Letter Sequence Request |
---|
|
|
MONTHYEARML20108E8031985-03-0404 March 1985 Notifies of Organizational Changes.Position of Senior Vice President - Nuclear Power Created.Application for Amend to Licenses DPR-57 & NPF-5 Will Be Submitted in Near Future Project stage: Request ML20136E7581985-12-23023 December 1985 Informs of Listed Organizational Changes.Request for Amend to Tech Specs to Reflect Changes Will Be Submitted in Near Future Project stage: Request ML20153E9071986-02-17017 February 1986 Proposed Tech Spec Changes,Modifying Offsite Organization & Responsibilities of Plant Review Board,Reflecting Addition of Primary Meteorological Tower & Clarifying Retention Period for QA Documents Project stage: Other ML20153E8991986-02-17017 February 1986 Application for Amends to Licenses DPR-57 & NPF-5,modifying Offsite Organization & Responsibilities of Plant Review Board,Adding Primary Meteorological Tower & Clarifying QA Documents Retention Period.Fee Paid Project stage: Request ML20198D9731986-05-16016 May 1986 Proposed Tech Specs,Revising Administration of Plant & Safety Review Boards Project stage: Other ML20198D9611986-05-16016 May 1986 Application for Amend to Licenses DPR-57 & NPF-5,revising Tech Specs to Change Administrative Controls Covering Organization & Responsibilities of Plant & Safety Review Boards.Fee Paid Project stage: Request ML20214P0681986-08-25025 August 1986 Proposed Tech Spec,Changing Section 6.6.1.b to Read: Each Reportable Occurrence Requiring Notification.. Project stage: Other ML20214P0261986-08-27027 August 1986 Application for Amends to Licenses DPR-57 & NPF-5,revising Tech Spec Section 6.6.1.b to Read: Each Reportable Occurrence Requiring Notification.. Project stage: Request ML20210N5321986-09-29029 September 1986 Forwards Request for Addl Info Clarifying 860516 Request to Revise Tech Specs Re Administration of Safety Review & Plant Review Boards.Info Should Be Provided as Rev or Suppl to Proposed Tech Spec Change,Within 60 Days Project stage: RAI ML20213D5431986-10-27027 October 1986 Proposed Tech Specs,Revising Section 6.0 Re Adminstrative Controls & ETS Section 5 to Reflect Recent Changes in Company Organization Project stage: Other ML20213D5161986-10-27027 October 1986 Application for Amends to Licenses DPR-57 & NPF-5,revising Administrative Controls Section 6.0 & ETS Section 5 to Reflect Recent Changes in Company Organization.Fee Paid Project stage: Request ML20214T0931986-11-24024 November 1986 Revised Proposed Tech Spec 6.5.1.2,Pages 6-6 for Unit 1 & Page 6-5 for Unit 2,adding Addl Requirement for Two Persons to Be at Least Dept Managers Project stage: Other ML20214S7631986-11-24024 November 1986 Resubmits Tech Spec Pages Re Administration of Plant Review Board & Safety Review Board,Per NRC 860929 Request.Pages Revised to Add Addl Restriction Requiring Two Persons to Be at Least Dept Managers Project stage: Other 1986-02-17
[Table View] |
Similar Documents at Hatch |
---|
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
Georg'a Pewer Company 333 Piedmont Avenue Atianta. Georg a 30308 Telerbene 404 526-7020 _
Masng Adcess Post Off ce Sox 4545 Atianta.Georg a 30302 b Georgia Power J. T. Beckham, Jr, t% supern e -nectnc system V ce Presideat and Geners: Manager Nuctear Ocerat.ons SL-204 251C February 17, 1986 Director of Nuclear Reactor Regulation Attention: 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 ADMINISTRATIVE CHANGES Gentlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59( c)(1), Georgia Power Company hereby proposes changes to the Technical Specifications, Appendices A and B to Operating Licenses DPR-57 and NPF-5 The proposed changes are an amendment to, and in addition to, those described in our letters of November 21,1984, March 4,1985, March 22,1985, and December 23, 1985 The proposed changes would: modify the offsite organization, modify the responsibilities of the Plant Review Board, show the addition of a new primary meteorological tower, clarify the retention period for certain Quality Assurance documents, and delete reference to the Environmental Program Description Document.
Attachment 1 provides a detailed description of the proposed changes and circumstances necessitating the change request.
