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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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by: y Nebraska Public Power District
_ " " ""$bhbMt "___'*"_
NLS8800078 March 25, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Proposed Change No. 34 to the Cooper Nuclear Station Technical Specifications Alternate Shutdown Capability NRC Docket No. 50-298, DPR-46
Reference:
Letter from W. O. Long to G. A. Trevors, dated January 15,1987, ' Technical Specifications for Alternate Shutdown Panels" In accordance with the applicable provisions specified in 10CFR50 and in response to the letter referenced above, the Nebraska Public Power District requests that the Ccoper Nuclear Station Technical Specifications be revised as indicated in Attachment 1. The purpose of these changes is to add operability and surveillance requirements for the alternate ,
shutdown panels.
Attachment I contains a description of the proposed changes and I 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. ,
1 By copy of this letter and the attachment, the appropriate State of Nebraska Official is being notified in accordance with 10CFR50.91(b).
This proposed change incorporates all amendments to the Cooper Nuclear Station Facility Operating License through Amendment 117 issued February 23. 1988.
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 the CNS Resident Inspector in accordance with inCFR50.4(b)(2).
g (hg Y 50 88041203e7 DR 880325 W 'c 3 Y ADGCK 05000293 DCD EAWi
NLS8800078 Page 2 March 25, 1988 Should you have any questions or require additional information, please contact this office. .
Sincerely, 6
L. G. Kunc1 Nuclear Power Group Manager LGK/mtb:dmr29/1 Attachment ,
cc: H. R. Borchert Department of Health j State of Nebraska ,
NRC Regional Office Region IV Arlington, TX l NRC Senior Resident Inspector .
Cooper Nuclear Station I i
I l
l i
?
l i
NLS8800078 Page 3 March 25, 1988 STATE OF NEBRASKA)
)ss PLATTE COUNTY )
L. G. Kuncl, 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 on behalf of Nebraska Public Power District; and that the statements contained herein are true to the best of his knowledge and belief.
L, G. Kuncl Subscribed i of / y An p esence
.) and sworr,
, 1988. to before me this Mday
/
Q ), 7 A GEMMI 10TARY %t. el Ritrata NOTARY PMBLK gh (OM'QQQ i
l I
NLS8800078 Attachment 1 Page 1 of 6 Revised Technical Specifications for .
Alternate-Shutdown Panels Revised Pages: i 67d 48 82b.
49 87a 67c The requirements of 10CFR50, Appendix R, Section III.G.2, specify.that where cables and equipment of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located sithin the same fire area (outside primary containment), certain separation requirements must be met.
Those separation requirements are: 1) separation by a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire barrier, 2) ceparation by a horizontal distance of more than 20 feet with no intervening combustibles, or 3) enclosure of one redundant train in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rated fire barrier, with fire detection and fire suppression capability The District conducted extensive evaluations to ensuce compliance with the ;
requirements of 10CFR50, Appendix R. Those evaluations were docketed with the Commission as the CNS Response to 10CFR50, Appendix R, "Fire Protection of Safe Shutdown capability," Volumes I, II, and III. In certain areas of the plant it was not feasible to make the modifications necessary to comply with ,
Section III.G.2 of Appendix R. Therefore, in accordance with Section III.G.3 of Appendix R, it was necessary to provide alternate shutdown (ASD) capability. The ASD system allows shutdown of the plant independent of the ;
cables, equipment and components required for hot ,.hutdown located in those :'
areas of the plant, where the separation requirements of Section III.G.2 of Appendix R are not met.
As documented in Volume III of the CNS Response to 10CFR50, Appendix R, "Fire Protection of* Safe Shutdown capability," there were eleven (11) areas of the j Cooper Nuclear Station (CNS) that did not meet literal compliance with ;
Section III.G.2. Of these, six (6) were addressed by modifications which were approved as exemptions to Appendia R in an NRC letter from D. B. Vassallo to
- L. G. Kuncl, dated September ". L982. Alternate shutdown capability is l provided for the remaining fivt 5) arcaa of the plant. The five areas of the plant are
- the control room, the cebte spreading room, the cable expansion room, the auxiliary relay room and the northeast corner of the Reactor Building, 903' elevation. The proposed alternate shutdown (ASD) capability was submitted to NRC in a letter dated December 2, 1983. The NRC approved the '
proposed ASD system in a letter from D. B. Vassallo to J. M. Pilant, dated-April 16, 1984 The NRC concluded that the proposed alternate shutdown system l at CNS met the requirements of Section III.G 3 and III.L of 10CFR50, i Appendix R. The alternate shutdown capability was installed during the Cycle 10 refueling outage.
