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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
,_-
db - % A. g Public Service Electric and Gas Cornpany Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 Senior Vice President -
Nudar May 22, 1987 NLR-N87091
. United States _ Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10 CFR 50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10 CFR 170.21, a check in the amount of $150.00 '
is enclosed. In accordance_ with the requirements of 10 CFR 50.91(b)(1), a copy of this request has been sent to the State of New Jersey as indicated below.
This amendment request revises Technical Specification Table 2.2.1-1, 3.3.2-1 and 3.3.2-2 for the Main Steam Line Radiation -
High - High full power radiation background levels and.
associated trip setpoints (see Attachment 2). These changes permit PSE&G to test the feasibility of a Hydrogen Water Chemistry System as a mitigator of Intergranular Stress Corrosion Cracking (IGSCC) of stainless steel recirculation-piping at HCGS. Attachment I contains further' discussion and justification for these proposed revisions. This submittal includes one (1) signed original, including affidavit, and thirty-seven (37) copies pursuant to 10 CPR 50.4(b)(2)(ii).
Should you have any questions on the subject transmittal, please do not hesitate to contact us.
Sincerely, l
p Encicsure (check) j} 4( 0\
Affidavit r Attachments (2) [L 9 B705290122 B70522 PDR ADOCK 05000354 1 P PDR i L
- . . . .- - - . . .. . _ . = . .
l Document' Control' Desk 2 5-22-87 i
C' Mr. G. W. Rivenbark' USNRC Licensing Project Manager.
Mr. R. W. Borchardt USNRC Senior Resident Inspector 1 .
Mr. D. M.. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection
-380 Scotch Road Trenton, NJ 08628 i'
i 4
+
4
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1 i
. . -_, _ _ . ,_,. _ .u- _. _ . _ , . . , , , . . _ . . . . . , _ . ._, . _ _ _ _ -,_ _ , _ , .,... . ._
7-.
=. .#
Ref: HCGS LCR 87-08
-STATE OF NEW JERSEY -)
) SS.
COUNTY OF SALEM )
~
Corbin'A..McNeill, Jr.,_being' duly sworn according to law deposes
- and says:
I.am Senior Vice President of Public Service Electric and Gas Company, and as such, I find :the matters set forth in' our letter dated May 22, 1987 , concerning Hope Creek Generating Station License Change Request 87-08, are true to the best of my knowledge, information and belief.
A s N Subscribje and Sworn to before,me this 2d day of M 1987 d'
)
+~~ 7%
c(Notary Puplic of New Jersey lARMNE Y. BEARD Notory Public of New Jersey My Commission Empires May 1,1991 My-Commission expires on
,y - y , ,
.- 3 4
l e Attachment 1 i PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS LCR 87-08 HOPE CREEK GENERATING STATION Page 1/6
- FACILITY OPERATI'NG LICENSE NPF-57
. DOCKET NO. 50-354 I
i I. Description of the Chance Revise Technical Specification ( TS) Table 2. 2.1 -1, Reactor Protection System Instrumentation Setpoints. Table 3.3.2-1 Isolation Actuation Instrumentation and Table 3.3.2-2, Isolation Instrumentation Setpoints to footnote a discussion regarding the hydrogen injection test and its affect on the Main Steam Line Radiation - High High trip function.
l These revisions will temporarily permit full power radiation background levels and trip'setpoints to be changed based on either calculations or measurements of actual radiation levels resulting from the hydrogen injection test discussed below.
4
{
II. Reason for the Chance Public Service Electric and Gas Company ( PSE&G) intends to i'
perform a hydrogen injection test ( currently scheduled for the late July, 1987) on the primary coolant' system at Hope Creek Generating Station ( HCGS) . The purpose of'this-test '
! is to tetermine the feasibility of hydrogen water chemistry 4 contrci as a means of reducing Intergranular Stress
- i Corrosion Cracking (IGSCC) of stainless steel piping.
l The test involves the addition of hydrogen to the primary
? coolant at increasing increments over a range of l approximately 0 to 70 standard. cubic feet per minute - ( scf m) .
