LESS THAN PRESCRIBED DOSE

The State of Wisconsin sent the following report via email:

"On June 15, 2011, the licensee's Radiation Safety Officer reported the identification of two medical events that were discovered, involving permanent implants of I-125 for prostate brachytherapy where the total dose delivered differs from the prescribed dose by 20% or more. During a routine inspection conducted on March 8, 2011, DHS (Department of Health Services) inspectors determined that the licensee was not reviewing prostate brachytherapy cases against the medical event criteria and identified numerous potential medical events. A Confirmatory Action Letter was sent on April 6, 2011 which required the licensee to have all of their manual brachytherapy prostate implants reviewed by an outside radiation oncologist. Upon completion of the external review of the licensee's manual brachytherapy program for prostate implants, the licensee identified the following underdoses to the prostate (using D90<80% and D90>120% as medical event criteria):

"December 12, 2005: Prescribed dose 108 Gy. Prostate D90 was 67.16%.
"July 26, 2007: Prescribed dose 144 Gy. Prostate D90 was 74.09%.

"The licensee RSO stated that they will not be notifying the patients involved. DHS will send a special inspection team following the receipt of the licensee's 15 day written report."

Wisconsin Event Report ID No.: WI10007

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.

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Research Reactor Event Number: 46982
Facility: KANSAS STATE UNIVERSITY
RX Type: 250 KW TRIGA MARK II
Comments:
Region: 4
City: MANHATTAN State: KS
County: RILEY
License #: R-88
Agreement: Y
Docket: 05000188
NRC Notified By: JEFFREY GUTHER
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/24/2011
Notification Time: 14:55 [ET]
Event Date: 06/24/2011
Event Time: 13:53 [CDT]
Last Update Date: 06/24/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RICK DEESE (R4DO)
JEFFERY GRANT (IRD)
JACKE GROBE (NRR)
MARK KING (NRR)
WILLIAM KENNEDY (PM)
JESSE QUICHOCHE (DPR)
MICHELE EVANS (NRR)
MARK HILL (DHS)
MIKE BLANKENSHIP (FEMA)

Event Text

UNUSUAL EVENT DECLARED DUE TO INDICATIONS OF FUEL DAMAGE

The reactor operated at 10 W to 25 kW steady-state power for a total of 25 minutes. At 1257 CDT the Reactor Manager noticed that the radiation monitor (AMS-4) was reading approximately 80 times the Derived Air Concentration (DAC) for Iodine. A second continuous air monitor and a portable thin-window ionization chamber both read background levels of radiation. A high-volume air sampler was used to sample the air near the sampling location of the AMS, which draws air from the reactor deck. The filter from the air sampler read 3700 DPM after drawing 50 cubic feet of air, indicating elevated levels of activity. An HPGe (High Purity Germanium Detector) spectrograph indicated some Cs-137 in the air filter sample, but no I-131. Primary water activity and conductivity were both at normal levels. The indicated DAC of Iodine increased to a value of 149 times DAC before decreasing to 145 times DAC.

The Reactor Manager and Radiation Safety Officer agreed that fuel damage was unlikely, but the results of testing were inconclusive, and that it would be prudent to declare an Unusual Event.

* * * UPDATE FROM JEFFREY GUTHER TO CHARLES TEAL AT 1528 EDT ON 6/24/11 * * *

HPGe spectroscopy indicated only background levels of Cs-137 for a air sample, a primary water sample, and a swipe taken from the reactor deck. None of these samples showed I-131. A second portable air sample taken at the reactor deck, but on the opposite side of the deck from the radioactive sampling handling table, did not have elevated counts.

The Reactor Manager and Radiation Safety Officer agreed that the AMS-4 was most likely mis-calibrated, and the elevated levels in the first high-volume air sample were probably due to the proximity of the radioactive sample handling table to the sampling location.

Notified NRR (Grobe), NRR EO (Evans), R4DO (Deese), IRD (Grant), DHS (Hill), FEMA (Blankenship)

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Power Reactor Event Number: 46985
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GRETCHEN CARTER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/25/2011
Notification Time: 08:15 [ET]
Event Date: 06/25/2011
Event Time: 07:55 [EDT]
Last Update Date: 06/25/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
MICHELE EVANS (NRR)
JEFFERY GRANT (IRD)
BRUCE BOGER (NRR)
BILL DEAN (R1RA)
BRADSHAW (DHS)
HOWELL (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 FIRE LASTING GREATER THAN 15 MINUTES

"Unit 1 experienced a confirmed fire in power board H12. The fire brigade has responded and the power board has been deenergized. Awaiting confirmation that the fire is out."

