|
---|
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
. !-.
Nebraska Public Power District "?hh55$S$NM"** '"
NLS8800060 February 2, 1988 ,
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen :
Subject:
Proposed Change No. 50 to the Cooper Nuclear Station Technical Specifications, NRC Docket No. 50-298, DPR-46 In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that the Cooper Nuclear Station Technical Specifications be revised as indicated in Attachment 1. The purpose of these changes is to revise instrument identification (ID) numbers to reflect change-out of various components per previous District commitments.
Attachment 1 contains a description of the proposed changes and the results of the evaluation of the proposed changes with respect to the requirements of 10CFR50.92. Also enclosed are the applicable revised Technical Specification pages.
By copy of this letter and the attachment, the appropriate State of Nebraska Official is being notified in accordance with 10C FR50.91(b) .
This proposed change incorporates all amendments to the Cooper Nuclear Station Facility Operating License through Amendment 114 issued December 22, 1987.
This change has been reviewed by the necessary Safety Review Committees and payment of $150 is submitted in accordance with 10CFR170.12.
In addition to the signed original, 37 copies are also submitted for your use. Copies are being sent to the NRC Region IV Office and Resident Inspector in accordance with 10CFR50.4(b)(2).
l 6802110277 0802O2 f 00 I l
l PDR ADOCK 05000290 l l P pon k
\ s
$ 60$ .;11f m of
NLS8800060 Pega 2 February- 2, 1988 Should you have any questions or require additional information,
' please contact this office.
Sincer ly,
/
L. G. -Ku cl Nuclear Power Group Manager LGK /mtb:dmr25/1 Attachment cc: 11. R. Borchert Department of Health ,
State of Nebraska NRC Regional Office Region IV Arlington, TX NRC Resident Inspector Office Cooper Nuclear Station
NLS8800060 Page 3 February 2,1988 STATE OF NEBRASKA)
)ss PLATTE COUI' ?Y )
L. G. Kr .., 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 request ori cehalf of Nebraska Public Power District; and that the statements contained herein are true to the best of his knowledge and belief.
l ,
- y. G. Kuncl Subscribed in my presence and sworn to before me this day of fdMnAAu , 1988.
G bNs/O7/lM/71 NmAn voamc Asamt gggwame w ==
l
r .-
3 < .
NL S8800060 Attach m e nt - 1.
Page 1 of 5-Revised Technical Specifications' to Update Instrument ID Numbers Revised Pages: 10 56 53 70 54 .71 55 73 The first proposed change revises the Instrument I.D. Number for the reactor low pressure trip instruments, on pages 53, 54, 70, and 71. The Instrument ID Number is being changed from NBI-PS-52A and C to NBI-PS-52A1, A2, C1 and C2.
The reason for this change is that the two existing switches are dual element.
switches, which are being replaced with four single element switches. Each of the single element switches is baing given a separate ID Number.
The NBI-PS-52A and C switches are currently dual element, independent setpoint Barksdale switches. One contact of each switch provides one of the closing signals to the. reactor recirculation discharge valves when reactor pressure reaches 185 to 235 psig. The other contact of each switch provides a pressure permissive input to t'e Core Spray and Low Pressure Coolant Injection (LPCI) injection valves, when reactor pressure reaches 450 psig, decreasing.
The existing Barksdale pressure switches were environmentally qualified to IE Bulletin 79-01B (DOR Cuidelines). It has become necessary to replace the existing switches, since available spares on site are limited and it is no longer possible to purchase qualified replacements. The new switches selected to replace the existing Barksdale switches are Static-0-Ring Model 9TA-B4-NX-CIA-JJTTX6. These are single element switches that are qualified to the more stringent 10CFR50.49 and NUREG-0588, Category I requirements. Each of the dual element switches (NBI-PS-52A and 52C) will be ,
replaced with two , single element switches to duplicate their dual element function. These switch pairs will share a common sensing line, but will be installed as separate switches and will, therefore, be assigned a separate ID Number. The switches will be mounted on the same racks, at the same location, and will be m unted using seismically qualified brackets and fasteners. Also, there is no ef fect on circuit loading since the new switches function in the same manner as the old switches and consume no power.
The second proposed change is to revise the RHR Crosstie Valve Limit Switch Instrument I. D. Number from RHR-LMS-2 to RHR-LMS-8. This change is made on page 55, Table 3.2.B of the Technical Specifications. This is a typographical error and is administrative in nature. Control Room indication of the RHR Crosstie valve position was wired to the limit switch as a part of LPCI modifications. This change was made to ensure that the RHR Crosstie Valve, RHR-M0-20, position indication was a true indication. Prior to this modification, the control room annunciator that indicated "valve open" was wired to indicate control switch position, which is not necessarily the actual valve position. The appropriate Burns and Roe drawings correctly label the cross-tie limit switch as RHR-LMS-8. However, there is a typographical error in the ID number listed in the Technical Specifications that has never been corrected.
