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Event Notification Report for June 28, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
6/27/2018 - 6/28/2018

** EVENT NUMBERS **


53392 53393 53461 53477

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53392
Facility: FARLEY
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: STEVEN VITTO
Notification Date: 05/08/2018
Notification Time: 01:39 [ET]
Event Date: 05/07/2018
Event Time: 00:00 [CDT]
Last Update Date: 06/27/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BINOY DESAI (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby

Event Text

UNANALYZED CONDITION

"On May 7, 2018 at 1041 CDT, Unit 1 performed an RCS (reactor coolant system) leakrate procedure that calculated an unidentified RCS leakrate of 0.202 gpm. The leak source investigation concluded at 2150 that the packing for the charging flow control valve (FCV) was the source of the RCS leakage when it was bypassed, which isolated the leakage. A second RCS leakrate calculation was performed after the charging flow control valve was isolated which calculated an acceptable leakrate of 0.00 gpm.

"The packing leakage from the charging flow control valve represented leakage external to containment which would result in a greater that 5 Rem dose projection to control room personnel during accident conditions which does not satisfy the GDC19 criteria described in Technical Specification Bases 3.7.10. Therefore the control room emergency filtration system would not be able to fulfill its design function resulting in an unanalyzed condition.

"This condition is being reported pursuant to 10CFR50.72(b)(3)(ii) for a 'condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety'.

"The packing leak from the charging flow control valve will remain isolated until repaired under work order SNC944374."

The NRC Resident Inspector has been notified.


* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/2018 * * *

"Retraction - There was sufficient margin in the analysis of record to account for the increased leakage in the charging flow control valve that was not known at the time of reporting. Doses at the site boundary and in the Main Control Room would have remained less than the legal limits had a Loss of Coolant Accident occurred based on plant conditions at the time."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Michel).

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53393
Facility: FARLEY
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DOUGLAS HOBSON
HQ OPS Officer: DAN LIVERMORE
Notification Date: 05/08/2018
Notification Time: 10:38 [ET]
Event Date: 05/08/2018
Event Time: 00:00 [CDT]
Last Update Date: 06/27/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BINOY DESAI (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby

Event Text

CONTAINMENT LEAK RATE GREATER THAN TECH SPEC

"On May 8, 2018 at 0139 Central Daylight Time, Farley Nuclear Plant Unit 1 declared containment inoperable due to total containment leak rate greater than technical specifications. The 1B containment cooler had seat leakage of approximately 30 gallons per minute from a service water drain valve.

"Though the containment cooler service water supply is not tested per the Appendix J program, a loss of the containment barrier is possible under accident conditions.

"The service water flow path to the 1B containment cooler has been isolated to exit the condition."

The licensee will notify the NRC resident inspector.


* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/18 * * *

"During the time of the leakage reported in event notification 53393 the system was under administrative control. The containment isolation valves for the 1B containment cooler were closed as restoration of the containment cooler was still in progress following the outage. With the system isolated, operations had identified a 50 drop per minute (dpm) leak downstream of a service water drain valve to the 1B containment cooler. To quantify the leak, operations removed the downstream pipe cap and piping to better measure the leak under system pressure. Upon opening the service water containment isolation valves the leak rate was measured at 30 gpm. Operations re-closed the service water containment isolation valves per the pre-briefed contingency actions. It was determined that the service water drain valve (a ball valve) was not properly seated. This was all performed with operations personnel on station in the containment and in the Main Control Room. At no time were the containment isolation valves degraded. Following closure of the containment isolation valves they were also powered down to prevent inadvertent opening."

The licensee notified the NRC Resident Inspector.

Notified R2DO (Michel).

