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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARCY-99-105, Application for Amend to License DPR-61,incorporating Changes Into OL & Ts.Addl Clarifications & Retyped TS Replacement Pages,Included1999-08-24024 August 1999 Application for Amend to License DPR-61,incorporating Changes Into OL & Ts.Addl Clarifications & Retyped TS Replacement Pages,Included CY-99-041, Application for Amend to License DPR-61,incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant1999-06-0303 June 1999 Application for Amend to License DPR-61,incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant CY-98-003, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant1998-08-13013 August 1998 Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant CY-98-084, Application for Amend to License DPR-61,incorporating Attached Proposed Changes Into TS Re Relocation of Requirements for Seismic Monitor to Be Consistent W/Guidance Contained in GL 95-101998-06-0202 June 1998 Application for Amend to License DPR-61,incorporating Attached Proposed Changes Into TS Re Relocation of Requirements for Seismic Monitor to Be Consistent W/Guidance Contained in GL 95-10 CY-97-024, Application for Amend to License DPR-61,reflecting Staff Limitations & Requirements Appropriate to Present Configuration of Plant1997-05-30030 May 1997 Application for Amend to License DPR-61,reflecting Staff Limitations & Requirements Appropriate to Present Configuration of Plant CY-97-006, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant1997-05-30030 May 1997 Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant B16167, Addendum to Application to Amend License DPR-61,revising Section 6, Administrative Controls1997-01-31031 January 1997 Addendum to Application to Amend License DPR-61,revising Section 6, Administrative Controls B16046, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49 to Revise Section 6, Administrative Controls & TS to Reflect New Organizational Responsibilities & Titles1996-12-24024 December 1996 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49 to Revise Section 6, Administrative Controls & TS to Reflect New Organizational Responsibilities & Titles B14711, Application for Amend to License DPR-61,revising TS 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability1994-01-25025 January 1994 Application for Amend to License DPR-61,revising TS 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability ML20059G5821993-11-0202 November 1993 Application for Amend to License DPR-61,proposing Rev to TS by Increasing AOT for Charging Pump from 72 Hours to Seven Days B14572, Application for Amend to License DPR-61,proposing Interim Changes for Incorporation of Addl LCO for TS Requiring That 480 Volt Ac MCC 5 & Abt Scheme Be Operable During Modes 1,2, 3 & 4.Permanent Changes Will Be Proposed Later Half of 19941993-08-18018 August 1993 Application for Amend to License DPR-61,proposing Interim Changes for Incorporation of Addl LCO for TS Requiring That 480 Volt Ac MCC 5 & Abt Scheme Be Operable During Modes 1,2, 3 & 4.Permanent Changes Will Be Proposed Later Half of 1994 ML20056E3341993-08-18018 August 1993 Application for Amend to License DPR-61,changing TS Sections to Permanently Remove Ability of Plant to Operate W/Three Loops While in Modes 1 or 2 B14502, Application for Amend to License DPR-61,proposing Changes to Modify Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS 3/4.5.1 to TS 3/4.5.2 as Surveillance Requirement 4.5.2.c1993-07-26026 July 1993 Application for Amend to License DPR-61,proposing Changes to Modify Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS 3/4.5.1 to TS 3/4.5.2 as Surveillance Requirement 4.5.2.c B14532, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual1993-07-16016 July 1993 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual B14369, Application for Amend to License DPR-61,changing TS Re Editorial Cleanup,Including Incorporation of Missing Sections in Index,Providing Editorial Consistency Throughout