As a result, the radiolysis of water is suppressed, thereby lowering the free oxygen content in the reactor coolant.
- The reduction of free oxygen eliminates one of the necessary ,
causative agents of IGSCC ( see Final Safety Analysis Report '
( FS AR) Section 5.2.3),
f A by-product of oxygen suppression by hydrogen addition'is l an increase of radiation levels from the main steam lines l caused by Nitrogen-16 ( N-16) . The increased carry-over of l nitrogen is due to a conversion of N-16 from a soluble-form ,
to a gaseous form'in the reactor. The requested revisions !
to the TS tables, identified above and included in ' this
! transmittal as Attachment 2, permit a temporary increase in the Main Steam Line Radiation - High '- 'High scram and
, isolation setpoints to allow operation with expected higher i l
radiation levels resulting from hydrogen injection. The l
! Main' Steam Line' Radiation - High - High'setpoint will remain ,
I i at 3 times the background level and the allowable value will remain at 3.C times the background. level; however, the l
) background radiation level used to determine these setpointa j i
)
I i.
i
. _ ..~.,. _ ,.____ _ ._. _ . _ . _ _ , . . . .. - ,__,,,._. __.- _ _.,_ ..-- ,. _ - , _- , _ , . .
h t
i LCR 87-08 Page 2/6 will be increased prior to the' hydrogen injection test based l - on a calculation of the anticipated background level. The ,
4 changes also permit the full load background radiation level
- to be adjusted during the testito correct for uncertainties in the initial computation. At'the maximum planned hydrogen injection rate, an increase of approximately.one to five times the normal main steam line' background radiation levels is expected. The pretest main steam line radiation monitor setpoints will be restored promptly following the conclusion of the hydrogen injection. test and whenever power is decreased to less than 22% of rated thermal power ( this latter restriction is in accordance with guidance provi de d in References 1 and 2). The hydrogen injection -test .will be -
i discontinued whenever reactor power is reduced to less than 22%.of rated thermal power.
i
) i i III. Hydrocen Test Summarv 4
- PSE&G has decided to employ an experienced contractor to develop, prepare and execute the hydrogen injection test under the management of HCGS personnel. The contract'has not yet been awarded, although contractor selection is-
, expected during the month of May 1987; therefore, complete l test details have not yet been finalized. However, the i following information is available on the test itself:
- 1) Rated thermal power at least 90 percent in order to develop full-power radiation background levels i and optimize hydrogen effectiveness,
- 2) Hydrogen will be supplied from a tank truck
- outside the turbine building near the condensate l storage tank ( CST), to the turbine building i through flex hosing and/or tubing,
- 3) Hydrogen injection points into the feedwater i system will be on the suction side of the i secondary condensate pumps,
! 4) Radiation levels will be monitored at various
! points inside HCGS ( such as the administrative
- offices, the turbine deck, the control room and at l selected points within the plant) as well as outside the plant ( such as the administration building, parking lots and at various points in l the site boundary and immediate general population areas) using monitors already in place and -
l additional monitors if required, i
- 5) Oxygen will be added to the offgas system prior to entering the catalytic recombiners to
4 1
1- LCR 87-08 Page 3/6 scavenge.any free hydrogen and minimize: hydrogen build-up, These details have been developed'as general guidelines and 4
were included in request . for proposals - f rom contractor's.
- Further refinement of these details, as well as additional ~
test information, will utilize the experience of'the contractor selected. PSE&G is also working with. selected r utilities which have previously performed a hydrogen water chemistry test,. including Carolina Power . and Light. Company's Brunswi'ck -Station and Georgia Power Company's Hatch Station, such that the HCGS test incorporates useful experiences and I
averts unnecessary' problems.
I V. Environmental 'moact Annraisal and Onsite Dose Imnact 4
From an analysis of previous tests, radiation levels can be expected to-increase approximately one- to five-fold.
