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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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JUtt1 5 1992 NLR-H91209 LCR 91-17 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen' -
LICENSE AMENDMENT APPLICATION LPCI/ CSS " KEEP FILLED" AIARM INSTRUMEN"" l'Iw FACILITY OPERATING LICENSE NPF-57 IIOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby submits a request for amendment of Facility Operating License HPF-57 for the Hope Creek Generating Station in accordance with 10 CFR 50.90. A copy of this submittal has been sont to the state of New Jersey as indicated below pursuant to the requirements of 10 CFR 50.91(b)(1).
The proposed change voald provide an allowable-out-of-service (ACT) tor the Low Pressure Coolant Injection (LPCI) system and Core Spray System (CSS) discharge line " keep filled" alarm $
instrumentation. This would allow monthly sur,eillance tests to be performed on interrelating instrumentation without requiring the CSS and/or LPCI system (s) to be vented.
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Attachment 1 includes a description, justification and significant hazards analysis for the proponed change.
Attachment 2 contains marked up Technical Specification (TS) pages which reflect the proposed change.
PSE&G bellaves that this submittal contains sufficient technical justificet. ion to conclude that a detailed specialist review should not be required and that the proposed change can be classified as a Category 2 change.
Upon NRC approval, please issue a License Amendment which will be effective upon issuance and shall be implemented within 60 days of issuance.
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- _ _ . - . . _ _ _ _ . . . .___._____m.___ . . _
e Document control Desk 2 JUN 151992 NLR-N91209 Should you have any questions or comments on this submittal, please do not hesitate to contact us.
Sincerely, h r( frrrc e t Affidavit Attachments (2) 4 C Ms. A. Keller
- USNRC Licensing Project Manager - Nope Creek -
Mr. T. Johnson USNRC Senior Resident Inspector Mr. T. T. Martin Administrator - USNRC Region I Mr. Kent Tosch' Chief -New Jersey Department of-Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering h' CN 415 Trenton, NJ 08625 l
c --. - . . - _ . - _ . . .~_._-a.-... . _ - . . _ _ _ _ _ _ _ _ _ _ . . _ . . . _ . . -
e JU:41 6 1992 Ref NLR-N91209 LCR 91-17 l l
STATE OF NEW JERSF.Y )
) SS.
COUNTY OF SALEM ) l l S. LaBruna, being duly sworn according to law deposes and says?
1' I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth-on our letter dated , concerning the Hopo creek Generating Station, are true to the best of my knowledge, information and bo11ef.
,h 7&o w i
Subscribed and Sworn-t:o before me this /5 "' day of ( ..jtLRA , 1992 =
i V
l 11fL(Ahyh. , N Ndtary Publ)lc of New Jersey NOTARY N!ittC Of NEW JERSEY i My Commission expires on "# C*""" " " ""
l 4
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I -
ATIACHMENT 1 REQUEST FOR LICENSE AMENDMENT LPCI/ CSS " KEEP FILLED" AIARM INSTRUMENTATION FACILITY OPERATING LICENSE HPs'-57 IlOPE CREEK GENERATING STATION DOCKET NO. 50-354
1 i
NIR-N91209 IDPE CREK ICR 91-17 l
I. Description of the Pro. paged chances This amendment request proposes to provide a six hour allowable-out-of-service time (AoT) for the discharge line " keep filled" alarm instrumentation (hereafter referred to as " keep filled" instrumentation) associated with the Low Pressure Coolant Injection (LPCI) system and Core Spray System (CSS). This would allow monthly surveillance tests to be performed on interrelating instrumentation without requiring the CSS and/or LPCI system (s) .
to be vented.
II. Reason for the Pronosed Chances There are no monthly surveillance requirements associated with the LPCI and CSS " keep filled" instrumentation; consequently, there is no allowable out-of-service time (A0T) specified in Technical Specifications. However, operability of this instrumentation is directly impacted by monthly surveillance testing that is required to be performed on interrelating instrumentation as described below.
