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ENS 5400717 April 2019 12:52:00The following report was received via e-mail: The Department (Arizona Department of Health Services) received notification from the licensee that they dismantled 24 tritium exit signs by removing the outer glass and aluminum housing, and then releasing the glue that held the glass ampules onto the inner plastic. The licensee said they were attempting to reduce the cost of shipping the signs for disposal. The Department has requested additional information and continues to investigate the event. The Licensee is: Arizona License Number- 07-138 Banner Boswell Medical Center 10401 Thunderbird Blvd Sun City, Arizona 85351 Arizona Incident: 19-005 None of the vials were damaged and the wipe tests were all negative.
ENS 5400617 April 2019 12:22:00The following report was received via e-mail: On April 16, 2019, the licensee notified the Agency that one of its Humboldt model 5001-C moisture/density gauges (SN: 2076), containing 40 milliCuries americium-241/beryllium (SN: 47-6041) and 10 milliCuries of cesium-137 (SN: 40-6862), had been run over and damaged by a dump truck at a temporary job site in Danbury, Texas. While a density test was being performed and the cesium source was extended into the ground, a dump truck backed up into the test area. The technician had to jump out of the way. The truck tire ran over and shattered the housing on one side of the gauge. The source was retracted, with some difficulty, into its shielded position. Radiation surveys indicated the shielding was intact. However, the technician reported that the source rod could be pulled completely out of the top of the housing. With the source in the normal shielded position, the gauge was placed inside its transport case and returned to the licensee's facility. The licensee is making arrangements for repair/disposal. There were no exposures as a result of this event. More information will be provided as it is obtained in accordance with SA-300. Texas Incident: 9675
ENS 5400115 April 2019 20:12:00The following report was received via fax: Pacific Gas and Electric notified Curtiss Wright (CW) Enertech that they observed white particulate in SF-1154 fluid in three containers. The white particulate was found settled at the bottom of the containers. The fluid was dedicated and supplied by CW Enertech in November 2016 The fluid was traced back to Momentive Batch 14ELVS145. The momentive batch 14ELVS145 was previously reported by Lake Engineering Company (Ref NRC ML17212A628 and ML17128A465). The white particulates/semisolid material was identified as phenyl cyclic precipitate. The safety hazard that could be created by this defect is the blockage of snubber bleed port as reported by Duane Arnold (Ref ML070300154). This blockage could prevent the snubber from unlocking after a seismic event, thus preventing the snubber to allow for system movement during normal operations. In addition, evaluation performed by Lake Engineering Company has found that all of the solids are dissolved back into the fluid when heated to 110 (degrees) fahrenheit. With all solids dissolved, there is no potential safety hazard with this fluid. Affected sites: Fermi, Shearon Harris, Beaver Valley, Diablo Canyon, Watts Bar, Perry, and Almaraz (Spain). Curtiss-Wright point of contact: Rosalie Nava, 714-528-2301 ext 1872 See also EN 43071 dated 1/3/2007
ENS 539825 April 2019 12:19:00

EN Revision Text: FITNESS-FOR-DUTY: FALSIFIED PRE-EMPLOYMENT INFORMATION A non-licensed employee falsified pre-employment information. The employee's access to the plant has been terminated.

  • * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019. Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting. The NRC Resident Inspector has been notified. Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

ENS 539774 April 2019 15:16:00Oyster Creek NGS (Nuclear Generating Station) Tech Support Center (TSC) ventilation is not functional due to a broken belt on exhaust fan FN-843-14. The TSC ventilation system will remain non-functional until fan belt replacement can be completed. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures. This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to partial loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified.
ENS 539794 April 2019 16:50:00

The following report was received via e-mail: On April 4, 2019, the Agency was notified by the licensee that one of their radiography crews was unable to retract a source on April 3, 2019, when a jig on a ladder fell on the source tube. The crew contacted the RSO (Radiation Safety Officer). The RSO, an authorized source retriever, reported to the temporary job site in approximately 20 minutes and retrieved the source. No member of the general public received an exposure from this event. No additional information has been provided. The radiographers were to be interviewed on April 4, 2019. Additional information will be provided as it is received in accordance with SA-300. Texas Incident: 9670

  • * * UPDATE ON 4/5/2019 AT 1222 EDT FROM ART TUCKER TO MARK ABRAMOVITZ * * *

The following information was received via e-mail: On April 5, 2019, the licensee provided the following information. The device was a QSA 880D exposure device containing a 62 curie iridium-192 source. The highest exposure received from this event to any of the individuals involved was to the individual who retrieved the source. (The RSO) received 370 millirem whole body dose and his right hand received 350 millirem. No individual exceeded any exposure limits due to this event. The exposure device has been returned to the manufacturer for service and the guide tube has been taken out of service. Additional information will be provided as it is received in accordance with SA-300. Notified the R4DO (Kozal) and NMSS Events Notification (via e-mail).

ENS 539784 April 2019 15:19:00The following report was received via e-mail: On 4/3/19, during preparation to conduct maintenance on a coal chute, workers prepared to isolate a gauge from service to prevent worker exposure to the beam. It was discovered that the gauge was missing its isolation shutter. The RSO (Radiation Safety Officer) and plant personnel conducted an extensive search and investigation of the missing shutter, but it could not be located. A six-month physical inventory of the facilities devices was conducted on 3/26/19 and 3/27/19 and there was no notation of any problems with this gauge on the inventory sheets. The gauge involved is a Texas Nuclear Model 5189 with a 20 mCi Cesium-137 source. The RSO and job supervisor held a discussion and decided that they could use the shutter from another Model 5189 gauge in the vicinity. The second gauge is used in a continuously operating process line and would have the shutter open for operations. The area around the second gauge will have signage and barricades installed to safely mark the area if future work activities will take place in that location. The shutter from the second gauge was placed on the first gauge and it was tagged out for maintenance of the coal chute. The second gauge remains in the open position during operation of the second process line. The RSO contacted ThermoFisher Scientific and discovered that because of the age of the gauge, replacement parts could not be obtained. They were provided with a list of third-party service providers to assist with proper repair or removal and disposal of the gauge. The licensee will explore options and inform ODH (Ohio Department of Health) of the actions to be taken. Ohio Item Number: OH190005
ENS 5395525 March 2019 11:14:00At 0402 Eastern Daylight Time (EDT) on March 25, 2019, an actuation of the four Emergency Diesel Generators (EDGs) occurred. At the time of the event, Unit 1 was in Mode 1 at approximately 100% power and Unit 2 was in Mode 4 at 0% power. Unit 2 was in the process of aligning the electrical distribution system to power the emergency buses via the Unit Auxiliary Transformer (UAT) in accordance with plant procedures. It was determined that a fault occurred on the power path between the 230 KV switchyard and the UAT. This caused a main generator differential lockout relay to actuate; thereby starting the EDGs. All emergency buses remained energized from offsite power via the Startup Auxiliary Transformer and, therefore, the EDGs did not tie to their respective buses. The EDGs responded per design to this event. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuation of the EDGs. Due to the shared configuration of the Brunswick electrical system, both Unit 1 and Unit 2 are affected. The Unit 2 main generator lockout was reset and the EDGs have been restored to standby condition. Troubleshooting activities to determine the cause of the fault are in progress. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5395324 March 2019 05:23:00At 0159 (EDT), with Unit 2 in Mode 1 at 25 percent power, the reactor was manually tripped due to degrading condenser vacuum. After the turbine was tripped, the station service electrical buses did not transfer to alternate supply resulting in loss of the condensate feedwater system and level being controlled by the RCIC system. Operators responded and stabilized the plant. Reactor water level is being maintained via the RCIC system. Pressure is being controlled and decay heat is being removed by the HPCI system in pressure control mode. Unit 1 is not affected. Additionally, an actuation of the primary containment isolation system occurred during the reactor scram. The reason for the actuation was a group II isolation signal was received on reactor water level and a group I isolation was received on decreasing vacuum. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non- emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the primary containment isolation system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5394921 March 2019 11:14:00