Attachment 2 details the basis for our determination that the proposed changes do not constitute and unreviewed safety question.
Attachment 3 details the basis for our determination that the proposed changes do not involve significant hazards considerations.
Attachment 4 provides page change instructions for incorporating the proposed changes. The proposed changed Technical Specification pages follow Attachment 4.
The required app 1tcation fee is attached.
w Q.
00 d ffV$Y
( 8602250195 860217 PDR P
ADOCK 05000321 el l' PDR
GeorgiaPower d j Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 February 17, 1986 Page Two In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, 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 issuance of the amendment.
Pursuant to the requirements of 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
J. T. Beckham, Jr. states that he is 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.
GEORGIA POWER COMPANY By: h --
--- ,c-y J. T. Beckham, Jr.
Sworn to and subscribed before me this 17th day of February,1986
~/~
- I Notary Public gg7p.m oth. C nn coumy, c. wm m
Enclosure c: Mr. H. C. Nix, Jr.
Senior Resident Inspector Dr. J. N. Grace, (NRC-Region II)
Mr. J. L. Ledbetter GO-NORMS l
! i 700775 L _- 1
-- .-- .~ . .
GeorgiaPower1 ATTACHMENT 1 NRC DOCKETS 50-321, 50-366-OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 ADMINISTRATIVE CHANGES Basis for Change The proposed changes are an amendment to, and in addition to, those- described in our letters of November 21, 1984, March 4, 1985, March 22, 1985, and December 23, 1985. . The following proposed changes have been.made to Section 6.1 and Figure 6.2.1-1 of Appendix A' Technical Specifications and Figure .
5.2-1 of Appendix 'B' Environmental Technical Specifications as appropriate as well as the applicable parts of Section 5 of Appendix 'B' as shown in the pages of Attachment 4. The proposed changes reflect a significant increase in staffing of the corporate Nuclear Operations organization. In the overview,
, the organizational changes have been made to create a more effective
- management structure. ,
i The organization is being enhanced by the addition of the title and position of Senior Vice President Nuclear Operations. The Senior Vice President Nuclear Power has been reassigned to have total control of the Plant Vogtle construction. The Senior Y'M President Nuclear Operations has assumed all of the functions for Plant Hatch formerly assigned to the Senior Vice President Nuclear Power.
4 The responsibility for the Radiological Environmental Monitoring Program, as currently described in the Technical Specifications, is divided among the General Manager - Plant Hatch, the Manager of Nuclear Engineering and Chief Nuclear Engineer and the Manager of Environmental Affairs. The proposed amendment would change the title of the Manager of Nuclear Chemistry and Health Physics to Manager of Radiological Safety, and would indicate his responsibility for the Radiological Environmental: Monitoring Program and
' management oversite of the Health Physics Program. The proposed amendment would concurrently eliminate the Manager Nuclear Engineering and Chief Nuclear Engineer's responsibility for elements of the Program. The title of Manager Nuclear Engineering and Chief Nuclear Engineer Environmental -Monitoring has been changed to Manager Nuclear Safety and Licensing. The position ,
reports to the Senior Vice President Nuclear Operations.
The proposed' amendment would recognize the change of title and respor.sibilities of the General Manager Quality Assurance and Radiological -
Health and Safety to General Manager- Quality Assurance. Concurrent with the change in title for the General Manager Quality Assurance, the Manager of Radiological Safety has assumed ; responsibilities similar to~ the Radiological-Health and Safety Representative. Therefore, the position of ' Radiological .
Health and Safety Representative has been removed from the ' organizational '
chart. Clarifying our statements in the - December 23, 1985, submittal, the title and . position of Deputy General Manager - Quality Assurance ' remains within - the Quality Assurance Department; however, the - position is currently vacant. When the position is filled, we will submit an additional amendment l
to show the Deputy General Manager - Quality Assurance. !
4 700775
- _-. - - . _ . - . . - . . _ _ . . . . _ - . - - - . - _ _ - . . . , _ . . . - - . , - - ..~, , ,, . . . . _ . . . - .
Georgia Power A ATTACHMENT 1 (Continued)
The amendment would also remove the position of Vice President and Chief ,
Engineer Power Supply Engineering and Services from the Engineering and l Construction Services Department organization due to retirement and j reorganization. The title of Hatch Project Manager has been changed to ,
the Engineering Manager Nuclear Projects and the position moved from Department to the Nuclear Operations Department. Concurrent with the move of the Manager Nuclear Projects, the title of Manager Engineering Services is being removed from the organizational charts.