.l The purpose of the CNS alternate shutdown system is to provide the ability to -
shut down the plant in the unlikely event of a fire which disables both divisions of control and instrumentation circuits necessary to shut the plant down from the control room. The alternate shutdown capability is made up of three control panels in the Alternate Shutdown (ASD) Room, local controls for i diesel generator No. 2 and manual operation of salected pumps, valves and l circuit breakers. I
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NLS8800078 ,
Attachment 1 Page 2 of 6 The three ASD panels provide an alternate location from which to operate selected components of the Automatic Depressurization (ADS), High Pressure Coolant Injection (HPCI), Reactor Equipment Cooling (REC) and Residual Heat Removal (RRR) Systems. Also located on these panels are certain process variable indications. These panels are remote from the location of the five (5) areas of the plant that necessitate an alternate shutdown capability and are independent of any equipment located in those areas. Diesel Generator No. 2 is the backup AC power source for the ASD panels. DC power is supplied by the station batteries. The controls for No. 2 Diesel Generator and output breaker EG2 have been modified to ensure startup and operation of the diesel locally.
The Automatic Depressurization System (ADS) is used to control reactor pressure. By using Isolation Switches on the ADS - Alternate Shutdown (ASD)
Panel, control of three safety relief valves can be isolated from the control room and controlled at the Alternate Shutdown Panel. The valves may then be used to reduce reactor pressure to where the RHR system, in LPCI mode, can be used to remove decay heat. Also included on ADS ASD pansi are isolation.
switches and controls for Reactor Equipment Cooling (REC) Pumps C and D. The REC valves are lined up locally at the motor control centers. The REC system is used to provide cooling to the RHR pumps and the HPCI room area cooler. ,
The torus temperature indicators are also located on the ADS-ASD panel. TPs torus temperature indicators on the ADS ASD panel are independent of those in i the control room. These redundant sensors do not require isolation switches.
The HPCI system is used to control reactor vessel coolant inventory, while in hot shutdown and to provide coolant makeup while depressurizing. Isolation switches on the HPCI Alternate Shutdown (ASD) Panel allow isolation from the
, control room of the HPCI Turbine controla, HPCI Auxiliary Lube Oil Pump, HPCI Fan Coil Unit, the Gland Seal Condensate Pump, HPCI Cland Seal Exhauster, and required motor operated valves. This facilitates operation and testing of the l HPCI system from the ASD panel, independent of the control room. Also, indication is provided on the HPCI ASD panel for HPCI Turbine Speed, Turbine l
Inlet Pressure, HPCI Pump discharge pressure and flow, torus level, reactor water level, reactor shroud level, ECST level and HPCI pump succion pressure.
These are isolated from the control room by isolation switches on the HPCI ASD panel. This allows the operator to assess the status of reactor coolant, HPCI system flows and pressures, sources of make up wcter level (torus and ECST),
HPCI turbine status (speed and lube oil) and status of system valves.
l, The Residual Heat Removal (RHR) system is used in the suppression pool cooling mode to cool the torus. This is needed to remove the heat added by the HPCI turbine exhaust and ADS valve discharges. RHR Pump D and Loop B of the RHR system are used. The pump is controlled locally at the pump breaker in Critical Switchgear Room 1G. Certain RHR valves are provided with isolation switches on the RRR-ASD panel. Other RHR valves are aligned locally in the Reactor Building from the motor control center. Indication of Loop B flow is also provided on the RRR ASD panel to assess system operation. Torus temperature can be monitored on the ADS-AS9 panel and torus level can be monitored on the HPCI ASD panel.
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l-NLS8800078 Attachment.1
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Page.3 of 6 The Service Water system wfil be used to provide cooling water to the diesel -
generator, RHR heat exchanger anc REC heat exchanger. Service water Pumps C and D will be operated locally in the critical switchgear room and system valves will be operated manually at the MCC.
Valves which are used to isolate the reactor vessel will be de energized to prevent spurious operation. Diesel Cenerator No. 2 will provide reliable ,
power to the ASD panels.
Thus, in the unlikely event of a fire in one of the fire areas of the plant which would necessitate shutdown of the reactor from outside the control room, operators could depressurize and cool the reactor from the alternate shutdown panels. ,
This proposed Technical Specification change adds operability and surveillance requirements for alternate shutdown equipment as Sections 3.2. I and 4.2. I .
First, specification 3.2.1.1 requires ASD equipment to be operable during reactor power operations and when the reactor coolant temperature is above i 212*F. Tables 3.2.I-1 and 3,2.I 2 identify the required ASD equipment.
Specification 3.2.I.2 provides the action statement which requires that if ASD <
equipment is inoperable, it must be restored within 30. days or the NRC must be "
notified and provided with plans to restore alternate shutdown capability.
Surveillance requirement 4.2.I.1 requires channel checks and channel calibrations of ASD instruments and Table 4.2.I has been added to specify the j frequency. Also, Specification 4.2.I.2 has been added to require testing of each isolation switch, power supply and control circuit for the equipment listed in Tabis 3.2.I-2 once per refueling cycle.
The minimum list of equipment in Tables 3.2.I 1 and 2 is based on those controls and instruments necessary to achieve alternate shutdown. Since this system is only designed to achieve hot shutdown, the operability requirements ,
only apply above 212*F reactor coolant and during power operation. This !
system has no safety function during normal or abnormal (except certain fire scenarios) operation. Thus, this system is a backup to redundant safe shutdown systems, only designed for use in the unlikely event of a small set of fire scenarios. Based upon this, the action to be taken when ASD components are found to be inoperable is established as restore operability within 30 days or notify the NRC.
