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Event Notification Report for February 10, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/09/2017 - 02/10/2017

** EVENT NUMBERS **


52394 52524 52525 52528 52542

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Part 21 Event Number: 52394
Rep Org: ENERCON
Licensee: ENERCON
Region: 1
City: KENNESAW State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: NICK EGGEMEYER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2016
Notification Time: 11:56 [ET]
Event Date: 09/28/2016
Event Time: [EST]
Last Update Date: 02/09/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
JAMES DWYER (R1DO)
AARON McCRAW (R3DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART-21 NOTIFICATION - DESIGN BASIS ERRORS USING FLO-2D SOFTWARE

The following report was received via e-mail:

"This letter serves as an Interim Report in accordance with 10 CFR 21.21 pertaining to a potential defect associated with a design basis calculation delivered to First Energy Nuclear Operating Company's Perry Nuclear Power Plant. Subsequent to delivering this calculation, FLO-2D software errors were identified which resulted in erroneous outputs that affect the local intense precipitation calculation. These errors were discovered on September 28, 2016, at which time, ENERCON generated a Corrective Action Report (CAR) to address the issue. ENERCON has initiated a reevaluation of the calculation using the latest version of the software that will correct the errors in the calculation.

"An evaluation of the reportability of this issue in accordance with 10 CFR Part 21 is not able to be completed within the 60-day evaluation period due the need to verify and validate the latest version of the software and then complete all the analysis required for updating the calculation. This evaluation is being tracked by CAR 2016-0335 and will be completed no later than February 10, 2017.

"If you have any questions or need further clarifying information, please contact Nick Eggemeyer, Corporate Quality Assurance Manager, at (770) 590-2031."


* * * UPDATE AT 0910 EST ON 12/13/2016 FROM TIMOTHY CLEARY TO MARK ABRAMOVITZ * * *

The following update was received via e-mail:

"This letter serves as an amendment to the 10 CFR 21.21 Interim Report filed on November 23, 2016, pertaining to a potential defect associated with a design basis calculation delivered to First Energy Nuclear Operating Company's Perry Nuclear Power Plant. Subsequent to delivery of the calculation, a standard, periodic review of the FLO-2D Pro software supplier website indicated that a new build of this software (version 16.06.16) had been issued. It replaced the software build (version 14.08.09) that was used for the above referenced design calculation. As a result of the model revision associated with FLO-2D, it was determined that the outputs were impacted which could affect this design basis calculation. These output changes were discovered on September 28, 2016, at which time ENERCON generated a Corrective Action Report (CAR) to address the issue. ENERCON has initiated a reevaluation of the calculation using this new build of the FLO-2D Pro software.

"An evaluation of the reportability of this issue in accordance with 10 CFR Part 21 is not able to be completed within the 60-day evaluation period due the need to verify and validate the latest version of the software and then complete all the analysis required for updating the calculation. This evaluation is being tracked by CAR 2016-0335 and will be completed no later than February 10, 2017.

"If you have any questions or need further clarifying information, please contact Nick Eggemeyer, Corporate Quality Assurance Manager, at (770) 590-2031."

Notified the R1DO (Schroeder), R3DO (Cameron), and Part 21 Group (via e-mail).


* * * UPDATE FROM TIMOTHY CLEARY TO DONALD NORWOOD AT 1602 EST ON 2/9/2017 * * *

The following information was received via E-mail:

"This letter serves as an evaluation summary in accordance with 10 CFR 21.21 pertaining to a potential defect associated with a design basis calculation delivered to FirstEnergy Nuclear Operating Company's Perry Nuclear Power Plant. The 10 CFR 21.21 Interim Report was filed on November 23, 2016. An Amendment to the 10 CFR 21.21 Interim Report was filed on December 12, 2016.

"Subsequent to the filing of the Amendment to the Interim Report, the updated FLO-2D software, build 16.06.16, was verified and validated and a re-analysis performed. A comparison between the original analysis and the updated analysis using the updated software was then performed. This analysis indicates flood water level changes assumed in the Perry Nuclear Plant flooding analyses are small, -0.14 feet to +0.16 feet (-1.6 inches to +1.9 inches).

"The comparative results between the two analyses were provided to First Energy Company's Perry Nuclear Power Plant on February 3, 2017. Perry Nuclear Plant staff are continuing to review these results in order to complete the determination of whether the change in flood water levels results in additional reporting requirements.

"If you have any questions or need further clarifying information, please contact Nick Eggemeyer, Corporate Quality Assurance Manager, at (770) 590-2031."

Notified the R2DO (Sandal), R3DO (Kunowski), and Part 21 Group (via e-mail).