Document & Removal of Cycle Specific Comments1993-03-16016 March 1993 Application for Amend to License DPR-61,changing TS Re Editorial Cleanup,Including Incorporation of Missing Sections in Index,Providing Editorial Consistency Throughout Document & Removal of Cycle Specific Comments B14327, Application for Amend to License DPR-61,revising TS Re Steam Generator Repair Criteria,To Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area1993-01-29029 January 1993 Application for Amend to License DPR-61,revising TS Re Steam Generator Repair Criteria,To Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area B14342, Application for Amend to License DPR-61,revising TS for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases.Draft Rev 0 to Project Assigment 90-013, CT Yankee Modernize Fwd Encl1993-01-29029 January 1993 Application for Amend to License DPR-61,revising TS for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases.Draft Rev 0 to Project Assigment 90-013, CT Yankee Modernize Fwd Encl ML20141M3441992-07-31031 July 1992 Application for Amend to License DPR-61,revising TSs to Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area B13669, Application for Amend to License DPR-61,reflecting Addition of New Manual locked-closed Containment Isolation Valve & Removal of solenoid-operated Containment Isolation Valve. Valve CC-V-884 No Longer Containment Boundary Valve1990-11-27027 November 1990 Application for Amend to License DPR-61,reflecting Addition of New Manual locked-closed Containment Isolation Valve & Removal of solenoid-operated Containment Isolation Valve. Valve CC-V-884 No Longer Containment Boundary Valve B13619, Application for Amend to License DPR-61,clarifying Definition of Operability of Automatic Auxiliary Feedwater Initiation Sys at Plant for Cycle 16 Operation Only1990-08-25025 August 1990 Application for Amend to License DPR-61,clarifying Definition of Operability of Automatic Auxiliary Feedwater Initiation Sys at Plant for Cycle 16 Operation Only ML20055J2091990-07-26026 July 1990 Application for Amend to License DPR-61,allowing Plant to Progress Into Mode 3 W/O First Demonstrating Auxiliary Feedwater Sys Operability.Temporary Waiver of Compliance from Tech Spec 4.7.1.2.2 Requested Until NRC Acts on Amend ML20055F3221990-07-0505 July 1990 Application for Amend to License DPR-61,revising Tech Specs Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases.No Radiological or Nonradiological Impact Associated W/Changes ML20055E0051990-06-25025 June 1990 Application for Amend to License DPR-61,establishing Limit of 160 Failed Fuel Rods for Cycle 16 Operation,Per 900524 Meeting B13333, Application for Amend to License DPR-61,revising Tech Spec Sections 3.6.2,3.9.11 & 3.9.12 Re Containment Air Recirculation Sys,Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys,Respectively1989-08-0404 August 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 3.6.2,3.9.11 & 3.9.12 Re Containment Air Recirculation Sys,Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys,Respectively B13324, Application for Amend to License DPR-61,revising Tech Spec 3/4.5.1, ECCS - ECCS Subsystem - Tavg Greater than or Equal to 350 F to Reflect Component Configurations Following 1989 Refueling Outage Mod to ECCS to Resolve Single Failure1989-08-0202 August 1989 Application for Amend to License DPR-61,revising Tech Spec 3/4.5.1, ECCS - ECCS Subsystem - Tavg Greater than or Equal to 350 F to Reflect Component Configurations Following 1989 Refueling Outage Mod to ECCS to Resolve Single Failure ML20248A0461989-08-0101 August 1989 Application for Amend to License DPR-61,modifying Proposed Tech Spec 3.12, Electrical Power Sys, Provided in .Tech Spec Incorporated Degraded Grid Voltage Protection Requirements in Westinghouse STS Format B13317, Application for Amend to License DPR-61,revising Tech Specs to Reflect Changes in Fire Detection/Suppression Sys Upgrades to Support New Switchgear Bldg Const1989-07-31031 July 1989 Application for Amend to License DPR-61,revising Tech Specs to Reflect