| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/07/2015 - 08/10/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51276 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: AMERICAN PIPING INSPECTION, INC
Region: 4
City: TULSA State: OK
County:
License #: OK-27438-02
Agreement: Y
Docket:
NRC Notified By: LIBBY McCASKILL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/30/2015
Notification Time: 09:48 [ET]
Event Date: 07/30/2015
Event Time: 08:30 [CDT]
Last Update Date: 07/30/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Category 2 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIOGRAPHY TRUCK (WITH CAMERA) STOLEN AND RECOVERED
The following report was received from the State of Oklahoma via e-mail:
"At about 0830 [CDT] American Piping Inspection, Inc., [license] OK-27438-02 (Tulsa, OK) reported to [the State of Oklahoma] that one of their radiography trucks was stolen and that there was a radiography camera on board. The truck has GPS and the company had tracked the truck to North Garnett Street in Tulsa, OK and the police were enroute.
[At approximately 0930 CDT], "the radiography camera was recovered by the company [American Piping Inspection, Inc]."
The thieves were in the truck when the police arrived. The thieves departed the scene on foot and were not apprehended. There was no apparent damage to the truck or the camera.
Device Model Number: Spec. G-60, containing 100 curies of IR-192.
THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 51277 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NEA BAPTIST MEMORIAL HOSPITAL
Region: 4
City: JONESBORO State: AR
County:
License #: ARK-0504-0212
Agreement: Y
Docket:
NRC Notified By: STEVE E. MACK
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/30/2015
Notification Time: 17:26 [ET]
Event Date: 07/29/2015
Event Time: 09:00 [CDT]
Last Update Date: 07/30/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Category 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIOACTIVE SHIPMENT DELIVERED TO WRONG ADDRESS
The following information was received from the State of Arkansas via email:
"The Arkansas Radiation Control Program is making this immediate notification under 10 CFR 20.2201(a)(1)(i) and Arkansas Regulations RH-1501.c.1.A.
"On July 30, 2015, at 1349 [CDT], NEA Baptist Memorial Hospital, in Jonesboro, Arkansas Radioactive Material License Number ARK-0504-02120, reported that an Iridium-192 sealed source, approximately 10 Curies had been delivered to the wrong address. The source was in an unsecured location for approximately 23.5 hours. The source had been delivered by [common carrier] at 0900 [CDT] on July 29, 2015, to a clinic of a similar name as the hospital but at the wrong address. The source was delivered to the therapy department through the Hospital's receiving department this morning at 0830 [CDT].
"This concludes the available information at this time. The Licensee is investigating this event. The Arkansas Radiation Control Program continues to investigate this event under Arkansas Event Number AR-2015-010."
THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL
Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 51278 | Rep Org: WA OFFICE OF RADIATION PROTECTION
Licensee: KLEINFELDER, INC.
Region: 4
City: Redmond State: WA
County:
License #: WN-I0475
Agreement: Y
Docket:
NRC Notified By: CRAIG LAWRENCE
HQ OPS Officer: DANIEL MILLS | Notification Date: 07/30/2015
Notification Time: 18:18 [ET]
Event Date: 07/30/2015
Event Time: [PDT]
Last Update Date: 07/30/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following was received from the State of Washington via email:
"A Troxler 3440 gauge used by Kleinfelder, Inc., license number WN-I0475, fell from the back of a truck onto the middle of the runway at Seatac airport. The only sign of damage was to the circuit board. The source rod was undamaged and still works. Reporting requirement WAC 246-221-250(2)(f)(ii) - Damage affects the integrity of the radioactive material or its container."
The gauge contains 10 mCi of Cs-137 and 50 mCi of Am-241/Be. The damage is attributed to a failure to block and brace equipment.
Washington Incident Number WA-15-026 |
| Agreement State | Event Number: 51281 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: APPLIED INSPECTIONS SYSTEMS, INC.
Region: 4
City: BENTON State: AR
County:
License #: PA-1467
Agreement: Y
Docket:
NRC Notified By: DAVID J. ALLARD
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/31/2015
Notification Time: 17:02 [ET]
Event Date: 07/31/2015
Event Time: [CDT]
Last Update Date: 07/31/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - INABILITY TO RETRACT A RADIOGRAPHY SOURCE
The following information was received from the Commonwealth of Pennsylvania:
"On July 31, 2015, the licensee reported a disconnected radiography source at a work site in New Milford Township, Pennsylvania. A secure and restricted area around the source has been established, limiting potential public radiation exposure to below the 2 millirem in any one hour 'unrestricted area' limit.
"Source: lridium-192 (lr-192)
"Activity: 68 curies
"The license has informed the Department [PA DEP Bureau of Radiation Protection] they will keep the source secure and shielded until the radiography device manufacturer arrives. They are expected be onsite at approximately 0300 [EDT] on August 1st. A full report is expected within 15 days. A Southeast Regional Office Radiation Protection staff radiological health physicist has already been onsite to perform a reactive inspection and validate the licensee's actions. More information will be provided as received.
