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Event Notification Report for June 04, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
6/1/2018 - 6/4/2018

** EVENT NUMBERS **


53427 53438 53442 53443

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Agreement State Event Number: 53427
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ALTER METAL RECYCLING
Region: 3
City: GREEN BAY   State: WI
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: MEGAN SHOBER
HQ OPS Officer: OSSY FONT
Notification Date: 05/25/2018
Notification Time: 18:04 [ET]
Event Date: 05/23/2018
Event Time: 00:00 [CDT]
Last Update Date: 05/31/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FOUND SOURCE

The following information was received via E-mail:

"On May 23, 2018, a scrap yard identified a radioactive source in an outgoing load of waste intended for a landfill. The radioactive source is one inch long and approximately one-half inch in diameter. The Wisconsin Department of Health Services responded to the scrap yard on May 25, 2018, and measured a maximum exposure rate of 210 mR/hr on contact with the source. The source was confirmed to not be leaking. There are no markings or numbers on the source, and isotope identification is pending. It is not known how long the scrap yard was in possession of the source. The source is now in secured storage at the scrap yard. Additional updates will be provided as information about the source and possible original device become available."

Wisconsin Event Report ID No.: WI180008


* * * UPDATE FROM KRISTA KUHLMAN TO DONALD NORWOOD AT 1524 EDT ON 5/31/2018 * * *

The following information was received via E-mail:

"On May 31, 2018, the department performed additional characterization of the source at the scrap yard with assistance from the EPA. It has been determined that it is a Ba-133 source, with an activity between 350 - 500 microCuries. The department has not been able to determine the origin of the source. It will continue to work with the scrap yard to determine the proper disposal path."

Notified R3DO (Cameron) and NMSS Events Notification E-mail group.

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Power Reactor Event Number: 53438
Facility: SALEM
Region: 1     State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW D. MOG
HQ OPS Officer: JEFF HERRERA
Notification Date: 06/01/2018
Notification Time: 14:42 [ET]
Event Date: 06/01/2018
Event Time: 00:00 [EDT]
Last Update Date: 06/19/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GLENN DENTEL (R1DO)
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

TORNADO MISSILE VULNERABILITIES

"During the period of evaluation of tornado missile vulnerabilities and the potential impacts to technical specification (TS) plant equipment, it was determined that the power cables to a safety related motor control center (MCC) in the service water (SW) intake structure are not adequately protected from tornado generated missiles. During walk downs, it was identified that the installed SW pipe tunnel barrier is not adequate. A tornado could generate missiles capable of striking the power cables and rendering a SW MCC inoperable.

"These conditions are reportable per 10 CFR 50.72(b)(3)(ii)(B) and per 10 CFR 50.72(b)(3)(v)(D).

"This condition is being addressed in accordance with NRC enforcement guidance provided in Enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado- Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents.

"The NRC Resident Inspector has been notified."

The licensee will be notifying the Lower Alloways Creek Township.

* * * UPDATE ON 6/18/2018 AT 1604 EDT FROM JUSTIN HARGRAVE TO RICHARD SMITH * * *

"During subsequent walk downs, PSEG [Public Service Enterprise Group] identified that both the Unit 1 and Unit 2 turbine driven auxiliary feedwater pumps are also not adequately protected from tornado generated missiles. The steam exhaust pipe could be potentially impacted and cause crimping that could reduce steam exhaust flow and pump capacity. EN 53438 is updated to include both Salem units and these additional components.

"This condition is being addressed in accordance with NRC enforcement guidance provided in enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents."

The NRC Resident Inspector has been notified.

The licensee will be notifying the Lower Alloways Creek Township.

Notified R1DO (Burritt).

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Part 21 Event Number: 53442
Rep Org: FRAMATOME INC.
Licensee: FRAMATOME INC.
Region: 1
City: LYNCHBURG   State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: GAYLE ELLIOTT
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/02/2018
Notification Time: 14:32 [ET]
Event Date: 05/31/2018
Event Time: 00:00 [EDT]
Last Update Date: 06/02/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
JAMIE HEISSERER (R2DO)
PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 NOTIFICATION - FAILURE OF RELAYS TO CHANGE STATE

The following report was received via a fax:

"Identification of Basic Activity:
Eaton NBF66F Relay

"Basic Activity Supplied By:
Framatome Inc.

"Nature of Defect:
While performing analysis on AC Eaton NBF relays, Framatome discovered that, unless a specific application technique is utilized while applying epoxy to the pin within the crossbar, the potential for the epoxy to become foreign material is introduced. This foreign material could migrate to the area between the moving and stationary magnets, preventing the relay from completing its change of state when called upon. This condition does not occur in the de-energized direction. Framatome has not been notified of any occurrence of this condition. A different epoxy application technique was utilized between 2008 and May of 2013 on relays provided to HB Robinson (the only customer requiring the epoxy application by Framatome). Thus, a potential for this defect is limited to those relays provided during that time period.

"Defect Determination Date:
This issue was determined to be a 10 CFR 21 defect on May 31, 2018.

"Number and Location of Basic Components:
307 potentially affected safety related relays with epoxy applied to their relay pins were supplied to the H.B. Robinson nuclear plant.

"Corrective Actions to Date:
The application process was reevaluated and revised in 2013.

"Advice related to the Defect:
Framatome is working to provide advice to the customer on the path forward related to this defect."

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Power Reactor Event Number: 53443
Facility: BRAIDWOOD
Region: 3     State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACOB EILERTSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/04/2018
Notification Time: 14:00 [ET]
Event Date: 06/04/2018
Event Time: 09:20 [CDT]
Last Update Date: 06/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP ON LOWERING STEAM GENERATOR WATER LEVEL

"At 0920 CDT, Braidwood Unit 1 reactor was manually tripped due to lowering steam generator water levels following a trip of the 1C main feedwater pump. The cause of the 1C main feedwater pump trip is unknown at this time and is under investigation.

"Both trains of Braidwood Unit 1 auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.

"All systems responded as expected. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in standby and all safety systems available. There is no impact to Unit 2.

"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8-hr. notification."

All rods inserted into the core during the trip. Concerning the relief valves momentarily lifting and reseating, there is no known primary-to-secondary leakage.

The licensee has notified the NRC Resident Inspector.


Page Last Reviewed/Updated Friday, May 03, 2019
Friday, May 03, 2019