The position of Manager Nuclear Training now reports to the Senior Vice President Nuclear Operations. The position of Manager Nuclear Generation, which has been vacant, is being removed from the organizational charts. The designation of " corporate responsibility for fire protection" is being removed from the Technical Specifications organizational charts. This designation, while required by Appendix R of 10 CFR 50 for the Fire Plan, is not required for Technical Specifications.
In addition to the above changes, there are nine positions which- are being added to the offsite organization chart. These are: Manager Nuclear Support, Manager Nuclear Performance, Manager Engineering Liaison, Manager Maintenance j and Modification, Nuclear Safety Reviews Manager, Nuclear Safety Manager, '
Nuclear Licensing Manager - Hatch, Nuclear Licensing Manager - Vogtle, and Gener al Manager Plant Vogtle. The Manager Nuclear Support is responsible for !
administration of purchasing contracts for the department, human resource l planning, records management, control of budgets for the nuclear plants, monitoring of the plants' security and industrial safety programs. The Manager Nuclear Performance is responsible for establishment of the Independent Safety Engineering Groups for the plants, review of audit findings, review of industry publications for items applicable to Georgia Power Company nuclear plants and trend analysis of plant operation. The Manager Engineering Liaison is responsible for control of the design interface between organizations performing engineering work for the plants, provide interpretation of engineering codes and standards and review of vendor information. The Manager Maintenance and Modification is responsible for monitoring plant modification status, development of critical path schedules for outages, monitoring the effectiveness of maintenance programs, and negotiations for outage services. The Nuclear Safety Reviews Manager is responsible for maintaining the Safety Review Board charter, procedures and files, and ensuring communication between the Safety Review Board and the Independent Safety Engineering Groups for the respective plants. The Nuclear Safety Manager is responsible for review of audit findings, review of industry publications for items applicable to Georgia Power Company nuclear plants, independent analysis of unusual occurrences at the plants, and responses to generic nuclear issues. The Nuclear Licensing Manager - Hatch and the Nuclear Licensing Manager - Vogtle have similar duties for their respective plants.
These are to communicate Company positions to the NRC, to follow regulatory commitments, to respond to NRC requests for information, and to be the single point of contact between NRR licensing personnel and the Company. The General Manager Plant Vogtle is responsible for the Nuclear Operations of Plant Vogtle.
2 700775
l Georgia Pbwer d ATTACHMENT 1 (Continued)
Additionally, the change would amend the responsibilities of the Plant Review Board to limit review of Technical Specification violations to those which have been determined to be reportable. Another change to the. PRB responsibilities would expand review of event for written notifications to the Comission required by Technical Specifications and/or 10 CFR 50.73. It would also change one of the members of the PRB from the Superintendent of Maintenance to the Superintendent of Instrument and Controls.
This change would also change the referenced figure in Section 5 of Unit 2 l Appendix A' Technical Specifications for the exclusion area, low population. '
zone, and site boundary. The new figure also shows the location of the primary and backup meteorological towers. The newly referenced figure was .
submitted as part of the Radiological Effluent Technical Specifications in l Section 3/4 The amendment would remove the current figure from Section 5 to :
eliminate any redundancy or confusion. There is no change to the physical l boundaries of the site boundary, exclusion area, or low population zone. A recreational area has been added within the site boundary for the use of Plant Hatch employees and their guests.
Additionally, the change would clarify the record retention period for certain Quality Assurance documents. This change is accomolished by inserting additional wording into Specification 6.10.2.1. The proposed change was initiated by discussions with the Hatch Licensing Project Manager at Nuclear Reactor Regulation. This change is intended to reduce potential confusion as to the retention requirements. There is no change to the Quality Assurance Program.
The proposed change would also eliminate reference to the Environmental Program Description Document (EPDD) from Appendix 'B' Technical Specifications. The Fnvironmental Program as described by the EPDD is now complete. Therefore, any reference remaining to it in the Technical Specifications is obsolete and confusing. There has been significant l renumbering of Environmental Technical Specifications to accommodate the l changes made to the Administrative Section as a result of deletion of the EPDD.
3 1
l l
700775
l
.)
