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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20196D0071999-06-16016 June 1999 Application for Amend to License DPR-35,changing TS Re Reactivity Control by Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8101999-05-11011 May 1999 Application for Amend to License DPR-35,requesting NRC Review & Approval of Change to TS Section 3/4.5.C, HPCI, Sys,Section 3/4.5.D, RCIC Sys & Bases Associated with Sections ML20206H9651999-05-0505 May 1999 Application for Amend to License DPR-35,modifying Licensing Basis for EDG on-site Diesel Fuel Storage Requirement & Corresponding TSs ML20203B5721999-02-0505 February 1999 Redacted Application for Amend to License DPR-35, Transferring FOL & Matls License 20-07626-04 from Boston Edison to Entergy Nuclear ML20202B4821999-01-21021 January 1999 Application for Amend to License DPR-35,using New Values for post-accident Containment Pressure in Plant NPSH Analyses Performed for ECCS Pumps.Calculations Supporting Request, Encl ML20198G5731998-12-21021 December 1998 Application for Amends to License DPR-35 & Matls License 20-07626-04,transferring PNPS from Boston Edison to Entergy Nuclear.Proprietary Info Encl.Proprietary Info Withheld. Pages 608 Through 621 of Incoming Submittal Not Included ML20249C7081998-06-26026 June 1998 Application for Amend to License DPR-35,correcting Typos & Updating Bases.Changes Are Considered Administrative ML20217H2681998-03-25025 March 1998 Application for Amend to License DPR-35,modifying Tech Specs 3.6.A.1 & 4.6.A.1 as It Pertains to Primary Sys Boundary, Thermal & Pressurization Limitations & Surveillance Requirements & Basis 3/4.6.A.Calculation Encl ML20203D4851998-02-20020 February 1998 Application for Amend to License DPR-35,to Change TS 3/4.5.B & Bases to Incorporate Ultimate Heat Sink Temperature 75 F, as Required by Amend 173.Request Fulfills Commitment to Submit TS Amend for UHS Temperature by First Quarter 1998 ML20203A0781998-02-11011 February 1998 Application for Amend to License DPR-35 UFSAR Section 10.7, Clarifying Design Basis for Salt Water Svc Water Sys BECO-LTR-97-107, Application for Emergency Amend to License DPR-35,changing TS 3.7.A.5 as Pertains to Periodic Surveillance Testing of Check Valve 30-CK-432.Exemption from LCO Footnote Provides Would Expire When Testing Is Performed1997-10-24024 October 1997 Application for Emergency Amend to License DPR-35,changing TS 3.7.A.5 as Pertains to Periodic Surveillance Testing of Check Valve 30-CK-432.Exemption from LCO Footnote Provides Would Expire When Testing Is Performed BECO-97-096, Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-14331997-09-19019 September 1997 Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-1433 BECO-LTR-97-002, Application for Amend to License DPR-35,requesting Rev to Safety Limit Minimum Critical Power Ratio.Encl Attachment 1 Re Description & Evaluation of Proposed TS Change to Min Critical Power Ratio Safety Limit Withheld1997-01-24024 January 1997 Application for Amend to License DPR-35,requesting Rev to Safety Limit Minimum Critical Power Ratio.Encl Attachment 1 Re Description & Evaluation of Proposed TS Change to Min Critical Power Ratio Safety Limit Withheld ML20135C1271996-11-26026 November 1996 Application for Amend to License DPR-35,modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consistent W/Lco 3/4.7.A.2.a.4 BECO-96-042, Application for Amend to License DPR-35,revising Note 7 to Table 3.1.1,note 6 to Table 3.2.C.1 & Section 3/4.4, Standby Liquid Control1996-05-0101 May 1996 Application for Amend to License DPR-35,revising Note 7 to Table 3.1.1,note 6 to Table 3.2.C.1 & Section 3/4.4, Standby Liquid Control ML20111B4121996-05-0101 May 1996 Application for Amend to License DPR-35,revising TS to Reflect Implementation of 10CFR50 App J,Option B ML20108C0781996-05-0101 May 1996 Application for Amend to License DPR-35,relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Util QA Manual ML20108C0261996-05-0101 May 1996 Application for Amend to License DPR-35 Re Core Alteration & LCO & Surveillance Conditions Associated W/Secondary Containment BECO-LTR-96-040, Application for Amend to License DPR-35,proposing Part of Overall Effort to Improve Outage Performance at Plant1996-04-25025 April 1996 Application for Amend to License DPR-35,proposing Part of Overall Effort to Improve Outage Performance at Plant BECO-95-074, Application for Amend to License DPR-35,reflecting Use of Advanced GE-11 Fuel Design in Cycle 111995-07-14014 July 1995 Application for Amend to License DPR-35,reflecting Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078N4751995-02-0909 February 1995 Application for Amend to License DPR-35,increasing Reactor High Water Level Isolation Trip Level Setting BECO-94-128, Application for Amend to License DPR-35,revising Suppression Chamber Water Level Operating Range,Increasing & Revises Water Level Recorder Range in Response to Commitment from Insp 50-293/91-2011994-11-22022 November 1994 Application for Amend to License DPR-35,revising Suppression Chamber Water Level Operating Range,Increasing & Revises Water Level Recorder Range in Response to Commitment from Insp 50-293/91-201 ML20078K7881994-11-22022 November 1994 Application for Amend to License DPR-35 to TS Re Change to MSIV Leakage Requirement BECO-94-127, Application for Amend to License DPR-35,revising Mode Conditions Under Scram Discharge Instrument vol-scram Trip Bypass in Table 3.2.C.1,required to Be Operable & Changes Associated Functional Test Frequency from Quarterly1994-11-22022 November 1994 Application for Amend to License