Application for Amend to License DPR-46,consisting of Proposed Change 98,changing Tech Specspage 55 Re Voltage Relay Setting LimitsML20082B889 |
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Cooper |
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07/10/1991 |
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NEBRASKA PUBLIC POWER DISTRICT |
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ML20082B887 |
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References |
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NLS9100446, NUDOCS 9107170116 |
Download: ML20082B889 (5) |
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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] |
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NLS9100446 Attachment 1 Page 1 of 5 Emergenty Technical Specification Change Proposed Change No. 98 (Revised Loss of Voltr3e Relay - Setting Limits)
Technical Specification Page 55 Refereace: 1) Telecon between J . M. Meacham (NPPD) and John Zwolinski (NRC) on July 9,1991, Request for Waiver of Compliance
- 2) Letter from G. Lear (NRC) to J. M. Pilant (NPPD) dated April 11, 1978, CNS Amendment No. 43 to CNS Technical Specifications
- 3) Letter from J. M. P11 ant (NPPD) to D. K. Davis (NRC) dated July 18,1977, Electrical Under Voltage Protection BACKGROUND License Amendment No. 43 (Reference 2) approved, among other things, the addition of and setting limits for the first level undervoltage relays or (loss of voltage relays) 27/1FA-1, 27/lF-1, 27/1CB 1, 27/1G-1, and 27/ET-1 (27/ET-2 was added by Amendment 75), Also this Amendment approved the addition of and the setting limits for the second level undervoltage or (degraded voltage relays) 27/lF-2, 27/1FA-2, 27/10-2, and 27/lGB-2. These relays and settings limits were included in the CNS Technical Specifications in response to an NRC request (Reference 3).
This request addressed the susceptibility of the on-site emergency power system to sustained degraded grid voltage conditions at the offsite power source and the interactions between the offsite and on-site emergency power systems, lt also requected modifications be made if necessary and that Technical Specification changes be submitted to comply with the Staff's position.
During the course of the District's Design Basis Review of the Standby AC Power System, the design settings of Loss of Voltage Relays were determined to be outside of the settings limits specified in the CNS Technical Specifications. By Reference 1. the Nebraska Public Power District requested a Walver of Compliance to the Cooper Nuc! ear Station (CNS) Technical Specifications regarding the CNS Loss of Voltage Relays setting limits. During this telecon the District was granted an Oral Waiver of Compliance. The Nuclear Regulatory Commission, in Reference 1, notified the District that an Emergency Technical Specification Change would be necessary to resolve this concern.
The critical buses (lF and 1G) are monitored for loss of voltage conditions by the first level (loss of voltage) relays. This protective function utilizes inverse time delay relays. There are two settings associated with these relays.
The tap setting determines the point that the relay will actuate and the time dial setting determines the prescribed time delay curve. The combination of these parameters uniquely identifies the operating characteristics which form an inverse time-voltage curve. This setting limit is currently listed in the Technical Specification as 2900 V 5 Percent, 5 seconds i 1 second time delay.
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i 1
NLS9100446 Attachment 1 Page 2 of 5 The first level undervoltage (loss of voltage) relays for buses IF and IG (27/1F-1, 27/1G 1) perform the following two actions: a) Initiate load shedding of the 4160 volt motor loads on Bus IF and 1G; and b) Provide a start signal to the emergency diesels. The remaining first level undervoltage (loss of voltage) relays (27/1FA-1, 27/lGB 1) have a slightly longer time delay and trip the tie breakor from Bus lA/1B to-Dus 1F/lG. This extra time delay is to allow the shedding of loads prior to closing breakers IFS /1GS (which close immediately after tripping IFA/1GB), The second level undervoltat,e logic will only trip the tie breaker IFA/1GB, which will initiate the first level undervoltage relays to accomplish actions a) and b).
The functions of relays 27/ET-1, and 27/ET-2 are to: a) Provide an interlock to prevent the closing of Emergency Transformer (ET) Tie Breakers IFS and ICS, respectively, during loss of the ET and, b) Trip breakers IFS and 1GS if a loss of the ET occurs while operating from the ET The Emergency Transformer also has second level undervoltage protection that provides an interlock to prevent the closing of Breakers IFS and 1GS during degraded voltage conditions on the ET and its 69kV feeder line.