"Event Report ID No.: PA150021" |
| Part 21 | Event Number: 51291 | Rep Org: ALPHA-OMEGA SERVICES, INC
Licensee: ALPHA-OMEGA SERVICES, INC
Region: 4
City: BELLFLOWER State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TROY HEDGER
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/05/2015
Notification Time: 19:02 [ET]
Event Date: 08/04/2015
Event Time: [PDT]
Last Update Date: 08/07/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RAY AZUA (R4DO)
PART 21 MATERIALS (EMAI)
| Event Text PART 21 - POTENTIAL RADIOACTIVE MATERIAL TRANSPORT PACKAGING SHIELDING FAILING TO COMPLY WITH 10CFR71.47 AND/OR 10CFR71.51
The following information is a summary that was excerpted from a facsimile received from Alpha-Omega Services, Inc.:
"Pursuant to 10CFR 21.21 (d)(3)(ii) Alpha-Omega Services, Inc. [AOS] is providing the USNRC with written notification of the identification of a potential failure to comply. The following information is required per 10CFR 21.21 (d)(4):
"Name and Address of the individual or individuals informing the Commission. Troy Hedger, President, Alpha-Omega Services, Inc., 9156 Rose Street, Bellflower, CA 90706
"Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. AOS Document Number FM9054, Rev. H, Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages (Revision H, December 30, 2012; Docket No. 71-9136) Model AOS-100A Package, USA/9316/B(U)-96 (Certificate of Compliance #9316)
"Nature of the defect of failure to comply and the safety hazard which is created or could be created by such defect of failure to comply. There is a potential issue that shielding fails to comply with 10CFR 71.47 and/or 10CFR 71.51 (a)(2). This is not a 'defect' of the package, but rather an un-analyzed condition that could lead, if credible, to a safety hazard. DAHER-TLI Engineering Services notified AOS via telephone conversation on July 28, 2015 that there is a possible discrepancy in the original SAR shielding calculations originally performed. The potential discrepancy was discovered in conjunction with the independent preparation of a DAHER-TLI symposium paper that they are working on for presentation for future use of the AOS Cask family products. Specifically, DAHER-TLI observed that the AOS SAR does not analyze the radiation levels on the exterior of the package when a point source is located in a corner of the cask cavity.
"In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part. Currently, four (4) AOS-100A packages have been fabricated and three (3) were certified for use prior to August 4, 2015; one (1) is currently not in service. There are two (2) AOS-050 packages which are on hold for completion of fabrication activities. The following are the locations of the active units: AOS - Bellflower, CA, Serial no. AOS-100A-0001 (not currently in service); Elekta - Nordion Ottawa, Canada, Serial no: AOS-100A-0002; AOS - GE Vallecitos Sunol, CA, Serial no: AOS-100A-0003; Elekta - Nordion Ottawa, Canada, Serial no: AOS-100A-0004"
* * * UPDATE FROM TROY HEDGER TO JOHN SHOEMAKER AT 0954 EDT ON 8/7/15 * * *
The following update information is a summary that was excerpted from a facsimile received from Alpha-Omega Services, Inc.:
"As of August 6, 2015. responsible personnel for the owner/users of the AOS Packages have been notified in writing, as follows:
Elekta AB
GE-Hitachi
International Isotopes, Inc.
Nordion
Source Production and Equipment Co., Inc.
"Based on our initial evaluation, AOS has initiated CAPA No. FM9016.1-082015-001 for providing corrective action relating to the above-identified subject. A 10CFR Part 21 Applicability Form (re. FM9015.2-082015-001) has also been prepared and is currently under evaluation. The CAPA identifies the issue and begins the internal investigation process to determine the cause and to identify corrective action(s); this investigation is currently in progress.
1. AOS has initiated a Part 21 evaluation to determine applicability.
2. In parallel, AOS has contacted the NRC to inform the project manager of the concern; and to seek guidance/advice as to the direction that this evaluation needs to proceed.
3. Assuming that all of the activity is condensed in a point source in the corner of the cavity is a very conservative assumption.
4. In reality there may not be a problem due to self-shielding and distributed activity; i.e., it is very unlikely to have all of our activity in a single source and if we did, we would constrain it to the center of the cavity.
"In parallel to this notification, AOS is notifying the owners and users of the AOS-100 package of this potential failure to comply."
For additional information, contact the following;
Troy Hedger, President
Alpha-Omega Services, Inc.
