Event Notification Report for July 16, 2024

EN Revision Imported Date: 7/16/2024

EN Revision Text: NON-AGREEMENT STATE REPORT - FAILED INDICATING LIGHT

The following information was provided by the licensee via phone and in accordance with Headquarters Operations Officers Report Guidance:

On November 11, 2023, at about 1330 EST, at the Cleveland Cliffs Steel Corporation in Dearborn Michigan, the licensee staff noted that the indicating light for a 1 curie Am-241 thickness gauge shutter position was malfunctioning. The light indicated open continuously even though the shutter was closing normally. Operation of the plant continued and the shutter remained in its normally open position measuring the product steel thickness. Shutter position was subsequently checked by radiation measurements to confirm that the indicating light was not indicating correctly. No abnormal exposure resulted and the vendor will troubleshoot and repair. The location of the gauge is not normally manned.

* * * UPDATE ON 11/18/23 AT 1509 EST FROM WAYNE LANGDON TO IAN HOWARD * * *

The following update was received from the licensee via email:

"Today, a Thermo Fisher Scientific technician came on site to diagnose the shutter position indicator light issue. It was found that the shutter arm flag was bad. The technician replaced the shutter arm flag with a new one and verified that the unit was properly working. No Cleveland Cliffs employees nor the Thermo Fisher Scientific technician were exposed at any time during the event."

Notified R3DO (Feliz-Adorno) and NMSS Event Notifications (E-mail).

* * * RETRACTION ON 07/15/24 AT 1430 EDT FROM WAYNE LANGDON TO KERBY SCALES * * *

The following is a summary of information provided by the licensee via phone and email:

The licensee is withdrawing the event following further analysis. The failure only affected the indicator light, and all safety devices (the shutter) continued to function normally. There was no exposure to personnel.

Notified R3DO (Nguyen) and NMSS Events Notification via email.

EN Revision Imported Date: 7/16/2024

EN Revision Text: CONTAMINATION IN RESTRICTED AREA

The following is a summary of information provided by the licensee via telephone:

On March 6, 2024, around 0600 CST, a technician found loose molybdenum (Mo-99) / technetium (Tc-99m) contamination inside a restricted area. Prior to the discovery, a production hot cell inside the restricted area had been deep cleaned as part of the regular maintenance program.

A thorough investigation of the area was conducted which revealed additional loose contamination on the lab floor. Surveys of surrounding areas did not reveal any spread of contamination outside of the restricted lab area.

Due to (1) the existing access controls, (2) personal protective equipment requirements for lab access, and (3) the absence of contamination identified by body scans of personnel exiting the lab; the licensee does not suspect any spread of contamination outside of the restricted area or personnel intake. Biological samples will be collected to confirm that no intake occurred.

The highest contamination level identified was 260 mrem/hr on contact and 2.3 mrem/hr at 1 foot. The contamination has been remediated to below licensee action levels. Overall, 2.4 mCi of Mo-99 was identified outside of the production hot cell. The 10 CFR 20 Appendix B limit for Mo-99 is 1 mCi. The licensee is investigating the root cause of this event.

* * * RETRACTION ON 07/15/24 AT 1205 EDT FROM DANEIL SZATKOWSKI TO KERBY SCALES * * *

The following retraction is a summary of information provided by the licensee via telephone:

Due to performing additional air samples and biological assays, the licensee determined that they did not exceed any thresholds, and the event is not reportable.

Notified R3DO (Nguyen) and NMSS Events Notification via email.

EN Revision Imported Date: 7/16/2024

EN Revision Text: TECHNICAL SPECIFICATION REPORTABLE OCCURRENCE

The following information was provided by the licensee via phone and email:

"In accordance with Technical Specification (TS) 6.7.2.1, a report is required to be made within 24 hours by telephone, confirmed by digital submission or fax to the NRC Operations Center if requested, and followed by a report in writing to the NRC, Document Control Desk, Washington, D.C. within 14 days that describes the circumstances associated with eight different specifications, one of which, (h), is abnormal and significant degradation in reactor fuel, cladding, or coolant boundary.

