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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217C7871999-10-0606 October 1999 Application for Amend to License DPR-46,to Revise TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5 to Adopt Implementation Requirements of 10CFR50,App J,Option B,For Performance of Type A,B & C Containment Leakage Rate Testing ML20195J6961999-06-15015 June 1999 Application for Amend to License DPR-46 to Allow USAR Change to Establish Leakage Criteria for Reactor Equipment Cooling (REC) Sys Which Is Sufficiently Conservative to Assure REC Operation at Least Seven Days Following Large Break LOCA ML20195J3961999-06-15015 June 1999 Application for Amend to License DPR-46,revising Containment Overpressure Contribution to ECCS Pump,Revising NPSH Requirement post-LOCA & Revising Encl USAR Section 5.2.6. Proprietary GE Repts Encl.Proprietary Info Withheld ML20195E8951999-06-0808 June 1999 Application for Amend to License DPR-46,correcting Method by Which SGTS Heaters Are to Be Tested ML20205H2831999-03-31031 March 1999 Application for Amend to License DPR-46,modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236Y4921998-08-0606 August 1998 Application for Amend to License DPR-46,accepting as-built Plant Configuration Involving Unreviewed Safety Question as Specified in Attachment 1 ML20216H0481998-04-15015 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS 4.2.C.Application Supersedes 980402 Request.Revised OL Pages,Encl ML20216H0731998-04-15015 April 1998 Application for Amend to License DPR-46,deleting Max Rated Power for APRM Rod Block Trip Setting in TS Sections 2.1.A.1.d & 3.2.C.Revised OL Pages,Encl ML20217Q2551998-04-0202 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS Table 4.2.C.Revised Operating License Pages,Encl ML20148G2981997-05-30030 May 1997 Application for Amend to License DPR-46,changing TS Re Frequency of Testing RHR Cross Tie Valve Position Indication from Once Per Month to Once Per Operating Cycle ML20138J0691997-05-0505 May 1997 Application for Amend to License DPR-46,relocating Control of Standby Liquid Control Relief Valve Setpoint in TS Section 4.4.A.2.a & Associated Bases ML20148A9971997-05-0202 May 1997 Application for Amend to License DPR-46 Ts,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20147H5441997-03-27027 March 1997 Application for Amend to License DRP-46 Re Proposed Change to TSs to Convert to Improved STS ML20134K3651997-02-10010 February 1997 Application for Amend to License DPR-46 to Provide Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term.. ML20117K3231996-06-0606 June 1996 Application for Amend to License DPR-46,revising TS Section 1.1, Fuel Cladding Integrity, Subsection 1.1.A to Specify New MCPR Value of 1.07.Rev 3 of GE Rept 24A5187, Suppl Reload Licensing Rept for CNS Reload 16 Cycle 17 Encl ML20100R4361996-03-0505 March 1996 Application for Amend to License DPR-46,consisting of Change Request 142,revising TS, DG Enhancements ML20086B7021995-06-28028 June 1995 Application for Amend to License DPR-46.Amend Would Increase RPV Boron Concentration & Mod Surveillance Frequency for SLC Pump Operability Testing ML20085J2571995-06-15015 June 1995 Application for Amend to License DPR-46.Amend Would Extend Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7101995-05-0505 May 1995 Application for Amend to License DPR-46.Amend Would Revise Listed TSs & Associated Bases ML20083A1281995-05-0202 May 1995 Application for Amend to License DPR-46.Amend Would Temporarily Revise SR 4.7.A.2.f.1 to Extend Two Year LLRT Interval Requirement ML20078F4371995-01-27027 January 1995 Suppl to 950126 Proposed Change 135 to License DPR-46 Re Control Room Emergency Filter Sys ML20078S5641994-12-22022 December 1994 Proposed Change 148 to License DPR-46,revising Definition of LCO Consistent W/Guidance Provided in NRC GL 87-09 ML20073J2271994-09-26026 September 1994 Application for Amend to License DPR-46,consisting of Proposed Change 136,revising TS LCOs 3.5.C.1 & 3.5.C.4 to Increase Min Pressure at Which HPCI Sys Required to Be Operable ML20071K1231994-07-26026 July 1994 Application for Amend to License DPR-46,revising CNS TS to Increase Flow Capacity of Control Room Emergency Filter Sys ML20070M6601994-04-26026 April 1994 Proposed Change 126 to License DPR-46,revising TS Tables 3.2.H & 3.2.F,including Associated Notes to Clarify Requirements Re Intermittent Sampling of Hydrogen & Oxygen Concentrations During Normal Plant Operations ML20058N2261993-12-10010 December 1993 Proposed Change 115 to License DPR-46 Ts,Extending Reporting