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MONTHYEARML20154D6151988-05-0606 May 1988 Proposed Tech Spec Section 6, Administration Controls, Replacing Organization Charts W/More General Requirements Project stage: Other ML20154D6081988-05-0606 May 1988 Application for Amends to Licenses DPR-57 & NPF-5,replacing Organization Charts in Tech Specs W/General Requirements. Change Consistent W/Guidance Provided in Generic Ltr 88-06. Fee Paid Project stage: Request ML20155B2501988-06-0707 June 1988 Proposed Tech Specs,Changing Ref to Senior Vice president-nuclear Operations & Vice president-plant to Vice president-nuclear & General manager-nuclear Plant, Respectively Project stage: Other ML20155B2331988-06-0707 June 1988 Application for Amends to Licenses DPR-57 & NPF-5,revising Ref to Senior Vice president-nuclear Operations & Vice president-plant to Vice president-nuclear & General manager-nuclear Plant,Respectively Project stage: Request 1988-05-06
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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
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- SL-3970 0921m X7GJ17-H600 May 6, 1988 U. S. Nuclear Regulatory Commission ATTN
- Document Control Desk Hashington, D. C. 20555 PLANT HATCH - UNITS 1, 2 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES OPR-57, NPF-5 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 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.
The proposed amendment replares the organization charts in the Technical Specifications with more general organizational requirements. These general requirements capture the essential organizational features depicted on the 4
charts necessary for ensuring that the plant is operated safely. This change is consistent with the guidance provided in Generic Letter 88-06 "Removal of Organization Charts from Technical Specification Administrative Control Requirements", issued on March 22, 1988.
Enclosure 1 provides detailed descriptions of there preposed changes and -
circumstances n;tessitating the change request.
Enclosure 2 details the bases for our determination that the proposed changes do not involve significant hazards considerations.
Enclosure 3 provides page change instructions for incorporating the l nroposed changes. The proposed changed TS and ETS pages for Unit I and Unit 2 '
follow Enclosure 3.
9 d
lb f 00 0 4k 8905190260 PDR 880506 I\
i P ADOCK 05000321 DCD
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l GeorgiaPower A l U. S. Nuclear Regulatory Commission May 6, 1988 Page Two
! 4 Payment of the filing fee in the amount of one hundred fif ty dollars is enclosed.
In order to allow time for procedure revisions and orderly incorporation into copies of TS, we request that 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 issutv.e 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 Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of !
Natural Resources. '
Mr. R. P. Mcdonald states that he is an Executive Vice President of Georgit Power Company and is authorizsf 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 and enclosures are true.
GEORGI 40HER COM ANY t
By: b<
R. P. Mcdonald Sworn to and subscribed before me this 6th day of May 1988.
tLPs -
' ' ~[Y/ *mau 4
Notaty Public **""rMan,wh'hatunes D m tage i GPD/lc
Enclosures:
.' 1. Basis for Change Request i l 2. 10 CFR 50.92 Evaluation I i 3. Page Change Instructions l J
- 4. Filing Fee - $150.00 l 1 '
c: (see next page)
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Georgia Power d U. S. Nuclear Regulatory Comission '
Hay 6, 1988 Page Three c: Georgi LEow1LCo.uany Mr. J. T. Beckham, Jr., Vice President - Plant Hatch GO-NORMS U. S. NucleALRegulatory Commission Huhington. D. C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U. S. Nuclear Regglalqry_ Commission. Regic1LII Dr. J. N. Grace, Regional Administrator Mr. P. Holmes-Ray, Senior Resident Inspector - Hatch State of Georgia Mr. J. L. Ledbetter, Commissioner - Department of Natural Resources I
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GeorgiaPower A ENCLOSURE 1 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 l OPERATING LICENSES OPR-57, NPF-5 ,
REQUEST TO REVISE TECHNICAL SPECIFICATIONS: t j CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANGE REOUISI Prooosed Change 1_:
In the TS submittal of October 27, 1986 (Reference 1) Georgia Power Company (GPC) proposed changes to the administrative controls in the TS
- and ETS to reflect changes to the company organization. In addition to these organization changes, GPC proposed that iS figures depicting onsite and corporate organization be deleted since they also appear in Section 13 of the Plant Hatch Unit 2 Updated Final Safety Analysis Report (FSAR). The Nuclear Regulatory Commission (NRC) safety evaluation addressing these changes (Reference 2) approved the proposed organization !
changes, however, it did not approve the deletion of the TS organization charts. The staff stated that they were generically examining the requirement for organization charts in TS, and that until a generic 1 decision is reached, the figures must remain in the TS and the ETS.