Changes in Fire Detection/Suppression Sys Upgrades to Support New Switchgear Bldg Const ML20247R7071989-07-28028 July 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 3.0/4.0 & 3.4.6.2 Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage ML20248C4041989-07-28028 July 1989 Application for Amend to License DPR-61,changing Tech Specs to Reflect Upgrade of Reactor Protection Sys & Nuclear Instrumentation Sys at Plant ML20245E5921989-07-28028 July 1989 Application for Amend to License DPR-61,changing Tech Specs to Support Cycle 16 Operation ML20245L2401989-06-29029 June 1989 Application for Amends to Licenses DPR-61 & NPF-49, Clarifying Tech Specs Re Steam Generator Tube Insp Criteria. Change Would Add Cold Leg Side as Alternate Point of Entry ML20245J4501989-06-23023 June 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 2.0 Re Safety Limits & Limiting Safety Sys Settings & 3/4.3 Re Instrumentation ML20244B0691989-06-0202 June 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 3/4.4,3/4.6 & 3/4.7.Proposed Changes Would Add Limiting Conditions for Operation & Surveillance Requirements for RCS ML20247N2651989-05-25025 May 1989 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,simplifying Administrative Controls for Changes in Radiological Effluent Monitoring Manual in Tech Specs,Per Generic Ltr 89-01 B13155, Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Revising Tech Spec Re Admin Controls in High Radiation Area1989-04-25025 April 1989 Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Revising Tech Spec Re Admin Controls in High Radiation Area ML20245C9181989-04-21021 April 1989 Application for Amend to License DPR-61,revising Tech Specs Re Core Cooling Sys & Min Water Vol & Boron Concentration in Refueling Water Storage Tank by Combining Into New Section 3.6, ECCS, Per Westinghouse STS ML20245A5731989-04-14014 April 1989 Application for Amend to License DPR-61,supporting Coastdown Operation of Facility at End of Cycle 15,current Cycle ML20248F9271989-03-31031 March 1989 Application for Amend to License DPR-61,changing Tech Spec Section 3.11.B Re Containment Integrity During Containment Air Recirculation Fan Motor HX Cleaning Activities ML20246N0911989-03-13013 March 1989 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,changing Tech Specs Re Administrative Controls & Organizational Charts,Per Generic Ltr 88-06 ML20235Z2611989-03-0606 March 1989 Application for Amend to License DPR-61,revising Tech Spec 3/4.1, Reactivity Control Sys. Comparison Matrix to Existing Tech Specs & Westinghouse STS Encl ML20235V0851989-03-0101 March 1989 Application for Amend to License DPR-61,revising Tech Specs Re Core Exit Thremocouples,Main Stack wide-range Noble Gas Monitor,Reactor Vessel Water Level & RCS Subcooling Margin Monitor,Per Generic Ltr 83-37 B13065, Application for Amend to License DPR-61,changing Tech Spec Tables 7.2-1 & 8.2-1 to Identify Which Radiation Monitors Required to Be Operable.Fee Paid1988-11-0707 November 1988 Application for Amend to License DPR-61,changing Tech Spec Tables 7.2-1 & 8.2-1 to Identify Which Radiation Monitors Required to Be Operable.Fee Paid ML20205M9881988-10-26026 October 1988 Application for Amend to License DPR-61,revising Sections 1.0,3/4.2,3/4.9,3/4.10,3/4.11,5.0 & 6.0 of Tech Specs ML20154J5671988-09-13013 September 1988 Application for Amend to License DPR-61,incorporating New Section of Sprinkler Protection in Turbine Bldg & Reduction in Number of Smoke Detectors Available in Containment from 23 to 22.Fee Paid ML20153F9491988-08-29029 August 1988 Rev to 871117 Application for Amend to License DPR-61, Adding New Tech Spec 3.12, Electrical Power Sys Which Would Incorporate Degraded Grid Requirements in Westinghouse STS Format B12958, Revised Application for Amends to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,changing Tech Specs Number of Members & Time as Member of Nuclear Review Board1988-07-21021 July 1988 Revised Application for Amends to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,changing Tech Specs