|
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/18/2010 - 10/19/2010
** EVENT NUMBERS **
|
| General Information or Other |
Event Number: 46332 |
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: LEE TESTING & ENGINEERING, INC
Region: 3
City: HILLIARD State: OH
County:
License #: OH31210250011
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 10/14/2010
Notification Time: 13:43 [ET]
Event Date: 08/30/2010
Event Time: [EDT]
Last Update Date: 10/14/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
MONTE PHILLIPS (R3DO)
ANGELA MCINTOSH (FSME) |
Event Text
OHIO AGREEMENT STATE REPORT - ABANDONED MOISTURE DENSITY GAUGES
The following information was obtained from the State of Ohio via email:
"On August 11, 2010, the licensee submitted a request to [the State of Ohio to] terminate their portable gauge license. On September 9, 2010, the Ohio Department of Health (ODH) was notified by a third party that Lee Testing had vacated the premises at 3530 Parkway Lane and had left behind a total of seven (7) devices containing radioactive materials. Upon contacting the building owner, it was determined that the licensee had moved out of the building sometime during the prior week, and that the keys to the building and its contents were relinquished to the building owner.
"On September 13, 2010, representatives from ODH and a licensed service provider visited the 3530 Parkway Lane location and removed the seven devices present at that location. This removal was determined to be necessary as authorized under rule 3701:1-38-06(E) of the Ohio Administrative Code (OAC). The seven devices are currently in a safe and secure storage location pending a decision on final disposition.
"ODH is conducting an ongoing investigation.
"The NRC Registry of Radioactive Sealed Sources and Devices indicates that [three Troxler Model] 3411-B gauges contain a Cs-137 source with a maximum activity of 0.33 GBq (9 mCi) and an Am-Be source with a maximum activity of 1.63 GBq (44 mCi). The Registry indicates that [Troxler Model] 3241-C gauge contains an Am-Be source with a maximum activity of 11.1 GBq (300 mCi). The Registry also indicates that the [three Humboldt Scientific Model] 5001 gauges contain a Cs-137 source with a maximum activity of 0.41 GBq (11 mCi) and an Am-Be source with a maximum activity of 1.63 GBq (44 mCi)."
Ohio Report Number: OH100494 |
| General Information or Other |
Event Number: 46333 |
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: RIVERSIDE METHODIST HOSPITAL
Region: 3
City: COLUMBUS State: OH
County:
License #: 02120250070
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 10/14/2010
Notification Time: 13:43 [ET]
Event Date: 04/06/2010
Event Time: [EDT]
Last Update Date: 10/14/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
MONTE PHILLIPS (R3DO)
ANGELA MCINTOSH (FSME) |
Event Text
OHIO AGREEMENT STATE REPORT - D90 DOSE LESS THAN PRESCRIBED DOSE
The following information was obtained from the State of Ohio via email:
"Note: This information is reported as a result of a special inspection performed [by the State of Ohio] on July 28 and 29, 2010, limited to the licensee's prostate implant program.
"The licensee performed a prostate seed implant on April 6, 2010. The patient was prescribed a dose of 100Gy using Iodine-125 seeds. The D90 post implant dosimetry performed on May 12, 2010, indicated a D90 of 62.5 Gy was given. This is a difference of 37.5% from the prescribed dose. The post plan dosimetry was performed by a radiation therapist on May 12, 2010, and the results were reviewed by a medical physicist on May 18, 2010. This qualifies as a Medical Event per rule 3701:1-58-101(A)(1)(a) of the Ohio Administrative Code (OAC).
"The licensee failed to notify by telephone the Ohio Department of Health no later than the next calendar day after the discovery of the medical event, and submit a written report within fifteen days after discovery of the medical [event]. This is a violation of ODH requirements as referenced in rule 3701:1-58-101 ® and (D)."
Ohio Report Number: OH100025 |
| 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: 10/18/2010 |
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.
