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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEAR3F1099-01, LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc1999-10-12012 October 1999 LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc 3F0999-07, Application for Amend to License DPR-72,to Change ITS Proposed in LAR 239,rev 0,increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revise Configuration for Storage of Fresh Fuel.Proprietary Encl Withheld1999-09-16016 September 1999 Application for Amend to License DPR-72,to Change ITS Proposed in LAR 239,rev 0,increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revise Configuration for Storage of Fresh Fuel.Proprietary Encl Withheld 3F0999-06, Rev 1 to LAR 249,dtd 990505,application for Amend to License DPR-72,revising Once Through Steam Generator Tube Surveillance Program1999-09-0202 September 1999 Rev 1 to LAR 249,dtd 990505,application for Amend to License DPR-72,revising Once Through Steam Generator Tube Surveillance Program 3F0799-07, LAR 222,Rev 2 for Amend to License DPR-72,proposing Changes to ITS for CREVS & to VFTP & Correcting Typo in ITS Section 5.6.2.121999-07-0808 July 1999 LAR 222,Rev 2 for Amend to License DPR-72,proposing Changes to ITS for CREVS & to VFTP & Correcting Typo in ITS Section 5.6.2.12 3F0599-15, Rev 0 to LAR 250 to License DPR-72,changing CR-3 ITS Section 3.3.8, EDG Lops, SR 3.3.8.1 by Revising Note for Surveillance & Deleting Note for Frequency.Conforming ITS Bases Changes,Encl1999-05-17017 May 1999 Rev 0 to LAR 250 to License DPR-72,changing CR-3 ITS Section 3.3.8, EDG Lops, SR 3.3.8.1 by Revising Note for Surveillance & Deleting Note for Frequency.Conforming ITS Bases Changes,Encl 3F0599-16, Rev 0 to LAR 251 to License DPR-72,revising CR-3 ITS Administrative Controls Section 5.8, High Radiation Area. Util Requests NRC Approval by June 30,20001999-05-10010 May 1999 Rev 0 to LAR 251 to License DPR-72,revising CR-3 ITS Administrative Controls Section 5.8, High Radiation Area. Util Requests NRC Approval by June 30,2000 3F0599-01, Rev 1 to LAR 241 for Amend to License DPR-72,revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,rev 1 & Clarifying Process of Valve Position Verification1999-05-0707 May 1999 Rev 1 to LAR 241 for Amend to License DPR-72,revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,rev 1 & Clarifying Process of Valve Position Verification 3F0599-02, Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.7901999-05-0505 May 1999 Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.790 3F0399-01, Rev 1 to LAR 235 to License DPR-72,proposing Repair Roll Process for CR-3 OTSG tubes.Non-proprietary Rev 1 to BAW-2342 & Proprietary Rev 1 to BAW-2342P Repts Encl. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)1999-03-18018 March 1999 Rev 1 to LAR 235 to License DPR-72,proposing Repair Roll Process for CR-3 OTSG tubes.Non-proprietary Rev 1 to BAW-2342 & Proprietary Rev 1 to BAW-2342P Repts Encl. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) 3F0199-04, LAR 243,Rev 0 to License DPR-72,requesting one-time Rev of ITS to Extend Insp Interval for OTSG Tubes to Coincide with Planned Operating Cycle.Rev 0 to Calculation M-99-0017 & Rev 0 to Calculation AES-C-3543-1 Encl1999-01-27027 January 1999 LAR 243,Rev 0 to License DPR-72,requesting one-time Rev of ITS to Extend Insp Interval for OTSG Tubes to Coincide with Planned Operating Cycle.Rev 0 to Calculation M-99-0017 & Rev 0 to Calculation AES-C-3543-1 Encl 3F1198-06, LAR 244,rev 0,for License DPR-72,proposing Changes to Improved TS LCO 3.9.3 to Allow Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations1998-11-30030 November 1998 LAR 244,rev 0,for License DPR-72,proposing Changes to Improved TS LCO 3.9.3 to Allow Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations 3F1198-01, Application for Amend to License DPR-72,consisting of LAR 240,re Addition of safety-related diesel-driven Emergency Feedwater Pump.Overview of Proposed Mods Presented to NRC on 980921.Addl Info on post-mod Testing Will Be Sent by 9901291998-11-24024 November 1998 Application for Amend to License DPR-72,consisting of LAR 240,re Addition of safety-related diesel-driven Emergency Feedwater Pump.Overview of Proposed Mods Presented to NRC on 980921.Addl Info on post-mod Testing Will Be Sent by 990129 3F1198-13, LAR 221,rev 2 to License DPR-72,revising Improved Tech Spec (ITS) 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic.Rev of LAR 221 Due to Latest Guidance in Draft RG DG-10741998-11-17017 November 1998 LAR 221,rev 2 to License DPR-72,revising Improved Tech Spec (ITS) 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic.Rev of LAR 221 Due to Latest Guidance in Draft RG DG-1074 3F1098-15, Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl1998-10-30030 October 1998 Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl 3F1098-02, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-11998-10-30030 October 1998 Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-1 3F1098-04, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) Sections 5.6.2.19,ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits1998-10-30030 October 1998 Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) Sections 5.6.2.19,ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 3F1098-01, Application for Amend to License DPR-72,revising Plant FSAR, Improved Tech Specs (ITS) & ITS Bases to Resolve USQ Re Leaving Valves DHV-34 & DHV-35 Normally Closed1998-10-16016 October 1998 Application for Amend to License DPR-72,revising Plant FSAR, Improved Tech Specs (ITS) & ITS Bases to Resolve USQ Re Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1531998-09-30030 September 1998 LAR 238 to License DPR-72,correcting RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR 3F0898-01, LAR 235,rev 0 to License DPR-72,proposing New Repair Process for Plant Otsgs.Technical Basis for Repair Roll Process Proposed by LAR Is Contained in BAW-2303P,Rev 31998-08-31031 August 1998 LAR 235,rev 0 to License DPR-72,proposing New Repair Process for Plant Otsgs.Technical Basis for Repair Roll Process Proposed by LAR Is Contained in BAW-2303P,Rev 3 3F0898-04, LAR 234,Rev 0 to License DPR-72,adding Three Addl Reg