| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/15/2010 - 10/18/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 46328 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: KANSAS DEPARTMENT OF TRANSPORTATION
Region: 4
City: TOPEKA State: KS
County:
License #: 22-B315-01
Agreement: Y
Docket:
NRC Notified By: DAVID WHITFILL
HQ OPS Officer: CHARLES TEAL | Notification Date: 10/12/2010
Notification Time: 13:26 [ET]
Event Date: 10/12/2010
Event Time: [CDT]
Last Update Date: 10/14/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
ANGELA MCINTOSH (FSME)
ILTAB VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE - TROXLER MOISTURE DENSITY GAUGE MISSING IN TRANSIT
One Troxler moisture/density gauge and three thin layer density gauges were transported to InstroTek, Inc. on September 23, 2010. The licensee was later notified that only three Troxler thin layer density gauges had arrived. The licensee searched their loading docks and did not find the missing gauge. InstroTek and R and L Trucking have also performed searches, but did not locate the gauge. The information about the gauge is below:
Troxler Model 3440 Nuclear Moisture/Density gauge
Serial Number 22504
CS-137, 8 mCi, Serial Number 47-4236
Am-241 Be, 40 mCi, Serial Number 47-18335
KS NMED KS100012
* * * UPDATE ON 10/14/2010 AT 1052 FROM DAVID WHITFILL TO MARK ABRAMOVITZ * * *
The Troxler Moisture Density Gauge was found at the R and L Trucking Terminal in Wilson, NC (about 40 miles from the intended destination of Raleigh, NC). The gauge is being delivered to InstroTek today (10/14/2010).
Notified the R4DO (Haire) and FSME (McIntosh).
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
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 46336 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GARY MEEKINS
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/16/2010
Notification Time: 01:52 [ET]
Event Date: 10/15/2010
Event Time: 23:21 [EDT]
Last Update Date: 10/16/2010 | 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):
TODD JACKSON (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 Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO A TURBINE TRIP
"An automatic reactor trip of Salem Unit 1 [occurred] due to a turbine trip above P-9. The crew entered EOP [Emergency Operating Procedure] Trip 1, appropriately transitioned to EOP Trip 2, and stabilized the plant at no load conditions. All rods fully inserted on the trip, and all systems responded as designed with decay heat removal being removed via the steam dump system with condenser vacuum being maintained. The Auxiliary Feed Water Pumps automatically started due to low steam generator levels. Salem Unit 1 is currently in Mode 3. Reactor Coolant System temperature is 547 degrees, and pressure is 2235 pounds. All Emergency Core Cooling Systems and Engineered Safety Function Systems are available. No personnel injuries occurred as a result of the trip. No radiological release [occurred] due to this event."
Approximately 5 minutes prior to the turbine trip, Salem Unit 1 lowered reactive loading on the voltage regulator as requested by the load dispatcher while Hope Creek Unit 1 was coming off line due to their outage. The cause of the trip is still under investigation. There was no impact on Salem Unit 2 as a direct result of this event.
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 46337 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACK OSBORNE
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/17/2010
Notification Time: 06:38 [ET]
Event Date: 10/17/2010
Event Time: 05:12 [EDT]
Last Update Date: 10/17/2010 | 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):
WILLIAM COOK (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 4 KV GROUP BUS UNDERVOLTAGE CONDITION
"On 10/17/10 at 0512 [EDT], Unit 2 experienced an [automatic] reactor trip due to 4 kV group bus under voltage. While restoring the voltage regulator to automatic, following a swap to manual at 0123 [EDT] on 10/17/10 while 500 kV line 5014 was being restored to service, the reactor tripped after placing the voltage regulator in automatic.
"The crew entered EOP [Emergency Operating Procedure] Trip 1, and then EOP Trip 2 as required. The plant was stabilized at no load conditions. All rods fully inserted on the trip, and all systems responded as designed with RCS [Reactor Coolant System] temperature being controlled via 21 RCP [Reactor Coolant Pump] and the steam dump system. 22, 23, and 24 RCP's tripped on group bus under voltage. The AFW [Auxiliary Feed Water] Pumps started in response to low steam generator levels. 23 AFW was subsequently tripped per procedure since 21 and 22 AFW pumps were in service feeding 21-24 steam generators.
"Salem Unit 2 is currently in Mode 3. RCS temperature is 547 degrees. RCS pressure is 2235 pounds. All Emergency Core Cooling Systems and Engineered Safety Function Systems are available. No personnel injuries occurred as a result of the trip. No radiological release is in progress due to this event."
At 0123 EDT, following the restoration of a 500 kV line, perturbation in the line caused an over current condition which shifted the voltage regulator to manual. After engineering's recommendation, the voltage regulator was placed in automatic shortly prior to the reactor trip. The plant is in a normal shutdown electrical lineup. There was no impact on Salem Unit 1 as a result of this event.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46338 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/17/2010
Notification Time: 14:35 [ET]
Event Date: 10/17/2010
Event Time: 09:53 [CDT]
Last Update Date: 10/17/2010 | 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):
MARK HAIRE (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 16 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP ON LOW STEAM GENERATOR LEVEL DURING PLANT STARTUP
"At 0953 CDT, Wolf Creek experienced a reactor trip due to low steam generator level. At the time of the trip the plant was in Mode 1 approximately 16% power following a forced outage. A feedwater isolation signal [FWIS] was generated due to high S/G level (P-14) in 'B' S/G [steam generator]. The FWIS resulted in a low S/G level. Although a manual reactor trip was ordered by the duty Shift Manager, the manual trip signal was not inserted before the reactor automatically tripped on low steam generator level.
"Auxiliary Feed Water systems actuated as expected due to low steam generator levels.
"The plant is presently in Mode 3 at normal operating temperature and pressure.
"The Senior Resident Inspector has been notified."
All control rods fully inserted during the trip. All three Auxiliary Feedwater Pumps started to maintain S/G levels.
The plant was stabilized with the motor driven startup feedwater pump maintaining S/G level. Decay heat is being removed using the atmospheric steam dumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup.
A press release will be issued. | |