Number of Members & Time as Member of Nuclear Review Board ML20150D6751988-07-0101 July 1988 Application for Amend to License DPR-61,revising Tech Specs That Provide Limiting Conditions for Operation & Surveillance Requirements in Response to Generic Ltr 83-37. Fee Paid ML20154P0851988-05-25025 May 1988 Application for Amends to Licenses DPR-61,DPR-21,DPR-67 & NPF-49,revising Tech Specs Re Administrative Controls. Changes Eliminate Conflicting Submittal Directions for Correspondence W/Nrc.Fee Paid B12859, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,revising Tech Specs Re Administrative Controls, Nuclear Review Board.Fee Paid1988-04-29029 April 1988 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,revising Tech Specs Re Administrative Controls, Nuclear Review Board.Fee Paid B12860, Application for Amend to License DPR-61,adding License Condition Requiring Util to Implement & Maintain Integrated Implementation Schedule Program Plan1988-03-31031 March 1988 Application for Amend to License DPR-61,adding License Condition Requiring Util to Implement & Maintain Integrated Implementation Schedule Program Plan 1999-08-24
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217K3221999-10-19019 October 1999 Amend 195 to License DPR-61,deleting Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor,Duplicate Regulatory Requirements or Duplicate Info Located in UFSAR CY-99-105, Application for Amend to License DPR-61,incorporating Changes Into OL & Ts.Addl Clarifications & Retyped TS Replacement Pages,Included1999-08-24024 August 1999 Application for Amend to License DPR-61,incorporating Changes Into OL & Ts.Addl Clarifications & Retyped TS Replacement Pages,Included CY-99-041, Application for Amend to License DPR-61,incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant1999-06-0303 June 1999 Application for Amend to License DPR-61,incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20206C8731999-04-28028 April 1999 Amend 194 to License DPR-61,authorizes Relocation of Requirements Related to Seismic Monitoring Instrumentation from TSs to Technical Requirements Manual CY-98-003, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant1998-08-13013 August 1998 Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20202D1521998-06-30030 June 1998 Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant CY-98-084, Application for Amend to License DPR-61,incorporating Attached Proposed Changes Into TS Re Relocation of Requirements for Seismic Monitor to Be Consistent W/Guidance Contained in GL 95-101998-06-0202 June 1998 Application for Amend to License DPR-61,incorporating Attached Proposed Changes Into TS Re Relocation of Requirements for Seismic Monitor to Be Consistent W/Guidance Contained in GL 95-10 ML20217K2041998-03-27027 March 1998 Amend 192 to License DPR-61,changing Administrative Controls,Section 6.0 of Ts,To Reflect Permanent Shutdown & Defueled Status of Plant CY-97-006, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant1997-05-30030 May 1997 Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant CY-97-024, Application for Amend to License DPR-61,reflecting Staff Limitations & Requirements Appropriate to Present Configuration of Plant1997-05-30030 May 1997 Application for Amend to License DPR-61,reflecting Staff Limitations & Requirements Appropriate to Present Configuration of Plant ML20141K4161997-05-22022 May 1997 Amend 191 to License DPR-61,changing Administrative Controls Section of TSs as Needed to Implement Revised Mgt Responsibilities & Titles That Reflect Permanently Shut Down Status of Plant B16167, Addendum to Application to Amend License DPR-61,revising Section 6, Administrative Controls1997-01-31031 January 1997 Addendum to Application to Amend License DPR-61,revising Section 6, Administrative Controls B16046, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49 to Revise Section 6, Administrative Controls & TS to Reflect New Organizational Responsibilities & Titles1996-12-24024 December 1996 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49 