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Agreement State Event Number: 53461
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: MEMORIAL MISSION HOSPITAL
Region: 1
City: ASHEVILLE   State: NC
County:
License #: 0091-6
Agreement: Y
Docket:
NRC Notified By: TRAVIS CARTOSKI
HQ OPS Officer: RICHARD SMITH
Notification Date: 06/19/2018
Notification Time: 16:00 [ET]
Event Date: 06/19/2018
Event Time: 00:00 [EDT]
Last Update Date: 06/19/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ART BURRITT (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - REMOVABLE CONTAMINATION ON PACKAGE

The following information was received via E-mail:

"North Carolina Radioactive Material Branch (NCRMB) is reporting the following event:

"On 6/19/2018, Memorial Mission Hospital, Asheville (NC License, 0091-6) reported receiving two Biodex PET boxes containing F-18 FDG [fludeoxyglucose] from Cardinal Health, Asheville (NC License, 0794-7). Both boxes were delivered to Cardinal Health, Asheville via courier from Cardinal Health, Charlotte (NC License, 0794-1).

"Upon receipt of the boxes, Memorial Mission personnel performed surveys and wipes and noted the following contamination for Tc-99m on the boxes with the concentration of contamination being on the side handles of both boxes:

Box 1: 88.96 kdpm/300 cm2
Box 2: 46.92 kdpm/300 cm2

"No contamination was found inside either of the boxes containing F-18 patient doses and contamination was only on outside handles of both boxes. Memorial Mission confirmed that no further contaminated packages were received.

"Cardinal Health, Charlotte performed wipes and surveys of its work areas, courier vehicle and personnel. No contamination was found at this location with regards to this event.

"Cardinal Health, Asheville performed wipes and surveys of its work areas, courier vehicle and personnel. The courier at this location that delivered the two boxes to Memorial Mission Hospital is also a Pharmacy Technician. Removable contamination was found on this person's hands and cleaned. No other contamination was discovered at this location or the courier vehicle.

"No other notifications were made to any other agencies in NC. NCRMB was notified same day as the event. There are no other generic implications.

"NCRMB has dispatched an inspector to perform an on-site investigation. This report will be updated once more information is discovered, to include corrective actions and any other info needed to close and complete this report.

"Reporting Requirement: 10 CFR 20.1906(d)(1): Reports of removable contamination on package > limits in 10 CFR 71.87; removable contamination greater than limits specified in 49 CFR 173.443."

NC Tracking Event Number: 180028.

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Power Reactor Event Number: 53477
Facility: PALO VERDE
Region: 4     State: AZ
Unit: [] [] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ROBERT WARNER
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/28/2018
Notification Time: 05:37 [ET]
Event Date: 06/27/2018
Event Time: 00:00 [MST]
Last Update Date: 06/28/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RYAN ALEXANDER (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS [Emergency Notification System] or under the reporting requirements of 10 CFR 50.73.

"On June 27th, 2018 at approximately 2310 Mountain Standard Time (MST), in Palo Verde Unit 3, the #1 Steam Generator Economizer valve started closing. This caused Steam Generator #1 water level to decrease. Both Feed water pumps speed increased to raise Steam Generator level. At approximately 2311 [MST], the B Main Feed water pump tripped resulting in a Reactor Power Cutback. Steam Generator #1 level continued to decrease resulting in an Automatic Reactor Trip on Low Steam Generator #1 water level. All control rods inserted to shut down the Reactor to Mode 3 using Main Feed water and Steam Bypass. Post trip Steam Generator #1 level then increased and at approximately 2316 [MST] a Main Steam Isolation Signal (MSIS) was received on high Steam Generator level. The 'B' Auxiliary Feed water pump was manually started to maintain Steam Generator water levels and Steam Generator pressure was controlled using the Atmospheric Dump Valves (ADVs).

"Following the reactor trip, all CEAs [Control Element Assemblies] inserted fully into the core. All systems operated as expected. No emergency plan classification was required per the Emergency Plan. Safety related busses remained powered during the event from offsite power and the offsite power grid is stable. No major equipment was inoperable prior to the event that contributed to the event or complicated operator response. Unit 3 is stable and in Mode 3 feeding Steam Generators with Auxiliary Feed water Pump 'B'. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.

"The NRC Resident Inspector was informed of the Unit 3 reactor trip."

Unit 1and Unit 2 were unaffected by the Unit 3 trip.


Page Last Reviewed/Updated Thursday, June 28, 2018
Thursday, June 28, 2018