| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/29/2012 - 10/30/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48422 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: DIVERSIFIED SCIENTIFIC SERVICES, INC.
Region: 1
City: KINGSTON State: TN
County:
License #: R-73014-H14
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 15:51 [ET]
Event Date: 10/19/2012
Event Time: [EDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAKE WELLING (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT- CONTAMINATION EVENT
The following information was received by facsimile:
"DRH [Tennessee Division of Radiological Health] was notified on 10/19/12 by the licensee that preliminary analytical results of a 30-gallon waste container of tritium contaminated waste oil and absorbents indicate approximately 8,600 curies of tritium. The container was manifested by the generator (SRS) [Savannah River Site] as containing 14.9 curies. Post sampling of this container, DSSI [Diversified Scientific Services, Inc.] had a controlled but elevated level of tritium contamination in the process room; this room is under negative ventilation. The room has been decontaminated back to normal processing levels. Contents of the container have been overpacked and placed in a safe state, [and] not a source of tritium contamination to the air or surface."
Tennessee Event: TN-12-267 |
| Agreement State | Event Number: 48423 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: POLARIS
Region: 3
City: SPIRIT LAKE State: IA
County:
License #: 3093-1-30-SEM
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSON
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 16:25 [ET]
Event Date: 08/03/2012
Event Time: [CDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (EMAI)
GARY LANGLIE-EMAIL (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST SOURCE
The licensee misplaced a static eliminator device containing 10 mCi of Po-210. The device model number is P-2021-8301; Serial number is A2HS590. The device was used to neutralize static charge on plastic parts prior to entering the paint process. The licensee considers the device as lost.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Non-Agreement State | Event Number: 48424 | Rep Org: ACUREN INSPECTION
Licensee: ACUREN INSPECTION
Region: 4
City: PRUDHOE BAY State: AK
County:
License #: 42-32443-01
Agreement: N
Docket:
NRC Notified By: ROBERT JEFFERSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/19/2012
Notification Time: 17:08 [ET]
Event Date: 10/04/2012
Event Time: 23:30 [YDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
GREG PICK (R4DO)
FSME RESOURCES (FSME)
| Event Text RADIOGRAPHY SOURCE STUCK
"A drive cable designed for 25' controls was installed in a 35' control assembly. This resulted in 15' of usable drive cable to travel through the guide tube. The radiographers were using a guide tube and extension with a total length of 17' and were unaware that there was not enough drive cable to reach the source stop. The cable was run out past the stop, and could not be retracted.
"The exposure being taken at the time of the incident was a 6:00 shot on a 12" oil line. The line was 15' off the ground near an elevated platform. There was a 42" pipe running between the platform and the pipe being inspected. The exposure device was placed on the platform and an extension was added to the guide tube to route the source around the 42" pipe. The total length of the guide tube and extension was 16'11". The control cables were rerouted to take advantage of nearby shielding. The conduits were disconnected from the Pistol Grip Assembly exposing the drive cable. The source was then retracted into the fully shielded position by pulling the drive cable by hand.
"The entire inventory of control assemblies were inspected to ensure the proper drive cables are installed, as will new assemblies when they are initially received. Additionally, personnel qualified to repair control assemblies will be retrained with emphasis placed on ensuring proper length of drive cable is in place. Training will be documented and filed in personnel records.
"Qualifications of personnel involved in incident:
1. Radiographer, Texas Industrial Radiographer Certification holder, Dose Received, 3mR (dosimeter)
2. Radiographer, IRRSP card holder, Dose Received, 5mR (dosimeter)
3. Radiographer, Illinois Industrial Radiography Certification holder, Dose Received, 7mR (dosimeter)
4. Assistant Radiographer, Dose Received, 2mR (dosimeter)
Source retrieval personnel: Site Radiation Safety Officer, IRRSP card holder, Source Retrieval trained by LAMCO & Associate February 25, 2011, Dose Received, 2mR (Dosimeter)
"Equipment Involved:
7' flexible Guide Tube, serial # GT 1211 22
10' flexible Guide Tube Extension, serial # EXT 12 11
Crank Assembly serial # 11652
Exposure Device Model #: Sentinel Delta 880
Exposure Device serial #: D3534
Isotope: Iridium 192
Source serial #: 84462B |
| Agreement State | Event Number: 48425 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: UNIVERSITY OF IOWA HOSPITAL AND CLINIC
Region: 3
City: IOWA CITY State: IA
County:
License #: 0037-1-52-AAB
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSON
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 17:34 [ET]
Event Date: 10/18/2012
Event Time: [CDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL DOSAGE NOT DELIVERED AS PLANNED
A patient was being treated for a liver tumor and the dosage was delivered to the wrong lobe. The physician prescribed 17 mCi of Y-90 to the left lobe of the liver. The prescribing physician was not present during the dose administration procedure. The intervention radiologist examined a fluoroscope of the patient's liver and noted a larger tumor on the right lobe. The prescribed dosage was then delivered to the right lobe of the liver, not in accordance with the prescribed dosage plan. Patient examination detected no observable impact, and the physician is developing another dosage plan for the patient. The Iowa Department of Public Health will perform an onsite investigation.
