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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
"-
pi; Georga P er Comhany 333 Pedmont Aymue
,-'~ Ati:nta, Georga 30308 -
- Telephone 404 526-6526 e x 4545 '
A:lanta. Georgia 30302
- J' ames P. O'Reilly -. the southem electrc system Senior Vice President -
Nuclear Operations 'J
' SL-1441 3049N: l
. October 27, 1986-Director of Nuclear Reactor Regulation Attention: l Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555- ,
NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS-REGARDING CORPORATE AND ONSITE ORGANIZATION Gentlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes changes to the L Plant Hatch Units 1 and 2 Technical Specifications (TS) and Environmental Technical Specifications (ETS), Appendices A and B, respectively, to Operating Licenses DPR-57 and NPF-5.
These proposed changes, which are strictly administrative in nature, would revise the administrative controls in the TS (Section 6.0) and the ETS (Section 5.0) to reflect recent changes to company organization.
These organization changes, as outlined in our. letter of October 13, 1986 to Dr. J. N. Grace of NRC Region II~, are designed to enhance our ability to safely and effectively operate Plant Hatch. These organizational changes were additionally discussed with NRC Region II Management by Mr.
J. H. Miller, President, and Mr. H. G. Baker, Senior' Executive Vice President, on September 22, 1986 and by Mr. J. P. O'Reilly, Senior Vice President Nuclear Operations on October 7,1986.
Enclosure 1 provides a detailed description of the proposed changes and circumstances necessitating the change request.
Enclosure 2 details the bases for our determination that the proposed changes do not involve a significant hazards consideration.
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- $60%
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L Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 October 27, 1986 Page.Two Portions of the proposed changes represent partial . revisions to our previous organizational change submittals of February 17, 1986 and May 16, 1986. Certain changed pages provided as part of this submittal additionally reflect these previously proposed changes. The remaining pages of the previous submittals are unaffected. Enclosure 3 provides a table delineating which proposed changed pages affect which previous submittals.
Enclosures 4A and 4B provide page change instructions for incorporating the proposed changes.
The proposed changed Technical Specifications pages follow Enclosures 4A and 4B.
Payment of filing fee is enclosed.
Pursuant to the requirements of 10 CFR 50.91, a copy of this letter and all applicable attachments will be forwarded to Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources.
Mr. J. P. O'Reilly states that he is Senior Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter are true.
GECRGIA POWER COMPANY By: hs f Oh0L James P. O'Reill Sworn to and subscribed before me this 27th day of October 19 th 2& Mb i Notary Public Natory Public, Clayton County, Georgia REBkC mm'ssi n Experes Dec. 12,1989 Enclosures
,7y - , . . - - - _ _ . . - . . . . ,. _ . . . - . - - - - , , ~ ,, _ , , . . . .-.-_-e.._ - . . . . . . . . . ~ _ _ _ _ _ _ ,
i Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 October 27, 1986 Page Three l c: Georria Power Company Nuclear Regulatory Commission l Mr. i . T. Beckham, Jr. Dr. J. N. Grace, Regional Administrator l Mr. H. C. Nix, Jr. Mr. P. Holmes-Ray, Senior Resident l Inspector Hatch GO-NORMS i
l State of Georgia Mr. J. L. Ledbetter l
l 3049N
h k ENCLOSURE 1 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANGE REQUEST The proposed changes to the Plant Hatch Units 1 and 2 TS and ETS fall into four categories: 1) Changes reflecting the creation of a Senior Executf ve Vice President position in the corporate office. 2) Changes reflecting the creation of an onsite executive position, Vice President Plant Hatch. 3) Changes reflecting restructuring of plant departments.
- 4) Proposed deletion from the TS and ETS of the onsite and offsite organizational charts.
Proposed Change 1:
A new position of Senior Executive Vice President has been created in the corporate office. This position reports directly to the President of GPC, and is responsible for all activities related to power supply. The Senior Vice President Nuclear Operations and the General Manager Quality Assurance report to this position. The Senior Executive Vice President position is similar in function and structure to the previous position titled Executive Vice President Power Supply, which has been eliminated.
Figure 1 of this enclosure provides, for information, a partial organizational chart focusing on the new position and its relationship to the Plant Hatch management structure.
I The following areas of TS and ETS (Units 1 and 2) are affected by proposed change 1:
- 1. TS 6.5.2.10 Audit reports encompassed by Section 6.5.2.8 shall be forwarded to the Senior Executive Vice President instead of the Executive Vice President Power Supply.
