Event Notification Report for December 26, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/25/2011 - 12/26/2011
EVENT NUMBERS
47553
Power Reactor
Event Number: 47553
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/26/2011
Notification Time: 16:00 [ET]
Event Date: 12/26/2011
Event Time: 12:50 [EST]
Last Update Date: 12/26/2011
Notification Time: 16:00 [ET]
Event Date: 12/26/2011
Event Time: 12:50 [EST]
Last Update Date: 12/26/2011
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):
NEIL PERRY (R1DO)
NEIL PERRY (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 REQUIRED SHUTDOWN - SAFETY RELIEF VALVE DECLARED INOPERABLE
"On Monday, December 26, 2011, at 1250 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 of safety relief valve (SRV) RV-203-3D 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 and the two SSVs 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-203-3D 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 he 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 prig within 24 hours per T.S. 3.6.D.2.
"Currently, preparations are being completed to conduct the reactor shutdown and to initiate safety relief valve repairs.
"This event had no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."
"On Monday, December 26, 2011, at 1250 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 of safety relief valve (SRV) RV-203-3D 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 and the two SSVs 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-203-3D 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 he 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 prig within 24 hours per T.S. 3.6.D.2.
"Currently, preparations are being completed to conduct the reactor shutdown and to initiate safety relief valve repairs.
"This event had no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."