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. |
| Non-Agreement State | Event Number: 48432 | Rep Org: ANDERSON ENGINEERING INC
Licensee: ANDERSON ENGINEERING INC
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-20063-01
Agreement: N
Docket:
NRC Notified By: STEVEN BRADY
HQ OPS Officer: VINCE KLCO | Notification Date: 10/22/2012
Notification Time: 16:48 [ET]
Event Date: 10/22/2012
Event Time: 11:30 [CDT]
Last Update Date: 10/22/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text DAMAGED NUCLEAR DENSITY GAUGE
"Incident: At approximately 1130 CDT, at the new Joplin High School Construction Site in Joplin, Jasper County, Missouri, a nuclear density [gauge] was run over by a tire of a towed scraper. The damage was primarily to the housing of the meter. The technician immediately secured the area and contacted his supervisor. [The supervisor] went to the site and took readings using a TROX-A-LERT Model 3105B Radiation Survey Meter of the gauge and the soil where the gauge was run over and of the scraper which ran over the [gauge]. Readings at 1 meter from the [gauge] ranged from 0.12 to 0.20 mrem/hr. A reading of 2.5 mrem/hr [was indicated at the] housing of the [gauge] . The source did not appear to be damaged and was still encapsulated in the [gauge].
"The gauge was placed in a truck box mounted in the bed of a pickup truck and taken back to [the licensee's lab]. Once at the lab the gauge was wrapped in lead sheeting and placed in a nuclear [gauge] storage box. A reading of 0.1 mrem/hr was obtained at 1 meter with the lead sheeting wrapped around the meter."
The damaged gauge is a CPN, serial number MD1205992. |
| Power Reactor | Event Number: 48450 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: DAN LIVERMORE | Notification Date: 10/29/2012
Notification Time: 16:15 [ET]
Event Date: 10/29/2012
Event Time: 15:00 [EDT]
Last Update Date: 10/30/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF 21 EMERGENCY NOTIFICATION SIRENS
On October 29, 2012, at approximately 1500 EDT, ANS, the licensee's provider of siren maintenance, reported a loss of 12 out of 43 sirens in the Oyster Creek Emergency Planning Zone, which exceeded the licensee's reporting threshold of 25 percent or more sirens out of service.
At 1600 EDT, ANS, updated that the number of sirens out of service was 21 out of 43 sirens. ANS and the licensee continues to work to rectify the issue.
The NRC Resident Inspector will be notified.
* * * UPDATE ON 10/30/12 AT 0428 EDT FROM JOHN CLARK TO RYAN ALEXANDER * * *
As of 0320 EDT on 10/30/12, it was determined that 36 of the 43 Emergency Planning Zone sirens were out of service, and the license continues work to rectify the issue.