DPR-35,revising Mode Conditions Under Scram Discharge Instrument vol-scram Trip Bypass in Table 3.2.C.1,required to Be Operable & Changes Associated Functional Test Frequency from Quarterly BECO-94-126, Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days1994-11-22022 November 1994 Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days BECO-94-098, Application for Amend to License DPR-35,requesting Change to Reflect Standard TSs Re Maintenance of Filled Discharge Pipe1994-09-0606 September 1994 Application for Amend to License DPR-35,requesting Change to Reflect Standard TSs Re Maintenance of Filled Discharge Pipe ML20072S0741994-09-0606 September 1994 Application for Amend to License DPR-35 Re Proposed TS Change to Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20072S0331994-09-0606 September 1994 Application for Amend to License DPR-35 Re Proposed TS Change to Setpoint for Reactor Pressure to Isolate Shutdown Cooling Sys ML20072R9891994-09-0606 September 1994 Application for Amend to License DPR-35 Involving Proposed Administrative Change to TSs Re Control Room Annunciator. Amend Involves Relocation of Alarms for Drywell Suppression Vacuum Breakers ML20069M3181994-06-0909 June 1994 Application for Amend to License DPR-35,revising TS to Increase Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys.Proposed Change Also Made to Section 4.5.H, Maint Of...Discharged Pipe to Reflect Amend 149 ML20067B6941994-02-0909 February 1994 Application for Amend to License DPR-35,proposing Changes to TS by Revising Wording for Page 3 of License DPR-35,adding Clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion ML20058N0131993-12-10010 December 1993 Application for Amend to License DPR-35,proposing Changes to Ts,Re Request for Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20062J3311993-10-19019 October 1993 Application for Amend to License DPR-35 Proposing Changes to Remove Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint BECO-93-133, Application for Amend to License DPR-35 Proposing Changes to TS by Removing Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors1993-10-19019 October 1993 Application for Amend to License DPR-35 Proposing Changes to TS by Removing Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors ML20046D0411993-08-0909 August 1993 Application for Amend to License DPR-35,proposing 24 Month Fuel Cycle ML20044G1251993-05-20020 May 1993 Application for Amend to License DPR-35,revising TS Re MSIV Turbine Inlet Low Pressure Setpoint to Reduce Potential Spurious Isolations Caused by Existing Higher Setpoint.Ge Repts MDE-70-0586 & NEDO-31296 Encl ML20128P3651993-02-11011 February 1993 Application for Amend to License DPR-35,changing TS to Increase Allowed Fuel Assembly Storage Cells from 2,320 to 3,859 & Changing Max Loads Allowed to Travel Over Spent Fuel Assemblies to 2,000 Lbs.Holtec Rept HI092925 Encl BECO-92-126, Application for Amend to License DPR-35,revising TS Sections 1.0,4.3,4.4,4.5,4.6,4.7 & Associated Bases to Conform SRs for ASME Code Class 1,2 & 3 Pumps & Valves to IST Program, Per 10CFR50.55a(g)(5)(ii)1992-10-30030 October 1992 Application for Amend to License DPR-35,revising TS Sections 1.0,4.3,4.4,4.5,4.6,4.7 & Associated Bases to Conform SRs for ASME Code Class 1,2 & 3 Pumps & Valves to IST Program, Per 10CFR50.55a(g)(5)(ii) BECO-92-121, Application for Amend to License DPR-35,proposing Changes to TS Section 2.1, Safety Limits, to Reflect Use of Advanced GE-10 Fuel Design & Section 3.3.C, Scram Insertion Times, to Correct Error in Control Rod Scram Insertion Time1992-10-23023 October 1992 Application for Amend to License DPR-35,proposing Changes to TS Section 2.1, Safety Limits, to Reflect Use of Advanced GE-10 Fuel Design & Section 3.3.C, Scram Insertion Times, to Correct Error in Control Rod Scram Insertion Time BECO-92-116, Application for Amend to License DPR-35,consisting of Temporary Change to TS Sections 3.7.B.1.C,3.7.B.1.e, 3.7.B.2.a & 3.7.B.2.C,requiring Both Trains of SGTS to Be Operable During Irradiated Fuel Handling Operations1992-10-0808 October 1992 Application for Amend to License DPR-35,consisting of Temporary Change to TS Sections 3.7.B.1.C,3.7.B.1.e, 3.7.B.2.a & 3.7.B.2.C,requiring Both Trains of SGTS to Be Operable During Irradiated Fuel Handling Operations BECO-92-101, Application for Amend to License DPR-35,changing TS 3/4.2 Re HPCI Instrumentation to Support Mod Planned During Refueling Outage 9 of Control Conduit for Several Valves in HPCI Indication in CR Per Reg Guide 1.971992-08-17017 August 1992 Application for Amend to License DPR-35,changing TS 3/4.2 Re HPCI Instrumentation to Support Mod Planned During Refueling Outage 9 of Control Conduit for Several Valves in HPCI Indication in CR Per Reg Guide 1.97 BECO-92-097, Application for Amend to License DPR-35,revising TS Surveillance Requirements & Associated Bases for Station Batteries to Conform W/Industry Practices & Mfg Recommendations1992-08-10010 August 1992 Application for Amend to License DPR-35,revising TS Surveillance Requirements & Associated Bases for Station Batteries to Conform W/Industry Practices & Mfg Recommendations BECO-92-079, Application for Amend to License DPR-35,revising TS Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases to Incorporate LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions1992-07-24024 July 1992 Application for Amend to License DPR-35,revising TS Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases to Incorporate LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions BECO-92-039, Application for Amend to License DPR-35,changing TS Section 4.7 Re Primary