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 Issue dateTitleTopic
ML20196D02416 June 1999Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence
ML20206R81611 May 1999Proposed Tech Specs Re HPCI & RCIC Surveillance TestingReactor Vessel Water Level
ML20206H9775 May 1999Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSsSafe Shutdown
Abnormal operational transient
ML20205A14523 March 1999Core Shroud Insp PlanVT-2
Moisture barrier
EVT-1
ML20207F1173 March 1999Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule
ML20151S38531 August 1998Long-Term Program:Semi-Annual ReptSafe Shutdown
Ultimate heat sink
Coatings
Foreign Material Exclusion
Severe Accident Management Guideline
Maintenance Rule Program
Downpower
ML20237E08524 August 1998Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOTShutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Offsite Circuit
ML20236X71931 July 1998Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time
ML20249C71026 June 1998Proposed Tech Specs Correcting Typos & Updating BasesOvertravel
ML20249B32315 June 1998Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCMShutdown Margin
Packing leak
High Radiation Area
Offsite Dose Calculation Manual
Scram Discharge Volume
Annual Radiological Environmental Operating Report
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Unidentified leakage
ML20217F93426 March 1998Proposed Tech Specs Re EDG Allowed Outage Time
ML20217H27925 March 1998Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.AHydrostatic
ML20203D49820 February 1998Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173Safe Shutdown
Reactor Vessel Water Level
Ultimate heat sink
Offsite Circuit
ML20217K56924 October 1997Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing
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
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
ML20211G23112 September 1997Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCMHigh Radiation Area
Scram Discharge Volume
ML20216C06329 August 1997Semi-Annual Long Term Program ScheduleSafe Shutdown
Foreign Material Exclusion
Severe Accident Management Guideline
Downpower
ML20210K4388 August 1997Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCOOffsite Circuit
ML20196J00422 July 1997Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH
ML20210K3551 July 1997Rev 16 to Procedure 7.8.1, Water Quality LimitsGrab sample
Fuel cladding
ML20136J5507 March 1997Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned SequenceSpiral reload
ML20134C96724 January 1997Proposed Tech Specs 2.0 Re Safety LimitsAnticipated operational occurrence
Fuel cladding
ML20133A65123 December 1996Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical SysOffsite Circuit
ML20132E54910 December 1996Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation
ML20135C14626 November 1996Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4Earthquake
ML20134K4367 November 1996Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A
ML20117K6555 September 1996Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6Offsite Circuit
ML20116M15612 August 1996Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance ManualFire Protection Program
ML20117K66117 July 1996Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements
ML20108C0581 May 1996Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment
ML20108C1071 May 1996Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA ManualFitness for Duty
Fire Protection Program
ML20111B4201 May 1996Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B
ML20111C2761 May 1996Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control
ML20108A65625 April 1996Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at PlantShutdown Margin
Offsite Circuit
ML20095E0778 December 1995Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle DesignsFuel cladding
ML20100J25222 November 1995Rev 7 to Pilgrim Nuclear Power Station OdcmOffsite Dose Calculation Manual
ML20092C4331 September 1995Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11Shutdown Margin
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
ML20092A44231 August 1995Corrected Tech Spec Page Re Reactor High Pressure Trip Setting
ML20086K26614 July 1995Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11Fuel cladding
ML20078R62215 February 1995Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 AuthorizationShutdown Margin
ML20078N4869 February 1995Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting
ML20077Q11813 January 1995Owner'S Specification for Reactor Shroud Repair
ML20077M6929 January 1995Proposed Reformatted Tech Specs & BasesReactor Vessel Water Level
Packing leak
High Radiation Area
Offsite Dose Calculation Manual
Anticipated operational occurrence
Abnormal operational transient
Scram Discharge Volume
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Unidentified leakage
ML20077B18622 November 1994Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc TimeOffsite Circuit
ML20077A89922 November 1994Proposed Tech Specs Re Suppression Chamber Water Level
ML20078K81522 November 1994Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C
ML20078K79622 November 1994Proposed Tech Specs Re Changes to MSIV Leakage Requirement
ML20078N84218 November 1994Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test