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Event Notification Report for April 03, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
4/2/2019 - 4/3/2019

** EVENT NUMBERS **

!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Independent Spent Fuel Storage Installation	Event Number: 53858
Rep Org: SAN ONOFRE Licensee: SOUTHERN CALIFORNIA EDISON COMPANY Region: 4 City: SAN CLEMENTE State: CA County: SAN DIEGO License #: GL Agreement: Y Docket: 72-41 NRC Notified By: MICHAEL JOHNSON HQ OPS Officer: OSSY FONT	Notification Date: 02/02/2019 Notification Time: 13:44 [ET] Event Date: 02/01/2019 Event Time: 14:05 [PST] Last Update Date: 04/02/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION	Person (Organization): RAY AZUA (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) JEFFERY GRANT (IRD)

Event Text

NO SEISMIC ANALYSIS FOR CANISTER TRANSPORT PROCESS

"During follow-up reviews resulting from the Aug. 3, 2018 canister downloading event (EN#53605), Southern California Edison [SCE] became aware of a condition where, during short periods of the canister transport process, the Vertical Cask Transporter (VCT) could have been operated without a supporting seismic analysis while transporting loaded canisters for storage. SCE has decided to conservatively report this issue.

"The VCT is a mobile gantry crane that is used to transport and download fuel canisters into an Independent Spent Fuel Storage Installation (ISFSI) enclosure. Twenty-nine canisters have been downloaded into the San Onofre nuclear plant ISFSI in this manner since January, 2018. The Holtec UMAX Certificate of Compliance requires that lifting of a loaded spent fuel canister must be performed with redundant (i.e., single-failure-proof) load drop protection features. Inherent in the definition is the ability to withstand seismic loading. SCE identified that although applicable rigging and downloading procedures were followed, a supporting seismic analysis should be developed for the short duration periods in the process where the canisters are transitioned to rigging.

"Southern California Edison has directed its vendor, Holtec, to perform this further seismic analysis. While the additional analysis may conclude that the VCT is stable and functional during these transitioning periods, SCE will work with the vendor should modifications to the canister transport process become necessary.

"SCE is making this notification in accordance with the requirements of 10 CFR 72.75(d)(1). There was no seismic event that resulted in damage to the VCT or a spent fuel canister during the fuel transfer campaign. All 29 spent fuel canisters are currently in safe storage within the ISFSI."

* * * RETRACTION FROM TIM CUSICK TO DONALD NORWOOD AT 1930 EDT ON 4/2/2019 * * *

"On 4/2/19, Southern California Edison (SCE) is retracting San Onofre Nuclear Generating Station (SONGS) Event Report 53858 dated February 2, 2019 for the Independent Spent Fuel Storage Installation (ISFSI). SCE conservatively submitted the event report under 72.75(d)(1) after it was initially determined the Vertical Cask Transporter (VCT) may have been operated for short periods of time during the canister transport process without a supporting seismic evaluation, contrary to the requirements of the Certification of Compliance (COC). A revision to the calculation by the vendor has subsequently confirmed the transport process and VCT operation met the seismic requirements of the Holtec COC. Therefore, Event Report No. 53858 is retracted."

Notified R4DO (Gaddy) and via E-mail IRD MOC (Kennedy) and NMSS Events Notification E-mail group.

Agreement State	Event Number: 53956
Rep Org: COLORADO DEPT OF HEALTH Licensee: TEST AMERICA Region: 4 City: ARVADA State: CO County: License #: Agreement: Y Docket: NRC Notified By: RAMON LI HQ OPS Officer: JOANNA BRIDGE	Notification Date: 03/25/2019 Notification Time: 16:37 [ET] Event Date: 03/04/2019 Event Time: 00:00 [MDT] Last Update Date: 03/25/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): JASON KOZAL (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE - LEAKING ELECTRON CAPTURE DEVICES

The following was received via e-mail:

"The department [Colorado Department of Public Health and Environment] received an e-mail notification on March 7th, 2019 reporting two leaking Electron Capture Devices (ECD's). The [ECD's] are associated with Agilent model G239765505 with serial numbers: U1186 and U6642. The semi-annual leak test results show 35300 picocurie/sample for serial number U1186 and 17100 picocurie/sample for serial number U6642. The wipe test results were received by Test America on March 4, 2019.

"Test America reported that the ECD's were removed from use and the instruments on March 4, 2019 and sent to Detector Service Center, LLC for cleaning and repair.

