Letter Sequence Request |
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MONTHYEARML20235U6271987-10-0808 October 1987 Application for Amends to Licenses DPR-57 & NPF-5,revising Fuel Average Planar Linear Heat Generation Rate Limits & ECCS Surveillance Requirements.Proprietary Tech Spec Pages & GE Topical Rept NEDC-31376P Encl.Fee Paid Project stage: Request ML20236Q4191987-11-17017 November 1987 Informs That Proprietary NEDC-31376P, Edwin I Hatch Nuclear Plant,Units 1 & 2,SAFER/GESTR-LOCA LOCA Accident Analysis, Dtd Dec 1986, Will Be Withheld from Public Disclosure (Ref 10CFR2.790(b)(5)),per 871008 Request Project stage: Other 1987-10-08
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Similar Documents at Hatch |
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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
,_
e IGeot0!a Fowhr Cornpany ;
[/ ' 333 Pmdmont Avenue
[ ; Atlanta, Georgia 30308 ,
p Toephone 404 526//8511 x " ' Mailing Address:
Fbot Office Box 4545 -
. Atlanta, Georgia 30302.'
i~
. James P. O'Reilly . : the southern eixtnc system
. . . Senior Vice President
'F-Nucleat Orierations SL-3232 1679C X7GJ17-H600 October 8, 1987 E .U.S.' Nuclear Regulatory Commission ATTN:: Document Control Desk '
Hashington, D. C. 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES.DPR-57, NPF-5
. REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0VIREMENTS i
. Gentlemen.
l 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
- - Plant - Hatch Units 1 and 2 Technical Specifications, Appendix A to Operating Licenses DPR-57 and NPF-5.
. The- proposed changes involve revisions to the Unit 1 and Unit 2 i Technical' Specifications defining fuel Average Planar Linear Heat Generation - Rate - ( APLHGR) limits and Emergency Core Cooling System (ECCS)
Surveillance Requirements.- Specifically, the proposed Technical Specifications changes would:
- 1. Revise APLHGR limits for General Electric BP8x8R and P8x8R fuel types (Units 1 and 2).
- 2. Add an APLHGR limit for fuel types BP8DRB301L and P8DRB301L l (Units 1 and 2). ,
1
- 3. Revise the minimum flowrate Surveillance Requirement for the i Core Spray System (Units 1 and 2) and the maximum Response Time Surveillance Requirements for the' Core Spray System and the Residual Heat Removal System (Low Pressure Coolant Injection mode) (Unit 2 only).
- 4. Revise the Bases to reflect the Plant Hatch SAFER /GESTR-LOCA analysis and delete APLHGR limits for the fuel that will not be !
used (Units 1 and 2).
B710140171 871000 v '
PDR ADOCK O 31 (g40 h%
Og 4 )
X 1
U.S. Nuclear Regulatory Commission October 8, 1987 Page.Two.
1 The proposed changes, if approved, would permit greater core design and operating ~ flexibility and would result in nuclear fuel cost savings.
The changes would also remove unnecessary conservatism from the ECCS Surveillance Requirements and ensure that the Technical Specifications are consistent with the new LOCA analysis.
Enclosure.1 provides a detailed -description of the proposed changes and circumstances necessitating the change request.
Enclosure 2 details the basis for our determination that the proposed changes do not involve significant hazard considerations.
Enclosure 3 provides page change instructions for incorporating the proposed changes.
The proposed changed Technical Specifications pages follow Enclosure 3.
To support the proposed changes, Enclosure 4 provides documents that have not been submitted to the Nuclear Regulatory Commission (NRC).
Please note that some information in Enclosure 4 has been marked
" Proprietary" to protect the commercial interest of the fuel vendor. In accordance with 10 CFR 2.790, an affidavit is included herein which requests that certain information be withheld from the public domain.
Payment of a filing fee in the amount of one hundred and fifty dollars is enclosed.
In order to allow time for procedure revisions 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, a copy of this letter and all applicable enclosures will be sent to Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources.
l 1679C L
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U S. Nuclear. Regulatory Commission
. October.8, 1987 Page Three Mr. James - P. O'Reilly states that. he is ' Senior. Vice President of-Georgia Power Company. and. is. authorized to execute this oath on behalf of Georgia. Power Company, and .that to the' best of his knowledge and belief,
.the facts set forth in this letter are true.
