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Issue date | Title | Topic | |
---|---|---|---|
ML20212J272 | 1 October 1999 | Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements | Safe Shutdown Anticipated operational occurrence Offsite Circuit |
ML20210G297 | 29 July 1999 | Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys | |
ML20210A404 | 15 July 1999 | Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 | Shutdown Margin Grab sample |
ML20204J603 | 19 March 1999 | Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 | Shutdown Margin Grab sample |
ML20203C593 | 5 February 1999 | Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes | Reactor Vessel Water Level High Radiation Area Offsite Dose Calculation Manual Scram Discharge Volume Overtravel |
ML20199J908 | 21 January 1999 | Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors | |
ML20197H517 | 4 December 1998 | Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 | Reactor Vessel Water Level Minimum Critical Power Ratio |
ML20236U255 | 22 July 1998 | Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors | |
ML20217A086 | 30 April 1998 | Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule | Safe 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 18 | 17 February 1998 | Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 | Shutdown Margin |
ML20197K186 | 18 December 1997 | Marked-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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect | Safe Shutdown Fire Protection Program |
ML20211J186 | 1 October 1997 | Corrected 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 | |
ML20211A230 | 19 September 1997 | Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR | Reactor Vessel Water Level Minimum Critical Power Ratio |
ML20210J049 | 8 August 1997 | Proposed 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 14 | 21 July 1997 | Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 | Shutdown Margin |
ML20141B759 | 9 May 1997 | Proposed 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 1997 | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio |
ML20141B856 | 9 May 1997 | Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys | Fuel cladding |
HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits | 29 April 1997 | Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits | Hydrostatic |
ML20133F364 | 7 January 1997 | Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done | Stroke time |
ML20138G627 | 19 December 1996 | Rev 11 to ODCM for Ei Hatch Nuclear Plant | |
ML20132G226 | 17 December 1996 | Proposed Tech Specs Re pressure-temp Limits | Hydrostatic |
ML20132E016 | 13 December 1996 | Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan | Safe Shutdown Fire Protection Program |
ML20135D488 | 3 December 1996 | Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 | Reactor Vessel Water Level Minimum Critical Power Ratio |
ML20129H918 | 29 October 1996 | Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware | |
ML20128M870 | 7 October 1996 | Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable | Stroke time |
ML20113F554 | 19 September 1996 | Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves | Unanalyzed Condition Shutdown Margin Anticipated operational occurrence Hydrostatic Fuel cladding |
ML20117M225 | 11 September 1996 | Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant | Safe 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 17 | 18 July 1996 | Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 | |
ML20115J486 | 16 July 1996 | Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 | Safe 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 |
ML20212C149 | 31 May 1996 | Stability Monitor | |
ML20117H139 | 21 May 1996 | Proposed 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 | |
ML20100P104 | 4 March 1996 | Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 | Shutdown Margin Reactor Vessel Water Level |
ML20100H743 | 21 February 1996 | Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F | |
ML20094K383 | 10 November 1995 | Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B | High Radiation Area Squib Pressure Boundary Leakage |
ML20093G940 | 5 October 1995 | Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 | |
ML20092H646 | 24 July 1995 | Ei Hatch Nuclear Plant Units 1 & 2 IST Program | |
ML20085K401 | 20 June 1995 | Proposed Tech Specs for Power Uprate | Shutdown Margin Reactor Vessel Water Level Hydrostatic Fuel cladding |
ML20086E847 | 19 June 1995 | Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds | |
ML20086E831 | 9 June 1995 | Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer | Nondestructive Examination Liquid penetrant |
ML20086E814 | 6 June 1995 | Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers | Earthquake |
ML20085A166 | 6 June 1995 | Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria | |
ML20086E812 | 17 May 1995 | Rev 0 to Design Spec 25A5718, Shroud Repair Hardware | Design basis earthquake Earthquake Liquid penetrant |
ML20082V379 | 4 May 1995 | Proposed Tech Specs,Minimizing Thermal Stratification Events | Reactor Vessel Water Level Hydrostatic |
ML20082L333 | 14 April 1995 | Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS | Reactor Vessel Water Level |
ML20081F347 | 14 March 1995 | Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor | Hydrostatic |
ML20077S033 | 13 January 1995 | Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt | Shutdown Margin Reactor Vessel Water Level Hydrostatic Fuel cladding |
ML20077D892 | 2 December 1994 | Proposed Deleted ETS | |
ML20078G716 | 1 November 1994 | Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 | |
ML20076L691 | 19 October 1994 | Proposed Improved Tech Specs,Rev F | Time 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 |
ML20149G375 | 13 October 1994 | Proposed 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 Obtained | Reactor Vessel Water Level |