! GeorgiaPower A ATTACHMENT 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 ADMINISTRATIVE CHANGES 10 CFR 50.59 Evaluation f
The Plant Review Board and Safety Review Board have . reviewed the proposed changes and have determined that they do not constitute an unreviewed safety I question. These changes do not increase the. probability or consequences of accidents or malfunctions of equipment previously analyzed since the amendment involves only administrative changes with no decrease in programmatic controls. The only equipment or design modification involved with . these changes is the addition of a new primary meteorological tower; The old tower remains in place as an installed, operational backup to the new tower.
Consequently, these changes do not create new modes of operation, a potential for new accidents, or a change in' the margin of safety as described in the Technical Specifications.
i j
700775
, , , .. - ...,r-. .- , . - -, ,,. ,, - . , , . . - , - . . . . - , . .
GeorgiaPowerb AT M HMENT 3 NRC DOCKETS 50-321 ~, 50-366 l OPERATING LICENSES DPR-57; NPF-5 1
EDWIN I. HATCH NUCLEAR-PLANT UNITS 1, 2 :l ADMINISTRATIVE CHANGES 10 CFR 50.92 Evaluation Change 1: The org'anization is being enhanced by the addition for the title and position of Senior Vice President Nuclear Operations.
l' The proposed change constitutes: an administrative change in that it changes the. personnel and title . of the responsible person without changing the responsibilities. Therefore, the results of the 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 April 4 6,1983, issue of the Federal Register.
l This change does not - cause a significant increase in the. probability or
' consequences of accidents or malfunctions ~ of equipment previously analyzed -
since the amendmenQnvolves only administrative changes with no decrease in programmatic controR. -Consequently,.this change does not create new modes of operation, a potential for new accidents; or a change in the margin of safety
, as described in the Technical Specifications.
1 Change 2: The proposed amendment would change the title of the Manager of Nuclear Chemistry and Health Physics to Manager. of . Radiological Sa fety. It would indicate his responsibility for the.
Radiological Environmental Monitoring Program and. management-oversite of the Health Physics Program. The Manager- of-
! Radiological Safety has assumed responsibilities similar' to the Radiological Health and Safety- Representative. Therefore, the l position of Radiological Health and . Safety Representative has been removed from the organizational chart.
i The proposed change constitutes: an administrative change in that 'it changes the title and responsibilities of an existing position. Therefore, tr.c -
results of the change is consistent with Item (i) of the " Examples of 4
Amendments that are Coasidered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the 3
Federal Register.
This change does not. cause a significant increase -in the probability or' consequences of . accidents or malfunctions of equipment previously analyzed
' since the amendment involves only administrative changes with no decrease -in programmatic controls. Consequently, this change does not create new modes of operation, a potential for new ' accidents, or a change in the margin of safety as described in the Technical Specifications._ i i
a 4
a
! 700775
,. .. _ . . , ,_-.,a,... . . . , - . ,,,.,_.-..u...-,,..._, . _ - ~ _ . , _ , . . . . _ , _ - , . . . , - . . . - _ _ - . , - - - , _ _ . . , . . , _ . .
~
l I
ATTACHMENT 3 Geo$i aPower1 (Continued) i Change 3: The proposed amendment would eliminate any responsibility for the Environnental Monitoring Program for the Manager Nuclear :
Engineering and Chief Nuclear Engineer. The title of Manager Nuclear Engineering and Chief Nuclear Engineer has been changed to Manager Nuclear Safety and Licensing. The position ' reports to the Senior Vice President Nuclear Operations.
The proposed change constitutes: an administrative change in that it changes- i the title and responsibilities of an existing position. Therefore, the results of the 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 April 6, 1983, issue of the Federal Register.
This change does not cause a significant increase in the probability or consequences of accidents or malfunctions of equipment previously analyzed '
since the amendment involves only administrative char.ges .with no decrease in l programmatic controls. Consequently, this change does not create new modes of I operation, a potential for new accidents, or a change in the' margin of safety as described in the Technical Specifications.
Change 4: The proposed amendment would recognize the change of title and responsibilities of the General Manager Quality Assurance and
. Radiological Health and Safety to General Manager Quality Assurance.
The proposed change constitutes: an administrative change in that it changes the title, responsibilities, and personnel of an Therefore, the results of the change is consistent withexisting Item (i) position.
of the
" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.
