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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
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en OENERAL OF FICE l ; P O BOX 499 COLUMDUS. NEBRASKA M0024499 l Nebraska Public Power District *7"i3l2F" i mesmmuzaar n =-w mumnc um -m _ w em s_ amu _ uy.= m 4
I:
i NSD920176 February 25, 1992 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Centlemen:
Subject:
Proposed Change No. 103 to Technical Specifications Clarification of DC Power System Technical Specifications Cooper Nucleer Station NRC Locket No. 50 298, DPR-46 1- In accordance with the applicable provisions specified in 10 CFR 50, the Nebraska Public Power District (District) requests that the Cooper Nuclear Station (CNS)
Technical Specifications be revised as specified in the attachment. The Dir.trict has determined that the CNS DC Power Systems technical specifications require clarification to better define DC System operability criteria, surveillance requirements, and actions to be taken following determination of unsatisfactory surveillance results. Therefore, the District proposes to change the CNS DC Power technical specifications to correspond .- the Standard Technical Specifications format to provide the necessary clarification.
Accordingly, the attached containt a description of the proposed change, the attendant 10 CFR 50.92 evaluation, and the CNS Technical Specification pages revised by the institution of this change. This proposed change has been reviewed by the necessary Safety Review Committees and incorporates all amendments to the CNS Facility Operating License through Amendment 151 issued Novcmber 19, 1991.
By copy of this letter and attachment the appropriate State of Nebraska of ficial is being notified in accordance with 10 CFR 50.91(b)(1) . Copies to the NRC y Region IV Of fice and the CNS Resident Inspector are also being sent in accordance with 10 CFR 50.4(b)(2).
9203030099 0201C2 920223 L
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- Page 2 of_.3 i February 25, 1992 Should you-have any q.iestions or require 'any additional information _please contact me.
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. llorn Nu( d ear Power Group ?!anager GRH/TJA/MJB-Attachment cc: it.R. Borchert Department of 11ealth State of Nebraska NRC Regional Administrator :
Region IV i Arlington, TX j NRC Resident Inspector i Cooper Nuclear Station !
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U. S. Nuclear Regulatory Commission
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PLATTE COUNTY )
G. R. llorn, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this requeat on behalf of Nebraska Public Power District; and that the statements containad herein are true to the best of his knowledge and belief.
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R.' llorn
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l Subscribed in my presence and sworn to before me thiscD day of Fv641LO Ad , 1992.
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d ler Comm. Erg Aug 4,1993 e
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.. - . - - - _ . . . _ - - . _ . - - . - -. . - . . ~ - . .
Attachment to NSD920176
- Page 1_of 6. l REVISED TECHNICAL SPECIFICATIONS CLARIFICATION OF DC POWER SYSTEM TECHNICAL SPECIFICATIONS e-Revised Pages 11 196 191 197 192 198 -
193- 199 194 200 195 I. I NTRODUCTIOl{
The Nebraska Public Power District (District) requests that the . NRC approve the proposed changes to the Cooper Nuclear Station (CNS) Technical Specifications described below. The proposed change clarifies the' performance criteria and surveillance requirements for the CNS DC Power Systems by reformatting ; them in accordence with the Fermi ? Standard Technical Specifications (STS), NUREC-1089.
The proposed changes are detailed below in Section II, and the Significant Hazards determination is provided in betion III. The District's analysis
- has . determined that- approval - of this proposed change involves no significant hazards consideration.
II. DESCRIPTION OF CHANCES The proposed changes are provided in Appendix A to this attachment. As discussed above, the changes consist of reformatting the CNS . DC . Power Systems technical specifications. The limiting conditions-for-operation *
(LCO) action statements have been ' revised, existing - surveillance requirements have_ been reformatted. .and. additional surveillance requirements were included to correspond with STS. In addition, several changes were made to the bases section concerning DC Power Systemr to also maintain consistency with the STS The Table of Contents changes and re-paginated section 3/4.9 are editorial changes only. The balance of the proposed changes-are described in the following discussion.
Format Channes (Pares 194 195. and 197)
The surveillance requirements for both the 125 VDC and - 250 . VDC unit.
batteries and chargers have been combined.