EN Revision Text: AGREEMENT STATE REPORT - FIXED GAUGE STUCK SHUTTER The following report was received from the state of Texas via e-mail: On March 21, 2019, the licensee notified the Agency (Texas Department of State Health Services) that during routine shutter checks on March 20, 2019, it had discovered that the shutter on one of the Ronan Model SA-1 gauges (SN: M-3824) was stuck in the open position. Open is the normal operating position for this gauge. The gauge contains a cesium-137 source with a calculated current activity of 10 milliCuries. Due to the location of the gauge, there is no increased risk of exposure. The licensee plans to replace the gauge. Texas Incident #9667

  • * * UPDATE AT 1518 EDT ON 10/14/19 FROM MATTHEW KENNINGTON TO JEFF HERRERA * * *

The following update was received from the Texas Department of State Health Services via email: Licensee contacted the Agency on October 9, 2019, to report that the vendor was successfully able to close the stuck shutter and the old source is being packaged and prepared for disposal. The gauge was replaced with a Vega SHLD-1. File is closed. Notified the R4DO (Kellar) and NMSS Events (via email).

ENS 5393515 March 2019 10:03:00The following report was received via e-mail: On 3/14/2019, NC Radioactive Materials Branch (RMB) was notified that a fixed nuclear gauge was stuck in the closed position (found that day). The reporting licensee had the vendor arrive on site, the same day, and repaired the gauge. Source Sr-90, 100 milliCuries North Carolina State Tracking ID: 190009
ENS 539136 March 2019 14:54:00The following report was received via e-mail from the state of Texas: On March 6, 2019, the licensee notified the Agency (Texas Department of State Health Services) that someone had broken into one of their vehicles at an oil well drilling site northeast of Odessa, Texas, and stole a shipping/transport container with a bottle of approximately 7 milliCuries of iodine-131 tracer material (liquid form) and a box containing radioactive waste (i.e. gloves, rags). A number of other items (computer and other equipment) were also taken. The licensee has reviewed the initial information and is of the opinion, at this time, that it appears the material was not the target of the break-in but was grabbed along with other items of value. The licensee notified local law enforcement. The tracer material was scheduled to be used late in the day on March 5, 2019, but the schedule was changed at the last minute for it to be injected the next morning. The licensee's employee left the company truck containing the material at the site overnight, the vehicle was locked. There were no workers at the site overnight. The licensee has employees searching around the well site, along the road, and other nearby areas it may have been discarded. Event Location: Approximately six miles South of Odessa, Texas. Texas Incident #9661 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
ENS 539115 March 2019 12:46:00At 05:35 Eastern Standard Time (EST) on March 5, 2019, with Unit 2 in Mode 5 at 0% power, an actuation of the Primary Containment Isolation System occurred during hydrolazing of the reactor water level variable leg instrumentation line nozzle N011B in the reactor cavity. The hydrolazing activity caused low reactor water level to be sensed on Division II of the shutdown range level instrumentation. Per design, the low level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Primary Containment Isolation System. There was no impact on the health and safety of the public or plant personnel. The Group 8 was reset and shutdown cooling was restored at approximately 05:45 EST. The safety significance of this event was minimal. Although there was a brief interruption of the shutdown cooling, the Residual Heat Removal (RHR) shutdown cooling system operation was restored in approximately 10 minutes without extensive troubleshooting or maintenance, and remained operable. The RHR shutdown cooling system is not credited in any Updated Final Safety Analysis Report Chapter 6 or 15 accidents or transients. The NRC Resident Inspector has been notified.
ENS 5393113 March 2019 08:46:00The following report was received via e-mail: On March 7, 2019, the Ohio Department of Health received a phone notification from Cardinal Health stating the first elution on 2/26/2019 from the NorthStar RadioGenix Mo-99/Tc-99m generator exceeded breakthrough limits in Ohio Administrative Code 3701:1-58-35 (10 CFR 35.204). The measured breakthrough was 0.252 microCuries Mo-99 per milliCurie Tc-99m. Cardinal Health stated this was an isolated event and all other elutions have been within the limits. The licensee is using the elution for research only; it is not for human use. Cardinal Health has contacted the manufacture to determine the cause. Ohio Event: 190004
ENS 5389423 February 2019 19:05:00Actuation of RPS (Reactor Protection System) with the reactor critical. Reactor scram occurred at 1458 (CST) on 2/23/2019 from 100% power. The cause of the scram was due to Turbine Control Valve Fast Closure. All control rods are fully inserted. Currently reactor water level is being maintained by the Condensate Feedwater System in normal band and reactor pressure is being controlled via Main Turbine Bypass valves to the main condenser. No ECCS (Emergency Core Cooling System) initiation signals were reached and no ECCS or Diesel Generator initiation occurred. The Low-Low Set function of the Safety Relief Valves actuated upon turbine trip. This was reset when pressure was established on main turbine bypass valves. The cause of the turbine trip is still under investigation. There were no complications with scram response. The licensee notified the NRC Resident Inspector. There was no maintenance occurring on the main turbine at the time of the scram.
ENS 5388821 February 2019 13:27:00The following was received from the licensee via e-mail: On 21 February 2019 the Aberdeen Proving Ground Garrison Radiation Safety Officer (RSO) notified (the Combat Capabilities Development Command Chemical Biological Center RSO) of a lost (commercial carrier shipment) containing multiple Chemical Agent Monitor (CAM) detectors. Shipment, dated November 26, 2018. On November 26, 2018, the Garrison RSO shipped a package containing multiple chemical detectors with radioactive sources. One CAM, serial # 11769, containing 10 mCi of Ni-63 which is owned by the Chemical Biological Center under NRC license 19-10306-01, was included in the package. The shipment was going to Pine Bluff, Arkansas for final waste disposal. The Garrison RSO stated that a search for the packaged had been conducted at two (commercial carrier) locations, one in Maryland and one at the Pine Bluff final destination location with no package being found. This event is related to NRC Event Number 53884. 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
ENS 5389122 February 2019 14:35:00