"At approximately 0900 MDT this morning, abnormal and significant degradation in reactor cladding was observed on fuel element 681E, an aluminum-clad element being inspected for removal from service. The degradation was in the form of an L-shaped hole, approximately 0.25 inches long in the upper section of the fuel element body approximately one inch from the top edge, where the upper aluminum pin and upper graphite section meet internally. It is unknown how long this damage has existed, as there is no visual record of any of this fuel since first inspected in 2003 at the VA Omaha TRIGA reactor before USGS took possession. At that point, it did not have this damage. According to the records, it was dropped during handling in 2003 when it was being unloaded from the shipping cask here at the GSTR [Geological Survey TRIGA Reactor], but no record of further inspection appears to exist. Therefore, this element may have been in the operating core for as long as 18 years in this condition, as USGS was first licensed to use it in 2006."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

No fission products were detected in the primary, pool, or on an air particulate detector. The damaged element remains in its storage location in the pool with no other mitigating measures planned in the near term.

* * * UPDATE ON 07/03/2024 AT 0927 EDT FROM JONATHAN WALLICK TO JORDAN WINGATE * * *

The following is a summary of information provided by the licensee via phone and email:

After continued fuel inspections, four additional damaged fuel elements were identified (Fuel Element 3007, Fuel Element 5952, Fuel Follower Control Rod 5767, and Fuel Follower Control Rod 5768). The damaged elements will be moved to dry storage and will not be considered for further use.

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

Inspections are approximately one third complete.

Notified NRR PM (Boyle), NPR Event Coordinator (Waugh), and USGS PM (Sutherland).

* * * UPDATE ON 7/15/2024 AT 1005 EDT FROM JONATHAN WALLICK TO ERNEST WEST * * *

"[The licensee has] additional elements to report, under license technical specification 6.7.2.1 (h):

"Fuel element 3361, stainless-steel clad: Substantial cladding damage, but not an apparent breach. It has a severe scratch approximately one eighth of an inch wide along most of the element, and two other substantial scratches. The top of the main scratch terminates in what appears to be a cracking pattern, though likely not fully through the cladding, as no fission product release was detected. The element also exhibits apparent rust on the triangular spacer, covering approximately 10 percent of the serial number face surface. It will not be used in the future. None of our inspection records show a history of any damage. It was in service prior to this inspection. This element was transferred to our facility after previous use at Michigan State University in 1989, also having been previously used at General Atomics in San Diego. Estimated manufacture [date] in 1964.

"Fuel element 7932, stainless-steel clad: Substantial cladding damage, but not an apparent breach. It has multiple deep scratches, disconnected at the ends, though running in parallel for lengths down a side of the element for nearly the entire length. [The element] gives the appearance of potential separation, but no fission product release was detected. It will not be used in the future unless thorough non-destructive evaluation concludes sufficient cladding integrity remains. None of our inspection records show a history of any damage. It was in service prior to this inspection. This element was purchased directly from General Atomics new in 1974.

"Fuel element 9473, stainless-steel clad: Multiple deep scratches on several sides with little to no light reflection. Scratches are typical on elements, however, the appear to threaten the integrity of the cladding and further use may result in release, though none has been detected yet. It will not be used in the future unless thorough non-destructive evaluation concludes sufficient cladding integrity remains. None of our inspection records show a history of any damage. It was in service prior to this inspection. This element was purchased directly from General Atomics new in 1980.

"Fuel element 5888, stainless-steel clad: Several concerning scratches and a large, repeatedly damaged scratch, indicating improper handling and threatening cladding integrity. No fission product release detected, but further handling may result in even minor damage sufficient enough to enable a release. It will not be used in the future unless thorough non-destructive evaluation concludes sufficient cladding integrity remains. Inspection records show small amounts of damage; however, [the records were] not fully indicative of the degree [of damage] observed during this inspection. The element has not been in service at this facility. It was obtained from the fuel repository at Idaho National Lab in 2016, which transferred the element from General Atomics, originally used starting in 1970.

