|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217E0371999-09-30030 September 1999 Application for Amend to License NPF-57,supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10.Proprietary & non-proprietary Info Re Subject Amend,Encl. Proprietary Info Withheld,Per 10CFR2.790(a)(4) LR-N990357, Application for Amend to License NPF-57,to Change TS to Raise Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool1999-08-26026 August 1999 Application for Amend to License NPF-57,to Change TS to Raise Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML18107A3571999-06-0404 June 1999 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld ML20195B5461999-05-24024 May 1999 Application for Amend to License NPF-57,correcting Typos & Editorial Errors Contained in Ts.Corrections Are Considered to Be Administrative in Nature LR-N990137, Application for Amend to License NPF-57 to Revise TS to Include Oscillation Power Range Monitor (OPRM) Sys,In Preparation for Plans to Fully Enable OPRM Trip Function During Ninth Refueling Outage,Scheduled for Apr 22,20001999-05-17017 May 1999 Application for Amend to License NPF-57 to Revise TS to Include Oscillation Power Range Monitor (OPRM) Sys,In Preparation for Plans to Fully Enable OPRM Trip Function During Ninth Refueling Outage,Scheduled for Apr 22,2000 ML20206G0651999-03-29029 March 1999 Redistributed Application for Amend to License NPF-57, Incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements.Rev 18 to ODCM Also Encl ML20205E7931999-03-29029 March 1999 Application for Amend to License NPF-57,incorporating Programmatic Controls in TS for Radioactive Effluents & Environ Monitoring,Conforming to Applicable Regulatory Requirements ML20198T0131998-12-30030 December 1998 Application for Amend to License NPF-57,proposing Rev to Flood Protection TS LCO & Associated Action Statements ML20198N3901998-12-28028 December 1998 Application for Amend to License NPF-57,permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys LR-N980532, Application for Amend to License NPF-57,revising TS by Replacing Accelerated Testing Requirements of TS Table 4.8.1.2-1 with EDG Performance Monitoring & Delete TS 4.8.1.1.3 Requirement to Submit 30-day Special Rept1998-12-16016 December 1998 Application for Amend to License NPF-57,revising TS by Replacing Accelerated Testing Requirements of TS Table 4.8.1.2-1 with EDG Performance Monitoring & Delete TS 4.8.1.1.3 Requirement to Submit 30-day Special Rept ML20155D3441998-10-22022 October 1998 Application for Amend to License NPF-57,to Revise TS to Establish More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5821998-10-19019 October 1998 Application for Amend to License NPF-57,eliminating Restrictions Imposed by TS 3.0.4 for Filtration, Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities LR-N980363, Application for Amend to License NPF-57,permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries1998-09-0808 September 1998 Application for Amend to License NPF-57,permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4301998-08-25025 August 1998 Application for Amend to License NPF-57,implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs.Proprietary & non-proprietary Description of Revs to TS Encl.Proprietary Info Withheld ML20236F1121998-06-25025 June 1998 Application for Amend to License NPF-57,deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8101998-06-12012 June 1998 Application for Amend to License NPF-57,providing Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintaining Ultimate Heat Sink Operation within Design.Engineering Analyses Also Encl ML20247K7301998-05-13013 May 1998 Application for Amend to License NPF-57,revising TS Inservice Leak & Hydrostatic Testing Requirements.Review Is Requested by 981220,to Support Next Refueling Outage ML20217P9221998-04-28028 April 1998 Application for Amend to License NPF-57,revising TS 3/4.4.2 by Implementing More Appropriate SRV Setpoints.Proprietary GE TR NEDC-32511P, Safety Review for Hope Creek SRV Tolerance Analysis, Encl.Proprietary Info Withheld LR-N970670, Application for Amend to License NPF-57,requesting Rev to App B of TS 4.2.2, Terrestrial Ecology Monitoring, by Rewording Section to Include Completion of Salt Drift Monitoring Program Which Was Completed in Mar 19891997-12-19019 December 1997 Application for Amend to License NPF-57,requesting Rev to App B of TS 4.2.2, Terrestrial Ecology Monitoring, by Rewording Section to Include Completion of Salt