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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
. - - - - - - - .
- 1 H
Public Service l Electric and Gas '
l Company Stiven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 - q vice President and Chief Nuclear Officer JAN 2 41990 1 NLR-N89202 '
y LCR 89-15 ,
- , United States Nuclear Regulatory Commission' Document. Control Desk t
' Washington, DC 20555 .
Gentlemen: q REQUEST FOR AMENDMENT .
.i
. HOPE CREEK GENERATING STATION 1 FACILITY OPERATING LICENSE NPF-57 ,
DOCKET NO. 50-354
-[
Public Service Electric and Gas Company (PSE&G) hereby submits a request to amend Facility Operating License--No. NPF-57 in'--
l accordance with the requirements of 10CFR50.90.
The attached License-Change Request (LCR) 89-15 revises the Radiation Protection and. Radiological Environmental Monitoring.
technical specifications. It also includes changes to reflect S the current organization, and--proposes changes.to the Nuclear Safety Review department 1 and the' Station . Operations Revi'ew Committee. ;
Pursuant to the requirements of 10CFR50.91(b) (1), a copy of this
- requent for amendment has been sent to the State.of New Jersey as i indicated below.
Sincerely,
,, ' // / ~ -h.
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I Attachment' i
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l 9002050029.900124 -
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PDR ADOCK.05000354~ !
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Document Control Desk- 2
'NLR-N89202 : . JAN 2 4 1600- ,
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C Mr.'C. Y. Shiraki j Licensing Project Manager ,
i Mr. T. Johnson Senior / Resident Inspector:
.Mr.-W. T.. Russell, Administrator l Region I Mr. Kent Tosch, Chief New Jersey Department of. Environmental Protection Division of Environmental Quality ,
. Bureau of Nuclear Engineering.
CN 415 Trenton, NJ ' 08625 i
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STATE OF NEW JERSEY )'
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i S.'Miltenberger, being duly sworn according to law-deposes.and.
says:
I am Vice President!and Chief Nuclear, Officer.of Public. Service Electric and Gas-Company, and as such,-I find the-matters. set forth in our letter dated January 24,.'1990 , concerning the-Hope Creek Generating Station,.areLtrue-to-theibest of my ]j knowledge, information and belief.
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- ~bduY,,A- 1
- l. .i Subscribed and Sworn to before me d
, this 8bd. . day of b oa; u l
,.1990 l
W16' b. hillAAb AAd Notary Public of New Jersey _
l -
1/ANITA M. MARSHALL - ,
j NOTARY PUS!.10 0F NEW JERSEY .i Ny Commisska Expiros May 6,1993 =
My Commission expires on-i 4
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-LCR 89-15 s
NLR-N89202 l!
ATTACHMENT
. PROPOSED CHANGE TO THE TECHNICAL SPECIFICATIONS:
7ACILITY OPERATING LICENSE NO.'NPF-57-' ;
HOPE CREEK GENERATING STATION DOCKET-NO. 50-354 '
I. Descriotion of Chance
]
The proposed-amendment to the Hope Creek Generating l Station Technical Specifications (TSs) extensively revises-Section 6.0,
'" Administrative controls."
The changes are as follows:
- 1. Revise Tables-3.12.1-2 and 4.12.1-1:to change the reporting' levels'and-lower limits of detection of radioactivity i concentrations of I-131 for the radiological' environmental '
monitoring program.- The changes, will. allow higher activity 9 levels.provided that drinking water pathwaystare' noti involved.
j ;
- 2. Change " General Manager -Nuclear Safety' Review" to " General i Manager - Quality Assurance and Nuclear Safety"'throughout-Chapter 6.
- 3. Revise Section 6.2.2 to delete SpecifiOation 6.2.2 (c),
delete footnote, and provide editorial corrections; 1 Revise Table 6.2.2-1 to include'theLuinimum shift staffing requirements for.the radiation protection technician.
- 4. Revise Section 6.3.1 to read "..., except for the-individual designated as the Radiation Protection Manager..." Add insert 6.3.2, previously' item 6.2.2.f. Delete the position I of Senior Operating Supervisor from Section.6.3.2.
5.
Revise Section 6.4.1 to replace reference [toL10 CFR Part 55, Appendix A and supplemental requirements, with a general ;
reference to 10 CFR Part 55.
- 6. Revise Sections 6.5.1.2, 6.5.1.3 and 6.5.1.5 to change the SORC composition'and rules'concerning alternate members and j quorum requirements, respectively, o
- 7. Revise Section 6.5.1.6 to simplify'the SORC responsibilities with respect to internal distribution of reports and- i performance of reviews and investigations.. ; Revise Specification 6.5.1.6(a) to. require SORC review 'oftprocedure !
changes only if a 10CFR50.59, safety: evaluation is required.
