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| COUNTY OF SALEM ) | | COUNTY OF SALEM ) |
| Corbin A. McNeill, Jr., being duly sworn according to lau deposes and says: | | Corbin A. McNeill, Jr., being duly sworn according to lau deposes and says: |
| 7 am Senior Vice President of'Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated November 25, 1987 , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, are true to the best of my knowledge, information and belief. | | 7 am Senior Vice President of'Public Service Electric and Gas Company, and as such, I find the matters set forth in our {{letter dated|date=November 25, 1987|text=letter dated November 25, 1987}} , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, are true to the best of my knowledge, information and belief. |
| w SubscribeJ this 15 and day Sworn of to | | w SubscribeJ this 15 and day Sworn of to |
| /Abefore A ,me 1987 | | /Abefore A ,me 1987 |
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Line 54: |
| This revision will provide extended service life of FRVS charcoal and facilitate maintenance activities in the reactor building and control room areas while still meeting the efficiencies st 'ed in the FSAR and ensuring continued compliance with the requirements of Regulatory Guide 1.52. | | This revision will provide extended service life of FRVS charcoal and facilitate maintenance activities in the reactor building and control room areas while still meeting the efficiencies st 'ed in the FSAR and ensuring continued compliance with the requirements of Regulatory Guide 1.52. |
| The values proposed are consistent with the charcoal l | | The values proposed are consistent with the charcoal l |
| testing criteria clarification provided by William Gammil, Chief of the Effluent Treatment Systems Branch, in his letter dated September 24, 1981 (see Attachment 3). In this clarification, Mr. Gammill states that acceptance criteria should be based on the accident analysis. | | testing criteria clarification provided by William Gammil, Chief of the Effluent Treatment Systems Branch, in his {{letter dated|date=September 24, 1981|text=letter dated September 24, 1981}} (see Attachment 3). In this clarification, Mr. Gammill states that acceptance criteria should be based on the accident analysis. |
| l The proposed change incorporates an 80% value into the FRVS Recirculation laboratory testing criteria by allowing a 7.5% penetration (by interpolation of the clarification in Mr. Gamill's letter). For the overall FRVS, Sections 6.8 of the Hope Creek FSAR and 6.5.1.2 of t hi SER assign a 99% | | l The proposed change incorporates an 80% value into the FRVS Recirculation laboratory testing criteria by allowing a 7.5% penetration (by interpolation of the clarification in Mr. Gamill's letter). For the overall FRVS, Sections 6.8 of the Hope Creek FSAR and 6.5.1.2 of t hi SER assign a 99% |
| system decontamination efficiency for accident iodines (elemental and organic). For the FRVS Ventilation and Filtration subsystem, Regulatory Guide 1.52 assigns a 95% | | system decontamination efficiency for accident iodines (elemental and organic). For the FRVS Ventilation and Filtration subsystem, Regulatory Guide 1.52 assigns a 95% |
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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
' . . .
4 Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609 339-4800 Senor Vice President -
November 25, 1987 NLR-N87223 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: l REQUEST FOR AMENDMENT PACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10CPR50.90, 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 10CFR50.91(b)(1), a copy of this request has been sent to the State of New Jersey as indicated below. In accordance with the requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed.
This amendment request revises Technical Specification 3/4.6.5.3, Filtration, Ventilation and Recirculation System (FRVS) and 3/4.7.2, Control Room Emergency Filtration System (CREFS).
Specifically, the chances shown in Attachment 2 separate subsystems within the FRVS Technical Specification, clarify surveillance requirements in order to extend PRVS service life and permit the interposition of a detailed evaluation of the potential impact of specific maintenance activities on the FRVS and CREFS efficiencies as predecisional to the presently required surveillance testing.
Attachments 1, 3 and 4 contain further discussion and justification for these proposed revisions. In order to effectively implement these revisions when issued, please issue the license amendment, following the necessary review and approval, with an implementation date within sixty (60) days after issuance.
8712110311 871125 \ yi d II I44l PDR ADOCK 05000354 A gD\
P PDR ,57 g
Document Control Desk 2 11-25-87 This submittal includes one (1) signed original, including affidavit, and thirty-sevea (37) copies pursuant to 10CFR50.4(b)(2)(ii).
Should you have any questions on the subject transmittal, please do not hesitate to contact us.
Sincerely, l
Enclosure (check)
Affidavit Attachments (4) l C Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. W. Borchardt USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
Ref: LCR 87-17 STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
Corbin A. McNeill, Jr., being duly sworn according to lau deposes and says:
7 am Senior Vice President of'Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated November 25, 1987 , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
w SubscribeJ this 15 and day Sworn of to
/Abefore A ,me 1987
/ nt n fft
/ NotaryjPublic of New Jersey g p E9 Y) B ersey My Commission Expires May In 1993 My Commission expires on
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[TTACHMENT__1 PROPOSED CHANGE TO Ref. LCR 87-17 TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DESCRIPTION OF CHANGE Within Technical Specification Section 3/4.6.5.3, Filtration, Ventilation and Recirculation System (FRVS) create separate sections.. 3/4.6.5.3.1, FRVS Ventilation and Piltration and 3/4.6.5.3.2,_PRVS Recirculation and Filtration ...and reword certain surveillance requirements and add _a footnote per the marked-up pages in Attachment 1 for those sections.
Additionally, for Section 3/4.7.2, Control Room Emeroency Filtration System (CREFS), reword surveillance requirement 4.7.2.c and add the same footnote as above per the attached-marked-up pages for that section.