Drift Monitoring Program Which Was Completed in Mar 1989 LR-N970622, Application for Amend to License NPF-57,revising TS 3/4.11.1, Liquid Effluents - Concentration, by Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated1997-09-29029 September 1997 Application for Amend to License NPF-57,revising TS 3/4.11.1, Liquid Effluents - Concentration, by Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated LR-N970618, Application for Amend to License NPF-57,adding Surveillance Requirement in Section 3/4.5.1 to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie Valves1997-09-24024 September 1997 Application for Amend to License NPF-57,adding Surveillance Requirement in Section 3/4.5.1 to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie Valves ML20211M2571997-08-26026 August 1997 Sanitized Supplement to 970331 & 970716 Applications for Amend to License NPF-57,revising Ts.Addl Info & Revised TS Bases Pages Associated W/Amend 101 ML20217Q6641997-08-26026 August 1997 Application for Amend to License NPF-57,requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20210P3341997-08-20020 August 1997 Application for Amend to License NPF-57,deleting References to Plants Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage,Per NRC Bulletin 96-003 ML20211M2451997-07-16016 July 1997 Sanitized Version of Supplement to 970331 Application for Amend to License NPF-57,revising TS & Providing Revised SLMCPR Values for Upcoming Operating Cycle (Cycle 8) ML20149G4271997-07-16016 July 1997 Supplements Application for Amend to License NPF-57, Submitted 970331.Supplement Provides Revised SLMCPR Values for Upcoming Operating Cycle (Cycle 8).TSs & Proprietary Info Re SLMCPR Changes,Encl.Proprietary Info,Withheld LR-N970217, Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10%1997-06-19019 June 1997 Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20141G8221997-05-19019 May 1997 Application for Amend to License NPF-57,revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Related Issues Documented in Hope Creek Corrective Action Program ML20140F0261997-04-30030 April 1997 Application for Transfer of Control Re Operating License NPF-57 for Hcngs.Joint Proxy Statement/Prospectus Describing Details of Util Agreement & Plant of Merger W/Delmarva Power & Light Co,Encl LR-N970183, Application for Amend to License NPF-57,requesting Mod to Listed TSs to Adopt Option B of 10CFR50,App J1997-04-0101 April 1997 Application for Amend to License NPF-57,requesting Mod to Listed TSs to Adopt Option B of 10CFR50,App J ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20137M5811997-03-31031 March 1997 Application for Amend to License NPF-57,representing Changes to TS 2.1.2,action a.1.c for LCO 3.4.1.1 & Bases for TS 2.1. Info Re Safety Limit Min Critical Power Ratio Changes Encl. Info Withheld ML20135E8041997-03-0303 March 1997 Application for Amend to License NPF-57,changing TS 3/4.3.1, Reactor Protection Sys Instrumentation, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.3.3, Emergency Core Cooling Sys Actuation Instrumentation ML20134M0771997-02-11011 February 1997 Application for Amend to License NPF-57,requesting Rev to 3/4.8 Re Electrical Power Systems for Improvements to EDG ML20134B5441997-01-24024 January 1997 Application for Amend to License NPF-57,changing TS 3.1.5, Control Rod Scram Accumulators ML20134F4231996-10-25025 October 1996 Application for Amend to License NPF-57,requesting Rev to 3.1.3.5 Re Control Rod Scram Accumulators ML20117K1231996-08-30030 August 1996 Application for Amend to License NPF-57,changing FSAR Decoupling SSE from LOCA ML18102A2541996-07-12012 July 1996 Suppls to Application for Amend to Licenses DPR-70,DPR-75 & NPF-57 Re Qualifications of Operations Manager ML20100R0841996-03-0606 March 1996 Application for Amend to License NPF-57,revising Diesel Fuel Oil Storage & Transfer Requirements ML18101B2501996-02-26026 February 1996 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57, Revising TS Section 6.0 Re Administrative Controls of Plant ML20097C5671996-02-0505 February 1996 Application for Amend to License NPF-57,revising SR 4.6.2.2.b & 4.6.2.3.b to Include Flow Through RHR Heat Exchanger Bypass Line in SPC & Suppression Pool Spray Flow Path Used During RHR Pump Testing ML18101B1751996-01-11011 January 1996 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57, Revising TS Section 6.0 Re Administrative Controls & Replacing Specific Mgt Titles W/Generic Mgt Functional Positions