Application to Amend Licenses DPR-57 & NPF-5,in Response to Generic Ltr 84-15, Proposed Staff Actions to Improve & Maintain Diesel Generator Reliability. Amend Revises Tech Specs Re Limiting Conditions for Operation.Fee PaidML20099E164 |
Person / Time |
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Site: |
Hatch |
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Issue date: |
11/07/1984 |
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From: |
Conway R GEORGIA POWER CO. |
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To: |
Stolz J Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20099E167 |
List: |
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References |
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GL-84-15, NED-84-085, NED-84-85, TAC-55865, TAC-558655, TAC-55866, TAC-56522, TAC-56523, NUDOCS 8411210140 |
Download: ML20099E164 (14) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARHL-5770, Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons1999-10-0101 October 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons HL-5811, Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys1999-07-29029 July 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC1999-02-0505 February 1999 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC HL-5694, Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors1999-01-21021 January 1999 Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.21998-12-0404 December 1998 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2 HL-5658, Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors1998-07-22022 July 1998 Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors HL-5400, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect1997-12-18018 December 1997 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect HL-5413, Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl1997-08-0808 August 1997 Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl HL-5362, Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys1997-05-0909 May 1997 Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys HL-5368, Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4)1997-05-0909 May 1997 Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4) ML20138H4021997-04-29029 April 1997 Application for Amend to License DPR-57,revising TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5345, Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-14014 April 1997 Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done1997-01-0707 January 1997 Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done HL-5270, Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 141996-12-0303 December 1996 Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 14 HL-5054, Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware1996-10-29029 October 1996 Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV1996-10-0707 October 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves1996-09-19019 September 1996 Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves HL-5163, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel1996-05-21021 May 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F1996-02-21021 February 1996 Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B1995-11-10010 November 1995 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B HL-4861, Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria1995-06-0606 June 1995 Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria HL-4816, Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events1995-05-0404 May 1995 Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS1995-04-14014 April 1995 Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS HL-4724, Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 21995-01-13013 January 1995 Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 2 HL-4723, Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes1994-12-0202 December 1994 Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes ML20078G7051994-11-0101 November 1994 Application for Amends to Licenses DPR-57 & NPF-5,converting TS to Improved TS Consistent w/NUREG-1433 HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained1994-10-13013 October 1994 Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained HL-4695, Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions1994-09-20020 September 1994 Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions HL-4648, Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys1994-08-16016 August 1994 Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys HL-4661, Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-14331994-08-0808 August 1994 Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-1433 ML20072B7441994-08-0404 August 1994 Application for Amend to License NPF-5,revising TSs for Traversing Incore Probe Operability Requirements HL-4651, Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable1994-07-19019 July 1994 Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable HL-4620, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 14331994-07-0808 July 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 1433 HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt1994-06-0707 June 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/41994-02-25025 February 1994 Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4 HL-3433, Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions1993-11-0909 November 1993 Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions HL-3416, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips1993-10-19019 October 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips ML20045E7261993-06-28028 June 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 3.7.A.4 & 3.6.4.1,respectively,to Allow One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing ML20044D0771993-05-0303 May 1993 Suppl to 920921 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Administrative Controls Section Re Semiannual Radioactive Effluent Release Rept to Reflect New 10CFR50.36a,per GL 89-01 HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F0231992-12-21021 December 1992 Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023 HL-2962, Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-161992-11-10010 November 1992 Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-16 HL-2006, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure..1992-10-19019 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure.. HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-011992-10-14014 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 HL-2390, Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-011992-09-21021 September 1992 Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-01 ML20118A5761992-09-18018 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,allowing Southern Nuclear Operating Co,Inc to Possess,Manage,Use, Operate & Maintain Facilities.Certificate of Concurrence from Southern Nuclear Operating Co,Inc Encl HL-2335, Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level1992-09-0202 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level HL-2355, Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error1992-07-30030 July 1992 Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error HL-2231, Application for Amends to Licenses DPR-57 & NPF-5,proposing to Revise Several Portions of TS Involving Shutdown & Refueling Operations1992-07-17017 July 1992 Application for Amends to Licenses DPR-57 & NPF-5,proposing to Revise Several Portions of TS Involving Shutdown & Refueling Operations HL-2225, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs to Add Addl Electrical Sys