At the time of the notification (0815 EDT), the licensee determined that the fire was out. Power board H12 supplies 480V non-safety plant loads. There was no damage to any safety related equipment and no injuries to personnel. Offsite assistance was not requested.

During the notification, at 0825 EDT, the licensee terminated from the Unusual Event. Unit 2 was not affected by this event.

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

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Power Reactor Event Number: 46986
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RAY SWAFFORD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/25/2011
Notification Time: 22:51 [ET]
Event Date: 06/25/2011
Event Time: 16:15 [CDT]
Last Update Date: 06/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

METEOROLOGICAL MONITORING INSTRUMENTATION INOPERABLE DUE TO LOSS OF POWER

"At approximately 1615 [hrs. CDT] on 6/25/11, the Meteorological Monitoring Instrumentation at Browns Ferry Nuclear Plant was lost due to a loss of normal and backup power to the Meteorological Monitoring station.

"This is reportable as an 8 hour ENS report in accordance with 10CFR50.72(b)(3)(xiii) as 'Any event that results in a major loss of emergency assessment capability...'

"Meteorological monitoring was restored to operation at 1841 on 6/25/11. BFN Units 1, 2, and 3 remained in Mode 1 at 100% power throughout the event.

"The NRC Resident has been notified."

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Power Reactor Event Number: 46987
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ROY GLACKIN
HQ OPS Officer: PETE SNYDER
Notification Date: 06/26/2011
Notification Time: 05:25 [ET]
Event Date: 06/26/2011
Event Time: 00:30 [EDT]
Last Update Date: 06/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

PIPING LEAK ISOLATED ON HIGH PRESSURE COOLANT INJECTION

"On 06/26/11, at 0030 [hrs. EDT], Peach Bottom Atomic Power Station Unit 3 declared the High Pressure Coolant Injection [HPCI] system inoperable for an ASME class 2 exempt piping leak found during operator rounds. Piping on the steam line pressure indication sensing line downstream of a sensing line root valve had an approximate 5 drop per minute leak. The leak has been isolated and the Unit 3 HPCI system was restored to an operable condition as of 0347 on 06/26/11.

"This report is being submitted pursuant to 10CFR 50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46988
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/26/2011
Notification Time: 07:58 [ET]
Event Date: 06/26/2011
Event Time: [CDT]
Last Update Date: 06/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
R4IRC (WALKER) (R4)
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

BOTH EMERGENCY DIESEL GENERATORS SUPPLYING PLANT EMERGENCY BUSES PER PLANT PROCEDURE

"At approximately 0125 [hrs. CDT], the AquaDam providing enhanced flood protection for FCS [Ft. Calhoun Station] Unit 1 failed. At 0221, as a precautionary measure, DG-2 [Diesel Generator] was automatically started per plant procedure to divorce bus 1A4 from offsite power. At 0250, DG-1 was automatically started to divorce bus 1A3. Both Emergency Diesel Generators loaded on buses as designed. 345KV and 161KV offsite power remain available.

"This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), 'System Actuation of the Emergency Diesel Generators'. All safety related flood protection barriers remain in place.

"Current river level is 1006.5' MSL and stable. FCS remains in a NOUE [Notification of Unusual Event] due to high river level.

"NRC personnel stationed onsite for flood monitoring have been informed."

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Power Reactor Event Number: 46989
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/26/2011
Notification Time: 12:22 [ET]
Event Date: 06/26/2011
Event Time: 10:45 [CDT]
Last Update Date: 06/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

OFFSITE NOTIFICATION DUE TO PETROLEUM RELEASE TO THE MISSOURI RIVER

"At approximately 0125 CDT, the AquaDam providing enhanced flood protection for Fort Calhoun Station Unit 1 failed. This resulted in approximately 100 gallons of petroleum being released into the river after a protective barrier was breached and many fuel containers were washed out to the river. The fuel/oil containers were staged around the facility to supply fuel for pumps which remove water within the flood containment barriers. The spill was reported to the State of Nebraska at 10:45 AM CDT on 6/26/2011.