Frequencies of Semiannual Radioactive Matls Release Rept from Semiannual to Annual & Annual Design Change Rept from Annual to Annually or Along W/Usar Updates ML20058N2791993-12-10010 December 1993 Proposed Change 119 to License DPR-46 Ts,Revising Pressure Vs Temp Operating Limit Curves for Plant Based on Results of Testing & Analysis Performed as Part of Util Reactor Vessel Matl Surveillance Program ML20058M2541993-09-28028 September 1993 Application for Amend to License DPR-46,requesting TS Be Revised to Modify Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operations ML20056G5911993-08-31031 August 1993 Proposed Change 120 to License DPR-46,adding Requirements for Primary Containment Isolation of Drywell Air Sampling Sys to Clarify Requirements for Instrumentation to Initiate Primary Containment Isolation Signals ML20056G5721993-08-31031 August 1993 Proposed Change 106 to License DPR-46,revising TS Sections Pertaining to Standby Gas Treatment Sys & Secondary & Primary Containment Isolation Valves ML20056F3311993-08-23023 August 1993 Proposed Change 121 to License DPR-46,changing TS 6.0, Administrative Controls to Modify Organizational Structure by Creating Mgt Position of Vice President - Nuclear ML20045C8281993-06-14014 June 1993 Proposed Change 117 to License DPR-46,revising TS to Incorporate New Requirements in 10CFR20.Advises That Util Plans to Implement Revised Part 20 on 940101 ML20128E5961993-02-0101 February 1993 Application for Amend to License DPR-46,revising TS to Reflect Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8291993-01-0505 January 1993 Proposed Change 116 to License DPR-46,changing TS to Remove Bus 1 a & 1B Low Voltage Auxiliary Relays for RHR & Core Spray Sys as Result of Plant Mods to Be Implemented During Spring 1993 Refueling Outage ML20115F2591992-10-15015 October 1992 Rev to 920504 Application,Consisting of Proposed Change 100, Eliminating Main Steam Line Radiation Monitor to Accurately Ref Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3421992-10-0808 October 1992 Application for Amend to License DPR-46,consisting of Proposed Change 111 to Ts,Modifying Onsite Organizational Structure by Creating New Site Mgt Positions to Ensure Acceptable Performance of Util Staff ML20104B2041992-09-0909 September 1992 Proposed Change 110 to License DPR-46,revising TS Table 3.1.1 Re Reactor Protection Sys Instrumentation Requirements to Indicate That MSIV Closure Scram Only Required While in Run Mode & Adding Settings for Core Spray & RHR Sys ML20104A8631992-09-0202 September 1992 Proposed Change 84 to License DPR-46,changing TS to Increase Min Amount of Diesel Fuel Oil Capacity Required to Be Available in Onsite Diesel Fuel Oil Storage Tanks ML20099D4101992-07-28028 July 1992 Proposed Change 109 to License DPR-46,changing TS to Revise pressure-temp Limitation Curves Beyond Current 12 EFPYs & Removing Vessel Matl Surveillance Capsule Withdrawal Schedule from TS Per Guidance in Generic Ltr 91-01 NLS9100589, Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-081992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-08 ML20096D6021992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of TS Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A7861992-02-25025 February 1992 Application for Amend to License DPR-46,consisting of Proposed Change 103,clarifying Dc Power Sys TSs to Better Define Dc Power Sys Operability Criteria NLS9100488, Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power1991-11-15015 November 1991 Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power NLS9100409, Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-361991-10-0707 October 1991 Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-36 NLS9100581, Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table1991-10-0303 October 1991 Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table NLS9100058, Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems1991-09-30030 September 1991 Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems NLS9100394, Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-091991-08-0505 August 1991 Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-09 NLS9100187, Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790)1991-07-29029 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790) NLS9100459, Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation1991-07-19019 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation NLS9100460, Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels1991-07-18018 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels 1999-06-08