Requirements,Per Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers....'1992-07-17017 July 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs to Add Addl Electrical Sys Requirements,Per Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers....' HL-1946, Application for Amends to Licenses DPR-57 & NPF-5,changing Snubber Functional Test Insp Interval to 18 Months,Per Generic Ltr 90-091992-02-20020 February 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing Snubber Functional Test Insp Interval to 18 Months,Per Generic Ltr 90-09 1999-07-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARHL-5770, Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons1999-10-0101 October 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons HL-5811, Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys1999-07-29029 July 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC1999-02-0505 February 1999 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC HL-5694, Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors1999-01-21021 January 1999 Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.21998-12-0404 December 1998 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2 HL-5658, Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors1998-07-22022 July 1998 Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors HL-5400, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect1997-12-18018 December 1997 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J9351997-10-0606 October 1997 Corrected TS Pps to Amends 208 & 150 for Licenses DPR-57 & NPF-5,respectively,consisting of Pps 3.4-8 & 3.5-6 for Unit 1 & Pps 3.4-8 & 3.5-5 for Unit 2 to Reflect Revised SRV Setpoints HL-5413, Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl1997-08-0808 August 1997 Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl HL-5368, Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4)1997-05-0909 May 1997 Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4) HL-5362, Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys1997-05-0909 May 1997 Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys ML20138H4021997-04-29029 April 1997 Application for Amend to License DPR-57,revising TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5345, Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-14014 April 1997 Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20137N1751997-04-0404 April 1997 Amends 206 & 147 to Licenses DPR-57 & NPF-5,respectively, Revising Surveillance Requirements Addressing Reactor Vessel Pressure & Temperature HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done1997-01-0707 January 1997 Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done HL-5270, Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 141996-12-0303 December 1996 Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 14 HL-5054, Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware1996-10-29029 October 1996 Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV1996-10-0707 October 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves1996-09-19019 September 1996 Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves HL-5163, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel1996-05-21021 May 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F1996-02-21021 February 1996 Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B1995-11-10010 November 1995 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B HL-4861, Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria1995-06-0606 June 1995 Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria HL-4816, Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events1995-05-0404 May 1995 Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS1995-04-14014 April 1995 Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS HL-4724, Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 21995-01-13013 January 1995 Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 2 HL-4723, Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes1994-12-0202 December 1994 Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes ML20078G7051994-11-0101 November 1994 Application for Amends to Licenses DPR-57 & NPF-5,converting TS to Improved TS Consistent w/NUREG-1433 HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained1994-10-13013 October 1994 Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained HL-4695, Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions1994-09-20020 September 1994 Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions HL-4648, Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys1994-08-16016 August 1994 Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys HL-4661, Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-14331994-08-0808 August 1994 Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-1433 ML20072B7441994-08-0404 August 1994 Application for Amend to License NPF-5,revising TSs for Traversing Incore Probe Operability Requirements HL-4651, Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable1994-07-19019 July 1994 Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable HL-4620, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 14331994-07-0808 July 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 1433 HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt1994-06-0707 June 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/41994-02-25025 February 1994 Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4 HL-3433, Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions1993-11-0909 November 1993 Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20059E6831993-10-21021 October 1993 Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively, Relocating Procedural Details Contained in Radiological Effluent Ts,Incorporating New Part 20 & Revising Frequency of Reporting Radiological Effluent Releases HL-3416, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips1993-10-19019 October 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips ML20045E7261993-06-28028 June 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 3.7.A.4 & 3.6.4.1,respectively,to Allow One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing ML20044D0771993-05-0303 May 1993 Suppl to 920921 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Administrative Controls Section Re Semiannual Radioactive Effluent Release Rept to Reflect New 10CFR50.36a,per GL 89-01 HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F0231992-12-21021 December 1992 Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023 HL-2962, Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-161992-11-10010 November 1992 Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-16 HL-2006, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure..1992-10-19019 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure.. HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-011992-10-14014 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 HL-2390, Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-011992-09-21021 September 1992 Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-01 ML20118A5761992-09-18018 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,allowing Southern Nuclear Operating Co,Inc to Possess,Manage,Use, Operate & Maintain Facilities.Certificate of Concurrence from Southern Nuclear Operating Co,Inc Encl HL-2335, Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level1992-09-0202 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level HL-2355, Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error1992-07-30030 July 1992 Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error 1999-07-29
[Table view] |
Text
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" ;:Gootgd Power Company _-.