Presently, the only guidance provided by Technical Specifications when the " keep filled" instrumentation is rendered inoperable as a result of monthly surveillance testing on interrelating instrumentation is to. vent the affected ECCS subsystem (s). This evolution requires personnel to enter high radiation areas (greater than 100 mrem /hr). PSE&G believes that the potential safety benefits of this requirement are not sufficient to warrant the associated radiological exposure.
l The incorporation of the proposed change would reduce future occupational radiological exposure. This philosophy is consistent with the guidance provided in Regulatory Guide 8.10,
" Operating Philosophy For Maintaining occupational Radiation l Exposures As Low As Reasonably Achievable", which, in part, l
states:
" Modifications to operatir.g and maintenance procedures and to plant equipment and facilities should be made where they will substantially redace exposures at a reasonable cost."
PME 1 OF 6 ATTAQlMDTP 1
NUl-N91209 IDPE CRDD< U3191-17 III. Justification for the Pronosed Changga A. Cov}onent Configuration The LPCI/ CSS discharge line fill network is designed to maintain the LPCI and CSS pump discharge lines in a filled condition in order tot 1) minimize the time lag between the signal to start the pumps and the initiation of flow to the reactor pressure vessel (RPV); and 2), prevent water hammer damage to the injection piping during pump starts.
The fill network consists of two independent jockey pumps (CP228 and DP228) and their associated controls and instrumentation.
Jockey Pump CP220 serves LPCI Subsystems A and C and CSS Subsystem A while Jockey Pump DP228 serves LPCI Subsystens B and D and CSS Subsystem B. Power is recolved from separate-Class 1E electrical channels. Although the fill network is safety-related and designed to Seismic Category I criteria, it is not considered an integral part of the ECCS.
Each ECCS injection loop is provided with a separate, isolable fill line, supplied from the Condensate Transfer and Storage System, to permit maintenance of individual ECCS injection loops without disabling other ECCS injection equipment.
B.. Instrumentation Configuration The LPCI and CSS " keep filled" instrumentation consists of the following trip units:
- 1-BC-PSL-N654A (LPCI Subsystem A)
- 1-DC-PSL-N654B (LPCI Subsystem B)
- 1-BC-PSL-N654C (LPCI Subsystem C)
- - 1-BC-PSL-N654D (LPCI Subsystem D) l -- 1-BE-PSL-N658A (CSS Subsystem A) l
- 1-BE-PS L-N 658 B (CSS Subsystem B) l IYCE 2 OF 6 ATTAQMDIT 1 I
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NIR-N91209 4 IlOPE CREEK IfR 91-17 The instruments listed above are configured as slave trio units.
Each receives an input signal from a master trio unit which, in turn, receives a signal from a pressure transmitter located in the injection line of the respective ECCS subsystem. The master trip units are designated as follows: ;
I 1-BC-PISil-N653A (LPCI Subsystem A)
- 1-BC-PISH-N653B (LPCI Subsystem B)
- 1-BC-PISil-N653C (LPCI Subsystem C)
- 1-BC-PISil-N653 D (LPCI Subsystem D)
- 1-BE-PISil-N654A (CSS Subsystem A)
- 1-BE-PISil-N 65 4 B (CSS Subsystem B)
Thus, in each LPCI and CSS injection line, there is a pressure transmitter which provides a signal to a master / slave pair of trip units in series.
The master trip units are designated as the " reactor coolant interface valves leakage pressure monitors" (hereafter referred to as leakage pressure monitors) and actuate upon sensing a high nressure condition to indicate potential back leakage from the reactor into the' low pressure injection lines.
The slave trip units, composing the LPCI and CSS " keep filled" instrumentation, actuate upon sensing a low nrossure condition to indicate potential failure of the respective fill network.
Both trip units within each master / slave pair provide input signals to a common control room overhead annunciator. These annunciators are listed below:
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NIR-N91209 Il0FE CREEK IG 91-17 l
The annunciators listed above subsequently provide initiating inputs, via repeater relays, to activate the following computer digital alarms:
- RHR PUMP A DISCHARGE PRESSURE
- RHR PUMP B DISCHARGE PRESSURE
- RHR PUMP C DISCHARGE PRESSURE
- RHR PUMP D DISCilARGE PRESSURE
- CS LOOP A INJECTION LINE PRESS
- CS LOOP B INJECTION LINE PRESS C. Technical Specification Requirements The LPCI and CSS discharge line " keep filled" alarm instrumentation is encompassed by Specification 3.5.1, "ECCS -
Operating". Within that specification, surveillance 4.5.1 requires a channel calibration of the affected instrumentatinn to be performed at least once per 18 months. There is no allowable-out-of-service time specified. If a " keep filled" instrumentation becomes inoperable, Action f requires the affected LPCI and/or CSS subsystems to be vented in order to verify that the systems are filled with water. This evolution, which is also a 31 day surveillance requirement, requires personnel to enter high radiation areas in order to obtain access to the respective high-point vent valves.