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C7871999-10-0606 October 1999 Application for Amend to License DPR-46,to Revise TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5 to Adopt Implementation Requirements of 10CFR50,App J,Option B,For Performance of Type A,B & C Containment Leakage Rate Testing ML20195J6961999-06-15015 June 1999 Application for Amend to License DPR-46 to Allow USAR Change to Establish Leakage Criteria for Reactor Equipment Cooling (REC) Sys Which Is Sufficiently Conservative to Assure REC Operation at Least Seven Days Following Large Break LOCA ML20195J3961999-06-15015 June 1999 Application for Amend to License DPR-46,revising Containment Overpressure Contribution to ECCS Pump,Revising NPSH Requirement post-LOCA & Revising Encl USAR Section 5.2.6. Proprietary GE Repts Encl.Proprietary Info Withheld ML20195E8951999-06-0808 June 1999 Application for Amend to License DPR-46,correcting Method by Which SGTS Heaters Are to Be Tested ML20205H2831999-03-31031 March 1999 Application for Amend to License DPR-46,modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236Y4921998-08-0606 August 1998 Application for Amend to License DPR-46,accepting as-built Plant Configuration Involving Unreviewed Safety Question as Specified in Attachment 1 ML20216H0481998-04-15015 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS 4.2.C.Application Supersedes 980402 Request.Revised OL Pages,Encl ML20216H0731998-04-15015 April 1998 Application for Amend to License DPR-46,deleting Max Rated Power for APRM Rod Block Trip Setting in TS Sections 2.1.A.1.d & 3.2.C.Revised OL Pages,Encl ML20217Q2551998-04-0202 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS Table 4.2.C.Revised Operating License Pages,Encl ML20148G2981997-05-30030 May 1997 Application for Amend to License DPR-46,changing TS Re Frequency of Testing RHR Cross Tie Valve Position Indication from Once Per Month to Once Per Operating Cycle ML20138J0691997-05-0505 May 1997 Application for Amend to License DPR-46,relocating Control of Standby Liquid Control Relief Valve Setpoint in TS Section 4.4.A.2.a & Associated Bases ML20148A9971997-05-0202 May 1997 Application for Amend to License DPR-46 Ts,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20147H5441997-03-27027 March 1997 Application for Amend to License DRP-46 Re Proposed Change to TSs to Convert to Improved STS ML20134K3651997-02-10010 February 1997 Application for Amend to License DPR-46 to Provide Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term.. ML20117K3231996-06-0606 June 1996 Application for Amend to License DPR-46,revising TS Section 1.1, Fuel Cladding Integrity, Subsection 1.1.A to Specify New MCPR Value of 1.07.Rev 3 of GE Rept 24A5187, Suppl Reload Licensing Rept for CNS Reload 16 Cycle 17 Encl ML20100R4361996-03-0505 March 1996 Application for Amend to License DPR-46,consisting of Change Request 142,revising TS, DG Enhancements ML20086B7021995-06-28028 June 1995 Application for Amend to License DPR-46.Amend Would Increase RPV Boron Concentration & Mod Surveillance Frequency for SLC Pump Operability Testing ML20085J2571995-06-15015 June 1995 Application for Amend to License DPR-46.Amend Would Extend Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7101995-05-0505 May 1995 Application for Amend to License DPR-46.Amend Would Revise Listed TSs & Associated Bases ML20083A1281995-05-0202 May 1995 Application for Amend to License DPR-46.Amend Would Temporarily Revise SR 4.7.A.2.f.1 to Extend Two Year LLRT Interval Requirement ML20078F4371995-01-27027 January 1995 Suppl to 950126 Proposed Change 135 to License DPR-46 Re Control Room Emergency Filter Sys ML20078S5641994-12-22022 December 1994 Proposed Change 148 to License DPR-46,revising Definition of LCO Consistent W/Guidance Provided in NRC GL 87-09 ML20073J2271994-09-26026 September 1994 Application for Amend to License DPR-46,consisting of Proposed Change 136,revising TS LCOs 3.5.C.1 & 3.5.C.4 to Increase Min Pressure at Which HPCI Sys Required to Be Operable ML20071K1231994-07-26026 July 1994 Application for Amend to License DPR-46,revising CNS TS to Increase Flow Capacity of Control Room Emergency Filter Sys ML20070M6601994-04-26026 April 1994 Proposed Change 126 to License DPR-46,revising TS Tables 3.2.H & 3.2.F,including Associated Notes to Clarify Requirements Re Intermittent Sampling of Hydrogen & Oxygen Concentrations During Normal Plant Operations ML20058N2261993-12-10010 December 1993 Proposed Change 115 to License DPR-46 Ts,Extending Reporting Frequencies of Semiannual Radioactive