- 333 Pedmcnt Avenue '
t Ahanta Georg:a 30308 ^ -
e '. Telephone 404 526-6724
[, Masnh Adtress:1
<'r l PotioHce Bot 4545 A!!arna Georgo 30302
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p ;jR. E. Conway
, Senior vice Prescent NED-84-085 h 2 -
November 7, 1984 E
. Director of Naclear Reactor IW p at l on i
Attention: Mr.; Jbbn F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing ~
U. S. Maclear Reg.41atory Oommission -
' Nashington, D. C. 220555 NRC DOGETS 50-321, 50-366 OPERATING LICDBES DPR-57, NPF-5 EDWIN 'I. HA701 NUCIEAR MANT LNI'IS 1, -2 RESIONSE TO NRC GENERIC IRITFR 84-15/ REQUEST TO AME20 DIESEL GENERATOR 1EOMICAL SPECIFICATIONS Gentlemen Georgia Power @npany (GPC) has completed a review of NRC Generic Intter-84-15, " Proposed Staff Actions to Inprove and Maintain Diesel ' Generator Reliability". Enclosure 1 of this letter and its attachmento form GPC's response. Included as part of our response and in accordance with the provisions of- 10 'CER 50.90, as realired by 10 CER 50.59(c) (1), GPC' bereby subnits a' reglest to amend diesel generator Technical Specifications 'for Plant Hatch Units 1 and 2. The proposed changes '(Attachnent 1) would revise the 'mchnical Specifications associated with the Limiting conditions for Operation, surveillance Regiirements, and bases for diesel generator operability. GPC and' the diesel merufacturer (Colt Indastries) have determined that some of the current Technical Specification airveillance regiirements are not beneficial to the reliable performance of the onsite emergency. power system. The proposed c.hanges to the 'mchnical Specifications provide improvements ' which we believe will enhance the reliability of the diesel generators. We have - previcusly addressed cur concern in our-letter dated Jaruary 9,1984 which was prepared as a response to - your letter (Generic Letter 83-41) dated December 16, 1983, regarding
' fast cold starts of diesel generators.
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GeorgiaPowerk o ,
Director of Maclear Reactor Regalation
' Attentions 'Mr. Jbhn F. Stolz, Chief Operating Reactors Branch No.-4 November 7,:1984 Page 'Dso The proposed changes have' been reviewed and approved by the Plant Review Board and the' Safety Review Board and have been determined not to constitute
' an unreviewed safety gaestion.
The= probability of ocairrence or the consegnances of an accident or malAnnction of egaipsant important to safety wtmald not be increased above those ' analysed in the PSAR harmee the operation of safety-related egnigment 'is not affected by the proposed changes. - The possibility of an accident or malainction of a different type than any analyzed in the- PSAR would not remalt from these changes bacalma no
. new mode of failure is introdLiced. - As stated above, the proposed changes to the Technical Specifications provide improvements ' which enhance D/G reliability, thus the margin of ' safety < would not be reduced by these proposed changes. Also, the proposed changes have been evaluated and determined not to-involve significant hazards considerations. Enclosed is a complete - safety evaluation as reg 11 red by ' OR . 50.59 (Attachment 2), and a' significant hazards review as reglired by 10 GR 50.92 (Attachment 3).
R1ralant to 10 OR 170.21 a check for the amendment application of
$150.00 is enclosed.
