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Event Notification Report for December 5, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/02/2016 - 12/05/2016

** EVENT NUMBERS **


52359 52406

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Part 21 Event Number: 52359
Rep Org: SOR
Licensee: SOR
Region: 4
City: LENEXA State: KS
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MELANIA DIRKS
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2016
Notification Time: 17:50 [ET]
Event Date: 11/03/2016
Event Time: [CST]
Last Update Date: 12/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
RAY MCKINLEY (R1DO)
STEVE ROSE (R2DO)
MARK JEFFERS (R3DO)
VIVIAN CAMPBELL (R4DO)
PART 21/50.55 REACT (EMAI)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

PART 21 - NOTIFICATION OF DEVIATION - SOR QUALIFICATION TEST REPORT 9058-102

The following information was excerpted from a facsimile received by SOR:

Pursuant to the requirements of 10CFR Part 21, this letter notifies the NRC of a Part 21 condition. Irradiation testing performed since 1984 did not take into account all of the uncertainties associated with reported doses of gamma radiation to nuclear test specimens for qualification testing.

SOR contracted services with lsomedix in 1992 for the radiation aging that was performed per SOR nuclear qualification report 9058-102 Revision 1. Although SOR imposed Part 21 reporting requirements, lsomedix did not include SOR as part of their Part 21 notification. The Part 21 was brought to SOR's attention through an inquiry by a nuclear power station.

SOR requested a conference with Steris lsomedix which occurred on November 3, 2016. The teleconference confirmed that the subject radiation aging test results report would be affected by the Steris lsomedix Part 21. As a result, corrections are underway per qualification test report 9058-102 regarding the uncertainty calculations.

SOR does not have the capability to perform further evaluations to determine if a safety hazard exists as the specific customer application is unknown. The end user must confirm for each application that the qualified life dose + accident dose + 10% of accident dose is less than or equal to the corrected values.

SOR is currently identifying all customers potentially affected by this deviation. At the conclusion of this activity, SOR will notify the customers and the U.S. Nuclear Regulatory Commission in accordance with the requirements of 10 CFR Part 21.

* * * UPDATE FROM MELANIE DIRKS TO JOHN SHOEMAKER AT 1455 EST ON 12/2/16 * * *

The following is an excerpt of an updated Part 21 received via email:

"Corrections are now complete to test report 9058-102 regarding the uncertainty calculations. The calculations changed from 8% uncertainty to 9.6% uncertainty for the minimum irradiation aging.

"SOR does not have the capability to perform further evaluations to determine if a safety hazard exists as the specific customer application is unknown. The end user must confirm for each application that the qualified life dose + accident dose + 10% of accident dose is less than or equal to the above noted values."

Should you have any additional questions regarding this matter, please contact:

Linda Coutts
Inside Sales Representative
Email: lcoutts@sorinc.com
Tel 91.3-956-3071

Charles Lautner
Customer Service Manager
Email: clautner@sorinc.com
Tel 913-956-3070

Notified R1DO (Bower), R2DO (McCoy), R3DO (Stoedter), R4DO (Haire), NMSS_Events_Notification, and Part 21/50.55 Reactors via email.

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Power Reactor Event Number: 52406
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ERVIN LYSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/04/2016
Notification Time: 01:48 [ET]
Event Date: 12/03/2016
Event Time: 22:24 [EST]
Last Update Date: 12/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
FRED BOWER (R1DO)

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 CAUSED BY MAIN TURBINE TRIP

"On 12/3/16 at 2224 EST, Calvert Cliffs Unit-2 experienced an automatic reactor trip from full power due to a leak in the Unit-2 Main Turbine Electro-Hydraulic Control (EHC) system. The EHC leak caused the Unit-2 Main Turbine governor valves to close, resulting in a turbine trip and automatic reactor trip. The site Outage Control Center is manned, and investigation into the cause of the leak is underway. Unit-2 remains stable in Mode 3 with normal heat removal.

"Unit-1 remains at full power and was not affected by the trip."

The plant is in a normal shutdown electrical lineup. All Control rods fully inserted and no primary or secondary safety relief valves lifted during the trip.

The licensee has notified the NRC Resident Inspector. The licensee will be notifying Calvert County.

Page Last Reviewed/Updated Monday, December 05, 2016
Monday, December 05, 2016