- 2. ETS 5.0 Corporate responsibility for implementing the ETS rests with the Senior Executive Vice President rather than the Executive Vice President Power Supply.
Proposed Change 2:
A new onsite executive position of Vice President Plant Hatch has been created. This position reports directly to the Senior Vice President Nuclear Operations and maintains the line authority and responsibility previously held by the corporate position of Vice President and General fianager Nuclear Operations, which has been eliminated. Figures 2 and 3 of this enclosure provide, respectively, the relationship of the Vice 3049N El-1 10/27/86
c4-1 ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANGE REQUEST B
President Plant Hatch to the onsite and corporate organizations. In addition, changes .to the corporate support staff have been provided to
- reflect the creation of the onsite executive position and elimination of
- ' the previous - corporate position of Vice President and General Manager Nuclear Operations. Figure 4 of this enclosure provides, for
- information, the new structure of the corporate support staff.
The following areas of TS and ETS (Units 1 and 2) are affected by
. proposed change 2:
- 1. Proposed TS 6.1.0 is added to indicate the addition of the onsite executive position.-
! 2. TS 6.5.1.6 The Plant Review Board (PRB) shall forward reports of investigations of reportable violations of the TS to the Vice i President Plant Hatch and the Senior Vice President Nuclear
! Operations, rather than to the Vice President and General Manager Nuclear Operations. These reports are also provided to the Safety Review Board (SRB).
- 3. TS 6.5.1.7 The PRB shall . provide notification of disagreement between the PRB and the Plant Manager (see proposed change 3) to the i' Vice-President Plant Hatch and to the Senior Vice President Nuclear j Operations, rather than to the Vice President and General Manager j Nuclear Operations. This notification is also provided to the SRB.
! 4. TS 6.5.1.8 Copies of PRB meeting minutes shall be provided to
- j. the Vice President Plant Hatch and the Senior Vice President Nuclear l
Operations, rather than to the Vice President and General Manager
- Nuclear Operations. These minutes are also provided to the SRB.
1 S. TS 6.6.1.b Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be submitted to the Vice President Plant i Hatch and the Senior Vice President Nuclear Operations, rather than '
to the Vice President and General Manager Nuclear Operations. These reports are also submitted to the SRB.
l
- 6. TS 6.7.1.b and 6.7.1.d Safety limit violations shall be reported to the Vice President Plant Hatch and to the Senior Vice President l+ Nuclear Operations, rather than to the Vice President and General Manager Nuclear Operations. These reports are also submitted to the ,
SRB.
3049N El-2 10/27/86 l
1 i
~ ~
ENCLOSURE 1 l l
I REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANGE REQUEST
. Proposed Change 3:
In order to optimize the effectiveness of the assignment of a corporate officer - onsite, the onsite organization has been modified appropriately.
Figure 2 _ of this enclosure provides, for information, the new onsite departmental .and managerial structure. The previous position of General
- Manager - Plant Hatch has been retitled Plant Manager. The Plant Manager continues to have overall and direct responsibility for operation of the units. However, the Plant Manager's functional responsibilities . have been redefined to focus on those activities strictly related to - the safety and effectiveness of day-to-day operation of the plant (Operations, Maintenance, Health Physics and Chemistry.) A new position of Plant Support Manager has been formed to oversee support-type functions (Engineering, Security, Outages and Planning, Administrative Support). The position of Deputy General Manager - Plant Hatch has been eliminated. The Plant Manager and the Plant 1 Support Manager report directly to the Vice President Plant - Hatch.
Additionally, two other manager positions report directly to the Vice President Plant Hatch. These are the Manager Plant Training and Onsite Emergency Preparedness, and the Manager Nuclear Safety and Compliance. This reflects GPC's emphasis in these important areas. The Hatch Quality Assurance Site Manager's primary onsite line of communication is now with the Vice President Plant Hatch instead of the General Manager - Plant Hatch (now Plant Manager).
The position of Plant Manager will continue to fill the responsibilities presently included in the TS and ETS for the General Manager Plant Hatch, with the following exceptions:
- 1. TS 6.1.1 is revised to reflect that the Plant Support Manager has responsibility for plant support functions.
- 2. As previously noted, the Hatch Quality Assurance Site Manager's primary line of onsite communication will be with the Vice President Plant Hatch rather than the the General Manager Plant Hatch (now Plant Manager).
