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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
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Pubhc Service Dectne and Gas
. Canpany Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609-339-1200 m ..oi. .o-.-.
JAN 2 01995 I NLR-N94209 l LCR 94-26 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LICENSE AMENDMENT APPLICATION REMOVAL OF EXPLOSIVE GAS MIXTURE FROM THE TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 l This letter submits an application for amendment to Appendix A of Facility Operating License NPF-57 for the Hope Creek Generating Station, and is being filed in accordance with 10CFR50.90.
Pursuant to the requirements of 10CFR50. 91(b) (1) , a copy of this request for amendment has been sent to the State of New Jersey.
The proposed Technical Specification changes contained herein represent changes to Section 3/4.11.2.6 " Explosive Gas Mixture,"
Table 3.3.7.11-1 " Radioactive Gaseous Effluent Monitoring Instrumentation," and Table 4.3.7.11-1 " Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements."
The proposed revision removes this specification from the Technical Specifications and relocates the Bases to the Hope Creek Updated
, Final Safety Analysis Report (UFSAR) and the Surveillance l Requirements to the applicable surveillance procedures. The Limiting conditions for Operation (LCOs) will be eliminated. While 10CFR50.36 will no longer provide the determination of acceptable functional capability / performance for safe operation of the main condenser offgas treatment explosive gas monitoring system, operation and maintenance of this system will be commensurate with its safety significance.
The proposed changes have been evaluated in accordance with 10CFR50. 91 (a) (1) , using the criteria in 10CFR50.92 (c) , and it has been determined that this request involves no significant hazards considerations.
A description of the requested amendment, supporting information and analyses for the changes, and the basis for a no significant l hazards consideration determination are provided in Attachment 1.
I 9501270124 950120 s t a
\
! PDR ADOCK 05000354 ,
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JAN 2 01995 i
i Document Control Desk l NLR-N94209 l
The Technical Specification pages affected by the proposed changes are provided in Attachment 2 with pen and ink changes.
l In accordance with the guidance presented '
the " Final Policy Statement on Technical Specifications Im7.ovemants for Nuclear Power Reactors" as published in the Federal Register (58 FR 39132) , l the proposed changes have received a multidisciplinary review by l responsible technical supervisory personnel, including onsite i operations personnel. l l
Upon NRC approval of these proposed changes, PSE&G requests that the amendment be made effective on the date of issuance, but ,
implemented within sixty days to provide sufficient time for associated administrative activities.
Should you have any questions regarding this request, we will be l
pleased to discuss them with you. l Sincerely,
- =
. . Hagan Vice e ident Nuclear Operations ;
l l
Affidavit j Attachments (2) !
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Moran, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission one White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. R. Summers (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
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[. REF: NLR-N94209 i LCR 94-26 :
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! STATE OF NEW JERSEY )
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! COUNTY OF SALEM l
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! J. J. Hagan, neing duly sworn according to law deposes and saysi i 1 ,
~
j I am Vice President - Nuclear Operations of Public' Service Electric'-
i and Gas Company, and as such, I find the matters set forth in the >
i j above referenced letter, concerning the Hope Creek Generating j I. Station, are ' true to the'best of my knowledge, information and 1
i belief.
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l Subscribed and S or to before me .
f this d o M day MtmHMLh *, 1995
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[ Notary Public $f New Jersey '
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MBERLY Jo BROWN NOTARY PUBLIC l i
My Commission expires on uv ew.. . r..,:0F ,..,_.s. NEWJERSEY____ :
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9 ATTACHMENT 1 l l
PROPOSED CHANGES TO TECHNICAL SPECII*ICATIONS LICENSE AMENDMENT APPLICATION REMOVAL OF EXPLOSIVE GAS MIXTURE FROM THE TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 NLR-N94209 DOCKET NO. 50-354 LCR 94-26 i
I. DESCRIPTION OF THE PROPOSED CHANGE _S_
This amendment removes Specification 3/4.11.2. 6 " Explosive Gas j Mixture" and its asscciated Bases from the Technical Specifications with corresponding changes to the Table of l Contents. References to the main condenser offgas treatment l system explosive gas monitoring system made in Tables l 3.3.7.11-1 " Radioactive Gaseous Effluent Monitoring l Instrumentation" and 4.3.7.11-1 " Radioactive Gaseous Ef fluent l Monitoring Instrumentation Surveillance Requirements" are also deleted along with associated footnotes and required actions.
II. REASONS FOR THE CHANGES The proposed changes to the Technical Specifications conforms with the NRC's " Final Policy Statement on Technical l Specifications Improvements for Nuclear Power Reactors," dated July 22, 1993. During the development of NUREG-1433 " Standard Technical Specifications, General Electric Plants, BWR/4" the j NRC issued a letter to the B&W Owners Group, T.E. Murley to '
W.S. Wilgus dated May 9, 1988, which identified the Explosive Gas Mixture monitoring system for the main condenser as a Limiting Condition for Operation (LCO) which may be relocated to other licensee-controlled documentation contingent upon NRC staff approval of the location of and controls over the relocated requirement.
Through this submittal, PSE&G is requesting implementation of ,
the NRC's recommendation regarding the relocation of the i Explosive Gas Mixture specification. Along with the relocation of the Bases to the Hope Creek Updated Final Safety Analysis Report (UFSAR) and the Surveillance Requirements to the applicable surveillance procedures, this submittal eliminates the LCO's. Removal of this specification from the Technical Specifications would reduce regulatory burden, since future changes to the explosive gas mixture monitoring functions would be conducted using the 10CFR50.59 process.