to Revise Section 6, Administrative Controls & TS to Reflect New Organizational Responsibilities & Titles B14711, Application for Amend to License DPR-61,revising TS 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability1994-01-25025 January 1994 Application for Amend to License DPR-61,revising TS 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability ML20058F1101993-11-23023 November 1993 Amends 170,69,169 & 86 to Licenses DPR-61,DPR-21 DPR-65 & NPF-49,respectively,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20059G5821993-11-0202 November 1993 Application for Amend to License DPR-61,proposing Rev to TS by Increasing AOT for Charging Pump from 72 Hours to Seven Days ML20059G6331993-11-0101 November 1993 Amend 169 to License DPR-61,changing TS by Incorporating New TS Section 3/4.8.3.1.2, Onsite Power Distribution ML20059G5091993-10-27027 October 1993 Amend 168 to License DPR-61,permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057E2001993-10-0404 October 1993 Amend 167 to License DPR-61,changing Plant TS to Allow Redundant Train Operability to Be Verified Operable by Exam of Appropriate Plant Records Rather than Performing Test of Redundant Equipment ML20057E1911993-10-0404 October 1993 Amend 166 to License DPR-61,modifying TS Tables 3.3-9 & 4.3-7 by Replacing Obsolete Footnote W/Clarification as to When SG Blowdown Radioactivity Monitors Are Required to Be Operable ML20058M9011993-09-29029 September 1993 Amend 165 to License DPR-61,replacing TS Section 4.0.6 of Plant TS, Augmented Inservice Insp Program W/New TS Section 4.0.6, Augmented Erosion/Corrosion Program ML20057A3531993-09-0202 September 1993 Amend 163 to License DPR-61,adding Footnote to TS 3.4.2.2 to Allow Relaxation in Pressurizer Safety Valve Point Tolerance to +3%,used for as Found Acceptance Criterion for Addl Valve Testing ML20057A3481993-09-0202 September 1993 Amend 164 to License DPR-61,revising TS to Reflect Staff Positions & Improvements to TS in Response to GL-90-06 Re Resolution of Generic Issues 70 & 74 ML20056G2871993-08-25025 August 1993 Amend 162 to License DPR-61,revising TSs to Increase Shutdown Margin (Boron Concentration) in Modes 1-5 to Compensate for Addl Reactivity Added by Boron Dilution Event Due to Transition to Zircaloy Clad Core ML20056E3341993-08-18018 August 1993 Application for Amend to License DPR-61,changing TS Sections to Permanently Remove Ability of Plant to Operate W/Three Loops While in Modes 1 or 2 B14572, Application for Amend to License DPR-61,proposing Interim Changes for Incorporation of Addl LCO for TS Requiring That 480 Volt Ac MCC 5 & Abt Scheme Be Operable During Modes 1,2, 3 & 4.Permanent Changes Will Be Proposed Later Half of 19941993-08-18018 August 1993 Application for Amend to License DPR-61,proposing Interim Changes for Incorporation of Addl LCO for TS Requiring That 480 Volt Ac MCC 5 & Abt Scheme Be Operable During Modes 1,2, 3 & 4.Permanent Changes Will Be Proposed Later Half of 1994 B14502, Application for Amend to License DPR-61,proposing Changes to Modify Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS 3/4.5.1 to TS 3/4.5.2 as Surveillance Requirement 4.5.2.c1993-07-26026 July 1993 Application for Amend to License DPR-61,proposing Changes to Modify Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS 3/4.5.1 to TS 3/4.5.2 as Surveillance Requirement 4.5.2.c B14532, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual1993-07-16016 July 1993 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual B14369, Application for Amend to License DPR-61,changing TS Re Editorial Cleanup,Including Incorporation of Missing Sections in Index,Providing Editorial Consistency Throughout Document & Removal of Cycle Specific Comments1993-03-16016 March 1993 Application for Amend to License DPR-61,changing TS Re Editorial Cleanup,Including Incorporation of Missing Sections in Index,Providing Editorial Consistency Throughout Document & Removal of Cycle Specific Comments B14327, Application for Amend to License DPR-61,revising TS Re Steam Generator Repair Criteria,To Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area1993-01-29029 January 1993 Application for Amend to License DPR-61,revising TS Re Steam Generator Repair Criteria,To Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area B14342, Application for Amend to License DPR-61,revising TS for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases.Draft Rev 0 to Project Assigment 90-013, CT Yankee Modernize Fwd Encl1993-01-29029 January 1993 Application for Amend to License DPR-61,revising TS for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases.Draft Rev 0 to Project Assigment 90-013, CT Yankee Modernize Fwd Encl ML20141M3441992-07-31031 July 1992 Application for Amend to License DPR-61,revising TSs to Reduce Unnecessary Plugging of SG Tubes in Tubesheet Expansion Zone Roll Transition Area B13669, Application for Amend to License DPR-61,reflecting Addition of New Manual locked-closed Containment Isolation Valve & Removal of solenoid-operated Containment Isolation Valve. Valve CC-V-884 No Longer Containment Boundary Valve1990-11-27027 November 1990 Application for Amend to License DPR-61,reflecting Addition of New Manual locked-closed Containment Isolation Valve & Removal of solenoid-operated Containment Isolation Valve. Valve CC-V-884 No Longer Containment Boundary Valve ML20062B7341990-10-22022 October 1990 Amend 132 to License DPR-61,adding Footnote to Tech Spec Table 3.3-2,Item 3,Table 3.3-3,Item 2 & 4.3-2,Item 3 B13619, Application for Amend to License DPR-61,clarifying Definition of Operability of Automatic Auxiliary Feedwater Initiation Sys at Plant for Cycle 16 Operation Only1990-08-25025 August 1990 Application for Amend to License DPR-61,clarifying Definition of Operability of Automatic Auxiliary Feedwater Initiation Sys at Plant for Cycle 16 Operation Only ML20055J2091990-07-26026 July 1990 Application for Amend to License DPR-61,allowing Plant to Progress Into Mode 3 W/O First Demonstrating Auxiliary Feedwater Sys Operability.Temporary Waiver of Compliance from Tech Spec 4.7.1.2.2 Requested Until NRC Acts on Amend ML20055G5401990-07-19019 July 1990 Amend 128 to License DPR-61,revising Tech Specs to Reflect Removal of Thermal Shield & Attached Surveillance Capsules ML20055G5551990-07-19019 July 1990 Amend 129 to License DPR-61,adding Footnote to Tech Spec Section 5.3.1, Fuel Assemblies to Allow Operation of Cycles 16 & 17 W/Two Solid Type 304 Stainless Steel Filler Rods in Place of Two Fuel Rods & Correcting Table 3.3-1a ML20055F3221990-07-0505 July 1990 Application for Amend to License DPR-61,revising Tech Specs Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases.No Radiological or Nonradiological Impact Associated W/Changes ML20055E2331990-07-0202 July 1990 Amend 126 to License DPR-61,revising Tech Specs to Reflect Mods Performed on Fire Protection Sys.Changes Include Increasing Smoke & Heat Detectors Required to Be Operable in Diesel Generator Rooms a & B & in Lube Oil Reservoir Area ML20055E0051990-06-25025 June 1990 Application for Amend to License DPR-61,establishing Limit of 160 Failed Fuel Rods for Cycle 16 Operation,Per 900524 Meeting ML20247K2291989-09-11011 September 1989 Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively, Allowing Licensees to Inspect Steam Generator Tubes by Insertion of Ultrasonic Test Probe from Cold Leg Side of Steam Generator Tube ML20247E3691989-09-0707 September 1989 Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Lifetime Records Retention for Radiological Effluent Monitoring & ODCM ML20247A4651989-09-0505 September 1989 Amend 121 to License DPR-61,revising & Combining Tech Spec Sections 3.6,3.7 & 4.3 B13333, Application for Amend to License DPR-61,revising Tech Spec Sections 3.6.2,3.9.11 & 3.9.12 Re Containment Air Recirculation Sys,Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys,Respectively1989-08-0404 August 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 3.6.2,3.9.11 & 3.9.12 Re Containment Air Recirculation Sys,Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys,Respectively