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Non-Agreement State Event Number: 52524
Rep Org: HENRY FORD HOSPITAL
Licensee: HENRY FORD HOSPITAL
Region: 3
City: DETROIT State: MI
County:
License #: 21-04109-16
Agreement: N
Docket:
NRC Notified By: ALAN JACKSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/01/2017
Notification Time: 15:13 [ET]
Event Date: 01/31/2017
Event Time: 10:51 [EST]
Last Update Date: 02/01/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
Person (Organization):
ERIC DUNCAN (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

POTENTIAL MEDICAL EVENT

A patient at the Henry Ford Hospital Interventional Radiology Department was prescribed a Y-90 Theraspheres treatment of 60 Gray to the left lobe of the liver. The Interventional Radiologist administered 46 Gray total to both the right and the left lobe of the liver. The referring physician has been notified and the licensee has notified the patient. It is believed that this event will not result in any harm to the patient. The licensee is in the process of determining corrective action to prevent reoccurrence.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Agreement State Event Number: 52525
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OLSSON ASSOCIATES
Region: 4
City: OMAHA State: NE
County:
License #: 02-34-01
Agreement: Y
Docket:
NRC Notified By: LARRY HARISIS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/01/2017
Notification Time: 15:41 [ET]
Event Date: 02/01/2017
Event Time: 11:00 [CST]
Last Update Date: 02/01/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST/FOUND MOISTURE DENSITY GAUGE

The following report was received via e-mail:

"Nebraska Department of Health and Human Services, Office of Radiological Health was notified on February 1, 2017, by a representative from Olsson Associates, of a loss and subsequent return of licensed material from the back of a pickup truck on Wednesday, February 1, 2017, in Omaha, Nebraska. The licensed material is a Troxler 3400 series moisture density gauge, serial number 19309, containing 9 mCi of Cs-137 and 44 mCi of Am:Be. The licensee reported to the State that an employee placed the licensed material on the back of the pickup truck and not in the yellow shipping case, and drove away from a temporary jobsite. While the employee made a right hand turn, the Troxler gauge fell out of the truck. A vehicle that was passing nearby found the Troxler gauge and returned it to the licensee about 10 minutes after the employee notified the Radiation Safety Officer. The gauge was visually inspected and no physical damage was found. The gauge was also surveyed to confirm the presence of the source. No elevated readings were found. The licensee has locked the gauge in the yellow shipping container and removed it from service. A follow-up site visit is scheduled and a 30 day written report is to follow."

Nebraska Event: NE-17-0001

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: 52528
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: KENNECOTT UTAH COPPER, LLC
Region: 4
City: SOUTH JORDAN State: UT
County:
License #: UT 1800289
Agreement: Y
Docket:
NRC Notified By: GWYN GALLOWAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/02/2017
Notification Time: 20:44 [ET]
Event Date: 02/02/2017
Event Time: 13:30 [MST]
Last Update Date: 02/02/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE SHUTTER FAILED TO CLOSE DURING PREVENTATIVE MAINTENANCE

The following information was provided by the State of Utah via email:

"DWMRC [Utah Department of Environmental Quality, Division of Waste Management and Radiation Control] was notified of the event at 4:26 PM MST, on February 2, 2017.

"The licensee indicated that an employee had been assigned to conduct some preventative maintenance checks on an Ohmart Vega Gauge, Model SH-1, Serial Number 2199CG. At about 1:30 PM MST, the employee attempted to shut the gauge's shutter and one of the two screws attaching the handle to the shutter sheared off. The shutter could not be closed after that because the handle would just spin around. The gauge contained 50 mCi (as assayed 11/01) of Cs-137. The gauge is located about 10 feet above the walkway in the smelter/slag mill. The beam is running parallel to the ground and poses no danger to individuals in the building."

The licensee will remove the gauge and send it to an authorized repair facility.

UT Event Report ID No.: UT170002

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Power Reactor Event Number: 52542
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: ADAM SCHUERMAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/08/2017
Notification Time: 17:06 [ET]
Event Date: 02/08/2017
Event Time: 08:51 [CST]
Last Update Date: 02/10/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER EMERGENCY VENTILATION SYSTEM INOPERABLE

"At 0851 CST on Wednesday, February 8th, 2017, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) Emergency Ventilation System was emergently declared inoperable due to a failure of the outside air damper to reposition. This resulted in the inability for the TSC ventilation to maintain the required air flow to support habitability during emergency conditions. Actions are being taken to repair damper to restore functionality of the TSC ventilation system. In the interim, station procedures provide guidance to relocate the TSC to an alternate facility. This event is being reported under 10 CFR 72(b)(3)(xiii), Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).

"The NRC Resident Inspector has been notified."

* * * UPDATE PROVIDED BY RYAN CHAMBERLAIN TO JEFF ROTTON AT 0418 EST ON 02/10/2017 * * *

"At 0108 CST on February 10, 2017, Dresden TSC ventilation has been restored and is now functional.

"The NRC Resident Inspector has been notified."

Notified R3DO (Kunowski).

Page Last Reviewed/Updated Friday, February 10, 2017
Friday, February 10, 2017