This change does not cause a significant_ increase in the probability or consequences of accidents or malfunctions of equipment previously analyzed since the amendment involves only administrative changes with no decrease in programmatic controls. Consequently, this change does not create new modes of operation, a potential for new accidents, or a change in the margin of safety as described in the Technical Specifications.
Change 5: The amendment would also remove the position of Vice President and Chief Engineer Power Supply Engineering and Services which has been deleted from the Engineering and Construction Services Department due to retirement and reorganization.
The proposed change constitutes: an administrative change in that it removes an existing position. Therefore, the results of the 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 April 6,1983, issue of the Federal Register. '
2
--- I
N i GeorgiaPower1 ATTACHMENT 3 (Continued) e
~
- This change does not cause a significant increase in the probability or i
- consequences 'of accidents or malfunctions of equipment previously analyzed .
since the amendment involves only administrative changes with no decrease. in prograsunatic controls. Consequently, this change does not create:new modes of operation, a potential for new accidents,' or a change in the margin of safety - -
4 as described in the Technical Specifications.
Change 6: The title of Hatch Project Manager has been changed to Manager
., Nuclear. Projects .and . the position moved from the Engineering Department to- the Nuclear Operations Department. Concurrent with the move of the Manager Project Engineering, the title of Manager Engineering Services is being removed from .the organizational charts.
The proposed change constitutes: an administrative change in that it changes-the title and relative position of an existing position and removes another position. Therefore, the results of the change is consistent with Item (i) of 1 the " Examples of Amendments that are Considered Not Likely to Involve
, Significant Hazards Considerations" listed on page 14,870 of the . April 6, 1983, issue of the Federal Register.
This change does not cause a significant increase in the probability or consequences of accidents or malfunctions of . equipment previously analyzed
^
since the amendment involves only administrative changes with no ' decrease in programmatic controls. Consequently, this change does not_ create new modes of operation, a potential for new accidents, or a change in the margin of safety as described in the Technical Specifications.
. Change 7: The position of Manager Nuclear Training reports to the Senior Vice President Nuclear Operations.
The proposed change constitutes: an administrative change in that it changes the relative position of an existing position.- Therefore, the results of the 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 April 6,1983, issue of the Federal Register.
This change does not cause a significant increase in the probability or
- consequences of accidents or malfunctions of equipment previously analyzed
~; since the amendment involves only administrative changes with no decrease in programmatic controls. Consequently, this' change does not create new modes of
' operation, a potential for new accidents, or a change in the. margin of safety as described in the Technical Specifications.
3 l
700ns
, , . _ . . , , . _ - . . . - . . . _ , .._,m ..__,...,_..-_____.-.__..,.___.._..m.. . - . . . , , . . . - - . , . - ,
e"'
- GeorgiaPower1 AnACHMENT 3
- (Continued)
Change 8: The position of Manager Nuclear. Generation, which_ has been 1
- . vacant, is being removed from the organizational charts. l
- The proposed change constitutes
- an administrative change in that it removes _
from the charts a vacant position. Therefore, the results of the change is :
consistent with Item (i) of the " Examples of Amendments' that -are Considered I
- Not Likely to Involve Significant Hazards Considerations" . listed .on page
- 14,870 of the April 6,1983, issue of the Federal Register. ,
i This change does not cause a significant increase in the probability or i consequences of accidents or malfunctions of equipment previously analyzed j since the amendment involves only administrative changes with no decrease in l l programmatic controls. Consequently, this change does not create new modes of operation, a potential for new accidents, or a change in the margin of safety l as-described in the Technical Specifications.
I Change 9: The designation of " corporate responsibility for fire protection is being removed from the organizational charts.
, The proposed change constitutes: an administrative change in that it removes
! an adninistrative designation. Therefore, the results of the change is consistent with Item (i) of the " Examples of Amendments that are Considered 3 Not Likely to Involve Significant Hazards Considerations" listed on page i 14,870 of the April 6,1983, issue of the Federal Register.
! This change does not cause a significant increase in the probability or :
- consequences of accidents or malfunctions of equipment previously analyzed '
i since the amendment involves only administrative changes.with no decrease in
, progranaatic controls. Consequently, this change does not create new modes of 3 operation, a pctential for new accidents, or a change in the margin of safety as described in the Technical Specifications.
4 Change 10: There are nine positions which are being added to the offsite U organization chart in Appendix 'A' Technical Specifications.
