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Event Notification Report for March 8, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/07/2016 - 03/08/2016

** EVENT NUMBERS **


51475 51759 51771 51772 51773 51775

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Agreement State Event Number: 51475
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: WAYNE COUNTY WELL SURVEYS
Region: 3
City: FAIRFIELD State: IL
County:
License #: IL-01804-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/16/2015
Notification Time: 12:12 [ET]
Event Date: 10/15/2015
Event Time: [CDT]
Last Update Date: 03/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HIRONORI PETERSON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ILTAB (EMAI)

This material event contains a "Category 3 " level of radioactive material.

Event Text

ILLINOIS AGREEMENT STATE REPORT - LOST AMERICIUM/BERYLLIUM SOURCE

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

"The Radiation Safety Officer of Wayne County Well Surveys contacted the Agency [Illinois Emergency Management Agency] on Friday morning, October 16, 2015, to report the loss of a 3 Ci Am-241/Be source. A description of the container which holds the source was provided as well as anticipated radiation levels, markings and the route along which was followed when the container was most likely lost. The licensee had conducted visual surveys along this route with no success. The Agency dispatched teams with appropriate radiation detection instrumentation to traverse the route. The search is currently underway. Local law enforcement and emergency managers have also been advised of the matter."

The RSO last verified possession of the source on June 2, 2015 during a leak test. The search is being concentrated on several rural roads between Fairfield and Decatur, IL. The loss is believed to have happened sometime in the middle of September.

Source information: QSA Global; model number AMNK8208; serial number 82989B

IL Report Number: IL15020

* * * UPDATE FROM DAREN PERRERO TO HOWIE CROUCH AT 1528 EST ON 4/7/16 * * *

On March 4, 2016, the State was informed that the source was returned, intact, by a citizen to the licensee. The source was still locked in its transport case and was not tampered with. The licensee swiped the source with negative results.

The State of Illinois considers this event closed.

Notified R3DO (Riemer) and NMSS Events resource (email).

THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL

Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Non-Agreement State Event Number: 51759
Rep Org: SAINT ALPHONSUS HEALTH SYSTEM
Licensee: SAINT ALPHONSUS HEALTH SYSTEM
Region: 4
City: BOISE State: ID
County:
License #: 11-27396-01
Agreement: N
Docket:
NRC Notified By: ERIC COLIANNI
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/26/2016
Notification Time: 18:36 [ET]
Event Date: 02/26/2016
Event Time: 11:20 [MST]
Last Update Date: 02/26/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
JACK WHITTEN (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

MEDICAL EVENT - UNDERDOSE TO PATIENT

Notification from the licensee's Radiation Safety Officer, of a medical event that occurred on February 26, 2016 at 1120 MST, in which the Y-90 SIR-Sphere dose delivered to the patient's liver was less than the prescribed dose. The intended dose to the patient was 86 mCi, however, most of the dose remained in the catheter and it is estimated the patient received 13 mCi. The patient and attending physician have been informed and there was no harm to the patient.

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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Power Reactor Event Number: 51771
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES PETTY
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/07/2016
Notification Time: 02:00 [ET]
Event Date: 03/06/2016
Event Time: 20:00 [CST]
Last Update Date: 03/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
KENNETH RIEMER (R3DO)

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

UNANALYZED CONDITION INVOLVING DIESEL DRIVEN AUXILIARY FEEDWATER PUMP AIR INTAKES

"The Auxiliary Feedwater (AF) system at Braidwood automatically supplies feedwater to the Steam Generators (SG) to remove decay heat from the Reactor Coolant System following a loss of normal feedwater supply. The AF System consists of a motor driven pump (A) and a diesel driven pump (B) configured into two trains for each unit. Each pump provides 100% of the required AF capacity to the SGs as assumed in the accident analysis. One pump at full flow is sufficient to remove decay heat and cool the unit to Residual Heat Removal (RHR) entry conditions. The diesel driven AF pump is powered from an independent diesel whose combustion air intake is located in the Seismic Category II (non-seismically qualified) Turbine Building but the diesel and pump are located in the Seismic Category I (seismically qualified) Auxiliary Building.

"During the ongoing NRC Component Design Basis Inspection at Braidwood Station, Inspectors asked about the acceptability of the diesel combustion air intake being located in the non-seismic Turbine Building. During the review of available documentation related to the AF diesel engine combustion air intake, it was identified that the documentation did not support operation of the diesel with High Energy Line Break (HELB) environmental conditions in the Turbine Building. This has been reviewed and determined to be applicable to Braidwood Station Units 1 and 2. Specifically, prior evaluations did not account for air displacement by steam release during the event. After running different models for the Turbine Building HELB, diesel driven AF pump operability was supported for all but the Main Feedwater (FW) HELB. For the FW HELB, the best air density obtained failed to remain above the required levels deemed acceptable for engine operation and remained suppressed for extended periods of time. Additional efforts to qualify the FW piping in the Turbine Building for an Operating Basis Earthquake (OBE) to eliminate this piping from HELB considerations were not successful. This condition applies to both Units 1 and 2 but does not affect the motor driven AF pumps. This event does not constitute a loss of safety function at the point of discovery because the Braidwood opposite train motor driven AF pumps were operable on both Units 1 and 2.