Guide 1.97 Type a Category 1 post-accident Monitoring Instrumentation Variables & One Type B Category 1 PAM Instrumentation Variable to Improved TS Table 3.3.17-11998-08-31031 August 1998 LAR 234,Rev 0 to License DPR-72,adding Three Addl Reg Guide 1.97 Type a Category 1 post-accident Monitoring Instrumentation Variables & One Type B Category 1 PAM Instrumentation Variable to Improved TS Table 3.3.17-1 3F0798-15, Application for Amend to License DPR-72,changing Improved TS for CREVS & Ventilation Filter Test Program.Control Room Habitability Rept,Ts Pages & Commitments Encl1998-07-30030 July 1998 Application for Amend to License DPR-72,changing Improved TS for CREVS & Ventilation Filter Test Program.Control Room Habitability Rept,Ts Pages & Commitments Encl 3F0698-28, Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG1998-06-18018 June 1998 Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG 3F0598-01, Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis1998-05-28028 May 1998 Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis 3F0598-09, License Amend Request 231,Rev 1 to License DPR-72,providing Addl Clarification to Improved Tech Specs 5.2.1, Onsite & Offsite Organizations1998-05-22022 May 1998 License Amend Request 231,Rev 1 to License DPR-72,providing Addl Clarification to Improved Tech Specs 5.2.1, Onsite & Offsite Organizations 3F0498-06, LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels1998-04-28028 April 1998 LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels 3F0498-02, Application for Amend to License DPR-72,clarifying Improved Tech Specs 5.7.2, Special Repts, to State That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure)1998-04-23023 April 1998 Application for Amend to License DPR-72,clarifying Improved Tech Specs 5.7.2, Special Repts, to State That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) 3F0398-17, Rev 0 to LAR 231 to License DPR-72,proposing Editoral Changes to Improved Tech Specs Safety Limits & Administrative Controls to Replace Listed Titles W/Position of Chief Nuclear Officer1998-03-20020 March 1998 Rev 0 to LAR 231 to License DPR-72,proposing Editoral Changes to Improved Tech Specs Safety Limits & Administrative Controls to Replace Listed Titles W/Position of Chief Nuclear Officer 3F0398-07, Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp1998-03-20020 March 1998 Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp 3F1297-19, Application for Amend to License DPR-72,proposing Changes to Improved TSs for CREVS & to Vftp.List of Commitments,Summary of Changes,Reason & Justification for Request,Control Room post-accident Dose Calculations & Analysis Also Encl1997-12-0505 December 1997 Application for Amend to License DPR-72,proposing Changes to Improved TSs for CREVS & to Vftp.List of Commitments,Summary of Changes,Reason & Justification for Request,Control Room post-accident Dose Calculations & Analysis Also Encl 3F1297-11, Application for Amend to License DPR-72,revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal1997-12-0505 December 1997 Application for Amend to License DPR-72,revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal 3F1097-08, Rev 1 to License Amend Request 220,supersedes 970626 Application,Removing Portion of License Condition 2.C.(5) Which Requires Installation & Testing of Flow Indicators in ECCS for Boron Dilution.Description of Changes Encl1997-10-31031 October 1997 Rev 1 to License Amend Request 220,supersedes 970626 Application,Removing Portion of License Condition 2.C.(5) Which Requires Installation & Testing of Flow Indicators in ECCS for Boron Dilution.Description of Changes Encl ML20212F2671997-10-31031 October 1997 LAR 214,rev 0 to License DPR-72,proposing Changes to Improved TS & Bases Pages Re Decay Heat Removal Requirements in Mode 4.List of Commitments Also Encl 3F1097-32, Application for Amend to License DPR-72,addressing Methodology for post-LOCA Boron Precipitation Prevention. Revised Framatome Technologies,Inc Document 51-5000519-02, Boron Dilution by RCS Hot Leg Injection, Encl1997-10-31031 October 1997 Application for Amend to License DPR-72,addressing Methodology for post-LOCA Boron Precipitation Prevention. Revised Framatome Technologies,Inc Document 51-5000519-02, Boron Dilution by RCS Hot Leg Injection, Encl 3F1097-04, Application for LAR 217,Rev 0 to DPR-72,addessing Rev to Description of Electrical Controls for Operating Reactor Bldg Recirculation Sys fan/cooler,AHF-1C,as Discussed in FSAR & Improved TS Bases1997-10-0404 October 1997 Application for LAR 217,Rev 0 to DPR-72,addessing Rev to Description of Electrical Controls for Operating Reactor Bldg Recirculation Sys fan/cooler,AHF-1C,as Discussed in FSAR & Improved TS Bases 3F1097-21, Application for LAR 221,Rev 0 to License DPR-72,adding Methodology to Monitor Indication Growth in Group of Tubes within Crystal River Unit 3 B Otsg.Ts Pages,Encl1997-10-0101 October 1997 Application for LAR 221,Rev 0 to License DPR-72,adding Methodology to Monitor Indication Growth in Group of Tubes within Crystal River Unit 3 B Otsg.Ts Pages,Encl 3F0997-25, TS Change Request Notice 213,Suppl 1 to License DPR-72, Proposing New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys1997-09-12012 September 1997 TS Change Request Notice 213,Suppl 1 to License DPR-72, Proposing New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys 3F0997-16, Application for Amend to License DPR-72,revising EDG Protective Relaying Scheme,As Described in FSAR Chapter 81997-09-12012 September 1997 Application for Amend to License DPR-72,revising EDG Protective Relaying Scheme,As Described in FSAR Chapter 8 3F0997-14, Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR1997-09-0909 September 1997 Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR 3F0897-25, Application for LAR 216 Proposing Amend to License DPR-72, to Change Design Basis of EDG Air Handling Sys1997-08-26026 August 1997 Application for LAR 216 Proposing Amend to License DPR-72, to Change Design Basis of EDG Air Handling Sys 3F0897-22, Application for Amend to License DPR-72,TS Change Request Notice 215,extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified1997-08-0404 August 1997 Application for Amend to License