R1ratant to the reglirements of 10 OR 50.92, J. L.. Imdbetter of the Georgia' Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
R. E. (bnway states that he is Senior Vice President of Gecrgia Power Company and is althorized to exealte this oath on behalf of Georgia Power (bapany, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GDRGIA ICHER COMPA!N By: ' b
, R. E.
1 and albecribed before um this 7th day of November,1984.
A ^ 8. n o /
/' l - g g Notary Riblic e .e i m w CTAb _g,ca.ia s.,a, uyains Ehclosure xc: H. C. Nix, Jr.
Eenior Resident Inspector
, .J. P. O'Reilly, (IEC-Region II)
J. L. Ischetter
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Enclomare 1 r l
Information Romested to Address Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability (Generic Intter 84-15) 4 l I e k
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Mtam 1 - Rekction' in Masbar of Cold Fast Start &arveillance i hets for Diesel Generators 1his item is directed towards re& cing the mober of cold fast. start
, marveillance tests for diesel generators whid . the staff has . determined results' in premature - diesel engine degradation. %e details relating to this subject are provided in mclosure 1 of Generic Intter 84-15. Licensees are reenested to describe' their current . programs to avoid cold fast start surveillance testing or their ' intended actions to .re&ce cold fast start marveillance testing for diesel generators.
Osorgia Power -has long been concerned with the. reliability of the diesel generators at' Plant Hatch. . his is demonstrated by Georgia Power's initiation of a Diesel Generator Reliability Study, 'in the latter part of 1980, to determine the '. reliability of the diesels and provide reccomended actions for owing ' diesel reliability. %e results of _ this study,-
published in ary of 1982, showoci that the availability of the Plant Hatch diesels was better than the national average. However, Georgia Power was still concerned with the mober of diesel failures and in the fall of 1982 L formed a Diesel Generator Task Force to resolve . diesel generator problems with respect to testing reesirements, replatory concerns and
%e Diesel Generator Task Mrce members include design, licensing and site engineers as well as representatives from colt In& stries, the diesel's memfacturer. h Task Force has currently developed fifty-six action items of which only ten remain open. Although the Task Force did not use NWEG-0660, "mhancement of On-site anergency Diesel Generator Reliability",
as' a pide, many of the action items developed were .. recommendations of NWEG-0660 (see discussion in response to item 3). %e action items include proce&ral, lesign and technical specification changes. Several of these action items are directly related to the re&ction in the mober of cold fast starts.
In the fall of 1982 tte Task Force implementated two proce&ral changes.
De first proce&ral change incorporated a four mimte prelubrication time preceding all engine startc except actual or simulated emergency starts.
nis change will re&ce the number of cold fast starts on the diesel s generators. We second change revised loading and unloading - proce&res, which includes loading the diesels in incremental steps in accordance with the anmfacturer's reconwendations. %is proce&ral change will decrease the m ober of cold fast starts.
As discussed in Georgia Power letter dated January 9,1984 on fast cold starts of diesel generators, a lube oil keep warm / circulation system was installed on diesels 2A and 2C and the swing diesel IB tring the recent Page 1 3 9 vm tw A v '
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- r (mit 2 oreAmeling' cutage. A' lube. oil keep wataVcirculation ' system is schechsled to be -. installed on the Unit 1 diesels charing . the = current 1984
- outage. . Thei installation of . this . system J was rarv=== ruled by - the diesel
, . memfacturer. : Se lube oili system will'aatomatically provide prelubrication -
o upon normal and emergency startup, while the keep wara/ciroslation system
~~will provide better lubrication by contimously circulating warm oil through
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' > the header. _ De addition of this ' system should . significantly enhance the-
-overall' performance and reliability of the diesel generators.
-In addition to thei prococharal' and design' changes already discussed, ' the Diesel Generator Task- 1%rce has been , developing : proposed technical specification changes to eliminate the excessive . testing reunirements.- Se-proposed changes should rectice the msber of ' cold fast starts, : improie diesel performance and increase - overall reliability of the diesel generators. Sese proposed Unit 1 'and Unit 2 Technical Specifications are being anbeitted as part of this response and are included as Attachment 1.
