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Event Notification Report for May 08, 2014

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
05/07/2014 - 05/08/2014

EVENT NUMBERS
50102501035009850099501005009550231

Power Reactor
Event Number: 50102
Facility: HARRIS
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: WILLIAM BULLOCK
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/09/2014
Notification Time: 12:37 [ET]
Event Date: 05/08/2014
Event Time: 18:15 [EDT]
Last Update Date: 05/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BRIAN BONSER (R2DO)
Power Reactor Unit Info
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
NON-LICENSED CONTRACT SUPERVISOR IN VIOLATION OF FITNESS FOR DUTY POLICY

"A non-licensed contract supervisor has been found in violation of the Fitness for Duty Policy. The individual's access to the plant has been terminated.

"The licensee has notified the NRC Resident Inspector."


Agreement State
Event Number: 50103
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF TEXAS
Region: 4
City: GALVESTON   State: TX
County:
License #: 01299
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/09/2014
Notification Time: 15:57 [ET]
Event Date: 05/08/2014
Event Time: 00:00 [CDT]
Last Update Date: 05/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JACK WHITTEN (R4DO)
FSME EVENTS RESOURCE (EMAI)
Event Text
AGREEMENT STATE REPORT INVOLVING OVER DOSE TO PATIENT

The following information was received from the State of Texas via email:

"The University of Texas Medical Branch reported that a patient received .975 MBq (26.35 æCi) instead of the prescribed .37 MBq (10 æCi) of I-131 for a diagnostic test for Grave's Disease on May 7, 2014. The rinse bottle used to add water to the I-131 to ensure all Iodine was ingested was contaminated from a previous therapeutic treatment on May 2, 2014. The rinse bottle tip which was used to squirt water into a 20 mCi I-131 solution for the therapeutic dose siphoned some of the iodine back into the bottle. The expected thyroid dose for the diagnostic procedure was 26 cGy (rad). The calculated thyroid dose with the additional contamination from the bottle was 68.51 cGy (rad). The Agency directed that the hospital immediately inform the patient. An investigation into this event by the Texas Department of State Health Services in ongoing. Additional information will be provided IAW with SA300 reporting requirements.

"Texas Incident #: I-9192"

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.


Power Reactor
Event Number: 50098
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GRETCHEN CARTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/08/2014
Notification Time: 20:57 [ET]
Event Date: 05/08/2014
Event Time: 16:45 [EDT]
Last Update Date: 05/08/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
Power Reactor Unit Info
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
POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"A review of industry operating experience regarding the potential for secondary fires being caused by DC Motor control circuit wiring has determined the described condition to be applicable to Nine Mile Point Unit 1 resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and configuration for the containment isolation valve IV-33-04 does not include separate over current protection for the power and control wiring. The only protection for the control circuit wiring is provided by the power circuit fuses.

"In the postulated event, a fire in the reactor building at the DC MOV could cause one of the control circuit wires to short and potentially over heat creating a secondary fire in the raceway system in a different fire zone. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. This event entered into the Nine Mile Point corrective action program as Condition Report (CR) 2014-004630.

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire zone inspections) have been implemented for affected areas of the plant."

The licensee has notified the State and the NRC Resident Inspector.


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility
Event Number: 50099
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 2     State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: DEREK WARFORD
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/08/2014
Notification Time: 21:15 [ET]
Event Date: 05/08/2014
Event Time: 10:24 [CDT]
Last Update Date: 05/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
BRIAN BONSER (R2DO)
PATTI SILVA (NMSS)
Event Text
HIGH PRESSURE FIRE WATER SPRINKLER SYSTEM B-6 DECLARED INOPERABLE

"At 1024 CDT, on 05-08-2014, the Plant Shift Superintendent was notified that the C-333 High Pressure Fire Water (HPFW) Sprinkler System B-6 had been inspected by Fire Services and 5 sprinkler heads had visible corrosion or paint on them, including 2 heads adjacent to each other. The system configuration was evaluated using EN-C-822-99-047 [Engineering Notice], 'Effects of Impaired Sprinkler Heads on System Operability' and determined that with these heads potentially impaired, a portion of the building would not have sufficient sprinkler coverage. The HPFW system is required to be operable according to TSR LCO [Technical Safety Requirement Limiting Condition for Operation] 2.4.4.5. HPFW Sprinkler System B-6 was declared inoperable and TSR LCO 2.4.4.5 Required Action B was implemented for the area without sprinkler coverage.

"Based on past testing results, there is a possibility that the heads would have been able to perform their specified safety function. Once the heads are removed from the system, testing will be performed to determine the actual effect on operability.

"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or fails to function as designed.

"The NRC Region II (Marvin Sykes) has been notified of this event.