The following report was received via fax: Description: GE BWXT, acting on behalf of Ontario Power sent five valves back to the Flowserve facility for evaluation of the spring which could spread apart when the flapper rotates open and wedge between the valve body and flapper, creating the potential for the valve flapper to stick open. Evaluation: Shop inspections of the returned valves confirmed the potential for the spring legs to rotate outwards and potentially wedge between the flapper and seat retainer. Of the five valves evaluated, two of the valves had the spring legs rotate outward and after repeated cycles got caught between the flapper and disc; on one of the instances the spring legs prevented full closure of the flapper. If the valves have a safety-related function to isolate flow and must transfer closed, then the springs could prevent the valve from performing its safety related function. The evaluation determined the cause is an inadequate spring design which allows the spring to deflect and permit the legs to move outward. Extent of Condition: In discussion with the customer, it is believed the problem did not exist with valves originally supplied from the Worcester, Scarborough Canada facility; although this cannot be confirmed by Flowserve. It is believed the extent of condition resides with valves and replacement springs supplied from the Flowserve Raleigh, NC facility when the product line was transferred and the spring vendors changed; even though it has been confirmed that the springs supplied out of the Raleigh, NC facility comply with the product drawing requirements. The springs were first sold in valve assemblies or as replacement parts from the Raleigh facility starting in 2008. Valve Scope: The scope of impacted valves is the Worcester series 44 swing check valves. (Please note Worcester also has a series 44 three piece ball valve, which is not in the scope.) The Raleigh facility has supplied parts or valves for four Worcester series 44 swing check valves assemblies which use these springs. The drawings numbers for these valve assemblies are listed below:

   Drawing                  Valve Size             Customer
   KN44-0590             1.5 X 1 X 1.5         Bruce Power, GE BWXT & Ontario Power 
   KN44-0630             2                            Comanche Peak
   14-107362-001      1.5 X 1 X 1.5          GE BWXT
   16-118733-001      1.5 X 1 X 1.5          GE BWXT

Corrective Actions: 1) Owner's may remove the springs. The valves will check-off and seal under low pressure conditions without the assistance of the spring; this was demonstrated in shop tests using tap water pressure (approximately 60 psig) and will initiate closure when full open without the assistance of the spring.

2) Flowserve is evaluating alternate spring designs along with the possibility of adding guides to prevent the undesired spring movement. Any new design will be proof tested.

Respectfully submitted, Mark Rain, PE Product/Design Engineering Specialist Flowserve Corporation Flow Control Division 1900 S. Saunders St. Raleigh, NC 27603

ENS 5385331 January 2019 10:48:00

EN Revision Text: BOTH EMERGENCY DIESEL GENERATORS INOPERABLE DUE TO LOW AIR TEMPERATURE At 0743 (CST) on 1/31/2019, both trains of Unit 2 Diesel Generators were declared INOPERABLE due to outside air temperature exceeding the low temperature design limit for the diesel engines; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v) for an event or condition that could have prevented the fulfillment of a safety function. The Unit 2 Diesel Generators are still able to start if necessary to provide power. Additionally, multiple layers of defense in depth measures are in place to ensure safety. Prairie Island has five sources of offsite power; all of which are currently available. The Unit 1 Diesel Generators are OPERABLE and capable of being cross-connected to Unit 2. Additional equipment capable of responding to beyond design basis events is available on site providing another layer of defense in depth. Both Unit 2 Diesel Generators were returned to an OPERABLE status at 0810 on 1/31/2019 based on outside air temperature rising above the low temperature design limit with forecasted temperatures to remain above the low temperature design limit. There is no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The air temperature limit was -30 degrees Fahrenheit. Unit 1 was not affected. The EDGs were supplied by a different manufacturer with different air temperature limits.

  • * * RETRACTION AT 1340 EDT ON 03/22/2019 FROM BRIAN JOHNSON TO JEFFREY WHITED * * *

Engineering analysis performed subsequent to the event notification has determined that both Unit 2 Diesel Generators would have been able to fulfill their safety function during the period of time when the outside air temperature had exceeded the low temperature design limit. Therefore, EN# 53853 is being retracted. The NRC Resident Inspector has been notified of the event notification retraction. Notified R3DO (McCraw).

ENS 5385231 January 2019 04:23:00At 0301 (EST) on 1/31/19, with Unit 2 in Mode 1 at 100% power, the reactor was manually tripped due to icing conditions requiring the removal of 4 Circulating Water Pumps from service. The trip was not complex, with all systems responding normally post-trip. 21 CFCU (Containment Fan Cooler Unit) was inoperable prior to the event for a planned maintenance window and did not contribute to the cause of the event and did not adversely impact the plant response to the trip. An actuation of the Auxiliary Feedwater System occurred following the manual reactor trip. The reason for the Auxiliary Feed Water System auto-start was due to low level in a steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feed Water System. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The icing condition was described as frazil ice. Unit-1 reduced power to 88% because one circulating water pump was shutdown.
ENS 5382413 January 2019 17:49:00

EN Revision Text: HIGH PRESSURE CORE SPRAY SELF TEST FAILURE On January 13, 2019, the Self Test System reported a fault associated with the logic system for the High Pressure Core Spray (HPCS) high reactor water level closure function that could prevent the system from performing its safety function. The HPCS system was subsequently declared inoperable with actions taken per LCO (Limiting Condition for Operation) 3.6.1.3 to close and deactivate the 1E12-F004 valve, a primary containment isolation valve. Since HPCS is an emergency core cooling system and is a single train safety system, this condition is reportable under 10 CFR 50.72(b)(3)(v)(D) 'Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.' The NRC Resident Inspector has been notified. HPCS is in a 14-day technical specification LCO action statement.

  • * * RETRACTION AT 1908 EST ON 3/7/19 FROM JAMES FORMAN TO JEFF HERRERA * * *

Testing of the logic system load driver card for the High Pressure Core Spray (HPCS) high reactor water level closure function was completed both on site and at General Electric Hitachi (GEH). This testing determined the cause of the self-test system fault report was limited to the self-test portion of the load driver card and did not impact the ability of HPCS system to perform its specified safety function. Based on the testing results, this event is not reportable under 10 CFR 50.72(b)(3)(v)(D), 'Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.' Therefore, EN 53824 is being retracted. The NRC Resident Inspector has been notified. Notified the R3DO (Hills).

ENS 5382211 January 2019 10:07:00

EN Revision Text: FITNESS FOR DUTY A non-licensed employee disclosed that he had previously used illegal drugs. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.

  • * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019. Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting. The NRC Resident Inspector has been notified. Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

ENS 5380626 December 2018 11:38:00(At 0930 MST on 12/24/18, a) Technologist went to screw the bottom of the pig on and had difficulty getting the bottom screwed on. The vial (containing approximately 272 mCi of Tc-99m) then slipped from the pig and the technologist's hands and dropped to the floor and broke. The technologist was wearing (Personal Protective Equipment) PPE in the form of gloves. Her shoes, clothing were removed and placed in a sealed bag to decay in the hot waste area. Initial reading from the sealed bag was 0.8 mR/hr. PPE was worn and the spill was covered with absorbent material. To prevent the spread of contamination movement of staff was limited. A witness was not contaminated during the incident as she was more than 10 feet from the hot lab and her personal survey results were 0.05 mR/hr which is equivalent to the background of the room. The contaminated personnel's skin readings post decon were 0.1 mR/hr at skin level on her leg. The spill was sprayed with Radiacwash and the contaminated absorbent material was placed in a sealed bag, labeled with date and radioactivity and placed in the hot waste storage area to decay. The spill was contained within the nuclear medicine hot lab, a sign was posted to close the room and secure the area to prevent entry. Final survey and wipe tests were completed on 12/26/2018 at 1100 (MST). The (Radiation Safety Officer) RSO was notified on 12/24/2018 at 0952 (MST). The RSO talked to the Avera St. Luke's Director of Nuclear Medicine to ensure we are following the correct protocol. The RSO was notified on 12/26/2018 of the final survey and final wipe tests performed, and permission was given to return to work in the area.
ENS 5380421 December 2018 15:55:00

EN Revision Text: AGREEMENT STATE REPORT - RADIOACTIVE SOURCE FAILS LEAK TEST The following report was received via e-mail: A routine leak test at the Swedish Cancer Institute found a leaking Cs-137 e-vial source in the Physics Lab. The initial leak test was taken 12/19/2018 and analyzed on 12/20/2018. It revealed an activity of approximately 10 nanoCuries, and additional confirmation tests found contamination above the regulatory threshold for a leaking source. The source was immediately removed from service, contained within multiple non-permeable barriers, and placed into a larger pig while it is being held for disposal. Surveys of the original storage pig and the hot lab where the source was utilized found no removable contamination and there was no personnel contamination detected. The RSO (Radiation Safety Officer) was notified of the positive results the morning of 12/21/2018 and provided notification to DOH (Washington State Department of Health) at 1114 PST on 12/21/2018.

