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Event Notification Report for November 01, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/31/2018 - 11/1/2018

** EVENT NUMBERS **


53464 53689 53692 53708 53711 53712

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Part 21 Event Number: 53464
Rep Org: AAF FLANDERS
Licensee: AAF FLANDERS
Region: 1
City: WASHINGTON   State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SHAWN WINDLEY
HQ OPS Officer: RICHARD SMITH
Notification Date: 06/20/2018
Notification Time: 20:55 [ET]
Event Date: 05/02/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/31/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
KENNETH RIEMER (R3DO)
PART 21/50.55 REACTORS ()

Event Text

PART 21 - INTERIM REPORT NOTIFICATION

The following was received via phone call and email:

This report provides notification and interim information concerning an evaluation being performed by AAF Flanders for an unapproved design change in a High Efficiency Particulate Air Filter.

"An evaluation is underway for filters that underwent a non-approved design change. AAF Flanders has determined that an evaluation cannot be completed within the 60 day period. Discovery of the potential deviation was May 2, 2018.

"The information required for the 60-Day Interim Report Notification 21.21(a)(2) was provided. We anticipate that the evaluation will be completed by Sept 15, 2018.

"AAF Flanders is evaluating a potential nonconforming condition associated with filters (model number 0-007-C-42-03-NU-11-13-GG FU5) supplied to Prairie Island Nuclear Generating Plant (PINGP) / Xcel Energy."

AAF Flanders notified Prairie Island Nuclear Plant of this potential defect.

* * * UPDATE ON 9/14/2108 AT 1129 EDT FROM SHAWN WINDLEY TO ANDREW WAUGH * * *

The following information was received via email:

"A notification was submitted to the Commission with the subject matter of, 'Unapproved Design Change in a High Efficiency Particulate Air Filter.' At this time, the evaluation is pending third party qualification testing of the product. Information obtained from the qualification will be used in the determination of a defect. AAF Flanders had anticipated this process to have been completed by Sept 15, 2018 but because it is still on-going, we request an extension until October 31, 2018 to submit a final report to the Commission.

"The subject filters (model number 0-007-C-42-03-NU-11-13-GG FU5) supplied to Prairie Island Nuclear Generating Plant (PINGP)/ Xcel Energy had not been installed. AAF Flanders has recalled the subject filters and currently have them segregated and stored at our facility. They pose no threat public safety."

Notified R3DO (Hanna) and Part 21/50.55 Reactors Group (email).

* * * UPDATE ON 10/31/18 AT 1545 EDT FROM SHAWN WINDLEY TO HOWIE CROUCH * * *

The following information was excerpted from information received via email:

"AAF Flanders had anticipated the qualification process for said filters to have been completed by Sept 15, 2018. AAF requested a second extension by October 31, 2018 to submit a final report to the Commission, however; at this time our qualification is still pending third party approval. AAF Flanders is requesting another extension on the basis of an incomplete qualification of these filters. We anticipate qualification and a completed report on or before 12/15/2018."

Notified R3DO (Stoedter) and Part 21/50.55 Reactors Group (email).

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Agreement State Event Number: 53689
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: EXXONMOBIL CHEMICAL
Region: 4
City: BEAUMONT   State: TX
County:
License #: L 00603
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/23/2018
Notification Time: 12:39 [ET]
Event Date: 10/22/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/23/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER

The following was received from the State of Texas by email:

"On October 23, 2018, [a report was received by the Texas Department of State Health Services that] a consulting company servicing the equipment for a licensee found during a maintenance operation that a gauge had a stuck shutter on October 22, 2018. The device is labeled Vega, SH-F1A, 20 mCi, Cesium-137, Source Serial number 5786CN. The gauge measures vessel material levels and is mounted about 10 feet above ground level. No risk of radiation exposure to members of the public or radiation workers at the location. The gauge shutter is stuck in the open operating position. A repair company was called to contract an inspection to repair or replace the gauge. An update will be provided as information is obtained."

Texas Incident #: 9624

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Agreement State Event Number: 53692
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: ELEKTA, INC.
Region: 1
City: PARAMUS   State: NJ
County:
License #: 535964
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: OSSY FONT
Notification Date: 10/24/2018
Notification Time: 10:45 [ET]
Event Date: 10/23/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/24/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DONNA JANDA (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - LEAKING SEALED SOURCE

The following was received from the State of New Jersey via email:

"A reciprocity licensee informed [New Jersey Department of Environmental Protection Radioactive Materials Program] that during a routine preventive maintenance and source exchange of a [high dose rate] HDR unit at a hospital, the sealed Ir-192 source was found to be leaking. Upon discovery of the leakage, the source exchange was halted. The sealed source is a model 105.002 Ir-192 source manufactured by Alpha Omega Services, Inc. for use in an Elekta HDR microSelectron model 106.990, serial number 10362.

