| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/22/2014 - 08/25/2014 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 50365 | Rep Org: UNION ELECTRIC DBA AMEREN MISSOURI
Licensee: UNION ELECTRIC DBA AMEREN MISSOURI
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-02020-08
Agreement: N
Docket:
NRC Notified By: BRIAN HOLDERNESS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/14/2014
Notification Time: 09:40 [ET]
Event Date: 08/13/2014
Event Time: 10:30 [CDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PROCESS DENSITY GAUGE DAMAGED BY FIRE AND/OR HEAT
"On the morning of August 13, 2014 while cleaning up from a fire event on coal handling conveyer belt #2 at the Ameren Missouri (Ameren) Rush Island Energy Center it was observed that the nucleonic gauge located outside of the area of the original fire had some indications of potential damage. The gauge is located approximately 12 feet above the walkway near the ceiling of the room in an area that was not easily accessible. The gauge is a Ronan Engineering Model SA1-C10 containing 100 mCi of CS-137 in sealed solid form. Ameren contacted R. M. Wester (NRC Licensed maintenance vendor) to evaluate the nucleonic gauge on August 13, 2014 to determine if the gauge had been damaged due to the fire.
"R. M. Wester examination of the source housing showed the exterior to be in good condition with some minor scorching. The shutter check performed showed smooth operation and good beam strength with the shutter open (greater than 200 mR/hr) and good shielding with the shutter closed (1.5 mR/hr). Wipes of the source and the area below the source indicated no contamination or leakage from the source.
"An area radiation survey did indicate that some of the lead inside of the source housing had potentially melted and shifted. The on contact readings of the back (0.2 mR/hr), sides/bottom (0.3 mR/hr), and shutter (1.5 mR/hr) were all consistent with expected readings. The 30 cm readings from the source back, sides, and bottom were also as expected (approximately 0.03 mR/hr). The readings on top of the source were higher than expected with a reading of 6 mR/hr on contact and 0.4 mR/hr at 30 cm. These readings on the top of the source do not present an immediate radiological hazard due to their low intensity and the fact that the source is mounted very close to the ceiling in the room. The ceiling support beam and water deflection shield make it difficult to even get a reading 30 cm from the top of the source.
"R. M. Wester's recommendation was that the gauge is functional and it could continue to be use until a replacement device could be procured and installed." |
| Agreement State | Event Number: 50366 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MISTRAS GROUP INC
Region: 4
City: DEER PARK State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/14/2014
Notification Time: 11:07 [ET]
Event Date: 08/13/2014
Event Time: [CDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE - RADIOGRAPHY CAMERA SOURCE WOULD NOT RETRACT
The following information was provided by the State of Texas via email:
"On August 14, 2014, the Agency [Texas Department of State Health Services] was notified by the licensee's Radiation Safety Officer (RSO) that on August 13, 2014, a radiography crew using a 50 foot crank out device could not retract a 54 curie iridium-192 source to the fully retracted and locked position in a QSA 880D exposure device (camera). The RSO stated the radiographer had completed an exposure at a temporary field site and was retracting the source when he felt the resistance to movement in the crank out handle disappear and he could no longer move the source. The radiographer noted the dose rates were still higher than those for a fully shielded source. The radiographer contacted the RSO and increased the control area. The radiographer placed two bags of lead on the guide tube where he believed the source was located. The RSO stated the radiographer was in the area of the source for just a few seconds. The radiographer checked his self reading dosimeter after placing the lead at the source and found it off scale.
"The RSO and a recovery team went to the location to retrieve the source. The RSO had additional lead placed on the guide tube and the dose rates at the crank out device dropped to less than 2 millirem per hour. The RSO disconnected the drive cable housing from the broken in two at crank out device. The RSO grabbed the drive cable inside the drive cable housing with a set of pliers and was able to pull the drive cable and return the source to the fully shielded position.