The NRC Resident Inspector will be notified. Notified R1DO (Caruso) and IRD (Marshall). |
| Power Reactor | Event Number: 48451 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: BRETT JEBBIA
HQ OPS Officer: DAN LIVERMORE | Notification Date: 10/29/2012
Notification Time: 18:15 [ET]
Event Date: 10/29/2012
Event Time: 17:00 [EDT]
Last Update Date: 10/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LAURA KOZAK (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 68 | Power Operation | 68 | Power Operation | Event Text ERDS LOST DUE TO PROCESS COMPUTER SYSTEM DATA SERVER FAILURE
"At 1700 EDT on October 29, 2012, Fermi 2 discovered a failure occurred with a data server within the Process Computer system at 0115 EDT on October 28, 2012. The failure of the data server affects data input to the server providing information to the Emergency Response Data System (ERDS). ERDS is currently not receiving updated information from Fermi data systems. This loss in capability is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"Indications of related plant variables are available in the Main Control Room. The Visual Annunciator System (VAS) and other portions of the Process Computer system remain functional. Meteorological and process effluent radiological monitor indications are available and dose assessment capability is available. Fermi 2 personnel will use normal phone communications to update NRC Operations Center in the case of an event declaration. Information normally provided by ERDS can be transmitted via the notification system as described in the Radiological Emergency Response Preparedness Plan. Fermi 2 will notify the NRC when ERDS is returned to service."
The licensee has notified the NRC Resident Inspector. Notified R3DO (Kozak). |
| Power Reactor | Event Number: 48452 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: STEVE SERPE
HQ OPS Officer: RYAN ALEXANDER | Notification Date: 10/29/2012
Notification Time: 21:41 [ET]
Event Date: 10/29/2012
Event Time: 20:44 [EDT]
Last Update Date: 10/30/2012 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
JOHN CARUSO (R1DO)
WILLIAM DEAN (R1 R)
ERIC LEEDS (NRR)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
VICTOR MCCREE (R2 R)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text NOTICE OF UNUSUAL EVENT DECLARED DUE TO HIGH INTAKE STRUCTURE WATER LEVEL
At 1855 EDT on 10/29/2012, the licensee declared a Notice of Unusual Event (NOUE) per criteria HU4 for high water level in the station intake structure of greater than 4.5 feet. At the time of the notification, water level in the intake structure was approximate 4.8 feet and slowly rising. The cause of the increased water level was due to storm surge associated with Hurricane Sandy. No other station impacts were reported at the time. The licensee continues to monitor the intake levels and ocean tides.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
* * * UPDATE ON 10/29/2012 AT 2141 EDT FROM STEVE SERPE TO RYAN ALEXANDER * * *
At 2044 EDT on 10/29/2012, the licensee escalated its emergency declaration to an Alert per criteria HA4 for high water level in the station intake structure of greater than 6.0 feet. At the time of the notification, water level in the intake structure was approximately 6.6 feet. The site also experienced a loss of offsite power event concurrent with the additional water level increase. Both emergency diesel generators started and are supplying power to the emergency electrical busses. Shutdown cooling and spent fuel pool cooling have been restored. Reactor pressure vessel level is steady at 584.7 inches. Intake levels continues to rise slowly and the licensee is monitoring.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.
* * * UPDATE on 10/30/12 at 0414 EDT FROM GILBERT DEVRIES TO RYAN ALEXANDER * * *
The licensee updated this report with an 8-hour non-emergency notification of emergency diesel generator auto-actuation due to the actual loss of off-site power event [which occurred at 2018 EDT on 10/29/2012]. This event caused a valid RPS actuation with automatic containment isolations that resulted in a temporary loss of shut-down cooling to the reactor. Shutdown cooling was subsequently restored with power provided by the emergency diesel generators.
The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso). |
| Power Reactor | Event Number: 48453 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KEVIN MATTESSICH
HQ OPS Officer: ERIC SIMPSON | Notification Date: 10/29/2012
Notification Time: 21:58 [ET]
Event Date: 10/29/2012
Event Time: [EDT]
Last Update Date: 10/29/2012 | 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):
JOHN CARUSO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text RPS ACTUATION WHILE CRITICAL DUE TO GENERATOR LOAD REJECT
On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 1 experienced an automatic reactor scram due to a generator load reject. The cause of the load reject is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram.
Following the automatic scram, the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. At 2101 EDT, RPV level was restored above the HPCI System low level actuation set point and the HPCI System initiation signal was reset. Pressure control was established on the Turbine Bypass Valves, the preferred system. Three Electromatic Relief Valves actuated due to this scram and re-closed automatically.
Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using bypass valves. Both Reserve Station Transformers are in service and being supplied by their normal power sources. Both Emergency Diesel Generators are operable and in standby.
The unit is currently implementing post scram recovery procedures.