"Test America performed surveys for the affected machines and cleaned with a radiacwash solution. A wipe test was done on the instruments and counted by Gas Flow Proportional Counter low background instrument which indicated no removable contamination present. A direct survey with a Ludlum Model 3 Giger Muller detector indicated no fixed contamination. The completion date was reported to be March 5, 2019.

"Test American has removed the leaking ECD's and will continue 6-month wipe tests as required."

Colorado Event Report ID No.: CO190004

Agreement State	Event Number: 53957
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES Licensee: HOLLY ENERGY PARTNERS LLC Region: 4 City: EL PASO State: TX County: License #: GLA02278 Agreement: Y Docket: NRC Notified By: MATTHEW KENNINGTON HQ OPS Officer: JOANNA BRIDGE	Notification Date: 03/25/2019 Notification Time: 17:53 [ET] Event Date: 03/21/2019 Event Time: 00:00 [CDT] Last Update Date: 03/25/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): JASON KOZAL (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE - STUCK OPEN GAUGE SHUTTER

The following was received via e-mail:

"On March 25, 2019, the agency [Texas Department of State Health Services] reviewed a voicemail left on an investigator's office phone line in which a licensee reported a stuck shutter on a gauge. The gauge is a Thermo Fisher Scientific model 7062BP, with serial number S99G0101, containing a 100 millicurie Cesium-137 source with serial number 6551GQ. The shutter is stuck in the open position. Open is the normal operating position. The gauge is located on a 6" line and no exposures are anticipated as a result of this malfunction. The manufacturer has been contacted and service will be scheduled. Updates will be sent in accordance with SA-300."

Texas Incident: I-9668

Agreement State	Event Number: 53958
Rep Org: COLORADO DEPT OF HEALTH Licensee: CARDINAL HEALTH 414, LLC Region: 4 City: DENVER State: CO County: License #: CO 1219-01 Agreement: Y Docket: NRC Notified By: MATT GIFT HQ OPS Officer: JEFFREY WHITED	Notification Date: 03/25/2019 Notification Time: 18:05 [ET] Event Date: 03/22/2019 Event Time: 00:00 [MDT] Last Update Date: 03/25/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): JASON KOZAL (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST AND FOUND RA-223 PACKAGE

The following was received via e-mail:

"The Department [Colorado Department of Public Health and Environment] received an e-mail notification on March 25, 2019, from Cardinal Health reporting a lost and found package of Ra-223. On March 22, 2019, the package was suspected to have fallen out of a [common carrier] truck and onto a member of the public's lawn located a few blocks away from the Cardinal Health Facility. The member of the public returned the package to the doorstep of Cardinal Health later that day (3/22/19). No signs of damage to the package were identified. Cardinal Health performed wipes for removable contamination and exposure rate surveys and determined there was no outer or inner contamination and all of the safety seals remained intact. More details are forthcoming."

The activity of the shipment is unknown at this time, however, it is assumed to be less than CAT 3. The State of Colorado will update the event when the activity has been determined.

Colorado Event Report No: CO190005

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

Agreement State	Event Number: 53960
Rep Org: NE DIV OF RADIOACTIVE MATERIALS Licensee: FLINT HILLS RESOURCES Region: 4 City: FAIRMONT State: NE County: License #: GL0693 Agreement: Y Docket: NRC Notified By: HOWARD SHUMAN HQ OPS Officer: JOANNA BRIDGE	Notification Date: 03/26/2019 Notification Time: 16:28 [ET] Event Date: 03/25/2019 Event Time: 00:00 [CDT] Last Update Date: 03/26/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): JASON KOZAL (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE - LOST TRITIUM EXIT SIGNS

The following is a summary of information received from the State of Nebraska:

On March 26, 2019, the Nebraska Department of Radioactive Materials received a letter dated March 25, 2019, from the licensee (Flint Hills Resources) concerning the loss of two tritium exit signs, each with an activity of 17.51 Curies. Two H-3 exit signs were lost during recent construction of additional warehouse space on an existing building. One sign was over a personnel door on the wall demolished for the new space and one was on a personnel door proximal to the construction area.

NE Item Number: NE190002

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

Part 21	Event Number: 53973
Rep Org: WEIR VAVLES AND CONTROLS Licensee: WEIR VALVES AND CONTROLS USA Region: 1 City: IPSWICH State: MA County: License #: Agreement: Y Docket: NRC Notified By: ALLEN FISHER HQ OPS Officer: JEFFREY WHITED	Notification Date: 04/03/2019 Notification Time: 17:32 [ET] Event Date: 11/06/2018 Event Time: 00:00 [EST] Last Update Date: 04/03/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE	Person (Organization): MATT YOUNG (R1DO) ALAN BLAMEY (R2DO) JOHN HANNA (R3DO) MICHAEL VASQUEZ (R4DO) - PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 REPORT - RESIDUAL HEAT REMOVAL SYSTEM MOTOR OPERATED GLOBE VALVE EXPERIENCED STEM FAILURES

The following was received via e-mail:

"This notification is being submitted pursuant to the guidelines of 10 CFR Part 21 to report that a 24in Class 150 Globe valve for RHRSW HX [Residual Heat Removal Service Water Heat Exchanger] Isolation MOV [motor operated valves], E1150F068B at Detroit Edison - Fermi 2, experienced two stem failures.