Matls Release Rept from Semiannual to Annual & Annual Design Change Rept from Annual to Annually or Along W/Usar Updates ML20058N2791993-12-10010 December 1993 Proposed Change 119 to License DPR-46 Ts,Revising Pressure Vs Temp Operating Limit Curves for Plant Based on Results of Testing & Analysis Performed as Part of Util Reactor Vessel Matl Surveillance Program ML20058M2541993-09-28028 September 1993 Application for Amend to License DPR-46,requesting TS Be Revised to Modify Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operations ML20056G5721993-08-31031 August 1993 Proposed Change 106 to License DPR-46,revising TS Sections Pertaining to Standby Gas Treatment Sys & Secondary & Primary Containment Isolation Valves ML20056G5911993-08-31031 August 1993 Proposed Change 120 to License DPR-46,adding Requirements for Primary Containment Isolation of Drywell Air Sampling Sys to Clarify Requirements for Instrumentation to Initiate Primary Containment Isolation Signals ML20056F3311993-08-23023 August 1993 Proposed Change 121 to License DPR-46,changing TS 6.0, Administrative Controls to Modify Organizational Structure by Creating Mgt Position of Vice President - Nuclear ML20045C8281993-06-14014 June 1993 Proposed Change 117 to License DPR-46,revising TS to Incorporate New Requirements in 10CFR20.Advises That Util Plans to Implement Revised Part 20 on 940101 ML20128E5961993-02-0101 February 1993 Application for Amend to License DPR-46,revising TS to Reflect Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8291993-01-0505 January 1993 Proposed Change 116 to License DPR-46,changing TS to Remove Bus 1 a & 1B Low Voltage Auxiliary Relays for RHR & Core Spray Sys as Result of Plant Mods to Be Implemented During Spring 1993 Refueling Outage ML20115F2591992-10-15015 October 1992 Rev to 920504 Application,Consisting of Proposed Change 100, Eliminating Main Steam Line Radiation Monitor to Accurately Ref Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3421992-10-0808 October 1992 Application for Amend to License DPR-46,consisting of Proposed Change 111 to Ts,Modifying Onsite Organizational Structure by Creating New Site Mgt Positions to Ensure Acceptable Performance of Util Staff ML20104B2041992-09-0909 September 1992 Proposed Change 110 to License DPR-46,revising TS Table 3.1.1 Re Reactor Protection Sys Instrumentation Requirements to Indicate That MSIV Closure Scram Only Required While in Run Mode & Adding Settings for Core Spray & RHR Sys ML20104A8631992-09-0202 September 1992 Proposed Change 84 to License DPR-46,changing TS to Increase Min Amount of Diesel Fuel Oil Capacity Required to Be Available in Onsite Diesel Fuel Oil Storage Tanks ML20099D4101992-07-28028 July 1992 Proposed Change 109 to License DPR-46,changing TS to Revise pressure-temp Limitation Curves Beyond Current 12 EFPYs & Removing Vessel Matl Surveillance Capsule Withdrawal Schedule from TS Per Guidance in Generic Ltr 91-01 NLS9100589, Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-081992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-08 ML20096D6021992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of TS Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A7861992-02-25025 February 1992 Application for Amend to License DPR-46,consisting of Proposed Change 103,clarifying Dc Power Sys TSs to Better Define Dc Power Sys Operability Criteria NLS9100488, Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power1991-11-15015 November 1991 Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power NLS9100409, Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-361991-10-0707 October 1991 Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-36 NLS9100581, Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table1991-10-0303 October 1991 Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table NLS9100058, Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems1991-09-30030 September 1991 Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems NLS9100394, Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-091991-08-0505 August 1991 Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-09 NLS9100187, Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790)1991-07-29029 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790) NLS9100459, Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation1991-07-19019 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation NLS9100460, Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels1991-07-18018 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels 1999-06-08
[Table view] |
Text
_
a.