ML20099L6571995-12-28028 December 1995 Application for Amend to License NPF-57,revising TS Definition 1.4 Re Channel Calibr to Ensure Required Testing Methodology Aligns W/Std Industry Methodology for Instrument Channels Having T/C or RTD as Sensor ML20098D0011995-10-0707 October 1995 Application for Amend to License NPF-57,revising SR 4.8.1.1.2 Re Testing of EDGs to Be Consistent W/Applicable Licensing Documents Used for Development of EDG Surveillance ML20086T6991995-07-27027 July 1995 Application for Amend to License NPF-57,revising Ts,By Incorporating Updated Pressure Vs Temperature Operating Limit Curves Contained in TS Figure 3.4.6.1-1 ML20083B9591995-05-0404 May 1995 Application for Amend to App a of License NPF-57,increasing Annual Operational Limit for Drywell & Suppression Chamber Purge Sys from 120 H to 500 H ML20082T3351995-04-18018 April 1995 Application for Amend to License NPF-57,revising TS Table 4.3.7.1-1, Radiation Monitoring Instrumentation SRs by Extending Channel Functional Test Interval from Monthly to Quarterly for Each Instrument ML20082C1171995-03-30030 March 1995 Application for Amend to License NPF-57 for Hope Creek Generating Station.Amend Would Eliminate Selected Response Time Testing Requirements from TS & Associated Bases Changes ML20078C8351995-01-20020 January 1995 Application for Amend to License NPF-57,to Remove Specification from TSs & Relocates Bases to Plant UFSAR & Surveillance Requirements to Applicable Surveillance Procedures ML20078C8141995-01-20020 January 1995 Application for Amend to License NPF-57,to Revise Surveillance Requirement 4.1.3.1.2.b Re CR Immovable as Result of Excessive Friction or Mechanical Interference 1999-09-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217E0371999-09-30030 September 1999 Application for Amend to License NPF-57,supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10.Proprietary & non-proprietary Info Re Subject Amend,Encl. Proprietary Info Withheld,Per 10CFR2.790(a)(4) ML20211N5471999-09-0808 September 1999 Amend 121 to License NPF-57 Revising TSs by Locating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990357, Application for Amend to License NPF-57,to Change TS to Raise Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool1999-08-26026 August 1999 Application for Amend to License NPF-57,to Change TS to Raise Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML18107A3571999-06-0404 June 1999 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld ML20195B5461999-05-24024 May 1999 Application for Amend to License NPF-57,correcting Typos & Editorial Errors Contained in Ts.Corrections Are Considered to Be Administrative in Nature LR-N990137, Application for Amend to License NPF-57 to Revise TS to Include Oscillation Power Range Monitor (OPRM) Sys,In Preparation for Plans to Fully Enable OPRM Trip Function During Ninth Refueling Outage,Scheduled for Apr 22,20001999-05-17017 May 1999 Application for Amend to License NPF-57 to Revise TS to Include Oscillation Power Range Monitor (OPRM) Sys,In Preparation for Plans to Fully Enable OPRM Trip Function During Ninth Refueling Outage,Scheduled for Apr 22,2000 ML20205E7931999-03-29029 March 1999 Application for Amend to License NPF-57,incorporating Programmatic Controls in TS for Radioactive Effluents & Environ Monitoring,Conforming to Applicable Regulatory Requirements ML20206G0651999-03-29029 March 1999 Redistributed Application for Amend to License NPF-57, Incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements.Rev 18 to ODCM Also Encl ML20198T0131998-12-30030 December 1998 Application for Amend to License NPF-57,proposing Rev to Flood Protection TS LCO & Associated Action Statements ML20198N3901998-12-28028 December 1998 Application for Amend to License NPF-57,permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys LR-N980532, Application for Amend to License NPF-57,revising TS by Replacing Accelerated Testing Requirements of TS Table 4.8.1.2-1 with EDG Performance Monitoring & Delete TS 4.8.1.1.3 Requirement to Submit 30-day Special Rept1998-12-16016 December 1998 Application for Amend to License NPF-57,revising TS by Replacing Accelerated Testing Requirements of TS Table 4.8.1.2-1 with EDG Performance Monitoring & Delete TS 4.8.1.1.3 Requirement to Submit 30-day Special Rept ML20155D3441998-10-22022 October 1998 Application for Amend to License NPF-57,to Revise TS to Establish More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5821998-10-19019 October 1998 