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Event Notification Report for January 19, 2016

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
01/18/2016 - 01/19/2016

EVENT NUMBERS
516665166351673

Agreement State
Event Number: 51666
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: GEOSTRUCTURES, INC
Region: 1
City: KING OF PRUSSIA   State: PA
County:
License #: PA-1068
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/20/2016
Notification Time: 13:05 [ET]
Event Date: 01/19/2016
Event Time: 00:00 [EST]
Last Update Date: 01/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
HAROLD GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was received from the Commonwealth of Pennsylvania via E-mail:

"On January 19, 2016, the Department [Pennsylvania Department of Environmental Protection] was notified that a moisture density gauge became disabled from damage in Berwyn, Pennsylvania. This event is reportable per 10 CFR 30.50(b)(2).

"The gauge was run over by a piece of heavy equipment. This damaged the gauge and it became unusable. The source rod was in the retracted position at the time of the incident and instrument readings confirmed no damage to the source occurred. The gauge was taken out of service and transported to the manufacturer for servicing. No exposures occurred.

"Manufacturer: lnstroTek
"Gauge Model: 3500 Xplorer
"Gauge S/N: 000856
"Radioactive Material: Cesium-137: 11 milliCuries, Americium-241: 44 milliCuries

"[The cause is attributed to] human error.

"The gauge was transported to the manufacturer for repair. A reactive inspection was performed by the Department and verified the validity of the licensee's instrument readings regarding exposure and leaking sources.

"Pennsylvania Event Report ID No.: PA160003"


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 51663
Facility: SALEM
Region: 1     State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS MULHOLLAND
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/19/2016
Notification Time: 17:42 [ET]
Event Date: 01/19/2016
Event Time: 16:30 [EST]
Last Update Date: 03/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
HAROLD GRAY (R1DO)
Power Reactor Unit Info
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 DISCOVERED DURING REVIEW OF OUTAGE DATA

"On January 19, 2016, while reviewing outage data, plant staff recognized that anomalous data collected in October, 2015, for the 21 Auxiliary Feed Pump time response loop resulted in an unanalyzed condition. Preliminary investigation has revealed that the condition most likely existed since April 20, 2015, when maintenance activities were performed on the auxiliary feedwater pump discharge pressure transmitter. Consequently, there were multiple instances when one of the other auxiliary feedwater pumps was removed from service, thus creating a condition which did not meet the accident analysis assumptions for auxiliary feedwater flow initial response.

"This event is being reported under the requirements of 10 CFR 50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' This condition was corrected on November 20, 2015."

The auxiliary feedwater pump discharge pressure transmitter instrument isolation valve was inadvertently left closed after the April 20, 2015 maintenance.

The licensee has notified the NRC Resident Inspector and will notify the State of New Jersey, State of Delaware, and the local township.

* * * RETRACTED ON 3/10/16 AT 1647 EST FROM JACK OSBORNE TO DONG PARK * * *

"This event is being retracted. An engineering review determined that while the auxiliary feedwater flow loop response time test results did not meet the procedural acceptance criteria, the accident analysis assumptions remained valid. The ATWS [Anticipated Transient Without Scram] was the limiting accident, and the loop response time results were still bounded by the existing analyses. The failed loop response time did result in a condition prohibited by TS which will be reported in a Licensee Event Report (LER). This condition has been documented in the licensee's Corrective Action Program."

The licensee has notified the NRC Resident Inspector. Notified R1DO (Dimitriadis).


Non-Agreement State
Event Number: 51673
Rep Org: UNIVERSITY OF MISSOURI
Licensee: UNIVERSITY OF MISSOURI
Region: 3
City: COLUMBIA   State: MO
County:
License #: 24-00513-32
Agreement: N
Docket:
NRC Notified By: JACK CRAWFORD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/22/2016
Notification Time: 12:37 [ET]
Event Date: 01/19/2016
Event Time: 10:30 [CST]
Last Update Date: 01/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
JAMNES CAMERON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
Event Text
LEAKING NI-63 SOURCE

A 15 mCi Ni-63 source (Sealed Source Device Registry # CA0406S214S), used for research and development, was determined to be leaking greater than the 0.005 microCi limit. The leakage contaminated the desktop where it was being used. No personnel contaminations or overexposures occurred. The source was removed from service and is awaiting proper disposal.

Decontamination of the desk, which is in a secure area, is in progress. An investigation into the event is in progress.