  • * * UPDATE ON 01/17/2019 AT 1201 EST FROM ANDREW HALLORAN TO JEFFREY WHITED * * *

The following report was received via e-mail: A leaking sealed source was discovered at The Swedish Cancer Institute during periodic leak tests performed by the health physics staff. The source (MED3550 Gamma Reference Standard, SN 11345, Cs-137, initial activity 209.6 micro-Ci, reference date 8/1/2001) was used in the A Level Physics Lab as part of routine radiation oncology operations. The source was initially received by Swedish 12/6/2007. The sample was collected on 12/19/2018 using an alcohol wipe, and analyzed on 12/20/2018 using a Ludlum 261 single channel analyzer coupled with a NaI well detector. The system was set to detect the 662 keV photon energy for Cs-137, with a calculated efficiency of 11.71 percent. The result of the wipe test analysis was a removable activity of 9.92 Nano-Ci, above the 5 Nano-Ci threshold for a leaking source. After the RSO was notified of the positive result on 12/21/2018, the source was immediately removed from service, contained within multiple non-permeable barriers, and placed into a lead pig. The pig is currently being stored in the Radiation Safety Office Lab awaiting disposal. Wipes of the A Level Physics Lab source storage cabinet and all surfaces of the pig used to house the source when it was in service yielded no detectable removable contamination. After reviewing the final report of the licensee, this event is now closed as of 1/3/2018. DOH will verify that the source has been disposed of during the next routine inspection of the licensee. Washington Event Report ID: WA-18-031 Notified R4DO (Drake) and NMSS Event Notification (e-mail).

ENS 5379820 December 2018 13:56:00As part of the reviews following the August 3rd 2018 canister downloading event (EN#53605), SCE has identified events where the HI-PORT may have been operated outside the analytical assumptions of the seismic analysis while transporting a loaded canister in the HI-TRAC. SCE has decided to conservatively report this issue. The HI-PORT is subject to requirements in the Certificate of Compliance that result in seismic restrictions on center of gravity and proximity to structures that could adversely affect the function of the HI-PORT along the haul route. SCE has concluded that during previous movements of loaded spent fuel canisters during 2018, the HI-PORT likely exceeded these procedural and analytical limits in some cases. Additional analysis is underway that may conclude that damage to the HI-PORT would not occur under these conditions. Nevertheless, this situation is being reported in accordance with 10CFR72.75(d)(1) for an important to safety component that was disabled or failed to function. There was no seismic event that resulted in damage to the HI-PORT during the fuel transfer campaign. All 29 spent fuel canisters are currently in safe storage within the ISFSI. NRC Region IV will be notified as SONGS does not have a NRC Resident Inspector.
ENS 5379013 December 2018 15:03:00

EN Revision Text: AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA LOST BY COMMERCIAL CARRIER The following report was received from the state of Florida via e-mail: Received a call from Versa Integrity Group to report a missing Ir-192 radiography camera. The device was shipped from Sanford, Florida via (commercial carrier) on 11-29-18 in route to Corpus Christi, Texas, but never arrived. The last location that (the commercial carrier) can confirm the location of the package was Memphis, Tennessee. (Source information - model: A424-9, S/N: 62109G). The camera had a 330 GBq Ir-192 source. The licensee contacted the commercial carrier on 12-10-18, to inquiry about the shipment and was told it was delayed. The licensee recontacted the commercial carrier on 12-13-18 and was told the package could not be located. Florida Incident: FL18-153

  • * * UPDATE FROM ART TUCKER TO HOWIE CROUCH AT 1556 EST ON 12/13/18 * * *
The state of Texas also reported the same event since their licensee was the intended recipient. The Texas Department of State Health Services will be contacting the state of Florida about this event.

Texas Incident: 9645 Notified R4DO (Taylor) and NMSS Events Notification group (email).

  • * * UPDATE AT 1345 EST ON 12/21/2018 FROM ART TUCKER TO MARK ABRAMOVITZ * * *

The following information was received via fax: At 12:39 PM (CST) on December 21, 2018, the licensee contacted the Agency (Texas Department of State Health Services) and stated they had received an email from (the commercial carrier) stating the exposure device would be delivered to the facility in Corpus Christi by 1645 (CST) hours today. Texas Incident: I-9645 Notified the R1DO (Jackson), R4DO (Alexander) and NMSS (via e-mail).

  • * * UPDATE AT 1703 EST ON 12/21/2018 FROM ART TUCKER TO TOM KENDZIA * * *

The following information was received via fax: The licensee contacted the Agency (Texas Department of State Health Services) at 1550 hours and reported they had received the exposure device. The licensee stated they would provide additional information after they completed their investigation. Additional information will be provided as it is received in accordance with SA-300. Texas Incident: I-9645 Notified the R1DO (Jackson), R4DO (Alexander) and NMSS (via e-mail). 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 Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)

ENS 5379113 December 2018 16:12:00Braun Intertec Corporation reported an event of the inability to retract a 1.44 TBq (39 Ci) Ir-192 sealed source (QSA Global, Inc. Model A424-9, SN 67476) which occurred at a temporary job site near Belfield, ND at approximately 4:02 pm CST on December 12, 2018. While performing radiography using a QSA Global, Inc. Model 880 Delta (SN D9541) exposure device on a pipe section resting on a stand, the pipe fell from the stand and kinked the guide tube. The radiography crew was unable to retract the source and immediately expanded the public dose boundary to an actual 2 mR/hr distance and maintained continuous surveillance and contacted their RSO for guidance. The RSO arrived on site the same day at approximately 8:45 pm CST and completed the source retrieval at approximately 9:45 pm CST. The sealed source was successfully retrieved into the exposure device. The maximum exposure readings from the direct reading exposure devices of the radiography crew and retrieval personnel was 3 mR. The crank assembly and guide tube were taken out of service. Visual inspection noted no defects to the pigtail assembly. North Dakota Event: 180003
ENS 537795 December 2018 20:07:00At 1539 (CST) December 5, 2018, with Unit 1 at 100 percent power, the reactor was manually tripped due to degrading condenser vacuum. The trip was uncomplicated with all systems responding normally, post-trip. An actuation of the auxiliary feedwater system occurred during the manual trip. The auxiliary feedwater system automatically started as designed when the valid actuation signal was received. Operations stabilized the plant in mode 3 (hot standby). Decay heat is being removed by atmospheric dump valves. Unit 2 is not affected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The loss of condenser vacuum resulted because one of two circulating water pumps was running and its discharge valve shut. The cause for the valve shutting is under investigation. There is no primary to secondary leakage. The licensee notified the NRC Resident Inspector
ENS 537785 December 2018 17:06:00At 1010 (EST) on December 5, 2018, Secondary Containment differential pressure exceeded the Technical Specification Surveillance Requirement of greater than or equal to 0.25 inches of vacuum water gauge. This condition existed for approximately 3 minutes before the differential pressure was restored to normal when the Standby Gas Treatment system was manually initiated. This event was caused by a trip of the service air compressor 39AC-2A. The loss of instrument air pressure caused Reactor Building ventilation to isolate and raise Secondary Containment differential pressure. The instrument air pressure was restored when 39AC-2A was isolated and the two backup air compressors started. This condition did not impact the leak tightness of Secondary Containment or the ability of the Standby Gas Treatment system to establish and maintain the required differential pressure. When Secondary Containment did not meet the Technical Specification Surveillance Requirement 3.6.4.1.1 for differential pressure, the Limiting Condition of Operation (LCO) was not met. Therefore, Secondary Containment was inoperable. This event is being reported under 10 CFR 50.72(b)(3)(v)(C). The licensee notified the NRC Resident Inspector.
ENS 537662 December 2018 17:52:00