Application for Amend to License NPF-57,eliminating Restrictions Imposed by TS 3.0.4 for Filtration, Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities LR-N980363, Application for Amend to License NPF-57,permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries1998-09-0808 September 1998 Application for Amend to License NPF-57,permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4301998-08-25025 August 1998 Application for Amend to License NPF-57,implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs.Proprietary & non-proprietary Description of Revs to TS Encl.Proprietary Info Withheld ML20236F1121998-06-25025 June 1998 Application for Amend to License NPF-57,deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8101998-06-12012 June 1998 Application for Amend to License NPF-57,providing Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintaining Ultimate Heat Sink Operation within Design.Engineering Analyses Also Encl ML20247K7301998-05-13013 May 1998 Application for Amend to License NPF-57,revising TS Inservice Leak & Hydrostatic Testing Requirements.Review Is Requested by 981220,to Support Next Refueling Outage ML20217P9221998-04-28028 April 1998 Application for Amend to License NPF-57,revising TS 3/4.4.2 by Implementing More Appropriate SRV Setpoints.Proprietary GE TR NEDC-32511P, Safety Review for Hope Creek SRV Tolerance Analysis, Encl.Proprietary Info Withheld LR-N970670, Application for Amend to License NPF-57,requesting Rev to App B of TS 4.2.2, Terrestrial Ecology Monitoring, by Rewording Section to Include Completion of Salt Drift Monitoring Program Which Was Completed in Mar 19891997-12-19019 December 1997 Application for Amend to License NPF-57,requesting Rev to App B of TS 4.2.2, Terrestrial Ecology Monitoring, by Rewording Section to Include Completion of Salt Drift Monitoring Program Which Was Completed in Mar 1989 ML20199C1411997-11-0606 November 1997 Amend 108 to License NPF-57,changes TS 3/4.11.1, Liquid Effluent-Concentration. Change Adds Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Station Service Water Sys LR-N970622, Application for Amend to License NPF-57,revising TS 3/4.11.1, Liquid Effluents - Concentration, by Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated1997-09-29029 September 1997 Application for Amend to License NPF-57,revising TS 3/4.11.1, Liquid Effluents - Concentration, by Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated LR-N970618, Application for Amend to License NPF-57,adding Surveillance Requirement in Section 3/4.5.1 to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie Valves1997-09-24024 September 1997 Application for Amend to License NPF-57,adding Surveillance Requirement in Section 3/4.5.1 to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie Valves ML20217Q6641997-08-26026 August 1997 Application for Amend to License NPF-57,requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20211M2571997-08-26026 August 1997 Sanitized Supplement to 970331 & 970716 Applications for Amend to License NPF-57,revising Ts.Addl Info & Revised TS Bases Pages Associated W/Amend 101 ML20210P3341997-08-20020 August 1997 Application for Amend to License NPF-57,deleting References to Plants Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage,Per NRC Bulletin 96-003 ML20149G4271997-07-16016 July 1997 Supplements Application for Amend to License NPF-57, Submitted 970331.Supplement Provides Revised SLMCPR Values for Upcoming Operating Cycle (Cycle 8).TSs & Proprietary Info Re SLMCPR Changes,Encl.Proprietary Info,Withheld ML20211M2451997-07-16016 July 1997 Sanitized Version of Supplement to 970331 Application for Amend to License NPF-57,revising TS & Providing Revised SLMCPR Values for Upcoming Operating Cycle (Cycle 8) LR-N970217, Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10%1997-06-19019 June 1997 Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20141G8221997-05-19019 May 1997 Application for Amend to License NPF-57,revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Related Issues Documented in Hope Creek Corrective Action Program ML20140F0261997-04-30030 April 1997 Application for Transfer of Control Re Operating License NPF-57 for Hcngs.Joint Proxy Statement/Prospectus Describing Details of Util Agreement & Plant of Merger W/Delmarva Power & Light Co,Encl LR-N970183, Application for Amend to License NPF-57,requesting Mod to Listed TSs to Adopt Option B of 10CFR50,App J1997-04-0101 April 1997 Application for Amend