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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARHL-5770, Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons1999-10-0101 October 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons HL-5811, Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys1999-07-29029 July 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC1999-02-0505 February 1999 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC HL-5694, Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors1999-01-21021 January 1999 Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.21998-12-0404 December 1998 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2 HL-5658, Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors1998-07-22022 July 1998 Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors HL-5400, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect1997-12-18018 December 1997 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect HL-5413, Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl1997-08-0808 August 1997 Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl HL-5362, Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys1997-05-0909 May 1997 Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys HL-5368, Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4)1997-05-0909 May 1997 Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4) ML20138H4021997-04-29029 April 1997 Application for Amend to License DPR-57,revising TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5345, Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-14014 April 1997 Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done1997-01-0707 January 1997 Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done HL-5270, Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 141996-12-0303 December 1996 Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 14 HL-5054, Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware1996-10-29029 October 1996 Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV1996-10-0707 October 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves1996-09-19019 September 1996 Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves HL-5163, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel1996-05-21021 May 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F1996-02-21021 February 1996 Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B1995-11-10010 November 1995 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B HL-4861, Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria1995-06-0606 June 1995 Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria HL-4816, Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events1995-05-0404 May 1995 Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS1995-04-14014 April 1995 Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS HL-4724, Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 21995-01-13013 January 1995 Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 2 HL-4723, Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes1994-12-0202 December 1994 Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes ML20078G7051994-11-0101 November 1994 Application for Amends to Licenses DPR-57 & NPF-5,converting TS to Improved TS Consistent w/NUREG-1433 HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained1994-10-13013 October 1994 Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained HL-4695, Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions1994-09-20020 September 1994 Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions HL-4648, Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys1994-08-16016 August 1994 Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys HL-4661, Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-14331994-08-0808 August 1994 Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-1433 ML20072B7441994-08-0404 August 1994 Application for Amend to License NPF-5,revising TSs for Traversing Incore Probe Operability Requirements HL-4651, Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable1994-07-19019 July 1994 Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable HL-4620, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 14331994-07-0808 July 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 1433 HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt1994-06-0707 June 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/41994-02-25025 February 1994 Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4 HL-3433, Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions1993-11-0909 November 1993 Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions HL-3416, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips1993-10-19019 October 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips ML20045E7261993-06-28028 June 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 3.7.A.4 & 3.6.4.1,respectively,to Allow One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing ML20044D0771993-05-0303 May 1993 Suppl to 920921 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Administrative Controls Section Re Semiannual Radioactive Effluent Release Rept to Reflect New 10CFR50.36a,per GL 89-01 HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F0231992-12-21021 December 1992 Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023 HL-2962, Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-161992-11-10010 November 1992 Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-16 HL-2006, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure..1992-10-19019 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure.. HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-011992-10-14014 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 HL-2390, Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-011992-09-21021 September 1992 Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-01 ML20118A5761992-09-18018 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,allowing Southern Nuclear Operating Co,Inc to Possess,Manage,Use, Operate & Maintain Facilities.Certificate of Concurrence from Southern Nuclear Operating Co,Inc Encl HL-2335, Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level1992-09-0202 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level HL-2355, Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error1992-07-30030 July 1992 Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error HL-2231, Application for Amends to Licenses DPR-57 & NPF-5,proposing to Revise Several Portions of TS Involving Shutdown & Refueling Operations1992-07-17017 July 1992 Application for Amends to Licenses DPR-57 & NPF-5,proposing to Revise Several Portions of TS Involving Shutdown & Refueling Operations HL-2225, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs to Add Addl Electrical Sys Requirements,Per Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers....'1992-07-17017 July 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs to Add Addl Electrical Sys Requirements,Per Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers....' HL-1946, Application for Amends to Licenses DPR-57 & NPF-5,changing Snubber Functional Test Insp Interval to 18 Months,Per Generic Ltr 90-091992-02-20020 February 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing Snubber Functional Test Insp Interval to 18 Months,Per Generic Ltr 90-09 1999-07-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARHL-5770, Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons1999-10-0101 October 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons HL-5811, Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys1999-07-29029 July 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC1999-02-0505 February 1999 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC HL-5694, Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors1999-01-21021 January 1999 Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.21998-12-0404 December 1998 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2 HL-5658, Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors1998-07-22022 July 1998 Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors HL-5400, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect1997-12-18018 December 1997 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J9351997-10-0606 October 1997 Corrected TS Pps to Amends 208 & 150 for Licenses DPR-57 & NPF-5,respectively,consisting of Pps 3.4-8 & 3.5-6 for Unit 1 & Pps 3.4-8 & 3.5-5 for Unit 2 to Reflect Revised SRV Setpoints HL-5413, Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl1997-08-0808 August 1997 Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl HL-5368, Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4)1997-05-0909 May 1997 Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4) HL-5362, Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys1997-05-0909 May 1997 Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys ML20138H4021997-04-29029 April 1997 Application for Amend to License DPR-57,revising TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5345, Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-14014 April 1997 Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20137N1751997-04-0404 April 1997 Amends 206 & 147 to Licenses DPR-57 & NPF-5,respectively, Revising Surveillance Requirements Addressing Reactor Vessel Pressure & Temperature HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done1997-01-0707 January 1997 Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done HL-5270, Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 141996-12-0303 December 1996 Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 14 HL-5054, Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware1996-10-29029 October 1996 Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV1996-10-0707 October 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves1996-09-19019 September 1996 Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves HL-5163, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel1996-05-21021 May 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F1996-02-21021 February 1996 Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B1995-11-10010 November 1995 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B HL-4861, Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria1995-06-0606 June 1995 Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria HL-4816, Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events1995-05-0404 May 1995 Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS1995-04-14014 April 1995 Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS HL-4724, Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 21995-01-13013 January 1995 Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 2 HL-4723, Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes1994-12-0202 December 1994 Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes ML20078G7051994-11-0101 November 1994 Application for Amends to Licenses DPR-57 & NPF-5,converting TS to Improved TS Consistent w/NUREG-1433 HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained1994-10-13013 October 1994 Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained HL-4695, Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions1994-09-20020 September 1994 Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions HL-4648, Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys1994-08-16016 August 1994 Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys HL-4661, Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-14331994-08-0808 August 1994 Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-1433 ML20072B7441994-08-0404 August 1994 Application for Amend to License NPF-5,revising TSs for Traversing Incore Probe Operability Requirements HL-4651, Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable1994-07-19019 July 1994 Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable HL-4620, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 14331994-07-0808 July 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 1433 HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt1994-06-0707 June 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/41994-02-25025 February 1994 Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4 HL-3433, Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions1993-11-0909 November 1993 Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20059E6831993-10-21021 October 1993 Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively, Relocating Procedural Details Contained in Radiological Effluent Ts,Incorporating New Part 20 & Revising Frequency of Reporting Radiological Effluent Releases HL-3416, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips1993-10-19019 October 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips ML20045E7261993-06-28028 June 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 3.7.A.4 & 3.6.4.1,respectively,to Allow One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing ML20044D0771993-05-0303 May 1993 Suppl to 920921 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Administrative Controls Section Re Semiannual Radioactive Effluent Release Rept to Reflect New 10CFR50.36a,per GL 89-01 HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F0231992-12-21021 December 1992 Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023 HL-2962, Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-161992-11-10010 November 1992 Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-16 HL-2006, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure..1992-10-19019 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure.. HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-011992-10-14014 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 HL-2390, Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-011992-09-21021 September 1992 Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-01 ML20118A5761992-09-18018 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,allowing Southern Nuclear Operating Co,Inc to Possess,Manage,Use, Operate & Maintain Facilities.Certificate of Concurrence from Southern Nuclear Operating Co,Inc Encl HL-2335, Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level1992-09-0202 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level HL-2355, Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error1992-07-30030 July 1992 Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error 1999-07-29
[Table view] |
Text
Grogia Power Company 40 inveness Con'er Pa*way Post Off(c eos 129s Denningtwn, Ale vna 3s201 ielaphone 205 B77-7273 n
J. T. Beckham, Jr. Georgia Power Vice Presdent - Nachiar HMch Project i 4 4 n Hn tre m HL-2390 003917 September 21, 1992 U.S. Huclear Regulatory Commission ATT!1: Document Control Desk Washington, D.C. 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 _
OPERAllNG LICENSES DPR-57, NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS 1!L A CORDANCE WITH CJfER]C LETTFR 89-01 Gentlemen:
In accordance with thc provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes a change to the Plant Hatch Units 1 and 2 lechnical Specifications (TS), Appendix A to Operating Licenses DPR-57 and NPF-5.