T NL S 8800060 Attachment 1 Page 2 of 5 The third proposed change would revise pages 56 and 73 of the Technical Specifications. The high drywell pressure instrument I. D. Numbers would be changed from 14A-K5 A and B(6) and 14A-K6 A and B(6) to PC-PS-101A, B, C, and D. These incorrect instrument I.D. Numbers were previously corrected on pages 53, 54, 70 and 71. Since the note (6) referred to initial Startup Testing after construction and has since been deleted, only the correct ID Numbers remain.
Finally, the District proposes to change the instrument range for the fuel zone reactor'ater w level instruments (NBI-LI-91 A and B) on page 10, Figure 2.1.1, of the Technical Specifications. This proposed change reflects changes to reactor level measurement instrumentation in accordance with the commitments made by the District to comply with the guidance of Regulatory Guide 1.97. The District committed to provide qualified redundant level measurement channels down to 6 inches below the bottom of active fuel and up to +225 inches above top of active fuel. The District also committed to a single qualified channel for the upper water level range, from +225 inches to the centerline of the main steamlines at 287.44 inches, referenced to top of active fuel. The range of the fuel zone level instruments is, therefore, being extended from: -100" to +200" to: -150" to +225". This allows these instruments, NBI-LI-91 A and B, to cover the range between 6" below the bottom of active fuel (-150") and slightly above the top of the steam separators
(+225"), where zero is top of active fuel. Also, a new steam nozzle range level transmitter will be installed to cover the range from +160 inches to
+340 inches above top of active fuel. This single qualified level transmitter covers the upper range from well below +225 inches to well above the centerline of the steamlines. These changes are being reflected in Figure 2.1.1 of the Technical Specifications. .
The guidance of Regulatory Guide (RG) 1.97 recommends Category 1 instrumentation for vessel level, with a range from the bottom of the core support plate to the centerline of the main steamline. The increase in the range of the fuel zone level instruments extends the range down to the bottom of the core support plate (6 inches below the bottom of active fuel) and up to the top of the steam separator. The addition of the steam nozzle range provides Category 1 level instrumentation (except redundancy) from the top of the steam separator up to the centerline of the main steamlines. Although some new equipment is being installed to improve level measurement capability, the other existing ranges and equipment configurations will remain the same.
Evaluation of this Amendment with Respect to 10CFR50.92 A. The enclosed Technical Specification 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:
- a. The first proposed change will not alter the function or operation of the pressure switches. Each dual element, independent setpoint Barksdale switch will be replaced with two single element Static-0-Ring (S-0-R) pressure switches. Each of the new switches will use the existing electrical circuits
N L S8800060 Attach m ent 1 Page 3 of 5 and will be installed on the existing instrument racks. The new switches will be mounted with S-0-R seismically qualified brackets and fasteners. The new switches meet -all original design specifications of the switches to be replaced and will have no effect on circuit loading since they consume no power.
The new switches share a common sensing line, and therefore, each pair of new single element switches exactly, duplicates the function of the dual element switch replaced.
This change is, therefore, primarily administrative in nature, to provide a separate ID Number for each of the four new single element switches. The new switches will not change the function or operation of the instrument, and thus, will not increase the probability or. consequences of any accident previously evaluated. Further, the new switches are qualified to the new, more stringent environmental qualification standards, and will thus provide increased assurance of operation in post accident environments.
- b. The second proposed change, revision of the RHR crosstie valve limit switch ID Number, does not involve an increase in the probability or consequences of an accident previously evaluated. This change is strictly administrative. The ID Number of this limit switch, as listed on the appropriate Cooper Nuclear Station drawings, has always been RHR-LHS-8.
The currently listed I.D. Number is a typographical error.
This change, therefore, cannot affect the probability or consequences of an accident.
- c. The third proposed change, to revise the I.D. Number of the high drywell pressure instrument from 14A-K5 A and B and 14A-K6 A and B to PC-PS-101 A, B, C and D, is also an administrative change. This administrative change corrects a typographical error that was previously overlooked, and therefore, does not ir.volve an increase in the probability or consequences of an accident.