These are: Manager Nuclear Support, Manager Nuclear. Performance, 4
Manager Engineering Liaison, Manager Maintenance and Modification, Nuclear Safety Reviews Manager, Nuclear Safety l Manager, Nuclear Licensing Manager - Hatch, Nuclear Licensing Manager - Vogtle, and General Manager Plant Vogtle.
1 The proposed change constitutes: an administrative change in that it increases
, the detail given in the organization chart. Therefore, the results of the -
j change is consistent with Item (i) ' of the " Examples of Amendments that are
~
Considered Not Likely to Involve Significant Hazards Considerations" listed on 3
page 14,870 of the April 6,1983, issue of the Federal Register.
This change does not cause a significant increase .in the probability or consegaces of accidents or malfunctions of ' equipment previously analyzed L since the amendment involves only- administrative . changes with .no decrease in i
I programmatic controls. Consequently, this change does not create new modes of operation, a potential for new accidents, or a change in the margin of safety l n described in the Technical Specifications.
.4
.700775
. . - ~ - .- . - . - -- - . . - . -. ...-
F W
- Georgia Poker ATTACHMENT 3' p (Continued)
! Change 11: Additionally, the change would amend the responsibilities of the Plant Review Board ' to limit Technical Specification Violations to those which have been determined to be reportable.
4 i
The proposed change constitutes: an administrative change in that it clarifies the responsibilities of the Plant Review Board. Therefore, the results of the change is consistent with Item (i) of the " Examples of Amenhents that are
- Considered Not Likely to Involve Significant Hazards Considerations" listed on j page 14,870 of the April 6,1983, issue of the Federal Register.
This change does not cause a significant increase in the probability or !
- consequences of accidents or malfunctions of equipment previously ' analyzed l i since the amendnent involves only administrative changes with no decrease in I i progrannatic controls. Consequently, this change does not create new modes of l
i operation, a potential for new accidents, or a change in the margin of safety 1 i as described in the Technical Specifications.
1
~
Change 12: This change would also change the referenced figure in Section 5 l of Unit 2 Appendix 'A' Technical Specifications for the :
exclusion area, low population zone, and site boundary to the figure submitted as part of the- Radiological Effluent Technical i
Specifications in Section 3/4 There is no change to the physical boundaries of the site boundary, exclusion area, or low
- population zone.' There has been the addition of a recreational i area within the site boundary for the use of Plant Hatch j employees and their guests.
The proposed change constitutes: an administrative change in that it changes the location of a referenced drawing within Technical Specifications and increases the information on that drawing. Therefore, the results of the change is consistent with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on l page 14,870 of the April 6,1983, issue of the Federal Register, ,
j 4
This change does not cause a significant increase in the probability or
' consequences of accidents or malfunctions of equipment previously analyzed since the amendment involves an increase in the equipment available to-assess
- an accident by the addition of a new primary meteorological tower and retention of the old as an installed backup. Consequently, this change does not create new modes of operation,'a potential for new accidents, or a change in the margin of safety as described in the Technical Specifications.
- Change 13: Additionally, the change would clarify the record retention i period for certain Quality Assurance documents. This change is -
i accomplished by inserting additional wording into Specification 6.10.2.1. There is no change to the Quality Assurance Program.
The proposed change constitutes: an administrative change in that it clarifies i the retention requirements for certain records. Therefore, the results of the change is consistent with Item (i) of the " Examples of Amendnents that are
~
L Considered Not Likely to Involve Significant Hazards Considerations" listed on
~
- page 14,870 of the April 6,1983, issue of the Federal Register.
! 5 L
! 700775
-. ,,.m~-. - . - , - ....,a-., - _ _ u -._ -.._ _ _ . . . - ~ . _ _ _ . , . - - _ - - . - _ , _ _ _ _ , - - . . _ - - . -
r l
I A CHMENT 3 GeorgiaPower f (Continued) i
- This change does not cause a .significant increase in the probability or r consequences .of accidents or malfunctions of. equipment . previously ' analyzed since the amendment -involves only. administrative changes with no decrease in
, programmatic controls.' consequently, this change does not create new modes of operation,' a potential for new accidents, or a change in the margin of safety
! as described in the Technical Specifications.-
Change 14: Another change to the PRB responsibilities would expand review 4
of event for written notifications to the Commission to those i required by Technical Specifications and/or 10 CFR 50.73 The proposed change constitutes: an administrative change in that it increases
( the responsibilities of the Plant Review Board. Therefore, the results of the ' '
~
change is consistent with Item (ii) of the " Examples of Arendments that .are Considered Not Likely to Involve Significant Hazards Considerations" listed on ,
page 14,870 of the April 6,1983, issue of the Federal Register. ,
! This change does not cause a significant -increase in the probability or :
- consequences of accidents or malfunctions of equipment previously analyzed ,
- since the amendment involves only administrative changes 'with an increase in '
- programmatic controls. Consequently, this change does not create new modes of
- operation, a potential for new accidents, or a change in the margin of safety j as described in the Technical Specifications.