SAFETY EVALUATION
[ The relays at issue (first level) monitor the Gritical AG bus.s for a loss of l voltage condition and were installed as part of the original de. sign of GNS. Later modifications added the second level undervoltap protectior (Reference 2), The original design setpoints (tap and time dial setting) were determined by Burns and Roe calculation 2.09.06. Thesc two settings identify a unique time voltage curve that 6 scribes the operation of the relay.
The design - bases for the first level relaya a9 oefined in Burns and Roe calculation 2.09.06 are:
- 1) Both 27-1F1/27-101 and 27-1FA1/27-1GB1 must ride through (i.e. not pick up-and time out) during motor starting cycles at 70% voltage for 5 seconds.
l
- 2) 27-1Fl/27 1G1 must initiate motor trips: immediately and initiate a permissive signal to load the diesel generator on the bus in 8.5 seconds if-the offsite supply voltage has not stabilizad.
- 3) 27-lFAl/27-1GB1 must trip breaker 1FA/lGB which autom stically closes breaker 1FS/ LGS to the emergency transformer.
- 4) The emergency transformer tie breaker 1FS/1G5 must close on the bus
. after it is cleared of motors and before the diesel generator breakers attempt to close.
- 5) 27/1FA-1 (27/1GB-1) contacts should actuau approximately 1 seconds after 27/1F-1 (27/10-1) close in the 70% bus voltage range, and sooner for lower voltages to allow for motor trips and voltage collapse before re energizing with the emergency transformer.
j NLS9100446 Attachment 1 Page 3 of 5 These relays are inverse time relays and are calibrated every 18 months per CNS Surveillance Procedure 6.2.2.1.9. This procedure calibrates and tests the relays at four points which lie on the time-voltage curves specified by the original Burns and Roe setting calculation 2.09.06. The subject relays are calibrated and adjusted to function as designed. However, during the design basis review of the
- . Standby AC Power -System, it was determined that the Technical Specification setpoint'is not the same as the original design basis setpoint. These relays were added to Tsble 3.2.B (with the published setpoint) in Amendment 43 of the CNS Technical Specifications (Reference 2). Although there was extensive communication with the NRC concerning the operation of these relays the basis for the published setpoint is unclear. It is believed _ to be a result of a incorrect translation of the original Burns and Roe calculation.
V'.th the addition of the second level undervoltage protection (Reference 2), the I
fu st level undervoltage relays need only detect a loss of voltage and not l degraded voltage conditions. CNS Technical Specification Table 3.2.B lists the subject relays as " Emergency Buses Mss of Voltagt Relays" as compared to a
" Emergency Buses Undervoltage Relays (degraded voltage)" that describe the second
, level relays.' The actual setpoint of the first level (loss of voltage) relays is somewhat arbitrary, provided the setpoint does not create spurious transfers, or diesel starts, and does initiate load shedding in the required ti.ne, The actual setpoint translates to 'a lower voltage point for the. relay logic to actuate. It should be _noted that the second level undervoltage relays independently trip the tie breaker. The trip of the tie breaker will create a complete loss of voltage.
When this loss of voltage occurs, the loss of voltage relays, as currently set
- in the plant, will respond as designed and quickly clear the buses. The Emergency AC System will respond as described in the USAR and the CNS Technical Specification Section 3.9 BASES, because there is no loss of function over the
{ entire range of voltage (normal to zero).
Although the first level undervoltage relays are not adjusted or calibrated to i
the published setpoint described in the CNS Technical Specification Table 3.2.B, they continue to perform their safety function. This safety function is described 4- in the BASES of section 3.9 of the CNS Technical Specifications, and in the USAR.
- The . original design calculations that established _ the setting have not been l superseded or determined to be inadequate; however, the setting reflected in the
, Technical Specifications does rmt agree with the original design basis setting, i
In summary, the District requests the following change:
- 1) On page 55, for the Emergency Bus Loss of Voltage Relays, change the setting limit from 2900V 5 percent, 5 second i 1 second time delay to 2300V i 5% and 0 to 5 second time delay.