DPR-72,TS Change Request Notice 215,extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified 3F0797-21, TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt1997-07-29029 July 1997 TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt 3F0797-10, TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys1997-07-18018 July 1997 TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys 3F0697-08, Application for Amend to License DPR-72,removing Wording for Requirement Re Installation & Testing of Flow Indicators1997-06-26026 June 1997 Application for Amend to License DPR-72,removing Wording for Requirement Re Installation & Testing of Flow Indicators 3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes1997-06-14014 June 1997 TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes 3F0597-21, TS Change Request 212,Rev 1 Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J, Option B1997-05-0101 May 1997 TS Change Request 212,Rev 1 Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J, Option B 3F0397-16, Application for Amend to License DPR-72 Re Once Through SG Tube Surveillance Program1997-03-27027 March 1997 Application for Amend to License DPR-72 Re Once Through SG Tube Surveillance Program 3F0297-09, TS Change Request 212 to License DPR-72,adopting 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water- Cooled Reactors, Option B1997-02-17017 February 1997 TS Change Request 212 to License DPR-72,adopting 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water- Cooled Reactors, Option B 3F0996-05, Application for Amend to License DPR-72,consisting of Change Request 209,Rev 0,proposing Listed Changes to CR-3 post- Accident Monitoring Instrumentation TS1996-09-27027 September 1996 Application for Amend to License DPR-72,consisting of Change Request 209,Rev 0,proposing Listed Changes to CR-3 post- Accident Monitoring Instrumentation TS ML20129E7381996-09-27027 September 1996 Application for Amend to License DPR-72,proposing Changes to CR-3 post-accident Monitoring Instrumentation 3F0996-14, TS Change Request 206 to License DPR-72,revising Engineered Safeguards Actuation Sys Automatic Actuation Logic. Certificate of Svc Encl1996-09-23023 September 1996 TS Change Request 206 to License DPR-72,revising Engineered Safeguards Actuation Sys Automatic Actuation Logic. Certificate of Svc Encl 1999-09-02
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEAR3F1099-01, LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc1999-10-12012 October 1999 LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc 3F0999-07, Application for Amend to License DPR-72,to Change ITS Proposed in LAR 239,rev 0,increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revise Configuration for Storage of Fresh Fuel.Proprietary Encl Withheld1999-09-16016 September 1999 Application for Amend to License DPR-72,to Change ITS Proposed in LAR 239,rev 0,increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revise Configuration for Storage of Fresh Fuel.Proprietary Encl Withheld 3F0999-06, Rev 1 to LAR 249,dtd 990505,application for Amend to License DPR-72,revising Once Through Steam Generator Tube Surveillance Program1999-09-0202 September 1999 Rev 1 to LAR 249,dtd 990505,application for Amend to License DPR-72,revising Once Through Steam Generator Tube Surveillance Program 3F0799-07, LAR 222,Rev 2 for Amend to License DPR-72,proposing Changes to ITS for CREVS & to VFTP & Correcting Typo in ITS Section 5.6.2.121999-07-0808 July 1999 LAR 222,Rev 2 for Amend to License DPR-72,proposing Changes to ITS for CREVS & to VFTP & Correcting Typo in ITS Section 5.6.2.12 3F0599-15, Rev 0 to LAR 250 to License DPR-72,changing CR-3 ITS Section 3.3.8, EDG Lops, SR 3.3.8.1 by Revising Note for Surveillance & Deleting Note for Frequency.Conforming ITS Bases Changes,Encl1999-05-17017 May 1999 Rev 0 to LAR 250 to License DPR-72,changing CR-3 ITS Section 3.3.8, EDG Lops, SR 3.3.8.1 by Revising Note for Surveillance & Deleting Note for Frequency.Conforming ITS Bases Changes,Encl 3F0599-16, Rev 0 to LAR 251 to License DPR-72,revising CR-3 ITS Administrative Controls Section 5.8, High Radiation Area. Util Requests NRC Approval by June 30,20001999-05-10010 May 1999 Rev 0 to LAR 251 to License DPR-72,revising CR-3 ITS Administrative Controls Section 5.8, High Radiation Area. Util Requests NRC Approval by June 30,2000 3F0599-01, Rev 1 to LAR 241 for Amend to License DPR-72,revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,rev 1 & Clarifying Process of Valve Position Verification1999-05-0707 May 1999 Rev 1 to LAR 241 for Amend to License DPR-72,revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,rev 1 & Clarifying Process of Valve Position Verification 3F0599-02, Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.7901999-05-0505 May 1999 Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.790 3F0399-01, Rev 1 to LAR 235 to License DPR-72,proposing Repair Roll Process for CR-3 OTSG tubes.Non-proprietary Rev 1 to BAW-2342 & Proprietary Rev 1 to BAW-2342P Repts Encl. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)1999-03-18018 March 1999 Rev 1 to LAR 235 to License DPR-72,proposing Repair Roll Process for CR-3 OTSG tubes.Non-proprietary Rev 1 to BAW-2342 & Proprietary Rev 1 to BAW-2342P Repts Encl. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) 3F0199-04, LAR 243,Rev 0 to License DPR-72,requesting one-time Rev of ITS to Extend Insp Interval for OTSG Tubes to Coincide with Planned Operating Cycle.Rev 0 to Calculation M-99-0017 & Rev 0 to Calculation AES-C-3543-1 Encl1999-01-27027 January 1999 LAR 243,Rev 0 to License DPR-72,requesting one-time Rev of ITS to Extend Insp Interval for OTSG Tubes to Coincide with Planned Operating Cycle.Rev 0 to Calculation M-99-0017 & Rev 0 to Calculation AES-C-3543-1 Encl 3F1198-06, LAR 244,rev 0,for License DPR-72,proposing Changes to Improved TS LCO 3.9.3 to Allow Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations1998-11-30030 November 1998 LAR 244,rev 0,for License DPR-72,proposing Changes to Improved TS LCO 3.9.3 to Allow Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations 3F1198-01, Application for Amend to License DPR-72,consisting of LAR 240,re Addition of safety-related diesel-driven