- 3. Approval of administrative procedures and security plan implementing procedures and changes thereto, pursuant to TS 6.8.2, will be performed by l the Plant Support Manager, rather than the General Manager Plant Hatch (now Plant Manager). Approval of Emergency plan implementing procedures and changes thereto will be performed by the Manager Plant Training and Onsite Emergency Preparedness, rathar than the General Manager Plant Hatch (now Plant Manager). Temporary procedure changes may be approved, pursuant to TS 6.8.3, by the Plant Manager or Plant Support Manager.
i 3049N El-3 10/27/86
ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANGE REQUEST Proposed Change 4:
It is proposed to delete TS Figures 6.2.1-1 and 6.2.2-1 depicting offsite and unit organizations, respectively, and ETS Figure 5.2-1, depicting the organization structure related to environmental activities. The presence of these figures in the TS and ETS results in numerous amendment' requests. The approval cycle for these requests is such that the figures in the TS and ETS tend to be out of date. Section 13 of the Hatch Unit 2 Updated FSAR contains organizational information and charts depicting, in equivalent detail, the information hereby proposed for deletion from the -
Technical . Specift:ations. This FSAR information is required to be updated and submitted to NRC annually under the provisions of 10 CFR 50.71. The NRC has provided a Safety Evaluation supporting the deletion of organization charts from the Technical Specifications of the McGuire Nuclear Station. (Reference Amendment 52 to Operating License NPF-9 and Amendment 33 to Operating License NPF-17, issued March 19, 1986.) The NRC's Safety Evaluation for these amendments found this change acceptable because "...the two figures were in error in some respects, and their inclusion in the Technical Specifications was redundant because they are contained in Chapter 13 of the McGuire Nuclear Station Final Safety Analysis Report, and are maintained there in accordance with 10 CFR 50.71." GPC proposes deletion on this same basis.
3049N El-4 10/27/86
y ENCLOSURE 1 Figure 1 CORPORATE ORGANIZATION PRESIDENT SENIOR EX ECUTIVE VIC E PRESIDENT ENGINEERING FOSSIL AND NUCLEAR QUALITY VOGTLE AND CONSTRUCTION ASSURANCE HYDRO SERVICES OPERATIONS PROJECT POWER
ENCLOSURE 1 Figure 2 ONSITE ORGANIZATION CORP.
OA VICE PRESIDENT - -
HATCH QA SITE P LANT HATC H MANAGER Iu .
E E MANAGER PLANT PLANT MANAGER TRAINING AND PLANT SUPPORT -
NUCLEAR SAFETY ONSITE EMERGENCY MANAGER
^" " " # "
PREPAREDNESS MANAGER NUCLEAR MANAGER SECURITY OPERATIONS SUPT.
MANAGER MANAGER ENGINEERING MAINTENANCE SUPPORT MANAGER MANAGER HEALTH PHYSICS OUTAGES AND AND CHEMISTRY PLANNING
- - - LINES OF COMMUNICATION MANAGER LINES OF RESPONSIBILITY GENERAL SUPPORT
ENCLOSURE 1 Figure 3 NUCLEAR O P ERATIO N S LINE ORGANIZATION SENIOR VICE PRESIDENT NUCLEAR O P ERATIO N S l
SAFETY CORP.
R EVIEW SUPPORT BOARD STAFF VIC E GENERAL j PRESIDENT MANAGER HATCH -
VOGTLE
ENCLOSURE 1 Figura 4 CORPORATE SUPPORT STAFF SENIOR VICE PRESIDENT NUCLEAR OPERATIONS ASSISTANT ASSISTANT FOR FOR OPERATIONS FINANCE
=
MANAGER MANAGER MANAGER
- " EA ^
_ - _ * "& %" sAF AND PERFORMANCE LICENSING SUPPORT VICE GENERAL PRESIDENT MANAGER HATCH VOGTLE
I i,
ENCLOSURE 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2
!. REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
i CORPORATE AND ON5ITE ORGANIZATION I L 10 UrR 50.9Z EVALUATIDH
[ Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the l enclosed proposed amendments to the Plant Hatch 'Jnits 1 and 2 Technical Specifications and has determined that their adoption would not involve a significant hazards consideration. The basis for this determination is L as follows:
Proposed Change 1:
Provide changes to the Technical Specifications and Environmental
- . Technical Specifications to reflect the creation of a new corporate position, Senior Executive Vice President.
l Basis For Proposed Change 1:
This change is consistent with Item (i) of the " Examples of Amendments That are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal Register April 6, ,
1983. Item (1) covers changes which are purely administrative. The proposed organizational changes affect only the Administrative Controls section of the Plant Hatch Units 1 and 2 Technical Specifications and ;
Environmental Technical Speci fications. Georgia Power Company has proposed changes and has determined that they do not
! reviewed these ;
involve a significant hazards consideration for the following reasons:
) A. The probability of occurrence and the consequences of an
! accident or malfunction of equipment important to safety would not be increased above those analyzed in the FSARs, because the l
changes are administrative in nature and do not affect the !
l operation of any plant equipment or system.
i B. The possibility of an accident or malfunction of a different type than any previously analyzed in the FSARs would not be created, because the changes are administrative in nature and l
would not introduce any new modes of plant equipment operation
- or failure.