b-h Nebraska Public Power District #
" "?N5bfshMf"'-"
December 22, 1987 U.S. Nuclear Regulatory Commission Document ~ Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Proposed Change No. 54 to - Technical Specifications Cooper Nuclear Station' N R C Docket No. 50-298, D PR-46 In accordance with the ap plicable provisions specified in 10CFR50, Nebraska Public Power District requests that Technical Specifications for Cooper Nuclear Station (C NS) be' revised to modify the operating requirements for the Rod Sequence Control System (RSCS) and Rod Worth Minimizer (RWM).- The changes ,
will allow the Banked Position Withdrawal' Sequence to be followed I for the first 50% of control rod withdrawals resulting in lower maximum rod worths during startu p. Several administrative changes in the Technical Specification Bases are also requested.
A discussion and the applicable revised Technical Specification pages are contained in Attachment 1. The modifications to the Technical Specifications within this proposed change have been evaluated with respect to the requirements of 10C FR50.92. The results of the evaluations are also included in the attachment.
This proposed change incorporates all amendments to the CNS Facility O perating License throug h Amendment 112 issued October 27, 1987. By copy of this letter and attachment the appropriate State of Nebraska official is being notified in accordance with 10C FR50.91(b).
This change has been reviewed by the necessary Safety Review Committees and payment of $150 is submitted in accordance with 10 C F R170.12.
8712290242 871222 hoo\
PDR ADOCK 05000298 p.00 r 'g getJw uco' g.,.
Page 2' .I December 22, 1987 l
In addition to the: signed. original, 37 copies 'are also submitted for ~your use. Copies to the NRC Region IV Office and theLCNS.
Resident Inspector are also being sent in accordance : with 10 C F R 50.4(b)(2) . - Should you have any questions .or require additional .information, please contact me.
Sincere y, 4
L . G . K u nci Vice-President - N uclear L G K/grs:dmr3/4 -
Attach ment cc: H. R. Borchert ..
Department of Health State of Nebraska N R C . Regional Office Region IV Arlington, TX l N RC Resident Inspector Office Cooper Nuclear Station i
-l l
i
.! Page 3 December 22, 1987 ,
ST ATE OF NEBRASKA)
)ss PLATTE COUNTY )
L. G. Kuncl, being first duly sworn, deposes and says that he is an authorized repre::entative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to sLbmit this request on behalf of Nebraska Public Power District; and that the statements contained herein are true to the best of his knowledge and belief.
L . 6) K u ncl S u bscribe in m resence and sworn to before me this day of 01 % O , 1987.
- N O T A R Y P U B,LIC
- h. Y ~
seem mun am n ===
conEEN M. KUTA Ny Ceest Em Aug 4,195 i
- e < . - Attachmsnt II Revised Technical' Specifications for RSCS and RWM Operability.-
Revised Pages: 95 . .
100 95a (deleted) 101 96 101a:
99 104
Reference:
- 1) NRC Letter from Cecil O. Thomas to J. S. Charnley. " Acceptance
= for Referencing of Licensing. Topical Report NEDE-240ll-P-A.
' General Electric Standard Application for Reactor Fuel ,
Revision 6, Amendment 12," October. 11,.1985.
- 2) General Electric Service Information Letter ' No. - 316 Reduced Notch Worth Procedure, November 1979.
