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 Issue dateTitleTopic
ML20205A14523 March 1999Core Shroud Insp PlanVT-2
Moisture barrier
EVT-1
ML20151S38531 August 1998Long-Term Program:Semi-Annual ReptSafe Shutdown
Ultimate heat sink
Coatings
Foreign Material Exclusion
Severe Accident Management Guideline
Maintenance Rule Program
Downpower
Operability Assessment
Water hammer
ML20211N68716 September 1997Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing ProgramSafe Shutdown
High Radiation Area
Ultimate heat sink
Stroke time
Squib
Scram Discharge Volume
Intergranular Stress Corrosion Cracking
Excess Flow Check Valve
Cold shutdown justification
Power Operated Valves
Scaffolding
Grace period
ML20211G23815 September 1997Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station OdcmGrab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
ML20216C06329 August 1997Semi-Annual Long Term Program ScheduleSafe Shutdown
Foreign Material Exclusion
Intergranular Stress Corrosion Cracking
Severe Accident Management Guideline
Downpower
ML20210K3551 July 1997Rev 16 to Procedure 7.8.1, Water Quality LimitsGrab sample
Feedwater Heater
Intergranular Stress Corrosion Cracking
Stress corrosion cracking
Fuel cladding
ML20117K66117 July 1996Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements
ML20100J25222 November 1995Rev 7 to Pilgrim Nuclear Power Station OdcmOffsite Dose Calculation Manual
ML20092B5861 September 1995Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power StationHydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
Pressure boundary leak
Backfit
ML20077Q11813 January 1995Owner'S Specification for Reactor Shroud Repair
ML20127N27124 November 1992Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing ProgramSafe Shutdown
High Radiation Area
Ultimate heat sink
Stroke time
Squib
Local Leak Rate Testing
Scram Discharge Volume
Intergranular Stress Corrosion Cracking
Excess Flow Check Valve
Cold shutdown justification
Power Operated Valves
Scaffolding
Grace period
ML20128M77031 March 1992Amend 92-01 to Second Ten Year ISI ProgramHydrostatic
VT-2
Dissimilar Metal Weld
ML20094P54119 March 1992Rev 23 to Procedure 5.4.6, Primary Containment Venting & Purging Under Emergency Conditions, Revising Coversheet & Attachment 1,Sheet 3 of 5,page 8 of 20
ML20058E52825 October 1990Rev 1 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20006C05718 January 1990Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan.
ML15264A1572 January 1990Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21Health Physics Network
ML16152A8952 January 1990Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations.
ML20012A3751 January 1990Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station.Offsite Dose Calculation Manual
ML20012A3771 January 1990Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station.Boric Acid
Offsite Dose Calculation Manual
ML20012A3791 January 1990Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station.Offsite Dose Calculation Manual
ML20012A3801 January 1990Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations.Offsite Dose Calculation Manual
Uranium Hexafluoride
ML20005F07913 December 1989Rev 0 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program.Safe Shutdown
High Radiation Area
Ultimate heat sink
Stroke time
Squib
Scram Discharge Volume
Intergranular Stress Corrosion Cracking
Excess Flow Check Valve
Cold shutdown justification
Power Operated Valves
Operability Assessment
ML20012A3695 December 1989Rev 8 to, Process Control Program,Mcguire Nuclear Station.Process Control Program
ML20011D2441 December 1989Crisis Mgt Implementing Procedures.
ML20012A37227 November 1989Rev 4 to, Process Control Program,Cawtaba Nuclear Station.Boric Acid
Process Control Program
ML20012A37315 November 1989Rev 4 to, Process Control Program Oconee Nuclear Station.Process Control Program
ML19325F1931 November 1989Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations.Safe Shutdown
ML19332C8451 November 1989Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13Health Physics Network
ML20247H33715 September 1989Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting ..Boric Acid
Earthquake
Fatality
Siren
Potassium iodide
ML20245L7657 August 1989Rev 0 to Offsite Dose Calculation ManualOffsite Dose Calculation Manual
ML20247M79231 July 1989Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data EnclBoric Acid
Stroke time
Feedwater Heater
Overspeed trip
ML20247N36131 July 1989Rev 2 to Dcrdr Program PlanPost Accident Monitoring
Probabilistic Risk Assessment
Emergency Lighting
Feedwater Heater
Backfit
Loss of condenser vacuum
ML20247M91527 July 1989Procedure Generation Package
ML20247N04219 June 1989Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test
ML20247M75826 May 1989Rev 0 to Test NO-1, Braidwood Simulator Normal Operations TestingShutdown Margin
ML20247M78626 May 1989Rev 0 to SV-1, Braidwood Simulator Surveillance TestingShutdown Margin
ML20245D65521 April 1989Power Ascension Program Resumption Plan
ML20245C2545 April 1989Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear StationsSiren
ML20247M7804 April 1989Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985Stroke time
ML20247M8011 February 1989Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1Power change
ML20247M8201 February 1989Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2Power change
ML20247M8661 February 1989Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1Power change
ML20247M8741 February 1989Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2Power change
ML20235R34428 December 1988Rev 26 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test
ML20235R46722 December 1988Rev 25 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test
ML20155C01428 September 1988Rev 3 to Appendices to Restart PlanSafe Shutdown
Reactor Vessel Water Level
Loop seal
Packing leak
High Radiation Area
Fire Barrier
Temporary Modification
Emergency Lighting
Missed surveillance
Local Leak Rate Testing
Feedwater Heater
Stress corrosion cracking
Integrated leak rate test
Exemption Request
Fire Protection Program
Fire Watch
Scaffolding
Overspeed trip
Water hammer
ML20204J1397 September 1988Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection
ML20155F9047 September 1988Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating ProceduresHydrostatic
Scram Discharge Volume
Earthquake
ML20153H64831 August 1988Ascension ProgramOverspeed trip
ML20204J03923 August 1988Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed