|
---|
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
.
"P GENERAL OFFICE h Nebraska Public Power District "
"" fEdo"?j'e'""'!{"*"
E NLS8800339 July 5, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Proposed Change No. 64 to the Cooper Nuclear Station Technical Specifications , NRC Docket No. 50-298, D P R-4 6, Main Steamline isolation Valve Testing Requirements 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. This proposed change would delete the requirement to perform a weekly partial closure surveillance test or. the Main Steamline isolation Valves (MSIVs).
The District recently attempted to conduct this partial closure surveillance and was not able to complete the test on one inboard MSIV, MS-AO-80A. The inability to complete the test is attributed to failure of the nonsafety-related test solenoid valve.
The solenoid valve is only used for the partial closure test; it provides no~ function during MSIV closure as a result of an isolation signal or from the control switch in the Control Room.
Upon identifying an MSlV that could not be exercised by partial closure, the District performed the normal quarterly full stroke MSIV trip test. The full stroke trip test simulates the actual MS!V isolation and supersedes the need to perform the weekly partial closure test. The full stroke trip test, conducted in accordance with Technical Specification 4.7.D.1.b(2), verifies that the MISV will fulfill its safety function. The District currently intends to continue conducting the full stroke trip test on the one inboard MSIV on a weekly basis, until the NRC provides a disposition of this proposed Technical Specification Change.
00I 1
I{
gRO709000s 880705 (M l p ADOCK 05000293 PDC gO [
% -m ry g g g g g Q p ; g g y-
. ,. NLS8800339 Pags 2 July 5,1988
$1nce the Standard Technical Specifications and the ASME Boller and Pressure Vessel Code do not require the partial closure test, the District proposes eliminating the test from the Cooper Nuclear Station Technical Specifications.
Attachment 1 contains a description of the proposed change and the results of the evaluation of the proposed change with respect to the requirements of 10CFR50.92. Also enclosed is the applicable revised Technical Specification page.
By copy of this letter and the attachment, the appropriate State of Nebraski Official is being notified in accordance with 10 CFR50.91 ( b) .
This proposed change incorporates all amendments to the Cooper Nuclear Station Facility Operating License through Amendment 122 issued June 16, 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 Resident inspector in accordance with 10CFR50.4(b)(2).
While this proposed change does not meet the requirements for an emergency situation as defined in 10CFR50.91(a)(5), it is requested that consideration be given to the following exigent circumstances. The inability to complete the weekly MSIV partial
! closure surveillance was discovered recently (June 25, 1988) during power operation. The District could not have anticipated this problem, since successful weekly partial closure and full closure tests were performed on this valve during the preceding fuel cycle and no work was performed on this MSIV during the l recent refueling outage. Since the suspect test solenoid valve is located inside the drywell, which is inerted during power operation, additional troubleshooting beyond that already conducted is very difficult.
The District can meet the weekly MSIV testing requirements by performing a full stroke trip test. However, this requires reducing power to below seventy-five percent (75%) once per week as required by Technical Specification 4.7 D.1.b(2). Also, the full stroke test is normally only conducted quarterly. While the MSIVs are designed for up to 50 fast closures per year, it is not considered desirable to perform this test on a weekly basis for an extended period of time due to excessive wear on the valve,
.. NLS8800339
- Paga 3 July 5,1988 Should you have any questions or require additional information, please contact this office.
Sincerely, Y,
L. G. Ku cl Nuclear Power Group Manager LGK/mtb:dmr29/ 3 Attachment cc: H. R. Borchert Department of Health State of Nebraska NRC Regional Office Region IV Arlington, TX NRC Resident inspector Office Cooper Nuclear Station
s NLS8800339 P:ga 4 July 5,1988 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 pub 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.
, Y - . - .
}.G.Kunci Subscribed n y presence and sworn to before me this 5d. day of I; i ,1988.
! 0'
(%1n Mk NOTARY /PUpLIC
~~~~
COutEN AG.KUTA myc m is w 4. ins
. NLS8800339 Attcchn;nt 1 Paga 1 of 4 Revised Technical Specifications to Delete Weekly MSIV Partial Closure Surveillance Test Revised Page: 167 On June 25, 1988, the inboard Main Steamline Isolation Valve (MSIV),
MS-AO-80A, on the "A" main steamline could not be verified to be closing during the weekly partial closure test. The weekly partial closure is required by Technical Specification (TS) 4.7.D.I.c. The other seven (7) MSIVs were successfully closed to the 90% open position and reopened, in accordance with TS 4.7.D.l.c.
During the weekly partial closure test, a test solenoid is manually energized.
Energizing the test solenoid causes a three way test pilot valve to change position, allowing a slow exhaust of the air pressure that maintains the MSIV open. The compressed springs in the MSIV exert a force on the stem which closes the MSIV. When the MSIV reaches the 90% open position a limit switch is tripped, indicating that the valve is closing. The operator then de-energizes the test solenoid valve and the affected MSIV returns to the full open position. No reduction in plant power is required to perform this weakly test, since the MSIV only goes to 90% of full open and steam flow through the valve is not significantly reduced until the valve is lese than 50% of full open.
Upon discovering that the inboard MSIV on the "A" main steamline (MS-AO-80A) did not close when the test solenoid valve was manually energized, operators conducted the normal quarterly full stroke trip test on the valve. The full stroke trip test requires that the two main solenoid pilot valves be de-energized which causes the MSIV to be tripped to the full closed position.
During this test, it was verified that the closing time was within the Technical Specification requirements (3 sec. < t < 5 sec.). Since the full stroke fast closure test simulates the actual FGIV isolation, and this test exercises the valve through its full stroke, the fast closure test adequately meets the weekly surveillance requirement. This test also provides positive assurance that the valve can fulfill its safety function.
Troubleshooting to determine the cause of the failure of the MSIV, MS-AO-80A, to close upon energizing the test solenoid valve has led to the conclusion that a mechanical feature of the test solenoid valve is at fault. This conclusion is based upon the following facts:
o MSIV MS-AO-80A was last se rviced during the 1986 outage. The packing chamber of this valve has not been adjusted since that time, o The valve was successfully tested both weekly and quarterly for one full operating cycle prior to the 1988 outage.
o The other seven (7) MSIVs all passed the weekly partial closure test. No previous failures of this kind have been experienced at CNS. This indicates packing and service practices are correct.
o MSIV MS-A0-80A was successfully tested during the fast closure full stroke trip test and was successfully reopened. (Note that this test does not rely on the test solenoid valve.)
NLS8800339 Attachm:nt 1 '
Pago 2 of 4 o The closure time during the fast closure test met the Technical Specification closure time requirements, indicating that there is not an increase in friction or resistance in the MSIV. This indicates that the MSIV is not binding.
The above points provide reasonable assuranco that the MSIV is not the problem. Therefore, the probable cause of the problem is the test solenoid valve.
Isolation of the MSIV does not rely on the test solenoid valve. A failure of this valve in the test circuit does not affect the reliability of the FBIV to perform its isolation (safety-related) function.
A review of the Standard Technical Specifications and the ASME Boiler and Pressure Vessel Code indicates that neither of these documents requires a partial closure test such as CNS Technical Specification (TS) 4.7.D.I.c. In addition, the only potential purpose for the partial closure test that could be identifiud is to ensure that the MSIV is not binding. However, this is adequately tested during the quarterly fast closure and reopening, which is required by TS 4.7.0.1.b (2) .
Discussions with our NSSS (General Electric) determined that the weekly partial closure test was intended to verify proper operation of a particular type of MSIV air pilot valve that was sealed by non-contacting metal-to-metal surfaces. This valve depended upon a very small clearance between the metal surface of the spool piece and the valve body to minimize leakage and was susceptible to unequal thermal expansion and fouling by contaminants in the plcnt air supply. Because of these factors, some instances of MSIV failure to close had occurred. This type of valve was then replaced by ones with elastomeric seals making the valve movement much less sensitive to air contaminants and ambient temperature. Cooper Nuclear Station has always utilized these replacement valves in the MSIV pneumatic control units although plant Technical Specifications were not revised to remove the weekly partial closure test.
