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Event Notification Report for April 3, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/02/2014 - 04/03/2014

** EVENT NUMBERS **


49957 49961 49982 49985 49987 49988 49990 49991

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Agreement State Event Number: 49957
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: LSU, LOUISIANA STATE UNIVERSITY
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-0001-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/25/2014
Notification Time: 15:50 [ET]
Event Date: 03/07/2014
Event Time: [CDT]
Last Update Date: 03/25/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST HANDHELD TRACE DETECTOR CONTAINING NI-63 SOURCE

The following information was received via facsimile:

On the evening of March 11, 2014, the LA Department of Environmental Quality (DEQ) received a notification from Louisiana State University (LSU) that they had sent a Smiths Detection model Sabre 5000 handheld trace detector, containing 15 mCi of Ni-63, to the manufacturer for repairs. The device was sent by common carrier. The device was repaired and sent back to the common carrier's distribution center. The common carrier's records show that on December 20, 2013 at 1832 CST, the device was delivered and left at the front door of 3south LLC, the local distributor of Smiths Detection products. The records at 3south do not show receipt of the device. A claim was filed and the resolution took several weeks. The device was never located by the common carrier or the local distributor. The device was replaced by Smiths Detection.

DEQ considers this event closed.

Louisiana Event Report ID No.: LA-140002

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: 49961
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: BAKER HUGHES OILFIELD OPERATIONS
Region: 4
City: BROUSSARD State: LA
County:
License #: LA-6025-L01A,
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/26/2014
Notification Time: 11:06 [ET]
Event Date: 03/14/2014
Event Time: [CDT]
Last Update Date: 03/26/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

LOUISIANA AGREEMENT STATE REPORT - TWO ABANDONED WELL LOGGING SOURCES

The following information was obtained from the State of Louisiana via facsimile:

"Event Location: The source became stuck down hole at Deer Island CL&F 005, Terrebonne Parish, LA

"Event type: Two sources were in a device used to log down hole wells. The two sources became lodged down hole and Baker Hughes, after 'fishing', decided to cap the location and go around the sources. Cement and a whip-stock were used as deflection devices.

"Notifications: LDEQ [Louisiana Department of Environmental Quality] was notified of the lodged sources on March 17, 2014 @ 15:00 hrs. [CDT]. At that time, Baker Hughes requested to plug the lodged location and place a deflection device to continue their work. The request was granted.

"Event description: On March 17, 2014, Baker Hughes contacted LDEQ reporting that two well-logging sources became stuck down hole; a QSA Global 2.5 Ci Cs-137 source, SR# 90652B and a QSA Global 5 Ci Am/Be neutron source, SR# 77860B. A request to continue work was granted after a cement plug and a whip stock deflection device was placed at the location of the lodged sources. This incident was reported and will be abandoned and maintained by the requirements of LAC 33:XV.2051 and 2099 Appendix B.

"The Department [LDEQ] considers this event closed."

Louisiana Event Report ID No.: LA-140003

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Power Reactor Event Number: 49982
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARK HAWES
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/01/2014
Notification Time: 14:02 [ET]
Event Date: 04/01/2014
Event Time: 06:45 [EDT]
Last Update Date: 04/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
CHRISTOPHER CAHILL (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

VENTILATION FAN FAILURE AFFECTING RHRSW/ESW PUMP OPERABILITY AND EDG OPERABILITY

"At 0645 EDT on the morning of April 1, 2014, with James A. FitzPatrick Nuclear Power Plant (JAF) operating at 100 percent power, the Control Room received an alarm associated with the ventilation system for the 'B' division of the Residual Heat Removal Service Water (RHRSW) and Emergency Service Water (ESW) pump room. Investigation identified that the ventilation exhaust fan (73FN-3B) associated with this pump room had tripped due to thermal overload. The overload relay was reset at 0704 EDT and the fan automatically started; the fan is currently operable. During this period, the fan would not have automatically started.

"The ventilation systems for the RHRSW and ESW pump rooms are not included in the JAF Technical Specifications (TS), nor are they in the JAF Technical Requirements Manual (TRM). The ambient temperature limit in the RHRSW and ESW pump room was never challenged. However, with 73FN-3B non-functional, it is procedurally required to declare 10P-1B (RHRSW Pump B), 10P-1D (RHRSW Pump D) and 46P-2B (ESW Pump B) inoperable. The 'B' ESW pump cools the 'B' EDG subsystem, which would therefore also be inoperable. During this period, the 'A' EDG subsystem was inoperable for an emergent issue. Because the 'A' and 'B' EDG subsystems were concurrently inoperable for a period of approximately 45 minutes, this condition resulted in a loss of safety function for the Emergency Diesel Generators, which is reportable pursuant to 10 CFR 50.72(b)(3)(v)(A)."