Since that time, the NRC has issued a generic letter (Reference 3) that allows for the deletion of TS organization charts. The letter states that with certain additions, the administrative TS wvuld capture those
+
) organizational features necessary to assure safe plant operation without '
l the need to maintain the organization charts. The addition to Section ,
j 6.2.0 of the 1S proposed by GPC is consistent with the guidance provided in the generic letter. On this basis, it is proposed that the onsite and i corporate organization charts be deleted from the Units 1 and 2 TS and ETS. Specifically. Units 1 and 2 TS Figures 6.2.1-1 and 6.2.2-1 and ETS 1 Figure 5.2-1 will be deleted.
BASIS i Inclusion of organization charts in the Technical Specifications is not specifically required by regulation. The presence of these charts i requires GPC's processing and the NRC's review of unnecessary license )
amendments for organization changes. Consistent with NRC and industry commitment to improve Technical Specifications, GPC proposes to replace i i
4 0921m El-1 05/06/88 SL-3970 1
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Georgia Powerkh ENCLOSURE 1 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION BASIS FOR CHANG LREQUESI the organization charts with more general organizational requirements.
The proposed change would eliminate a needless expendicure of resources by both GPC and the NRC. Replacement of organization charts with more general requirements was recently endorsed by the NRC in Generic Letter 8 P,-0 6 . The change proposed by GPC is consistent with the guidance provided in the Generic Letter.
ERQ_ POSED CHANGE 2 Change references to the Senior Vice President-Nuclear Operations to the "vice president" in Specifications 6.5.1.6.e, 6.5.1.7.c, 6.5.1.8,
- 6. 5. 2. 2, 6. 5. 2. 3, 6. 5. 2. 8. g . 6. 5. 2. 9, 6. 5. 2.10. a . 6. 5. 2.10. b , 6. 5. 2.10. c ,
- 6. 6.1. b 6.7.1. b and 6.7.1.d. Change references to the Vice President -
Plant Hatch to the "general manager" in Specifications 6.1. 0, 6. 5.1. 6. e .
- 6. 5.1. 7. c , 6. 5.1. 8, 6.6.1.b, 6.7.1.b and 6.7.1.d. Change references to the Senior Executive Vice President to the "vice president" in ETS Section 5.0.
BASIS Consistent with the replacement of the organization charts with more general requirements, GPC proposes to incorporate more general references to the vice president and general manager positions. These revisions would reduce the need for license amendments to reflect title changes while still maintaining the same level of management oversight to activities affecting safety. ,
1 REEEREEIS:
- 1. Letter, J. P. O'Reilly (GPC) to D. Huller (NRC), "Edwin I. Hutch Nuclear Plant Units 1, 2 - Proposed changes to Technical Specifications Rrgarding Corporate and Onsite Organization", October 27, 1986.
- 2. Letter, L. P. : rocker (NRC) to J. P. O'Reilly (GPC), "Issuance of Amendment Nos.145 and 80 to Facility Operating Licenses DF3-57 and NPF Edwin I. Hatch Nuclear Plant, Units 1 and 2", August 10, 1987.
- 3. NRC Generic Letter 88-06, "Removal of Organization Charts from Technical Specification Administrative Control Requirements", issued March 22, 1988.
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Georgia Power d ENCLOSURE 2 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION 10 CFR 50J1EALVAIl0B Proposed Chaqgej :
This proposed change would delete the ccrporate and onsite organization charts (Units 1 and 2 TS Figures 6.2.1-1 and 6.2.2-1 respectively) and the organization structure related to environmental activities (Units 1 and 2 ETS Figure 5.2-1).
