| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/1/2018 - 11/2/2018 ** EVENT NUMBERS ** |
| 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." |
| 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." |
| !!!!! 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). | |