"The site notified WVC USA [Weir Valves and Controls, USA] on November 6 of this issue involving two stems. WVC USA had supplied these stems on orders 20000262-10 and 20012001-10, Detroit Edison PO's [part orders] 4700505700 and 4701149217. A new stem failed after approximately 1 month in service in valve F068B. A replacement stem was installed and failed soon after being placed in service. This second stem failure had previously been in service for approximately three years while installed in sister valve F068A. Both stem breakages occurred at the transition area of the stem backseat and were visually identical. See pictures of failure in Attachment A. In the as found condition, the disc to stem connection appears to have lacked design clearances. The cause of this clearance issue was cleaning of the disc surface where the disc nut is tack welded. The material supplied is A276 410 heat treated and tempered to obtain (269-311 BHN). This material was approved by Powell as an acceptable alternate to the original material A182 F6 (269-311 BHN). During original Part 21 evaluation, testing of the stem material revealed low impact values and reflected effects of temper embrittlement. Other possible contributors to the failure were transition region at stem backseat and the valve service conditions where vibration due to throttling has been experienced. It was determined that although temper embrittlement and other factors may have contributed to the failures, that the lack of design clearance led to the failure of the stems and was not reportable by WVC USA. However, after discussions with Detroit Edison, WVC USA was requested to evaluate the failure considering the effects of temper embrittlement that might lead to future failures.

"WVC USA engineering is unable to determine the effects of temper embrittlement for the A276 410 material. Powell engineering was also consulted and there are no known methods to evaluate the potential for failure on the stem in this condition. As noted in NRC Information Notice No. 85-59, tempering in the 700 degrees F to 1050 degrees F range is not recommended because it results in low and erratic impact properties and poor resistance to corrosion and stress corrosion for 410 stainless steel.

"The stem failures in this case reflected these low and erratic impact properties based on material testing that was performed by DTE [Detroit Edison] Fermi and WVC USA. The A276 410 materials supplied in this event were tempered at 1025 degrees F and 1050 degrees F.

"The best solution is to eliminate the potential for temper embrittlement by using a higher required tempering temperature. The recommendation is to use A276 410 tempered at a minimum of 1100 degrees F. This is also in alignment with Code Case N-62-7. We are in the process of updating our item records to reflect this minimum tempering requirement and expect this action to be completed within one month.

"WVC USA is notifying the following sites of this potential issue so that they can evaluate the impact on the safe operation of the plant.

"74347-10 Entergy PO 10118969 Site Grand Gulf
Item Number P 26126666ASSEMAO_QLA Stem & Disc Assy 14" Qy (1) Shipped 7/28/06

"0020005433-10 Georgia Power Company PO SNG10081312 REV. 2 Site Hatch
Item Number P0000419C Stem/Disc Assy 24-300 Globe Valve Qty (1) Shipped 10/29/15

"0020006979-10 Detroit Edison Company PO 4700846295 Site Fermi 2
Item Number P0000455C Stem Bin Gate Valve Qty (1) Shipped 6/29/15

"0020011676-10 Detroit Edison Company PO 4701123403 Site Fermi 2
Item Number P0000455C Stem Bin Gate Valve Qty (1) Shipped 2/14/18

"0020013251-10 Detroit Edison Company PO 4701230062 Site Fermi 2
Item Number P0000283 Stem Globe 24in 150# Qty (1) Shipped 9/19/18

"0020013586-10 Detroit Edison Company PO 4701259926 C0#6 Site Fermi 2
Item Number P0000283 Stem Globe 24in 150# Qty (1) Shipped 11/13/18

"Stem supplied under order 0020013251-10 is currently installed in F068A and order
0020013586-10 was delivered but not installed. F068B valve has been restored by Detroit
Edison with a stem which has acceptable properties for the service."

The above Part 21 notification affects Grand Gulf, Fermi 2, and Hatch.

Point of Contact: Allen Fisher
Director of Engineering
978-825-8451
allen.fisher@mail.weir

Page Last Reviewed/Updated Wednesday, March 24, 2021