to License NPF-57,requesting Mod to Listed TSs to Adopt Option B of 10CFR50,App J ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20137M5811997-03-31031 March 1997 Application for Amend to License NPF-57,representing Changes to TS 2.1.2,action a.1.c for LCO 3.4.1.1 & Bases for TS 2.1. Info Re Safety Limit Min Critical Power Ratio Changes Encl. Info Withheld ML20135E8041997-03-0303 March 1997 Application for Amend to License NPF-57,changing TS 3/4.3.1, Reactor Protection Sys Instrumentation, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.3.3, Emergency Core Cooling Sys Actuation Instrumentation ML20134M0771997-02-11011 February 1997 Application for Amend to License NPF-57,requesting Rev to 3/4.8 Re Electrical Power Systems for Improvements to EDG ML20134B5441997-01-24024 January 1997 Application for Amend to License NPF-57,changing TS 3.1.5, Control Rod Scram Accumulators ML20134F4231996-10-25025 October 1996 Application for Amend to License NPF-57,requesting Rev to 3.1.3.5 Re Control Rod Scram Accumulators ML20117K1231996-08-30030 August 1996 Application for Amend to License NPF-57,changing FSAR Decoupling SSE from LOCA ML18102A2541996-07-12012 July 1996 Suppls to Application for Amend to Licenses DPR-70,DPR-75 & NPF-57 Re Qualifications of Operations Manager ML20100R0841996-03-0606 March 1996 Application for Amend to License NPF-57,revising Diesel Fuel Oil Storage & Transfer Requirements ML18101B2501996-02-26026 February 1996 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57, Revising TS Section 6.0 Re Administrative Controls of Plant ML20097C5671996-02-0505 February 1996 Application for Amend to License NPF-57,revising SR 4.6.2.2.b & 4.6.2.3.b to Include Flow Through RHR Heat Exchanger Bypass Line in SPC & Suppression Pool Spray Flow Path Used During RHR Pump Testing ML18101B1751996-01-11011 January 1996 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57, Revising TS Section 6.0 Re Administrative Controls & Replacing Specific Mgt Titles W/Generic Mgt Functional Positions ML20099L6571995-12-28028 December 1995 Application for Amend to License NPF-57,revising TS Definition 1.4 Re Channel Calibr to Ensure Required Testing Methodology Aligns W/Std Industry Methodology for Instrument Channels Having T/C or RTD as Sensor ML20098D0011995-10-0707 October 1995 Application for Amend to License NPF-57,revising SR 4.8.1.1.2 Re Testing of EDGs to Be Consistent W/Applicable Licensing Documents Used for Development of EDG Surveillance ML20086T6991995-07-27027 July 1995 Application for Amend to License NPF-57,revising Ts,By Incorporating Updated Pressure Vs Temperature Operating Limit Curves Contained in TS Figure 3.4.6.1-1 ML20083B9591995-05-0404 May 1995 Application for Amend to App a of License NPF-57,increasing Annual Operational Limit for Drywell & Suppression Chamber Purge Sys from 120 H to 500 H ML20082T3351995-04-18018 April 1995 Application for Amend to License NPF-57,revising TS Table 4.3.7.1-1, Radiation Monitoring Instrumentation SRs by Extending Channel Functional Test Interval from Monthly to Quarterly for Each Instrument ML20082C1171995-03-30030 March 1995 Application for Amend to License NPF-57 for Hope Creek Generating Station.Amend Would Eliminate Selected Response Time Testing Requirements from TS & Associated Bases Changes 1999-09-08
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _
e .
Pubhc Service f Electric and Gas Company Corbin A. McNeill, Jr. Pubhc Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Semor Vice President -
Nuclear December 14, 1987 NLR-N87229 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. In accordance with the requirements of 10CFR50.91(b)(1), a copy of this request has been sent to the State of New Jersey as indicated below.
This amendment request revises Technical Specifications 3/4.2.1, Average Planar Linear Power Ratio, 3/4.3.6, Control Rod Block Instrumentation, 3/4.4.1, Recirculation System, as well as the ,
associated Safety Limits and Bases. Specifically, the changes l identified in Attachment 2 are necessary to support the HCGS I Cycle 2/ Reload 1 analysis and permit the use of Extended Load l Line Limit (ELLLA) and Increased Core Flow (ICF) operation. l Attachment I contains further discussion and justification for i these proposed revisions. These changes are required prior to l startup following the refueling outage currently scheduled for April 9, 1988; hence this amendment request should be issued and effective prior to this date.
