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Event Notification Report for March 31, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/30/2016 - 03/31/2016

** EVENT NUMBERS **


51813 51818 51830 51831 51836 51837

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Agreement State Event Number: 51813
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: HCA HEALTH SERVICES OF OKLAHOMA
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: OK-21035-01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: VINCE KLCO
Notification Date: 03/22/2016
Notification Time: 11:07 [ET]
Event Date: 01/22/2016
Event Time: 12:00 [CDT]
Last Update Date: 03/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION FOUND ON SHIPMENT

The following report was excerpted from an Oklahoma Department of Environmental Quality via email:

"On January 22, 2016 the RSO [Radiation Safety Officer] reported that a package received by the University of Oklahoma Health Science Center pharmacy (OK-03176-04MD) was found to have 2,118,858 cpm of removable contamination. The outside of the package was surveyed at 30 mR/hr, the reading at 1 meter was 0.12 mR/hr. The contaminant was identified as Tc-99m and was confined to the outside of the package. The package contained a number of empty unit dose syringes in lead pigs and had been returned from HCA Health Services of Oklahoma which administers the University of Oklahoma Medical Center. The package was transported by the pharmacy."

Refer to NRC Event #51661.

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Non-Agreement State Event Number: 51818
Rep Org: BOTSFORD CANCER CENTER
Licensee: BOTSFORD CANCER CENTER
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: MISBAH GULAM
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/23/2016
Notification Time: 16:12 [ET]
Event Date: 03/22/2016
Event Time: [EDT]
Last Update Date: 03/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

BRACHYTHERAPY EQUIPMENT MALFUNCTION

On 3/22/16, a medical event occurred from a high dose rate brachytherapy treatment of the prostate. After the first catheter was delivered, the treatment console reported an error. The medical physicist went inside the treatment room with the survey meter to verify that the source retracted and the connections were fine.

The vendor was called out to the facility, and parts had to be replaced. The treatment was stopped, and the patient was notified.

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: 51830
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/30/2016
Notification Time: 02:13 [ET]
Event Date: 03/29/2016
Event Time: 22:56 [EDT]
Last Update Date: 03/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMES DWYER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE

"On March 29, 2016 at 2256 [EDT], Secondary Containment Zone 2 (Unit 2 Reactor Building) differential pressure lowered to 0.0 [inches] WG [water gauge] due to a failed closed discharge damper on the in service Zone 2 exhaust fan. Required differential pressure per SR 3.6.4.1.1 could not be maintained. Zone 2 ventilation was restored by starting the standby Zone 2 exhaust fan. Zone 2 differential pressure recovered to [greater than] 0.25 [inches] WG at 2321 hours. Zone 3 (Unit 1&2 Reactor Buildings) ventilation remained in service and stable. Zone 1(Unit 1 Reactor Building) ventilation remained in service however it is not required in this mode of Operation.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 51831
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEPHEN APREA
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/30/2016
Notification Time: 11:58 [ET]
Event Date: 03/29/2016
Event Time: 17:50 [EDT]
Last Update Date: 03/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JAMES DWYER (R1DO)
FFD GROUP (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Defueled

Event Text

FITNESS-FOR-DUTY REPORT INVOLVING A NON-LICENSED SUPERVISOR

A non-licensed, licensee supervisory employee had a confirmed positive test for alcohol during a random fitness-for-duty test. The employee's access to the plant has been removed.

The licensee notified the NRC Region I.

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Power Reactor Event Number: 51836
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: GLENN BENJAMIN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/30/2016
Notification Time: 20:45 [ET]
Event Date: 03/30/2016
Event Time: 15:45 [CDT]
Last Update Date: 03/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
PATTY PELKE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE OUTSIDE REQUIRED TECHNICAL SPECIFICATION VALUE

"At approximately 1545 CDT on 3/30/16, the Main Control Room received numerous annunciators that indicated a trip of the Emergency Reserve Auxiliary Transformer (ERAT) Static VAR Compensator (SVC) caused by a voltage transient on the 138 kV feed due to thunderstorms in the area. As a result of the voltage transient, the Division 1 Fuel Building ventilation (VF) system isolation dampers closed causing a trip of VF supply and exhaust fans. With no running VF fans, secondary containment differential pressure rose to slightly greater than 0 inches water gauge which exceeded the Technical Specification requirement of greater than 0.25 inches vacuum water gauge. The Control Room entered EOP-8, Secondary Containment Control. This event is being reported as a condition that could have prevented fulfillment of a safety function under 10 CFR 50.72(b)(3)(v)(C). Secondary Containment differential pressure was restored within Technical Specification requirements at 1550 CDT by starting the Standby Gas Treatment HVAC (VG) system.

"The NRC Resident has been notified."

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Power Reactor Event Number: 51837
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: BILL RAYBURN
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/31/2016
Notification Time: 00:14 [ET]
Event Date: 03/30/2016
Event Time: 17:15 [EDT]
Last Update Date: 03/31/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
PATTY PELKE (R3DO)

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

Event Text

DEGRADED CONDITION DUE TO DISCOVERY OF PRESSURE BOUNDARY LEAKAGE

"On March 30, 2016, at 1715 EDT, with the Unit shutdown and in Mode 6 for refueling, evidence of leakage was identified on a 3/4-inch flexible braided piping connection on Reactor Coolant Pump (RCP) 1-1, and this issue was determined to be reactor coolant system pressure boundary leakage. This flexible piping is for RCP 1-1 first stage seal cavity vent line, and is categorized as ASME Section III Class 2 piping. The leakage was identified due to the discovery of a small amount of boric acid (approximately 1/2 teaspoon) on the welded end connection of the flexible piping. No active leakage was identified at the time of discovery with the Reactor Coolant System depressurized and approximately 110 degrees F.

"Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, 'RCS Operational Leakage,' does not apply in the current plant condition (Mode 6). The cause and resolution of the leakage are under evaluation. This event is reportable within 8 hours per 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Thursday, March 31, 2016
Thursday, March 31, 2016