Revise Specification 6.5.1.'6(j) L to require ~ SORC review of changes to the Facility Security Plan'and-implementing procedures only if a 10CFR50.39 safety' evaluation is required -(or an evaluation under 10CFR50.54(p) for Security i
Page 1 of 8
l-LCR'89-15; NLR-N89202:
o Plan changes). ' Revise Specification'6.5.1.6(k) and' ['
-6.5.1.6(1) to require SORC review of changes to the ll' J Emergency Plan or Fire Protection-Plan and.their. "(
- i. implementing procedures only-if'a'10CFR50.59Esafety .
evaluation is required - (or an evaluation; under :10CFR50.54 (q) ,
for Emergency Plan Changes).. Delete the; -i L phrase "and the Radwaste-Treatment Systems" from section-6.5.1.6(n). Revise Specification . 6.5.3.2 (d); to replace the >
reference to significant safety issues with as referenceito-
'10CFR50.59.
3 j
Provide editorial clarification to' Specification 6;5.1.8(a),.
with regard to SORC recommendations.of approval or disapproval of items:to the General ~ Manager? ' Hope Creek
~
operations.- ,
- 8. Revise Section 6.5.2 to. reflect the proposed;N'uclear Safety ~ q department configuration. :The Manager - Offsite. Safety a Reviewfand the Manager - Onsite--Safety Review will be: >
replaced.by the Manager NuclearLSafety, who will'!have management responsibility:for both the Offsite Safety: Review
~
(OSR) staff and the Onsite Safety Review Group (SRG) .-
{
- 9. Revise Section 6.5.2.3 to. clarify the use-of consultantsLbyl j the Nuclear Safety Department. Provide l editorial revisions 'l to Section 6.5.2.4. 4
- 10. Revise Section'6.5.3 to replace "NSR"/with "the OSRl staff".-
- 11. Revise Sections 6.9.1, 6.9.2 and 6.9.3ito refer >specifically- .;
to the USNRC . Administrator, Region:I. : Revise :Section =l 6.9.1.4 to delete-requirements for submittal'of therinitial.
~ '
Annual Report.
q
- 12. Revise Section 6.9.1.5 to replace;"filmfbadge measurements" with "self-reading dosimeter, measurements." -;
- 13. - Revise the requirements of - Section 6.9.1.6 : regarding . ,
radiological ~ sampling' location maps ~ submitted with the Annual Radiological Environmental OperatingsReport.
- 14. ' Revise'Section 6.10.3 to reflect'the. succession of the Nuclear. Safety Review by the;Offsite SafetysReview staff and ';'
to provide editorial corrections.
- 15. Revise Section 6.12'.1 to reference 10CFR20.20'3 (c) (4) , which - q
-allows a high 3 radiation area' established forLthirty days orf j less to be controlled via direct surveillance.- :'
16 . . Revise Section 6.15.1 to change "FSAR" to "UFSAR" and to provide editorial corrections.
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Page 2'of 8 4 g
LCR 89-15.
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NLR-N89202 II. Reason for the Prooosed Chance
- This LCR is being submitted to reflect'the recent management reorganization and to propose additionalichanges to
. administrative controls. The reasons for tho; specific changes are as follows:
- 1. .The changes are consistent with.NUREG10472i " Standard.
Radiological Effluent Technical Specifications;for Pressurized Water Reactors,"~ Revision 3,; draft. 'The currenti values of allowable' activity levels for I-131'are. based on- j 40CFR141 limits for drinking water pathways. ~ Where'such; 'i pathways are not potentially affected,- it is proposed that I the' limits be increased. As discussed intthe Justification. I section below, these changes do not affect' compliance of: ]
'PSE&G's Radiological Environmental Monitoring Program with" 'I 10CFR20. I
- 2. In the current organization, the General. Manager - Quality < q Assurance and Nuclear Safety-Review has replaced 1the General. ;
Manager - Nuclear Safety Reviewiwith regard'to l responsibility for the Onsite and'Offsite SafetyLReview 1 Groups. This License Change Request proposes' changing.the- j title'to " General Manager - Quality Assurance and Nuclear Safety" to more accurately reflect the responsibilities of-the position (i.e., safety related review and audit ;
functions). '
l 3. " Radiation protection technician"'is beingradded:toLTable' i l
6.2.2-1 to be consistent with the current requirement 1 (Specification 6.2.2(c)) to have a technician'present whenever fuel ic in the reactor. Specification 6.2.2 (c) is being deleted to eliminate redundancy lto revised Table 6.2.2-1.
