Event Notification Report for February 16, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/15/2016 - 02/16/2016
Power Reactor
Event Number: 51742
Facility: HATCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: STEVEN VITTO
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: STEVEN VITTO
Notification Date: 02/18/2016
Notification Time: 15:48 [ET]
Event Date: 02/16/2016
Event Time: 06:31 [EST]
Last Update Date: 02/18/2016
Notification Time: 15:48 [ET]
Event Date: 02/16/2016
Event Time: 06:31 [EST]
Last Update Date: 02/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
SHANE SANDAL (R2DO)
SHANE SANDAL (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
WELD OVERLAY FLAW DID NOT MEET ACCEPTANCE CRITERIA
"As part of the upgrade to the full structural weld overlays (FSWOL) per NRC-approved ISI [In-service Inspection] Alternative HNP-ISI-ALT-15-01, the surface of the existing weld overlay for the 1E Recirculation weld (1B31-1RC-12BR-E-5) was ground to prepare the surface for receipt of a new Alloy 52M overlay. Upon performance of the subsequent liquid penetrant testing examination, it was discovered that the as-found condition of the flaw did not meet acceptance criteria. It was determined that the flaw constituted a defect in the primary coolant system that could not be found acceptable per ASME Section XI. Therefore, this event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A).
"Evaluation of the flaw found in the weld overlay suggests that the non-satisfactory liquid penetrant surface examination is a result of the propagation of the original flaw that was found on the 1E Recirculation Loop Piping. The flaw is axial in nature and therefore there is no impact on structure integrity degradation. No leakage is currently present or was seen during the previous operating cycle from this flaw. There is also reasonable assurance that there was not a breach in the credited RCS [Reactor Coolant System] boundary during the previous operating cycle.
"As part of the corrective action to fix the flaw, the 1E Recirculation weld will be upgraded to full structural weld overlay per the NRC-approved ISI Alternative."
The Licensee notified the NRC Resident Inspector.
"As part of the upgrade to the full structural weld overlays (FSWOL) per NRC-approved ISI [In-service Inspection] Alternative HNP-ISI-ALT-15-01, the surface of the existing weld overlay for the 1E Recirculation weld (1B31-1RC-12BR-E-5) was ground to prepare the surface for receipt of a new Alloy 52M overlay. Upon performance of the subsequent liquid penetrant testing examination, it was discovered that the as-found condition of the flaw did not meet acceptance criteria. It was determined that the flaw constituted a defect in the primary coolant system that could not be found acceptable per ASME Section XI. Therefore, this event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A).
"Evaluation of the flaw found in the weld overlay suggests that the non-satisfactory liquid penetrant surface examination is a result of the propagation of the original flaw that was found on the 1E Recirculation Loop Piping. The flaw is axial in nature and therefore there is no impact on structure integrity degradation. No leakage is currently present or was seen during the previous operating cycle from this flaw. There is also reasonable assurance that there was not a breach in the credited RCS [Reactor Coolant System] boundary during the previous operating cycle.
"As part of the corrective action to fix the flaw, the 1E Recirculation weld will be upgraded to full structural weld overlay per the NRC-approved ISI Alternative."
The Licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 51737
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: JARDEN ZINC
Region: 1
City: GREENEVILLE State: TN
County:
License #: R-30012
Agreement: Y
Docket:
NRC Notified By: RUBIN CROSSLIN
HQ OPS Officer: JOHN SHOEMAKER
Licensee: JARDEN ZINC
Region: 1
City: GREENEVILLE State: TN
County:
License #: R-30012
Agreement: Y
Docket:
NRC Notified By: RUBIN CROSSLIN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/16/2016
Notification Time: 10:32 [ET]
Event Date: 02/16/2016
Event Time: 00:00 [EST]
Last Update Date: 02/16/2016
Notification Time: 10:32 [ET]
Event Date: 02/16/2016
Event Time: 00:00 [EST]
Last Update Date: 02/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - DAMAGED FIXED NUCLEAR GAUGE
The following report was received from the State of Tennessee via email:
"On February 16, 2016 the RSO [Radiation Safety Officer] of Jarden Zinc reported that one of their fixed nuclear gauges (make, model, serial number not reported) had been damaged. Details concerning the cause of the damage were unknown. Surveys of the damaged gauge indicate that the gauge shutter is in the closed position, no radiation beam is emanating from the gauge, and there do not appear to be any exposures to staff. The gauge has been moved into storage until the manufacturer can arrive to inspect the gauge. The RSO indicated that follow-up information to the Tennessee Division of Radiological Health would occur within 24 hours."
State Event Report ID NO.: TN-16-021
The following report was received from the State of Tennessee via email:
"On February 16, 2016 the RSO [Radiation Safety Officer] of Jarden Zinc reported that one of their fixed nuclear gauges (make, model, serial number not reported) had been damaged. Details concerning the cause of the damage were unknown. Surveys of the damaged gauge indicate that the gauge shutter is in the closed position, no radiation beam is emanating from the gauge, and there do not appear to be any exposures to staff. The gauge has been moved into storage until the manufacturer can arrive to inspect the gauge. The RSO indicated that follow-up information to the Tennessee Division of Radiological Health would occur within 24 hours."
State Event Report ID NO.: TN-16-021
Power Reactor
Event Number: 51738
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MUFFLEY
HQ OPS Officer: DANIEL MILLS
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MUFFLEY
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/16/2016
Notification Time: 13:44 [ET]
Event Date: 02/16/2016
Event Time: 08:27 [EST]
Last Update Date: 02/16/2016
Notification Time: 13:44 [ET]
Event Date: 02/16/2016
Event Time: 08:27 [EST]
Last Update Date: 02/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 4 | Startup | 4 | Startup |
AUXILIARY FEEDWATER PUMP AUTO START DUE TO FEED PUMP TRIP
"At 0827 [EST], the 21 and 22 Aux Feedwater pumps auto started due to a trip of the running Steam Generator Feed pump (22). The 22 Steam Generator Feed pump tripped while swapping from heating steam to main steam in accordance with normal operating procedures. The cause of the 22 Steam Generator Feed pump trip is being investigated at this time.
"The auto start of the Unit 2 Auxiliary Feedwater pumps is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any system listed in Technical Basis 11.3.3 except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'"
The licensee has notified the NRC Resident Inspector and will notify the Lower Alloways Creek Township.
"At 0827 [EST], the 21 and 22 Aux Feedwater pumps auto started due to a trip of the running Steam Generator Feed pump (22). The 22 Steam Generator Feed pump tripped while swapping from heating steam to main steam in accordance with normal operating procedures. The cause of the 22 Steam Generator Feed pump trip is being investigated at this time.
"The auto start of the Unit 2 Auxiliary Feedwater pumps is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any system listed in Technical Basis 11.3.3 except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'"
The licensee has notified the NRC Resident Inspector and will notify the Lower Alloways Creek Township.