Event Notification Report for September 18, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/17/2015 - 09/18/2015
Power Reactor
Event Number: 51409
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARTIN NEWSHAN
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARTIN NEWSHAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/18/2015
Notification Time: 18:01 [ET]
Event Date: 09/18/2015
Event Time: 14:08 [EDT]
Last Update Date: 09/18/2015
Notification Time: 18:01 [ET]
Event Date: 09/18/2015
Event Time: 14:08 [EDT]
Last Update Date: 09/18/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
SILAS KENNEDY (R1DO)
SILAS KENNEDY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 85 | Power Operation | 85 | Power Operation |
EQUIPMENT FAILURE RESULTS IN INOPERABLE SECONDARY CONTAINMENT
"At 1408 EDT on 9/18/2015, Secondary Containment Refuel Floor exhaust flow degraded due to an equipment malfunction in the running Refuel Floor exhaust train. The degraded exhaust flow caused Secondary Containment differential pressure to go positive for approximately three minutes, resulting in Secondary Containment being declared inoperable. Corrective action to start the Stand-by Gas Treatment System and the alternate Refuel Floor exhaust train restored Secondary Containment operable by re-establishing its required negative differential pressure.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG-1022, Rev. 3, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'
"The Duty Team has been activated to develop a repair plan.
"The NRC Resident Inspector has been notified."
"At 1408 EDT on 9/18/2015, Secondary Containment Refuel Floor exhaust flow degraded due to an equipment malfunction in the running Refuel Floor exhaust train. The degraded exhaust flow caused Secondary Containment differential pressure to go positive for approximately three minutes, resulting in Secondary Containment being declared inoperable. Corrective action to start the Stand-by Gas Treatment System and the alternate Refuel Floor exhaust train restored Secondary Containment operable by re-establishing its required negative differential pressure.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG-1022, Rev. 3, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'
"The Duty Team has been activated to develop a repair plan.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 51410
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SHANE HARVEY
HQ OPS Officer: JEFF HERRERA
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SHANE HARVEY
HQ OPS Officer: JEFF HERRERA
Notification Date: 09/19/2015
Notification Time: 00:11 [ET]
Event Date: 09/18/2015
Event Time: 20:00 [CDT]
Last Update Date: 09/19/2015
Notification Time: 00:11 [ET]
Event Date: 09/18/2015
Event Time: 20:00 [CDT]
Last Update Date: 09/19/2015
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):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
REACTOR VESSEL HEAD PENETRATION REPAIR DID NOT MEET ACCEPTANCE CRITERIA
"On 9/18/2015 at 20:00 [CDT], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration requires repairs prior to returning the vessel head to service. These indications are not in the reactor coolant pressure boundary; however they are very near the previously repaired J-groove weld. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to ensure the structural integrity of the reactor vessel head pressure boundary. No ultrasonic indications have been identified at this time. Repairs are currently being planned in accordance with the ASME Code of Record. The repairs will be completed prior to returning the vessel head to service.
"This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The licensee has notified the NRC Resident Inspector.
"Per regulatory commitment, Exelon Generation Company, LLC (EGC) is notifying NRC staff of the Division of Component Integrity or its successor, of changes in indication(s) or findings of new indication(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities.
"The original indications that led to the overlay repairs were discovered during ultrasonic testing and were reported to the NRC and assigned EN46686 and EN48311."
"On 9/18/2015 at 20:00 [CDT], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration requires repairs prior to returning the vessel head to service. These indications are not in the reactor coolant pressure boundary; however they are very near the previously repaired J-groove weld. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to ensure the structural integrity of the reactor vessel head pressure boundary. No ultrasonic indications have been identified at this time. Repairs are currently being planned in accordance with the ASME Code of Record. The repairs will be completed prior to returning the vessel head to service.
"This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The licensee has notified the NRC Resident Inspector.
"Per regulatory commitment, Exelon Generation Company, LLC (EGC) is notifying NRC staff of the Division of Component Integrity or its successor, of changes in indication(s) or findings of new indication(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities.
"The original indications that led to the overlay repairs were discovered during ultrasonic testing and were reported to the NRC and assigned EN46686 and EN48311."