"Fuel element 5671, stainless-steel clad: Appears to have oddly spaced and shaped bands of rust around the fuel section of the element. Coloration and lack of light reflection strongly suggest an abnormal corrosion, prominent on all sides of the element in varying degrees. Gently rubbing with a soft cloth resulted in minimal transfer of material, only some coloration but no discernable particulate, indicating the defects are integrated into the cladding and not freely releasable. No obvious mechanism exists to explain the features, though other elements on site have a similar pattern, none exhibit the degree of discoloration or loss of luster. The element was in storage at the facility but had been previously used. It will not be used in the future. It was originally purchased new from General Atomics in 1968.

"[The licensee is] still working through fuel inspections. There will likely be future updates."

Notified NRR PM (Boyle), NPR Event Coordinator (Waugh), and USGS PM (Sutherland).

CRITICALITY ACCIDENT AND ALARM SYSTEM OUT OF SERVICE FOR TESTING

The following information was provided by the licensee via fax or email:

"The American Centrifuge Plant (ACP) criticality accident and alarm system (CAAS) is designed to detect a nuclear criticality accident and provide audible and visual alarms that alert personnel to evacuate the immediate area, as required by 10 CFR 70.24, criticality accident requirements.

"The CAAS will be temporarily disabled (declared inoperable in accordance with approved plant procedures) to perform periodic CAAS testing activities. The planned CAAS outage is expected to last for approximately 48 hours, commencing at approximately 0800 EDT, on Wednesday, July 10th, 2024. The planned maintenance activities will affect the CAAS in the X-3001 North.

"Essential personnel will be present inside the controlled access area during the maintenance activities. Compensatory measures will be implemented in accordance with section 5.4.4 of the License Application for the American Centrifuge Plant. These measures include the following: evacuation of non-essential personnel from the area of concern and the immediate evacuation zone (IEZ) before removing CAAS equipment from service; limiting access into the area; restricting fissile material movement; and the use of personal alarming dosimeters for personnel that must access the area during the CAAS outage. These measures will be implemented until CAAS coverage is verified to be operational and the CAAS is declared operable in accordance with approved plant procedures.

"American Centrifuge Operating, LLC (ACO) will notify the NRC when CAAS coverage is returned to normal operation.

"The licensee has notified the NRC Project Manager."

ACP condition notification #11933

AGREEMENT STATE REPORT - STUCK OPEN SHUTTER
The following information was received from the state of Nevada via email:

"Nevada Gold Mines LLC - Goldstrike, [Nevada license] 05-11-13545-01, reported a stuck open shutter on a Berthold LB 7440, serial number 1459. The fixed gauge remains installed pending the arrival of a contractor to replace the failed shutter. Radiation surveys of the installed gauges are as expected for a gauge in service giving 0.11 mR/hour 1 foot back from the gauge (in walkway). Gauge is installed in a location where there is occasional foot traffic, providing no additional exposure mine/mill staff until it can be repaired. Licensee [was] reminded to report the failure to the manufacturer in accordance with the operations and maintenance manual for the gauge."

The gauge contains 50 mCi of Cs-137. The state of Nevada considers this event closed.

Nevada Item Number: NV240005

AGREEMENT STATE REPORT - STUCK SHUTTER

The following report was received from the Louisiana Department of Environmental Quality via email:

"A nuclear gauge was stuck in the open shutter position. This event is considered an equipment failure. The failure occurred while BBP (Bonds Barton Pilcher) tried to remove a screw on the rotor on July 2, 2024.

"Marathon Petroleum brought in a third party to work on the nuclear gauge. BBP was the third party. Marathon Petroleum plans on having BBP replace the nuclear gauge with another one as soon as possible."

Device information is as follows:
Model: Ohmart SH-F1A
Serial number: 13524941
Isotope: Cs-137 with an activity of 15 mCi
Source serial number: 65511
The device was acquired in June 2006.

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
There were no reports of exposures and the licensee has taken measures to prevent future potential exposures.

Louisiana Event Report ID No.: LA20240007