"The personnel dosimeter for the radiographer who had approached the guide tube was sent to the licensee's dosimetry processor for processing and the radiographer has been removed from all work involving exposure to radiation until the results for their badge has been received. The RSO stated that based on the exposure rates and the time the radiographer was in the area of the source he did not believe the radiographer received
a significant exposure from the event. The RSO received 8 millirem by pocket dosimeter from the event. No other individuals received any significant exposure in this event.
"The crank out and drive cable will been sent to the manufacturer for inspection. The RSO stated he examined the drive cable, but did not see anything that would indicate why the cable failed. The RSO stated they performed a flex test of the drive cable and it passed. The RSO stated the camera and guide tube were inspected and returned to service. Additional information will be provided in accordance with SA-300."
Texas Incident #: I-9219 |
| Agreement State | Event Number: 50367 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: THERMO SCIENTIFIC - PORTABLE SCIENTIFIC INSTRUMENTS
Region: 1
City: TEWKSBURY State: MA
County:
License #: 55-0238
Agreement: Y
Docket:
NRC Notified By: DOUG CULLEN
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/14/2014
Notification Time: 14:16 [ET]
Event Date: 08/11/2014
Event Time: [EDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
SILAS KENNEDY (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - LEAKING SEALED SOURCE
The following was received from the State of Massachusetts via email:
"Thermo Scientific received a total of 15 sealed sources, Model XFB-3, manufactured by Eckert & Ziegler Isotope Products, containing Cd-109, each with an activity of 40 mCi. As part of Thermo's inspection protocol, individual sealed sources were leak tested, and one source, serial number TR3042 tested greater than the leak test limit of 0.005 microcuries.
"Following the initial leak test, two additional leak test measurements were made and all three measurements were found to be in excess of the 0.005 microcurie limit, with measurements ranging from 0.0126 to 0.0184 microcuries.
"Eckert and Ziegler was notified immediately by Thermo Scientific, a return authorization was provided, and Thermo returned the sealed source via [common carrier] to Eckert and Ziegler on 08/11/14.
"The licensee reports that the area where the leaks tests were obtained was surveyed thoroughly and no contamination was found.
"The Agency [State of Massachusetts] considers this event open."
MA Docket #: 20-1427 |
| Agreement State | Event Number: 50368 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: COLORADO STATE UNIVERSITY
Region: 4
City: FORT COLLINS State: CO
County:
License #: CO 002-19
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: DANIEL MILLS | Notification Date: 08/14/2014
Notification Time: 17:16 [ET]
Event Date: 08/14/2014
Event Time: 14:45 [MDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - INOPERABILITY OF THE ACCESS CONTROL SYSTEM
The following was received from the State of Colorado via email:
"CDPHE [Colorado Department of Public Health] received telephone notification of an inoperability of the access control system on 8/14/2014 at approximately 1445 [MDT]. Colorado State University, a research licensee, reported that a radiation monitor provided to detect the presence of high radiation levels in the radiation room of a panoramic irradiator was alarming when there was no [abnormal] radiation level present. One of the irradiator users noticed the audible alarm when their work was complete and they were leaving the area. The RSO responded and suspected a stuck source. Using a hand held radiation detection instrument, the irradiator door was opened and the irradiator room was entered. As the RSO entered the room there was no indication of radiation levels above what was expected when the source is in its shielded position, and as a result, it was determined that the source was in its shielded position. The room radiation monitor was reset but shortly after again alarmed without any [abnormal] radiation field present. The irradiator has been taken out of service and the monitor has been removed for repair."
Colorado event report ID: CO14-I14-22 |
| Non-Agreement State | Event Number: 50369 | Rep Org: BOTSFORD HOSPITAL
Licensee: BOTSFORD HOSPITAL
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: TEAMOUR NURUSHEV
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/14/2014
Notification Time: 17:17 [ET]
Event Date: 07/10/2014
Event Time: 13:20 [EDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PATIENT RECEIVED LESS THAN PRESCRIBED DOSE
A patient undergoing High Dose Rate Brachytherapy using Ir-192 was prescribed 700 cGy per fraction and only received 700 cGy to 60% of the planned volume.
