| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
5/23/2018 - 5/24/2018 ** EVENT NUMBERS ** |
| Agreement State | Event Number: 53402 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: CHURCH OF JESUS CHRIST OF LATTER DAY SAINTS - NORFOLK
Region: 4
City: NORFOLK State: NE
County:
License #: GL0370
Agreement: Y
Docket:
NRC Notified By: MALISA MCCOWN
HQ OPS Officer: ANDREW WAUGH | Notification Date: 05/15/2018
Notification Time: 17:28 [ET]
Event Date: 05/15/2018
Event Time: 00:00 [CDT]
Last Update Date: 05/15/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HEATHER GEPFORD (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text NEBRASKA AGREEMENT STATE REPORT - TWO MISSING TRITIUM EXIT SIGNS
The following information was obtained from the State of Nebraska via email:
"GL0370 Church of Jesus Christ of Latter Day Saints - Norfolk submitted their Annual Renewal and Inventory on March 9, 2018. On May 15, 2018, GL0370 re-submitted their Inventory, indicating that two tritium exit signs were missing. A follow-up phone call placed to the licensee indicated the licensee did not actually conduct an inventory of the devices prior to the March 9th documentation. They have searched through all back records and can find no indication of when the devices were removed.
"Source number 1 information:
Device name: Sealed Source Luminous
Manufacturer: Isolite
Model Number: SLX60
Serial Number: 10-7234
Radionuclide: H-3
Activity: 10 Ci
"Source number 2 information:
Device name: Sealed Source Luminous
Manufacturer: Isolite
Model Number: SLX60
Serial Number: 10-17588
Radionuclide: H-3
Activity: 10 Ci"
Nebraska Item Number: NE180004
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.p |
| Part 21 | Event Number: 53422 | Rep Org: WESTINGHOUSE ELECTRIC COMPANY
Licensee: WESTINGHOUSE
Region: 1
City: CRANBERRY TOWNSHIP State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES GRESHAM
HQ OPS Officer: THOMAS KENDZIA | Notification Date: 05/23/2018
Notification Time: 14:19 [ET]
Event Date: 05/23/2018
Event Time: 00:00 [EDT]
Last Update Date: 05/23/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
EUGENE GUTHRIE (R2DO)
ROBERT DALEY (R3DO)
JASON KOZAL (R4DO)
- PART 21/50.55 REACTORS (EMAIL) | Event Text PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS
The following notification is an excerpt from the received report:
"Westinghouse nuclear steam supply system (NSSS) plants that have thermal sleeves in the control rod drive mechanism (CRDM) penetration tubes, wear of the thermal sleeve flange against the tube could have safety consequences that were not previously considered. Recent operating experience, during startup procedures at an Electricite de France (EdF) plant, has shown the possibility for the flange remnant from a thermal sleeve to interfere with control rod movement."
Potential affected plants include, A. W. Vogtle 1 & 2, Braidwood 1 & 2, Byron 1 & 2, Callaway, Catawba 1 & 2, Comanche Peak 1 & 2, Diablo Canyon 1 & 2, McGuire 1 & 2, Millstone 3, Seabrook, Sequoyah 1 & 2, Shearon Harris, South Texas 1 & 2, Watts Bar 1 & 2, Wolf Creek, Beaver Valley 1 & 2, D.C. Cook 1 & 2, Indian Point 2 & 3, North Anna 1 & 2, Point Beach 1 & 2, Prairie Island 1 & 2, R. E. Ginna, Salem 1 & 2, Surry 1 & 2, and Turkey Point 3 & 4.
Name and address of the individual or individuals informing the Commission.
James A. Gresham
Westinghouse Electric Company
1000 Westinghouse Drive, Suite 259 Cranberry Township, Pennsylvania 16066
Direct tel: (412) 374-4643
Direct fax: (724) 940-8560
e-mail: greshaja@westinghouse.com |
| Power Reactor | Event Number: 53423 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LOREN STUCK
HQ OPS Officer: THOMAS KENDZIA | Notification Date: 05/23/2018
Notification Time: 16:10 [ET]
Event Date: 05/23/2018
Event Time: 08:48 [CDT]
Last Update Date: 05/23/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JASON KOZAL (R4DO) | | 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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At time 0848 (CDT), Main Steamline Radiation Monitor 2-RE-2328 (Main Steamline 2-04) lost communications and was declared non-functional.
"With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 2-04 could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10CFR50.72(b)(3)(xiii).
"Comanche Peak Nuclear Power Plant [CPNPP] has assurance of steam generator integrity and fuel cladding integrity and there is a negligible safety significance to the current condition from a public health and safety perspective.
"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding. The N16 radiation monitor serves as a backup with alarm function and Radiation Protection technicians have been briefed on taking local readings with a Geiger-Mueller tube on MSL 2-04.
"Corrective actions are being pursued to restore 2-RE-2328 to a functional status.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53424 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID HECKMAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/23/2018
Notification Time: 17:37 [ET]
Event Date: 05/23/2018
Event Time: 11:28 [MST]
Last Update Date: 05/23/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JASON KOZAL (R4DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW DEPARTURE FROM NUCLEATE BOILING RATIO
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On May 23, 2018, at approximately 1128 Mountain Standard Time (MST), the Palo Verde Nuclear Generating Station (PVNGS) Unit 2 control room received reactor protection system alarms for low departure from nucleate boiling ratio and an automatic reactor trip occurred. Prior to the reactor trip, Unit 2 was operating normally at 100 percent power. Plant operators entered the reactor trip procedures and diagnosed an uncomplicated reactor trip. All CEAs [control element assemblies] fully inserted into the core. No emergency classification was required per the PVNGS Emergency Plan.
"The Unit 2 safety-related electrical buses remained energized from normal offsite power during the event. There was no impact to the required circuits between the offsite transmission network and the onsite Class 1E Electrical Power Distribution System; the offsite power grid is stable.
"No major equipment was inoperable prior to the event that contributed to the event or complicated operator response. Unit 2 is currently stable in Mode 3 with the reactor coolant system at normal operating temperature and pressure. The cause of the reactor trip is under investigation.
"The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.
"The NRC Resident Inspector has been informed of the Unit 2 reactor trip."
Decay is being removed via steam dumps to condenser. Units 1 and 3 at Palo Verde were unaffected by the transient and continue to operate at 100 percent power. |
| Power Reactor | Event Number: 53426 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEREMY CZESCHIN
HQ OPS Officer: THOMAS KENDZIA | Notification Date: 05/23/2018
Notification Time: 18:32 [ET]
Event Date: 05/23/2018
Event Time: 07:30 [CDT]
Last Update Date: 05/23/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JASON KOZAL (R4DO)
FFD GROUP (EMAIL) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY
"On May 23, 2018 Callaway determined that a violation of one provision of the site's Fitness for Duty (FFD) policy occurred. FFD pre-access testing confirmed a test failure for alcohol. The violation was committed by a non-licensed supervisory employee. The individual did not hold unescorted access to the plant but did perform behavioral observation program (BOP) duties. The BOP qualification has been removed.
"The NRC Resident Inspector has been notified by the licensee." | |