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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
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Text
LER 293/83-039 Event
Description:
Trip with HPCI Inoperable Date of Event: July 2, 1983 Plant: Pilgrim Summary During reactor startup surveillance tests on July 2, 1983, the high-pressure coolant injection (HPCI) system was declared inoperable when the HPCI turbine stop valve required more than the normal amount of time to open. A manual scram occurred six days earlier.
Assuming HPCI was inoperable during the scram, the conditional core damage probability estimated for this event is 5.2x10-6. 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).