Event Notification Report for September 30, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/29/2013 - 09/30/2013
Power Reactor
Event Number: 49395
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SCHWER
HQ OPS Officer: DANIEL MILLS
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SCHWER
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/30/2013
Notification Time: 15:35 [ET]
Event Date: 09/30/2013
Event Time: 14:22 [EDT]
Last Update Date: 09/30/2013
Notification Time: 15:35 [ET]
Event Date: 09/30/2013
Event Time: 14:22 [EDT]
Last Update Date: 09/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
JUDY JOUSTRA (R1DO)
JUDY JOUSTRA (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 |
TRANSPORT OF POTENTIALLY CONTAMINATED INJURED WORKER
"At approximately 1422 EDT on 9/30/2013, a craft contractor worker was transported to an off-site medical facility due a work-related injury. The injured individual was in a radiologically controlled area when the injury occurred. The injured was partially surveyed by a Health Physics technician in their anti-contamination clothing prior to leaving the site and no radioactive contamination was detected. The injured individual was then transported by ambulance accompanied by a Health Physics technician to the local hospital for medical treatment.
"Follow up surveys determined that no contamination was detected on the individual or materials transported. All materials are being recovered and returned to the site.
"This notification is being made under the 10CFR50.72(b)(3)(xii) reporting requirements, since a complete survey of the injured individual was unable to be made and he was considered to be potentially contaminated prior to being transported off-site."
The NRC Resident Inspector has been notified.
"At approximately 1422 EDT on 9/30/2013, a craft contractor worker was transported to an off-site medical facility due a work-related injury. The injured individual was in a radiologically controlled area when the injury occurred. The injured was partially surveyed by a Health Physics technician in their anti-contamination clothing prior to leaving the site and no radioactive contamination was detected. The injured individual was then transported by ambulance accompanied by a Health Physics technician to the local hospital for medical treatment.
"Follow up surveys determined that no contamination was detected on the individual or materials transported. All materials are being recovered and returned to the site.
"This notification is being made under the 10CFR50.72(b)(3)(xii) reporting requirements, since a complete survey of the injured individual was unable to be made and he was considered to be potentially contaminated prior to being transported off-site."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 49398
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID LANTZ
HQ OPS Officer: CHARLES TEAL
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID LANTZ
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/01/2013
Notification Time: 01:05 [ET]
Event Date: 09/30/2013
Event Time: 22:57 [CDT]
Last Update Date: 10/02/2013
Notification Time: 01:05 [ET]
Event Date: 09/30/2013
Event Time: 22:57 [CDT]
Last Update Date: 10/02/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HEATHER GEPFORD (R4DO)
HEATHER GEPFORD (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFF-SITE EMERGENCY OPERATIONS FACILITY DECLARED INOPERABLE DUE TO AIR IN-LEAKAGE
"At 2257 CDT on September 30, 2013 the Callaway Plant Emergency Off-Site Facility (EOF) was declared nonfunctional due to air in-leakage outside acceptance criteria while ventilation is in filtration mode.
"Efforts are underway to restore the air in-leakage within acceptance criteria at the EOF.
"If EOF activation is necessary during the period of EOF non-functionality, the Recovery Manager will evaluate the suitability of the facility for the specific conditions of the event.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the unavailability of an emergency response facility.
"The NRC Senior Resident Inspector has been notified."
* * * UPDATE FROM RICHARD HUGHEY TO JOHN SHOEMAKER AT 0248 EDT ON 10/02/13 * * *
"Repairs were made to the EOF ventilation system and all required post-maintenance testing has been completed satisfactorily. The EOF has been restored to a functional status."
The licensee will notify the NRC Resident Inspector.
Notified R4DO (Gepford).
"At 2257 CDT on September 30, 2013 the Callaway Plant Emergency Off-Site Facility (EOF) was declared nonfunctional due to air in-leakage outside acceptance criteria while ventilation is in filtration mode.
"Efforts are underway to restore the air in-leakage within acceptance criteria at the EOF.
"If EOF activation is necessary during the period of EOF non-functionality, the Recovery Manager will evaluate the suitability of the facility for the specific conditions of the event.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the unavailability of an emergency response facility.
"The NRC Senior Resident Inspector has been notified."
* * * UPDATE FROM RICHARD HUGHEY TO JOHN SHOEMAKER AT 0248 EDT ON 10/02/13 * * *
"Repairs were made to the EOF ventilation system and all required post-maintenance testing has been completed satisfactorily. The EOF has been restored to a functional status."
The licensee will notify the NRC Resident Inspector.
Notified R4DO (Gepford).
Power Reactor
Event Number: 49392
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SCHWER
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SCHWER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/30/2013
Notification Time: 09:26 [ET]
Event Date: 09/30/2013
Event Time: 02:38 [EDT]
Last Update Date: 09/30/2013
Notification Time: 09:26 [ET]
Event Date: 09/30/2013
Event Time: 02:38 [EDT]
Last Update Date: 09/30/2013
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):
JUDY JOUSTRA (R1DO)
JUDY JOUSTRA (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
MANUAL START OF MOTOR DRIVEN AUXILIARY FEEDWATER PUMP
"At 0238 [EDT] hours on September 30, 2013, during a planned shutdown of Beaver Valley Unit 1 for a refueling outage, the 'B' Motor Driven Auxiliary Feedwater (AFW) pump was manually started in Mode 3 due to lowering levels in the steam generators. The steam generator levels were restored to normal following the start of the AFW pump. The lowering [steam generator] levels were a result of a component failure in a normal non-safety related make up system. The manual start for the AFW pump is being reported as a system actuation per 10 CFR 50 72(b)(3)(iv). The plant is currently in Mode 5.
"The NRC Resident Inspector has been notified."
A condensate pump recirculation valve failing open was the component failure in the normal non-safety related make up system.
"At 0238 [EDT] hours on September 30, 2013, during a planned shutdown of Beaver Valley Unit 1 for a refueling outage, the 'B' Motor Driven Auxiliary Feedwater (AFW) pump was manually started in Mode 3 due to lowering levels in the steam generators. The steam generator levels were restored to normal following the start of the AFW pump. The lowering [steam generator] levels were a result of a component failure in a normal non-safety related make up system. The manual start for the AFW pump is being reported as a system actuation per 10 CFR 50 72(b)(3)(iv). The plant is currently in Mode 5.
"The NRC Resident Inspector has been notified."
A condensate pump recirculation valve failing open was the component failure in the normal non-safety related make up system.