GEORGIA POWER COMPANY By: O>vreA .@ b James P. O'Reilly o
. Sworn to and subscribed befor e this th day of October 1 .
~ '/:
Nk Notary Public k$Y nevry p sc. cia,en county. Gern GKN/lc Uycmune n E
Enclosures:
- 1. Basis for Change Request
- 2. 10 CFR 50.92 Evaluation
- 3. Page Change Instructions-
.4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA
-Loss of Coolant Accident Analysis," NEDC-31376-P.
- 5. Filing Fee - $150.00 c: Georaia Power Comoany Mr. J. T. Beckham, Jr. w/o enclosures GO-NORMS w/o enclosures U.S. Nuclear Regulatory Commission. Washington. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch w/ enclosures U.S. Nuclear Regu1Atory Commission. Reaion II Dr. J. N. Grace, Regional Administrator w/ enclosures Mr..P. Holmes-Ray, Senior Resident Inspector - Hatch w/ enclosures Stitte of Georaj.A Mr. J. L. Ledbetter ,
l 1679C
i-i ENCLOSURE 1-PLANT HATCH UNITS 1, 2 NRC 00CKETS 50-321 50-366 OPERATING ~ LICENSES DPR-57, NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS: .
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0UIREMENTS-BASIS-FOR CHANGE RE0 VEST PROPOSED CHANGE 1:
Eackground: j This change revises the Technical Specifications Average Planar Linear Heat Generation Rate (APLHGR) limits to reflect results from the "Edwin I. Hatch ! Nuclear Plant Units .1 and 2 SAFER /GESTR-LOCA Analysis Report,"- -
NEDC-31376-P (Enclosure 4). The- APLHGR limits presently in the- Technical
- Speci fications were calculated using General Electric SAFE /REFLOOD methodology. The . proposed new APLHGR limits for P 8R and BP8x8R fuel
. covered. .in ' the ' Technical Specifications were calc! 2ted .using approved -
. SAFER /GESTR-LOCA and GEMINI physics methods.
Basis for Procosed Change 1: I The General Electric SAFER /GESTR-LOCA methods are described in References 1, 2, and 3. The NRC approval of these methods is documented in ;
References 4, 5, .and 6. Plant-specific LOCA/ECCS analyses with l SAFER /GESTR-LOCA have been reviewed and approved by the NRC for Duane Arnold Energy Center.-(Reference 7) and for the James A. Fitzpatrick ,
Nuclear Power Plant (Reference 8).
The Plant Hatch SAFER /GESTR-LOCA analysis (Enclosure 4) demonstrates that the generic peak clad temperature (PCT) versus break-size curves (Reference 3) for both nominal and Appendix K model assumptions are i applicable to both Plant Hatch units. The PCT points calculated for
. Plant Hatch Units 1.and 2 using realistic models demonstrate that the shapes of the PCT versus break-size curves match the shape of the nominal generic curve for the BHR 3/4 plant class. The SAFER /GESTR-LOCA licensing: basis PCT calculations for Plant Hatch Units 1 and 2 with Appendix _ K model assumptions also show that both units' PCT versus break-size curves match the gener.c Appendix K PCT versus break-size curves for the BWR 3/4 class of plants.
The Plant Hatch analysis was performed with many of the Emergency Core Cooling System .(ECCS) parameters conservatively established relative to
. the actual performance of the ECCSs at Plant Hatch. This was done in support of the Technical Specifications program for Plant Hatch so that 1679C El-1 10/8/87 SL-3232
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ENCLOSURE 1 (Continued)
RE0 VEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS l BASIS FOR CHANGE RE0UEST future improvements to the plant could be accommodated without requiring extensive reanalysis. The maximum PCT from the Plant Hatch SAFER /GESTR-LOCA analysis for nominal model assumptions was nearly identical to that of the generic BWR 3/4 nominal analysis at 14.4 kW/ft presented in Reference 3. Furthermore, Plant Hatch has similar '
sensitivities, as does the generic plant, to the parameters used to calculate the generic upper-bound PCT. Consequently, the results from the generic BHR 3/4 calculations of the statistical upper bound are applicable to the Plant Hatch units with the assumed ECCS parameters. l The Plant Hatch ECCS configuration for the limiting-break and single- h failure combination is identical to the generic BWR 3/4 ECCS configuration.