Se proposed Unit 1 Technical Specifications include eliminating diesel generator testing when 'certain emergency core cooling systens -(i.e., core-spray and low presaire coolant injection) and essential service water systems (i.e., plant service water and IUR service water) are declared
-inoperable, as reccamended in Generic Intter 84-15.
Several other proposed diesel generator technical specifications for both units will help eliminate excessive testing- and increase. diesel reliability. It is proposed that the test schedLile be revised so that routine testing is done only in faarteen or seven day. intervals and that these intervals be determined by the mnber of failures per diesel . ratter than per melear unit basis. It is proposed that the testing reesirements, when an onsite AC ~ saarce(s) and/or offsite power souroe(s) is declared
~
inoperable, be revised to allow more . time for testing and loading' the diesels. Finally it is proposed to recisce the frecuency of the~ atusite tests, which recuire five successive starts of the diesels to verify tre capability of the air start receivers, and that the overload test be revised to reatire the overload operation to occur in the last two hours of the twenty-four hour test. All of these technical specification changes are being proposed per the diesel marufacturer's recensendations and are compatible with the reconmendations contained in Generic Intter 84-15.
Item 2 - Diesel Generator Reliability Data 21s item reezests licensees to furnish the current reliability of each diesel generator at their plant (s), based on surveillance test data.
Licensees are rentested to provide the information recuested in Encionare 2 of Omneric Intter 84-15. .
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Response:-
%e. reliability of the ' diesel generators at Hatch Nuclear . Plant' has been .
determined- in accordance with 'Regalatory Gaide 1.108 position C.2.e and is-L provided below.' Table 1 provides the maber of failures -in tre last 20 and ~
100 . valid demands through Aagust 1984 and ' the ' associated . reliability ' for-each diesel. Table 2 lists the time history -(failure date) for .the > three
- diesel 2C failures. _:a,
.in developing this response to Generic Ietter 84-15 'tre Diesel. Generator F.eliability Study, psblished in February .of 1982, was updated. %e data from this original study went from startup for both units to mid-1981. In' comparing the resalts of ' the original. study to the data collected face the
. last three years trere is a 'significant inprovement in diesel reliability, with four diesels having 'no failures in the last- 456 tests. %e only exception- is diesel 2C whose reliability has remained about the same. %is -
might be attrituted to the fact that diesel 2C has been tested over twicef as nuch as any other diesel-in the same time, period. With the incorporation of-the proposed technical specifications provided in Attactment. 1, this excessive testing will be redaced. . In addition, the_ design and procedaral
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changes _ developed by the Diesel Generator Task Force, as .disatssed in - the responne to Item 1'above, shaald increase the reliability .of tie aiesels.
Regarding the casestion conceraing records, Georgia Power does maintain a log '
of diesel generator trials and failures for each diesel. Tests which are valid according to Regulatory G11de -1.108 position'. C.2.e are entered.
Failures are indicated and a brief description 'is entered indicating tre .
casse of the failure. %is log does not include all tre provisions ~ of ,
Regalatory Gaide 1.108 position C.3.a.~ However Georgia Power feels that the ;
information given in the. log and in' the procediral data steets are adecniate for determining diesel reliability.
A yearly data report is currently not maintained for the diesel generators. ,
However the proposed technical specifications for both units, provided in Attachment 1 to this response, recnires that an anmal report be mitaitted to the IRC in lieu of the reportable ocmtrences reca11rement -(Unit' 2 :
'mchnical Specification 4.8.1.1.3) . ' 'Ite anmal report would provide the NRC -
with the mmber of valid tests and the mmber of failures to start on demand
- and would provide a monitor on diesel reliability.
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- - Licensees 'are recanested: to_ describe their; progrant, fif any, for . attaining and
- msintaining a reliability goalffor their Mamal generators. An example of f a -
) performance TechnicalE Specification 1 to mapport a" desired diesel-. generator .
- n - reliability goal;has .been provided byhthe staff in Enclomare ;3. of Generic
.Istter 84-15. Licensees are recanested J tof comment ' on, andc compare their-
- existing program . 'or any ; p- . - a ; program with the example - performance
- ~ specification.,
- Response:; .
