|
---|
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
LERs 293/82-043 and -042 Event
Description:
RCIC and HPCI Suction Valves Inoperable Date of Event: September 30, 1982 Plant: Pilgrim Summary On September 30, 1982 at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, position indication was lost for reactor core isolation cooling (RCIC) torus suction valve 1301-25 during a surveillance test. Prior to this, on September 29, high-pressure coolant injection (HPCI) had been declared inoperable, owing to the failure of HPCI torus suction valve 2301-35 during a timing surveillance (licensee event report (LER) 293/82-42).
The increase in core damage probability (CDP), or importance, , over the duration of the event is 5.8x10-6. The base-case CDP over the duration of the event is 1.8x10-6 resulting in an estimated conditional core damage probability of 7.6x10-6. The dominant sequence involves a postulated loss of offsite power with successful reactor shutdown, failure of the emergency power system, successful restoration of offsite power before battery depletion, no more than one safety relief valve failing to close, failure of HPCI, and failure of RCIC.