Finally, the licensing basis PCTs for each Hatch unit exceeded the statistical upper bound PCT, but remained below the 22000F 10 CFR 50.46 limit, as required by Reference 6. All 10 CFR 50.46 requirements for LOCA ECCS evaluations (maximum cladding oxidation, maximum hydrogen generation, PCT, coolable geometry, and long-term cooling) are met by the Plant Hatch fuel types addressed in the SAFER /GESTR-LOCA analysis. ;
)
The Plant Hatch SAFER /GESTR-LOCA analysis demonstrates that APLHGR limits proposed for these Technical Specifications are derived on the basis of the maximum allowable fuel pellet power level (MLHGR) used as the fuel design basis. Lattice local power and exposure peaking factors ,
calculated using approved GEMINI methods (Reference 9) are applied to !
transform MLHGR into APLHGR limits for each bundle type. '
i i
1679C El-2 10/8/87 SL-3232 1
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ENCLOSURE 1 (Continued)
REOUEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENT _S BASIS FOR CHANGE RE0 VEST PROPOSED CHANGE 2:
Backaround:
This change would add an APLHGR limit curve to the Technical Specifications for both Plant Hatch units to allow for the use of General ;
Electric fuel types BP8DRB301L and P80RB30ll. !
Basis for ProDosed Change 2:
Average Planar Linear Heat Generation Rate limit data, as a function of Average Planar Exposure for BP8DRB301L fuel, is given in Reference 10.
The Plant Hatch SAFER /GESTR-LOCA analysis, reported in NEDC-31376-P, demonstrated that BP8x8R and P8x8R fuel types are not limited by ECCS considerations. Therefore, the Reference 10 data result solely from fuel thermal mechanical design limits divided by appropriate bundle local i peaking factors to yield average planar power limits. In this case, the i local peaking factors were derived with General Electric's NRC-approved l GEMINI physics methods (Reference 9).
l l
I 1679C El-3 10/8/87 SL-3232
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h ENCLOSURE 1-(Continued)
REOUEST TO REVISE TECHNICAL ~ SPECIFICATIONS:
LFUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0VIREMENTS I BASIS FOR CHANGE RE00EST PROPOSED CHANGE 3:
Backaround:
This. change revises .certain Technical Specifications Surveillance
. Requirements for the Core Spray (CS) System and the Low Pressure Coolant !
Injection -(LPCI) mode of the Residual Heat Removal (RHR) System. The
~ changes are: (1) a decrease in the required CS System flowrate i
. Surveillance Requirement from 4625 gpm to 4250 gpm (Units 1 and 2), )
(2) an increase in .the ECCS maximum Response -Time for the CS System from 27 sec to 34 sec- (Unit 2), and (3) an increase in the ECCS maximum Response Time for the LPCI mode of RHR from 40 sec to 64 set (Unit 2).
Basis for Proposed Change 3:
Analyses of the Design Basis Loss-of-Coolant Accident (LOCA) for Plant.
Hatch Units 1 and 2, performed with the SAFER /GESTR-LOCA methods (Enclosure 4), assumed that the performance of the ECCS equipment was as given in. the proposed Surveillance Requirements. No plant safety
. functions, except LOCA mitigation, are being performed by the equipment with proposed revised Surveillance Requirements. Therefore, for consistency with the analysis requirements, the' Surveillance Requirements are' being revised. Neither the CS System nor the LPCI mode of RHR would be modified as a result of the approval of this proposed change.
Emergency Core Cooling System Response Time, defined in the Plant Hatch Unit 2 Technical Specifications Definition section, is that time interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). The
' Response Time includes diesel generator starting and sequence loading delays for the RHR and CS pumps. The existing requirements for diesel generator starting and sequence loading for RHR are not being revised at this time. The proposed required Response Times reflect the availability of LPCI and/or CS flow assumed in the SAFER /GESTR-LOCA analysis.
It should be noted that the proposed relaxations in pump flow rates and ECCS response times are consistent with the LOCA analysis assumptions.