- d. The increase in the range of NBI-LI-91 A and B is in accordance l with the District's commitment to provide redundant qualified level instru=ents dowr to 6 inches below the bottom of active l fuel (-150") and up to just above the top of the steam separator (+225"). Also, the new steam nozzle range instrument will provide Category 1 level measurement capability from
+160 inches up to the centerline of the main steamlines, with the exception of redundancy. This is in accordance with the commitments made to comply with the guidance of Regulatory l
Guide 1.97. The existing level transmitters will be used for l the fuel zone range. They are redundant and environmentally l qualified. A third new environmentally qualified transmitter
- will also be installed. This transmitter will be powered f rom L the same division as one of the other two, and will provide l
indication to resolve any ambiguity in the readings from the two redundant transmitters due to electronic failure. The increase in the range of the fuel zone reactor water level indicators from -100" to +200" to -150" to +225" provides a
i
% e NL S8800060 Attachment 1 Page 4 of 5 wider range of accurate water level indication, to assist the operator in assessing level in the vessel. The new qualified level transmitter in the steam nozzle range will provide accurate indication up to above the steamlines. This increased level indication is in accordance with NRC guidance and improves the operator's assessment _ capability. Therefore.-this change cannot increase the probability or consequences of an accident previously evaluated. Also, since environmentally qualified equipment is used, and a third indication is being installed to resolve a mismatch in the fuel zone, this change will decrease the probability of false level indication contributing.to any accident.
- 2. Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?
Evaluation:
- a. This proposed change will not modify in any way the safety function of the NBI pressure switches. In the original design, one contact of each of the two dual element switches provided a signal to close the recirculation system discharge
- valve. The other contact of each dual element switch provided one of the inputs to the Core Spray and LPCI injection valves. This function has not changed. The only change is that instead of a switch with dual contacts, two single contact switches will be used. The existing sensing lines, electrical circuits, instrument racks and setpoints will be used. This change will not create any new or different kind of accident, since the two single element switches exactly duplicate the dual element switch function, with no negative effects on the circuitry.
- b. Revising the I.D. Number of the RHR crosstie valve limit switch is purely administrative. No hardware changes are being made.
This I.D. Number has always been RHR-LMS-8 instead of RHR-LMS-2 as currently listed. This administrative change does not create any new or different kind of accident.
- c. The change to correct the high drywell pressure instrument I.D.
Numbers is also administrative. This typographical error correction cannot create any new or different kind of accident, since it involves no hardware changes or changes in the function or operation of the instruments.
- d. The increase in the range of the fuel zone level instruments and the addition of the steam nxzzle range instruments in Figure 2.1.1 of Technical Specifications cannot create any new or different kind of accident. This change increases the range, by providing accurate level measurement capability from the core support plate to above the centerline of the main steamlines. These level instruments provide indication of water level in the vessel, but do not provide any RPS or ESF input signals. The range increase will provide better water level assessment capability and is in accordance with SRC
- r. ,
. .. -,n NLS8800060 Attachment 1 Page 5 of 5 guidance provided in Regulatory Guide 1.97~. This increase in the range of NBI-LI-91 A and B and the. addition of the steam nozzle range cannot create any new or different kind of L accident, since they are used for assessment purposes only.
Also, since environmentally qualified equipment is used and a third indication is being installed in the fuel zone to resolve any ambiquity in the two redundant indications, this change will decrease the probability of false level indication contributing to any new or different kind of accident.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
- a. The only change involved is to replace the Instrurent I.D.
Numbers NBI-PS-52A and C with NBI-PS-52Al, A2, C1 and C2. This will provide a separate I.D. Number for each single element switch. If each switch has a unique I.D. Number, the tracking
- of maintenance and surveillances is easier. This change does not alter the system electrically, and therefore, changing the I.D. Numbers does not affect any margin of safety.
- b. The instrument I.D. Numbers in the Technical Specifications do not constitute a margin of safety. These I.D. Numbers are part of a system intended to track data and work on particular components. This change corrects incorrect I.D. Numbers, and therefore has no negative affect on any margin of safety.
- c. The correction of the high drywell pressure instrument 'I.D.
Number is also a change to correct a typographical error.
These I.D. Numbers are not part of the margin of safety, and therefore, this change does not reduce any margin of safety,
- d. Since this proposed change would add range onto the existing fuel zone level instruments plus provide accurate level measurement up to the steamlines, providing capability to assess water level over more of the vessel, this change does not reduce any margin of safety. Further, the redundant, qualified equipment and addition of a third indication in the fuel zone, to resolve questions in case of two dif ferent readings, reduces the likelihood of f alse indication contributing to the consequences of an accident. Therefore, this change does not reduce any margin of safety.
B. Additional basis for proposed no significant hazards consideration determination:
The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48CFR14870). The examples include:
"(1) A purely administrative change. . . ." The District feels that proposed changes a, b, and c fall under this example. Proposed change d falls under the example: "(vii) A change to conform a license to changes in the regulations, where the License change results in very minor changes to the facility operations clearly in keeping with the regulations."
--- - --. .