The leakage pressure monitors are encompassed by Specification 3.4.3.2, " Operational Leakage". Within that specification, surveillance 4. 4. 3. 2. 3 requires channel functional tests at least once per 31 days and channel calibrations at least once per 18 months for the affected monitors which are listed in Table 3.4.3.2-2. Action d allows a monitor to be inoperable for up to seven days; if it cannot be restored to operable status within seven days, the pressure in the respective discharge line must be verified to be less than the alarm setpoint at least once per twelve hourst if the monitor cannot be restored to operable status within 30 days, the plant must be placed in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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NIR-N91209
, HORB QEIX bO191-17 l
Because of the master / slave configuration described above, a LPCI or CSS " keep filled" instrumentation channel (slave trip unit) is rendered inoperable whenever its associated leakage pressure i monitor channel (master trip unit) is inoperable. This occurs ;
during the monthly channel functional tests of the leakage pressure monitors required by Specification 4.4.3.2.3.a. Thus, although there are no monthly surveillance test requirements for the " keep filled" instrumentation, operability of this instrumentation is directly impacted by the monthly surveillance tests required to be performed on the interrelated leakage pressure annitor instrumentation.
D. Proposed Change i Based upon the preceding discussion, PSE&G is hereby proposing to provide an allowable-out-of-service time (A0T) in Specification 3.5.1 for the LPCI and CSS " keep filled" instrumentation. This AOT would apply only if the affected " keep filled" instrumentation is inoperable due to the performanco of required .
surveillance testing. This includes testing of the leakage '
pressure monitors in accordance with Specification 4.4.3.2.3.
! If the " keep filled" instrumentation becomes inoperable for reasons other than surveillance testing, or cannot be returned to operable status within cix hours, the requirement to vent the affected ECCS subsystems would still exist.
i Additionally, the six hour A0T would apply only if the " keep filled" instrumentation associated with at least one other LPCI or CCS subsystem serviced by the affected " keep filled" system reraains operable. This would ensure that failure of a " keep filled" system associated with an inoperable channel would still be annunciated by a redundant channel of instrumentation associated with an interconnected ECCS subsystem. If the " keep filled" portion of the affected LPCI or CSS subsystem is isolated L from the other subsystems serviced by the respective fill j network, the proposed AoT would not apply.
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liLR-N91209 il01E CREEK ICR 91-17 IV. Slanificant Hazards Consideration Evaluation PSE&G has, pursuant to 10 CFR 50.92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration. We have determined that operation of the Hope creek Generating Station in accordance with the proposed i changest
- 1. Will not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment does not involve a physical or procedural change to any structure, component or system that significantly affects the probability or consequences of any accident or malfunction or equipment important to safety previously evaluated in the Updated Final Safety Analysis Report (UFSAR). The proposed change will provide a reasonable period of time to accomplish required surveillance testing while assuring continued operability of redundant instrumentation.
- 2. Will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed revision will not involve any physical changes to the plant. Additionally, the A0T will apply only if redundant instrumentation remains operable thereby ensuring that failure of the affected " keep fill" system will still be annunciated.
- 3. Will not involve a dignificant reduction in a margin of
-safety.-
The proposed A0T will reduce radiological exposure of plant personnel. Insofar as the A0T will apply only for surveillance testing and only if redundant annunciation remains operable, this change can be made with no significant change in the margin of safety.
3 V. Conclusion Based on the preceding discussion, PSE&G has concluded that the -
proposed change to the_ Technical Specifications does not involve a significant hazards consideration insofar as the change: (1) does not involve a significant increase in the probability or
- consequences _of an accident previously evaluated, (ii) does not create the possibility of a new or different kind of accident from any' accident previously evaluated, and (iii) does not involve a significant reduc ~c ion in a margin of safety.
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r e l ATTACH 11ENT.1 RFQUEST FOR LICENSE AMENDMENT LITI/ CSS " KEEP FILLED" AIARM INSTRUMENTATION FACILITY OPERATING LICENSE NPP-57 IlOPE CREEK GENERATING STATION DOCKET NO. 50-354
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