The Dictrict considers the weekly partial closure test to be unnecessary.
Therefore, it is proposed that TS 4.7.D.I.c on page 167 of the CNS Technical Specifications be deleted and TS 4.7.D.I.d be renumbered to 4.7.D.I.c.
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 license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation:
This proposed change deletes the weekly exercise of the MSIVs. The weekly surveillance involves partial closure of each individual valve to the 90% cpen position and reopening to the full open position.
L
NLS8800339
,- Attach 22nt 1 '
Pags 3 of 4 The safety function of the MSIV is to isolate the main steamline in case of a steamline break or major fuel failure, to limit the loss of reactor coolant and to limit the release of radioactive materials. Since the MSIVs perform a safety function which only mitigates the consequences of accidents previously evaluated, altering the testing of the MSIVs does not affect the probability of any accident occurring. Also, the test which is being deleted does not test the safety function of the MSIVs. The safety function is tested during the quarterly full stroke fast closure trip test.
Since deleting the weekly partial closure test is not considered to have any effect on the reliability of the MSIVs to perform their safety function, there is no increase in the consequences of any postulated accidents.
Therefore, deleting the weekly partial closure test does not involve a significant increase in the probability or consequences of an 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:
The safety function of the MSIVs is to mitigate the consequences of accidents by isolating the main steamline to limit the release of reactor coolant and radioactive materials. The MSIVs do not prevent the occurrence of any accident. Failure of the MSIVs to isolate could increase the consequences of several accidents previously evaluated in Chapter 14 of the Updated Safety Evaluation Report, but would not create any new or different kind of accident since they perform only a mitigation function. The elimination of the weekly exercising of the MSIVs by partial closure does not test the safety function of the valves, and therefore, cannot increase the consequences of an accident. Since the MSIVs perform a mitigating safety function, and the quarterly test adequately tests the safety function, elimination of the weekly test cannot create any new or different kind of accident.
- 3. Does the proposed license amendment involve a significant reduction in a margin of safety?
Evaluation:
The deletion of the weekly partial closure test of the MSIVs does reduce the frequency of testing the MSIVs. This could be considered to reduce the margin of safety for the MSIVa, however, the test to be deleted does not test the safety function of the valves, and i
therefore, does very little to test any function or capability of the valve.
(
I The weekly partial closure test uses a test solenoid valve to change the positica of the three way pilot valve, which slowly exhausts the air pressure that holds open the MSIV. As the air pressure is t reduced, the springs in the MSIV start to close the valve. At the l 90% open position, a limit switch is tripped and the test solenoid t
NLS8800339
, Attichm nt 1 Pago 4 of 4 valve is de-energized by the operator, allowing the MSIV to return to its full open position. The normal MSIV isolation does not rely upon the test solenoid valve for full closure. The only purpose that this test fulfills is a weekly check to verify that the MSIV is not binding. The MSIVs are tested quarterly, and this test adequately verifies that the MSIVs are not binding and that the valves will perform their safety function.
The quarterly full stroke fast closure trip test is considered to be adequate, since this is the only test required by the ASME Boiler and Pressure Vessel Code and the Standard Technical Specifications (STS). Also, a quarterly test is all that is required of the other power operated primary containment isolation valves.
Based upon the discussion above, the weekly partial closure test does not test the safety function of the MSIVs, the quarterly full stroke fast closure test is clearly a better test and fulfills the ASME and STS requirements. Therefore, eliminating the weekly partial closure test does not significantly 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:
"(vi) A change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria. . . ." The District feels that this proposed change falls under this example since deleting the weekly partial closure test will bring the CNS Technical Specifications to the same level of testing required by the ASME Code and the Standard Technical Specifications.
l l
t l
l