This submittal includes one (1) signed oriainal, includ ing affidavit, and thirty-seven (37) copies pursuant to 10CPR50.4(b)(2)(ii).
fooI gu!883$*4$i4 k
">,,,ssc
+
i l
1 I
Document Control Desk 2 12-14-87 )
l Should you have any questions on the subject transmittal, please do not hesitate to contact us.
Sincerely, b
Enclosure (check)
Affidavit Attachments (2)
C Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. W. Borchardt USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
Ref: HCGS LCR 87-19 STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:
I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated December 14, 1987, concerning Facility Operating License NPF-57 for Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
Subscribed and Sworna to before me this /f day of S = A , 1987 7
/M Yfhcu l' Notary Public of New Jersey LACAINE Y. BEARD l Notary Pobrc of IAw Jeney My Cornmission Expires May 1,1993 My Commission expires on i
ATTACHMENT 1 PROPOSED CHANGE TO THE TECHNIC AL SPECIFIC ATIONS FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING FIATION DOCKET NO. 50-354 LCR 87-19 l
I. DESCRIPTION OF THE CHANGE Revise the following Technical Specification Sections, Tables and Figures as shown in Attachment 2.
Section 2.1.2 Thermal Power, High Pressure and High Flow b$s !h!bke 02.b 2-1 bSS$Na[nk"s Used in the l
Determination of the Fuel Cladding Safety Limit Figures 3.2.1-1 and Maximum Average Planar Linear 3.2.1-2 Heat Generation Rate ( MAPLHGR) l Versus Average Planar Exposure l Section 3/4.2.3 Minimum Critical Power Ratio i ( MCPR)
Figure 3.2.3-1 MCPR Versus Tau at Rated Flow Figure 3.2.3-2 K( f) Factor
, Table 3.2.3-1 MCPR Feedwater Heating l Capacity Adjustment l Table 3.3.6-2 Control Rod Block l Instrumentation Setpoints Section 3/4.4.1 Recirculation System, Recirculettion Loops Bases 3/4.2.3 Minimum Critical Power Ratio The changes shown in Attachment 2 for the Technical Specifications listed above can be separated into three distinct categories. First are changes which address the Minimum Critical Power Ratio ( MCPR) Safety Limit as a result of changing f rom an initial core to a reload core. Second are changes to the Operating Limits required as a function of the specific analysis of Cycle 2/ Reload 1. Third are changes required for the implementation of Extended Load Li ne Li mi t ( ELLLA) and Increased Core Flow (ICF) Operation.
The reload specific changes could be considered routine, while the ELLLA/ICF changes reflect r e vi si ons which have been implemented at other operating BWR/4 plants si mila r to Hope Creek.
l II. REASON FOR THE CHANGES l The discussion provided below addresses the three categories I
of Technical Specification changes contained within this submittal.
l l
l Page 1 l
l
- 1. Minimum" Critical Power Ratio Safety Limit The changes to the Minimum Critical Power Ratio ( MCPR)
Saf ety Limit are required since this reload is the first reload for HCGS. The current MCPR limit of 1.06 shown in Technical Specification 2.1. 2 is used for initial cores only. The uncertainties associated with this value are shown in Technical Specification Bases Table B2.1.2-1. For reload cores, the uncertainties in the Traversing Incore Probe ( TIP) readings and the R-factor increase slightly thereby creating the slight increase in the MCPR limit from 1.06 to 1.07. The values of troertainties for both the initial and reload cores are ioend in Reference 1.
For Single Loop Operation, the uncertainties in the Core Total Flow and the TIP readings also increase slightly which in turn increases the Si ngle Loop Operation MCPR limit from 1.07 t o 1. 0 8.
These changes in the MCPR limits and their associated uncertainties have been reflected in the following Technical Specifications:
l l Saf ety Limit 2.1.2 Page 2-1 Safety Limit Bases 2. 0 Page B 2-1 Bases Table B2.1.2-1 Page B 2-3 Specification 3/4.4.1 Page 3/4 4- 1 l
- 2. Reload Specific Operating Limits References 2 and 3 contain the new core design and transient analyses for the HCGS Cycle 2/ Reload 1, performed by General Electric Company. These analyses indicate that the Technical Specification power distribution limits for Cycle
! 1 operation need to be revised for continued operation in Cycle 2.
The new Cycle 2 design discharges two fuel types used in the l
Cycle 1 design and replaces them with two new fuel types.