Containment Integrity to Remove Words Each Operating Cycle for MSIV & Personnel Airlock Door Testing1992-04-0808 April 1992 Application for Amend to License DPR-35,changing TS Section 4.7 Re Primary Containment Integrity to Remove Words Each Operating Cycle for MSIV & Personnel Airlock Door Testing BECO-92-012, Application for Amend to License DPR-35.changing TS to Extend Reactor Protection Sys Instrumentation Surveillance Test Intervals from 1 Month to 3 Months to Provide for 12 & 6 H Allowable out-of-svc Times for Repairs & Tests1992-02-0707 February 1992 Application for Amend to License DPR-35.changing TS to Extend Reactor Protection Sys Instrumentation Surveillance Test Intervals from 1 Month to 3 Months to Provide for 12 & 6 H Allowable out-of-svc Times for Repairs & Tests ML20086J5411991-12-0606 December 1991 Application for Amend to License DPR-35,revising Section 3/4.9, Auxiliary Electrical Sys,To Incorporate Surveillance for Inverters Associated W/Hpci & RCIC Sys BECO-91-136, Application for Amend to License DPR-35,changing Tech Spec 3.5.D.2, RCIC Sys,Under Exigent Circumstances to Provide Limited Extension of 7-day LCO1991-10-24024 October 1991 Application for Amend to License DPR-35,changing Tech Spec 3.5.D.2, RCIC Sys,Under Exigent Circumstances to Provide Limited Extension of 7-day LCO BECO-91-127, Application for Amend to License DPR-35,revising TS Section 3/4.12, Fire Protection, Per Generic Ltr 88-12.Amend Will Relocate Most of Existing Fire Protection TSs Into Fire Protection Program Ref in FSAR1991-10-0707 October 1991 Application for Amend to License DPR-35,revising TS Section 3/4.12, Fire Protection, Per Generic Ltr 88-12.Amend Will Relocate Most of Existing Fire Protection TSs Into Fire Protection Program Ref in FSAR BECO-91-076, Application for Amend to License DPR-35,revising Thermal & Pressurization Limit Curves of Tech Specs Figures 3.6.1 & 3.6.2 & Adding New Curve to Figure 3.6.3 to Cover Operation Between 10 & 32 Effective Full Power Years1991-06-11011 June 1991 Application for Amend to License DPR-35,revising Thermal & Pressurization Limit Curves of Tech Specs Figures 3.6.1 & 3.6.2 & Adding New Curve to Figure 3.6.3 to Cover Operation Between 10 & 32 Effective Full Power Years BECO-91-052, Revised Application for Amend to License DPR-35,changing Tech Spec Re Reactor Coolant Leakage Detection Sys at Plant1991-04-10010 April 1991 Revised Application for Amend to License DPR-35,changing Tech Spec Re Reactor Coolant Leakage Detection Sys at Plant 1999-06-16
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20196D0071999-06-16016 June 1999 Application for Amend to License DPR-35,changing TS Re Reactivity Control by Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8101999-05-11011 May 1999 Application for Amend to License DPR-35,requesting NRC Review & Approval of Change to TS Section 3/4.5.C, HPCI, Sys,Section 3/4.5.D, RCIC Sys & Bases Associated with Sections ML20206H9651999-05-0505 May 1999 Application for Amend to License DPR-35,modifying Licensing Basis for EDG on-site Diesel Fuel Storage Requirement & Corresponding TSs ML20203B5721999-02-0505 February 1999 Redacted Application for Amend to License DPR-35, Transferring FOL & Matls License 20-07626-04 from Boston Edison to Entergy Nuclear ML20202B4821999-01-21021 January 1999 Application for Amend to License DPR-35,using New Values for post-accident Containment Pressure in Plant NPSH Analyses Performed for ECCS Pumps.Calculations Supporting Request, Encl ML20198G5731998-12-21021 December 1998 Application for Amends to License DPR-35 & Matls License 20-07626-04,transferring PNPS from Boston Edison to Entergy Nuclear.Proprietary Info Encl.Proprietary Info Withheld. Pages 608 Through 621 of Incoming Submittal Not Included ML20249C7081998-06-26026 June 1998 Application for Amend to License DPR-35,correcting Typos & Updating Bases.Changes Are Considered Administrative ML20217H2681998-03-25025 March 1998 Application for Amend to License DPR-35,modifying Tech Specs 3.6.A.1 & 4.6.A.1 as It Pertains to Primary Sys Boundary, Thermal & Pressurization Limitations & Surveillance Requirements & Basis 3/4.6.A.Calculation Encl ML20203D4851998-02-20020 February 1998 Application for Amend to License DPR-35,to Change TS 3/4.5.B & Bases to Incorporate Ultimate Heat Sink Temperature 75 F, as Required by Amend 173.Request Fulfills Commitment to Submit TS Amend for UHS Temperature by First Quarter 1998 ML20203A0781998-02-11011 February 1998 Application for Amend to License DPR-35 UFSAR Section 10.7, Clarifying Design Basis for Salt Water Svc Water Sys BECO-LTR-97-107, Application for Emergency Amend to License DPR-35,changing TS 3.7.A.5 as Pertains to Periodic Surveillance Testing of Check Valve 30-CK-432.Exemption from LCO Footnote Provides Would Expire When Testing Is Performed1997-10-24024 October 1997 Application for Emergency Amend to License DPR-35,changing TS 3.7.A.5 as Pertains to Periodic Surveillance Testing of Check Valve 30-CK-432.Exemption from LCO Footnote Provides Would Expire When Testing Is Performed BECO-97-096, Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-14331997-09-19019 September 1997 Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-1433 BECO-LTR-97-002, Application for Amend to License DPR-35,requesting Rev to Safety Limit Minimum Critical Power Ratio.Encl Attachment 1 Re Description & Evaluation of Proposed TS Change to Min Critical Power Ratio Safety Limit Withheld1997-01-24024 January 1997 Application for Amend to License DPR-35,requesting Rev to Safety Limit Minimum Critical Power Ratio.Encl Attachment 1 Re Description & Evaluation