Both affected emergency diesel generators were in the same division with another redundant division operable.

The licensee notified the NRC Resident Inspector and will be notifying the State of New York.


* * * UPDATE AT 1200 EDT ON 4/2/14 FROM CHRIS ADNER TO S. SANDIN * * *

The statement "Both affected emergency diesel generators were in the same division with another redundant division operable" is incorrect. Both divisions of emergency diesel generators were inoperable, since one of two available emergency diesel generators per division were inoperable at the time of this event.

The Licensee notified the NRC Resident Inspector.

Notified R1DO (Cahill).

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Power Reactor Event Number: 49985
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DAN CIFONELLI
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/02/2014
Notification Time: 08:42 [ET]
Event Date: 04/02/2014
Event Time: 01:23 [EDT]
Last Update Date: 04/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
CHRISTOPHER CAHILL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

SECONDARY CONTAINMENT INOPERABLE DUE TO TWO AIR LOCK DOORS OPEN SIMULTANEOUSLY

"At 0123 EDT on April 2, 2014, Nine Mile Point Unit 2 was in Mode 5, Refueling, and in the other specified condition of Operations with Potential for Draining the Reactor Vessel. During this condition both redundant personnel airlock doors were open at the same time in an airlock penetration of the reactor building. This condition represents a loss of Secondary Containment safety function. Technical Specification 3.6.4.1, Action A.1 was entered for the loss of Secondary Containment and was promptly exited when the doors were closed.

"Secondary containment being inoperable is an 8-hour report per 10 CFR 50.72(b)(3)(v)(C), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49987
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DON ROGERS
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/02/2014
Notification Time: 14:42 [ET]
Event Date: 04/02/2014
Event Time: 14:01 [EDT]
Last Update Date: 04/02/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAVE PASSEHL (R3DO)
TIM McGINTY (NRR)
WILLIAM GOTT (IRD)
JENNIFER UHLE (ET)
CYNTHIA PEDERSON (R3RA)

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

UNUSUAL EVENT DECLARED DUE TO TOXIC GAS RELEASE

"Release of toxic or flammable gas affecting the Protected Area boundary deemed detrimental to the safe operation of the plant."

Emergency Action Level entered: MU-1. The leak is Trichloroethylene (TCE) gas used in the Off-Gas building. The Off-Gas building ground and basement levels were evacuated due to the leak. There is no safe-shutdown equipment located in the Off-Gas building. The licensee is working to isolate the leak.

The licensee informed the NRC Resident Inspector.

The licensee notified the State of Ohio and the local counties.

Notified DHS SWO, FEMA Ops Center, NICC Watch Officer, DOE Ops Center, USDA Ops Center, HHS Ops Center, and Nuclear SSA via email.

* * * UPDATE AT 1630 EDT ON 4/2/14 FROM DON ROGERS TO S. SANDIN * * *

The licensee notified the following outside agencies: U.S. EPA National Response Center, Ohio EPA, Perry Township Fire Department, Lake County Emergency Planning Committee, and the U.S. Coast Guard.

Notified R3DO (Passehl).

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Power Reactor Event Number: 49988
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: WILLIAM STRICKLAND
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/02/2014
Notification Time: 15:32 [ET]
Event Date: 04/02/2014
Event Time: 13:40 [CDT]
Last Update Date: 04/02/2014
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVE PASSEHL (R3DO)
TIM McGINTY (NRR)
WILLIAM GOTT (IRD)
JENNIFER UHLE (ET)
CYNTHIA PEDERSON (R3RA)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 8 Power Operation 0 Hot Shutdown

Event Text

ALERT DECLARED DUE TO FIRE IN UNIT 2 TURBINE BUILDING

"Quad Cities Unit 2 Alert Classification (HA3) Due to Fire.

"On April 2, 2014, at 1340 CDT, an ALERT was declared due to a fire in the Unit 2 turbine building. Prior to declaring the ALERT, Unit 2 was manually scrammed at 1302 CDT. All control rods inserted and all automatic isolations actuated as designed. The Main Steam Isolation Valves were manually closed. The fire has been extinguished. Unit 2 is currently in Hot Shutdown.