On January 31, 1989, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 89-01, " Implementation of Programmatic Controls for Radiological Ef fluent Technical Specifications into the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Radiological Effluent Technical Specificotions to the Offsite Dose Calculation Manual or to the Process Control Program." In GL 89-01, the NRC encouraged licensees to submit proposed changes to their -
plant TS which would relocate procedural details on radioactive effluents and radiological environmental monitoring to the Offsite Dose Calculation Manual (ODCM), and relocate procedural details on solid radioactive wastes to the Process Control Program (PCP). Such action would simplify the Radiological Effluent Technical Specifications (RETS), meet the regulatory requirements for radioactive effluents and radiological environmental monitoring, and would be categorized as a line-item improvement to the TS consistent with the Commission's Interim Policy Statement on Technical Specification improvements.
GPC has reviewed the recommendations of GL 89-01 and has elected to implement the guidance contained therein to prepare proposed changes to the Plant Hatch Unit I and Unit 2 TS.
This TS change request will (1) incorporate programmatic controls in the Administrative Controls section of the TS which satisfy the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a and Appendix 1 to 10 CFR Part 50, (2) relocate the existing procedural details in current TS involving radioactive effiuent monitoring instrumentation, the control of liquid and gaseous ef Guents, equipment requirements for 9209290250 920921 PDR AD9CK 05000321 S(ethls y~
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Geo:gia Power 1 U.S. Nuclear Regulatory Commission September 21, 1992 Page Two liquid and gaseous effluents, radiological environmental monitoring, and radiological reporting details from the IS to the ODCM, (3) relocate the definition of solidification and existing procedural details in the current TS on solid radioactive wastes to the PCP, (4) simplify the associated reporting requirements, (5) simplify the administrative controls for changes to the ODCM and PCP, (6) add record retention requirements for changes to the ODCM and PCP, (7) update the definitions of the ODCM and PCP consistent with these changes, (8) relocate definitions from the TS to the ODCM and PCP as appropriate, consistent witi, these changes, and (9) incorporn e terminology changes into the procedural details transferred from t'.e TS to the ODCM and PCP in order to facilitate the implementation of Gl 89-01.
The revised ODCM and PCP have been prepared iii accordance with the proposed changes to the Administrative Controls section of the TS so that their implementation can be coordinated with that of the proposed amendment, once issued.
Enclosure 1 provides the RETS cross-reference table which describes the disposition of the affected TS sections.
Enclosure 2 details the basis for our determination the proposed change does not involve a significant hazards consideration.
Enclosure 3 provides page change instructions for incorporating the proposed change, following Enclosure 3 are the proposed TS pages and the associated markups of the existing pages. Also following Enclosure 3 are copies of the proposed ODCM pages, which are to be revised due to this sange, and a complete copy of the proposed PCP.
To allow time for procedure revisions and orderly incorporation into copies of the TS, GPC requests the proposed amendment, once approved by the NRC, be issued with an effective date to be no later than 60 days from the date of issuance of the amendment.
In accordance with the requirements of 10 CFR 50.91, a copy of this letter and all applicable enclosures will be sent to the designated State official of the Environmental Protection Division of the Georgia Department of Natural Resources, i
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L,eOrgia Ibwer K(
U.S. Nuclear Regulator / Commission i September 21, 1992 Page Three l
Mr. J. T. Beckham, Jr. states he is duly authorized to ev. acute this oath on behalf of Georgia Power Company, and to the best vi his knowledge and belief, the facts set forth in this letter are true, i GEORG1A POWER COMPANY O
BY: f[/
- UfT. Ifeckham, Jr.
