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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/23/2008 - 06/24/2008
** EVENT NUMBERS **
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| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! |
| Power Reactor |
Event Number: 44165 |
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TERRY DAMASHEK
HQ OPS Officer: JOHN KNOKE |
Notification Date: 04/25/2008
Notification Time: 10:39 [ET]
Event Date: 04/25/2008
Event Time: 02:56 [CDT]
Last Update Date: 06/23/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP |
Person (Organization):
CHUCK CAIN (R4) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Refueling |
0 |
Refueling |
Event Text
BOTH EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE
"On 4/24/2008 at 0110 CDT, a concern with the flexible connection alignment between heat exchangers on the 'A' Emergency Diesel Generator was identified. At the time this condition was identified the 'A' Diesel was out of service for outage maintenance activities. During evaluation of this condition, and discussions with the vendor supplier for this flexible connection, additional questions arose and the condition of the identical connections on the 'B' Emergency Diesel Generator was questioned. Inspection of the 'B' Emergency Diesel Generator identified a similar problem, and at 0256 CDT on 4/25/2008, the 'B' Emergency Diesel Generator was declared inoperable, and the Plant entered TS 3.8.2, Condition B, for one required Diesel Generator being inoperable. All required actions regarding TS 3.8.2 have been complied with.
"The 'B' Emergency Diesel Generator is still considered to be functional, and remains aligned for automatic start. The 'A' EDG is currently tagged out and work is ongoing to correct the alignment issue. Upon completion of repair to the 'A' EDG it will be restored to operation and the 'B' EDG will be removed from service to correct the alignment issue.
"The plant is currently in Mode 6, with RCS level greater than 23 feet above the Reactor Vessel Flange, and both required Offsite Power Sources remain operable."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION PROVIDED BY LANCE LANE TO JASON KOZAL AT 1254 ON 6/22/08 * * *
"Testing, conducted by the vendor, was performed on the flexible connections in the configuration found at Wolf Creek and in a worst case configuration. The joints were tested, up to design pressure with a joint movement equivalent to a design bases earthquake, without failing. Additionally, the joints were pressurized to burst pressure, which was determined to be greater than 5 times the design pressure of the connection. The testing showed that even though the joints were not installed in accordance with the vendor's recommendation they would have fulfilled their safety function as installed. Therefore, a condition that could have prevented fulfillment of a safety function did not exist. Wolf Creek is retracting the 50.72(b)(3)(v)(B) notification."
The licensee notified the NRC Resident Inspector. Notified R4DO (Proulx). |
| General Information or Other |
Event Number: 44303 |
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: 'R' PLACE
Region: 4
City: HORDVILLE State: NE
County:
License #: GL0683
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: JASON KOZAL |
Notification Date: 06/18/2008
Notification Time: 08:28 [ET]
Event Date: 07/20/2007
Event Time: [CDT]
Last Update Date: 06/18/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
THOMAS FARNHOLTZ (R4)
MICHELE BURGESS (FSME)
ILTAB VIA E-MAIL () |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS
The state provided the following information via e-mail:
"The Department contacted the general licensee because the annual fee for the general license was overdue for two self illuminating signs. The signs were from Best Lighting (Model SLTURW10)(Serial # 166473 and 166474) with 7.03 curies [each] of H3 (in June of 2006). The general licensee hired an individual to remove the signs from the dining room and put them into the storage room in the cafĂ during July of 2007.
"The general licensee went to the storage room in the second week of August 2007 to retrieve some stored items. Items were missing and additionally the two exit signs were also missing. The general licensee tried to contact the man who she hired to move the supplies and equipment. She did not find a phone listing. She sent him a letter to the address he had given her and the letter was returned as no such address."
Nebraska event number: NE080003.
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.