"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for News Release or Notification of Other Government Agency. Applicable governmental agencies have been notified per plant procedures."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46990
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARCY BLOW
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/26/2011
Notification Time: 18:00 [ET]
Event Date: 06/26/2011
Event Time: 16:09 [CDT]
Last Update Date: 06/26/2011
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):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 82 Power Operation 0 Hot Standby

Event Text

REACTOR MANUAL TRIP DUE TO MAIN FEED PUMP TRIP

"6/26/11 at 1609 CDT, the reactor was manually tripped due to the trip of the 'B' Main Feed Pump while operating in Mode 1 at approximately 82% reactor power. The unit was increasing power to 95% after the current refuel outage. The cause of the trip of the 'B' Main Feed Pump is not known at this time. All equipment functioned normally as expected. The investigation into the cause of the 'B' Main Feed Pump trip is ongoing at this time.

"Current plant status is Mode 3. The NRC Senior Resident has been contacted."

All rods fully inserted upon reactor trip. The unit is stable with Auxiliary Feedwater supplying the Steam Generators. Decay heat is being removed to the Main Condenser via steam dumps. The electrical system is in a normal post-trip alignment. The licensee characterized the reactor trip as uncomplicated.


* * * UPDATE FROM MARCY BLOW TO DONALD NORWOOD AT 1923 EDT ON 6/26/2011 * * *

"A valid Auxiliary Feed[water] actuation signal [occurred] due to trip of both of the Main Feed pumps from a turbine trip and low steam generator levels. This is reportable under 10CFR50.72 (b)(3)(iv)(A), 8-hour report. All auxiliary feed pumps started and operated as expected."

The licensee will notify the NRC Resident Inspector.

Notified R4DO (Deese).

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Power Reactor Event Number: 46991
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF EPPERSON
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/26/2011
Notification Time: 19:39 [ET]
Event Date: 06/26/2011
Event Time: 16:14 [EDT]
Last Update Date: 06/26/2011
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):
GERALD MCCOY (R2DO)

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

AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP

"At 1614 EDT on 6/26/2011, Unit 1 reactor automatically tripped following a turbine trip from greater than 50% rated thermal power (P-9 interlock).

"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically actuated as expected on loss of the operating main feedwater pumps.

"Initially, the steam dump system functioned as expected (all valves opened). Subsequently, the steam dump system was manually turned off when 3 of the valves did not close when expected. Consequently, decay heat removal is via the Steam Generators' atmospheric relief valves.

"No primary or secondary safety valves opened during or after this trip.

"Unit 1 is currently being maintained in Mode 3 at NOT/NOP, approximately 548 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators."

There is no indications of any primary to secondary leakage. All control and shutdown rods are inserted. The electrical alignment is normal, supplied from off-site power. There was no impact to Unit 2. Unit 2 is operating at 100% power / Mode 1"

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46992
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/26/2011
Notification Time: 22:08 [ET]
Event Date: 06/26/2011
Event Time: [EDT]
Last Update Date: 06/26/2011
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):
CHRISTOPHER CAHILL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO LOSS OF REACTOR COOLANT PUMP

"This notification is being made to report that Salem Unit 2 has experienced an automatic reactor trip. The trip was caused by 23 Reactor Coolant (RC) loop low flow and P-8 caused by 23 reactor coolant pump trip. The cause of the 23 Reactor Coolant Pump trip is under post reactor trip investigation. Main Feedwater to the Steam Generators was isolated due to the 'Feed Water Interlock' which is expected on a reactor trip. The Auxiliary Feed Water (AFW) system auto started on low Steam Generator levels. This is also expected on a reactor trip. 21, 22 and 23 AFW pumps all automatically started and fed the Steam Generators. 23 AFW pump has been shutdown by procedure and is available.

"The crew entered EOP-TRIP-1, and then transitioned to EOP-TRIP-2 and stabilized the plant at no load conditions. Salem Unit 2 is currently in Mode 3. Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig NOP/NOT. 21, 22, and 24 Reactor Coolant Pumps are in service.

"Decay heat removal is being provided by 21 and 22 AFW pumps via the Main Steam Dump System. All shutdown and control rods fully inserted on the reactor trip. The plant is aligned with normal electrical lineup from offsite power sources.

"There were no personnel injuries associated with this event."

The NRC Resident Inspector has been informed.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012