- 4. The Radiation. Protection Manager is required.to. meet ~or exceed the personnel qualifications"criteriafof' Regulatory Guide 1.8., Insert Item 6.3.2,-previouslyJItem'6.2.2.f.
This is actually a qualifications item and-belongs as'part.
of the UNIT STAFF QUALIFICATIONS, Section 6.3. The. position.
of Senior Operating Supervisor is deleted due to reassessment and reallocation of resources. l
- 5. Appendix A to 10CFR Part 55 has'been deleted. The U requirements for the operator'requalification program formerly contained in 10CFR55 Appendix A are now contained in 10CFR55.59. The: proposed change references the applicable requirements (i.e., 10CFR'Part 55)-and reduces the likelihood of requiring an additional Technical Specification change by not being too specific. Operator l
requalification is still performed in accordance'with'the NRC-approved requalification program.
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LCR 89-15 ,
NLR-N89202
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- 6. The title " Assistant General Manager . Hope Creek-Operations". position has been deleted in the recent reorganization. Other changes.to.the SORC composition are being.made to assure that SORC meetings provide for equitable rapresentation_of the. Hope Creek Station departments. :Ry planing restrictions:on the:use of
, alternate members and quorum composition;'the. proposed change:willTrequire.that at least three departments.are.
represented in the voting quorum for any'given SORC meeting.
'The SORC responsibilities of Section.6.5.1.6 are.being'
- 7. i revised to1 delete; references,to internal distribution of l reports, which is addressed more appropriately 7in other sections. . For example, Sectionf6.5.1.9' addresses.
distribution of SORC meeting'ainutes to the General Manager
- QA and Nuclear Safety; Review;and'to:theLVice President and Chief. Nuclear: Officer;cSection 6.5.2 addresses the Nuclear Safety Department's review responsibilities;.-Section 6.5.3 '
q addresses review and control.of activities'in general. n
.Therefore,; references-to SORC: interfaces-with other Nuclear: R Department entities are being removed from'Section <5.5.1.6.
i specifications 6.5.1.6(a) and 6.5.3.2(d) are being revised to reflect PSE&G's intention'to discontinue use.of the significant safety issue determination in favor'of _,
consolidating the procedure revision screening'and review '
process!under the' requirements of'10CFR50.59. 4 Current Specifications.6.5.1.6(j), 6.5.1.6(k), and 6.5.1.6(1) require SORC' review'of all-changes 1to the' i Security Plan, Emergency Plan,Jand Fire Protection Program '
Plan respectively,'and'their implementing procedures. 1The ,
phrase."and the Radwaste Treatment Systems" isideleted fromi l section 6.5.'1.6(n) since SORC' reviews'of-changes t'lRadwaste-o d Treatment Systems for: nuclear. safety are-conducted under
.Section 6. 5.'1'. 6 (d) and.6.5.1.6(e)'. -The; proposed. change is- 1 intended to waive SORC' review if:the revisions are not safety significant. .This will1 eliminate ~unnecessaryxSORC
- reviews of revisions that.are editorial /or'are'otherwise, .
insignificant'with' respect'to safety. ]
- 8. Section 6.5.2 currently describes the Onsite Safety Review '
Group (SRG)<as consisting of the1Onsite Safety Review 3 Engineer and three dedicated, full time engineers._ d The Onsite Safety Review Engineer.currentlyihas review-as-2 well as management responsibilities within'the-Onsite Safety l Review Group (SRG)'. However, PSE&G'is-proposing to< replace = j the position of. Manager l 'Offsite Safety Review 1with that of' 'y Manager - Nuclear Safety, who;wil1~have management i responsibility for both the<Onsite Safety Review Group (SRG). e and the Offsite Safety Review staff (OSR). In this proposed .
configuration, the SRG.and OSR' staff will each-consist of at i least four full time dedicated engineers.
I s Page 4 of 8 l
l e li LCR 89-15. j NLR-N89202 L 9.. The revision to Section 6.5.2.3 provides more flexibility-to-the Nuclear Safety-Department _withcrogard to the usetof .i outside consultants / experts. Per Section 6.5.2.2, reviewers from organizations external to-the Nuclear Safety Department- .
L are required to-meet the'same qualification requirementscas z +
L the OSR staff.