/
i Sworn to and subscribed before me this //- day of v Insd h 1992. ~
~'
- Je 2((w)Tublic/(adaJ -
g Etary MCM/cr wyctwrmtmusuaum 003917 Enclosures
- 1. RETS Cross-reference Table
- 2. 10 CFR 50.92 Evaluation
- 3. Page Change Instructions cc: Georaia Power. Company Mr. H. L. Sumner, General Manager - Nuclear Plant NOR*iS U.S. Nuclear Requlatory Corrqission. Washinaton. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion Il Mr. S. D. Ebneter, Regional Administrator Mr. L. D. Wert, Senior Resident Inspector - Hatch State of Geor_qia
' Mr. J.' D. Tanner, Commissioner - Department of Natural Resources
ENCLOSURE 1 ,
q PLANT HATCH - UNITS 1,'2 l NRC DOCKETS 50-321, 50-366 ;
OPERATING LICENSE DPR-57, NPF-5 REQUEST TO' REVISE TECHNICAL SPECIFICATIONS: ;
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS -i IN ACCORDANCE WITH GENERIC LETTER 89-01 ;
RETS CROSS-REFERENCE TABLE
GL 89-01 TS HNP TS !
REFERENCE REFERENCE .HNP TS TITLE DISPOSITION OF EXISTING HNP TS l
1.17 Sec 1.0, XX,-(Ul) 0FFSITE DOSE' Definition ' updated to reflect change in ODCM i Sec 1.0 (U2) CALCULATION MANUAL (0DCM) scope. ~l 1
1.22 Sec'l.0, VV (01)' PROCESS CONTROL PROGRAM Definition updated to reflect change in.PCP Sec.1.0-(U2) _ scope and revised to clarify content of PCP.
1.32 Sec 1.0, WW (01) ' SOLIDIFICATION Definition relocated,to PCP, App A, A.I.3.
Sec 1.0'(U2) l
-Sec 1.0, YY (Ul) GASE0US RADWASTE Definition relocated to ODCM, 7.1.1.
Sec 1.0, (U2) . TREATMENT SYSTEM 3/4.3.3.10 3/4.14.1 (Ul) RADI0 ACTIVE' LIQUID Programmatic ' controls included in PTS 6.18(1).
3/4.3.6.9 (U2) EFFLUENT INSTRUMENTATION TS procedural details relocated to ODCM, 1.7.1.
i
- See LEGEND on Sheet El 6 for definition of abbreviated terms.
HL-2390 003924 El-1 u _ _.
ENCLOSURE 1~(Continued)
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 89-01
.RETS CROSS-REFERENCE TABLE
- GL 89-01
- TS HNP TS REFERENCE . REFERENCE HNP TS-TITLE DISPOSITION OF EXISTING HNP TS 3/4.3.3.'l- 3/4.14.2 (01) RADI0 ACTIVE' GASEOUS .
. Programmatic controls included in PTS 6.18(1).
3/4.3.6.10.(U2) EFFLUENT INSTRUMENTATION TS procedural details relocated to ODCM, 2.6.1.
Requirements' for explosive gas monitoring instrumentation retained in HNP TS.
3/4.11.1.1 3/4.15.1.1 (Ul) LIQUID EFFLUENTS: Programmatic controls included in PTS 6.18(2) &
3/4.11.l.1 (U2) CONCENTRATION 6.18(3). TS procedural . details relocated to ODCM, 1.7.2.
3/4.11.1.3 3/4.15.1.2 (U1) LIQUID EFFLUENTS: DOSE Programmatic controls included in PTS 6.18(4) &'
6.18(5). TS procedural details relocated to ODCM, 1.7.3.
3/4.11.1.2: 3/4.15.1.3 (Ul) ' LIQUID EFFLUENTS:' LIQUID- Programmatic controls. included in PTS 6.18(6).
3/4.11.1.3 (U2) WASTE TREATMENT TS procedural details relocated to '0DCM,1.7.4.
3/4.11.1.4 3/4.15.1.4 (Ul) LIQUID HOLDUP TANKS Existing requirements retained in HNP TS.
