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Issue date | Title | Topic | |
---|---|---|---|
ML20217K322 | 19 October 1999 | Amend 195 to License DPR-61,deleting Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor,Duplicate Regulatory Requirements or Duplicate Info Located in UFSAR | High Radiation Area Offsite Dose Calculation Manual Time to boil Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report Fire Protection Program |
ML20207G632 | 3 June 1999 | Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Replacing Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generid Titles | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20206C873 | 28 April 1999 | Amend 194 to License DPR-61,authorizes Relocation of Requirements Related to Seismic Monitoring Instrumentation from TSs to Technical Requirements Manual | |
ML20207L258 | 5 March 1999 | Amend 104 to License DPR-21,changing TSs for Staffing & Training Requirements to Allow Use of Certified Fuel Handlers to Meet Plant Staffing Requirements | Offsite Dose Calculation Manual |
ML20236K340 | 1 July 1998 | Amend 218 to License DPR-65,changing TS by Modifying Low Temp Overpressure Protection Requirements | Boric Acid Shutdown Margin Stroke time Anticipated operational occurrence Hydrostatic Power Operated Valves Power change |
ML20202D152 | 30 June 1998 | Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant | High Radiation Area Grab sample Offsite Dose Calculation Manual Time to boil Operating Basis Earthquake Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
ML20217K865 | 1 April 1998 | Errata to Amend 103 to License DPR-21.Page Inadvertently Listed Bases Page B3/4 1-2 Instead of B 3/4 1-2a | |
ML20217K204 | 27 March 1998 | Amend 192 to License DPR-61,changing Administrative Controls,Section 6.0 of Ts,To Reflect Permanent Shutdown & Defueled Status of Plant | High Radiation Area Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
ML20212G586 | 27 October 1997 | Amend 103 to License DPR-21,revising TSs Sections 3.1 & 4.1, RPS & Associated Bases to Remove Run Mode Intermediate Range Monitor High Flux/Inoperative W/Associated Average PRM Downscale Scram Trip Function | Scram Discharge Volume |
ML20212F130 | 22 October 1997 | Amend 102 to License DPR-21,clarifying Requirement for Calibr of Instrument Channels That Use RTD or Thermocouples | |
ML20211K153 | 2 October 1997 | Errata to Amend 122 to License NPF-49.Original TS 1-8 Replaces Revised Page That Should Not Have Been Included in Rev | |
ML20141L879 | 28 May 1997 | Amend 101 to License DPR-21,revising TS on Allowed Outage Times for Protective Instrumentation & for RB Access Control | Scram Discharge Volume Fuel cladding |
ML20141K416 | 22 May 1997 | Amend 191 to License DPR-61,changing Administrative Controls Section of TSs as Needed to Implement Revised Mgt Responsibilities & Titles That Reflect Permanently Shut Down Status of Plant | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20137V581 | 15 April 1997 | Amend 100 to License DPR-21,deleting License Condition 2.C.(5), Integrated Implementation Schedule from Plant Unit 1 Operating License | Safe Shutdown |
ML20137U296 | 10 April 1997 | Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Revising Section 6, Administrative Controls, of Plant,Units 1,2 & 3 TSs to Reflect Organizational Changes That Have Been Implemented in Nuclear Division | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20133N331 | 14 January 1997 | Amend 98 to License DPR-21,modifying Applicability Requirements for Certain Radiation Monitors So That Radiation Monitors Required to Be Operable Only When Secondary Containment Integrity Required | |
ML20128L749 | 4 October 1996 | Amend 97 to License DPR-21,removing TS Figure 5.1 & Substitutes Defined Requirement for Max Koo for Fuel Placed in Plant Spent Fuel Pool | |
ML20058L688 | 14 December 1993 | Corrected Amend 70 to License DPR-21,adding Safety Evaluation Date to License Condition 2.C(3) & Correcting Typo in License Condition 2.C(4) | |
ML20058H788 | 1 December 1993 | Amend 70 to License DPR-21,modifying Operating License Condition 2.C(3), Fire Protection, by Deleting Existing Wording of License Condition & Replacing W/Standard Wording Provided in GL 86-10 | |
ML20058F110 | 23 November 1993 | Amends 170,69,169 & 86 to Licenses DPR-61,DPR-21 DPR-65 & NPF-49,respectively,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual | |
ML20059L692 | 10 November 1993 | Amend 68 to License DPR-21,revises Surveillance Requirements for Local Leak Rate Testing Which Are Included in TS Section 4.7.A,to Remove 5% L Limit | |
ML20059G633 | 1 November 1993 | Amend 169 to License DPR-61,changing TS by Incorporating New TS Section 3/4.8.3.1.2, Onsite Power Distribution | |