- 10. . "NSR"'is being replaced by "the OSR staff" inLSection 6.5.3 I because the 10CER50.59' review activities described'therein are performed specifically by theLOffsite. Safety Review t (OSR) staff,Jwhich is:part'of.the Nuclear Safety! Department. ;
L
- 11. The changes are administrative.in nature. Referencesito the ,
initial submittal of the Annual report are being: deleted-since the reports have already been submitted for Hope i creek.
- 12. TLDs are our primary dosimetry' devices. "Self reading f' dosimeter"Lis more accurate than." film: badge";when' .
describing dosimetry.used at' Hope-Creek.. We have added ;
Digital Alarming Dosimeters to-enhance our' dose tracking a' capability. ,
~
13 . - This revision provides more specific'information.on .
t radiological: sampling location maps. . Dedicating one map to.
locations near the site boundary and another tocinclude=all locations assures that the maps will1be scaled such that they are legible. r
- 14. "OSR" is.the applicable group-in the current' organizational '
- configaration; the Nuclear Safety Review no longer exists.
~
- 15. When a high radiation area-is-established for a short period.
of time (i.e., 30 days or less), it'is~often more-practical to control the area using direct surveillance.than to erect a barricade surrounding the area. Thiszapproach'is.
consistent with 10CFR20.203 (c) (4) .~ ,,
- 16. " Updated Final Safety Analysis Report"' (UFSAR) :is the document relevant to Section 6.15.1.
III. Justification for the Pronosed Chance-The changes proposed in this IIR may. be cat'egorized and justified.
as.follows:
- a. o Changes related to PSE&G's organizati'nal configuration, ;
which reflect titular changes, changes in management' responsibility, changes: to the SORC 'and those: included in ;
item nos. 2, 3, 4, 5, 6, 7, 8, 10 and.14. This category is ~
administrative in nature and does not adversely impact l management attentiveness to safety operation of the Hope l- ,
Page 5 of 8 d
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'LCR 89-15 ~
NIR-N89202:
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Creek Generating Station'. The recent reorganization of PSE&G's Nuclear Department is-intended to increase overall management effectiveness,t in some cases by consolidating-oversight of?related activities.- For example, quality assurance and nuclear: safety. review and' audit activities will both be under the direction of one general-manager.' ;
1The Manager - Nuclear Safety will assume-management . q responsibility'of.the Onsite-Safety Review staff, thereby-allowing the Onsite Safety Review Engineer to' dedicate-his efforts to review activities.
The changes to SORC composition and voting quorum. i requirements will increase.the level of assurance thatfthe l various Station departments are adequately; represented-in the-SORC quorum.. By1 placing a two vote per' department limit on the quorum and restricting the use of alternates,.at least three departments will; comprise the quorum of each SORC meeting.
1 This-category includes the'proposedLchange to require SORC ']
review for procedure changes and. changes to the Security: S Plan, Emergency Plan and Fire Protection Program' Plan:only .L!
F if a 10CFR50.59 safety evaluation is involved. ~This j approach-will consolidate.the screening and review process l for procedure changes by doingnaway with theJsignificant- q safety issue' determination currentlyLin userat the Hope'. .
Creek Generating Station. Screening for' safety' significance i l will be performed'by determining-10CFR50.59l applicability !
(10CFR50.54 (p) for Security' Plan . changes and!10CFR50.54 (q) !
for Emergency Plan changes) , which- is consistent with ,NRC i regulations _regarding procedure changes (10CFR50.59_and-J' 10CFR50.54).
- b. PSE&G's current practice of preparing and= submitting the l Annual Radiological Environmental Operating! Report includes ;
the two sampling location maps explicitly. described by.the. l l proposed change (item no. '13). This.-LCR clarifies the' l current practice, which'is acceptable to'the NRC, in order '
to_ remove any ambiguity from the Technical-Specifications. i I
- c. The change to the-method of preventing unauthorized access I l to'high radiation' areas-established for-thirty' days or less L!
I is in direct compliance with 10CFR20;203 (c) (4) . - The' change 1 is being requested in order to address those cases where itf- 1 is more feasible to use direct surveillance, instead of a physical. barrier, to provide access control (item no. 15).