The LOCA li mi t ati ons on the power distributions are presented in Technical Specification 3/4.2.1, Average Planar Linear Hear Generation Rate. The li mi t s are expressed for each of the fuel types present in the core. With the deletion of two fuel types and their replacement with two new fuel types, the Maximum Average Planar Heat Generation Rate ( M APLHGR) curves for these bundles must be revised.
! Therefore, Figure 3.2.1-1, Initial Core Fuel Type P8CIB071, will be replaced by new Figure 3.2.1-1, Reload Fuel Type BP8CRB299HA, and Figure 3.2.1-2, I ni t i al Core Fuel Type P8CIB094, will be replaced by new Figure 3.2.1-2, Reload Fuel Type BP8CRB300L.
Page 2
I The transient analysis of the Cycle 2 design also requires I changes to Technical Specification 3/4.2.3, HCPR. The generation of new HCPR limits for HCGS Cycle 2 was done for two cycle exposure ranges. In other words, from the Beginning of Cycle ( BOC) to the End of Cycle ( EOC) minus 2000 MWD /ST, one set of limits was developed, while another set of li mi t s was been developed for EOC minus 2000 MWD /ST up to EOC. This mid-cycle MCPR analysis provides greater operational flexibility since the dominant transients in Cycle 2 are most limiting at EOC. Due to this added analysis point, less restrictive li mi t s can be used during the initial portions of the cycle. The new HCPR operating li mi t s are presented in two separate figures with one figure applicable to each of the two exposure ranges instead of the current single figure for the entire cycle.
Therefore, the wording of Specification 3/4.2.3, including the associated Action Statement and Surveillance Requirement, have been changed to reflect the two options, and Figure 3.2.3-1 will be replaced with new Figures 3.2.3-1 and 3.2.3-2. Finally, the current Figure 3.2.3-2, K( f)
Factor will be retained although renumbered as Figure 3.2.3-3 with the changes as discussed in the next section on ELLLA/ICF operation License Condi tion 2. C( 11) to Facility Operating License NPF-57 states:
The facility shall not be operated with reauced feedwater temperature for the purpose of extending the normal fuel cycle. After the first operating cycle, the facility shall not be operated with a feedwater heating capacity that would result ig a rated power feedwater temperature less than 400 F unless analyses supporting such operation are submitted by the licensee and approved by the staff.
Since HCGS Cycle 2 will no longer be the first operating cycle, the wording of Specification 3/4.2.3, including the Action Statement and Surveillance Requirement, has bgen revised to remove the o7 tion of operating below 400 F.
Table 3.2.3-1 whi c h re pc.rt g t he feedwater temperature MCPR adjustments for below JJO F operation has been deleted.
- 3. Extended Load Line Limit and Increased Core Flow Reference 4 contains the nalysis performed by General Electric Company in suppot' of expanding the operating domain of HCGS. This referanced report describes the analyses performed to justify operation of HCGS above the ,
100% Load Line and up to 105% of Rated Core Flow. j l
1 Page 3 1
l .
l The required Technical Specification changes for implementation of the expanded operating domain are centered around the Increased Core Flow (ICF) operation. The K( f)
Factor curve in the Technical Specifications for MCpR, currently Figure 3.2.3-2, must be modified so that the range of Core Flow extends up to the 110% Rated Core Flow instead of the current range of 100%. This change in the range is justified in Reference 4.
Technical Specification Table 3.3.6-2 discusses the Control Rod Block Instrumentation Setpoints. The Upscale Setpoints for the Rod Block Monitor are dependent en the recirculation flow. Since this flow will exceed the currently rated recirculation flow during ICF operation, the s e t poi n t needs to be clamped at the 100% recirculation flow value. The reanalysis of the Rod Withdrawl Error transient shown in Reference 4 has assumed this 100% recirculation setpoint for ICF operation.
Technical Specification Table 3.3.6-2 also shows the rod block generated by the Reactor Coolant S" stem Recirculation Flow. Since operation in the ICF region will exceed the current rated recirculation flow, the Upscale Rod Block Setpoint has been increased to prevent spurious control rod blocks when operating in the ICF region; however, ample protection from rod withdrawl at greater than analyzed recirculation flows is still provided.
Surveillance Requirement 4.4.1.1.3 for the Recirculation Loops is also changed to reflect the ability to operate at greater than currently rated recirculation flow. The Motor Generator ( MG) set mechanical and electrical s ',o p s have been increased in order to physically allow for increased core flow.