In order'to minimize control. rod reactivity worths' associated with the Control' Rod Drop Accident (CRDA), BWR control- rods are; pulled in specific; patterns during startup that are supervised.by. control ~ systems: such as the Rod Worth Minimizer (RWM) computer program or the hard wired Rod Sequence Control System-(RSCS). These rod patterns fall.into two classes of operation'for BWR. plants and restrict rod motions:to ensure that a postulated'CRDA will'not result'in peak fuel enthalpies in excess. of 280 calories per gram.for; the Lentire range of plant operations at.d core ' exposures.
Some BWR/4s, including Cooper Nuclear Station, are Group ^ Notch Rod Sequence Control System (CNRSCS) plants which utilize the'RSCS.with the RUM as.a backup to prevent high control rod reactivity worths. During 'startup ' prior to reaching the 50 percent rod density pattern, each of the control rods can be withdrawn in a specified sequence from its full in to its full out. position in one continuous. motion. Once the 50 percent' rod density pattern (checkerboard) is reached, further rod withdrawals take place in defined banks one notch at a time until a preset rated reactor power level is reached at which time RSCS constraints on rod patterns for CRDA consequences are not required. Above this minimum power setpoint the consequences of Ja' CRDA are mitigated by the presence of steam voids in the coolant which provided an additional negative reactivity feedback mechanism and the CRDA is of minimal safety fconcern.
Other BWR plants utilize a Bank'ed Position Withdraw Sequence "(BPWS) which restricts the first 50 percent of the rods withdrawn so ' that they 'are scepped out in a specified (banked) pattern rather than in one-continuous motion. This method of withdrawal is used for rod movement beyond the 50 percent density as well. The RSCS is not used in the sequence and rod motion is controlled by the RWM alone. Due to the use of the banked positions for. the first 50% of the rod withdrawal (pre-checkerboard), the BPWS 1 results in lower peak' rod reactivity worths for the CRDA than the GNRSCS pattern. Beyond 50% of rod withdrawal (post-checkerboard) the GNRSCS patterns provide a somewhat lower worth than the corresponding BPWS patterns.
~
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'.I For GNRSCS plants, the higher rod worths for the pre-checkerboard pattern result in an expensive and time-consuming analysis for each core reload of the Reference Loading Pattern to predict the results of a potential CRDA. At -
times the core has to be redesigned solely to meet. the CRDA limits with the resulting reload core configuration less than optimal for fuel cycle cost considerations. For the BPWS plants the rod worths are sufficiently low both in the first 50% rod withdrawal and beyond that statistical studies conclude with a high degree of confidence-that the CRDA will not exceed the required limits and that reload analyses for the accident are not required.for core reinads. If the GNRSCS plants could use the BPWS for the first.50% and the group notch mode for post-checkerboard rod movement (since the CNRSCS rod worths are lower), then they could take credit for the BPWS statistical analysis and eliminate the need for a reload CRDA analysis. Reference 1 evaluated the use of and credit for the BPWS in the pre checkerboard region for those plants which utilize the GNRSCS and found it to be acceptable.
Reference 1 went on to state "that it is preferable for the CNRSCS plants to have the improved pattern control of the BPWS as monitored by the RWM for.the first 50 percent of withdrawal. The ~ GNRSCS group notch ' mode should be retained beyond 50 percent. Plants making the change will be able to take I
credit for the statistical analysis of the CRDA and will not have to analyze the event for reloads." Reference 1 further stated that plants wishing. to make this change are to change Technical Specifications as required and to j
indicate that BPWS patterns will be enforced during applicable operations.
Cooper Nuclear Station currently u'tilizes the Reduced Notch Worth Procedure (Reference 2), which is basically an extension of BPWS, for the RWM input. As such, the RWM imposes more severe constraints on rod motion during the first 50% than does the RSCS. Plant startup and shutdown rod motion' operations will not be significantly changed by adapting the BPWS for the . first 50% rod density since the Reduced Notch Worth Procedure is being followed as recommended in Reference 2.