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ATTACHMENT 1 NLR-N94209 REMOVAL OF EXPLOSIVE GAS MIXTURE LCR 94-26 FROM THE TECHNICAL SPECIFICATIONS III. JUSTIFICATION FOR CHANGES The purpose of the explosive gas mixture specification is to ensure that the concentration of potentially explosive gas mixtures contained in the_ gaseous radwaste treatment system main condenser offgas system is maintained below the flammability limits of hydrogen. The hydrogen is mainly produced by radiolytic disassociation of water and carried' over to the main condenser via the main steam lines. The hydrogen is then removed, along with other noncondensible gases, by the Steam Jet Air Ejectors (SJAE) and trancferred to the gaseous radwaste treatment system. Any hydrogen not recombined in the feed gas recombiner is exhausted through the north plant vent. The effluent stream is monitored by two thermal conductivity type analyzers to determine the hydrogen concentration.
With the conclusion of the Technical Specification Improvement Program the NRC issued it's final policy statement on technical specification improvements for nuclear power
! reactors. The NRC concluded that the purpose of the Technical l Specifications is to impose those conditions or limitations l upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. This was achieved by identifying those issues that are of controlling importance to safety and establishing on them certain limiting conditions for operation which cannot be changed without prior NRC approval.
l This policy statement included a set of criteria which l delineated those constraints on design and opuration derived from the UFSAR and that belonged in the Technical Specifications in accordance with 10CFR50.36. Specifically, these criteria are as follows:
e Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary, o A process variable, design feature, or operating restriction that is an initial condition of a Design Basis Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, o A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either l
ATTACHMENT 1 NLR-N94209 REMOVAL OF EXPLOSIVE GAS MIXTURE LCR 94-26 FROM THE TECHNICAL SPECIFICATIONS l
assumes the failure of or presents a challenge to the integrity of a fission product barrier, 8 A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
While the explosive gas mixture specification provides guidance for minimizing the possibility of a hydrogen explosion in the main condenser or gaseous radwaste system this system does not fall ander any of the above criteria.
Taking into consideration the fact that the main condenser is ,
not a safety related component and that the offgas system is designed to withstana a hydrogen detonation, failure of the explosive gas mixture mclitoring instrumentation would not constitute a significant abnormal degradation of the reactor coolant pressure boundary nor would it be a design basis accident or transient.
l Therefore, the explosive gas mixture monitoring capability is not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolanc pressure boundary nor is it a process variable that is an initial condition of a Design Ba >is Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The explosive gas mixture monitoring capability is I also not a system, component or structure that is part of the I primary success path for mitigating a Design Basis Accident or l Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. A l review of the past five years operating history indicates that hydrogen concentrations have not exceeded operating limits.
In accordance with the NRC's criteria for determining those specifications which may be relocated to licensee-controlled documentaticn, PSE&G believes that this submittal for removing the Explosive Gas Mixture specification from the Technical Specifications is justified. These changes will reduce regulatory burden while maintaining existing levels of plant safety.
IV. DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION l
PSE&G has, pursuant to 10CFR50.92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration. We have determined that
l ATTACHMENT 1 NLR-N94209 REMOVAL OF EXPLOSIVE GAS MIXTURE LCR 94-26 FROM THE TECHNICAL SPECIFICATIONS the operation of the Hope Creek Generating Station in accordance with the proposed changes:
- 1. Will not involve a significant. increase in the probability or consequences of an accident previously evaluated.
The proposed changes involve no hardware changes, no changes to the operation of any systems or components, and no changes to existing structures. The relocation of this specification to the UFSAR and surveillance procedures will continue to ensure that the entrainment of hydrogen
! in the main condenser is monitored and controlled.
j Relocation of this specification's Bases and Surveillance Requirements to the UFSAR and surveillance procedures,
- respectively, and the deletion of the LCO's represent ,
I changes that do not affect plant safety and do not alter i existing accident analyses.
- 2. Will not create the possibility of a new or different kind of accident from any previously evaluated.
I i The proposed changes are procedural in nature concerning the location of the descriptive information and ,
,] surveillance requirements for the explosive gas mixture '
t monitoring instrumentation. Removing these specifications i from the Technical Specifications and placing them in the ;
4 UFSAR and surveillance procedures will not alter the 1 4
operation of the explosive gas monitors or their ability I to perform intended functions. Maintenance and testing of
! these monitors will continue based upon the manufacturers j~
recommendations taking into consideration plant operating experience. Therefore, these changes will not create a
- new or unevaluated accident or operating condition.
- 3. Will not involve a significant reduction in a margin of safety. '
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- The proposed changes relocate the Explosive Gas Mixture
- specifications from the Technical Specifications to the j
UFSAR and surveillance procedures in accordance with guidance provided by the NRC Final Policy Statement regarding the improvement of Technical Specifications.
The requ.4rements that will reside in the UFSAR and i
surveillance procedures for the explosive gas mixture
{ monitoring instrumentation will ensure that the ability to determine main condenser hydrogen concentrations is 1 properly maintained. Therefore, the proposed changes will i not involve a significant reduction in any margins of l safety.
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. l ATTACHMENT 1 NLR-N94209 l REMOVAL OF EXPLOSIVE GAS MIXTURE LCR 94-26 FROM THE TECHNICAL' SPECIFICATIONS V. CONCLUSIONS Based on the above, PSE&G has determined that the. proposed changes do not involve a significant hazards consideration.
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