|
---|
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
.. . . . . -
,. c i
Public Service Electne and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609-339-5700 s . e,..,oeni . uie., %.on.
FEB 0 51996 l LR-N96009 l l LCR H96-03 i l
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 i l Gentlemen:
EXIGENT LICENSE AMENDMENT APPLICATION j i
SUPPRESSION POOL COOLING & SPRAY SURVEILLANCES I
' HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby submits an i application for exigent 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.
Surveillance Requirements (SR) for Suppression Pool Cooling (SPC) and Suppression Pool Spray (SPS) require that during Residual Heat Removal (RHR) pump testing, 10,000 and 500 gpm pass through the RHR heat exchanger, respectively. The Hope Creek design has a bypass line around the RHR heat exchanger that contains a valve which is not designed for tight shut-off. Therefore, there is flow through the bypass line during the surveillance testing.
The flow measurement locations used during the performance of the two SRs do not permit distinguishing flow through the bypass line from flow through the heat exchanger.
To quantify flow through the RHR heat exchanger, Hope Creek has reviewed prior testing and determined that 10,000 gpm passes through the combined (i.e., heat exchanger and bypass line) flow path, but less than 10,000 gpm passes through the heat exchanger.
This results in the system not being in compliance with the SR for the SPC mode of operation. Hope Creek is therefore not in compliance with the Technical Specification for the SPC mode of RHR operation.
9602090109 960205 PDR ADOCK 05000354 P PDR Yk
@ Pnntedon R eyclM P yer l
FEB 0 51996 Document Control Desk 2-LR-N96009 With the SPC mode of RHR inoperable, Hope Creek cannot enter the applicability of the Suppression Pool Cooling Technical Specification (i.e., Operational Condition 1, 2 and 3). Since the current Hope Creek restart schedule,- (Operational Condition 3 on 2/27/96) does not provide the NRC with its normal review and noticing cycle of 30 days, it is requested that the proposed amendment be processed as an exigent change in accordance with 10CFR50. 91(a) (6) .
The proposed exigent amendment request revises SR 4.6.2.2.b and 4.6.2.3.b to include flow through the RHR heat exchanger bypass line (in addition to the RHR heat exchanger) in the Suppression Pool Cooling and Suppression Pool Spray flow path used during RHR pump testing. The proposed change to the SRs, and the associated Bases, is consistent with the basis of.the current surveillance requirement.
A similar change was submitted for the Limerick units which have a similar design of the suppression pool cooling flow path, including a similar type of valve in the bypass line. The change was approved on November 5, 1992 as amendments 57 and 23 to the Limerick Technical Specifications.
Attachment 1 includes a description, justification, and no significant hazards consideration evaluation for the proposed change. Attachment 2 contains the Technical Specification and Bases pages revised with pen and ink, and typed changes.
Based upon the justification provided, PSE&G has concluded that the proposed changes do not involve a significant hazard ,
consideration pursuant to 10CFR50.92.
PSE&G is requesting a 3 day implementation period after amendment approval.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Sincerely, 99 p <A '
i %
Affidavit Attachments (2)
FEB 0 51996 i i . . l Document Control Desk 3 I LR-N96009 C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 l Mr. D. Jaffe, Licensing Project Manager - Hope Creek l
U. S. Nuclear Regulatory Commission l
One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 l Mr. R. Summers (X24) !
USNRC Senior Resident Inspector ;
i Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 l
l l
l l
l l
i
Ref: LR-N9e009 i l
J l
)
l STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
[ L. F. Storz, being duly sworn according to law deposes and says:
l I
I am Senior Vice President - Nuclear Operations of Public Service l
Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Hope Creek )
Generating Station, are true to the best of my knowledge, j l information and belief.
i I
V .