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 |
| General Information or Other |
Event Number: 44304 |
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: KRAZAN & ASSOCIATES, INC
Region: 4
City: PUYALLUP State: WA
County:
License #: WN-I0431-1
Agreement: Y
Docket:
NRC Notified By: ARDEN SCROGGS
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 06/18/2008
Notification Time: 17:40 [ET]
Event Date: 06/17/2008
Event Time: 16:30 [PDT]
Last Update Date: 06/18/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
THOMAS FARNHOLTZ (R4)
JOSEPH HOLONICH (FSME) |
Event Text
AGREEMENT STATE - DAMAGE TO TROXLER MOISTURE DENSITY GAUGE
The Washington State Department of Health, Office of Radiation Protection provided the following report via e-mail:
"The Licensee was working with a Troxler Model 3430, portable moisture density gauge, serial number 19739, having a 10 millicurie, Cesium-137 and a 40 millicurie, Americium-241/Beryllium sealed sources. The work was being done at a temporary job-site near Walla Walla, Washington. The gauge operator was taking measurements with the Cs-137 source rod inserted into the test hole. The operator walked away from the gauge to look for the next test site. While the operator was away, the gauge was struck by a front-end loader. The gauge operator cordoned off the area and contacted the Radiation Safety Officer. The RSO then contacted the Office of Radiation Protection (ORP) to make a verbal report. Two ORP staff were already in the vicinity and were rerouted to the incident scene. When staff arrived they reported the gauge had been visibly damaged. The plastic exterior was smashed with the source rod still in the test hole. The gauge's guide rod with the handle had been sheared-off by the front-end loader. ORP staff were able to push the source rod back into the gauge's shielded position. They also took a wipe sample from the source rod, the gauge exterior, and surveyed the soil where the source rod had been. No contamination was found. The gauge was placed back into its transport box. ORP staff took dose-rate readings on the outside of the box and found normal levels. The gauge was taken to the licensee's storage facility in Walla Walla where it awaits shipping instructions for returning it to Troxler.
"The Licensee is being cited by DOH for not keeping the gauge under constant surveillance and control while away from an approved storage location."
Washington Report WA-08-040 |
| General Information or Other |
Event Number: 44307 |
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: CARDINAL HEALTH
Region: 1
City: WOBURN State: MA
County:
License #: 42-0146
Agreement: Y
Docket:
NRC Notified By: BOB GALLAGHAR
HQ OPS Officer: STEVE SANDIN |
Notification Date: 06/19/2008
Notification Time: 14:11 [ET]
Event Date: 06/13/2008
Event Time: 04:00 [EDT]
Last Update Date: 06/19/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
WAYNE SCHMIDT (R1)
MICHELE BURGESS (FSME) |
Event Text
AGREEMENT STATE REPORT INVOLVING A VEHICLE TRANSPORTING RADIOACTIVE MATERIAL
On 6/13/08, a Cardinal Health vehicle transporting Tc-99m and I-131 was involved in a vehicle accident on Route 495N. The vehicle overturned spilling eleven (11) shipping containers onto the roadway. The containers were not damaged and no radioactive material was released on the roadway or to the surrounding environment. The rad material was returned to the Cardinal Health facility in Woburn, MA. The licensee notified the National Response Center and the Commonwealth of Massachusetts. |
| Power Reactor |
Event Number: 44311 |
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: JOE O'HARA |
Notification Date: 06/23/2008
Notification Time: 03:26 [ET]
Event Date: 06/23/2008
Event Time: 03:00 [EDT]
Last Update Date: 06/23/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
MICHAEL KUNOWSKI (R3) |
| 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
LOSS OF EMERGENCY RESPONSE CAPABILITY - TSC IS UNAVAILABLE
"UNAVAILABILITY OF TSC CHARCOAL FILTER FOR SCHEDULED MAINTENANCE
"At 0300 on Monday, June 23,2008, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) ventilation system charcoal filter was removed from service for planned charcoal bed maintenance. The balance of the TSC ventilation is not affected by the charcoal bed maintenance and remains available.
"Under certain accident conditions the TSC may become unavailable due to the inability of the filtration system to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"Charcoal filter maintenance is scheduled to complete at 1000 on Wednesday, June 25, 2008.
"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 the loss an emergency response facility." |
| Power Reactor |
Event Number: 44312 |
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BOB MEIXELL
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 06/23/2008
Notification Time: 11:01 [ET]
Event Date: 06/16/2008
Event Time: 14:13 [EDT]
Last Update Date: 06/23/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH |
Person (Organization):
BINOY DESAI (R2)
PART 21 GROUP () |
| 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
REPLACEMENT BREAKER CHARGING MOTORS FAILED MINIMUM VOLTAGE TEST
"Event: On June 16, 2008, Duke Energy (Duke) completed a reportability determination which concluded that a defect associated with 10 electric charging motors for breakers is reportable under Part 21. This is a legacy issue from May 22, 2000, which was re-evaluated as a result of an assessment of Oconee's Part 21 processes. The motors were procured as safety-related from Asea Brown Boveri (ABB) (Florence, SC location) on February 22, 2000, ABB Part# 709799T11. The motors were received on March 9, 2000 and subsequently, breaker personnel identified the part number on the replacement motors did not agree with the existing motors. When installed in a breaker for testing, the replacement motors did not function at the required minimum 90VDC. Duke will provide follow up written notification within 30 days pursuant to Part 21.21(d)(3)(ii).