4
- EVALUATION OF THIS REOUEST WITH RESPECT TO 10CFR50.92
- The requested license amendment is judged to involve no significant hazards based upon the following:
4 4
1 v , . . ~ , ..,a-w, -w- -
NLS9100446 Attachment 1 Page 4 of 5
- 1. Does the proposed license amer.dment involve a significant increase in the
-probability or consequences of an accident previously evaluated?
Evaluation The previously evaluated cccident for the existing undervoltage protection at CNS t for the offsite power sources and the emergency buses is as follows:
"The startup transformer and the emergency transfarmer are the offsite power t Surces to CNS. Their voltages are monitored by undervoltage relays which provide low voltage protection for the emergency buses. Whenever the voltage setpoint and time delay limit for the undervoltage relays have been exceeded, the emergency
-buses are. automatically disconnected from the offsite power sources".
" Voltages on the 4160 volt bus IF (1G) are monitored by loss of voltage relays 27/1F-1 (27/10-1),-which is set to operate on decreasing voltage at about 2900 volts _i 5 %, 5 reconds i 1 second delay. Each relay initiates tripping of-all
- motor breakers on the bus, starts its associateo diesel ,enerator, and isolates its bus".
The District has determined that the Loss of Voltage Relay settings listed in the Technical Specifications are misstated. This proposed amendment will change the voltage < and time settings to correspond with the original existing loss of voltage relay setting of 2300 volts i 5 percent, with a 0 to 5 second time delay.
4 The relays will still begin to operate at less than 2900 volts decreasing and for loss of voltage the safety actions should be complete within 5 seconds depending on the rate of voltage loss. The settings will accurately reflect calibration points . on the curves to prove - operability. These revised voltage . and time settings are within the Plant Design . Basis, and are consistent with the JOperational Transient and Accident Analyses as documented in the USAR. The proposed amendment will not negate the ability of the first level undervoltage (loss of voltage) relays to satisfy the previu..-., evaluated and accepted criteria. The District has determined _that there is no safety significance resulting from inis change, as the electrical distribution system will continue to operate within the Design Basis assumed in the Operational Transient and
. Accident Analysis.'The proposed amendment will incorporate the original design basis settings of the subject relays and therefore will not involve a significant
- increase in the probability or consequence of any accident previously evaluated.
- 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previcusly evaluated?
Evaluation The proposed amendment will make changes to the setting limits on the first level
- undervoltage (loss of voltage) relays, to correspond with the original existing
m .
j NLS9100446 Attachment 1
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Page 5 of 5 loss of voltage relays, voltage and timer sottings of 2300 volts i 5%, with a 0 to 5 second time delay. These revised voltage and timer setpoints are within the Plant Design Basis, and are consistent with the Operational Transient and Accident Analysis of the USAR. The original design setpoints (tap and time dial setting) were determined by Butns and Roe calculation 2.09.06. These two settings identify a unique time voltage curve that describes the operation of the relay.
The function and operation of the first level undervol: age relays remains the same, and the previously evaluated safety function remains in effect. The Emergency AC System will continue to respond as described in the USAR and the CNS Technical Specification Section 3.9 BASES. The proposed amendment will not create a new mode of plant operation and will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in the margin of safety?
Evaluation The safety function of the first level undervoltage (loss of voltage) relays is described in the BASES of section 3.9 of the CNS Technical Specifications, and in the USAR. With the revised Technical Specification voltage and time settings, the safety function and operation of the first level undervoltage (loss of vcltage) relays remain the same. Also, with the addition of the second level undervoltage protection, the first level undervoltage (loss of voltage) relays need only detect a loss of voltare and not degraded voltage conditions. It should be noted that the second levd undervoltage relays independently trip the _
tie breakers. The trip of the tie breakers will create a complete loss of voltage. When this loss of voltage occurs, the loss of voltage relays, as currently set in the plant, will respond as designed and quickly clear the buses.
The Emergency AC System will continue to respond as described in the USAR and the CNS Technical Specification Section 3.9 BASES, because there is no loss of function over the entire range of voltage (normal to zero). The proposed amendment will continue to allow the electrical distribution system to operate within the Design Basis assumcd in the Operational Transient and Accider*.
Analysis. This proposed amendment will not involve a significant reduction in ' ne margin of safety.
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