The patient was scheduled for two treatments. The first treatment was successfully administered to the patient on 6/26/14. When the patient returned for the second treatment on 7/10/14 the HDR afterloader was loaded with the treatment plan for the original treatment instead of the second treatment. This resulted in the patient not receiving the full prescribed treatment.
The licensee discovered the problem during an audit when the number of catheters did not match.
There are no adverse health effects expected as a result of this treatment.
The licensee has contacted the vender to determine a way to remove old treatment plans from the machine to ensure this does not happen in the future.
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. |
| Agreement State | Event Number: 50372 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: OHIO STATE UNIVERSITY MEDICAL CENTER
Region: 3
City: COLUMBUS State: OH
County: FRANKLIN
License #: 02110250037
Agreement: Y
Docket:
NRC Notified By: KARL VON AHN
HQ OPS Officer: DANIEL MILLS | Notification Date: 08/15/2014
Notification Time: 14:53 [ET]
Event Date: 08/14/2014
Event Time: [EDT]
Last Update Date: 08/15/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL UNDERDOSE TO LIVER
The following was received from the State of Ohio via email:
"The licensee prepared and delivered a therapeutic dose of TheraSpheres to a patient's liver on August 14, 2014. The written directive was for 120 Gy to the liver with 27 mCi of Y-90 TheraSpheres. On August 15, 2014, the licensee discovered that 20% of the dose that was supposed to be administered to the patient was still in the bottom of the vial. Although the licensee prepared the vial in accordance with the manufacturer's instructions, 20% of the TheraSpheres remained in the bottom of the vial and did not go into suspension.
"The patient and referring physician have been notified.
"The Bureau [Ohio Bureau of Radiation Protection] will be conducting a follow-up investigation regarding this event."
The patient received 96 Gy to the liver instead of the prescribed 120 Gy.
Ohio incident # OH140010
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. |
| Agreement State | Event Number: 50374 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: PHILLIPS 66 CO
Region: 4
City: PONCA CITY State: OK
County:
License #: OK-07402-12
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/15/2014
Notification Time: 17:04 [ET]
Event Date: 08/15/2014
Event Time: [CDT]
Last Update Date: 08/15/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON FIXED INDUSTRIAL GAUGE
The following was received from the State of Oklahoma via email:
"Phillips 66 Co. (OK-07402-12) has reported the failure of the shutter mechanism on one of their fixed gauges. Earlier today the shutter was closed while the licensee collected a leak test sample. The RSO noted that the shutter was difficult to operate. When they returned the shutter handle to the 'open' position, the control room which monitors the gauge readings reported that the readout briefly returned to its normal level, then dropped back to zero when the shutter was supposed to be fully open. Repeated attempts showed that the gauge only operated when the shutter was approximately 75% of the fully 'open' position. The licensee has contacted the gauge manufacturer but they won't be able to supply a replacement for approximately 6 weeks. The licensee has requested permission to leave the gauge in service until a replacement is available. The gauge is installed on a stand pipe 18 feet above ground level in an oil refinery in Ponca City, OK. It is only accessible by catwalk which the RSO is going to cordon off. Material in the gauge is Cs-137, 25 mCi when new in 1993. We[State of OK] have told the RSO they may leave the gauge in operation pending the results of the leak test. If these show the source to be leaking they must immediately remove the gauge from service." |
| Power Reactor | Event Number: 50386 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/21/2014
Notification Time: 04:03 [ET]
Event Date: 08/21/2014
Event Time: 02:10 [EDT]
Last Update Date: 08/22/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DAVE PASSEHL (R3DO)
|
| 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 | Event Text OFFSITE NOTIFICATION DUE TO SUSPECTED FUEL OIL LEAK TO THE ENVIRONMENT
"At 0210 EDT on August 21, 2014, D.C. Cook made notifications to the State of Michigan, local authorities and the National Response Center due to a suspected release of approximately 8,700 gallons of diesel fuel oil to the environment. The level in the buried fuel oil storage tank for the Train B Emergency Diesel Generator was found to be approximately 8,700 gallons less than measurements taken within the last 24 hours. The tank is located within the plant protected area. At this time the suspected fuel oil plume has not left the site.