of Proposed TS Change to Min Critical Power Ratio Safety Limit Withheld ML20135C1271996-11-26026 November 1996 Application for Amend to License DPR-35,modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consistent W/Lco 3/4.7.A.2.a.4 ML20108C0261996-05-0101 May 1996 Application for Amend to License DPR-35 Re Core Alteration & LCO & Surveillance Conditions Associated W/Secondary Containment BECO-96-042, Application for Amend to License DPR-35,revising Note 7 to Table 3.1.1,note 6 to Table 3.2.C.1 & Section 3/4.4, Standby Liquid Control1996-05-0101 May 1996 Application for Amend to License DPR-35,revising Note 7 to Table 3.1.1,note 6 to Table 3.2.C.1 & Section 3/4.4, Standby Liquid Control ML20111B4121996-05-0101 May 1996 Application for Amend to License DPR-35,revising TS to Reflect Implementation of 10CFR50 App J,Option B ML20108C0781996-05-0101 May 1996 Application for Amend to License DPR-35,relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Util QA Manual BECO-LTR-96-040, Application for Amend to License DPR-35,proposing Part of Overall Effort to Improve Outage Performance at Plant1996-04-25025 April 1996 Application for Amend to License DPR-35,proposing Part of Overall Effort to Improve Outage Performance at Plant BECO-95-074, Application for Amend to License DPR-35,reflecting Use of Advanced GE-11 Fuel Design in Cycle 111995-07-14014 July 1995 Application for Amend to License DPR-35,reflecting Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078N4751995-02-0909 February 1995 Application for Amend to License DPR-35,increasing Reactor High Water Level Isolation Trip Level Setting BECO-94-126, Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days1994-11-22022 November 1994 Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days ML20078K7881994-11-22022 November 1994 Application for Amend to License DPR-35 to TS Re Change to MSIV Leakage Requirement BECO-94-128, Application for Amend to License DPR-35,revising Suppression Chamber Water Level Operating Range,Increasing & Revises Water Level Recorder Range in Response to Commitment from Insp 50-293/91-2011994-11-22022 November 1994 Application for Amend to License DPR-35,revising Suppression Chamber Water Level Operating Range,Increasing & Revises Water Level Recorder Range in Response to Commitment from Insp 50-293/91-201 BECO-94-127, Application for Amend to License DPR-35,revising Mode Conditions Under Scram Discharge Instrument vol-scram Trip Bypass in Table 3.2.C.1,required to Be Operable & Changes Associated Functional Test Frequency from Quarterly1994-11-22022 November 1994 Application for Amend to License DPR-35,revising Mode Conditions Under Scram Discharge Instrument vol-scram Trip Bypass in Table 3.2.C.1,required to Be Operable & Changes Associated Functional Test Frequency from Quarterly ML20072S0741994-09-0606 September 1994 Application for Amend to License DPR-35 Re Proposed TS Change to Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20072S0331994-09-0606 September 1994 Application for Amend to License DPR-35 Re Proposed TS Change to Setpoint for Reactor Pressure to Isolate Shutdown Cooling Sys ML20072R9891994-09-0606 September 1994 Application for Amend to License DPR-35 Involving Proposed Administrative Change to TSs Re Control Room Annunciator. Amend Involves Relocation of Alarms for Drywell Suppression Vacuum Breakers BECO-94-098, Application for Amend to License DPR-35,requesting Change to Reflect Standard TSs Re Maintenance of Filled Discharge Pipe1994-09-0606 September 1994 Application for Amend to License DPR-35,requesting Change to Reflect Standard TSs Re Maintenance of Filled Discharge Pipe ML20069M3181994-06-0909 June 1994 Application for Amend to License DPR-35,revising TS to Increase Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys.Proposed Change Also Made to Section 4.5.H, Maint Of...Discharged Pipe to Reflect Amend 149 ML20067B6941994-02-0909 February 1994 Application for Amend to License DPR-35,proposing Changes to TS by Revising Wording for Page 3 of License DPR-35,adding Clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion ML20058N0131993-12-10010 December 1993 Application for Amend to License DPR-35,proposing Changes to Ts,Re Request for Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059J1651993-11-0404 November 1993 Corrected Amend 149 to License DPR-35,correcting Administrative Errors ML20062J3311993-10-19019 October 1993 Application for Amend to License DPR-35 Proposing Changes to Remove Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint BECO-93-133, Application for Amend to License DPR-35 Proposing Changes to TS by Removing Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors1993-10-19019 October 1993 Application for Amend to License DPR-35 Proposing Changes to TS by Removing Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors ML20046D0411993-08-0909 August 1993 Application for Amend to License DPR-35,proposing 24 Month Fuel Cycle ML20044G1251993-05-20020 May 1993 Application for Amend to License DPR-35,revising TS Re MSIV Turbine Inlet Low Pressure Setpoint to Reduce Potential Spurious Isolations Caused by Existing Higher Setpoint.Ge Repts MDE-70-0586 & NEDO-31296 Encl ML20128P3651993-02-11011 February 1993 Application for Amend to License DPR-35,changing TS to Increase Allowed Fuel Assembly Storage Cells from 2,320 to 3,859 & Changing Max Loads Allowed to Travel Over Spent Fuel Assemblies to 2,000 Lbs.Holtec Rept HI092925 Encl ML20127P5311993-01-25025 January 1993 Amend 145 to License DPR-35,revising TS SRs for Station Batteries by Replacing Rated Load Discharge Test W/Svc Discharge Test once-per-cycle & Performance Discharge Test Every Five Yrs BECO-92-126, Application for Amend to License DPR-35,revising TS Sections 1.0,4.3,4.4,4.5,4.6,4.7 & Associated Bases to Conform SRs for ASME Code Class 1,2 & 3 Pumps & Valves to IST Program, Per 10CFR50.55a(g)(5)(ii)1992-10-30030 October 1992 Application for Amend to License DPR-35,revising TS Sections 1.0,4.3,4.4,4.5,4.6,4.7 & Associated Bases to Conform SRs for ASME Code Class 1,2 & 3 Pumps & Valves to IST Program, Per 10CFR50.55a(g)(5)(ii) BECO-92-121, Application for Amend to License DPR-35,proposing Changes to TS Section 2.1, Safety Limits, to Reflect Use of Advanced GE-10 Fuel Design & Section 3.3.C, Scram Insertion Times, to Correct Error in Control Rod Scram Insertion Time1992-10-23023 October 1992 Application for Amend to License DPR-35,proposing Changes to TS Section 2.1, Safety Limits, to Reflect Use of Advanced GE-10 Fuel Design & Section 3.3.C, Scram Insertion Times, to Correct Error in Control Rod Scram Insertion Time BECO-92-116, Application for Amend to License DPR-35,consisting of Temporary Change to TS Sections 3.7.B.1.C,3.7.B.1.e, 3.7.B.2.a & 3.7.B.2.C,requiring Both Trains of SGTS to Be Operable During Irradiated Fuel Handling Operations1992-10-0808 October 1992 Application for Amend to License DPR-35,consisting of Temporary Change to TS Sections 3.7.B.1.C,3.7.B.1.e, 3.7.B.2.a & 3.7.B.2.C,requiring Both Trains of SGTS to Be Operable During Irradiated Fuel Handling Operations BECO-92-101, Application for Amend to License DPR-35,changing TS 3/4.2 Re HPCI Instrumentation to Support Mod Planned During Refueling Outage 9 of Control Conduit for Several Valves in HPCI Indication in CR Per Reg Guide 1.971992-08-17017 August 1992 Application for Amend to License DPR-35,changing TS 3/4.2 Re HPCI Instrumentation to Support Mod Planned During Refueling Outage 9 of Control Conduit for Several Valves in HPCI Indication in CR Per Reg Guide 1.97 BECO-92-097, Application for Amend to License DPR-35,revising TS Surveillance Requirements & Associated Bases for Station Batteries to Conform W/Industry Practices & Mfg Recommendations1992-08-10010 August 1992 Application for Amend to License DPR-35,revising TS Surveillance Requirements & Associated Bases for Station Batteries to Conform W/Industry Practices & Mfg Recommendations BECO-92-079, Application for Amend to License DPR-35,revising TS Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases to Incorporate LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions1992-07-24024 July 1992 Application for Amend to License DPR-35,revising TS Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases to Incorporate LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions BECO-92-039, Application for Amend to License DPR-35,changing TS Section 4.7 Re Primary Containment Integrity to Remove Words Each Operating Cycle for MSIV & Personnel Airlock Door Testing1992-04-0808 April 1992 Application for Amend to License DPR-35,changing TS Section 4.7 Re Primary Containment Integrity to Remove Words Each Operating Cycle for MSIV & Personnel Airlock Door Testing BECO-92-012, Application for Amend to License DPR-35.changing TS to Extend Reactor Protection Sys Instrumentation Surveillance Test Intervals from 1 Month to 3 Months to Provide for 12 & 6 H Allowable out-of-svc Times for Repairs & Tests1992-02-0707 February 1992 Application for Amend to License DPR-35.changing TS to Extend Reactor Protection Sys Instrumentation Surveillance Test Intervals from 1 Month to 3 Months to Provide for 12 & 6 H Allowable out-of-svc Times for Repairs & Tests ML20086J5411991-12-0606 December 1991 Application for Amend to License DPR-35,revising Section 3/4.9, Auxiliary Electrical Sys,To Incorporate Surveillance for Inverters Associated W/Hpci & RCIC Sys BECO-91-136, Application for Amend to License DPR-35,changing Tech Spec 3.5.D.2, RCIC Sys,Under Exigent Circumstances to Provide Limited Extension of 7-day LCO1991-10-24024 October 1991 Application for Amend to License DPR-35,changing Tech Spec 3.5.D.2, RCIC Sys,Under Exigent Circumstances to Provide Limited Extension of 7-day LCO BECO-91-127, Application for Amend to License DPR-35,revising TS Section 3/4.12, Fire Protection, Per Generic Ltr 88-12.Amend Will Relocate Most of Existing Fire Protection TSs Into Fire Protection Program Ref in FSAR1991-10-0707 October 1991 Application for Amend to License DPR-35,revising TS Section 3/4.12, Fire Protection, Per Generic Ltr 88-12.Amend Will Relocate Most of Existing Fire Protection TSs Into Fire Protection Program Ref in FSAR 1999-06-16
[Table view] |
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.J L Ralph G. Bird '
'3 senior Vice Prestaent - Nudear .BECo 90-i36' l November 8. 1990 U.S. Nuclear Regulatory-Commission ~ a Document Control Desk' y Hashington, DC 20555 j
' License'DPRl 35' Docket 50-293-PROPOSED TECHNICALLSPECIFICATION- .
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CHANGE MINIMUM CRITICAL r3HER RAJJ.Q. !
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. Boston- Edison -Company proposes the attached revisions ;to. Appendix A of. -
i
, Operating License DPR-35 for the' Pilgrim Nuclear' Power Station in-accordance. H with-10CFR50.90. The' pro' posed revision :to :the1 Technical' Specifications ~
upgrades the Safety Limit Minimum Critical Power Ratio and revises ,thet J Operating Limit Minimum Critical! Power A. ;
These. proposed revisionsnwill extend the ,e of: spectral! shift to maximize fuel !
utilization during the present fuel cycle. Thisuchange tis <not _ nee'ded-if our
_ proposed change of August .21, a1990-is- approvedifirst F ' .