'd. Changes to reporting levels of radioactivity concentrations 1 and lower limits of detection"(LLD)1for the radiological! l environmental monitoring program are consistent'with'NUREG 0472,f" Standard Radiological Environmental Technical j Specification for Pressurized Water Reactors",, Revision 3, '
l draft-(item 1). These changes propose allowing higher ;
r Page 6 of 8 i
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c LCR 89-151 NLR-N89202.
levels'of'I-131 if'a' drinking' water: pathway-is not potentially affected by.the. effluent 1being monitored. . The: (
provisions of 40CFR141 will stillibe compiled with where H applicable. '10CFR20.106 requires that-effluents released to j
. unrestricted. areas are maintained within the~ limits-of n
. Appendix B,: Table.II of 10CFR20. Table.II specifies a111mit, I of .300 pCi/1 for soluble 'I-131 and1 60,000 pci/1 for the ,
. insoluble form. Using 300.pci/1 for comparison purposes,c <
'the proposed reporting-level andLLLD for I-131~are :
respectively'6.7% and 3.34'of-the Table II;11mits.- l Therefore, the proposed' changes =willinot'affectLcompliance with 10CFR20.106 and will' not allow for an increase irr :( '
radiation' dose to any. member of the public.
- e. Changesito the description of Nuclear'SafetyjReview (NSR) i responsibilities (item nos. 8, : 9, - 10) . . These changes: _ d include consolidating the management 1oflthe Offsite and' L Onsite Safety Review Groups and revising the description 1of- .,
NSR' activities to increase specificity.and' eliminate !
redundancy. ,
Changes in this category will'not les en~the' scope of-NSR activitiesLand will increase the effectiveness of the'onsite -
Safety Review Group by allowing the-Onsite Safety Review-
~ '
Engineer to dedicate lhisitime to review activities,.since the Manager - Nuclear Safety l will'have management' .
responsibility. None of the changes;in this'. category will reduce.the effectiveness of NSR reviewland audit functions. 1
- f. Changes deleting references to outdated requirementsLor +
documents are justified on the basis that'they are:largely editorial and provide clarification without: reducing'any commitments (item nos. 4,.11,.12, 16 ) '.
IV. Sianificant Hazards Analysis Consideration-l The proposed changes to the TechnicaliSpecifications: l l 1. Do not involve a significant increase in thel probability or j l consequences of an accident previously evaluated.
Those proposed change which are administrative in nature'do- ',
not impact any accident analyses'used to support operation-of the Nuclear Generating l Stations. Furthermore, the proposed changes do not involve any reduction in management effectiveness, nor do they adversely' affect:the. design:or: <
operation of any systems or components'important to-safety.
l Consequently, the reliability:of the performance of plant j safety' functions is not adversely affected..
The proposed increases to the reporting levels of radioactivity and lower limits of detection for I-131 (Section 3/4.12).do not~ increase 1the probability or Page 7 of:8
y LCR 89-15 NLR-N89202 consequences of an accident. Since the current. values are- ]
~
based on 40CFR141 requirements for drinking water supplies,- 1 this proposed change revises thoserlevels in; cases where no I drinking water pathways are-potentially.affected. The j reporting levels and LLD for I-131 will continue'to be a- q small fraction of the levels allowed by 10CFR20. ;
i Therefore, it'may be concluded'that the proposed changes do not involve a significant increase in the probability or.
consequences of an accident previously evaluated.
- 2. Do not create the. possibility.of'a new'or different kind of accident-from any accident previously evaluated..
i The proposed changes'do not. adversely affect the design or operation of any. systems or components.importantLtoJsafety.
No physical plant modifications or new operational
] .
configurations will'resultifrom these proposed changes. !
, .Therefore, it may be concluded that the proposed L changes do 1 I
not create the possibility.of a new or different kind of t accident from any previously: evaluated. <
- 3. Do not involve a significant reduction in a. margin of:
safety.
The revision of' radiological environmental' monitoring.
parameters discussed in Section IV.1 above, the1 changes proposed herein potentially affecting parametersidefining margins of safety affect only their administrative! aspects? "
and do not-allow for any reduction in'a margin 1of safety..
The proposed change to the radiological environmental f monitoring program does not' involve a significant' reduction-in a margin-of safety. -The program will still1 implement 1 l l Section IV.B to.10CFR50, Appendix I.. As str.ted above, the -
changes do not affect.the limits specified by:10CFR20.; The proposed change deletes'radioactivityLeoncentration' values i
associated with 40CFR141 in casesswhere:it is'notiapplicable (i.e., no drinking water pathways are involved)'. LTherefore, :;
1 1 it may be concluded that the proposed changes do not involve. 4 a significant reduction inLa margin of safety. l
' V. Conclusions As discussed above, PSE&G has concluded that the proposed changes n to the Technical Specifications do not. involve a significant- -
hazards concentration since the changes .(1) do not involve' a significant increase in the probability or consequences ~of an. 3 accident previously evaluated, (ii) do not create.the' possibility -
of a new <n different kind of accident ~from any accident '
previously evaluated, and1(iii)'do not' involve a significant reduction in a margin of safety. i Page 8 of 8 ,
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