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Issue date | Title | Topic | |
---|---|---|---|
ML20196D024 | 16 June 1999 | Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence | |
ML20206R816 | 11 May 1999 | Proposed Tech Specs Re HPCI & RCIC Surveillance Testing | Reactor Vessel Water Level |
ML20206H977 | 5 May 1999 | Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs | Safe Shutdown Abnormal operational transient |
ML20205A145 | 23 March 1999 | Core Shroud Insp Plan | VT-2 Moisture barrier EVT-1 |
ML20207F117 | 3 March 1999 | Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule | |
ML20151S385 | 31 August 1998 | Long-Term Program:Semi-Annual Rept | Safe Shutdown Ultimate heat sink Coatings Foreign Material Exclusion Severe Accident Management Guideline Maintenance Rule Program Downpower Operability Assessment Water hammer |
ML20237E085 | 24 August 1998 | Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT | Shutdown Margin High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Offsite Circuit |
ML20236X719 | 31 July 1998 | Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time | |
ML20249C710 | 26 June 1998 | Proposed Tech Specs Correcting Typos & Updating Bases | Overtravel |
ML20249B323 | 15 June 1998 | Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM | Shutdown 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 |
ML20217F934 | 26 March 1998 | Proposed Tech Specs Re EDG Allowed Outage Time | |
ML20217H279 | 25 March 1998 | Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A | Hydrostatic |
ML20203D498 | 20 February 1998 | Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 | Safe Shutdown Reactor Vessel Water Level Ultimate heat sink Offsite Circuit |
ML20217K569 | 24 October 1997 | Proposed 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 | |
ML20211N687 | 16 September 1997 | Rev 9 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 Scaffolding Grace period |
ML20211G238 | 15 September 1997 | Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
ML20211G231 | 12 September 1997 | Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM | High Radiation Area Scram Discharge Volume |
ML20216C063 | 29 August 1997 | Semi-Annual Long Term Program Schedule | Safe Shutdown Foreign Material Exclusion Intergranular Stress Corrosion Cracking Severe Accident Management Guideline Downpower |
ML20210K438 | 8 August 1997 | Revised 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 LCO | Offsite Circuit |
ML20196J004 | 22 July 1997 | Proposed 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 | |
ML20210K355 | 1 July 1997 | Rev 16 to Procedure 7.8.1, Water Quality Limits | Grab sample Feedwater Heater Intergranular Stress Corrosion Cracking Stress corrosion cracking Fuel cladding |
ML20136J550 | 7 March 1997 | Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence | Spiral reload |
ML20134C967 | 24 January 1997 | Proposed Tech Specs 2.0 Re Safety Limits | Anticipated operational occurrence Fuel cladding |
ML20133A651 | 23 December 1996 | Proposed 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 Sys | Offsite Circuit |
ML20132E549 | 10 December 1996 | Proposed 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 | |
ML20135C146 | 26 November 1996 | Proposed 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.4 | Earthquake |
ML20134K436 | 7 November 1996 | Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A | |
ML20117K655 | 5 September 1996 | Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 | Offsite Circuit |
ML20116M156 | 12 August 1996 | Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual | Fire Protection Program |
ML20117K661 | 17 July 1996 | Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements | |
ML20108C058 | 1 May 1996 | Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment | |
ML20111B420 | 1 May 1996 | Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B | Excess Flow Check Valve |
ML20111C276 | 1 May 1996 | Proposed 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 | Integrated leak rate test |
ML20108C107 | 1 May 1996 | Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual | Fitness for Duty Fire Protection Program |
ML20108A656 | 25 April 1996 | Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant | Shutdown Margin Offsite Circuit |
ML20095E077 | 8 December 1995 | Proposed 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 Designs | Fuel cladding |
ML20100J252 | 22 November 1995 | Rev 7 to Pilgrim Nuclear Power Station Odcm | Offsite Dose Calculation Manual |
ML20092B586 | 1 September 1995 | Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure boundary leak Backfit |
ML20092C433 | 1 September 1995 | Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 | Shutdown Margin |
ML20092A442 | 31 August 1995 | Corrected Tech Spec Page Re Reactor High Pressure Trip Setting | |
ML20086K266 | 14 July 1995 | Proposed 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 11 | Fuel cladding |
ML20078R622 | 15 February 1995 | Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization | Shutdown Margin Water hammer |
ML20078N486 | 9 February 1995 | Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting | |
ML20077Q118 | 13 January 1995 | Owner'S Specification for Reactor Shroud Repair | |
ML20077M692 | 9 January 1995 | Proposed Reformatted Tech Specs & Bases | Reactor 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 |
ML20077A899 | 22 November 1994 | Proposed Tech Specs Re Suppression Chamber Water Level | |
ML20077B186 | 22 November 1994 | Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time | Offsite Circuit |
ML20078K796 | 22 November 1994 | Proposed Tech Specs Re Changes to MSIV Leakage Requirement | |
ML20078K815 | 22 November 1994 | Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C | |
ML20078N842 | 18 November 1994 | Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test |