The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso). |
| Power Reactor | Event Number: 48454 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHUCK GUALDONI
HQ OPS Officer: ERIC SIMPSON | Notification Date: 10/30/2012
Notification Time: 00:30 [ET]
Event Date: 10/29/2012
Event Time: 22:41 [EDT]
Last Update Date: 10/30/2012 | 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):
JOHN CARUSO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC RPS ACTUATION ON GENERATOR TRIP
"On October 29, 2012, at 2241EDT, the Reactor Protection System automatically actuated at 100% reactor power due to a direct electrical trip to the Unit 3 Main Turbine Generator. The generator trip resulted in a turbine/reactor trip. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time.
"The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via condenser steam
dumps. There was no radiation released.
"Indian Point Unit 2 was not affected by this event and remains at 100% power.
"A post trip investigation is in progress."
The licensee notified the NRC Resident Inspector. Notified R1DO (Caruso). |
| Power Reactor | Event Number: 48455 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JAMES BROWN
HQ OPS Officer: ERIC SIMPSON | Notification Date: 10/30/2012
Notification Time: 03:20 [ET]
Event Date: 10/30/2012
Event Time: 00:30 [EDT]
Last Update Date: 10/30/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)
|
| 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 EMERGENCY SIRENS DUE TO IMPACTS FROM HURRICANE SANDY
"Peach Bottom Atomic Power Station Control Room was notified of a loss of greater than 25% of sirens after severe storms in the area associated with Hurricane Sandy. Thirty-one (31) of 97 Emergency Planning Zone (EPZ) sirens are currently unavailable in Lancaster, York, Cecil and Harford Counties. Actions are currently being taken to restore unavailable sirens."
The licensee notified the NRC Resident Inspector. Notified R1DO (Caruso) and IRD (Marshall). |
| Power Reactor | Event Number: 48456 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: ERIC SIMPSON | Notification Date: 10/30/2012
Notification Time: 03:35 [ET]
Event Date: 10/29/2012
Event Time: 21:00 [EDT]
Last Update Date: 10/30/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JOHN CARUSO (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 | Event Text AUTOMATIC INITIATION OF EMERGENCY DIESEL GENERATOR DUE TO LOSS OF ONE OFF-SITE POWER SOURCE
"On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 Emergency Diesel Generator due to a loss of line 5. Line 5 is one of the 115KV offsite power sources. Line 5 was lost due to a lightening arrestor falling onto electrical components in the Scriba switchyard during high winds.
"During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of line 5.
"The off-site power source, line 5, was restored on October 30, 2012 at 0326 EDT."
The licensee notified the NRC Resident Inspector. Notified the R1DO (Caruso). |
| Power Reactor | Event Number: 48457 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN BRENNAN
HQ OPS Officer: ERIC SIMPSON | Notification Date: 10/30/2012
Notification Time: 04:10 [ET]
Event Date: 10/30/2012
Event Time: 01:09 [EDT]
Last Update Date: 10/30/2012 | 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):
JOHN CARUSO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FROM 100% POWER
"This report if being made under the requirements of 10 CFR 50.72(b)(2)(iv)(B), Actuation of the Reactor Protection System While Critical, except preplanned, and under the requirements of 10 CFR 50.72(b)(3)(iv)(A), Valid Actuation of Listed System, except preplanned.
"Salem Unit 1 was operating at 100% reactor power when a loss of 4 condenser circulators required a manual reactor trip in accordance with station procedures. The cause of the 4 circulators being removed from service was due to a combination of high river level and detritus from Hurricane Sandy's transit.
"All control rods inserted. A subsequent loss of the 2 remaining circulators required transition of decay heat removal from condenser steam dumps to the 11-14 MS10s (atmospheric steam dump). Decay heat removal is from the 11/12 Aux Feed Pumps to all 4 steam generators via the 11-14 MS10s. 11/12/13 AFW pumps started due to low level on all steam generators due to shrink from full power operation (this is a normal response). All safety related equipment functioned as expected. No one has been injured. As an additional note, Hurricane Sandy had recently moved past artificial island. Salem Unit 1 is currently in Mode 3. Salem Unit 2 reactor is currently in its 2R19 refueling outage and is shutdown and defueled with no fuel movement in progress."
The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso). | |