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l Then personally appeared before me, George H.; Davis,-who'being duly. sworn,-did-state that he =is Vice President -_ Nuclear' Admi.nistration of Boston Edison Company and that hefis. duly authorized'to executeland file the; submittal contained hereiniin the.nameland on sbehalf'ofiBoston EdisonLCompany and that '
the' statements in said-submitta1Jare truelto the best ofchis-: knowledge and- i belief. "
My commission en s:JO M /995~
.DATE ' ;7'
)# ub NOTARYP0pIC n
Attachments: . A.< Description'.of' Propose'[Chinges 1
d :
'B. Replacement Technical l Specification Pages e"
C. Marked-up Technica1LSpecif,1 cation;Pages D. Supplemental Reload Licensing Submitted for Pilgrim Nuclear' '
Power ' Stationereload l 7o Cycl e. 8,123A4800 - Rev .- l.- -
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PDR ADOCK 05000293 %, /g, p PDG 4;3lp' 's' +: .j
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3 T 5 BOSTONLEDISON COMPANY' ,
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- U.S. Nuclear Regulatory Commission ]
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, i 4 s cc: Mr. R. Eaton, Project Manager .
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Divis_ ion of.' Reactor _ Projects'- I/II Office of Nuclear Reactor Regulationi l Mail Stop: .14D1 1
,l U. S. Nuclear Regulatory Commission ,
1 Hhite Flint North: $
11555 Rockville' Pike-Rockville, MD 20852 1 i
U.:S. Nuclear Regulatory Commission': 4 i
Region I _
475 Allendale Road , .
King of-Prussia,'PA':19406;
. Senior NRC Resident Inspector-
. Pilgrim Nuclear Power. Station:
Mr.-RobertM.:Hallisey,;Directorj Radiation Control Program . . -
, ~
Massachusetts Department of Public Health'.
150 Tremont Street, 2nd' Floor _.. ,
3 Boston, MA' 02111-
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^ d Atta'chment A'.-to BECo. 90-136 j Qginintion' of Proposed Chance 1 1
Pronosed Chad 221- .
Boston-Edison Company proposes to upgrade' the Safety Limit Minimum Critical Power Ratio (MCPR)-and revise the'0perating Limit Minimum Critical Power <
Ratio. The revision;to the' Safety Limit Minimum Critical Power Ratio reflects '
improved fur,) de:1gns in the core _ and the General Electric Boiling. Hater: '
Reactor Ger.eric- Reload Fuel, Application, NEDE-24011-P. ,
The revision to the Operating Lim',OMinimum'CriticalL Power Ratio is being .
proposed to be consistent with the upgraded Safety Limit'MCPR and to' reflect spectral' shift operation. Spcctral. shift. operation resultsfin' top peaked l flux' distriLution patterns <toward the end of.the fuel' cycle.- A. top. peaked flux:
distribution pattern increases the change in the Critical Power. Ratio. (ACPR)'
associated with'the analyzed operational trans.ients. The proposed-revision l
maintains conservative operating limits.
The upgraded Safety Limit -MCPR and. thetrevised Operating' Limit MCPR_ ensureLthe.
plant will be operated safely and willinot ' pose an,unoue: risk to the health and- I safety of the public. These revisions willzallow the plant to be. operated more;
~ ~
efficiently.
Basis for Changg-The NRC approved the upgraded Safety Liinit MCPR in its' safety. evaluation for- 1 Amendment 14 to NEDE-240ll-P-A, " General Electric ' Standard Application for J Reactor Fuel'.', dated December:27,1987; Incorporation of the upgraded. Safety i Limit-MCPR is appropriate -for BWR's with.0-lattice- fuel assemblies:provided:7,_ l
- 1) the fuel has a beginning of life'R-factor greater 1than4or equal:to1 1.04'and. l H consists of! fuel -types P8x8R BP8x8R,3 GE8x8E or GE8x8EB;- 2) the fuel is at L least 2.80 weight percent,U-235 bund _le average enrichment; and 3)1 the lower enrichment bundles in the core hav'efoperated for_-at:least 2 cycles'..
'The fuel assemblies presently. in:the core of the Pilgrim Nuclear: Power: Station' l satisfy the conditions; evaluated in NEDE-24011-P-A. _These conditions;wil_1lalso I be satisfied for future reloads',
The Supplemental Reload Licensing Submittal' for Pilgrim' Nuclear. Power Station, l Reload 7 Cycle 8. submitted by.BECo letter 87.081: dated:May 22~ 1987-has been. ,
revised to reflect operati_on:Using?a spectral shift fuel managementLstrategy.
a The' revise.d analysis also, reflects an' assumption that the Turbine Bypass Valves; a
- do not open in the analysisLof the Feedwater Controller Failureiwith maximum, !
' demand. This-assumption was made becausetprecise. measurements of the opening time are not available. The' assumption _ is. conservative and"it results in a 3 more severe transient analysis.and:aimore conservative . Operating; Limit MCPR. ,
This limit'is incorporated in the proposed Technical Specification. The- +
proposed Operating Limit MCPR willoensure the MCPR does not' decrease-below the~
proposed Safety Limit MCPR at anyttime during any abnormal operating transient.
!- as defined in the FSAR.
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, l Determination of No Sionificant Hazards Considerations The code of Federal Regulations (10CFR50.91). requires-licensees requesting an I amendment-to provide an analysis, using the standards!in 10CFR50.92,' that -
J determines whether a significant hazard consideration exists. The following :l analysis is provided in-accordance with-10CFR50.91 and-10CFR50.92'for the' proposed amendment.to Pilgrim's Minimum Critical: Power Ratio.
- 1. Upgraded Safety Limit MCPR. i A. The proposed change does not involve 6!significant increase'in the. .
