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Category:Accident Sequence Precursor (ASP) Analysis
MONTHYEARML20168A7072020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-78-035) ML20168A7062020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-78-003) ML20168A7052020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-75-034) ML20156A1392020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-87-014) ML20156A1292020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-069) ML20156A1312020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-080) ML20156A1322020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-82-023) ML20156A1332020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-82-042) ML20156A1342020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-007) ML20156A1352020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-039) ML20156A1362020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-052) ML20156A1372020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-85-027) ML20156A1382020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-86-027) ML20156A1302020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-079) ML20135H3062020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-90-013) ML20135H3072020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-91-024) ML20135H3082020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-93-004) ML19212A6512019-08-12012 August 2019 Transmittal of Final Accident Sequence Precursor Report (Licensee Event Report 293-2019-001) ML19169A2792019-08-12012 August 2019 Final Accident Sequence Precursor Analysis- Pilgrim Nuclear Power Station, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing 2020-06-04
[Table view] Category:Final
MONTHYEARML20168A7072020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-78-035) ML20168A7062020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-78-003) ML20168A7052020-06-16016 June 2020 Final ASP Analysis - Pilgrim (LER 293-75-034) ML20156A1392020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-87-014) ML20156A1292020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-069) ML20156A1312020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-080) ML20156A1322020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-82-023) ML20156A1332020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-82-042) ML20156A1342020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-007) ML20156A1352020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-039) ML20156A1362020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-83-052) ML20156A1372020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-85-027) ML20156A1382020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-86-027) ML20156A1302020-06-0404 June 2020 Final ASP Analysis - Pilgrim (LER 293-80-079) ML20135H3062020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-90-013) ML20135H3072020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-91-024) ML20135H3082020-05-14014 May 2020 Final ASP Analysis - Pilgrim (LER 293-93-004) ML19212A6512019-08-12012 August 2019 Transmittal of Final Accident Sequence Precursor Report (Licensee Event Report 293-2019-001) ML19169A2792019-08-12012 August 2019 Final Accident Sequence Precursor Analysis- Pilgrim Nuclear Power Station, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing 2020-06-04
[Table view] |
Text
LER 293/83-052 Event
Description:
Trip with HPCI Inoperable Date of Event: September 23, 1983 Plant: Pilgrim Summary While monthly surveillance of the high-pressure coolant injection (HPCI) system was being performed during steady-state operation on September 23, 1983, the HPCI was declared inoperable when the HPCI motor operated valve 2302-3 failed to open. Fourteen days earlier, on September 9, 1983, a scram occurred during surveillance testing.
Assuming HPCI was failed at the time of the scram, a conditional core damage probability of 5.2x10-6 is estimated. The dominant sequence involved a transient initiator followed by successful reactor shutdown, failure of the power conversion system, failure of two safety relief valves (SRVs) to close, unavailability of HPCI, and failure of the automatic depressurization system (ADS).