The following information was received via e-mail: On December 2, 2018, the Agency (Texas Department of State Health Services) was notified by the licensee's radiation safety officer (RSO) that they had admitted a patient at 2210 hours (CST) on December 1, 2018, complaining about a sickness. At 0000 hours on December 2, 2018, the patient gave the treatment nurse a piece of paper from a hospital in Houston, Texas, stating this individual had received a thyroid treatment with iodine-131 on November 29, 2018. At this time the patient was moved to an appropriate room. At this point the patient had been in four different rooms. The four rooms were surveyed for contamination. No contamination was found in the first room surveyed. In the second room, only paperwork was found to be contaminated and the paperwork was disposed of. The third room was a bathroom. Seven tiles in the bathroom were found to be contaminated and were removed. The fourth room was also a bathroom. In this room, the toilet was found to be contaminated. The RSO stated the first survey performed with a 14C rate meter with a pancake GM probe read greater than 20 millirem per hour (mR/hr) (maximum reading on the instrument, i.e. pegged high). A second survey performed with a second instrument indicated a dose rate of 60 mR/hr (on scale reading). The RSO was asked if the reading was in mR/hr or microrem per hour. The RSO confirmed the reading was 60 mR/hr at one foot from the top of the bowl. The RSO stated the room has been isolated and posted. The RSO stated all contaminated laundry had been removed from the areas and placed in the appropriate storage location. The RSO stated the second bathroom would be isolated for an extended period of time. The RSO had been at the facility since 0000 hours so he was headed home for rest. The RSO stated he would provide additional information on Monday December 3, 2018. Additional information will be provided as it is received in accordance with SA-300. Texas Incident: 9641

  • * * UPDATE ON 12/03/18 AT 1843 EST FROM KAREN BLANCHARD TO BETHANY CECERE * * *

The following update was received from the State of Texas via e-mail: The licensee's RSO informed the Agency that during its follow-up survey of the bathroom in which they had removed contaminated floor tiles, a single spot was found with readings of 5 mR/hr on the toilet near its water supply line. Therefore, access to this bathroom will also remain restricted. The patient was released from the emergency room late in the day on 12/02/2018. More information will be provided as it is received in accordance with SA-300. Notified R4DO (Gaddy) and NMSS Event Notification Group (by email).

ENS 5376330 November 2018 16:08:00

EN Revision Text: PART-21 - EMERGENCY DIESEL GENERATOR EMD FUEL AND SOAKBACK PUMPS LOOSE BOLTS The following report was received via fax: ESI (Engine Systems, Inc.) was notified by a nuclear customer of two instances where a bolt was found loose or backed out of the cover of an EMD (Electro-Motive Diesel) engine driven fuel pump P/N 8410219. Following notification, ESI inspected remaining pumps in inventory and found instances where one or more of the pump cover bolts were loose or lightly torqued. EMD fuel pump, P/N 8410219, is commonly used on all 12, 16, and 20-cylinder EMD model 645E4 and E4B engines. The pump is either mechanically driven from the engine (via the scavenging tube oil pump) or motor driven (as in the case of a backup/redundant fuel pump). The pump transfers fuel oil from the day tank to the fuel injectors to support fuel combustion. Without the supply of fuel oil, the diesel engine is unable to produce power which adversely affects the safety-related operation of the emergency diesel generator set. ESI recommends inspecting the bolts of all pumps for proper bolt tightness. Use a torque wrench and ensure all bolts are tightened to 108 to 120 in-lbs (12 to 13 Nm). This activity should be performed at the earliest opportunity; however, it is more important for the inspection to be performed on newly installed pumps. It is expected that for pumps supplied with low bolt torque, if a problem were to develop it would be in the form of a fuel leak soon after installation. For pumps that have been successfully installed for several months or years with no detectable leakage, it is less likely that bolt(s) are loose and therefore the urgency of this inspection is reduced. Points of Contact: (252) 977-2720

   Dan Roberts, Quality Manager
   John Kriesel, Engineering Manager

Affected Plants:

   Region 1: Nine Mile Point, Fitzpatrick
   Region 2: Brown's Ferry, Savannah River, Oconee, St Lucie, Surry Power Station, Turkey Point, Watts Bar 
   Region 3: La Salle, Point Beach, Dresden, Clinton
   Region 4: Grand Gulf, River Bend, Energy Northwest,, Entergy Operations Inc - Arkansas, Omaha Public Power - Fort Calhoun
  • * * UPDATE FROM DAN ROBERTS TO JEFFREY WHITED AT 1202 EST ON 12/21/18 * * *

The following was received via fax: Revision 1 involves updates on page 2 of the 10 CFR Part 21 Report which include: In item (iv), added reference to F4B engine application. Revised Item (vii): For all affected customers: ESI recommends inspecting the bolt tightness for all pumps. The recommended bolt torque is 108 to 120 in-lbs (12 to 13 Nm). After verifying bolt torque, a shaft freeness check is recommended. The pump shaft should be capable of being rotated by hand in either direction. Due to the small shaft size, this check is commonly performed with a small crescent wrench or with the coupling half installed on the shaft. Inability to rotate by hand indicates loss of end clearance and the pump should be returned to ESI for rework or replacement. Note: For installed pumps where it is not possible to check shaft freeness, ESI recommends using a reduced bolt torque of 60 to 70 in-lbs (7 to 8 Nm). This is sufficient to ensure the bolts are snug while safeguarding against loss of end clearance that would otherwise go undetected. This activity should be performed at the earliest opportunity; however, it is more important for the inspection to be performed on newly installed pumps. It is expected that for pumps supplied with low bolt torque, if a problem were to develop it would be in the form of a fuel leak soon after installation. For pumps that have been successfully installed for several months or years with no detectable leakage, it is less likely that bolt(s) are loose and therefore the urgency of this inspection is reduced. For ESI: The dedication procedures for these pumps have been revised or are being revised to add a step to verify proper bolt torque. This will be completed prior to any future shipments. In addition, ESI is in correspondence with the pump manufacturer to implement corrective actions to prevent reoccurrence. Notified R1DO (Jackson), R2DO (Bonser), R3DO (Stone), R4DO (Alexander), and Part 21/50.55 Reactors (e-mail).