ML20059H831 | 1 November 1993 | Amend 67 to License DPR-21,changing TS 4.7.A.3.d(2) | |
ML20059G509 | 27 October 1993 | Amend 168 to License DPR-61,permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 | |
ML20059G081 | 27 October 1993 | Amend 66 to License DPR-21,increasing Max Stroke Time for RWC Sys Isolation Valves CU-2,3,5 & 28 from 18 to 20 in TS 3.7.1 | Stroke time |
ML20057F849 | 12 October 1993 | Amend 65 to License DPR-21,removing Fire Protection Requirements from TS | |
ML20057E200 | 4 October 1993 | Amend 167 to License DPR-61,changing Plant TS to Allow Redundant Train Operability to Be Verified Operable by Exam of Appropriate Plant Records Rather than Performing Test of Redundant Equipment | |
ML20057E191 | 4 October 1993 | Amend 166 to License DPR-61,modifying TS Tables 3.3-9 & 4.3-7 by Replacing Obsolete Footnote W/Clarification as to When SG Blowdown Radioactivity Monitors Are Required to Be Operable | |
ML20057G356 | 29 September 1993 | Corrected Page 2 to Amend 64 to License DPR-21,revising Implementation Date to Occur by End of Cycle 14 Refueling Outage (Jan 94) | |
ML20058M901 | 29 September 1993 | Amend 165 to License DPR-61,replacing TS Section 4.0.6 of Plant TS, Augmented Inservice Insp Program W/New TS Section 4.0.6, Augmented Erosion/Corrosion Program | |
ML20057D743 | 29 September 1993 | Amend 64 to License DPR-21,removing Operability & Associated SR for Main Steam Line Radiation Monitor Scram & Group I Containment Isolation Functions | |
ML20057A348 | 2 September 1993 | Amend 164 to License DPR-61,revising TS to Reflect Staff Positions & Improvements to TS in Response to GL-90-06 Re Resolution of Generic Issues 70 & 74 | |
ML20057A353 | 2 September 1993 | Amend 163 to License DPR-61,adding Footnote to TS 3.4.2.2 to Allow Relaxation in Pressurizer Safety Valve Point Tolerance to +3%,used for as Found Acceptance Criterion for Addl Valve Testing | |
ML20056G287 | 25 August 1993 | Amend 162 to License DPR-61,revising TSs to Increase Shutdown Margin (Boron Concentration) in Modes 1-5 to Compensate for Addl Reactivity Added by Boron Dilution Event Due to Transition to Zircaloy Clad Core | Shutdown Margin |
ML20128P799 | 19 February 1993 | Amend 61 to License DPR-21,allowing for Temporarily Bypassing MSLRM Trip Function for Period Not to Exceed 2 Hours,In Order to Allow Condensate Demineralizers to Be Returned to Svc | |
ML20127E392 | 11 January 1993 | Amend 60 to License DPR-21,providing Alternative to Increase in App J,Type a Test Frequency Incurred After Failure of Two Successive Individual Leak Rate Tests | |
ML20058F716 | 1 November 1990 | Amend 47 to License DPR-21,deleting Requirement That Combined Time Interval for Any Three Consecutive Surveillance Intervals Not to Exceed 3.25 Times Specific Surveillance Interval from Tech Spec 1.0.X | |
ML20062B734 | 22 October 1990 | Amend 132 to License DPR-61,adding Footnote to Tech Spec Table 3.3-2,Item 3,Table 3.3-3,Item 2 & 4.3-2,Item 3 | |
ML20059J765 | 12 September 1990 | Amend 45 to License DPR-21,changing Tech Spec Section 3/4.5.C by Adding Operability & Surveillance Requirements for Mod Made to Tie Breakers 14A to 14G | |
ML20055G540 | 19 July 1990 | Amend 128 to License DPR-61,revising Tech Specs to Reflect Removal of Thermal Shield & Attached Surveillance Capsules | |
ML20055G555 | 19 July 1990 | Amend 129 to License DPR-61,adding Footnote to Tech Spec Section 5.3.1, Fuel Assemblies to Allow Operation of Cycles 16 & 17 W/Two Solid Type 304 Stainless Steel Filler Rods in Place of Two Fuel Rods & Correcting Table 3.3-1a | |
ML20055E455 | 5 July 1990 | Corrected Tech Spec Page 3/4 9-1 Re Auxiliary Electrical Sys to License DPR-21 | |
ML20055E233 | 2 July 1990 | Amend 126 to License DPR-61,revising Tech Specs to Reflect Mods Performed on Fire Protection Sys.Changes Include Increasing Smoke & Heat Detectors Required to Be Operable in Diesel Generator Rooms a & B & in Lube Oil Reservoir Area | |
ML20247K229 | 11 September 1989 | Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively, Allowing Licensees to Inspect Steam Generator Tubes by Insertion of Ultrasonic Test Probe from Cold Leg Side of Steam Generator Tube | Operating Basis Earthquake |
ML20247E369 | 7 September 1989 | Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Lifetime Records Retention for Radiological Effluent Monitoring & ODCM | High Radiation Area Offsite Dose Calculation Manual Process Control Program |
ML20247A465 | 5 September 1989 | Amend 121 to License DPR-61,revising & Combining Tech Spec Sections 3.6,3.7 & 4.3 | |
ML20247E650 | 20 July 1989 | Amend 120 to License DPR-61,changing Tech Specs 3.17.1, Axial Offset & 3.17.2, LHGR, to Allow Coastline Operation of Plant at End of Cycle 15 |