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Event Notification Report for March 26, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/23/2018 - 03/26/2018

** EVENT NUMBERS **


53192 53264 53285 53286 53287

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53192
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: Timothy Gates
HQ OPS Officer: VINCE KLCO
Notification Date: 02/01/2018
Notification Time: 14:23 [ET]
Event Date: 02/01/2018
Event Time: 10:57 [CST]
Last Update Date: 03/23/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 27 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM

"At 1057 CST on February 1, 2018 with the unit in Mode 1 at approximately 27% power, a manual actuation of the Reactor Protection System (RPS) was initiated due to an unexpected trip of the B Recirc Pump with A Recirc Pump in fast speed. B Recirc Pump tripped during transfer from slow to fast speed resulting in single loop operation. Operators were unable to reconcile differing indications of core flow. This resulted in a conservative decision to initiate a manual scram. The cause of the B Recirc Pump trip and the apparent issues with core flow indication are under investigation. The plant is currently stable in Mode 3.

"The plant response to the scram was as expected. All control rods [fully] inserted as expected; the feedwater system is maintaining reactor vessel water level in the normal control band and reactor pressure is being maintained with steam line drains and main turbine bypass valves.

"The NRC Senior Resident [Inspector] has been notified."

* * * RETRACTION AT 1015 EDT ON 03/22/2018 FROM DAVID DABADIE TO OSSY FONT * * *

"This event was initially reported under 10 CFR 72(b)(2)(iv)(B) as a manual actuation of the RPS due to an unexpected trip of the B Reactor Recirculation Pump with the A Reactor Recirculation Pump running in fast speed (Single Loop Operations). Operations was unable to reconcile differing indications of core flow and made the conservative decision to perform a planned shutdown in accordance with normal operating procedures. Therefore, this event 'resulted from and was part of a pre-planned sequence during testing or reactor operation' as specified in 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.73(a)(2)(iv)(A) and NUREG-1022 Section 3.2.6. Consequently, this event is not reportable as an actuation of RPS.

"The NRC Resident Inspector has been notified."

R4DO (Groom) has been notified.

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Non-Agreement State Event Number: 53264
Rep Org: TUV SUD AMERICA
Licensee: TUV SUD AMERICA
Region: 4
City: PASADENA State: TX
County:
License #: 42-32507-01
Agreement: Y
Docket:
NRC Notified By: MATTHIAS KRANEISS
HQ OPS Officer: DAVID AIRD
Notification Date: 03/15/2018
Notification Time: 15:57 [ET]
Event Date: 02/19/2018
Event Time: [CDT]
Last Update Date: 03/15/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
JESSE ROLLINS (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

RADIOGRAPHY SOURCE STUCK IN SOURCE TUBE

On 2/19/2018, a crew was performing work at the Phillips 66 Refinery in Billings, Montana. While moving the source into the open position, a loud noise was heard originating from the exposure set up area. The crew immediately attempted to crank the source back into the fully shielded position, but the attempt was unsuccessful. It was determined that the part to be inspected had tipped over and fallen onto the source tube, resulting in a crimp which prevented the source from being retracted into the fully shielded position. The source was shielded with lead plates, the crimp reduced, and the source successfully retracted into the fully shielded position. No members of the general public were exposed to any radiation and no workers received a dose exceeding the limit for personnel working with radiation sources. The source tube involved in this incident has been removed from service and destroyed. The exposure device involved in this incident has been inspected, checked for proper functionality, found to be in working order, and returned to service. The device was a QSA 880D exposure device containing an Iridium-192 source.

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Power Reactor Event Number: 53285
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. LORI KIFFMEYER
HQ OPS Officer: ANDREW WAUGH
Notification Date: 03/23/2018
Notification Time: 21:07 [ET]
Event Date: 03/23/2018
Event Time: 12:30 [CDT]
Last Update Date: 03/23/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ERIC DUNCAN (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

Event Text

LOSS OF EMERGENCY ASSESSEMENT CAPABILITY

"This report is made for a loss of Emergency Assessment Capability associated with Emergency Action Levels for Toxic and Flammable Gas and is reportable under 10 CFR 50.72(b)(3)(xiii). During an emergency equipment inventory, it was identified that methods were not available to detect levels of toxic or flammable gas at the IDLH (Immediately Dangerous to Life and Health) level for a number of substances due to the detector having an unsuitable range. The IDLH is used to assess the Emergency Action Level Alert Range.

"The ability of the Control Room Staff to detect and respond to the presence of toxic or flammable gas is unaffected.

"Because there have been no chemical spills or releases that would require sampling to be performed, the health and safety of the public was not affected.

"The resident NRC Inspector has been notified."

The licensee will be notifying the state of Minnesota.

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Power Reactor Event Number: 53286
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DON HARTINGER
HQ OPS Officer: STEVEN VITTO
Notification Date: 03/24/2018
Notification Time: 01:09 [ET]
Event Date: 03/23/2018
Event Time: 16:35 [CDT]
Last Update Date: 03/24/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ERIC DUNCAN (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

LOSS OF EMERGENCY ASSESSMENT CAPABILITY

"This report is made for a loss of Emergency Assessment Capability associated with Emergency Action Levels for Toxic and Flammable Gas and is reportable under 10 CFR 50.72 (b)(3)(xiii). During an emergency equipment inventory it was identified that methods were not available to detect levels of toxic or flammable gas at the IDLH (Immediately Dangerous to Life and Health) level for a number of substances. The IDLH is used to assess the Alert Emergency Action Level.

"The ability of the Control Room Staff to detect and respond to the presence of toxic or flammable gas is unaffected.

"Because there have been no chemical spills or releases that would require sampling to be performed, the health and safety of the public was not affected.

"The NRC Resident Inspector has been notified."

The State of Minnesota will be notified.

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Power Reactor Event Number: 53287
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOSEPH FRATTASIO
HQ OPS Officer: VINCE KLCO
Notification Date: 03/25/2018
Notification Time: 23:43 [ET]
Event Date: 03/25/2018
Event Time: 16:16 [EDT]
Last Update Date: 03/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RAY MCKINLEY (R1DO)

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

Event Text

CONTROL ROD DRIVE PIPING POTENTIALLY INOPERABLE

"On March 25, 2018 at 1616 hours [EDT], with the reactor in cold shutdown condition, two control rod drive piping lines were determined to be potentially inoperable in the event of a design basis earthquake due to support defects. The control rod drive piping forms a portion of the reactor coolant pressure boundary and primary containment boundary.

"The supports will be repaired prior to plant startup.

"This event had no impact on the health and/or safety of the public.

"The NRC Resident Inspector has been notified."

The licensee will notify the Commonwealth of Massachusetts.

Page Last Reviewed/Updated Monday, March 26, 2018
Monday, March 26, 2018