Emergency Feedwater Pump.Overview of Proposed Mods Presented to NRC on 980921.Addl Info on post-mod Testing Will Be Sent by 9901291998-11-24024 November 1998 Application for Amend to License DPR-72,consisting of LAR 240,re Addition of safety-related diesel-driven Emergency Feedwater Pump.Overview of Proposed Mods Presented to NRC on 980921.Addl Info on post-mod Testing Will Be Sent by 990129 3F1198-13, LAR 221,rev 2 to License DPR-72,revising Improved Tech Spec (ITS) 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic.Rev of LAR 221 Due to Latest Guidance in Draft RG DG-10741998-11-17017 November 1998 LAR 221,rev 2 to License DPR-72,revising Improved Tech Spec (ITS) 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic.Rev of LAR 221 Due to Latest Guidance in Draft RG DG-1074 3F1098-04, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) Sections 5.6.2.19,ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits1998-10-30030 October 1998 Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) Sections 5.6.2.19,ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 3F1098-15, Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl1998-10-30030 October 1998 Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl 3F1098-02, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-11998-10-30030 October 1998 Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-1 3F1098-01, Application for Amend to License DPR-72,revising Plant FSAR, Improved Tech Specs (ITS) & ITS Bases to Resolve USQ Re Leaving Valves DHV-34 & DHV-35 Normally Closed1998-10-16016 October 1998 Application for Amend to License DPR-72,revising Plant FSAR, Improved Tech Specs (ITS) & ITS Bases to Resolve USQ Re Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1531998-09-30030 September 1998 LAR 238 to License DPR-72,correcting RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR 3F0898-04, LAR 234,Rev 0 to License DPR-72,adding Three Addl Reg Guide 1.97 Type a Category 1 post-accident Monitoring Instrumentation Variables & One Type B Category 1 PAM Instrumentation Variable to Improved TS Table 3.3.17-11998-08-31031 August 1998 LAR 234,Rev 0 to License DPR-72,adding Three Addl Reg Guide 1.97 Type a Category 1 post-accident Monitoring Instrumentation Variables & One Type B Category 1 PAM Instrumentation Variable to Improved TS Table 3.3.17-1 3F0898-01, LAR 235,rev 0 to License DPR-72,proposing New Repair Process for Plant Otsgs.Technical Basis for Repair Roll Process Proposed by LAR Is Contained in BAW-2303P,Rev 31998-08-31031 August 1998 LAR 235,rev 0 to License DPR-72,proposing New Repair Process for Plant Otsgs.Technical Basis for Repair Roll Process Proposed by LAR Is Contained in BAW-2303P,Rev 3 3F0798-15, Application for Amend to License DPR-72,changing Improved TS for CREVS & Ventilation Filter Test Program.Control Room Habitability Rept,Ts Pages & Commitments Encl1998-07-30030 July 1998 Application for Amend to License DPR-72,changing Improved TS for CREVS & Ventilation Filter Test Program.Control Room Habitability Rept,Ts Pages & Commitments Encl 3F0698-28, Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG1998-06-18018 June 1998 Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG 3F0598-01, Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis1998-05-28028 May 1998 Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis 3F0598-09, License Amend Request 231,Rev 1 to License DPR-72,providing Addl Clarification to Improved Tech Specs 5.2.1, Onsite & Offsite Organizations1998-05-22022 May 1998 License Amend Request 231,Rev 1 to License DPR-72,providing Addl Clarification to Improved Tech Specs 5.2.1, Onsite & Offsite Organizations 3F0498-06, LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels1998-04-28028 April 1998 LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels 3F0498-02, Application for Amend to License DPR-72,clarifying Improved Tech Specs 5.7.2, Special Repts, to State That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure)1998-04-23023 April 1998 Application for Amend to License DPR-72,clarifying Improved Tech Specs 5.7.2, Special Repts, to State That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) 3F0398-07, Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp1998-03-20020 March 1998 Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp 3F0398-17, Rev 0 to LAR 231 to License DPR-72,proposing Editoral Changes to Improved Tech Specs Safety Limits & Administrative Controls to Replace Listed Titles W/Position of Chief Nuclear Officer1998-03-20020 March 1998 Rev 0 to LAR 231 to License DPR-72,proposing Editoral Changes to Improved Tech Specs Safety Limits & Administrative Controls to Replace Listed Titles W/Position of Chief Nuclear Officer 3F1297-11, Application for Amend to License DPR-72,revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal1997-12-0505 December 1997 Application for Amend to License DPR-72,revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal 3F1297-19, Application for Amend to License DPR-72,proposing Changes to Improved TSs for CREVS & to Vftp.List of Commitments,Summary of Changes,Reason & Justification for Request,Control Room post-accident Dose Calculations & Analysis Also Encl1997-12-0505 December 1997 Application for Amend to License DPR-72,proposing Changes to Improved TSs for CREVS & to Vftp.List of Commitments,Summary of Changes,Reason & Justification for Request,Control Room post-accident Dose Calculations & Analysis Also Encl 3F1097-32, Application for Amend to License DPR-72,addressing Methodology for post-LOCA Boron Precipitation Prevention. Revised Framatome Technologies,Inc Document 51-5000519-02, Boron Dilution by RCS Hot Leg Injection, Encl1997-10-31031 October 1997 Application for Amend to License DPR-72,addressing Methodology for post-LOCA Boron Precipitation Prevention. Revised Framatome Technologies,Inc Document 51-5000519-02, Boron Dilution by RCS Hot Leg Injection, Encl ML20212F2671997-10-31031 October 1997 LAR 214,rev 0 to License DPR-72,proposing Changes to Improved TS & Bases Pages Re Decay Heat Removal Requirements in Mode 4.List of Commitments Also Encl 3F1097-08, Rev 1 to License Amend Request 220,supersedes 970626 Application,Removing Portion of License Condition 2.C.