ENS 5375124 November 2018 21:27:00At 1420 (EST) on November 24, 2018, operators discovered that a door was blocked open creating a breach of the auxiliary building secondary containment enclosure (ABSCE) boundary that exceeded the allowed ABSCE breach margin (of three minutes). As a result, Unit 1 entered Technical Specification Limiting Condition of Operation (LCO) 3.7.12 Condition B for two trains of Auxiliary Building Gas Treatment System (ABGTS) inoperable due to an inoperable ABSCE boundary in MODE 1, 2, 3, or 4, and both Units entered Condition E for one required ABGTS train inoperable with fuel stored in the spent fuel pool. In MODES 1, 2, 3, and 4, the analysis of the loss of coolant accident (LOCA) assumes that radioactive materials leaked from the Emergency Core Cooling System are filtered and absorbed by the ABGTS. For the fuel handling accident, the analysis assumes that the ABSCE boundary is capable of being established to ensure releases from the auxiliary and containment buildings are consistent with the dose consequence analysis. The event is reportable in accordance with 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of the safety function of structures or systems that are needed to: (C) control the release of radioactive material and (D) mitigate the consequences of an accident. No actual LOCA or fuel handling accident occurred while both trains of ABGTS were inoperable. The condition had no impact on the health and safety of the public. The NRC Resident Inspector has been notified. This situation occurred because of maintenance activities. A breeching permit had been initiated however, the required personnel to ensure the door could be closed within the required three minutes were not assigned. The door was closed approximately 15 minutes after the situation was noticed.
ENS 5374015 November 2018 13:13:00The following report was received via e-mail: On Wednesday, November 14, (the University of Miami Radiation Safety Officer (RSO)) received an Occupational Exposure Report from Mirion Technologies indicating that for wear dates July 1 through July 31, 2018, x-ray technologist (redacted) received the following doses: Deep: 8328 mR, Eye: 8328 mR, and Shallow: 8328 mR. Upon interviewing Mr. (redacted), in the presence of his supervisor, Mr. (redacted) indicated that he had a therapeutic Nuclear Medicine procedure for hyperthyroidism during the month of July in one of our facilities. Upon review of his medical records it was confirmed that Mr. (redacted) received 24 microCuries of iodine-131 for an uptake scan on July 10, 2018, and a therapeutic dose of 28.9 mCi of iodine-131 on July 17, 2018. It was noted that Mr. (redacted) wears his dosimeter high on the collar of his scrubs, very close to the area overlying his thyroid and continued to wear it throughout the period in question. Based on this information it is (the RSO's) professional judgement that this dose does not constitute an Occupational Dose but is rather a medical dose, and he will be requesting that his dosimetry provider remove it from Mr. (redacted) Occupational (dose). Florida Incident: FL18-139
ENS 5369828 October 2018 08:57:00At 0445 (CDT), with reactor power less than 1% rated thermal power on Instrument Range Monitor (IRM) ranges 6 and 7, Clinton Power Station received an automatic Reactor Protection System (RPS) actuation. The Reactor Scram Off Normal procedure was entered and all control rods were verified to be fully inserted. The apparent cause of the scram is cold water injection causing an upscale trip of the IRMs due to Motor Driven Reactor Feedwater Pump (MDRFP) Feedwater Regulating valve 1FW004 valve coming off the full shut seat momentarily. All systems responded appropriately following the scram and the plant is currently stable. Clinton Power Station will be proceeding to Mode 4 to support the planned Maintenance Outage. The NRC Senior Resident Inspector has been notified.
ENS 5384323 January 2019 13:49:00The following report was received via fax: On 11/28/2018 the Department (New York State Department of Health) was notified of a missing I-125 localization seed (Best Medical International, Inc., Model 2301, Activity: 186 microCuries) at Roswell Park Cancer Institute in Buffalo, New York. Two lodine-125 breast localization seeds were placed into a patient on September 20, 2018 and removed on September 28, 2018. One seed was placed in a specimen container with the specimen, and the other seed was placed into a separate specimen container. Surgery has documentation that both seeds were sent to Pathology in separate containers; however, only one was returned to the Nuclear Medicine Department on October 4, 2018. The RSO was informed on October 5, 2018. The facility conducted searches and surveys of the Surgery, Pathology, Nuclear Medicine and Environmental Services areas, but could not locate the missing seed. Trash and regulated medical waste were also surveyed and inspected. Searches and surveys were repeated, but the seed was not found. It is believed that the seed was disposed of as regulated medical waste or in regular trash. New York State ID: NYSDOH - 18-04 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
ENS 5400316 April 2019 15:27:00The following report was received via e-mail: On January 11, 2018, FHL Industries, LLC, acquired Replogle Hardwood Flooring out of bankruptcy. The new owners were unaware of a generally licensed hazardous testing device from previous ownership. During a search of the facility during April 2018, FHL concluded the device was missing. FHL has no intentions of acquiring another radioactive testing device. Isotope and activity: Am-241, 0.03 mCi; Cm-244, 13.0 mCi Manufacturer: Asoma Instruments Model: 100 SN: 1537 Tennessee Event: TN-18-089 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
ENS 5380321 December 2018 14:46:00The following is a synopsis of the report received via email: The quick connect fitting on the guide tube came apart when the source was being cranked out. When the source was cranked out beyond where the end of the guide tube was supposed to be the technicians stopped and tried to crank the source back into the camera. The source rod became stuck because the control cable had become entangled. The RSO (Radiation Safety Officer) was later able to disconnect the source's pigtail, unkink the control cable, reconnect the guide tube, and reconnect the control cable to retrieve the source. The maximum doses received were 114 mRem whole body and 260 mRem to the right hand. Camera: model SPEC-300 with model G-70 source assembly Source: 88 Ci Co-60
ENS 5321014 February 2018 18:04:00A non-licensed contract supervisor had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5320713 February 2018 13:28:00The following report was received via e-mail: The licensee notified the Department (South Carolina Department of Health and Environmental Control) at 1115 (EST) on February 13, 2018, that it had discovered a broken shutter on one of its gauges during the six-month shutter checks on February 12th. The gauge is a Berthold Model LB7440D containing 100 mCi of Cs-137. Source serial number is N-A04538DZ242A and source holder serial number is 2179. The gauge is still in service and a radiation reading of 2 mR/hr was observed on the surface of the gauge. There is no radiation exposure risk to personnel.
ENS 5320412 February 2018 13:47:00

EN Revision Text: UNANALYZED CONDITION FOR TORNADO GENERATED MISSILES On February 12, 2018, during evaluation of protection for Technical Specifications (TS) equipment from the damaging effects of tornado generated missiles, Dresden Station identified a non-conforming condition in the plant design such that specific TS equipment is considered to not be adequately protected from tornado generated missiles. Tornado generated missiles could strike the Unit 2, Unit 2/3, and Unit 3 Emergency Diesel Generator main fuel oil tank vents. This could result in crimping of the vents, which would affect the ability of the main fuel oil tanks to perform their function if a tornado would occur. This condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B) as a condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. This condition is being addressed in accordance with NRC enforcement guidance provided in Enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion' per Enforcement Guidance Memorandum EGM 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents. The NRC Resident Inspector has been informed of this notification.