Agreement State
Event Number: 51690
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-413-01
Agreement: Y
Docket:
NRC Notified By: ROBERT SIMS
HQ OPS Officer: STEVEN VITTO
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-413-01
Agreement: Y
Docket:
NRC Notified By: ROBERT SIMS
HQ OPS Officer: STEVEN VITTO
Notification Date: 01/28/2016
Notification Time: 09:33 [ET]
Event Date: 09/18/2015
Event Time: 00:00 [CST]
Last Update Date: 03/18/2016
Notification Time: 09:33 [ET]
Event Date: 09/18/2015
Event Time: 00:00 [CST]
Last Update Date: 03/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - FIXED GAUGE OPEN/STUCK SHUTTER
The following was received from the State of Mississippi via email:
"During Fall shutter checks and inventory, on 9/18/2015, an Ohmart-Vega fixed gauge, DEA-2102, device model no. SHLM-BR1, (housing serial no. 13530993) (source serial no. 8533CN), was discovered to have an open/stuck shutter, the source disconnected, and was unable to be moved into the closed position. The RSO [Radiation Safety Officer] contacted the manufacturer and arrangements for repair are in motion. DRH [Mississippi Division of Radiological Health] was notified on 1/15/2016 and recommended that RSO take surveys with a survey measurement of the source. On 1/22/2016, [the] RSO provided readings that did not exceed 0.02 mR/hr at the surface of the steel drum that encloses the gauge and the source. The gauge and source is sealed in the steel drum and is only accessible by the manufacturer. The source is not in a designated work area, and is not causing exposure limits beyond the limits for radiation control to the general public and occupational workers."
Isotope: Cs-137
Activity: 40mCi
Mississippi report # MS-16001
* * * UPDATE FROM ROBERT SIMS TO DANIEL MILLS AT 1724 EDT ON 03/18/16 * * *
The following was received from the State of Mississippi via email:
"DRH [Department of Radiological Health] received vendor's field service update on 3/17/2016, from RSO. Report states that shutter failure was due to fatigue and the harsh environment to the roll pin that holds the two rods together. The source holder was repaired and leak test performed. DRH forwarded updated report to NRC on 3/17/2016. All Updated information on the source repair, the cause of the failure and all corrective action was forwarded the HOO on 3/18/2016.
"Violation issued for failure to report event to Mississippi State Department of Radiological Health within 24 hours."
Notified R4DO (Haire) and NMSS Events Notification (email).
The following was received from the State of Mississippi via email:
"During Fall shutter checks and inventory, on 9/18/2015, an Ohmart-Vega fixed gauge, DEA-2102, device model no. SHLM-BR1, (housing serial no. 13530993) (source serial no. 8533CN), was discovered to have an open/stuck shutter, the source disconnected, and was unable to be moved into the closed position. The RSO [Radiation Safety Officer] contacted the manufacturer and arrangements for repair are in motion. DRH [Mississippi Division of Radiological Health] was notified on 1/15/2016 and recommended that RSO take surveys with a survey measurement of the source. On 1/22/2016, [the] RSO provided readings that did not exceed 0.02 mR/hr at the surface of the steel drum that encloses the gauge and the source. The gauge and source is sealed in the steel drum and is only accessible by the manufacturer. The source is not in a designated work area, and is not causing exposure limits beyond the limits for radiation control to the general public and occupational workers."
Isotope: Cs-137
Activity: 40mCi
Mississippi report # MS-16001
* * * UPDATE FROM ROBERT SIMS TO DANIEL MILLS AT 1724 EDT ON 03/18/16 * * *
The following was received from the State of Mississippi via email:
"DRH [Department of Radiological Health] received vendor's field service update on 3/17/2016, from RSO. Report states that shutter failure was due to fatigue and the harsh environment to the roll pin that holds the two rods together. The source holder was repaired and leak test performed. DRH forwarded updated report to NRC on 3/17/2016. All Updated information on the source repair, the cause of the failure and all corrective action was forwarded the HOO on 3/18/2016.
"Violation issued for failure to report event to Mississippi State Department of Radiological Health within 24 hours."
Notified R4DO (Haire) and NMSS Events Notification (email).