B13324, Application for Amend to License DPR-61,revising Tech Spec 3/4.5.1, ECCS - ECCS Subsystem - Tavg Greater than or Equal to 350 F to Reflect Component Configurations Following 1989 Refueling Outage Mod to ECCS to Resolve Single Failure1989-08-0202 August 1989 Application for Amend to License DPR-61,revising Tech Spec 3/4.5.1, ECCS - ECCS Subsystem - Tavg Greater than or Equal to 350 F to Reflect Component Configurations Following 1989 Refueling Outage Mod to ECCS to Resolve Single Failure ML20248A0461989-08-0101 August 1989 Application for Amend to License DPR-61,modifying Proposed Tech Spec 3.12, Electrical Power Sys, Provided in .Tech Spec Incorporated Degraded Grid Voltage Protection Requirements in Westinghouse STS Format B13317, Application for Amend to License DPR-61,revising Tech Specs to Reflect Changes in Fire Detection/Suppression Sys Upgrades to Support New Switchgear Bldg Const1989-07-31031 July 1989 Application for Amend to License DPR-61,revising Tech Specs to Reflect Changes in Fire Detection/Suppression Sys Upgrades to Support New Switchgear Bldg Const ML20245E5921989-07-28028 July 1989 Application for Amend to License DPR-61,changing Tech Specs to Support Cycle 16 Operation ML20247R7071989-07-28028 July 1989 Application for Amend to License DPR-61,revising Tech Spec Sections 3.0/4.0 & 3.4.6.2 Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage 1999-08-24
[Table view] |
Text
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. CON N ECTICUT . YAN KEE ATO MIC POWER COMPANY l
B E R L I N, CONNECTICUT I
.. y P.o. Box 270
- HARTFORD, CONNECTICUT 06141-0270 TELEPHONE November 17,1987 ro>eas-sooo Docket No. 50-213 B12727 ,
. Re: 10CFR50.90 l
U. S. Nuclear Regulatory Commission
~Atto , Document Control Desk Washington, D. C. 20535 l
' Gentlemen:
l Haddam Neck Plant Proposed Revision to Technical Specifications j Degraded Grid Voltage Protection System i Pursuant ~ to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby ' proposes - to amend its Operating License, DPR-61, by
.-incorporating the attached proposed changes into the Technical Specifications of the Haddam Neck Plant.
'The proposed changes' to Technical Specification 3.12 involve the addition of operability requirements on off-site and on-site power sources with limiting
- conditions for operation (LCO) and time requirements for corrective actions. In addition, Technical Specification 4.2 has been modified to include requirements ,
for testing and channel calibration of the undervoltage setpoints, j Background i By letter dated October 20, 1981,(1) CYAPCO proposed technical specification ;
changes to reflect additional LCOs associated with the proposed degraded grid l voltage protection system. The NRC Staff provided its safety evaluation on !
degraded letter dated grid protection
. July of (Class 9, 1982. 21 IE power systems at the Haddam Neck Plant by As requested in the safety evaluation report,
- CYAP O submitted the operating procedures for NRC review on February 3, 1983.(
' (1) W. G. Counsil letter to D. M. Crutchfield, " Proposed Revisions to Technical Specifications," dated October 20,1981. ;
(2) D. M. Crutchfield letter to W. G. Counsit, " Degraded Grid Protection for h- Class IE Power Systems," dated July 9,1982.
W. G; Counsil letter to D. M. Crutchfield, " Degraded Grid Protection for 0 (3). . Class IE Power Systems," dated February 3,1983.
.q . 8711240098 871117 E D k
.P PDR- ADOCK 05000213 PDR _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _
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- B12727/Page 2
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k By, letterTdated 3uly 2,1985,(4)'the NRC Staff concluded that the procedures
, were acceptable; however, they stated _that the technical specifications P
Jsubmitted .on October 20, 1981 were not consistent' with these procedures.
Therefore, the NRC requested that CYAPCO revise and resubmit the technical
! ' specifications . to reflect the ' numerical values presented in the approved
- procedures.