  • * * RETRACTION ON 10/11/19 AT 1031 EDT FROM SAMANTHA COSENZA TO BETHANY CECERE * * *

The purpose of this notification is to retract event notification 53204 made on February 12, 2018, for Dresden Station. Additional review determined that the current design of all three Emergency Diesel Generators and associated Main Fuel Oil Storage Tanks Vents is consistent with the licensing basis for Dresden Station. There was no non-conformance of Dresden's tornado missile protection design, and the EDGs were operable at the time the event notification was made. Therefore, this event does not meet the criteria of 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(D). The ENS 53204 report is being retracted. The NRC Resident Inspector has been informed of this notification." Notified R3DO (Hills).

ENS 5320613 February 2018 12:57:00

The following report was received via e-mail: On February 12, 2018, the licensee notified the Agency (Texas Department of State Health Services) that one of its fixed nuclear gauges had a shutter stuck in the closed position. The gauge is an Ohmart-Vega model SH-F1B containing 40 milliCuries of cesium-137. Arrangements have been made with a service company to make repairs. There is no risk of exposure to employees or members of the public. More information will be provided as it is obtained in accordance with SA-300. Texas Event: I-9540

  • * * UPDATE ON 3/13/2018 AT 1120 EDT FROM ART TUCKER TO DAVID AIRD * * *

The following was received via e-mail: The license number provided earlier was incorrect. The license number is L00005. Additional information will be provided as it is received in accordance with SA-300. Notified R4DO (Rollins) and NMSS Events Notification (via email).

ENS 5320813 February 2018 16:00:00

The following report was received from the Maryland Department of the Environment Radiological Health Program via email: On February 8, 2018, the Maryland Department of the Environment - Radiological Health Program was contacted by Johns Hopkins Medical Institution (MD-07-005-03) of an incident in which one researcher had received a total effective dose equivalent exceeding 5 Rem and likely an extremity dose exceeding 50 Rem. The licensee received results of a researcher's 4th quarter 2017 radiation badge readings. The researcher was conducting tracer studies using PET isotopes C-11 and F-18 in animals. The researcher has been monitored since February 2012 and has frequently used F-18 in similar studies with no problems. Use of PET isotopes in the lab has been halted pending an investigation by the licensee. The Maryland Radiological Health Program will schedule a reactive investigation. The result of the whole-body radiation badge readings (monitoring period Oct 1 - Dec 31, 2017) was:

    Deep Dose:  12,818 milliRem
    Lens of the Eye:  28,280 milliRem
    Shallow Dose:  46,206 milliRem
    Beta Dose:  33,388 milliRem

The researcher's assigned extremity ring badge was not worn during the 4th quarter of 2017. The licensee will submit a written report as required within 30 days.

ENS 531964 February 2018 12:00:00

At 0445 (EST) on February 4, 2018, Watts Bar Unit 1 entered Technical Specification 3.6.1 condition A and 3.6.3 condition A.1 and A.2 due to inoperable containment penetration thermal relief check valves 1-CKV-31-3407 and 1-CKV-31-3421 associated with one train of the Containment Incore Instrument Room Chiller system. During surveillance testing, the thermal relief check valves failed to open and pass flow as required by acceptance criteria. The two penetrations were subsequently drained and isolated in accordance with the surveillance procedure to remove any thermal expansion concerns. Technical Specification 3.6.1 was exited February 4, 2018 at 0512 once the two penetrations were drained and isolated. The purpose of the thermal relief check valves is to allow flow from an isolated penetration back into the upstream containment piping to prevent over-pressurization due to thermal expansion. Over-pressurization of an isolated containment penetration could potentially cause the penetration or both of the isolation valves to fail and provide a direct flow path to the environment from the potentially contaminated containment atmosphere under certain Design Basis Accidents. Therefore, failure of the thermal relief check valves to open could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material. This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C). NRC Resident Inspector has been notified.

  • * * RETRACTION AT 1336 EST ON 03/29/2018 FROM TONY PATE TO TOM KENDZIA * * *

The purpose of this notification is to retract ENS notification 53196 made on 2/4/2018 for Watts Bar Nuclear Plant. The previous notification reported a surveillance failure of two containment penetration thermal relief check valves that, at the time of discovery, could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material. After Engineering evaluation, it has been determined there is reasonable assurance the two thermal relief check valves (1-CKV-31-3407 and 1-CKV-31-3421) were capable of performing their specified safety function to isolate containment and act as a thermal relief device during a design basis accident. The basis of the evaluation included: 1. No maintenance activities or interactions with the check valves had occurred since last tested. 2. All surveillance testing for the valves was within required frequency. 3. The opening force for a new check valve of the same size and similar to 1-CKV-31-3407 and 1-CKV-31-3421 is 0.38 pounds. Engineering analysis has determined the minimum failure pressure of the piping systems associated with the containment penetration in question is 450 psig. If it is assumed the force applied on the check valve seat reaches 450 psig, the force applied on the seat would reach 111 pounds or 300 times the force required to open a new, clean check valve. Based on engineering judgement of previous operating experience where the pressure required to open the same stuck check valve was within a safety factor of 6 to potential equipment damage, the thermal relief check valves would have opened prior to equipment damage and thus the identified condition would not have resulted in adversely affecting the containment isolation boundary. Entry into Technical Specification (TS) 3.6.1 condition A on 2/4/2018 at 0445 has been retracted. Although not a loss of safety function, the containment penetrations associated with 1-CKV-31-3407 and 1-CKV-31-3421 remain inoperable and are being tracked by TS 3.6.3 condition A.1 and A.2. The NRC Resident Inspector has been notified. Notified the R2DO (Rose).

ENS 531952 February 2018 17:07:00

The following report was received from the State of Texas via e-mail: On February 2, 2018, the Agency (Texas Department of State Health Services) was notified by the licensee's radiation safety officer (RSO) that a nuclear gauge shutter had failed to operate. The gauge is a Vega SHLG-2 gauge containing a 4,000 milliCurie Cesium-137 source. The source is a plunger type source and it is in the exposed position. The licensee stated the unit the gauge is installed on will be shutdown in the near future and the gauge will be repaired at that time. The licensee has contracted a service provider for the repairs. The Agency (Texas Department of State Health Services) has requested additional information. Additional information will be provided as it is received. Texas Incident #: I-9537

  • * * UPDATE ON 2/5/2018 AT 1714 EST FROM ART TUCKER TO DAVID AIRD * * *

The following report was received via e-mail: The inability to fully shield the source was discovered while they (the licensee) were making preparations for maintenance on the vessel the gauge is installed on. The licensee stated there is no additional risk of exposure to its workers or members of the general public. Notified R4DO (Deese) and NMSS Events Notification (via e-mail).