~
Georgia ^[ Power has'-several ongoing' activities ~ designed to improvei and-maintain f diesel generator reliability. , - In ithe ' fall : of 1982. the Diesel' Oenerator Task Mrce began implementing the fifty-six action ' items referred to in the response to Item 1 above. Although NUREG-0660, . "Enharamont- of On-site Snergency Diesel Generator Reliability", was not used as a guideiin developing the action items, the Task lBorce action items address many of the-recommendationsv of NUREG-0660. - Table- 3Dprovides a manmary : of :which
-recommendations were addressed and how they were _ implemented. Also, a list .
of Task ' Force action . items not . reconmended by NUREG-0660 but- whichS are
-significant.. to Georgia _ Power's program for improving diesel reliability 'is
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provided in Table 4.
'Ite major Task l Force ~ action - item involved revising - the Hatch Technical Specifications; 'Ite. revised technical specifications proposed changes to the marseillance and, testing performed to demonstrate' diesel generator reliability per ~ the diese1~. mamfacturer's recommendations.- 'Ite proposed technical specifications are enclosed ' as Attachment 1. 'Ihese changes, as aanmarized in the response to Item 1 and discussed in ~ detail in the safety evaluation (Attachment 2) and significant hazard evaluation (Attachment 3) will' redice the mmber of cold fast starts, eliminate excessive testing and redace the -frecalency of abisite testing. Georgia Power .is confident that these changes will inprove diesel performance and ~ increase diesel-reliability. Also, the proposed technical specifications will recalire that an anmal report on diesel reliability be' mitatitted to the Mtc as discussed in' the response to Item 2. ' Itis ' report will allow diesel reliability to- be
~
monitored.-
A trend analysis was performed using the data collected for the response to ~
cItem 2. As stated in the response to Item 2 this data shows an increase in diesel reliability oser the last three years as conpared to the reliability ,
prior to mid-1981. Since the Task Force has been implementing-recommendations for the last - two years, scue of this inprovement may be attrituted to their activities. ,
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considering the overall high reliability (of the diesels d2 ring the past
- three years, Georgia Rwer. believes that with the ongoing work of tre Diesel Generator Task Force, whose main objective is to improve diesel reliability, and with NRC approval of the proposed technical specifications (Attactment
- 1) that the current Georgia Rwer programs are attaining and will contirue to maintain a high reliability goal. For these reasons Georgia Power is of the opinion that the proposed changes to .the- technical specifications contained -in Attachment 1 are in our best interest for maintaining high diesel generator reliability in lieu of the performance specifications contained- in Generic Letter 84-15. In addition the surveillance - testing regiirements contained in Generic Intter 84-15 are not consistent with those recomended by the diesel generator marufaciturer.
9 Page 5
Table 1: Diesel Generator Reliability' Failures in Failures in lart Reliability- . last Reliability
- Diesel 20 Demands (20 Demands) 100 Demands (100 Demands)
^1A 0 '1004 - 0 100%
. -IC 0 1004- 0 100%
1B* 0 100% 0. 1004 2A 0 1004 0 1004 2C 1 954 3 974
- Diesel 1B is a swing diesel and serves both units.
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i Table 2: Time History of Failures-t
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Diesel Failure 'Date' ,
p 2C 17/27/82 p' 2C- 6/10/83-i.-
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'Imble 3: MJRI!G-0660 GMPARISON .
MatEG-0660 Item anbiect Task Pbece Action A-1 Air Driers in Air- .%e Diesel Generator' Task Start system Pbece fourd that moisture
- related failures were not a
. recurring problem in the starting air system therefore air driers would not be beneficial.
A Air Qaality In 'It was found that the Diesel Generator problems disoissed in ,
Room NURFG-0660 do not exist at Plant Patch, therefore no correctite actions were initiated.
A-3 'Iurtocharger Heavy Plant Hatch tas Eliott type Daty Gear Drive "H" turbo chargers and ras experienced no problems. ,
%erefore this reconnenda-tion is not applicable.
