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Event Notification Report for April 10, 2020

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
4/9/2020 - 4/10/2020

** EVENT NUMBERS **


54629 54633 54634 54652 54653

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Agreement State Event Number: 54629
Rep Org: COLORADO DEPT OF HEALTH
Licensee: THE AVENUES OF CROFTON PARK
Region: 4
City: BROOMFIELD   State: CO
County:
License #: GL002341
Agreement: Y
Docket:
NRC Notified By: KATHRYN MOTE
HQ OPS Officer: BRIAN LIN
Notification Date: 04/01/2020
Notification Time: 14:03 [ET]
Event Date: 07/01/2019
Event Time: 00:00 [MDT]
Last Update Date: 04/01/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LAURA PEARSON (ILTAB)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGN

The following was received from the State of Colorado via email:

One tritium exit sign, containing 6.2 Curies, was determined to be lost after not being found on the property by new management.

Initial Date Reported: 7/1/2019

Final Decision Material Lost Date: 7/1/2019

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

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Agreement State Event Number: 54633
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: GZA (MELLICK-TULLY)
Region: 1
City: EDISON   State: NJ
County:
License #: 507521
Agreement: Y
Docket:
NRC Notified By: JACK TWAY
HQ OPS Officer: BRIAN LIN
Notification Date: 04/02/2020
Notification Time: 16:11 [ET]
Event Date: 04/02/2020
Event Time: 12:30 [EDT]
Last Update Date: 04/02/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED PORTABLE GAUGE

The following is a synopsis of information received via e-mail:

On April 2, 2020, at 1230 EDT, a portable density gauge was damaged by a roller at a construction site. The density gauge is a Troxler model 3430, serial number 27555 containing 9 milliCuries of cesium-137 and 44 milliCuries of americium-241/beryllium. The source was not damaged and there was no exposure or health effects to the public. An investigation is ongoing.

New Jersey event report no. 749233.

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Agreement State Event Number: 54634
Rep Org: COLORADO DEPT OF HEALTH
Licensee: WATERFORD ON MAINSTREET
Region: 4
City: PARKER   State: CO
County:
License #: GL002380
Agreement: Y
Docket:
NRC Notified By: KATHRYN MOTE
HQ OPS Officer: KERBY SCALES
Notification Date: 04/02/2020
Notification Time: 17:19 [ET]
Event Date: 01/03/2020
Event Time: 00:00 [MDT]
Last Update Date: 04/02/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LAURA PEARSON (ILTAB)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following information was received from the state of Colorado via email:

"Seventy-five tritium exit signs, containing 6.0 Curies each, was determined unaccounted for and lost during a walk down of the property.

"Initial Date Reported: 10/29/19

"Final Decision Material Lost Date: 1/3/20"

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.

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Power Reactor Event Number: 54652
Facility: NORTH ANNA
Region: 2     State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: NEIL TURNER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/09/2020
Notification Time: 03:37 [ET]
Event Date: 04/09/2020
Event Time: 01:00 [EDT]
Last Update Date: 04/09/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MARK MILLER (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 35 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE

"On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased Reactor Coolant System (RCS) unidentified leakage, a leak was identified on the 'A' Reactor Coolant Pump (RCP) seal injection piping. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. At that time, Condition B of Technical Specification (TS) LCO 3.4.13, 'RCS Operational Leakage' was entered due to pressure boundary leakage. TS 3.4.4 'RCS Loops - Mode 1 and 2' and Technical Requirement (TR) 3.4.6 'ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs.

"This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'Initiation of plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded.'"

The licensee notified the NRC Resident Inspector. There is no effect on Unit 1

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Non-Power Reactor Event Number: 54653
Facility: UNIV OF MISSOURI-COLUMBIA
RX Type: 10000 KW TANK
Comments:
Region: 0
City: COLUMBIA   State: MO
County: BOONE
License #: R-103
Agreement: N
Docket: 05000186
NRC Notified By: BRUCE MEFFERT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/09/2020
Notification Time: 09:35 [ET]
Event Date: 04/08/2020
Event Time: 01:00 [CDT]
Last Update Date: 04/09/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
Person (Organization):
GEOFF WERTZ (NRR)
BETH REED (NRR)

Event Text

RESEARCH AND TEST REACTOR FORCED SHUTDOWN DUE TO FAILURE OF REGULATING BLADE DRIVE MECHANISM

"On 4/8/20 at 0100 CDT, the University of Missouri-Columbia Research Reactor (MURR) was shut down due to a failure of the regulating blade drive mechanism to move the regulating blade during reactor operation. This email is a required notification per MURR Technical Specification (TS) 6.6.c.(1) to report to the NRC Operations Center that an Abnormal Occurrence, as defined by MURR TS 1.1, had occurred. Specifically, MURR was not in compliance with all Limiting Conditions for Operations (LCOs). MURR was not in compliance with two (2) LCOs: 1. TS 3.2.a states, 'All control blades, including the regulating blade, shall be operable during reactor operation,' and 2. TS 3.2.f states, 'The reactor shall not be operated unless the following rod run-in functions are operable.' Specifically, the rod run-in function that occurs when the regulating blade position is less than or equal to 10 percent withdrawn was not operable as TS 3.2.f.8 requires.

"The regulating blade drive mechanism was repaired, post-maintenance operability testing was conducted on the regulating blade, and permission from the Reactor Facility Director was obtained prior to the reactor returning to operation later on 4/8/20. Currently, MURR is at 10 MW. A detailed event report will follow within 14 days as required by MURR TS 6.6.c.(3)."


Page Last Reviewed/Updated Friday, April 10, 2020
Friday, April 10, 2020