9156 Rose Street
Bellflower, CA 90706
Notified R4DO (Azua) and Part 21 Materials Group via email. |
| Part 21 | Event Number: 51298 | Rep Org: SEQUOYAH
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 1
City: SODDY-DAISY State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/07/2015
Notification Time: 15:48 [ET]
Event Date: 10/23/2013
Event Time: 12:00 [EDT]
Last Update Date: 08/07/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
ANTHONY MASTERS (R2DO)
PART 21/50.55 REACTO (EMAI)
| Event Text PART 21 - DAMAGED SURVEILLANCE CAPSULES
"In April 2015, during Sequoyah Nuclear Plant Unit 1 end of cycle 20 refueling outage, the Tennessee Valley Authority (TVA) identified that there was unanticipated damage to the 'S' and 'W' surveillance capsules that were located within the reactor pressure vessel. Inspections determined that the surveillance capsules were not contained within the intact designated baskets. TVA conducted an extensive foreign object search and recovery initiative to recover the specimen capsule contents prior to concluding the refueling outage.
"During the October 2013 Sequoyah Unit 1 refueling outage, the Westinghouse Electric Company (WEC) relocated the above referenced surveillance capsules in accordance with Westinghouse procedure MRS-SPP-2970. The procedure specified the requirements for performing specimen capsule relocations. WEC created a deviation when an inadequate procedure referenced in the applicable purchase order, which did not ensure proper seating of the sample capsule, was used at Sequoyah Nuclear Plant Unit 1.
"TVA considers the above condition to be reportable pursuant to 10 CFR 21.21 as a defect associated with a condition that, if uncorrected, could have created a substantial safety hazard."
"The NRC Resident Inspector and the vendor were notified." |
| Power Reactor | Event Number: 51300 | Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: STEVE CHURCHILL
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/07/2015
Notification Time: 19:58 [ET]
Event Date: 08/07/2015
Event Time: 13:40 [CDT]
Last Update Date: 08/07/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text DEGRADED CONDITION DUE TO PRESSURE BOUNDARY LEAKAGE ON VENT LINE WELDED JOINT
"This notification is being provided in accordance with 10 CFR 50.72(b)(3)(ii)A, Degraded Condition.
"At 1340 CDT on 8/7/15, on LaSalle Unit 2, a through-wall (welded joint) leak was identified on a 3/4 inch vent line off of the bonnet of the 2B33-F067B, 2B Reactor Recirculation Pump Discharge Valve. This condition qualifies as pressure boundary leakage, which requires entry into Technical Specification 3.4.5, Reactor Coolant System Operational Leakage, Required Action C, to be in Mode 4, Cold Shutdown, by 0140 on 8/9/15. This leakage is significantly less than 10 gpm [leak rate is 0.2 gpm] and therefore, does not meet the threshold for entry into the Emergency Action Plan. At the time of discovery, Unit 2 was in Mode 3 - Hot Shutdown, heading into Cold Shutdown for a planned maintenance outage."
This event does not affect Unit 1. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51301 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/09/2015
Notification Time: 20:15 [ET]
Event Date: 08/09/2015
Event Time: 16:27 [EDT]
Last Update Date: 08/09/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 90 | Power Operation | 90 | Power Operation | Event Text SALT SERVICE WATER SYSTEM DECLARED INOPERABLE
"On Sunday, August 9, 2015 at 1627 [EDT], with the reactor at 90 percent core thermal power (CTP), the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation Action Statement (LCO-AS) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO-AS was subsequently exited at 1653 when the temperature of SSW trended to below the TS limit.
"Under certain accident conditions, the SSW system is required to provide cooling water to various heat exchangers such as the Reactor Building Closed Cooling Water (RBCCW) and Turbine Building Closed Cooling Water (RBCCW) systems. When the inlet temperature to these supplied loads exceeds the 75 degrees F limit established in the TS, the SSW system is conservatively declared inoperable until the temperature trends below this value. This condition existed for approximately 1/2 hour. When the SSW system was declared operable, the LCO-AS was exited.
"The SSW temperature is being closely monitored and trended on a continuous basis.
"This event has no impact on the health and safety of the public.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b) (3) (v) (D) due to an event or condition that could have prevented fulfillment of a safety function."
The licensee will be notifying the Commonwealth of Massachusetts Emergency Management Agency. The licensee returned the unit to 100 percent power at approximately 2000 EDT. |
| Power Reactor | Event Number: 51302 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JEFFREY KELLY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/10/2015
Notification Time: 00:23 [ET]
Event Date: 08/09/2015
Event Time: 22:15 [EDT]
Last Update Date: 08/10/2015 | 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):
ANTHONY MASTERS (R2DO)
|
| 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 DURING TESTING
"On August 9, 2015, during the performance of Reactor Protection System Logic Matrix Testing, a reactor trip occurred. All CEA's [control rods] fully inserted into the core. Decay Heat removal is from Main Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently maintaining pressurizer pressure at 2250 psia, temperature maintaining at 532 degrees F.
"Unit 2 was unaffected and remains in Mode 1 at 100% power.
"This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the Reactor Trip and 10CFR 50.72(b)(3)(iv)(A) for the Specified System Actuation."
The plant is in its normal shutdown electrical lineup. No safety or relief valves lifted during this event. The cause of the trip is under investigation.
The licensee notified the NRC Resident Inspector. | |