"Initial Safety Significance: None. The motors were never placed in service. However, the evaluation concluded because of the safely related applications for which the motors were intended, the defect could have resulted in a significant safety hazard had the motor(s) been placed in service."
The licensee verified that this part was not used at other Duke nuclear plants.
The licensee notified the NRC Resident Inspector and the ABB Project Manager for Oconee. |
| Fuel Cycle Facility |
Event Number: 44313 |
Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: CHERYL GOFF
HQ OPS Officer: JOE O'HARA |
Notification Date: 06/23/2008
Notification Time: 11:28 [ET]
Event Date: 06/23/2008
Event Time: 10:35 [EDT]
Last Update Date: 06/23/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (a)(5) - ONLY ONE SAFETY ITEM AVAILABLE |
Person (Organization):
BINOY DESAI (R2)
GORDON BJORKMAN (NMSS) |
Event Text
ONLY ONE SAFETY ITEM AVAILABLE FOR SAFETY FOR GREATER THAN 8 HOURS
"I. EVENT DESCRIPTION: In April of this year, BWXT replaced the recirculation columns on the High Level Trough Dissolvers in the Uranium Recovery Facility. The columns were processed out of the area according to standard waste handling procedures for disposal. An NMC technician raised a concern as the columns were checked by BWXT Security before placement into a SeaLand container. The technician believed the response of Security's monitor was overly sensitive compared to the assigned 235-U values based on calculations. NMC immediately placed a hold on the columns.
"The columns were later moved into the Decon Area of BWXT's Waste Treatment Facility where they were stored for approximately three weeks. The Decon area is posted by Nuclear Criticality Safety for 100 grams of 235-U. NMC personnel conducted subsequent NDA field measurements of the columns and estimated an accumulation of approximately 695 grams 235-U in four of the columns. The Decon Area was immediately secured and a Radiation Work Permit (RWP) generated to clean and reevaluate the columns in the Uranium Recovery's Maintenance area.
"The four columns were relocated to the Recovery Maintenance area where they were cleaned according to the instructions in the RWP. NDA measurements of the columns and cleaning materials indicated a total 235-U content of 577 grams. The Limiting Condition for Operation (LCO) in the Decon Area is 400 grams. The Item Relied On For Safety (IROFS) for control of mass was degraded.
"II. EVALUATION OF THE EVENT: The safety basis for the Decon Area takes credit for two IROFS, control of mass and moderation. The control for mass was degraded. Although the LCO for 235-U mass was exceeded by 177 grams, this was less than the fully reflected, optimally moderated minimum critical mass of approximately 800 grams. A criticality was not credible in this scenario.
There was no immediate risk of a criticality or threat to the safety of workers or the public as a result of this event. The amount of 235-U present in the columns was less than the minimum critical mass of approximately 800 grams. However, with the degradation of one IROFS and only one remaining, double contingency could no longer be assured.
"III. NOTIFICATION REQUIREMENTS: BWXT is making this 1 hour report in accordance with 10 CFR 70, Appendix A, (a)(5) - Loss of controls such that only one item relied on for safety, as documented in the Integrated Analysis Summary, remains available and reliable to prevent a nuclear criticality accident, and has been in this state for greater than eight hours.
"IV. STATUS OF CORRECTIVE ACTIONS: An investigation of the root causes of this event is ongoing. Corrective actions will be determined as a result of the investigation."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor |
Event Number: 44314 |
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN WELLS
HQ OPS Officer: STEVE SANDIN |
Notification Date: 06/23/2008
Notification Time: 15:07 [ET]
Event Date: 06/23/2008
Event Time: 14:20 [EDT]
Last Update Date: 06/23/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION |
Person (Organization):
WAYNE SCHMIDT (R1) |
| 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
OFFSITE NOTIFICATION DUE TO MINOR OIL SPILL
"Oil spill detected in outfall structure of joint operating units IP2 and IP3. Oil pool contained by partial boom in place at outfall structure. Slight rainbow sheen detected after outfall structure in Hudson River."
The source of the leak is unknown. The licensee has made arrangements for remediation and has informed the U.S. Coast Guard National Response Center, State of New York and the NRC Resident Inspector. |
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