Therefore, extensive radiatio preplanning willcidentify the proper areas to monitor radiation levels. During the test radiation surveys will be conducted at regular intervals to monitor the actual doses. The surveys will . be performed by qualified PSE&G Radiation Protection technicians using approved site procedures. The objectives of the survey 4
program will be:
- 1) To provide data for shielding design should additional shielding be necessary,
- 2) To determine radiation levels in and around the facility as well as at the site boundaries, I
- 3) To determine the potential effects on operation
- and maintainence a c ti vi ti e s , and,
! l j 4) To determine the impact on the site ALARA ( as low as reasonably achievable) program.
k As stated in Paragraph II above, the increased radiation )
) levels are a result of an increased carry-over of N-16 in
- j. the main steam, not from increased N-16 production. Due to 1
the short half-life of N-16 ( approximately' 7 seconds), PSE&G
.does not expect hydrogen injection to have a significant effect on the gaseous effluent release rates. Therefore, i .the increased radiation levels will have no discernible effect on the health and safety of the public. This'will be confirmed during the test through the~use of offsite
} monitors. Radiation protection measures will be implemented I to maintain doses to plant personnel ALARA. These measures include:
l
l !
1 LCR 87-08 Page 4/6 l
- 1) Scheduling the test'during a weekend and at nights to the extent feasible in order to minimize the number of on-site-peraonnel affected. l l
- 2) Establishing access control by Radiation :i I
Protection personnel in accordance-with existing site procedures, and,.
- 3) Training of operations personnel in test j- procedures prior to ths start of'the test to ensure-efficient performance of duties.
- V. protective Measures Reaardina Hydrocen I
}i Compressed hydrogen will.be supplied to the plant site in gaseous form via tube trailer. The tube trailer will'be 3
! located in accordance with the requirements of NFPA. Code No.
50A, " Gaseous Hydrogen Systems at Consumer Sites," Section
- 5. 0, outside the turbine building near CST. A detailed ;
review of the . hydrogen water chemistry test will be performed to insure proper bulk storage of hydrogen onsite during the test. This review will included an assessment of 4
10 CFR 50.59'to determined whether there ara any unreviewed i safety questions involved.
The hydrogen control and distribution system consists of supply lines, control valves, a safety relief valve, an j excess flow check valve, a safety valve and a mechanical
- pipe break valve ( Ref. 2). The supply line will be routed i outdoors from'the supply trailer to the turbine building 1 ~
using high pressure flex hose and/or tubing. .The 1ines will i then be routed to the condensate booster pump rooms. The i hydrogen supply system will be leak tested and purged with l an appropriate gas prior to the introduction'of hydrogen.
l To further ensure that comuustible levels of hydrogen are not reached due to leakage, hydrogen area monitors will be utilized during the test ( Ref. 2). The hydrogen monitors will be located in various locations, such~as at the
, condensate booster pumps, near the control valves and/or at various locations along the supply line. The monitors will l' alarm when hydrogen concentration exceeds 2 percent end isolate the hydrogen supply when concentration reaches 4 l percent in order to prevent an explosive concentration from being reached.
1 PSE&G hac determined that the hydrogen supply and distribution system meets thw requirements of Section C. S. d( 2) of Branch Technical Position CMEB 9.5-1, NUREG-0800 (see FSAR Sections 9. 5.1.1.11 ' and 9. 5.1. 6) .
4
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LCR 87-08 Page 5/6 VI. Sionificant Hazards Analysis The proposed changes to the HCGS Technical Specifications:
a) Do not involve a significant increase in the ,
probability or consequences of an accident previously evo.uated. The only design basis accident which takes cr'.it for the main steam line high radiation scram and isolation setpoint is the Control Rod Drop Accident ( CRDA) as described in FSAR Section 15. 4. 9. Specifically, the Main Steam Isolation Valves ( MSIVs) are assumed to receive an LCR automatic closure signal at 0.5 seconds after detection of high radiation in the main steam lines and to be fully closed at 5 seconds from the receipt of the closure signal.
