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Event Notification Report for April 20, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/19/2017 - 04/20/2017

** EVENT NUMBERS **


52672 52673 52692

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State Event Number: 52672
Rep Org: HARRISON STEEL
Licensee: HARRISON STEEL
Region: 3
City: ATTICA State: IN
County:
License #: 13-02141-01
Agreement: N
Docket:
NRC Notified By: AMANDA DILL
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/11/2017
Notification Time: 14:23 [ET]
Event Date: 04/11/2017
Event Time: 12:00 [EDT]
Last Update Date: 04/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(b)(1) - PERS OVEREXPOSURE/TEDE >= 5 REM
Person (Organization):
MARK JEFFERS (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

RADIOGRAPHER LOST FILM BADGE IN VAULT

"On April 11, 2017 our Radiographic Supervisor dropped his film badge within the exposure vault after the clip had broken. [The individual] was not in the exposure vault during any exposure but his badge will reflect an exposure. His badge has been sent for processing this afternoon. [The individual] was working with another radiographer and their exposure amounts for this day should be comparable as to estimating his true daily exposure amount."

* * * RETRACTION ON 4/17/17 AT 1700 EDT FROM AMANDA DILL TO DONG PARK * * *

The event was initially reported by the licensee out of caution. Since the event does not meet reporting criteria, this notification is being retracted.

The licensee notified R3 (Craffey). Notified R3DO (Kunowski) and NMSS Events Notification.

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Agreement State Event Number: 52673
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: UNIVERSITY OF UTAH
Region: 4
City: SALT LAKE CITY State: UT
County:
License #: UT 1800001
Agreement: Y
Docket:
NRC Notified By: SPENCER WICKHAM
HQ OPS Officer: VINCE KLCO
Notification Date: 04/11/2017
Notification Time: 14:28 [ET]
Event Date: 04/10/2017
Event Time: [MDT]
Last Update Date: 04/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN KRAMER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - LEAKING TRITIUM EXIT SIGN

The following information was received from the State of Utah via email:

"[University] Radiological Health personnel responded to an incident involving a damaged tritium exit sign at the University Guest House. It was determined the damaged exit sign was leaking tritium and the licensee notified the [Utah] Division of Waste Management and Radiation Control. This incident report is the initial notification of the NRC Operations Center."

Utah Event Report: UT170003

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Part 21 Event Number: 52692
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LISA SCHICHLEIN
HQ OPS Officer: BETHANY CECERE
Notification Date: 04/19/2017
Notification Time: 10:29 [ET]
Event Date: 02/27/2017
Event Time: [EDT]
Last Update Date: 04/19/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
PHILIP McKENNA (R2DO)
LAURA KOZAK (R3DO)
RAY AZUA (R4DO)
PART 21/50.55 REACTO (EMAI)

Event Text

PART 21 REPORT - CONTROL ROD DRIVE MECHANISMS CONTAMINATED WITH CHLORIDES

Dale E. Porter
GE-Hitachi Nuclear Energy
Safety Evaluation Program Manager
3901 Castle Hayne Rd., Wilmington, NC 28401
(910) 819-4491
Dale.Porter@GE.Com

"The inappropriate addition of chlorinated water from container box desiccants into the CRDMs [Control Rod Drive Mechanisms] during leak testing after rebuild could potentially initiate Intergranular Stress Corrosion Cracking (IGSCC) or Transgranular Stress Corrosion Cracking (TGSCC). These two types of SCC could cause a separation of the stop piston or separation of the index tube contained within the CRDM. The stop piston separation could cause a slower scram speed and damage the drive so it could not be withdrawn. An index tube separation could result in a similar type of rod uncoupling event that would have the potential to result in a rod drop accident (RDA). The piston tube located within the CRDM is a reactor coolant pressure boundary (RCPB) and is an ASME component. There is a possibility of cracking causing a RCPB leak. SCC initiation on the Cylinder Tube and Flange (CTF) area of the CRDM could result in a separation that could prevent a scram or normal insertion of a CRDM.

"Reports have been issued to River Bend, LaSalle Unit 2, and Hatch Unit 2 providing the results of an evaluation that concludes that the condition will not create a substantial safety hazard or potentially cause a Technical Specification Safety Limit violation for a minimum of one operating cycle. The Browns Ferry Unit 2 drives were shipped but were not installed prior to recall, thus a short-term evaluation for Browns Ferry has not been completed.

"River Bend, Entergy, Shipped Date: 2017, Quantity Shipped: 15, Customer PO Number: 10478763
LaSalle Unit 2, Exelon, Shipped Date: 2017, Quantity Shipped: 24, Customer PO Number: 00414787-66
Hatch Unit 2, Southern Nuclear, Shipped Date: 2017, Quantity Shipped: 15, Customer PO Numbers: SNG50295-0001 & SNG50295-0002
Browns Ferry Unit 2, TVA, Shipped Date: 2017, Quantity Shipped: 32, Customer PO Number: 2424171"

Page Last Reviewed/Updated Thursday, April 20, 2017
Thursday, April 20, 2017