A j
t ./
& (dL<m (&
Subscribed and Sworn to before me this. 6E day of 6 bru oA a , 1996
), aw /1/ A A < 'm / .h nLub Nodary Public 'of blew Jersey KIMBERLY JO BROWN NOTARY f>UBilC 0F NEW JERSEY My Commission expirer on My conmision tipues April 21.1998 l
l l
l l .s , ,
a
- ATTACKMENT 1 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS
, EXIGENT LICENSE AMENDMENT APPLICATION LR-N96009 SUPPRESSION POOL COOLING E SPRAY SURVEILLANCES LCR E96-03 HOPd CREEK GENERATING STATION
] FACILITY OPERATING LICENSE NPF-57
- DOCKET NO. 50-354 I. DESCRIPTION OF THE PROPOSED CHANGES i The proposed amendment changes Surveillance Requirement (SR) 4.6.2.3.b of Technical Specification (TS) 3.6.2.3, Suppression a
Pool Cooling and SR 4.6.2.2.b of TS 3.6.2.2, Suppression Pool Spray, to reflect the intent of the specific SRs to confirm Residual Heat Removal (RHR) pump performance during Suppression Pool Cooling (SPC) and Suppression Pool Spray (SPS) operation.
The proposed changes revise the SRs to include the RHR heat
- exchanger bypass line, with the bypass valve closed, and the heat 4
exchanger in the SPS and SPC flow path used during performance of the surveillances.
The proposed change also includes a revision to the Bases of TS j 4.6.2 which adds the applicable portions of the corresponding Bases section of NUREG-1433, Revision 1, " Standard Technical Specifications, General Electric Plants, BWR/4".
II. REASON AND JUSTIFICATION FOR THE PROPOSED CHANGES Currently the two SRs state that RHR pump flow for SPC and SPS testing be through the RHR heat exchanger. The design of the Hope Creek system, unlike some older Boiling Water Reactors, includes a RHR heat exchan;er bypass line containing a bypass valve. The bypass valve is used for adjusting flow through the RHR heat exchanger and is not designed for tight shut-off. As a result of the valve design, even with the bypass valve closed, a portion of the total RHR pump flow travels through the bypass line.
The purpose of SR 4.6.2.2.b and SR 4.6.2.3.b, based on the SR's reference to 4.0.5, is to confirm RHR pump performance. This
, conclusion ic further supported by the Bases for the corresponding SRs in NUREG-1433, Revision 1. The NUREG Bases state that periodically demonstrating the required flow while operating in the SPC or SPS mode with flow through the heat exchanger ensures that pump performance has not degraded during the current cycle. It goes on to state that flow measurement is a normal test of centrifugal pump performance as required by Section XI of the ASME Code and that such a test confirms one point on the pump design curve, thereby indicative of overall pump performance. When testing for a specific flow value for pump performance, it is not imperative that flow be through the heat exchanger, but rather that a total flow measurement be performed.
Page 1 of 4
l I l 1- -
I
, Attachment 1 LR-N96009 l 4 SUPPRESSION POOL COOLING & SPRAY SURVEILLANCES LCR E96-03 )
I l
d The current SRs are not intended to confirm the heat transfer l performance of the RHR heat exchanger since there is no !
corresponding Safety Auxiliaries Cooling System (SACS) flowrate
- SR in TS Section 4.7.1. Verifying a specific flowrate through
- the shell-side of the RHR heat exchanger does not demonstrate heat removal capability in the absence of a corresponding requirement to verify SACS flow through the tube-side of the heat j exchanger. l However, operability of the system is not only predicated on an acceptable pump surveillance, but also on the system being'able to perform its safety function (i.e., heat removal capability).
The safety function of the SPC and SPS modes is to maintain containment integrity following a LOCA by preventing excessive containment temperatures and pressures, respectively. In order to ensure that the SPC safety function is maintained, testing is to be performed prior to operational condition 3 to ensure that the bypass line flow does not adversely impact the required heat removal capability of the system. PSE&G has determined, through analysis at design conditions, that a flowrate of 8985 gpm through the heat exchanger is necessary to achieve the desired SPC heat removal capability. Periodic testing will be conducted to ensure that the required flow rate through the RHR heat exchanger can be achieved during the SPC mode of operation.