The main steam line radiation monitors are provided to detect a gross failure of the fuel cladding. When high radiation is detected, a trip is initiated to reduce the continued failure of fuel cladding. At the same time, the main steam isolation valves are closed to limit the release of fission products. The trip setting is high enough above background radiation levels to prevent spurious trips yet low enough to promptly detect gross failures in the fuel cladding.
As indicated in the NEDO Report ( Ref erence 1), the consequences of the CRDA are most severe under Hot Standby conditions. In fact, the consequences of the CRDA are increasingly less severe above 10 percent power due to a faster Doppler response and a lower rodworth. Most importantly, above 20 percent power, the consequences of the CRDA are minimal. Since the Main Steam Line Radiation Monitor setpoint will only be adjusted for the purposes of the hydrogen injection test at power levels above 22 percent, there is no significant impact on the probability or consequences of the CRDA. Therefore, the change to the footnotes in the referenced TS tables have no affect on the probability or consequences of an accident pre vi o usly evaluated.
b) Does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not affect the design of any safety-related systems and as such do not affect the performance of any safety functions. The proposed changes do permit the performance of a hydrogen injection test; however, this test does not introduce a new kind of accident since the presence of hydrogen in the primary system has already been analyzed ( see PSAR Section 6.2.5, 10.4.2 and 11.3.2.1) and is already monitored and controlled ( see TS 3/4.3.7.10 and 3/4.11.2.6, re s pe c t i vel y) . Further, as discussed in Paragraph V above, additional protective measures are being applied which assure that the physical
LCR 87-08 Page 6/6 l
presence of test equipment does not create the potential for i a different kind of accident to occur.
Since the TS changes themselves do not affect existing :
- system function, nor do they create a situation which has not been previously analyzed and appropriately designed for,
- the change to the TS footnotes shown in Attachment 2 do not create new or different accidents than previously evaluated.
c) Does not involve a significant reduction in a margin of
- safety. The proposed temporary. increase in the Main Steam
- Line. Radiation - High - High scram and isolation setpoints will be permissable only when reactor thermal power is above
- - 22 percent. As discussed in Paragraph VI.a above, the only design basis accident which takes credit for this scram and
! isolation trip function is-the.CRDA. However,.above 20
- percent power, the consequences of a CRDA are so minimal that they may be considered negligible ( Ref. 1), and hence, the change in the TS setpoints has no significant effect on i the margins of safety for this accident scenerio.
The proposed change is-necessary to conduct a hydrogen injection test which will increase the carry-over of N-16.
This in turn, will cause the background radiation levels in the main steam system to be i ncreased. As discussed in l Paragraph IV above, several precautionary and preplanning l measures are being taken to maintain plant personnel j exposures ALARA. In addition, radiation levels will be monitored to assure measured radiation levels are within acceptable site ALARA. Due to the relatively short half-life of N-16 ( approximately 7 seconds), gaseous
! effluent release rates will not be significantly affected, i
Therefore, it can be concluded that the proposed change will not present a risk to the public health and safety nor significantly reduce a margin'of safety for plant personnel.
Based upon the discussions in the above three subparagraphs, l PSE&G concludes that the proposed change does not involve a
! significant safety hazard.
VII. References l
- 1. NEDO-10527, Supplement 1, " General Electric Rod Drop Accident Analysis for Large Boiling Water Reactors" dated July 1972. .
l 2. EPRI Report NP-4500-SR-LD, " Guidelines for Permanent BWR-Hydrogen Water Chemistry Installations" dated March 1986, i
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Attachment 2 LCR 87-08 This attachment contains copies of the Hope Creek Generating Station Technical Specifications, from Facility Operating License NPF-57, which require revision to support the proposed changes discussed in Attachment 1. Revisions are highlighted within balloon enclosures on the existing Technical Specification pages or are typed on separate insert pages. Tho following pages are affected and enclosed within this attachment:
Table 2.2.1-1 Page 2-4, and Page 2-5 Table 3.3.2-1 Page 3/4 3-12, Page 3/4 3-16, and A separate Insert Page for Page 3/4 3-16 Table 3.3.2-2 Page 3/4 3-22, and Page 3/4 3-25 l
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