The surveillance intervals for instrumentation channel checks and calibration )
4 were set at once per cycle. This frequency is based on the desire to conduct this testing during shutdown. These instruments would normally not be powered unless alternate shutdown is required. To achieve indication of the actual process variables on the ASD panels means isolating indication from the control room. This can only be done safely during shutdown. Further, this
! system provides no safety function during normal operations, transients and all accidents except a small group of fire scenarios. Due to the lack of safety function and the relatively small and unlikely group of scenarios where ASD is used, increased testing is not considered necessary. The once per cycle frequency is considered to meet the' guidance of IEEE 338 and Regulatory Guide 1.22.
The surveillance interval for the isolation switches, control circuits and power supplies is set at once per cycle. This is in accordance with the intent of the NRC approved Standard Technica! Specifications which specify a
'. NLS8800078 Attachment 1 Page 4 of 6 frequency of once per 18 months. The Cooper Nuclear Station refueling cycle is once per 12 months. The primary reason for this inte rval is that the components must be isolated from the control room, which must be done during shutdown.
This change also moves specifications 3/4.2.D.5 from page 49 to page 43 and adds a Section 3.2.1 in the Bases on page 87a. These changes are administrative in nature.
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:
The Alternate Shutdown (ASD) Capability at Cooper Nuclear Station was installed in accordance with commitments to the NRC and in accordance with the requirements of 10CFR50, Appendix R, Section III.G.3 and III.L. The ASD system is designed such that it will not interfere with any control or instrumentation fun'etions during normal operation. However, during a fire in one of the five plant areas where loss of shutdown capability from the control room is postulated the ASD system can isolate the necessary controls and instrumentati'on from the control room, allowing safe plant shutdown.
This additional remote shutdown capability increases plant safety in the event of a fire in the control room, cable spreading room, cable expansion room, auxiliary relay room, or the northeast corner of the 903' elevation of the Reactor Building. These are the five areas of the plant where a fire could cause loss of centrols and instrumentation necessary to shut down the plant from the control room.
The portions of the ASD system that interface with normal safe shutdown systems are designed, procured and installed to the same specifications as the normal system. The isolation switches are alarmed in the control room to notify operators of transfer of controls and instrumentation from the control room to the ASD panels. The doors to the ASD room are key locked and alarmed in the control room. The isolation switches are essential (safety related), seismically qualified and environmentally qualified. This proposed Technical Specification Change adds testing requirements to verify operability of controls, instrumentation, isolation switches and power supplies for the ASD system.
The design and operation of the Alternate Shutdown System was described in Volume III of the CNS Response to 10CFR50, Appendix R, "Fire Protection of Safe Shutdown Capability," submitted to NRC in a letter from J. M. Pilant to D. B. Vasallo, dated December 2, 1983.
NRC concluded that the ASD design meets the requirements of 1
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', NLS8800078 Attachment 1 Page 5 of 6 Section III.G.3 and III.L of Appendix R, in a letter from D. B. Vassallo to J. M. Pilant, dated April 16, 1984.
Based on the discussion a~oove, this proposed change, to add operability and surveillance requirements for the Alternate Shutdown Capability, does not increase the probability or consequences of any accident previously evaluated.
- 2. Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?
Evaluation:
This proposed change adds operability and surveillance requirements for the installed alternate shutdown system. -The system has.been ,
designed to comply with the requirements of 10CFR50, Appendix R, Section.III.L and has been found by NRC to meet those requirements. -
During normal plant operations, the ASD system is not in use and is !
isolated from the normal safe shutdown systems. The isolation !
switches are designed so that they cannot interfere with normal system controls and indi* cation in the control room. Also, during transients or accidents (except a fire in one of the five areas l requiring alternate shutdown) che ASD system remains isolated and all control and indication is maintained in the control room. Only in the event of a fire in one of the five areas, that makes shutdown of the plant from the control room impossible, would control of plant shutdown be transferred to the Alternate Shutdown System. '
The ASD System is only used when responding to a small set of identified fire scenarios. The ASD controls and instrumentation are only used to control the normal mode of HPCI, RHR Torus Cooling, ADS and REC, during a fire involving one of the 5 areas requiring i alternate shutdown. At all other times the system is idle, isolated from the plant and cannot affect plant equipment. Thus, the ASD System cannot create the possibility of any new or different kind of ,
accident. l
- 3. Does the proposed amendment involve a significant reduction in a margin of safety? l Evaluation-This change reflects the addition of an Alternate Shutdown System, installed as a means of placing the plant in hot shutdown, independent of the five areas which require alternate shutdown capability. This system adds a level of protection that is a backup to the existing redundant trains of the safe shutdown systems. The ASD system increases the margin of safety by improving plant
, capability to shutdown, in the unlikely event of certain fire scenarios. Based on the above, this proposed change does not l decrease any margin of safety. !
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B. Additional basis for proposed no significant hazards consideration determination:
The Commission has provided guidance concerning the application o'f the standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR14870) . The examples include
"(11) a change that . constitutes an additional limitation...." The' District considers this change to fall under this example.
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