3/4.11.1.4 (U2) 3/4.11.2.1 3/4.15.2.1 (U1) GASE0US EFFLUENTS: Programmatic controls included in PTS 6.18(3) &
3/4.11.2.1 (U2) DOSE: RATE- 6.18(7). ' TS procedural details relocated to 0DCM, 2.6.2.
HL-2390: -
003924 El-2 3 + g- , , y e-+:' .e + s-. .--w .
. ~
$NCLOSURE1(Continued)
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS.
IN ACCORDANCE WITH GENERIC LETTER 89-01 -l RETS CROSS-REFERENCE TABLE GL 33 '
TS HNP TS REFERENCE ret'ERENCE 'HNP TS TITLE DISPOSITION OF EXISTING HNP TS 3/4.11.2.2 3/4.15.2.2 (Ul) GASEOUS EFFLUENTS: Programmatic controls included in PTS 6.18(5) &
3/4.11.2.2 (U2) DOSE, NOBLE GASES 6.18(8). TS procedural details relocated to l
ODCM, 2.6.3.
i 3/4.11.2.'3 '3/4.15.2.3 (Ul) GASEOUS EFFLUENTS: Programmatic controls included in PTS 6.18(5) &
3/4.11.2.3-(U2) RADIOI0 DINES, RADI0 ACTIVE 6.18(9).: TS procedural details relocated to l MATERIAL IN PARTICULATE- ODCM, 2.6.4.
FORM, & RADIONUCLIDES OTHER THAN NOBLE GASES 3/4.11.2.4 3/4.15.2.4 (Ul) GASE0US EFFLUENTS: GASE0US Programmatic controls included in' PTS 6.18(6).
3/4.11.2.4 (U2) RADWASTE TREATMENT TS procedural details relocated to ODCM, 2.6 5.
3/4.11.2.5 3/4.15.2.6 (01) EXPLOSIVE GAS MIXTURE Existing requirements retained in HNP TS. '
3/4:11.2.6_(U2) 3/4.11.2.7- '3/4.15.2 7 (Ul) MAIN CONDENSER Existing requirements retained in HNP 15.
3/4.15.2.7 (U2) However, reference to TS 3.14.2 and 3.3.6.10
- j. changed to reference ODCM.
3/4.11.3 3/4.15.3-(Ul) RADIOACTIVE EFFLUENTS: Programmatic controls included in PTS 6.20.
3/4.11.3 (U2) SOLID RADI0 ACTIVE WASTE TS procedural details relocated to PCP, App A, A.3..
l l
HL-2390-003924 El-3
ENCLOSURE 1 (Continued)
RADIOLOGICAL EFFLUENT TECHNICAL' SPECIFICATIONS
.JfLACCORDANCE WITH GENERIC LETTER 89-01 RETS CROSS-REFERENCE TABLE GL 89-01
~TS liNP TS
! REFERENCE REFERENCE HNP TS TITLE DISPOSITION OF EXISTING HNP TS 3/4.11.4 3/4.15.2.5 (Ul) RADI0 ACTIVE EFFLUENTS: Programmatic controls included in PTS 6.18(10).
3/4.11.2.5 (U2) TOTAL DOSE TS procedural details relocated to 00CM, 4.1.1.
3/4.12.1 3/4.16.1 (Ul) .
RADIOLOGICAL ENVIRONMENTAL Programmatic controls included in PTS 6.19(1).
-(Also covers U2)- . MONITORING: MONITORING TS procedural details relocated to ODCM, 3.1.I'.
PROGRAM 3/4.12.2 3/4.16.2 (Ul) RADIOLOGICAL ENVIRONMENTAL Programmatic controls included in PTS 6.19(2).
(Also covers'U2) MONITORING: LAND USE SURVEY TS procedural details relocated to 00CM, 3.1.2.
3/4.12.3 3/4.16.3 (Ul) RADIOLOGICAL' ENVIRONMENTAL Programmatic controls included in PTS 6.19(3).
(Also covers U2)' MONITORING: INTERLABORA10RY TS procedural details relocated to 00CM, 3.1.3.