III. SIGNIFICANT HAZARDS ANALYSIS CONSIDERATION The proposed changes to the HCGS Technical Specifications:
(1) Do not involve a significant increase in the probability or consequences of an accident previously analyzed. The limiting overpressurization transients in the HCGS Final Safety Analysis Report ( FS AR) , Chapter 15, have been analyzed for their impact on the Operating Li mi t MCpR.
The results of these analyses indicate that the Operating Limit MCpR should be increased to the values shown in the marked-up Figures 3.2.3-1 and 3.2.3-2 in order to use the Cycle 2 core design. This analysis also accounts for operation in the ICF region which requires a 0.01 HCpR penalty to the operating li mi t at the EOC. Since the analysis differs only in the reload of the core and in the initial conditions of core flow rate, not the initiating circumstances, the probability of an overpressurization Page 4
~
! l event occurring does not increase. With the increase in the )
l Operating Limit MCPR, which was prepared with the new Safety Li mi t MCPR proposed in the enclosed changes, the analyzed
{ transients will not violate the MCPR Safety Limit; and l 'therefore, the consequences of the overpressurization event l are not increased.
l l ( 2) Does not create the possibility of a new or different l
kind of accident from any accident previously i evaluated. The creation of a new or different ki nd of accident from any previously evaluated accident is not l considered possible because no hardware modifications are l being made other than the reload of the core. The core l reload is of a fuel design similar to that of the initial core and previously evaluated and approved as detailed in Reference 1. The safety analysis that was performed only assumed a different kind of fuel loading and different initial conditions of core flow for ELLLA and ICF operation neither of which creates the possibility of a new or different kind of accident.
( 3) Does not involve a significant reduction in a m6rgin of safety. The analysis provided within this submittal q have recalculated the delta-CPR of the li mi t i ng overpressurization transients f or HCGS assuming the new initial conditions of core flow and new fuel loading. These ,
new delta-CPR calculations, along with the current HCGS FSAR J safety analyses, have provided re vi si ons to the Opereting Li mi t MAPLHGR curves and Operating Limit MCPR for EOC-RPT operable or inoperable. Operation with respect to these revised limits will insure that the margin of safety for the HCGS Cycle 2 Fuel Cladding Safety Limits will be maintained.
I V. CONCLUSIONS PSE&G concludes that this amendment request conforms to Example (iii) for Amendments That Are Not Likely To Involve A Significant Hazards Considerations ( published in Federal Register Volume 51, Number 44, dated March 6, 1986) because this request results from a reload where "no fuel assemblies tare) significantly different from those found previously acceptable to the NRC for a pr e vi ous core." Additionally, Example ( i v) is applicable for ELLLA/ICF operation in that this type of operation has been demonstrated acceptable at other BWR/4 facilities.
Based upon the comparison provided above, the information detailed in Sections II and III of this submittal and the referenced reports identified below. PSE&G concludes that these proposed changes to the HCGS Technical Specifications do not involve a Si gni fi cant Hazards Consideration.
Page 5
1
- w. Y\ !
(
',)'
1 v f, 1
y ,
V. REFERENp,J1 ( ~
4,
, -j q 3 7 ,
The followi>/c' references are proprietary in nature and therefore provided under separate covevi , f, .j d/
o i il
- 1. General Electric Standard Appli c a t i on f or Reac t'or . F uel,' +
GESTAR.f1, Uni t.e d States Supplement, General Electric Company, NEDE-24011-P-A-US, Table 3.2-1. ,
- 2. Su r plement al Reload Licenging Submittal for Hope Creek ,
Ga rierati ng . St ati on Uni t i koload 1 (Cycle 2), Genercl Electric Company, 23A585c, Revision 1. n
\. I I' 4
- 3. Supplement fi,to Supplemental Reload Licensing Sub'ittSi m for Hope Creek Generating Station Unit 1, Reload'One, 'S General Electric Company, 23A5854AA Supplement 1.
y
- 4. Increased Core Flow and Extended Load Line Li mi t i
'* Analysis for Hope Creek Generating Station Unit 1
, Cycle 2, General Electric Company, NEDC-31,487( (, ,
)
(
/
I I
,qs
% l l
\'
f
. /.
,j
/ ,
9
\
! y ,'
.i 1
/
1 I 1
) ,
(>
4
[
Page 6 d l