(5) Which Requires Installation & Testing of Flow Indicators in ECCS for Boron Dilution.Description of Changes Encl1997-10-31031 October 1997 Rev 1 to License Amend Request 220,supersedes 970626 Application,Removing Portion of License Condition 2.C.(5) Which Requires Installation & Testing of Flow Indicators in ECCS for Boron Dilution.Description of Changes Encl 3F1097-04, Application for LAR 217,Rev 0 to DPR-72,addessing Rev to Description of Electrical Controls for Operating Reactor Bldg Recirculation Sys fan/cooler,AHF-1C,as Discussed in FSAR & Improved TS Bases1997-10-0404 October 1997 Application for LAR 217,Rev 0 to DPR-72,addessing Rev to Description of Electrical Controls for Operating Reactor Bldg Recirculation Sys fan/cooler,AHF-1C,as Discussed in FSAR & Improved TS Bases 3F1097-21, Application for LAR 221,Rev 0 to License DPR-72,adding Methodology to Monitor Indication Growth in Group of Tubes within Crystal River Unit 3 B Otsg.Ts Pages,Encl1997-10-0101 October 1997 Application for LAR 221,Rev 0 to License DPR-72,adding Methodology to Monitor Indication Growth in Group of Tubes within Crystal River Unit 3 B Otsg.Ts Pages,Encl 3F0997-16, Application for Amend to License DPR-72,revising EDG Protective Relaying Scheme,As Described in FSAR Chapter 81997-09-12012 September 1997 Application for Amend to License DPR-72,revising EDG Protective Relaying Scheme,As Described in FSAR Chapter 8 3F0997-25, TS Change Request Notice 213,Suppl 1 to License DPR-72, Proposing New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys1997-09-12012 September 1997 TS Change Request Notice 213,Suppl 1 to License DPR-72, Proposing New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys 3F0997-14, Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR1997-09-0909 September 1997 Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR 3F0897-25, Application for LAR 216 Proposing Amend to License DPR-72, to Change Design Basis of EDG Air Handling Sys1997-08-26026 August 1997 Application for LAR 216 Proposing Amend to License DPR-72, to Change Design Basis of EDG Air Handling Sys 3F0897-22, Application for Amend to License DPR-72,TS Change Request Notice 215,extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified1997-08-0404 August 1997 Application for Amend to License DPR-72,TS Change Request Notice 215,extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified 3F0797-21, TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt1997-07-29029 July 1997 TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt 3F0797-10, TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys1997-07-18018 July 1997 TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys 3F0697-08, Application for Amend to License DPR-72,removing Wording for Requirement Re Installation & Testing of Flow Indicators1997-06-26026 June 1997 Application for Amend to License DPR-72,removing Wording for Requirement Re Installation & Testing of Flow Indicators 3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes1997-06-14014 June 1997 TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes 3F0597-21, TS Change Request 212,Rev 1 Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J, Option B1997-05-0101 May 1997 TS Change Request 212,Rev 1 Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J, Option B 3F0397-16, Application for Amend to License DPR-72 Re Once Through SG Tube Surveillance Program1997-03-27027 March 1997 Application for Amend to License DPR-72 Re Once Through SG Tube Surveillance Program 3F0297-09, TS Change Request 212 to License DPR-72,adopting 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water- Cooled Reactors, Option B1997-02-17017 February 1997 TS Change Request 212 to License DPR-72,adopting 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water- Cooled Reactors, Option B ML20133D3411997-01-0606 January 1997 Amend 155 to License DPR-72,consisting of Changes to TS in Response to 960923 Application to Delete Note for SR 3.3.7.1 for Engineered Safeguard Actuation Sys Logic 3F0996-05, Application for Amend to License DPR-72,consisting of Change Request 209,Rev 0,proposing Listed Changes to CR-3 post- Accident Monitoring Instrumentation TS1996-09-27027 September 1996 Application for Amend to License DPR-72,consisting of Change Request 209,Rev 0,proposing Listed Changes to CR-3 post- Accident Monitoring Instrumentation TS ML20129E7381996-09-27027 September 1996 Application for Amend to License DPR-72,proposing Changes to CR-3 post-accident Monitoring Instrumentation 1999-09-02
[Table view] |
Text
1
% l
Power COR PO R AT 1ON I March 22, 1989 3F0389-18 Document Control Desk (
U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 '
Technical Specification Change Request No. 166 Core Operating Limits Report
Dear Sir:
I Florida Power Corporation (FPC) hereby submits Technical Specification Change Request No. (TSCRN) 166, requesting amendment to Appendix A of ,
Operating License No. DPR-72. Proposed replacement pages for Appendix !
A and associated bases are provided. 4 1
This submittal requests that cycle-dependent core operating limits be l removed from Technical Specifications (TS) and relocated to a Core 1 Operating Limits Report. This report will document the specific values of parameter limits resulting from the licensee's calculations including any mid-cycle revisions to such parameter values. l Generic letter 88-16, which was issued by the NRC on October 4, 1988, provides a means for removing the numeric values of cycle specific parameters from the technical specifications. The generic letter-requires that the cycle specific limits be determined using an NRC-approved methodology.
B&W Fuel Company (BWFC) calculates the axial power imbalance ranges, control rod insertion ranges, axial power shaping rod insertion ranges, and quadrant power tilt limits with the methodology described in topical report BAW-10122A, Rev. 1, " Normal Operating Controls." This report received NRC approval in Safety Evaluation Reports (SERs) dated September 14, 1979 and April 20, 1984. The SERs conclude that the procedures and techniques described in BAW-10122A, Rev. 1 are acceptable for establishing limiting conditions for operation for the parameters discussed above.