BACKGRQUND The content required in the Administrative Controls section of the Technical Specifications is descrioed in 10 CFR 50.36.c(5). This regulation requires that the Technical Specifications contain the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Organization charts are not specifically required, but have generally been included in Technical Specifications as a means of depicting the organizational and management relationships necessary to support safe plant operation. As stated in Generic letter 88-06, the NRC staff has found the organization charts to be of little value in ensuring that the objectives of the Administrative Controls are satisfied. Other Technical Specifications contain specific operational requirements which bear more directly on operational safety.
At Plant Hatch, for example, Administrative Technical Specifica; ions establish the following controls:
- 1. the authority of the plant general manager for overall plant operation,
- 2. the control room command authority of the On-Shift Operations Supervisor,
- 3. control room shif t staffing and operator licensing in accordance with 10 CFR 50.54,
- 4. review and audit by the Plant Review Board and Safety Review Board, and
- 5. procedure, recordkeeping, and reporting requirements. l 1
l l
0921m E2-1 05/06/88 SL-3970 1
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GeorgiaPower A ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CORPORATE AND ONSITE ORGANIZATION 10 CFR 50.92 EVALUATION The staff determined that, with certain additions, the Administrative Technical Specifications would capture those organizational features necessary to assure safe plant operation without the need to maintain the organization charts. Consistent with the guidance provided in the Generic Letter, GPC is proposing to replace the organization charts with the following provisions:
ONSITE AND OFFSITE_0RGANIZATION 6.2.0: Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be estabitshed and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as depropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR.
- b. The general manager shall be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. The vice president shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
0921m E2-2 05/06/88 SL-3970 w3
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GeorgiaPowerkh ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS 10 CFR 50J 2 EVALUATIOff
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions m;y report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
With these additions, the Administrative Technical Specifications would continue to meet the objectives of 10 CFR 50.36.c(5) without the need for organization charts. Detailed descriptions of the onsite and offsite organizations, including organization charts, are presently contained in the Hatch FSAR. This information will be updated regularly in accordance with 10 CFR 50.71(e). The organization charts in the FSAR will be maintained with at least the same level of detail as the charts proposed for removal from the Technical Specifications. Positions requiring a senior reactor operator or reactor operator license are designated in Technical Specification 6.2.2.h, and hence, do not need to be added.
In summary, the Administrative Technical Specifications, as amended, would assure that the organizational features essential to safe plant operation are maintained without the need for prior NRC approval of changes to organization charts.
6MLLSIS GPC has reviewed the proposed change with respect to the requirements of 10 CFR 50.92 and has determined that the change does not involve significant hazards considerations. In support of this conclusion, the following analysis is provided:
- 1. The proposed change will not significantly increase the probability or consequences of an accident previously evaluated. The change is administrative in nature and involves no physical alteration of the plant or changes to setpoints or operating parameters. The change does not af fect operation, maintenance, or testing of the pli.nt. For these reasons, the response of the plant to previously evaluated accidents will remain unchanged, i
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GeorgiaPower A
- ENCLOSURE 2 (Continued)
(
) REQUEST TO REVISE TECHNICAL SPECIFICATIONS l 1 10 CFR 50.92 EVALUATION
! 2. The proposed change does not create the possibility of_ a new or i
) different kind of accident than any accident previously evaluated. Since no change is being made to the design, operation, maintenaace, or testing of the plant, a new mode of -
t failure is not created. A new or different kind of accident could therefore not result.
- 3. The proposed change does not significantly reduce a margin of safety. The general organizational requirements being added to j the Technical Specifications will assure that those '
4 organizational features necessary for safe plant operation will i
' continue to be maintained. Details of the organizational structure will be maintained in the FSAR and updated regularly. i Deletion of the organization charts from the Technical :
Specifications will eliminate the unnecessary expenditure of GPC :
resources currently required to process license amendment requests for organization changes. Margins of safety are i l therefore not reduced.