)
probability or consequences of an accident lpreviously evaluated because the. =l proposed change to the Safety Limit MCPR does not change ~ plant equipment, H operating procedures, or governing design. criteria _used-to protect >the; plant against the initiati_on of any analyzed accident or used to mitigate-the consequences of any' analyzed' accident.;
B. The proposed change does.not create the. possibility of a new or!different l kind of accident from any previously analyzed'because.the proposed change I does-_not change plant et,'uipment,' operating procedures .or governing design criteria-and the change toithe Safety Limit MCPR:provides the same level of:
protection as the existing' Safety Limit MCPR.againstLfuel cladding-failureL during an abnormal operational transient. The proposed Safety. Limit' MCPR .
. therefore provides equal: assurance against a. release'of radioactive l
material in excess of.10 CFR 20 limits. during abnormal operational '
+
transients and a new event. sequence leading to an accident is not2 created.
q C., The following design requirement ensures an' adequate safety margin is i '
maintained:
Abnormal operational transients caused by aLsingle operator error or w equipment malfunction shall be limited such that,-:considering :
uncertainties in manufacturing and moni_toring,the core operating i state, more than 99.97.Lof the: fuel l rods:would be expectedLto avoid. a boiling transition.
Theprposedchangedoesnotfinvolve.asignificantreduction;inthemargin-1 of safety because this design' requirement which governs fuel cladding . ,
integrityandmaintainsthedefense-in-depthphilosophy,hasinotchanged.
- 2. Revised Operating' Limited MCPRL 'l A. - The proposed change does noCinvolve.a:significant increase in thel j probability;or consequencesLof.an accident previously, evaluated because the
- proposed change'to the;0peratingl Limit MCPR doe's.not change plant equipment, operating procedures,-or; governing. design'criteriaiused to-protect the plant against the'initiationfof any analyzed l accident orcused' a
- to mitigaterthe conseque_nces-_of any analyzed accident.
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B. The proposed change does not create.the possibilityTof(a-new or;differentL - '
kind.of accident from any'accider.tfpreviously evaluated'because the ;
e -proposed change:does:not change plant equipment,-operating procedures',4or?
governing design criteria and'the: changes to Operating Limit MCPRs;providei j the same-level of' assurance thatsthe- Safety Limit MCPR will' not:be' exceeded during.an' abnormal operational transient thereby assuring a release of; '
- ' radioactive material = in' excess ofL10 CFR 20 limits ~will not
- occur'during; ,
abnormal operational transients and a' new event sequence / leading-to>an:
accident has not.i.een created , .m.
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. . . . i.. .. * .9 C. 'The' proposed change doesinot involve;aLsignificantJreduction:in the margin l=
'of3 safety because the conservative Operating Limit MCPR:ensuresLthe most: -,
limiting transient will not violate; the SafetyfLimit MCPR.., .+
B1 guested Schedule- ,
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The requested change /is not needed ! untildhe,present fuel (burnup;reac'hes 7200;
-HH9/T, about January 31,.1991'. , Additionally,s approval .off this'. t equest willo noti
' ed if our proposed change;of August 21.-L1990 isiapproved first. >
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. Attachment;B'to BECo 90-136'-
List of Effective Pages- '
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' l Revised Pages , j
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p LI ' SAFETY LIMIT - 2.1 LIMITING SAFETY SYSTEM SETTING _ . ;
l 1'1 FUEL CLADDING INTEGRITY' '2.1 ~ FUEL CLADDING INTEGRITY 5 ADDIicabilitV: '
ADDIiCabiIitV j L .
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Applies to the' interrelated Applies to tripJsettings of the- j variables associated with fuel '
instruments and devices which?are- n L thermal behavior. provided to prevent the reactort l K system: safety limits,from being. ' 1 L Obiective: exceeded. ,
~l L To establish limits below which Obiective:s L the integrity of-the fuel clade .E. .
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! ding'is preserved.- lTo define the level of the process I L,
variables at.which automatic; , 1 Soeci fi ca ti.QD:. .
protectite_-action is initiated toi 7 prevent the fuel claddingt 1 Reador Pressure >800 osia'and ' integrity.saf ety limits from tieing?
.A-Core Flow >10% of Rated. exceeded.- l The existence:of a minimum Speci f s ca' tion:-
critical . pcwer ratio (MCPR) less ' . .
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( than 1.04'sh611l constitute '. A.- Neutt'on' Flux' Scram; '
',integrity violationsafet'y of the'fuelicladding limit., A HCPR' -
. 1.
l of 1.04 is hereinafter referredL The limiting safety; system trip? ]
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- l. to as the Safety: Li.mit MCPR.; ~ settings shall be'as specified .
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- below: - ';
B. Core Thermal' Power Limit 1(Reactor . . .
4 Pressure 1800 psia.and/or; Core. . l.-Neutron Flux' Trio-Settinas r Flow 110%). . .
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.a.,=APRM Flux Scram Trioc e' .
When the reactor pressure Settina1Run Mode)- J
-1 800 psia or core-flow is,is- less , .. , . . . . .
than-or equal to?l0% of rated, When the ModetSwitch is in- i the' steady state core' thermal the:RUN position ktheLAPRM power shall not exceed 25% of '
ifluxi scram: trip. setting ci design 1 thermal power. =shall be: 1 Power Transient' b C. S f .58H~+ 62% 2 1000' a
The safety l limit shall be assumed 'Hhere: i u sto be exceeded when scram is .