"This event is reportable per 10 CFR 50.72(b)(3)(ii)(B) for 'any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.'

"The licensee has notified the NRC Resident Inspector."

The licensee entered a 72-hour Action Statement and is preparing to address the issue with a configuration change.

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Power Reactor Event Number: 51772
Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ALLEN SHEPHARD
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/07/2016
Notification Time: 11:18 [ET]
Event Date: 03/07/2016
Event Time: 04:00 [CST]
Last Update Date: 03/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
NICK VALOS (R3DO)

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

UNANALYZED CONDITION INVOLVING DIESEL DRIVEN AUXILIARY FEEDWATER PUMP AIR INTAKES

"The Auxiliary Feedwater (AF) system at Byron automatically supplies feedwater to the Steam Generators (SG) to remove decay heat from the Reactor Coolant System following a loss of normal feedwater supply. The AF System consists of a motor driven pump (A) and a diesel driven pump (B) configured into two trains for each unit. Each pump provides 100% of the required AF capacity to the SGs as assumed in the accident analysis. One pump at full flow is sufficient to remove decay heat and cool the unit to Residual Heat Removal (RHR) entry conditions. The diesel driven AF pump is powered from an independent diesel whose combustion air intake is located in the Seismic Category II (non-seismically qualified) Turbine Building but the diesel and pump are located in the Seismic Category I (seismically qualified) Auxiliary Building.

"During the ongoing NRC Component Design Basis Inspection at the sister Braidwood Station, inspectors asked about the acceptability of the diesel combustion air intake being located in the non-seismic Turbine Building. During the review of available documentation related to the AF diesel engine combustion air intake, it was identified that the documentation did not support operation of the diesel with High Energy Line Break (HELB) environmental conditions in the Turbine Building. This has been reviewed and determined to be applicable to Byron Station Units 1 and 2. Specifically, prior evaluations did not account for air displacement by steam release during the event. After running different models for the Turbine Building HELB, diesel driven AF pump operability was supported for all but the Main Feedwater (FW) HELB. For the FW HELB, the best air density obtained failed to remain above the required levels deemed acceptable for engine operation and remained suppressed for extended periods of time. Additional efforts to qualify the FW piping in the Turbine Building for an Operating Basis Earthquake (OBE) to eliminate this piping from HELB considerations were not successful. This condition applies to both Units 1 and 2 but does not affect the motor driven AF pumps. This event does not constitute a loss of safety function at the point of discovery because the Byron opposite train motor driven AF pumps were operable on both Units 1 and 2. This event is reportable per 10 CFR 50.72(b)(3)(ii)(B) for 'any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.'

"The licensee has notified the NRC Resident Inspector."

The licensee entered a 72-hour Action Statement and engineering is analyzing the issue.

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Power Reactor Event Number: 51773
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: STEVEN VITTO
Notification Date: 03/07/2016
Notification Time: 11:29 [ET]
Event Date: 03/07/2016
Event Time: 08:37 [EST]
Last Update Date: 03/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JON LILLIENDAHL (R1DO)
SCOTT MORRIS (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 92 Power Operation 92 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO FATALITY ONSITE

"At the Limerick Generating Station, an individual experiencing a non-occupational illness was taken to a local medical facility. The individual was not contaminated. Subsequently, Limerick was informed that the individual has suffered a fatality."

The individual was a contract employee and was located in a clean break area, within the protected area, when the individual became ill.

The licensee has notified the NRC Resident Inspector and OSHA.

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Power Reactor Event Number: 51775
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TOM OGGERI
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/07/2016
Notification Time: 17:12 [ET]
Event Date: 03/07/2016
Event Time: 10:18 [EST]
Last Update Date: 03/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JON LILLIENDAHL (R1DO)

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

Event Text

EMERGENCY DIESEL GENERATORS AUTO-STARTED ON VALID ACTUATION SIGNAL

"During Emergency Diesel Generator (EDG) surveillance testing, the normal 480V Bus 3A supply breaker tripped open. All EDGs auto-started as per plant design. During restoration of normal power to the 480V Buses, 23 EDG output breaker opened on overcurrent. All plant systems responded as per design.

"There was no loss of core cooling since steam generators were coupled with an operational RCP. No other ESF [Engineered Safety Feature] equipment automatically started.

"The 480V Bus 3A normal supply breaker was replaced and the cause of both issues is under investigation.

"Indian Point Unit 2 remains in a stable MODE 5 condition with all 480V Buses energized via normal power. The NRC Resident has been informed."

The licensee will inform the New York Public Service Commission.

Page Last Reviewed/Updated Tuesday, March 08, 2016
Tuesday, March 08, 2016