1679C El-4 10/8/87 SL-3232
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ENCLOSURE I (Continued) _
~
RE00EST-TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0VIREMENTS -;
BASIS FOR CHANGE RE00EST
- t This will . allow =GPC greater. flexibility in operation ~ and in the purchasing of . . qualified replacement components. Requirements for
- Inservice Inspection and Testing. (including ASME'Section XI and Appendix J) will still track the performance history of . mechanical components (eg., pumps and valves)... Sur_veillance and testing. . requirsnents for-Instrumentation and Control equipment will continue as before.
PROPOSED CHANGE 4:
flar,haround:
This change would revise -the Technical Specifications Bcses sectiolu for ',
both Plant Hatch units to reflect the changes. in the Design Basis' LOCA ^.
resulting. from the Plant. Hatch SAFER /GESTR-LOCA analysis. This change +
would. also delete ~ from the Technical Specifications for both units . the-existing APLHGR limits. for all 7x7 fuel, for other non-prepressurized- 5 fuel, and for fuel types BP8DRB284LA and P80RB284LA. >
The proposed changes are administrative in nature. Existing information H 1
in.the Bases which is no longer applicable is being deleted or modified; _.
analogous information which is applicable to the new LOCA analysis is being added to the Bases. The APLHGR limits for the.7x7 and other fuel types are being deleted, because they willj 'not be used for anticipated reload core designs.
b
.W 1679C E l .-5 10/8/87 SL-3232
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ENCLOSURE'1 (Continued)
EE00EST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS BASIS FOR CHANGE REOUEST REFERENCES
- 1. . . "The 'GESTR-LOCA and SAFER Models for the Evaluation of the Loss of-Coolant Accident," NEDE-23785-1-P (Proprietary); Volume 1, "GESTR/LOCA -A Model for the Prediction of Fuel Rod Thermal Performance," December 1981.
- 2. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss of Coolant Accident," EDE-23785-1-P (Proprietary); Volume 2, " SAFER -
Long: Term Inventory Model for BHR Loss-of-Coolant Analysis," December 1981.
- 3. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss of Coolant Accident", NEDE-23785-1-P (Proprietary); Volume 3
" SAFER /GESTR. Application Methodology," March 23, 1984.
- 4. U.S. Nuclear Regulatory Commission, " Safety Evaluation of the General Electric Company Topical Report, NEDE-23785-1, Volume 1 - GESTR/LOCA, A Model for the Prediction of Fuel Rod Thermal Performance,"
September 1983, report approved November 2, 1983.
- 5. U.S. Nuclear Regulatory Commission, " Safety Evaluation Report on the MFER Code," July _ 12, 1983.
- 6. Letter, C. O. Thomas (NRC) to J. F. Quirk (GE), " Acceptance of Referencing of Licensing Topical Report NEDE-23785 Revision 1. Volume III, 'The GESTR LOCA and SAFER Models for the Evaluation of the Loss of Coolant Accioent,'" June 1, 1984.
, 7. Letter, A. J. Cappucci (NRC) to L. Liu (IELP), " License Amendment No.
af 142 - Cycle 9 Reload (TACB568)," May 7, 1987.
8.' Letter H. I. Abelson (NRC) to J. C. Brons (NYPA), " Approval of James A. Fitzpatrick Nuclear Plant (Docket 50-333) Technical Sper.ification Amendment Number 109," April 3,1987.
- 9. Letter, C. O. Thomas (NRC) to J. S. Charnley (GE), " Acceptance for Referencing of Licensing Topical Report NEDE-30130, ' Steady State Nuclear Methods,'" December 22, 1985.
- 10. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss of Coolant Accident Analysis," NEDC-31376-P, as amended, December 1986.
i l
1679C El-6 10/8/87 SL-3232 1
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ENCLOSURE'2-
. PLANT HATCH UNITS 1, 2 NRC~ DOCKETS 50-321, 50-366
'0PERATING LICENSES DPR NPF-5 .
, . REOUEST TO REVISE TECHNICAL SPECIFICATIONS:
. FUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0UIREMENTS 10 CFR 50.92 EVALUATION PROPOSEDC/dE1:-
This changef revises .the Technical Specifications Average Planar Linear
Heat Generation Rate (APLHGR) limits to reflect results from' the "Edwin I. - Hatch Nuclear Plant Units 1. and 2 SAFER /GESTR-LOCA Loss of: Coolant Accident Analysis Report, ' NEDC-31376-P. The APLHGR limits presently in the Technical Specifications were calculated using General Electric t
SAFE /REFLOOD . methodology. The proposed new APLHGR limits for' P8x8R and BP8x8R fuel covered in the Technical . Specifications were calculated using-approved SAFER /GESTR-LOCA and GEMINI physics method:,. The revised limits would parmit, greater core design and operating flexibility and would result in nuclear fuel' cost savings.
j Basis far Significant Hazards Determination:
The proposed change does- not involve a significant hazards consideration.
for the following reasons:
1
- 1. It does not. involve a significant increase in the probability or consequences of- an accident previously evaluated, because no. change in plant design or. procedures will occur as a result of this change.