REASON FOR CHANGE There are similer needs for clarification in both the FRVS end CREFS Technical Specifications. The Hope Creek Reactor Building Filtration, Recirculation and Ventilation System consists of two separate subsystems as indicated by the proposed separation. Separation of the two FRVS subsystems in the specifications and incorporation'of the proposed wording in the surveillance requirements of both the FRVS and CREFS subsystems will: 1) clarify the surveillance requirements for both FRVS and CREFS; 2) relax presently over-conservative surveillance commitments which will, in turn, significantly extend the service life of the FRVS Recirculation and Filtration subsystem charcoal without affecting the systems' capabilities or effectiveness as stated in the FSAR; and, 3) permit maintenance activities, such as welding and painting, in the reactor building or control room areas without dogmatically requiring a lenothy (roughly 4 weeks) surveillance test of the FRVS or CREFS without regard for the actual impact of those maintenance activities on ventilation system efficiency.
SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS 1st criterion This change does not involve a significant increase in the probability or consequences of any previously evaluated
Ref. LCR 87-17 l
l l SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS (Cont'd) accident or malfunction of equipment important to safety.
This revision will provide extended service life of FRVS charcoal and facilitate maintenance activities in the reactor building and control room areas while still meeting the efficiencies st 'ed in the FSAR and ensuring continued compliance with the requirements of Regulatory Guide 1.52.
The values proposed are consistent with the charcoal l
testing criteria clarification provided by William Gammil, Chief of the Effluent Treatment Systems Branch, in his letter dated September 24, 1981 (see Attachment 3). In this clarification, Mr. Gammill states that acceptance criteria should be based on the accident analysis.
l The proposed change incorporates an 80% value into the FRVS Recirculation laboratory testing criteria by allowing a 7.5% penetration (by interpolation of the clarification in Mr. Gamill's letter). For the overall FRVS, Sections 6.8 of the Hope Creek FSAR and 6.5.1.2 of t hi SER assign a 99%
system decontamination efficiency for accident iodines (elemental and organic). For the FRVS Ventilation and Filtration subsystem, Regulatory Guide 1.52 assigns a 95%
removal efficiency, based on a two inch bed. Therefore, to l achieve the PSAR/SER-assigned overall system efficiency I value of 99%, the FRVS Recirculation and Filtration subsystem, which functions as the initial cleanup system prior to, and as a guard bed for, the FRVS Ventilation and Filtration subsystem, needs only to have an 80% efficiency.
Most Standby Gas Treatment Systems (which is the equivalent system designation to the Hope Creek FRVS Recirculation subsystem) are rated at 4,000 cfm at 95% efficiency. The Hope Creek FRVS Recirculation units are each rated at 30,000 cfm such that even at 80% lab test efficiency, each of the six units provides 110% protection against any iodiac releans.
Addition of the proposed footnote and wording changes to Sections 4.6.5.3.c and 4.7.2.c provide latitude for evaluation of the need for testing following any work or event involving potential communication of the FRVS or CREFS subsystems with the resulting off-products of painting, welding, fire or chemical releases. The present Technical Specification, interpreted literally, makes no allowances for the type, quantity, length of exposure, known impact, or previous accumulation history of contaminants which could reduce the FRVS or CREFS subsystem efficiency below the minimums required in the Technical Specifications.
E ,
Ref. LCR 87-17
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SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS (Cont'd)
The. proposed footnote will require a thorough evaluation of all' potential contamination events, taking into account the previously mentioned elements which are pertinent to any determination of the degree of impact on system efficiency.
In the event that any of these proposed evaluations determines that contamination which could reduce system efficiency to below that required by the current Technical Specification may have occurred, or if there is any arbiguity in the results any of the proposed evaluations, the appropriate testing will be performed.
The CREFS filter trains, described in FSAR Sections 6.4 and 6.5.1, are normally isolated from control room atmosphere.
Therefore, the addition of the words, ' filter train', to Section 4.7.2.c more clearly defines that portion of each CREFS subsystem that can be affected by any potential contamination...instead of considering communication with the control room supply units or return air fans as having any effect on subsystem efficiency.
2nd Criterion This proposed change does not create the possibility of a new or-different-kind of accident from any previously evaluated because, other than allowing an 80% efficiency for the FRVS Recirculation units which as previously stated will still meet all FSAR and SER overall system efficiency requirements, there is no change to existing plant equipment, procedures, or operating parameters.
3rd Criterion A)though this change would permit reduced efficiency of the FRVS Recirculation and Filtration subsystem from the existing (overly conservative) Technical Specification requirements, there is no significant reduction in any associated margin of safety. The efficiency values determined in the laboratory tests involve testing of a carbon sample two inches in diameter and two inches deep.
No consideration is given to the actual volume or frontal surface area of the carbon adsorbent in the as-built configuration. In each of the six FRVS Recirculation and Filtration units at the Hope Creek Station, there are roughly 5200 lbs. of carbon adsorbent. At the proposed efficiency of 80%, each unit would be capable of providing 110% protection against the projected accident iodine release for a 1150 MW(e) reactor...for a total of 660%
volumetric capacity for iodine removal for the FRVS subsystem. The formula for the volume of carbon adsorbent 3-
Ref. LCR 87-17 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS (Cont'd) required for a particular reactor size was extracted from page 63 of the Nuclear Air Cleaning Handbook (ERDA 76-21),
the reference book used by Regulatory Guide 1.52 and the Standard Review Plan Section 6.5.1 (see Attachment 4).
Based on the above, we have determined that this proposed change does not involve a Significant Hazards Consideration. Additionally, we suggest that this change conforms to example (vi) of the guidance provided by the Commission, in 48FR14870 of the Federal Register, for Amendments Not Likely To Involve A Significant Hazards Consideration, in that, although the change may reduce, in some way, a margin of safety, plant operation with the proposed change in place would remain within all acceptable criteria, with respect to the CREFS AND FRVS subsystems, as specified in Standard Review Plan Sections 6.4, 6.5.1 and 6.5.3.
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