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Event Notification Report for January 17, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/13/2017 - 01/17/2017

** EVENT NUMBERS **


52475 52487 52490 52491 52492

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Agreement State Event Number: 52475
Rep Org: COLORADO DEPT OF HEALTH
Licensee: CHATEAU RESIDENCE CLUB
Region: 4
City: BEAVER CREEK State: CO
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/05/2017
Notification Time: 09:26 [ET]
Event Date: 01/04/2017
Event Time: 11:30 [MST]
Last Update Date: 01/05/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGN

The following information was received via e-mail:

"Detail: Chateau Residence Club had a fire inspection that required the removal of two expired tritium exit signs. Encore Electric was contracted to remove the signs approximately around 10-13-16. According to Encore, the staff person performing the work tossed the exit signs in the trash. Encore Electric was informed by CDPHE [Colorado, Department of Public Health and Environment]/General License Coordinator to complete a corrective action to include tracking to disposal of all tritium exit signs, writing a report explaining their safety, handling and disposal of radioactive tritium signs. Colorado Rules and Regulations Pertaining to Radiation Control were provided to Encore Electric as guidance to complete the corrective action.

"Manufacturer: Best Lighting Products aka Forever Light.,
Model Number: SLXYU1BB10,
Serial Numbers: 215656 & 215657,
Isotope: H-3,
Activity: 7.09 Ci

"Event Description: Due to the continuous lack of information from manufacturing companies reaching the responsible parties at the destination where exit signs are to be installed; companies have no understanding of the regulations for products containing tritium. The General License Coordinator at CDPHE provided the Chateau Residence Club management a copy of the Colorado Rules and Regulations Pertaining to Radiation Control and the NRC guidelines K & L. The Chateau Residence Club uses sub contractors for services like fire safety and lighting. Encore Electric was unaware of the regulations for Tritium Exit Signs."

Event Report ID No.: CO17-0001

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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Part 21 Event Number: 52487
Rep Org: CURTISS WRIGHT ELECTRO MECHANICAL C
Licensee: WESTINGHOUSE ELECTRIC CORPORATION
Region: 1
City: CHESWICK State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAY GARDINER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/13/2017
Notification Time: 13:56 [ET]
Event Date: 01/12/2017
Event Time: [EST]
Last Update Date: 01/13/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
SCOTT SHAEFFER (R2DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART 21 INTERIM REPORT - EXCESS MATERIAL CONDITION ON THE CASING FOR THE AP1000 REACTOR COOLANT PUMP

The following summary was excerpted from report #EMD-GM-17-02, provided by the Curtis-Wright Electro-Mechanical Corporation:

"Curtiss-Wright Electro-Mechanical Corporation (CW-EMO) has identified a condition which is currently being evaluated to determine if a significant safety hazard exists in the casing for the AP1000 Reactor Coolant Pump (RCP). The investigation is underway, but will not be completed within the required 60 days from discovery as required by paragraph 21.21(a)(1) of the regulation. This submission constitutes CW-EMD's interim report on the condition in accordance with paragraph 21.21(a)(2) of the regulation.

"Casings for the AP1000 Reactor Coolant Pump. The casings have an excess material condition in the transition region between the cast bowl and the suction nozzle. The condition is a discontinuous (non-tangential) axisymmetric feature between the cast bowl region and machined suction nozzle OD. The as-built transition feature on the casings has not been analyzed and is not included in CW-EMO Engineering Memorandum 7242, Revision 1, Volume 1, which is the applicable generic design report for the AP1000 RCP casing and main closure.

"At present, the following domestic deliveries have been made:
- 8 casings have been provided to V.C. Summer Units 2 and 3.
- 8 casings have been provided to Vogtle Units 3 and 4.

"Name and address of the individual or individuals informing the Commission:
Brian W. Eckels, General Manager
Curtiss-Wright Electro-Mechanical Corporation
1000 Wright Way Cheswick, Pa 15024"

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Power Reactor Event Number: 52490
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: HENDRIK VERWEY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/14/2017
Notification Time: 13:09 [ET]
Event Date: 01/14/2017
Event Time: 06:13 [EST]
Last Update Date: 01/14/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Startup 0 Hot Shutdown

Event Text

DEGRADED CONDITION DUE TO THROUGH-WALL LEAK

"At 0613 EST on 1/14/2017, with the unit in Mode 2 at 0 percent power at the start of Refueling Outage 22, Drywell inspection identified a through-wall leak on the 3/4-inch vent line off the bonnet of valve 02MOV-43A, Reactor Water Recirc Pump A Suction Isolation Valve, in the Reactor Coolant System (RCS) loop inside the Primary Containment. This condition constitutes a defect in the primary coolant system.

"This event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) as a condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded."

The licensee has notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 52491
Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: DAVE SPANGLOR
HQ OPS Officer: STEVEN VITTO
Notification Date: 01/16/2017
Notification Time: 15:55 [ET]
Event Date: 01/16/2017
Event Time: 09:15 [EST]
Last Update Date: 01/16/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
SCOTT SHAEFFER (R2DO)
ANGELA MCINTOSH (NMSS)
NMSS_EVENTS_NOTIFIC (EMAI)
FFD GROUP (EMAI)

Event Text

FITNESS-FOR- DUTY
A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the site has been terminated.

The Licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 52492
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MICHAEL MCDONNELL
HQ OPS Officer: STEVEN VITTO
Notification Date: 01/16/2017
Notification Time: 16:39 [ET]
Event Date: 01/16/2017
Event Time: 11:55 [EST]
Last Update Date: 01/16/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

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

Event Text

FAILURE OF REACTOR BUILDING ISOLATION DAMPERS TO ISOLATE

"On January 16, 2017, with the reactor at 100 percent and the mode switch in RUN, Pilgrim Station was performing preventative maintenance of secondary containment isolation dampers when dampers AO-N-82 and AO-N-83, refueling floor supply isolation dampers, failed to fully close when the control switches were taken to close.

"This 8-hour non-emergency notification is being made in accordance with 10 CFR 50.72(b)(3)(v), Any event or condition that at the time discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.

"The reactor building isolation dampers were cleaned and lubricated and post-work tested and timed in accordance with station procedures to verify that they had satisfactory closing times. Pilgrim Nuclear Power Station has returned the dampers to Operable status.

"The licensee will notify the Commonwealth of Massachusetts."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, January 17, 2017
Tuesday, January 17, 2017