The electrolyte level float voltage, and specific gravity limits; for pilot cell and other connected cell values have been incorporated into new Technical Specification Table 3.9.1.
p c ana
. -Attachment to NSD920176
_Page 2 of 61 New, allowable values 'for each conne.cted cell consisting of electrolyte level, float voltage, and specific gravity have been defined and included in new Technical Specification Table 3.9.1.
LCO Action Statement.1Enge 194 and 195)
The existing Action Statement has been replaced with the following:
- "From and after the date'that one of the four unit 125 volt or 250 volt batteries is made or found to be inoperable for any reason, restore the inoperable battery to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN wir.hin the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."
"From and after the date that a unit battery charger is made or found to be inoperable, restore the inoperable ba:ter" charger to OPERABLE status or replace with the spare battery charger within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at Inest HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."
Surveillance Recuirements' (Pave 194 and 195)
Several new Surveillance Requirements have been added as discussed below. '
- All other changes relate to relocation of and/or reformatting of existing surveillance requirements in accordance with the STS format.
The' batteries will be verified operable within 7 days af ter a discharc to
- meet the new category B limits, which are the connected cell limits. This surveillance specifies acceptable discharge and overcharge terminal voltage values.
The batteries.will be verified quarterly that no visible corrosion exists at either terminal or connectors that could affect connection resistance, or the connection resistance of these items is less than 150 x 104 ohm.
Once each operating cycle the following will be verified: 1) the cell, cell plates,'and battery racks shall be visually inspected, 2) the cell-co-cell' and terminal connections are free of corrosion, and 3) the resistance of each cell to-cell and terminal connection is G 150 x 104 ohm.
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In addition, the required float voltage for the pilot cell and other connected cell limits has been reduced from 2.15 volts to 2.13 volts in accordance with the manufacturer's recommendations, and included in new Table 3.9.1. The District has verified that the voltage limit of 2.13-r volts provides . sufficient margin for .the batteries in meeting their design bases. Further, the electrolyte level surveillance has been changed from "between the minimum and maximum - level m4rks" to "2 Minimum level indication mark, and $ \" above the maximum level indication mark," and also relocated to new Tabic 3.9.1. This charge is more prescriptive, and is in accordance with the STS wording.
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. Attachment-to '
. NSD920176 Page 3 of 6 Bases Chantes (Pages 198. 199. and 200)
The changes to the_ Bases section are consistent with the wording found in STS for DC Power Systems. The bases now discuss NRC ondorsed standards which outline the surveillance requirements for demonstrating Operability, In addition the bases now discuss why the operability determinations and follow up actions ensure battery capacity, capability, and operability even during operation with a cell's parameter outside the normal limit but within the allowable limits.
i III. SIGNIFICANT HAZARDS DETERMINATION 10 CFR 50.91(a)(1) requires that licensee requests for operating license amendments be accompanied by an evaluation of significant hazards posed by -i the issuance of the amendment. This evaluation is to be performed with respect to the criteria given in 10 CFR 50.92(c). The following analysis meets these requirements.
Evaluation of this Amendmont with Respect to 10 CFR 50.92 The enclosed Technical Specifications change is judged to involve no significant hazards based on the following:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation This proposed change does not involve a significant increase in the ,
probability or consequences of an accident previously evaluated.
The proposed change reformats the existing DC Power System limiting conditions for operation and accompanying surveillance requirements into a format consistent with the Standard Technical Specifications, which is in accordance with applicable NRC guidance.
The CNS Technical Specifications, like the Standard Technical Specifications, currently provide a set of surveillance acceptance criteria associated with the station DC power sources. These criteria vary according to the appropriate surveillance interval, i.e. , weekly, quarterly, or during refueling. However, the Standard l Technical Specifications identify discrete actions associated with each surveillance requirement which are commencurate with the significance of surveillance results, and which provide an explicit means for determining DC Power System operability. In contrast, the CNS Technical Specifications provide only the action statement associated with the corresponding limiting condition for operation for battery inoperability, and while clearly defining surveillance test acceptance criteria, do not-clearly define the criteria for battery operability as with the STS. This proposed change will-
. reformat the DC Power System technical specifications to conform to the Standard Technical Specifications style which will assist the licensee in making accurate operability determinations and follow
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Attachment to i NSD920176 Page 4 of 6 i
appropriate actions.- Therefore, these format changes do not constitute a'significant increase in the probability or consequence of an accident previously evaluated.