COMPARISON PROGRAM 5.1.3 Fig. 3.15-1 (01)- UNRESTRICTED AREA BOUNDARY Figure retained in TS. Map also duplicated in Fig. 3.11-1.(U2) ODCM Figure 1.7-1 for convenience.
6.8.4 9 --
RADI0 ACTIVE EFFLUENTS Programmatic controls for radioactive effluents 4 CONTROL PROGRAM presented in PTS 6.18.
6.8.4.h --
RADIOLOGICAL' ENVIRONMENTAL Programmatic controls for radioactive effluents MONITORING-PROGRAM presented in PTS 6.19.
. HL-2390 t -003924 El-4
i ENCLOSURE 1 (Continued)
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 89-0!
RETS CROSS-REFERENCE TABLE l
GL 89-01 l TS HNP TS l REFERENCE HNP TS TITLE DISPOSITION OF EXISTING HNP TS
! REFERENCE l
l 6.9.1.6 TS 6.9.1.6 updated to reflect change in GL 89-01, 6.9.1.3 REPORTING REQUIREMENTS:
Enclosure 3, item 6.9.1.3. TS 6.9.1.7 deleted I 6.9.1.7 ANNUAL RADIOLOGICAL with reporting details relocated to 00CM. 6.1.
(UI, U2) ENVIRONMENTAL SURVEILLANCE REPORT 6.9.1.8 TS 6.9.1.8 updated to reflect change in GL 89-01, 6.9.1.4 REPORTING REQUIREMENTS:
Enclosure 3, item 6.9.1.4. TS 6.9.1.9 deleted 6.9.1.9 SEMIANNUAL RADIOACTIVE with reporting details relocated to 00CM, 6.2.
(UI, U2) EFFLUENT RELEASE REPORT Reporting details pertaining to solid radwaste also included in PCP, App A, A.4.1.
( Record retention requirements included in PTS 6.10 6.10.2 RECORD RETENTION 6.10.2.0 in accordance with GL 89-01, (UI, U2) Enclosure 3, item 6.10.
HL-2390 003924 El-5
l ENCLOSURE 1 (Continued)
.t RADIOLOGICAL EFFLUENT. TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GFNERIC LETTER 89-01 .
RETS CROSS-REFERENCE TABLE !
GL 89-01 TS HNP TS REFERENCE REFERENCE HNP TS TITLE DISPOSITION OF EXISTING HNP TS t
6.13 --
PROCESS CONTROL GL 89-01 states programmatic requirements for PCP CONTROL PROGRAM'(PCP) be retained in TS. However, GL 89-01 provides no ;
i guidance for incorporating programmatic controls pertaining to PCP into TS. TS 6.20 proposes'to incorporate definition of PCP stated in GL 89-01 :
as program description for PCP. Also included in ll PTS 6.20 are requirements related to PCP changes 1' in accordance with GL 89-01, Enclosure 3, item 6.13. ,
6.14 6.17 0FFSITE DOSE CALCULATION TS 6.17 requirements modified in accordance with
"(U1,'U2) MANUAL (ODCM) GL 89-01, Enclosure 3, item 6.14. l LEGEND:
PCP = Process Control Program U2 = Unit 2 TS = . Technical Specification (s) HNP = Hatch Nuclear Plant PTS = Proposed ' Technical Specification (s) GL = Generic Letter Ul - Unit 1
?
l f .
HL-2390 L 003924 El-6. j
i l
ENCLOSURE 2 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 REQUEST 10 REVISE TECHNICAL SPEClflCATIONS:
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LET1ER 89-01 10 CFR 50.92 EVALUATION PROPOSED CHANGE:
The proposed changes to the Plant Hatch Unit I and Unit 2 Technical Specifications (TS) will implement the recommendations contained in Generic Letter (GL) 89-01. The proposed changes add new programmatic requirements governing radioactive effluents, radiological environmental monitoring, and snlid radioactive wastes to the Administrative Controls Section of the TS.
