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Issue date | Title | Topic | |
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ML20206H152 | 5 May 1999 | Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant | |
ML20206G568 | 3 May 1999 | Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation | |
ML20204C456 | 16 March 1999 | Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet | |
ML20217H499 | 30 March 1998 | Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety | Time of Discovery High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Fire Protection Program |
ML20202D312 | 26 November 1997 | Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility | Annual Radioactive Effluent Release Report Process Control Program Fire Protection Program |
ML20216F129 | 8 August 1997 | Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20141G630 | 19 May 1997 | Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing | |
ML20138G340 | 2 May 1997 | Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical | |
ML20058E256 | 5 November 1993 | Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves | |
ML20056G932 | 1 September 1993 | Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 | |
ML20056F782 | 23 August 1993 | Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS | |
ML20127D488 | 11 January 1993 | Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements | |
ML20126H607 | 29 December 1992 | Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 | Shutdown Margin |
ML20126C098 | 9 December 1992 | Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One | |
ML20059D038 | 30 August 1990 | Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator | |
ML20246L429 | 14 July 1989 | Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos | |
ML20246F623 | 10 July 1989 | Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation | Shutdown Margin Anticipated operational occurrence Fuel cladding |
ML20245D445 | 24 April 1989 | Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels | |
ML20245D434 | 24 April 1989 | Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability | |
ML20207L602 | 11 October 1988 | Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 | |
ML20155B450 | 27 September 1988 | Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core | Shutdown Margin Anticipated operational occurrence Fuel cladding |
ML20154A131 | 7 September 1988 | Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC | |
ML20196G680 | 23 June 1988 | Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 | Boric Acid |
ML20151W573 | 26 April 1988 | Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure | |
ML20149H269 | 17 February 1988 | Amend 103 to License DPR-36,changing Tech Specs to Update Figures 5.2.-1 & 5.2-2 in Tech Spec 5.2 Organization Depicting Plant Offsite & Facility Organization, Respectively | |
ML20196C421 | 9 February 1988 | Amend 102 to License DPR-36,revising Tech Spec 3.10.C.3.1.1 to Reflect Revised LOCA Monitoring Limits to Be Used When in-core Monitoring Sys Inoperable | |
ML20235M459 | 29 September 1987 | Amend 101 to License DPR-36,requiring Written Administrative Controls for Implementation of Process Control Program | Process Control Program Fire Protection Program |
ML20216J016 | 25 June 1987 | Amend 99 to License DPR-36,revising Tech Specs 5.9.1.6 & 5.9.1.7,allowing Addl Time for Filing Supplemental Dose & Meteorological Summary Repts & Ensuring Refs to Other Tech Specs Correct | Annual Radiological Environmental Operating Report |
ML20234B169 | 25 June 1987 | Amend 100 to License DPR-36,revising Tech Specs to Conform W/Generic Ltr 83-37 Requirements Re RCS Vent Sys | Hydrostatic |
ML20215E921 | 15 June 1987 | Amend 98 to License DPR-36,modifying Tech Specs to Reflect Revised LOCA Limits Using Revised Delta P Injection Penalty Factor During Reflood Phase of LOCA & Limiting Axial Power Shapes | |
ML20214J596 | 20 May 1987 | Amend 97 to License DPR-36,deleting Requirement for Emergency Diesel Generator Testing in Event That Any Component of One Train of ECCS Becomes Inoperable | |
ML20206U900 | 9 April 1987 | Amend 96 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 10 Reload Core by Modifying steady-state Peak Linear Heat Rate to Reflect Acceptable Fuel Design Limits for Prevention of Centerline Melting | Anticipated operational occurrence Fuel cladding |
ML20197D418 | 26 March 1987 | Amend 94 to License DPR-36,revising Tech Specs Re Operability & Surveillance for New Noble Gas Effluent monitors,high-range Monitors & Water Level Monitors in Containment | |
ML20212N691 | 4 March 1987 | Amend 93 to License DPR-36,adding Administrative Controls to Limit Overtime of Staff Personnel & Allow Dual Role of Senior Reactor Operator & Shift Technical Advisor | Safe Shutdown Fire Protection Program |
ML20210V153 | 9 February 1987 | Amend 92 to License DPR-36,revising Tech Specs to Increase Fuel Enrichment Limit to 3.5 Weight Percent U-255 for Cycle 10 & Beyond | Boric Acid |
ML20207M815 | 6 January 1987 | Errata to Amend 91 to License DPR-36,including Revised Table 4.2-2, Min Frequencies for Equipment Tests | Liquid penetrant |
ML20215E785 | 11 December 1986 | Amend 91 to License DPR-36,revising Tech Specs,Including Restating Spec 3.14B for Clarity & Deleting Ref to Cycle 7 & Dividing Section 3.15 Re Reactor Power Anomalies Into Spec & Remedial Action | Shutdown Margin Hydrostatic Fire Protection Program Power change |
ML20197B600 | 27 October 1986 | Amend 90 to License DPR-36,revising Tech Specs to Incorporate Specific Requirements for Iodine Spiking Into Annual Rept Per Generic Ltr 85-19 & to Delete Primary Coolant Iodine Activity Rept | Annual Radiological Environmental Operating Report |
ML20195D393 | 27 May 1986 | Amend 89 to License DPR-36,adding Addl Manual Containment Isolation Valves & Blowdown & Body Vent Valves on Instrument Lines to List of Manual Containment Isolation Valves That May Be Repositioned | |
ML20140C882 | 17 March 1986 | Amend 88 to License DPR-36,requiring Operability of Three Independent Steam Generator Auxiliary or Emergency Feedwater Pumps to Supply Emergency Feedwater to All Three Steam Generators | |
ML20137Y723 | 4 March 1986 | Amend 87 to License DPR-36,changing Tech Specs to Require Monthly Operability Testing of turbine-driven Auxiliary Feedwater Pump | |
ML20137A039 | 31 December 1985 | Amend 86 to License DPR-36,modifying Tech Specs to Assure Compliance W/App I,10CFR50,50.36 & 50.34a to Ensure Releases of Radioactive Matl to Unrestricted Areas During Normal Operation Remain ALARA | |
ML20137Y842 | 30 September 1985 | Amend 85 to License DPR-36,modifying Tech Specs to Reflect Cycle 9 Power Distributions,Insertion Limits & Peaking Factors & Describe Max Reactor Inlet Temp Used in Modified Safety Analyses | Boric Acid Fuel cladding |
ML20134K865 | 20 August 1985 | Amend 84 to License DPR-36,changing Tech Specs to Require More Extensive Insp of Steam Generator Tubes in Critical Areas | Operating Basis Earthquake Earthquake |
ML20062E251 | 21 July 1982 | Tech Spec Page 5.2-3 Figure 5.2-2) Establishing Separate Training Dept & Other Organization Changes.Page Inadvertently Omitted from Original Transmittal | |
ML20062A096 | 14 July 1982 | Amend 61 to License DPR-36,increasing Required Number of Operable Safety Injection Actuation Signal Sensors & Establishing Training Dept & Other Organizational Changes | |
ML20148Q124 | 8 November 1978 | Amend 42 to Facil Oper Lic DPR-36 Rev Tech Specs Re Radiological & Thermal Effluent Monitoring.Changes Involve Environ Surveillance Prog,Air Particulate Charcoal Gamma Monitoring & Estuary Water Temp Monitoring | Grab sample |