.. . . J j' known-to have been accomplished cS = Setting in percent of I f by a means other;than the rated thermalzpower expected scram signal?unless.- N b' L(1998 MHt)-
L analyses--demonstrate-that the . ., i K fuel cladding:. integrity l safety: H - Percent-of drive flow: ;[
e limits defined. in' Specifications -
Jto produce'a rated; core- '
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'l.1A and l'.lB sare not': exceeded , flow of-69 H lb/hr. ' !
b during the actual transient. ' '
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r- Revision: .. '
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Amendment No. 721 '
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- j. The statistical: analysis used to-determine th'e MCPR safety: limit is- - '
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based on a model of the BHR corr which simulates theLprocess computer 3 l: function. The reactor. core selected for these analyses,was a large 76C 1 assembly, 251 inch reload core; Results from:the large reload-core- ;
L analysis apply for all operating. reactors:for all? reload cycles, c ,
- including equilibrium cycles. ' Random Monte Carlo selections-of all- l operating' parameters; based. on= the ' uncertainty. rangesiof manufacturing =
tolerances, uncertainties in-measurement of. core operating parameters, J L calculational uncertainties, and. statistical uncertainty' associated with? ,
the critical power correlations are imposed'upon the' analytical '
. representation'of the coreJand-the resulting-bundle critical power ratios. Details.of thisfstatistical. analysis are presented lin Reference 2.- ;
B. Core Thermal Power Limit-(Reactor: Pressure <-800 osia or Core Flow, :7
< 10% of Rated) , ,
1 The use of the GEXL1 correlation is not valid'.for the critical power 1 .. "
O calculations'at pressures-below:800;psig.or cor.e flows less1 than1 10% ofc rated. Therefore, the' fuel claddinglintegrity safety' limit is; _;
established by c,ther means.:DThis is done by; establishing a. limiting <
condition'ofcore; thermal-poweroperation.withnthe-followingbasis.. . 3 Sitce the pressure. drop inithe bypass regionsis essentially all elev6 tion head whichiis 4;56.psiitheicore pressure: drop at lowLpower/and- '
all-flows wil.1: iways be greater than 4.56 psin Analyses show,that wi.th '
a flow of 28x10 lu./hrl bundletflow, -bundle pressure drop-is nearly- 4 inden ndent-of bundle power:and hasca)valueiof:3.5 psi. Thus the ]
bundle flow with a 4.56; psi' driving -head willibe
c lbs/hr irrespective:of- totalfc6te:flowland independent of bundle power ;
for:the range of, bundle-powersjofLeoncern. Full: scale ATLAS test. data y taken at. pressures 1from 14.7 psia tto 800 psia 1 indicate that the fuel:
assembly critical powerJat this flow ris ?approximately 3.'35:MWt'. ; Hith'- s the design peaking; factors the.3.35lMHt; bundle power corresponds to'a: ';
core thermallpower :of more than150%L Therefore: a core t'iermal: power -
limit of 25% for reactor: pressures ;below 800 psia, or_ core flow less, ,
than 10% is conservativ'e; j
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C. Power Transient, .
Plantsafetyanalyseshaveshown[thatthescrams.causedbyexceeding.
any safety setting will assure that:the Safety < Limit lof Specification _l 1.lA or 1.1B will.not be. exceeded.:' Scram. times are: checked
-periodically to assure tht insertion times are adequate . The thermal .
power transient resultingLwhen'a scram is accomplished other;than;by ;
Jthe expected scram signal (e.g., scram from. neutron flux followingL -
closures of the~ main ' turbine stop valves) does notJnecessarily cause ' 1' fuel damage. However,; for: this specification la Safety Limit violation:
will be assumed when a seramLisionly; accomplished by means:of a,backupL '
feature of the' plant design.- The concept of,not: approaching'aiSafety ;
umit provided scram signals are;operableLis1 supported by.the. extensive" plant safety analysis.
The computer 'provided with Pilgrimidnit l' has isequ(nce annunciationi
. program which will indicate lthe sequence ~in.which events-such'.as: scram,. .i
- APRM trip initiationh pressurefscramiinitiation, etc.,' occur. ;This -
program also, indicates when the' scram setpok nis cleered. .This-will!
provide-information.on.howLlong;a scram condition' exists,and thust .
providesome(measureof'the'energyadded-during(a' transient. !
-D. Reactor Water Level (Shutdown Condition)
During periods' when :the' reactortis' shutdown',jconsideraGon must alsoEbe 1 given to water level requirements due.Lto the:effect.of decay heat.4If reactor water level .shouldsdrop below ,the top of the : active fuel during i this time,' the abilityito coo 1Lthe' core is reducedt TThis1 reduction in >
core cooling capabilityfcould:leaditotelevatedicladding temperaturesi ;
and clad perforation.! ..The core can1be cooled'sufficiently;should the, j water level be1 reduced toEtwo-thirdsithe coretheight.3 3Establishmenti of. i the safety.limitiatal2'inchesiabove the; top ofmthel fuel provides;
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adequate margin. This level will"be{ continuously monitored.
References , ,
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. .r 1 1.GeneralElectric:ThermalAnalysisiasis((GETAB):
Data,uCorrelation and '
l- . De si gn Appli cati on',1 General El ectri c Co ,q BHR ' Systems l Department ,
L November 1973 (NEDO-10958). (
- 2. General Electric' Boiling Hater Reactor Generic Reload / Fuel? Applicatio'n, "
'HEDE-24011-A.
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-' OPERATING LIMIT MCPR VALUES- ,;
A. MCPRL0perating Limit from Beginning of Cycle (BOCF to BOC E7,953 MHD/ST..
P8x8R/BP8x8R For all values of t - 1.48 -
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B.- MCPR Operating Limit from BOC-+ 7,953 MWD /ST.tW End;of' Cycle.'. ?
,1 P8x8R/BP8x8R' t m
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0.1.< t 1 0.2' 1.43- q 0.2.<~t 1:0.3; 1.44'. -
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0.4.<.t 1 0.5 1.46 0.5'<.t 1:0.6 1.47 0.6 < t 1 0.7.- 1.48' n
0.7.< t 1 0'8 .
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l 1;50 j 0.8 < t 1 0.9 0.9 < 2 1 1.0' .
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