Procedural details contained in existing TS pertaining to radioactive effluents. -
radiological environmental monitoring, solid radioactive wastes, and associated reporting requirements are being relocated to the ODCM or the PCP, as appropriate. In additicn, changes are proposed to other portions of the TS to accommodate the incorporation of GL 89-01. The details concerning these changes are provided in Enclosure 1.
BASIS FOR PROPOSED CHANGE:
By letter dated January 31, 1989, the Nuclear Regulatory Commission (NRC) issued GL 89-01, " Implementation of Programmatic Controls for Radiologicsl Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the _
Offsite Dose Calculation Manual (0DCM) or to the Process Control Program (PCP),"
and encouraged licensees to propose changes to their TS consistent with the guidance contained therein. Accordingly, Georgia Power Company (GPC) has prepared these proposed changes consistent with the guidance contained in GL 89-01. Such action will simplify the RETS, meet the regulatory requiremer.;s for radioactive effluents and radiological environmental monitoring, and implement a line-item improvement to the TS, consistent with the Commission's Interim Policy Statement on Technical Specification Improvements.
ANALYSIS The level of radiological control will not be reduced by the proposed changes to the TS since compliance with applicable regulatory requirements governing radioactive effluents and radiological environmental monitoring, including 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 will continue to be maintained. The proposed changes will allow for the relocation of procedural details frca the RETS to the ODCM or PCP, as appropriate.
HL-2390 003917 E2-1
- . , . - - - - . . . _ . . . - - - - - . . - .- - .- - -. - - - .- -~
bI I
1 i
ENCLOSURE 2 (Continued)
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS JN ACCORDANCE WITH GENERIC LETTER 89-01 10 CFR 50.32 EVALUATION Accordingly, future changes to these procedural details will be contrclled by the controls for changes to the 00CM or PCP included in the proposed changes to the Administrative Controls section of the TS. These procedural details are not required to be included in the TS by 10 CFR 50.36'.
- GPC has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed RETS changes and has made the following determination:
- 1. The proposed changes do not involve a significant increase in the probability or consequences of an accident _ previously evaluated. The proposed changes are administrative in nature and alter only the format'and location of programmatic controls and procedui i details relative to radioactive effluents, radiological environme,tal monitoring, solid ,
radioactive wastes, and associated reporting requictments, Compliance with applicable regul atory requirements will continue to be maintained. in addition, the proposed changes do not alter the conditions or assumptions in any of the FSAR accident analyses. Since the FSAR accident analyses remain bounding, the radiological consequences previously evaluated are not adversely affected by the proposed changes. Therefore, it can be concluded that the proposed changes do not involve a significant increase in the ,
probability or consequences of an accident previously evaluated.
- 2. The proposed changes do not create the possibility of a new or different '
kind of accident from those previously evaluated. The proposed changes oo ,
not involve any change to the configuration or method of operation of any l plant equipment. Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting
, single failure been identified as a result of the proroced changes. Also, there will be no change- in types or increarc in the amounts of any radioactive effluents released offsite. 1herefore, it can be concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed changes do not involve a significant reduction in a margin of safety. The proposed changes do not involve any actual change in the
-methodology used in the control of radioactive effluents, soli? adioactive wastes, or radiological environmental monitoring. Thesc .anges are considered administrative in nature, provide for the relacation of
. procedural details outside the TS, and add appropriate administrative e controls to provide continued assurance of compliance with applicable regulatory requirements. These proposed changes al so comply -with the a
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ENCLOSURE 2 (Continued) ;
- - - - i RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN ACCORDANCE Wi1H GENERIC LETTER 89-01 i 10 CFR.50.92 EVALVATIDN ;
guidance contained in GL 89-01. Therefore, it can be concluded that the I proposed changes do not involve a significant reduction in a margin of 4 safety.
i l
CONCLUSIONt Based on the preceding analysis, GFC has determined that the proposed _ changes to i
the TS will not significantly increase the probaoility or consequences of an accident previously evaluated, create the possibility of a ns or different kind of accident from any accident previously evaluated. -or involve a significant reduction in a margin of safety. Therefore, GPC has determined that the proposed changes meet the requirements of 10 CFR 50.92(c) and do not involve a-significant hazards consideration t
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