Heat removal is not part of the SPS safety function, however, confirmation of heat transfer for suppression pool spray is i bounded by the verification of the heat transfer capability for suppression pool cooling. In the SPS mode, RHR flow is directed through a RHR heat exchanger which has the same heat load as when ;
in the SPC mode. Since the suppression pool supply temperature is identical for both modes of operation, the system heat load is identical.
Page 2 of 4
~
Attachment 1 LR-N96009 SUPPRESSION POOL COOLING E SPRAY SURVEILLANCES LCR H96-03 III. NO SIGNIFICANT HAZARDS EVALUATION In accordance with 10CFR50.92, Public Service Electric & Gas (PSE&G) has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes:
- 1. Will not involve a significant increase in the probability or consequences of an accident previously analyzed.
The proposed amendment request changes Surveillance Requirement (SR) 4.6.2.3.b of Technical Specification (TS) 3.6.2.3, Suppression Pool Cooling, and SR 4.6.2.2.b of TS 3.6.2.2, Suppression Pool Spray, to clarify that the intent of these specific SRs is to confirm Residual Heat Removal (RHR) pump performance during Suppression Pool Cooling (SPC) and Suppression Pool Spray (SPS) operation. The proposed change revises the SRs to include the RHR heat exchanger bypass line, with the bypass valve closed, and the RHR heat exchanger in the SPC and SPS flow path used during performance of the surveillances.
The RHR system is an accident mitigation system. The proposed changes do not change the operation or capabilities of the RHR system in either mode of operation. The proposed changes do not involve any physical changes to the RHR system. The proposed changes merely modify the acceptable flow path for the surveillance tests; the purpose of which is to verify pump performance in these modes of operation.
Therefore, the proposed change to the SRs for the SPC and SPS mode of operation of the RHR system will not increase the probability of an accident previously evaluated.
Furthermore, the performance of the RHR system in any of its operational modes will be unchanged by the proposed change.
The changes affect only the pump performance SRs for the SPC and SPS modes of RHR system operation. The surveillances being changed only modify the acceptable flow path used during the performance of the pump performance surveillances. The surveillances still verify that pump performance has not degraded to a point where the accident mitigation function of the system has been compromised.
Therefore, the proposed change will not involve an increase in the consequences of an accident previously evaluated.
Page 3 of 4
Attachment 1 LR-N96009 SUPPRESSION POOL COOLING E SPRAY SURVEILLANCES LCR M96-03
- 2. Will not create the possibility of a new or different kind of accident from any previously evaluated. l The proposed change, a clarification of the SPC and SPS mode flow paths for pump performance testing, does not result in a modification of the RHR system, change the method of SPC or SPS operation, or alter the system's effectiveness.
Suppression Pool Cooling and Containment Spray Cooling, of which Suppression Pool Spray is a part, are manually initiated actions. Existing procedures for the initiation of these two modes of operation are unchanged, including the requirement that the Low Pressure Coolant Injection valve is closed before the containment spray valves can be opened.
There are no new failure modes created by the proposed changes and no new accident initiating events are created.
Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Will not involve a significant reduction in a margin of safety.
The proposed changes do not change the operation of the RHR system in any of its modes of operation. The changes only clarify the fact that the purpose of the SRs is to confirm RHR pump performance through the most restrictive conditions of the flow patn while operating in either the SPC or SPS modes. The changed surveillances still verify that pump performance has not degraded to a point where the original design basis can not be met. In order to assure the system meets its original design basis, adequate flow through the heat exchanger during surveillance testing will be maintained. Since the function of all of the operational modes of the RHR system are unaffected by the revised surveillance test flow path, the proposed changes will maintain the existing margin of safety.
IV. CONCLUSIONS Based on the information presented above, PSE&G has concluded that there is no significant hazards consideration associated with the proposed changes.
Page 4 of 4
. -