Event Notification Report for January 20, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/19/2013 - 01/20/2013
Power Reactor
Event Number: 48684
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: CHARLES TEAL
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/20/2013
Notification Time: 20:50 [ET]
Event Date: 01/20/2013
Event Time: 16:41 [EST]
Last Update Date: 01/20/2013
Notification Time: 20:50 [ET]
Event Date: 01/20/2013
Event Time: 16:41 [EST]
Last Update Date: 01/20/2013
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):
SCOTT FREEMAN (R2DO)
SCOTT FREEMAN (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER VENTILATION DISABLED
"At 1641 on January 20, 2013, the Technical Support Center (TSC) became non-functional when the ventilation system was secured and disabled by a fire alarm. Investigation of the alarm condition determined the fire alarm was not valid and would not reset. At 1830, Technical Support Center ventilation was restored by disabling the deficient fire alarm by using guidance in alarm response procedure APP-FP-KBLDG. The Technical Support Center was restored to functional status at 1830 on January 20, 2013.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this condition affected an emergency response facility for greater than facility activation time (one hour).
"The NRC Resident Inspector has been informed"
"At 1641 on January 20, 2013, the Technical Support Center (TSC) became non-functional when the ventilation system was secured and disabled by a fire alarm. Investigation of the alarm condition determined the fire alarm was not valid and would not reset. At 1830, Technical Support Center ventilation was restored by disabling the deficient fire alarm by using guidance in alarm response procedure APP-FP-KBLDG. The Technical Support Center was restored to functional status at 1830 on January 20, 2013.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this condition affected an emergency response facility for greater than facility activation time (one hour).
"The NRC Resident Inspector has been informed"
Power Reactor
Event Number: 48685
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: PAUL GALLANT
HQ OPS Officer: CHARLES TEAL
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: PAUL GALLANT
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/20/2013
Notification Time: 23:30 [ET]
Event Date: 01/20/2013
Event Time: 20:50 [EST]
Last Update Date: 01/20/2013
Notification Time: 23:30 [ET]
Event Date: 01/20/2013
Event Time: 20:50 [EST]
Last Update Date: 01/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JOHN ROGGE (R1DO)
JOHN ROGGE (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SPECIFICATION (TS) REQUIRED SHUTDOWN - SAFETY RELIEF VALVE DECLARED INOPERABLE
"On Sunday, January 20, 2013, at 2050 hours, with the reactor at 100% core thermal power, the station entered a 24-hour action statement to initiate a controlled shutdown and be less than 104 psig reactor pressure due to suspected leakage across the first stage pilot of safety relief valve (SRV) RV-203-3B and subsequent declaration of the SRV inoperable due to criteria specified in Pilgrim plant procedure 2.2.23.
"As background, the pressure relief system includes four (4) SRVs and two (2) spring safety valves (SSVs). The SRVs discharge through their individual discharge piping, terminating below the minimum suppression pool (torus) water level. The four SRVs are installed on the main steam piping in containment between the reactor pressure vessel and the flow restrictors.
"While at full power, indication of a steam leak across the first stage pilot of RV-203-3B was determined in accordance with criteria specified in procedure 2.2.23. Specifically, the SRV is inoperable if the pilot stage thermocouple temperature is 35 degrees F below its baseline temperature (with a lower decrease at the 2nd stage thermocouple) and cannot be explained by a corresponding downpower. The safety relief valve was subsequently declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.6.D was entered. Due to the valve being declared inoperable the station is required to be shutdown and reactor coolant pressure below 104 psig within 24 hours per TS 3.6.D.2.
"Currently a reactor shutdown is in progress to initiate safety relief valve repairs.
"This event has no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."
"On Sunday, January 20, 2013, at 2050 hours, with the reactor at 100% core thermal power, the station entered a 24-hour action statement to initiate a controlled shutdown and be less than 104 psig reactor pressure due to suspected leakage across the first stage pilot of safety relief valve (SRV) RV-203-3B and subsequent declaration of the SRV inoperable due to criteria specified in Pilgrim plant procedure 2.2.23.
"As background, the pressure relief system includes four (4) SRVs and two (2) spring safety valves (SSVs). The SRVs discharge through their individual discharge piping, terminating below the minimum suppression pool (torus) water level. The four SRVs are installed on the main steam piping in containment between the reactor pressure vessel and the flow restrictors.
"While at full power, indication of a steam leak across the first stage pilot of RV-203-3B was determined in accordance with criteria specified in procedure 2.2.23. Specifically, the SRV is inoperable if the pilot stage thermocouple temperature is 35 degrees F below its baseline temperature (with a lower decrease at the 2nd stage thermocouple) and cannot be explained by a corresponding downpower. The safety relief valve was subsequently declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.6.D was entered. Due to the valve being declared inoperable the station is required to be shutdown and reactor coolant pressure below 104 psig within 24 hours per TS 3.6.D.2.
"Currently a reactor shutdown is in progress to initiate safety relief valve repairs.
"This event has no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."