C. Margins of safety would not be significantly reduced because the changes only affect the " Administrative Controls" section of the Technical Specifications and Environmental Technical 3049N E2-1 10/27/86
ENCLOSURE 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION 10 CFR 50.92 EVALUATION Specifications and, therefore, do not change any Limiting Condition for Operation, Surveillance Requirement, Trip Setpoint Allowable Value, Limiting Safety System Setting, Safety Limit, or Definition. Therefore, margins of safety are unaffected by this proposed change.
Proposed Change 2:
1 Provide changes to the Technical Specifications to reflect the creation l of an onsite executive position, Vice President Plant Hatch.
Basis For Proposed Change 2:
This change is consistent with Item (i) of the " Examples of Amendments That are Considered Not Likely to Involve Significant Hazards Considerations" 1.isted on page 14,870 of the Federal Register, April 6, 1983. Item (i) covers changes which are purely administrative. The proposed organizational changes affect only the Administrative Controls section of the Plant Hatch Units 1 and 2 Technical Specifications.
Georgia Power Company has reviewed these proposed changes and has determined that they do not involve a significant hazards consideration for the following reasons:
A. The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety would not be increased above those analyzed in the FSARs, because the changes are administrative in nature and do not affect the operation of any plant equipment or system.
B. The possibility of an accident or malfunction of a different type than any previously analyzed in the FSARs would not be created, because the changes are administrative in nature and would not introduce any new modes of plant equipment operation or failure.
C. Margins of safety would not be significantly reduced because the changes only affect the " Administrative Controls" section of the Technical Specifications and, therefore, do not change any Limiting Condition for Operation, Surveillance Requirement, Trip Setpoint Allowable Value, Limiting Safety System Setting, Safety Limit, or Definition. Therefore, margins of safety are unaffected by this proposed change.
3049N E2-2 10/27/86
L ENCLOSURE 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION 10 CFR 50.92 EVALUATION Proposed Change 3:
Provide changes to the Technical Specifications and Environmental ;
Technical Specifications to reflect restructuring of plant departments '
and management titles.
Basis For Proposed Change 3:
This change is consistent with Item (i) of the " Examples of Amendments That are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal Register, April 6, 1983. Item (i) covers changes which are purely administrative. The proposed organizational changes affect only the Administrative Controls section of the Plant Hatch Units 1 and 2 Technical Specifications and Environmental Technical Specifications. Georgia Power Company has reviewed these proposed changes and has determined that they do not involve a significant hazards consideration for the following reasons:
A. The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety would not be increased above those analyzed in the FSARs, because the changes are administrative in nature and do not affect the
. operation of any plant equipment or system.
B. The possibility of an accident or malfunction of a different type than any previously analyzed in the FSARs would not be created, because the changes are administrative in nature and
- would not introduce any new modes of plant equipment operation i or failure.
C. Margins of safety would not be significantly reduced because the l changes only affect the " Administrative Controls" section of the l Technical Specifications and Environmental Technical 3049N E2-3 10/27/86
ENCLOSURE 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
i- CORPORATE AND ONSITE ORGANIZATION 10 CFR 50.92 EVALUATION Specifications and, therefore, do not. change any Limiting-Condition for Operation, Surveillance Requirement, Trip Sotpoint Allowable Value, Limiting Safety System Setting, Safety Limit, or Definition. Therefore, margins of safety are unaffected by this proposed change.
Proposed Change 4:
Provide changes to the Technical Specifications and Environmental Technical Specifications to delete TS Figures 6. 2.1 -1 and 6. 2. 2-1 depicting offsite and unit organizations, respe::tively, and ETS Figure
- 5. 2-1, depicting the organization structure related to environmental activities.
Basis For Proposed Change 4:
This change is consistent with Item (i) of the " Examples of Amendments That are Considered Not Likely. to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal Register, April 6, 1983. Item (i) covers changes which are purely administrative. The proposed deletion of - organizational charts affects only the Administrative Controls sections of the Plant Hatch Units 1 and 2 Technical Specifications and Environmental Technical Specifications.