ENS 531942 February 2018 13:50:00

The following report was received via email: The radiographers placed the camera on a pipe, several feet from the ground, to take a shot. They did not secure the camera to the pipe. During the crank out process the camera fell off the pipe, face first, crimping the guide tube and causing the source to become stuck. The company called their radiographer crew located in Jacksonville, FL, to assist them in the retrieval of the source. The RSO and the helper from that office are trained in source retrieval. In the meantime, the area was cordoned off and secured until assistance could arrive. The incident occurred at approximately 1216 EST and completed the source retrieval at approximately 1900 EST. The source was not damaged. The exposure device and drive cable were put out of service and sent to the manufacturer for inspection/repair. The guide tube was damaged due to the fall and was disposed. The licensee will be submitting a report within a few days with detailed information. The licensee will be in the State for the remainder of the month providing us an opportunity to do an on-site inspection. Camera: QSA Model 880 Delta Source: Ir-192, 91 Ci RSO dose: 310 mrem, Helper dose: 118 mrem

  • * * UPDATE FROM IRVIN GIBSON (VIA EMAIL) TO HOWIE CROUCH AT 1541 EST ON 3/2/18 * * *

After receiving the final report from the licensee, it was concluded that appropriate measures had been taken to limit overexposure from the source and corrective actions were set in place to reduce the likelihood of this incident reoccurring. The state of Georgia now considers this incident closed. Notified R1DO (Bickett) and NMSS Events (email).

ENS 531901 February 2018 11:59:00

Nine Mile Point unit 2 experienced an unusual event due to a small fire in the turbine building that was immediately extinguished and then reflashed. The fire was declared out at 1119 (EST), 2/1/18. The fire was caused when steam leak repair injection equipment failed and leaked onto hot piping. There was no equipment damage or impact to plant operation. The fire was extinguished by the fire brigade. Offsite assistance was not required. The fire resulted from Furmanite repair of a Moisture Separator Reheater inlet flow control valve. The unusual event will be terminated when sufficient lagging is removed to verify the extent of leaked fluid. The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

  • * * UPDATE AT 1240 EST ON 2/1/2018 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *

The unusual event was terminated at 1211 EST. The licensee notified the NRC Resident Inspector. Notified the R1DO (Janda), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

ENS 531931 February 2018 16:23:00The following notification is an excerpt from the received report: On November 30, 2017, an internal wire in a 480VAC cubicle, breaker B3424, was discovered to be terminated using incorrect size wire lugs. This deviation was identified by Monticello Nuclear Generating Plant (MNGP) electrical maintenance staff during bench testing of the cubicles in preparation for implementation of a modification. The cubicles were received by MNGP in September, 2017 from Westinghouse Electric Co. On January 26, 2017, MNGP completed an evaluation of this deviation and concluded this condition represents a significant safety hazard. As a result, this condition is a defect and is reportable pursuant to 10 CFR 21.21 (d)(4). Basic Component: Westinghouse: Eaton Breaker Cubicle Part No. 10149D92G05 On November 30, 2017, an internal wire in a 480VAC cubicle, breaker 83424, was discovered to be terminated using incorrect size wire lugs. This condition was discovered during bench testing in preparation for implementing a modification to the Control Room Ventilation (CRV) system. The wire connection was found loose and was able to be lifted off of the terminal without removing the screw. Upon further examination, the internal diameter of ring termination lugs was found to be too large, providing only a partial surface area for screw head contact. The affected lugs were on contactor coil resistor terminations internal to the cubicle. Without sufficient contact area or connection to the wiring on the resistor, control power could be lost to the contactor coil resulting in the fan V-EF-40A not starting, which would prevent proper ventilation to the room housing safety related batteries required to be operable during an accident scenario. Therefore, MNGP determined that a substantial safety hazard could have been created had the breaker cubicle been installed with the defect uncorrected. This defect was evaluated according to the station's Part 21 reporting process. The evaluation was completed on January 26, 2018 and the reporting officer was informed on January 30, 2018. Westinghouse was notified of this condition and the condition was incorporated into their corrective action program, number 100506324. The Westinghouse contact person is Adam Tokar, 724-722-6042. No further information on the vendor's corrective actions is known. MNGP entered the condition into the MNGP Corrective Action Program under 501000005918. Monticello has corrected the lugs on the installed breaker, B4423. The remaining uninstalled cubicles purchased by Monticello are being corrected in accordance with MNGP procedure MWl-8-M-4.06, Conductor Termination, prior in installation in the plant.
ENS 5316010 January 2018 02:13:00

During normal power operations at 100 percent power on Unit 2, both trains of Containment Air Return Fans (CARF) were declared inoperable at 19:28 (EST) on January 9, 2018 due to a common issue with control power fuses. The fuses potentially could not handle the in-rush current upon re-energizing the circuits. This condition resulted in a loss of a reasonable expectation that the Unit 2 Containment Air Return Fans would meet their design safety function and mitigate an accident. This loss of safety function is reportable under 10CFR50.72(b)(3)(v)(D), 8 hour report. The site entered T.S. 3.0.3 at 19:28 and exited at 20:54 when repairs to 2B CARF were completed. 2A CARF repairs are complete. There was no impact on the health and safety of the public or plant personnel. The senior NRC Resident Inspector has been notified. The licensee verified this problem does not affect unit-1.

  • * * RETRACTION AT 0939 EST ON 03/08/2018 FROM JUSTIN BLACK TO TOM KENDZIA * * *

A subsequent evaluation determined that the fuses for the Containment Air Return Fans (CARFs) would be able to perform their safety function and were operable at the time of discovery. The limiting safety condition for the fuses is the return to power following a Loss of Offsite Power (LOOP). The evaluation determined that the fuses would satisfy their safety function upon re-energizing the circuits if a LOOP occurred and would not impact the ability of the CARFs to perform their safety function. The subject fuses were replaced on January 9, 2018." The Licensee notified the NRC Senior Resident Inspector. Notified the R2DO (Musser).

ENS 531411 January 2018 12:45:00A South Texas Project Offsite Emergency Notification siren (#7) was inadvertently going off. The Matagorda County Sheriff's office notified the Emergency Response Organization at the station of the siren actuation. Station personnel are addressing the issue with the siren. The Matagorda County Sheriff's office was the only offsite agency that was contacted during this event. This notification is being made under 10CFR50.72(b)(2)(xi) as an event where other government agencies were notified. The licensee has personnel at the siren which is no longer alarming (1.5 hours after alarm notification). The licensee notified the NRC Resident Inspector
ENS 5313320 December 2017 21:22:00During review of the documentation for the 11/16/17 outage of the NOAA/NWS (National Oceanographic and Atmospheric Administration/National Weather Service) tower, it was identified that there was also record of a trouble ticket being issued on 11/19/17 for the NOAA/NWS tower. Further discussions with the National Weather Service determined that the tower did experience an outage on 11/19/17 which affected the ability to activate EAS (Emergency Alert System)/Tone Alert Radios. Final determination that the EAS/Tone Alert Radios were affected during this outage was made at 1559 (CST), which was the time that the National Weather Service sent the e-mail to the EP (Emergency Planning) Manager and EP Offsite Coordinator with notification that activation of the EAS/Tone Alert Radios was affected during the outage. This is considered to be a major loss of the Public Prompt Notification System capability, and is reportable under 10CFR 50.72(b)(3)(xiii). The transmission outage was on 11/19/2017 0853 until 1100 but CNS (Cooper Nuclear Station) was not notified until 1559 on 12/20/2017. The NRC Senior Resident has been informed
ENS 5311211 December 2017 11:06:00While operating at 97% power, the Watts Bar Unit 2 reactor was manually tripped at 0857 EST on December 11, 2017 due to multiple dropped control rods. All control and shutdown bank rods inserted properly in response to the manual reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and the Steam Dump System. The cause of the dropped rods is being investigated. The manual actuation of the Reactor Protection System (RPS) is being reported as a four hour report under 10 CFR 50.72 (b)(2)(iv)(B). The actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified for this event. No safety or relief valves lifted during this event.