$ 2 g :
P POST OFFICE BOX 219 + CRYSTAL RIVER, FLORIDA 326294219 * (904) 563-2943 A Florida Progress Company L
Merch 22, 1989 3F.0389-18 Page 2 BWFC calculates the moderator temperature coefficient with the methodology described in topical reports BAW-10118A, " Core Calculational Techniques and Procedures" and BAW-10152A, " NOODLE, A Multi-Dimensional Two-Group Reactor Simulator." Topical report BAW-10118A . received NRC approval in the Safety Evaluation Report dated September 25, 1979. Topical report BAW-10152A received NRC approval in the SER dated April 24, 1985. The SERs conclude that the procedures-and techniques described in BAW-10118A and BAW-10152A are acceptable for establishing limiting conditions for operation for the moderator temperature coefficient.
The methodology for calculating the programmed rod positions is described in BWFC topical' report , - BAW-10118A, " Core Calculational Techniques and Procedures", and in the attached methodology (attachment
- 1) provided by BWFC. Topical report BAW-10118A received NRC approval as noted above.- The refuel boron concentration limits are calculated by BWFC using the methodology described in the attached - BWFC report (attachment 1) . It is requested that these methodologies be approved with this change request as they will be utilized in determining the-parameters to be used in the Core Operating Limits Report for Rod Program and Refuel Boron Concentration.
The NRC issued a Safety Evaluation Report on January 26, 1989 to Duke Power Company for their Core Operating Limits Report change request.
Oconee Nuclear Station was the lead plant for the Babcock and Wilcox owners group regarding this submittal.
l FPC requests this amendment become effective 30 days after issuance in order to allow for procedure changes and training.
Very truly yours, 1
7 f '.
l Gary [.Boldt,VicePresident )
Nuclear Production GLB:dlh Attachment xc: Regional Administrator, Region II Senior Resident Inspector i
v i
9
, i STATE OF FLOHIDA COUNTY OF CITHUS i
G.L. Boldt states that he is the Vice President, Nuclear Production for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.
I G.L. gplidt, Vice President Nuclear Production l
Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 22nd day of March, 1989.
nso ary Public V
l Notary Public, State of Florida at Large My Commission Expires: June 21, 1991
v
. UNITED STATES OF AMERICA: j NUCLEAR REGULATORY COMMISSION' l
IN THE MATTER ~ )'
) . DOCKET NO. 50-302 FLORIDA POWER CORPORATION )
CERTIFICATE OF SERVICE G.L. Boldt deposes and says that the following has been served on the Designated State Representative and Chief Executive -of Citrus County, Florida, by deposit in the United States' mail, addressed as'follows: ;
I Chairman. ' Administrator _ _
Board of County Commissioners Radiological;_ Health rSe rvicas ,
of Citrus County Department of Health and-Citrus County Courthouse Rehabilitative Services Inverness, FL 3265G 1323 Winewood Blvd.
Tallahassee, FL 32301 l
l A copy of Technical Specification Change Request No. 166,' Revision 0,- :
requesting Amendment to Appendix A.of Operating Licensing No. DPR-72.
FLORIDA POWER CORPORATION
~
L XYhW W d%VF 1
G.L.,%1dt, Vice President NuclWar Production SWORN TO AND SUBSCRIBED BEFORE ME THIS 22nd DAY OF March, 1989.
'l l
- J! k SA) Yt No ' dry Public U U
i Notary.Public, State of Florida at Large '
My Commission Expires: June 21, 1991 ,
1-
i.
I
%' f n
FIIRIDik IOGER ERPCRATIN QUSDLL RIVER IMIT. 3 D00ET NO. 50-302/LIQBEiB NO. WR-72 REQUEST NO. 166 CORE WEEUEDG I2MHS REEUtf j LIQ 5EEE D00 MENT INVMRED: 'Dectinical 5t=r ifin'ations ,
RRFIGGS: Index,'Page la Definitions, Page 1-8 3.1.1.3 3.1.3.1 3.1.3.6 Figure 3.1-1 Figure 3.1-2 Figure 3.1-3 Figure 3.1-4 ,
3.1.3.7 .I Figure 3.1-7 3.1.3.9 3.2.1 Figure 3.2-1 Figure 3.2-2 3.2.4 Table 3.2-2 3.9.1 ..
4.1.1.3.1 4.1.3.6 j
4.1.3.9 '
4.2.1 4.2.4 6.9.1.7 IESmIPTICN OF REQUEST: i
'Ihis subnittal requests that cycle-dependent core operating limits be removed fran Technical Specifications (TS) and relocatai to 'a Core operating Limits Report. 'Ibe term, 00RE OPERATING LIMITS REPORP, will be arN1 to the Definitions Section of TS. A new administrative reporting requirausit will be ;
added to existing reportiny requirements of TS. Individual specifications and l applicable bases will be revised to state ~ that the values of cycle-specific ;
parameters shall be maintained within the limits identified in Core Operating 1 Limits Report.
REASW MR RBQUEST:
A number of Technical Specifications (TS). address limits associated with.
reactor physics parameters that generally change with each reload requiring the pwcassing of cnanges .to TS to update these limits each fuel cycle. 'Ibese limits are developed using an NRC-approved methodology, therefore, the license aasnisit prma is an unmaan burden on the licensee and the NRC. -An alternative to including the values of these cycle-specific parameters in' individual specifications is responsive to industry and NRC efforts on improvements in TS and is provided in this change request.
v EVAIIRTICE OF REQUESf:
It is essential to safety that the plant is operated within the bounds of cycle-specific parameter limits and that a requirement to maintain the plant within the appropriate bounds must be retained in the TS. However, the i specific values of these limits may be modified by licensees, without affecting nuclear safety, provided that these changes are determined using an NRC-approved methodology. and consistent with all applicable limits of the plant safety analysis that are addIm W in the Final Safety Analysis Report (FSAR).