Georgia Power Company has reviewed these proposed changes and has determined that they do not involve a significant hazards consideration for the fo11Cng reasons:
A. The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety would not be increased above those analyzed'in the FSARs, because. the changes are administrative in nature and do not affect the operation of any plant equipment or sys_ tem. All information proposed for deletion is contained in Chapter 13 of the Plant j Hatch Unit 2 Updated Final Safety Analysis Report, which is i updated annually pursuant to 10 CFR 50.71. ;
J B. The possibility of an accident or malfunction of a different type than any previously analyzed in the FSARs would not be
< created, because the changes are administrative in nature and would not introduce any new modes of plant equipment operation or failure.
C. Margins of safety would not be significantly reduced because the
-3049N E2-4 10/27/86
San ENCLOSURE 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION 10 CFR 50.92 EVALUATION changes only affect the " Administrative Controls" section of the Technical Specifications and Environmental Technical Specifications and, therefore, do not change any Limiting Condition for Operation, Surveillance Requirement, Trip Setpoint Allowable Value, Limiting Safety System Setting, Safety Limit, or Definition. Therefore, n:argins of safety are unaffected by this proposed change.
3049N E2-5 10/27/86
ENCLOSURE 3 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST T0 REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION PREVIOUS SUBMITTALS AFFECTED The proposed changes to the Plant Hatch Units 1 and 2 Technical Specifications (TS) and Environmental Technical Specifications (ETS) in part represent revisions to previous change requests dated February 17, 1986 and May 16, 1986. Certain TS and ETS pages provided following reflect these previously submitted changes. The following table provides infor. nation as to which proposed changed pages for each unit affect which previous submittal s. The remainder. of the pages provided in.the previous submittals are unaffected and should be acted on as previously submitted.
Unit 1 page # Unit 2 page # Previous submittal affected Technical Specification Pages:
x -
none 6-1 6-1 2/17/86 6-la 6-l a none 6-2 6-2 none 6-3 6-3 none 6-6 6-5 5/16/86 6-7 6-6 2/17/86, 5/16/86 6-8 6-7 2/17/86 6-12 6-11 2/17/86, 5/16/86 6-13 6-12 2/17/86 6-13a 6-12a 2/17/86 Environmental Technical Specification Pages:
iii 111 none 5-1 5-1 2/17/86 5-3 5-3 -
2/17/86 5-5 5-5 2/17/86 5-10 5-10 none 3049N E3-1 10/27/86
a
+
L ENCLOSURE 4A
^
NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION INSTRUCTIONS FOR INCORPORATION: UNIT 1 ihe proposed changes to the Technical Specifications (Appendix A to Operating License DPR-57) and Environmental Technical Specifications (ETS) (Appendix B to Operating License DPR-57) would be incorporated as follows:
- REMOVE PAGE INSERT PAGE X X 6-1 6-1 6-la 6-la 6-2 ---
6-3 ---
! 6-6 6-6 6-7 6-7 6-8 6-8 6-12 6-12 1
6-13 6-13
. 6-13a 6-13a ETS iii ---
ETS 5-1 ETS 5-1 ETS 5-3 ETS 5-3 ETS 5-5 ETS 5-5 ETS 5-10 ---
4 4
3049N 10/27/86 f
_~ _. , , _ , . _ _ _ _ . . _ , _ . __ . . _ _ - __,_,.____..._-_.,-...____m_._m_._m,_,,,_.-_- %w . r --.--3 _ . . - . - y-,,
4 k
ENCLOSURE 4B l H
NRC DOCKETS 50-321, 50-366 '
.0PERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1,-2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION INSTRUCTIONS FOR INCORPORATION: UNIT 2 The proposed changes 'to the Technical Specifications (Appendix A to' Operating License NPF-5) and Environmental Technical Specifications (ETS)
(Appendix B to Operating License NPF-5) would be incorporated as follows:
REMOVE PAGE INSERT PAGE 6-1 6-1 6-la 6-l a 6-2 -
6-3 ---
6-5 6-5 6-6 6-6 6-7 6-7 6-11 6-11 6-12 6-12 6-12a 6-12a ETS iii ---
ETS 5-1 ETS 5-1 ETS 5-3 ETS 5-3 ETS 5-5 ETS 5-5 ETS 5-10 ---
3049N 10/27/86