Any future core loading patterns or core operational conditions facilitated by the proposed change will be evaluated, using approved methods, and shown to meet the approved acceptance criteria for analysis of the limiting accidents that were previously evaluated.
Therefore, the consequences of an accident would not be significantly i increased.
The~ consequences of a hypothetical design basis LOCA have been !
evaluated, consistent with the proposed fuel limits, and shown to be ,
,less severe than those predicted to occur using existing limits in the earlier SAFE-REFLOOD analysis. The revised analysis is reported in General Electric report NEDC-31376-P, "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss of Coolant Accident Analysis." .
f .2. The proposed change would not create the possibility. of a new or different kind of accident from any previously analyzed, because no
[
o change in plant equipment or procedures will occur as a result of
[ this change.
1679C E2-1 10/8/87
.SL-3232-a 1
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M ENCLOSURE ~2 (Continued).
REOUEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS
_10 CFR 50.92 EVALUATION
- 3. The proposed change' would not involve a'significant reduction- in- the!-
margin of safety, because thel proposed ~ revised -limits : have .been determined, using approved analysis methods,- and. have been shown to n.< - maintain all existing fuel safety ~ margins associated with- Energency Core Cooling; System performance..
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ENCLOSURE 2 (Continued) ;
REOUEST TO REVISE TECHNICAL SPECIFICATIONS:
'EUEL THERMAL LIMITS-AND ECCS SURVEILLANCE REQUIREMENTS.
10 CFR 50.92 EVALUATION PROPOSED CHANGE 2i
.This change would add' an APLHGR limit curve to the Technical Specifications for .both Plant Hatch units to allow for the_ use of General Electric fuel types BP8DRB301L and P8DRB301L.
Basis for No Significant Hazards Determination:
L The proposed chhnge does not involve a significant hazards consideration
- for the following reasons
- 1. - It does not involve. a significant increase in the probability of an accident previously evaluated, because no change in plant design or procedures will occur as a result of this proposal. The proposed new fuel' type is' generically licensed for use in either Hatch unit under the " General Electric Standard Application for Reactor Fuel,"
NEDE-24011-P-A. Use of the proposed limits would- not significantly increase the consequences of an accident previously evaluated for the same reasons stated for Proposed Change 1 above.
~2. .It ' does not create. the possibility of a new or different kind of accident -from any previously analyzed, because no significant change in plant equipment or procedures will. occur as a result of this change.
- 3. It does not involve a significant reduction in the margin of safety for'the same reasons stated for Proposed Change 1 above.
1679C E2-3 10/8/87 SL-3232
ENCLOSURE 2 (Continued)
REQUEST TO REVISF_]ICHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE RE0VIREMENTS 10 CFR 50.92 EVALUATION PROPOSED CHANGE 3:
This change revises certain Technical Specifications Surveillance Requirements for the Core Spray (CS) System and the Low Pressure Coolant Injection (LPCI) mode of the Residual Heat Removal (RHR) System. The changes are: (1) a decrease in the required CS System flowrate Surveillance Requirement from 4625 gpm to 4250 gpm (Units 1 and 2),
(2) an increase in the Emergency Core Cooling System (ECCS) maximum Response Time for the CS System from 27 sec to 34 sec (Unit 2), and (3) an increase in the ECCS maximum Response Time for the LPCI mode of RHR from 40 sec to 64 sec (Unit 2).