* * * UPDATE FROM BILL MUFFLEY TO JOHN SHOEMAKER 1138 EDT ON 10/18/10 * * *
Notified by the licensee that the AFW Pumps started on loss of Steam Generator Feed Pumps which had tripped on low suction pressure.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 46339 |
Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: PETE SNYDER |
Notification Date: 10/18/2010
Notification Time: 09:34 [ET]
Event Date: 10/18/2010
Event Time: 10:00 [EDT]
Last Update Date: 10/18/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
STEVE ORTH (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
N |
0 |
Refueling |
0 |
Refueling |
Event Text
UNAVAILABILITY OF EMERGENCY RESPONSE DATA SYSTEM (ERDS) FOR SCHEDULED MAINTENANCE
"At approximately 10:00 a.m. on Monday, October 18, 2010, the Cook Nuclear Plant (CNP) Unit 2 Plant Process Computer (PPC) will be removed from service for scheduled power supply distribution panel preventive maintenance. This will remove Unit 2 PPC data input to ERDS rendering the system non functional for providing data to the NRC Operations Center. The scheduled maintenance will also affect the Safety Parameter Display System (SPDS), the Real Time Data Repository (RDR), and PPC data to Emergency Response Facilities at CNP.
"The scheduled maintenance is expected to take up to 6 hours to complete.
"Compensatory measures exist within the CNP Emergency Response procedure to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)."
CNP Unit 2 is currently defueled.
* * * UPDATE FROM DEAN BRUCK TO JOE O'HARA AT 1518 EDT ON 10/18/10 * * *
"Functionality has been restored to ERDS following restoration of the Unit 2 PPC at 1422. SPDS, RDR, and PPC data to Emergency Response Facilities at CNP have also been restored to service at 1422."
The NRC Resident Inspector has been notified.
Notified R3DO(Orth). |
| General Information or Other |
Event Number: 46340 |
Rep Org: ASCO VALVE
Licensee: AREVA
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT ARNONE
HQ OPS Officer: JOE O'HARA |
Notification Date: 10/18/2010
Notification Time: 13:09 [ET]
Event Date: 09/18/2010
Event Time: [EDT]
Last Update Date: 10/18/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH |
Person (Organization):
VIVIAN CAMPBELL (R4DO)
PART 21 GRP () |
Event Text
POTENTIAL EXTERNAL LEAKAGE IN SOLENOID VALVE
The following notification was received via fax:
"On 9/18/10 a single solenoid valve was returned to ASCO with a reported problem of external leakage at the bonnet area below the coil housing. The valve was returned from Cooper Nuclear Station through AREVA, who was the distributor.
"The returned valve was retested at ASCO. No external leakage was observed when the valve was tested in the de-energized state. However, when the valve was tested in the energized state, the reported leakage was confirmed. The root cause of the leakage was determined to be a misaligned O-ring between the solenoid base sub-assembly and the valve body.
"The customers that were shipped affected valves are being notified of the potential non-conformance. ASCO will recommend the affected valves be returned to be retested in accordance with updated test procedures." |
| Other Nuclear Material |
Event Number: 46341 |
Rep Org: ARCELORMITTAL BURNS HARBOR
Licensee: ARCELORMITTAL BURNS HARBOR
Region: 3
City: BURNS HARBOR State: IN
County:
License #: 13-32670-01
Agreement: N
Docket:
NRC Notified By: CHRIS SARVANIDIS
HQ OPS Officer: ERIC SIMPSON |
Notification Date: 10/18/2010
Notification Time: 13:38 [ET]
Event Date: 10/18/2010
Event Time: 07:00 [EDT]
Last Update Date: 10/18/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE |
Person (Organization):
STEVE ORTH (R3DO)
MICHELE BURGESS (FSME) |
Event Text
STUCK GAUGE SHUTTER
On 10/18/10 at approximately 8:32 am, the site Radiation Safety Officer (RSO) was contacted by a radiation worker at the 80" Hot Strip Mill location, indicating that the shutter on one of the slab detection radiation gauges would not close. The worker was in the process of performing a semi-annual wipe test when the situation was noticed.
The RSO directed site workers to barricade the area until he arrived. Upon arrival, the RSO conducted a survey of the area, compared the levels to a prior survey and found no significant difference in radiation levels. The RSO also performed a wipe test on the gauge and checked it with a survey meter and pancake probe, finding no detectable contamination. The radiation worker was directed to check the device counts using a survey meter and to compare them to counts on an adjacent gauge. The counts were similar, indicating proper function.
A melted metallic material was noted adjacent to the gauge whose shutter would not close. The material was analyzed and it showed to be 90-95% lead. As a result, it is believed some shielding may have overheated and blocked the shutter open or debris entered the shutter arm blocking it from closing. Although radiation levels in the area are normal, the RSO will attempt to safely remove the gauge to a secure location until the device can be serviced by the manufacturer.
The Cs-137 source is S/N 6326CM of a slab detection device manufactured by Ronan Engineering. |
|