1 CONCWSION !
4 i
Based on the preceding analysis, GPC has determined that the proposed i change to the Technical Specifications will not sig.iificantly increase j
the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any ;
accident previously evaluated, or involve a significant reduction in a
- i margin of safety. GPC therefore concludes that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve significant 4
hazards considerations. l 3 PROPOSED CHANGL2 4 7 i
Change references to the Senior Vice President-Nuclear Operations to l J
the "vice president" in Specifications 6.5.1.6.e. 6.5.1.7.c, 6.5.1.8 j
- 6. 5. 2. 2, 6. 5. 2. 3, 6. 5. 2. 8. g . 6. 5. 2. 9, 6. 5. 2.10. a . 6. 5. 2.10. b . 6. 5. 2.10. c .
I 6.6.1.b. 6.7.1.b and 6.7.1.d. Change references to the Vice President -
1 Plant Hatch to the "general manager" in Specifications 6.1.0, 6. 5.1. 6. e .
6.5.1.7. c 6. 5.1.8. 6. 6.1.b 6.7.1.b and 6.7.1.d. Change references to
- the Senior Executive Vice President to the "vice president" in ETS j Section 5.0.
)
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1 GeogiaPower d ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS 10 CFR 50.92 EVALUATION BACKGROUE The Administrative Technical Specifications currently contain numerous references to the Senior Vice President - Nuclear Operations, and the Vice President - Plant Hatch. These references assure that ar, appropriate level of management control is exercised over activities affecting operational safety. A change to either of these titles requires a license amendment; however, as in the case of the organization charts, these specific titles could be replaced with more general references and the objectives of the Administrative Technical-Specifications would continue to be met. Changing the above references to "vice president" and "general manager" would assure the same level of management control while eliminatin for unnecessary license amendments when title changes occur.For g the theneed same reason, Section 5.0 of the ETS has been changed to indicate that the "vice president", rather than the Senior Executive Vice President, assumes corporate responsibility for implementation of the ETS.
ANALYSIS GPC has reviewed the above proposed change and has deter. dined that the change does not involve significant hazards considerations. In support of this conclusion, the following analysis is provided:
- 1. The proposed change will not significantly increase '6 h e probability or consequences of an accident previously evaluated. The change is administrative in nature and involves no physical alteration of the plant or changes to setpoints or operating parameters. Since the change has no direct bearing on operation, maintenance, or testing of the plant, the response of the plant to previously evaluated accidents will not be affected.
- 2. The proposed change does not create the possibility of a new or different kind of accident than any accident previously evaluated. Since no change is being made to the design, operation, maintenance, or testing of the plant, a new mode of failure is not created. A new or different kind of accident could therefore not result.
- 3. The proposed change does not significantly reduce a margin of safety. The previous level of mar,agement oversight will be maintained over activities affecting nuclear safety.
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GeorgiaPower d ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS 10 CFR SL92 EVALUATIDH CONCLUSION.
Based on the preceding analysis, GPC has determined that the proposed change to the Technical Specifications will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or significantly reduce a margin of safety. GPC therefore concludes that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve significant hazards considerations.
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! GeorgiaPower A f
- ENCLOSURE 3 !
PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 i d
OPERATING LICENSES DPR-57 NPF-5 ?
REQUEST TO REVISE TECHNICAL SPECIFICATIONS: I
- CORPORATE AND ONSITE ORGANIZATION !
- PAGE CHANGE INSTRUCTIONS i
1
- The proposed changes to the Technical Specifications and Environmental Technical Specifications (Appendices A and B, respectively, to Operating 4
Licenses OPR-57 and NPF-5) would be incorporated as follows:
). UNIT 1
(
) Remove Pagt insert Pagg 1 i 6-1 6-1 !
j 6-la -
! 6-2 6-2 e 1 6-3 6-3 '
j 6-7 6-7 6-8 6-8
, 6-9 6-9 i 6-11 6-11 !
1 6-12 6-12
- 6-13 6-13 i'
! 5-1 (ETS) 5-1 j 5-10 (ETS) -
UNIT 2 l i
q Egmove PagL Insert Pagg 6-1 6-1 6-la -
- 6-2 6-2 1 6-3 6-3 1 6-6 6-6 l' 6-7 6-7 6-8 6-8 4
6-10 6-10 l 6-11 6-11
! 6-12 6-12
- 51 (ETS) 5-1 J 5-10 (ETS) -
1
)
j WM