Basis for No Significant Hazards Determination:
The proposed change does not involve a significant hazards consideration for the following reasons:
- 1. It does not involve a significant increase in the probability of an accident previously evaluated. The proposed revised Surveillance Requirements are unrelated to initiating events for the FSAR Chapter 15 accidents. Thus, the probability of occurrence of those ;
initiating events would not be affected by the proposed change. The ECCS equipment involved would function to mitigate a hypothetical Design Basis LOCA; other functions of the equipment require less performance capability. The performance of this equipment during a LOCA has been evaluated, consistent with the proposed change. It was !
shown that in such an event, all applicable acceptance criteria would be met. These LOCA acceptance criteria were established to ensure ,
that the consequences of a Design Basis LOCA would not significantly af fect public health and safety. Therefore, the consequences of an j accident would not be significantly increased.
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- 2. It would not create the possibility of a new or different kind of accident from any previously analyzed, because no change in plant design or operation is involved.
- 3. It would not involve a significant reduction in the margin of safety for the same reasons stated under Proposed Change 1 above.
1679C E2-4 10/8/87 SL-3232
ENCLOSURE 2 (Continued)
REOUEST TO REVISE TECHNICAL SPECIFICATI0XS: )
ffEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS 10 CFR 50.92 EVALUATION PROPOSED CHANGE 4 This change would revise the Technical Specifications Bases sections for both Plant Hatch units to reflect the changes in the Design Basis LOCA resulting from the Plant Hatch SAFER /GESTR-LOCA analysis. Existing information which is no longer applicable is being deleted or modified, as necessary. Analogous information applicable to the new LOCA analysis is being added to the Bases. This change would also delete from the Technical Specifications for both units the existing APLHGR limits for all 7x7 fuel, other non-prepressurized fuel, and for one prepressurized fuel type.
Basis for No Significant Hazards Determination:
The proposed change does not involve a significant hazards consideration for the following reasons:
- 1. It does not involve a significant increase in the probability or consequences of an accident, because it is purely an administrative change. The change is being proposed to: (1) achieve consistency of the Technical Specifications Bases requirements that would be revised by Proposed Changes 1, 2, and 3 and (2) delete from the Technical Specifications unnecessary information for fuel not expected to be used in future reload cores.
- 2. It would not create the possibility of a new or different kind of accident from any previously analyzed, because no change in plant design or operation is involved.
- 3. It would not involve a significant reduction in the margin of safety because the change is purely administrative.
1679C E2-5 10/8/87 SL-3232
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ENCLOSURE 3 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR NPF-5 RE0 VEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS EAGE CHANGE INSTRUCTIONS The proposed changes to Technical Specifications-(Appendix A to Operating Licenses DPR-57 and NPF-5) would be incorporated as follows:
Removed Page UNIT 1 Insert Pagg X X 3.5-1 3.5-1 !
3.5-14 3.5-14 3.5-21 3.5-21 3.11-3 3.11-3 Figure 3.11-1 (Sheet 1) Figure 3.11-1 (Sheet 1)
Figure 3.11.1 (Sheet 2) Figure 3.11-1 (Sheet 2)
Figure 3.11.1 (Sheet 3) Figure 3.11-1 (Sheet 3)
Figure 3.11.1 (Sheet 4) Figure 3.11-1 (Sheet 4)
Figure 3.11-1 (Sheet 5) Figure 3.11-1 (Sheet 5)
Figure 3.11-1 (Sheet 6) Figure 3.11-1 (Sheet 6) 3.11-6 3.11-6 Removed Pagg UNIT 2 Insert Paag 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4a 3/4 2-4a 3/4 2-4b 3/4 2-4b 3/4 2-4c 3/4 2-4c >
3/4 2-4d 3/4 2-4d 3/4 2-4e 3/4 2-4e 3/4 2-4f 3/4 2-4f 3/4 2-49 3/4 2-4g 3/4 2-4h 3/4 2-4h 3/4 2-41 3/4 2-41 3/4 3-30 3/4 3-30 3/4 5-5 3/4 5-5 ,
B 3/4 2-1 B 3/4 2-1 i B 3/4 2-2 B 3/4 2-2 l B 3/4 2-6 B 3/4 2-6 1
1679C E3-1 10/8/87 SL-3232 u_________-
ENCLOSURE 4 PLANT HATCH - UNITS 1, 2 NRC 00CKETS 50-321, 50-366 ,
. an OPERATING LICENSES DPR NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
FUEL THERMAL LIMITS AND ECCS SURVEILLANCE REQUIREMENTS Enclosed is the following document:
"Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss of Coolant Accident Analysis," NEDC-31376-P.
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