"PGDP Assessment and Tracking Report No. ATR-14-0444; PGDP Event Report No. PAD-2014-05; NRC Worksheet No. 50099; Responsible Division: Operations."

* * * RETRACTION FROM DEREK WARFORD TO VINCE KLCO AT 1932 EDT ON 5/16/2014 * * *

"Subsequent to the event, the corroded sprinkler heads were replaced with new heads and the removed heads were tested in the laboratory. Based on the test results, one of the adjacent heads that was potentially impaired was determined to be fully functional and in accordance with EN-C-822-99-047, HPFW Sprinkler System B-6 was capable of performing its intended safety function. Since this event does not meet the criteria for a reportable event under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or fails to function as designed, the event notification is being retracted.

"The NRC Region II (Marvin Sykes) has been notified of this retraction."

Notified the R2DO (Desai) and NMSS EO (Csontos).


Power Reactor
Event Number: 50100
Facility: PALISADES
Region: 3     State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: KEVIN DALTON
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/08/2014
Notification Time: 21:57 [ET]
Event Date: 05/08/2014
Event Time: 18:24 [EDT]
Last Update Date: 05/08/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
KENNETH RIEMER (R3DO)
Power Reactor Unit Info
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
OFFSITE NOTIFICATION MADE DUE TO OIL LEAK

"At 1824 hours [EDT] on May 8, 2014, an oil leak was discovered on EX-07 Safeguards Transformer 1-1 that sprayed outside the transformer containment berm. The oil released to the ground was approximately 70 gallons, which is greater than the reporting requirements. The oil was not released to any surface water and has no drain path to reach any surface water. The State of Michigan, via the Pollution Emergency Alert System (PEAS) and Van Buren County was notified as required by the Site Spill Plan by the Control Room at 2003 hours."

The licensee has notified the NRC Resident Inspector.


Power Reactor
Event Number: 50095
Facility: MCGUIRE
Region: 2     State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL GREMBECKI
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/08/2014
Notification Time: 12:17 [ET]
Event Date: 05/08/2014
Event Time: 04:29 [EDT]
Last Update Date: 05/08/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN BONSER (R2DO)
Power Reactor Unit Info
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
LOSS OF 34 EMERGENCY SIRENS

"At approximately 0429 hours (EDT) on May 8, 2014, McGuire was informed that 34 emergency sirens were incapable of activation from the primary location. The loss of these 34 sirens for more than one hour is reportable pursuant to 10 CFR 50.72(b)(3)(xiii). Until repairs are complete, backup route alerting is in place.

"Troubleshooting is in progress. During troubleshooting, an inadvertent actuation of emergency sirens occurred at 1030 hours (EDT) on May 8, 2014. Mecklenburg County Emergency Management was notified of this inadvertent actuation which is being reported pursuant to 10 CFR 50.72(b)(2)(xi). Although these sirens were activated there was no incident at McGuire. This event does not impact public health and safety.

"The NRC Resident Inspector and local agencies were notified."

* * * UPDATE FROM NICHOLAS BARTSCHER TO DANIEL MILLS ON 5/08/2014 AT 1603 EDT * * *

The emergency sirens have been repaired and are functional.

The NRC Resident Inspector has been notified.

Notified R2DO (Bonser).


Power Reactor
Event Number: 50231
Facility: GINNA
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: DALE BISAILLON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/27/2014
Notification Time: 11:22 [ET]
Event Date: 05/08/2014
Event Time: 13:20 [EDT]
Last Update Date: 06/27/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BRICE BICKETT (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
Event Text
60-DAY TELEPHONIC NOTIFICATION OF INVALID SPECIFIED SYSTEM ACTUATION

"This report is being made per paragraphs 50.73(a)(1) and 50.73(a)(2)(iv)(A) to address an actuation of Emergency Diesel Generator 'B' on May 8, 2014 during the performance of 480v safeguards Bus 16 Under Voltage (UV) testing. Emergency AC Electrical Power system, including Emergency Diesel Generators, is a system named in 50.73(a)(2)(iv)(B).

"During testing of the Bus 16 UV cabinet, a human performance error resulted in the simultaneous auto start of the 'B' Emergency Diesel Generator and trip of the Bus 16 normal supply breaker. This is defined as an 'invalid signal' in that the 'B' Emergency Diesel Generator did not start as the result of an actual UV condition on Bus 16.

"This start signal is considered an INVALID signal with respect to 50.73(a)(2)(iv)(A), however the system was not fully removed from service. The 'A' train was not affected by this event. The actuation was considered complete since all necessary components responded as would have been expected if there had been a valid UV signal.

"The NRC Resident lnspector was notified."