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 Issue dateTitleTopic
ML20212J2721 October 1999Proposed Tech Specs,Modifying DG Fuel Oil Storage RequirementsSafe Shutdown
Anticipated operational occurrence
Offsite Circuit
ML20210G29729 July 1999Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys
ML20210A40415 July 1999Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19Shutdown Margin
Grab sample
ML20204J60319 March 1999Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15Shutdown Margin
Grab sample
ML20203C5935 February 1999Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic ChangesReactor Vessel Water Level
High Radiation Area
Offsite Dose Calculation Manual
Scram Discharge Volume
Overtravel
ML20199J90821 January 1999Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors
ML20197H5174 December 1998Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2Reactor Vessel Water Level
Minimum Critical Power Ratio
ML20236U25522 July 1998Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors
ML20217A08630 April 1998Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal RuleSafe Shutdown
Fire Barrier
Anticipated operational occurrence
Coatings
Incorporated by reference
B.5.b
Aging Management
Fire Protection Program
HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 1817 February 1998Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18Shutdown Margin
ML20197K18618 December 1997Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in EffectSafe Shutdown
Fire Protection Program
ML20211J1861 October 1997Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders
ML20211A23019 September 1997Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPRReactor Vessel Water Level
Minimum Critical Power Ratio
ML20210J0498 August 1997Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%Shutdown Margin
Reactor Vessel Water Level
Hydrostatic
Scram Discharge Volume
Feedwater Controller Failure
HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 1421 July 1997Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14Shutdown Margin
ML20141B7599 May 1997Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
ML20141B8569 May 1997Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor SysFuel cladding
HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits29 April 1997Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp LimitsHydrostatic
ML20133F3647 January 1997Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently DoneStroke time
ML20138G62719 December 1996Rev 11 to ODCM for Ei Hatch Nuclear Plant
ML20132G22617 December 1996Proposed Tech Specs Re pressure-temp LimitsHydrostatic
ML20132E01613 December 1996Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification PlanSafe Shutdown
Fire Protection Program
ML20135D4883 December 1996Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14Reactor Vessel Water Level
Minimum Critical Power Ratio
ML20129H91829 October 1996Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware
ML20128M8707 October 1996Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions InoperableStroke time
ML20113F55419 September 1996Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New CurvesUnanalyzed Condition
Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Fuel cladding
ML20117M22511 September 1996Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of PlantSafe Shutdown
Offsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Fire Protection Program
HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 1718 July 1996Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17
ML20115J48616 July 1996Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71Safe Shutdown
Unanalyzed Condition
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Squib
Qualified Offsite Circuit
Abnormal operational transient
Scram Discharge Volume
Feedwater Controller Failure
Spiral reload
Overtravel
Power Operated Valves
Fuel cladding
Offsite Circuit
Coast down
ML20212C14931 May 1996Stability Monitor
ML20117H13921 May 1996Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet
ML20100P1044 March 1996Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13Shutdown Margin
Reactor Vessel Water Level
ML20100H74321 February 1996Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F
ML20094K38310 November 1995Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option BHigh Radiation Area
Squib
Pressure Boundary Leakage
ML20093G9405 October 1995Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2
ML20092H64624 July 1995Ei Hatch Nuclear Plant Units 1 & 2 IST Program
ML20085K40120 June 1995Proposed Tech Specs for Power UprateShutdown Margin
Reactor Vessel Water Level
Hydrostatic
Fuel cladding
ML20086E84719 June 1995Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds
ML20086E8319 June 1995Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud StabilizerNondestructive Examination
Liquid penetrant
ML20086E8146 June 1995Rev 1 to Code Design Spec 25A5717, Shroud StabilizersEarthquake
ML20085A1666 June 1995Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria
ML20086E81217 May 1995Rev 0 to Design Spec 25A5718, Shroud Repair HardwareDesign basis earthquake
Earthquake
Liquid penetrant
ML20082V3794 May 1995Proposed Tech Specs,Minimizing Thermal Stratification EventsReactor Vessel Water Level
Hydrostatic
ML20082L33314 April 1995Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TSReactor Vessel Water Level
ML20081F34714 March 1995Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation MonitorHydrostatic
ML20077S03313 January 1995Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 MwtShutdown Margin
Reactor Vessel Water Level
Hydrostatic
Fuel cladding
ML20077D8922 December 1994Proposed Deleted ETS
ML20078G7161 November 1994Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433
ML20076L69119 October 1994Proposed Improved Tech Specs,Rev FTime of Discovery
Reactor Vessel Water Level
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Fire Protection Program
ML20149G37513 October 1994Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be ObtainedReactor Vessel Water Level