A Core Operating Limits Report will be subnitted to NRC with the values of these limits. 'Ihis will allow continued trending of this information, even though prior NRC approval of the changes to these limits would not be required.
'Ibe Core Operating Limits Report will elev,=nt the specific values of parameter limits resulting from the licensee's calculations including any mid-cycle revisions to such parameter values. 'Ihe methodology for determining cycle-specific parameter limits (except for Rod Prwtaru and Refuel. Boron Concentration) is dev'=nted in NRC-approved 'Ibpical Reports IRW-10122A, Rev.
1, BAW-10118A, Rev. O, and BAW 10152A, Rev. O. As a consequence, the NRC review of proposed changes to TS for these limits is primarily limited to confirmation that the updated limits are calculated using an NRC-approved methodology and consistent with all applicable limits of the safety analysis. Attachment i describes .the methodology for determinire parameter limits for Rod hWram and Refuel Borun Concentration. It is requested that these methodologies be approved with this change request as they will be utilized in detennining the parameters to be used in the Core Operatiry Limits Report for Rod h^% ram and
, Refuel Boron Coraxultation.
l
'Ibe cycle specific core operating limits calculated in accordance with the approved methodologies will be included in the report, Core Operatirg Limits Report, and provided to the NRC upon issuance as required by the proposed Technical Specification 6.9.1.7. Controlled copies of the Core Operating Limits Report will be maintained at Crystal River Unit-3 (CR-3) and will be revised as required by the future CR-3 cycles. Attachment 2 provides a sartple copy of a Core Operating Limits Report for information purposes only.
SIUIZX EVAIIRTIN OF RB3]EST:
Florida Power Corporation (FPC) pin w the removal of cycle specific core operating limits frun Technical Specifications does not involve a significant hazard consideration. The removal of cycle dep=aiad. variables frcan Teudaical Specifications has no 4W upon plant operation or safety. The Technical Specifications will continue to require operation within the core operational limits for each cycle reload calculated by the approved reload design methodologies. Awwiate actions to be taken if limits are violated will j also remain in Technical Specifications.
FPC concludes this change will not:
- 1. Involve a significant increase in the probability or consequence of an i accident previously evaluated because the renoval of cycle specific core operating limits from the Crystal River Unit 3 (CR-3) Technical Specifications has no influence or 4W on the probability of a Design Basis Accident (DIR) nmwrence.
The cycle specific core operating limits will be relocated to a CORE OPERATING LIMITS REPORT. The requita-is to operate CR-3 within the limits will continue to be maintained in Technical Specifications.
- 2. Create the possibility of a new or different kind of accident frcan any !
accident previously evaluated because the removal of the cycle specific variables has no influence, .bmpact, nor does it contribute to the I probability or ue= sequences of an accident. The cycle specific variables are calculated using NRC approved methodologies, and Technical l Specifications will continue to require the operation within the core operatirg limits. .
- 3. Involve a significant reduction in the margin of safety because the margin of safety presently provided by current Technical Specifications remains unchanged. This proposed amendment still requires operation within the I core limits as obtained frun the NRC approved methodologies, and appropriate actions to be taken when, or if limits are violated, remain !
unchanged.
__...__m___._______.m__ _ _ _ . _ . _ _ _ _ _ _ _
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ATTACHMENT 1 I
METHODOLOGY !
I e ROD PROGRAM j i
9 REFUEL BORON CONCENTRATION 1
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l l
a .. .J 1
I msnmrmy !
ato Paoans h core operatinJ Limits Report has a figure which provides the Rod Frymu for each cycle. The mod Pr@mu Figure shows the location of each control
'i '
assembly in the core and identifies to which rod group assembly is _ assigned.
The Technical Specification states, "Each control rod assembly (safety, regulating and APSR) shall be sv:pmi. a.3 to operate in the core location and -
rod group specified in the 00RE OPERATING LIMITS RE10RT." The following-diam == ion daaeribes the procedures and methods of analysis used to determine the rods assigned to each group.
Eadi control rod amaemibly in the core can be electrically wui:cted to.any of the eight control rod groups. h only limitation is that each group nust have between 4 and 12 rod amaamblies. The groups are numbered 1 through 8 and are-divided into these categories. Groups 1 through 4 are the safety rods, Groups 5 through 7 are the regulating rods, and Group 8 is the axial power shaping rods (APSR's). The following dacv ription of the methods and guc.=dures for the analysis addramaa= the APSR's first and then the regulating rods and finally the safety rods.
1 N APSR's are unique in their physical characteristics fr m the other cont W rods. They have a shorter poison region and the poison' may 'be a differr -
composition. The latching mechanism for the APSR's is also different from tL other control rods in that these rods cannot be unlatched when the control rods are h cuuusi. The location of the APSR's in the core is symetric by quadrant.
These locations (L12 and N10 in the lower right quadrant) were determined to
w have a minimal impact on radial power peaking while adileving the greatest amount of overall control on core offset (or imbalance). W e locations of the APSR's have not been changed since the first cycle aM are not expected to be changed. l l
'Ihe regulating rods, Groups 5 through 7, are used to control the core power .
1 level. Wese red groups are electrically coupled to be sequentially withdrawn (5,6,7), with an overlap of 25% 5% and sequentially inserted (7,6,5). %e j i
location of the rods in each of the regulating groups is determined beginning with Group 7. Group 7 is usually m M of 8 rod assemblies. We location l
of the Group 7 rod is selected to be symmetrical in the eighth core and have a j i
minimal impact on the radial power distribution. 'Ihe locations are also l l
restricted to positions other than those adjacent to the Group 8 rods, if j i
possible. We Groups 6 and 5 rods are also selected to have eighth core j l
symmetry aM have a minimal impact on the radial power distribution. In l l
addition, the Groups 6 and 5 rods are positioned to ensure an ejected rod will not violate the safety criteria. (See BAW-10118A, " Core Calculational Techniques And Procedures," J.J. Romano, December, 1979, for a d%= ion of ejected red worth analysis.)