Consequently, the District requests changes be made to the CNS Technical Specifications to require adherence to a BPWS for RWM input and to delete RSCS operability requirements for the withdrawal of the first 50 percent of the rods from the core. From 50 percent rod density to 20 percent rated thermal power rods will continue to be withdrawn in the group notch mode as controlled by the RSCS. With the more restrictive (lowe.r maximum rod worth) BPWS pattern in place being supervised by the RWM computer system, the RSCS can be inoperable while the BPWS is in effect. Specifically, the following changes are proposed: ~
- 1. On Page 95 amend Sections 3.3.B.3a and 3.3.B.3b to require the RSCS to be l operable from the 50% rod density to 20 percent of rated thermal power region.
- 2. On Page 95 revise the surveillance requirements for the RSCS by deleting the sequence portion of the testing and reformatting the group notch j portion of the checks for startup and shutdown.
- 3. Repaginate Specification 4.3.B.3.b to Page 95 and delete Page 95a in its entirety. I l
- 4. On Page 96 amend Specification 4.3.3.3.b.11 to verify the correctness of the BPWS input to the RkH computer.
- 5. Amend the Bases on Page 101a to discuss the use of the BPWS.
- 6. Add Reference No. 4 to Page 104 on Reduced Notch Worth Procedure.
- 7. Finally, the District requests to amend the bases on Pages 99, 100, and 101 to change references of the Final Safety Analysis Report to the l Updated Safety Analysis Report. Also on Page 101, a no longer applicable l
USAR reference has been deleted.
I Evaluation of this Revision with Respect to 10CFR50.92 g A. The encic ed Technical Specification change is j udged to involve no significant hazards based on the following:
- 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluetion: I
- a. The proposed amendment would allow the. Rod Worth Minimizer (RkM), enforcing the Banked Position Withdrawal Sequence, to take -the place of the Rod Sequence Control System (RSCS) in controlling the allowed control rod patterus and rod reactivity worths during the period from all rods inserted into the core to 50% of the rods withdrawn. The use of the RkH enforcing the, Banked Position Withdrawal Sequence (BPWS) has been evaluated to lessen the consequences of a Control Rod Drop Accident over the present use of the RSCS during the first 50% of rod withdrawal because the BPWS bank positions result in lower peak rod reactivity worths. Thus, the use of the RkH utilizing the BPWS during the first 50% of rod withdrawal will reduce the consequences of any Control Rod Drop Accident (CRDA). The probability of the CRDA is not affected by the change ao current control rod to drive mechanism coupling requirements and surveillance remain .in effect. The proposed amendment )
affects no other evaluated accident scenarios. ,
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- b. The proposed amendment also contain various changes to the {
bases section that are administrative in nature, namely changing reference from the Final Safety Analysis Report (FSAR) {'
to the Updated Safety Analysis Report (USAR) which is periodically revised to reflect current plant configuration, analysis and operation. Additionally, an out-of-date reference is being deleted. These administrative changes do not affect any of the assumptions or analysis contained in the Safety j Analysis Report and hence do not increase the probability or consequences of any previous evaluated accident.
- 2. Does the proposed licensa amendment create the possibility for a new or difference kind of accident from any accident previously evaluated?
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Evaluation: ,
- a. The proposed amendment places a new restriction on rod' motion - i
'during the first 50% of red withdrawal to re' duce ' peak' rod . .
reactivity and miti;, ate the effects of a hypothetical- Control )
Rod Drop Accident.' No new mode-of plant operation is created
~'or made possible by the change ~which ^only affects. control rod j
, movement blocks. The . proposed -. amendment (does not create the ,
. possibility _ for a. new or different kind 'of. accident ' froml any -
i previously evaluated.H i
- b. The proposed . administrative changes ' have no , effect on plant-operation or its underlining analysis,: so will not create the-possibility for a new or different kind of accident.
- 3. Does . the proposed amendment involve a significant : reduction in' a margin 'of safety? -
- a. As explained above,' the proposed amendment places additionali I
rod motion.r'estraints in the'first 50% of rod ' withdrawal' that '
results.in lower peak: rod reactivity worths. This will' result' in a lower peak enthalpy reached in the fue1~in the' event'of a-Control Rod Drop Accident and will add' additional margin to the:
280 calories / gram limit. The proposed change does.not involve a significant reduction in~a margin of safety.
- b. The proposed administrative changes have :no effect on plant operations or the value of its safety limits and involves no .
significant reduction in a margin of safety.
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