"The NRC Resident Inspector was notified.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) and NUREG 1022 section 3.2.12, due to notification of offsite agencies."
* * * UPDATE FROM JAMES SHAW TO VINCE KLCO ON 8/22/14 AT 1342 EDT * * *
"An event investigation determined that no spill occurred. The discrepancy in level was due to maintenance activities that caused an error in level indication. No actual loss of inventory from the fuel oil storage tank occurred. Offsite agencies have been notified that this spill event is being retracted [to the State and Offsite agencies].
"The NRC Resident Inspector was notified."
Notified the R3DO (Passehl). |
| Power Reactor | Event Number: 50389 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/21/2014
Notification Time: 12:00 [ET]
Event Date: 08/21/2014
Event Time: 08:50 [EDT]
Last Update Date: 08/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY MCKINLEY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 50 | Power Operation | 50 | Power Operation | Event Text INADVERTENT ACTUATION OF ONE EMERGENCY SIREN
"The purpose of this report is to provide a telephone notification under 10 CFR 50.72(b)(2)(xi) to notify the NRC of the inadvertent actuation of one Oswego County emergency notification siren at approximately 0850 [EDT] on 08/21/14. Thunderstorms in the area are believed to have caused a lightning strike and the spurious activation. Siren repair personnel have been dispatched to isolate the siren and begin repair work. The siren has since been silenced. Alternate notification of the public in the area is through Hyperreach.
"The Oswego County Emergency Management Office issued a news release identifying the inadvertent actuation of the emergency siren.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1145 EDT ON 8/23/2014 FROM HENK VERWAY TO MARK ABRAMOVITZ * * *
"As of 0928 EDT on 08/23/2014, siren #13 has been repaired and returned to service."
The licensee notified the NRC Resident Inspector.
Notified the R1DO (McKinley). |
| Power Reactor | Event Number: 50390 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/21/2014
Notification Time: 12:04 [ET]
Event Date: 08/21/2014
Event Time: 08:50 [EDT]
Last Update Date: 08/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY MCKINLEY (R1DO)
|
| 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 INADVERTENT ACTUATION OF ONE EMERGENCY SIREN
"One of the 37 Prompt Notification System sirens surrounding the James A Fitzpatrick (JAF) / Nine Mile Point (NMP) sites spuriously activated at 0850 EDT. The Oswego County Emergency Operations Center notified Nine Mile Point via RECS [Radiological Emergency Communications System] that siren #13 had inadvertently activated. Repair technicians have de-activated and silenced the faulty siren as of 0943 EDT. Siren #13 is currently out of service and the backup method for siren #13 has been verified to be functional. The cause of the inadvertent siren activation is believed to be a lightning strike.
"The issue has been entered into the site's Corrective Action Program.
"The Oswego County Emergency Management Office issued a News Release identifying the inadvertent actuation of the emergency siren.
"The NRC Resident Inspector has been notified.
* * * UPDATE AT 1247 EDT ON 8/23/14 FROM MARK GREER TO MARK ABRAMOVITZ * * *
"As of 0928 EDT on 08/23/2014, siren #13 has been repaired and returned to service. The NRC Resident Inspector has been notified."