"The wipe test revealed the presence of 190 Bq on the check cable and 183 Bq on the source cable. Checks of the transfer tubes were within regulatory limits. Checks on the applicators used and the indexer cap are being conducted. The source is secured in its shielded position within the HDR unit. Exposure levels are normal for a shielded source. The unit itself is secured in its routine storage location. There are no HDR patient treatments scheduled for the next two weeks. This should be sufficient time for the levels of contamination to decay to below regulatory limits. At that time, the source exchange will proceed.

"A phone call and follow-up e-mail was made to the State of New Jersey Department of Environmental Protection's Bureau of Environmental Radiation."

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Part 21 Event Number: 53708
Rep Org: FISHER CONTROLS INTERNATIONAL, LLC
Licensee: EMERSON PROCESS MANAGEMENT - FISHER VALVES
Region: 3
City: MARSHALLTOWN   State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KIM SAGAR
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/31/2018
Notification Time: 17:05 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/31/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DAN SCHROEDER (R1DO)
RANDY MUSSER (R2DO)
KARLA STOEDTER (R3DO)
CALE YOUNG (R4DO)
PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 NOTIFICATION - FISHER DIGITAL VALVE CONTROLLERS 6000/6200 SERIES NOT ENVIRONMENTALLY QUALIFIED

The following information is summarized from information received from Fisher Valves via email:

A customer ordered a replacement digital valve controller. When the original controller was purchased, documentation indicated that it was qualified under IEEE 323-1974. The DVC6000 series and the DVC6200 series are not qualified in accordance with IEEE 323, nor was there any intent to qualify these devices to this standard.

The only customer that has requested Environmentally Qualified controllers is Seabrook Station.

Fisher requests that the recipient of this FIN review it and take appropriate action in accordance with 10 CFR 21. If there are any technical questions, please contact:

Jacob Clos
Quality Manager
Emerson Automation Solutions
Fisher Controls International LLC
301 South First Avenue
Marshalltown, IA 50158
Phone: (641) 754-2108
Jacob.Clos@Emerson.com

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Power Reactor Event Number: 53711
Facility: BEAVER VALLEY
Region: 1     State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEOFFREY WOOLSEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/01/2018
Notification Time: 15:38 [ET]
Event Date: 11/01/2018
Event Time: 00:00 [EDT]
Last Update Date: 11/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
DAN SCHROEDER (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Defueled 0 Defueled

Event Text

DISCOVERY OF INDICATIONS THAT DID NOT MEET ACCEPTANCE CRITERIA ON ONE REACTOR VESSEL HEAD PENETRATION

"On 11/01/2018, during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 27 will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. The other 65 penetrations will be examined during the 2R20 [current] refueling outage.

"The plant is currently shutdown and in Undefined Mode. The reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.

"This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as-found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-4 to remain in-service without repair.

"The NRC Resident Inspector has been notified."

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53712
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFFREY MYERS
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/01/2018
Notification Time: 20:10 [ET]
Event Date: 11/01/2018
Event Time: 13:00 [EDT]
Last Update Date: 12/28/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
KARLA STOEDTER (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

UNANALYZED CONDITION DUE TO MODIFICATION NOT ADDED TO PROCEDURE

"On November 1, 2018, at approximately 1300 EDT, Fermi 2 identified that a Station Blackout (SBO) procedure was deficient as a result of a modification installed during a recent refueling outage. A review identified that the performance of the SBO procedure could have resulted in a challenge to having an alternate AC source available within one hour as outlined in the Updated Final Safety Analysis Report (UFSAR) 8.4.2. The alternate AC source was always available to be manually aligned in accordance with other standard operating procedures. The modification did not affect the function for Appendix R alternative shutdown.

"Immediate actions are underway to revise the impacted procedure. The health and safety of the public was not affected as offsite power has remained available since the modification was installed. Investigation into the cause and corrective actions is ongoing.

"Fermi 2 is reporting this event as an unanalyzed condition pursuant to the requirements of 10 CFR 50.72(b)(3)(ii)(B)."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION ON 12/28/18 AT 1228 EST FROM JEFFREY MYERS TO JEFFREY WHITED * * *

"The purpose of this notification is to retract a previous report made on November 1, 2018 (EN 53712) under 10 CFR 50.72(b)(3)(ii)(B). Subsequent to the initial notification, the event, site procedures, and the NRC guidance in NUREG-1022 pertaining to 10 CFR 50.72(b)(3)(ii)(B) were reviewed further. The evaluation determined that at the time of the event, there were multiple methods defined in existing station procedures to establish an available alternate AC source within one hour as outlined in the Updated Final Safety Analysis Report (UFSAR) 8.4.2.

"Under these circumstances, the event does not represent an unanalyzed condition under 10 CFR 50.72(b)(3)(ii)(B). Therefore, EN 53712 can be retracted and no Licensee Event Report (LER) under 10 CFR 50.73(a)(2)(ii)(B) is required to be submitted.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Riemer).


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