A-4 Personnel Training %e diesel mamfacturer has cordicted a class for operators, maintenance persovinel and engineers.
Georgia power is working with Colt Ird2stries to I develop a training ccurse !
to be talght on a regalar basis B-1, 2 Pre-Lute Sgine The procedures have been Starts -
revised to include a four mirute prelube. Also, a lute oil keep warm / s ciraalation system has teen installed on Unit 2 and is being installed on Unit 1.
B-3 Testing, Test 'Ite proposed 'mchnical loading and Specifications revise the Preventive surveillance realirenents Mainter ance - per the diesel generator marufacturer's reconnenda-tions.
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Table 3: NLAtBG-0660 CINPNtISON (ODNTINUED)
MatEG-0660 ,
Item albject Task Force Action B-3a Minimi::ing no-load %e plant procedsres have and light load been revised to set mininum operations loading of Diesels at 25%
of rated load.
B-3b heting Frentencies %e proposed technical specifications revise tre test frestencies per tre diesel marufacturer's recom-sendation.
B-3c Maintenance 1be procedsres were reviewed Procedtres by site engineers and tre diesel tratufacturer and revised accordingly.
B-4 " Root Casse" and The Task Force immstigates Corrective Action probless to determine casses and implements action items to correct them.
C-1 DG Boom Ventila- Plant Itatch has experienced .
tion and comtus- no problems. 1herefore no tion Air Inlet corrective action has been taken. %e roads are paved and the grcunds are properly prepared marrcund-ing the diesel tuilding.
%erefore dast is not a
' problem.
C-2a niel Storage and Plant IIntch has no drain Handling gravity line at the bottom of the -
drains in tulk tank. Ilowever, fuel oil storage filel tanks analysin is performed once per 92 days to check for water por the Technical Specifications (Unit 1 -
4.9.A.2.D and Unit 2 -
- 4. 0.1.1. 2.D. ) . Nointure in fuel has not been a problem at plant !!atch.
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. r Tht4e 3: R5BG-0660 CGtPNLISCW MK4rtDRED) masG-0660 Item &aldect Task Perce Action C-2b '
' Rael Storage and Plant Hatdi fkael supply Handling Rael pamps are engine driven as L anpply masps . recommended. 'Itse fuel supply to this engine driven pump is gravity.
fed.
C-3 High 'Itaperature Plant Hatch diesels use Inaalation for class F inaalation which Overload is designed for a 105'c temperature rise (resistance method)
C-4 Engine Cooling 'this was included in the Water 'Itaperature ' original diesel generator Ctntrol design.
C-5 concrete Floors- nas to the age of tre floors Painting in the diesel generator tuilding, tre concrete has properly set. W refore,
-cmabling and dust experienced from new .
concrete is no problem.
l C-6 Instm ment and Plant Hatch has experienced controls Mxanting no problems with the instmments and controls.
W refore no corrective
- action has teen taken. W l 'instmments are nannted on the same concrete pad as the diesel tut not directly ,'
l on the diesel itself.
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Table 4:' Major Task Force Action Items Not Included in the Reconnendations of ICREG-0660
- 1. Replace ' diesel generator starting . air compressor : pressure - switch to correct setpoint drift problems.
2.. Revise ' operating procochares ' according to diesel marufacturer's roccamendations.
~3. Install more reliable governor booster units to deter start failures or long starting times.
- 4. Install sample test point for oil analysis on diesels 'and l incorporate oil analysis into diesel operating procedtares. alch an analysis may detect potential failures.-
'5. Remove the practice of 'barring-over the diesel from 'the procediares to prevent damage to the diesel, per mamfacturer's reconsnendations.
- 6. Remove cylinder relief valtes from diesel generators becaise trey leak and create a potential fire hazard. Dese ' valves were intended for ;
melear alb;narine service only.
- 7. Replace unloader bonnets with brass sleeved bonnets to correct corrosion problems associated with conpressor unloader valves.
- 8. Install an air filter on the air compressors for better mality air.
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