i Change 15: One of the members of the Plant Review Board is being changed.
The proposed change constitutes: an administrative change in that it changes ;
j the responsibilities of an existing position. Therefore, the results of the '
change is consistent with Item (i) of the " Examples of Amendments that are
, Considered Not Likely to Involve Significant Hazards Considerations" listed on j
4 page 14,870 of the April 6,1983, issue of the Federal Register. '
l This change does not cause a significant increase in the probability or consequences of accidents or malfunctions _of equipment previously analyzed
! since the amendment involves only administrative changes with no decrease in i programmatic controls. Consequently, this change does not create new modes of
} operation, a potential for new accidents, or a change in the margin of safety l as described in the Technical Specifications.
i
! Change 16: The proposed change would also- eliminate reference to the !
1- Environmental Program Description - Document. The Environmental Program as described by the document is now complete.
! The proposed change constitutes: relief granted upon demonstration of
- acceptable operation in that since the Environmental Program described by the i
EPDD has been completed, reference to that document should be deleted.
1 Therefore, the results of the change is consistent .with Item (iv) of ' the ;
i " Examples of Amendments that are Considered Not Likely to Involve Significant ;
i Hazards Considerations" listed on page 14,870 of the April '6,1983, issue of l 4
the Federal Register.
} 6 m,,,
. . ~. _ . - - . . -~. .. - -. . , - _ _ _ _ - _
ATTACHMENT 3 -
Geo3i aPower d (Continued)
This . change does not cause a significant increase- in _the probability or consequences of - accidents or malfunctions of equipment previously analyzed since .the amendment. involves only administrative changes with no decrease in progransnatic controls. Consequently, this change does not create new modes of operation, a potential for new accidents, or a change .in the margin of safety I as described in the Technical Specifications.
j Change 17: The proposed change would alter the approval requirements
, for temporary procedures under the Environmental Technical l Specifications (ETS).
The proposed change constitutes: clarification 'of the time limit for plant management approval and imposition of. the same SRO approval ' requirement for ETS as currently exists in Appendix 'A' Technical Specifications. Therefore, the results of the 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 April 6, 1983, issue of the
- j. Federal Register.
4 This change does not cause a significant increase in the probability or consequences of accidents or malfunctions of equipment previously analyzed !
since the amendnent involves only administrative changes with no decrease in
{
programmatic controls. Consequently,- this change does not create new modcs of ;
operation, a potential for new accidents, or a change in the margin of safety as described in the Technical Specifications.
1 i
l 7 4
4 l
4 l
4 7WT75 -
_ _ . . _ . . _ _ _ _ , . . - . , . . . - , , - , . _ , . , _ . - . , . . . . . , _ , , _ . . . , . . . . , , , , - - . , . , , . , , . . . . . - ~ _ . . _ , . . . _ _ ~ _ _
4 GeorgiaPowerI ATTACHMENT 4' NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I HATCH NUCLEAR PLANT UNITS 1, 2 ADMINISTRATIVE CHANGES 4
The proposed change to the Technical Specifications (Appendices A and B to the Operating Licenses) would be incorporated as follows:
Remove Page Insert Page Unit 1 6-1 6-1 6-2 6-2 6-6 6-6
, 6-7 6-7 6-8 6-8 l 6-12 6-12
- 6-13 6-13 6-13a 6-13a
. Unit 2 5-1 5-1 1
5-2 5-2 5-3 5-3 6-1 6-1 6-2
- 6-2 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-i i 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 !
i 5-5 5-5
) i 5-6 5-6 5-7 5-7 5-9 5-9
. 5-10 5-10 70077$
- - . _ . _ . _ _ . _ . _ .- ..._ __ .. . ~ . . , _ - . . , - . . . - _ . .