"The cause of the event is under investigation.

"Unit 1 remains at 100% power.

"The Senior Resident Inspector has been notified of the event."

Unit 2 is still being supplied from off-site power and is in a normal shutdown electrical lineup with the exception of Bus 29-1 (480 VAC safety bus) that was deenergized. One Unit 2 emergency diesel generator is inoperable due to the loss of power to its cooling water pump.

The licensee has notified the State and local agencies.

Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, USDA OPS Center, EPA EOC, FDA EOC, and Nuclear SSA via email.

* * * UPDATE FROM MIKE HAYES TO DONG PARK AT 2252 EDT ON 04/02/2014 * * *

At 2132 CDT on April 2, 2014, the licensee terminated the Unit 2 Alert declaration. Unit 2 is stable in Mode 3 (Hot Shutdown). Unit 2 is proceeding to Mode 4 (Cold Shutdown) on shutdown cooling.

The licensee notified the NRC Resident Inspector and the State emergency agencies.

Notified the IRD (Gott), R3DO (Passehl), and NRR EO (McGinty).

Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, USDA OPS Center, EPA EOC, FDA EOC, and Nuclear SSA via email.

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Power Reactor Event Number: 49990
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: AARON MICHALSKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/02/2014
Notification Time: 21:08 [ET]
Event Date: 04/02/2014
Event Time: 16:00 [EDT]
Last Update Date: 04/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
STEVEN VIAS (R2DO)

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

Event Text

FIRE RELATED UNANALYZED CONDITION THAT COULD IMPACT CREDITED SAFE SHUTDOWN ANALYSIS

"This is a non-emergency notification. As part of converting to NFPA (National Fire Protection Association) 805, Catawba determined that there are conditions that may not ensure required equipment remains available under certain postulated fire scenarios. The determination concluded that the effects of a postulated fire in specific fire areas could prevent critical systems or components from performing their intended functions, potentially resulting in the inability to achieve and maintain safe shutdown.

"Affected fire areas are as follows (elevation numbers are in parentheses):
1. Residual Heat Removal/Containment Spray Pump Room (522)
2. Unit 2 Auxiliary Feedwater Pump Room (543)
3. Unit 1 Auxiliary Feedwater Pump Room (543)
4. Auxiliary Building Common Area (543)
5. Unit 2 Electrical Penetration Room (560)
6. Unit 1 Electrical Penetration Room (560)
7. 2ETB Switchgear Room (560)
8. 1ETB Switchgear Room (560)
9. Unit 2 Battery Room (554)
10. Unit 1 Battery Room (554)
11. Auxiliary Building Common Area (560)
14. Unit 2 ETA Switchgear Room (577)
15. Unit 1 ETA Switchgear Room (577)
17. Unit 1 Cable Room (574)
18. Auxiliary Building Common Area (577)
20. Unit 1 Electrical Penetration Room (594)
45. Unit 1 Cable Room Corridor (574)
46. Unit 2 Cable Room Corridor (574)
48. Unit 2 Inside Doghouse
49. Unit 1 Inside Doghouse
RB1. Unit 1 Reactor Building
RB2. Unit 2 Reactor Building

"This is reportable as an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B). Fire watches have been implemented as appropriate in response to this determination. This condition has been entered into the Catawba Corrective Action Program.

"The NRC Resident Inspector will be notified."

The licensee will notify the State of North Carolina and South Carolina and well as the local counties.

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Power Reactor Event Number: 49991
Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WESLEY HILL
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/03/2014
Notification Time: 02:44 [ET]
Event Date: 04/03/2014
Event Time: 01:00 [EDT]
Last Update Date: 04/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
STEVEN VIAS (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

REACTOR COOLANT SYSTEM SAFETY INJECTION LINE ULTRASONIC TEST INDICATION

"On Tuesday April 1, 2014, while performing planned inspections of Reactor Coolant System piping welds, two flaw indications were identified on a 1.5 inch Safety Injection Line connection to the Reactor Coolant System piping. On Wednesday April 2, 2014, after confirmatory inspections and evaluation, one of the two flaw indications was determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii) as a Degraded Condition. A repair plan is being developed. There is no impact on current Unit 2 refueling operations. This condition and repair have no impact to the health and safety of the public or employees.

"The NRC Resident Inspector was notified."

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014