Design analyses with Groups 5 through 8 determine the limiting red positions for the operation of each cycle. Wese analyses evaluate the operation of the core at various power levels throughout the cycle and show how normal operating controls on the red groups can be set to ensure safe operation. (See BAW-10122A, Rev. 1, " Normal Operating Controls," G.E. Hanson, April, 1984, for a discussion of rod operation analyses which ensure operating margin with respect to power peaking, shutdown reactivity and ejected rod worths).
3
%e safety rods, Groups 1 through 4, are used to ensure sufficient scram reactivity for a safe shutdown of the reactor core. %ese rod groups are fully withdrawn prior to the core going critical. %ey are withdrawn one group at a time but not twmaat-ily in order. %e core remains ~ shutdown with Groups 1 through 4 out of the core, therefore there is no peaking requirement on the selection of the red groups for Groups 1 through 4. However, there are two conditions which influence the location of the Group 4 rods and the Group 1 rods.
1
% e Group 4 rods may be briefly inserted into the core while the core is in'the j 1
Startup Mode (2) during physics testing. ' mus the location of the Group 4 rod assemblies is chosen such that they are eighth core symmetric. %ey are also positioned with respect to the location of Groups 5 through 7 to have a worth of approximately 1.0%&K/K.
%e Group 1 rods may be withdrawn any time the core is in either the Hot Standby, Hot Shutdown, or Cold Shutdown Modes by. increasing the. boren i concentration above that required by the shutdown margin with all control rods i in. '
% e reason for withdrawing Group 1 when going through a~ heat-up to the Startup Mode (2) is to provide an extra margin of safety by havirg sczne worth for a t
scram should one be r== mary. Sus the location of the Group 1 rods is chosen to be sylunetrical and to have a worth on the order of 1.0% in reactivity. %e results of the Group 1 worth are also ocmpared to the stuck rod worth such that the reactivity difference can be included in the requirunents for.the shutdown boron unceritration if mea 7y.
E e We location of the renainirq safety groups, '2 and 3, are selected to be'in the renaining locations, but may not be eighth core synnetrical. If the Group 1 ruds are towards the interior, the Group 2 rods will be more towards the periphery ard the Group 3 rods will be more towards the interior. If the Group 1 rods are towards the periphery, then the location of the Group. 2 and 3 rods will be reversed. me Group 2 rods will be more towards the interior, and the Group 3 rods towards the periphery.
%e methods and procedures used to analyze the reactivity and power peaking effects of the control rods are diawW in BAW-10118A and BAW-10122A as noted above. In order for these analyses to be valid, the location of the rod groups in the core must be the same as those in the Frapmu Figure. % e verification that the electrical connections of the rod groups do irdeed cotr=:speili to the:
Rod Fregmu Figure is specified in the Surveillance Requirements of Technical Specification 3.1.3.7. mis surveillance requirement provides the link between the design analyses and core operation.
.a f
M !syr r m r q REPUEL B3Di QM3lNBUEIGi h Core Operating Limits Report contains the ' specification for the refuel boron w s iL ation. 'Ihe pv wtires and methods of' analysis to determine the refuel boron saw a rcation are h ibed in the following paragraph.
N calculations are performed with the approved conputer codes, (1) PDQ (BAW-10117A (P), "Rahmr'k & Wilcox's Version of PDQ07--User's Manual, "H.A. Fa-rl, et. al., June, 1976), (2) N00 DIE (BAW-10152A, "A Multi-Dimensional 'IWo-Group Reactor Simulator," 0.W. Mays, et. al. , June,1985), and (3) FIAME (BAW-10124A, "A 'Ihree-Dimensional NODAL Code for Calculating Core Reactivity - and. Power Distributions," C.W. Mays, May, 1976). Technical Specifications set the requirements on the value of the effective neutron multiplication factor (Keff) for the core. To this value and additional 1.0% in reactivity is added to account for uncertainties.
h formula to determine the refuel boron unmakations is:
Refuel Boron (ppn) = Base Case Boron (ppn)
+ Inverse Boron Worth (ppa fy,4 g) x (Base Case reactivity (g) + 6p(Shutdown Feff + 1.0%)
+ 6( (Model Corrections) + 6q (Uncertainty))
+ 6 ppu (Uncertainty) h calculational procedure to determine the values of the terms in the above equation begins with the base case. h base case calculation has 140 F and 14.7 psia, BOL cold, conditions, no u.nikul rods inserted, and uses an estimated BOL cold boron uamd. ration. h results provide the ha= case reactivity. To the base case reactivity three differential reactivities are
added. We first is the differential reactivity frun the critical condition to the shutdown Keff includirg a 1.0% reactivity increase for mdeling uncertainties. We second differential reactivity corrects the base case for l
modeling biases. W ese biases are a result of the methods or approximations in the base case, such a two-diensional calculation. %e third differential reactivity is an adjustment for uncertainties in the core corditions.
Conditions such as the BOL core burnup which is estimated while the previous cycle is operating. Any estimates or uncertainties include a reactivity increase to ensure conservative analyses.
We sum of the base case reactivity plus the second and third differential reactivities produce a total reactivity which is near zero. 'Ihis small total reactivity is converted into a boron concentration by multiplying it by the inverse boren worth. We inverse boron worth is calculated fran two NOODIE cases run at two different boron concentrations, bracketing the boron concentration required for refueling. We change in tin boron concentration due to the total reactivity correction is added to the base case boron concentration to establish the refuel boron concentration.
We refuel boron concentration may be increased by an additional incremental amount to account for uncertainties in the methods and crocedures and provide conservatism. me uncertainties and conservatism would arise from the same type of conditions noted above for the third differential reactivity term (previous cycle length estimates, etc.).
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