Notified the R1DO (McKinley). |
| Power Reactor | Event Number: 50392 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ERIAN STANDER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/22/2014
Notification Time: 13:37 [ET]
Event Date: 08/22/2014
Event Time: 06:45 [CDT]
Last Update Date: 08/22/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMES DRAKE (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 LOSS OF ASSESSMENT CAPABILITY BECAUSE THE METEOROLOGICAL TOWER COMPUTER FAILED
"This notification is being made due to a loss of emergency assessment capability in accordance with 10CFR50.72(b)(3)(xiii). At 0645 (CDT), on 8/22/2014, the meteorological tower computer system failed which resulted in a loss of meteorological data to the plant for greater than 1 hour. Proceduralized compensatory measures for dose assessment include use of National Weather Service followed by historically determined default values. Information Technology personnel have reported to the plant for investigation. The NRC Resident Inspector has been informed. The issue has been put into the corrective action process for further evaluation." |
| Power Reactor | Event Number: 50395 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: PAUL BOKUS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/23/2014
Notification Time: 20:19 [ET]
Event Date: 08/23/2014
Event Time: 13:00 [EDT]
Last Update Date: 08/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
RAY MCKINLEY (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 LOSS OF SAFETY FUNCTION
"At 13:00 [EDT] on Saturday, August 23, 2014, both trains of the Peach Bottom Atomic Power Station (PBAPS) Emergency Service Water (ESW) System were declared inoperable on Unit 2 and Unit 3, due to a pin-hole, through wall piping leak. In accordance with 10CFR 50.72(b)(3)(v), this event is being reported as an event or condition that could have prevented the fulfillment of the safety function of systems that are needed to shut down the reactor and maintain it in a safe shutdown condition, remove residual heat and mitigate the consequences of an accident.
"At 19:22 [EDT], the station received verbal approval of a Notice of Enforcement Discretion (NOED) request. Simultaneously, the station is preparing an evaluation to support an emergent-relief request.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50396 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ALEX RIVAS
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/24/2014
Notification Time: 03:23 [ET]
Event Date: 08/24/2014
Event Time: 00:00 [CDT]
Last Update Date: 08/24/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
DAVE PASSEHL (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO POST ACCIDENT MONITORING INSTRUMENTATION OUT OF SERVICE
"At 0039 [CDT] on 8/19/14, Point Beach Nuclear Plant, Unit 2 identified that 2TE-451A and 2TE-451C Cold Leg Temperature RTDs were out of service. Technical Specification 3.3.3, Post Accident Monitoring (PAM) Instrumentation, Action Condition C for one or more functions with two required channels inoperable was entered. Action Condition C requires one channel to be restored to OPERABLE status within 7 days. If completion time in Action Condition C cannot be met, Action Condition D will be entered, which requires entry into Action Condition E. Action Condition E would require Unit 2 to be in Mode 3 in 6 hours and Mode 4 in 12 hours thereafter.
"Unit 2 is being shut down to effect repairs within the 7 day required action completion time for Action Condition C. This event is reportable under 10 CFR 50.72(b)(2)(i), Plant Shutdown Required by Technical Specifications. The Resident Inspector has been informed." |
| Power Reactor | Event Number: 50397 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SAM MULLINS
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/25/2014
Notification Time: 04:10 [ET]
Event Date: 08/25/2014
Event Time: 05:00 [CDT]
Last Update Date: 08/25/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVE PASSEHL (R3DO)
|
| 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 | Event Text TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE
"On 8/25/2014, planned preventive maintenance activities are being performed on the Braidwood Generating Station Technical Support Center (TSC) Ventilation System. The work will be completed within approximately 42 hours. This activity includes preventive maintenance on the TSC condensing unit which affects the TSC ventilation. During the planned maintenance, the TSC condensing unit will be rendered non-functional.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff as necessary. This planned maintenance will not impact the emergency filtration capability of the TSC.
"This event is reportable per 10CFR50.72(b)(3)(xiii) for 'any event that results in a major loss of emergency assessment capability.' The planned maintenance will not be able to restore the TSC condensing unit to service within the facility activation time specified in the emergency plan (1 hour) in the event of an accident. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"The licensee has notified the NRC Resident Inspector." | |