In addition to improving DC Power System operability determinations, the change to the Standard Technical Specifications format will reduce the allowable reactor operation time with an inoperable j battery to correspond with applicable NRC guidance, Currently, the CNS Technical Specifications allow continued reactor operation with +
an inoperable station battery for a period of ten days. The Standard Technical Specifications. in accordance with NRC Regulatory Cuide li93, " Availability of Electric Power Sources," allow reactor operation to continue while atterepts are made to restore operability of the battery for a period of two hours af ter which the reactor ;
must be in llo t Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if battery ,
operability cannot be restored. Therefore, this change will significantly reduce the allowable reactor operation time with_an inoperable battery; accordingly, this change does not represent a significant increase in the probability of previously evaluated accidents.
. This proposed change also adds additional DC Power "ystem surveillance requirements, not currently in the CNS Technical Specifications, in accordance with the guidance provided in thu Standa/d Technical Specifications. These new surveillance requirements provide further assurance of battery operability and clarify operability determinations, and accordingly do not involve a signi"icant increase in the probability or consequences of an acc : dent previously evaluated.
This proposed change lowers the minimum float voltage for the_ pilot '
cell and other connected cells - from 2.15 to 2.13 volts . This value is consistent with the vendor (C - & D) recommendations for the acceptable float voltage for the type of batteries installed (lead calcium) at CNS for the category A and B limits as defined in the STS and the attached Table 3.9.1. In no way does the reduction of this new float voltage value affect the capability of the DC power system to perform its intended safety function. The vendor has indicated and the District has verified that a voltage of 2,13 volts for each connectec' cell will ensure the battery's capability to
-perform its desiga function.
These category A and B values provide the first level of surveillance and resulting evaluation. The category B allowable ,
value of 2.10 volts for a connected-cell ensures the capability of the remaining buttery cells to perform their design function. The battery vendor has indicated,- and District eagineering has verified that the battery is capable of performing its design function with a cell value much lower than the category B allowable value, therefore, reduction of the category A and B float voltage from 2,15 volts to 2.13 volts and the generation of a category B absolute allowable value of 2.10 volts and their attendant corrective actions does not constitute a significant increase in the probability or consequences of an accident previously evaluated.
Attachment to NSD920176
- Page 5 of 6 Based = on
- the above discussions. the .changas proposed - in. this amendment request do not represent-a significant increase in the ;
probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility for a- new or-
, .different kind of accident from any accident previously evaluated? ,
Evaluation This proposed change will-revise the LCO action statements and the surveillance requirements for the CNS DC Power Syster to conform to the Standard Technical Specifications style which will assist and improve the ability of the licensee to make accurate operability determinations and follow appropriate actions concerning the DC power system. This proposed change _ will not involve any plant design change, affect any plant desien criteria, or change the operation or the function of the DC power system as described in the USAR. This proposed change also does . 'no t allow any new mode of plant operation. Therefore, this proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change create a significant reduction in the margin of safety?
{ valuation This proposed change does not change existing facility equipment or represent any new mode of plant operation. This proposed change incorporates additiona'. surveillance requirements and reformats the existing surveillance requirements of the DC power system, making them more stringent than previously . required. The additional surveillance requirements and new format style is consistent with- -
the existing requirements and use NRC endorsed criteria for DC power 1 systems. Additionally, this proposed change will not reduce . the capability of the 125 volt and 250 volt battery systems to perform '
their_ intended function, therefore maintaining the margin of safety, l The remaining changes consist of reformatting the DC Power System technical specifications to conform to the Standard Technical Specifications style which will assist the District in making accurate operability determinations and follow appropriate actions.
Based on this discussion, this proposed change does not involve a-significant reduction in the margin of safety.
IV. CONCLUSION The District has evaluated the proposed changes described above against i the criteria given in 10 CFR 50.92(c) in accordance with the requirements of 10 CFR 50.91(a)(1) . This evaluation has determined that this proposed change does not 1) involve a significant increase in the probability or consequences of an accident previously evaluated, 2) create the
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Attachment to
' .NSD920176~
Page 6 of'6 possibility for a new or 'different kind' of accident from any. accident
- previously evaluated, or 3). create a significant reduction in the margin of ' safety. Therefore, for the reasons detailed above, the District-requests NRC approval of this Proposed Change 103, i
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