Discussion LThe proposed changes involve revisions to portions of Sections 3.12 and 4.2 of the
- Haddam Neck Technical Specifications. The changes to Section 3.12 involve the l'
addition of operability requirements on off-site and on-site power sources with LCO and time . requirements for corrective actions. . The changes apply to Modes 1,2,3, and 4 and include:
o . Increasing from one to two the number of off-site circuits required to be operable, j o' : Increasing from one to. two' the number of emergency diesel generators (EDGs) required to be operable, o Increasing from three to all four 480V buses required to be operable, o The addition of new requirements for the operability of the four 120V vital buses, .
o Increasing from'one to two the number of battery chargers required
-to be operable and addition of new requirements for the two 125V
< DC batteries and associated buses to be available,
- o. The addition of LCO time limits given the loss of any 4160V,480V,
- 120V AC bus, DC power supply or EDGs, e
o Deletion of the EDG loading limit (2850 kW), and o The addition of a new requirement on undervoltage setpoints with LCO time limits for Modes 1 or 2.
. . . . i Section 4.2 is revised to add requirements for calibrating the level-one, level-two, and level-three undervoltage setpoints and performing channel functional tests. Please note that these setpoints are different than those previously submitted to the NRC in AOP 3.2-25, Revision 3. Since new transformers were installed during the present refueling outage, CYAPCO had to recalculate the I setpoints. These new setpoints will be incorporated in Revision 6 of AOP 3.2-25 prior to start-up.
i (4)' 3. A. Zwolinski letter to 3. F. Opeka, " Safety Evaluation for Degraded Grid Voltage Procedures," dated July 2,1985.
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.Significant Hazards Consideration In accordance with 10CFR50.92, CYAPCO' has reviewed the attached proposed changes .and .has concluded that they do not involve a significant hazards f
- consideration. The basis for this conclusion is that the three criteria of
.. .10CFR50.92(c)'are not compromised; a conclusion which is supported by our determinations ' discussed below. The proposed changes do not involve a
'significant hazards consideration because the changes do not:
1 1.. Involve a significant increase in the probability or consequences of an accident previously analyzed. The' impact of the change on design
' basis accidents (DBAs) which assume loss of off-site power has been
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reviewed and has been determined to be unaffected by the change.
The proposed changes in general provide for more conservatism in
'that the operability requirements for the on-site 4160V emergency buses, 480V buses,120V vital buses, and the 125V DC systems are more' restrictive than the existing-requirements. These changes do not : impact the failure probability of the associated electrical systems, rather L they. increase the probability that a train of emergency electrical; power is available following an accident. The probability. of occurrence or the consequences of the DBAs are 7 unchanged.-
In addition, the deletion of the loading limit on the EDGs does not affect the probability or consequences of an EDG failure. The
-loading limit was required when there was no circuit for load shedding prior to automatic sequencing of emergency safeguards loads onto each diesel generator. These circuits have since been installed and calculations have-shown these loads do not overload the EDGs. The potential for overloading the EDGs by the operator is. addressed by having caution statements in the Emergency Response Procedures.~. in addition, removing this requirement from
'.the Haddam Neck Technical Specifications is consistent with the NRC approved Westinghouse Standard Technical Specifications.
The proposed changes to Section 4.2 improve system availability by providing for ' periodic testing since no periodic testing was previously required. .These changes do not increase the failure '
probability of the undervoltage logic.
2.- Create the possibility of a new or different kind of accident from ;
any previously evaluated. There are no new failure modes associated !
with Technical Specification 3.12 since these changes involve more l restrictive requirements on the operability of the electrical power systems and do not involve design changes. No new accident is created because the same equipment is assumed to perform in the same' manner as before. The deletion of the EDG loading limit does not provide any new failure modes since this limit was required when there was no circuit for load shedding prior to automatic sequencing of loads onto each diesr! generator. These circuits have 2-___.
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- U. S. Nuclear Regulatory Commission L B12727/Page 4 '
. November 17,1987
.since been installed and calculations have shown these loads do not
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overload the EDGs. The potential for overloading the EDGs by the operator is ' addressed by caution statements in the Emergency Response Procedures. Thus, the deletion of the loading limit from
.Section 3.12 does not impact the failure probability of the EDGs nor does it increase the probability of an accident.
v Changes to Technical Specification 4.2 provide for periodic testing and calibration of the undervoltage setpoints. - The changes improve
' system availability by providing periodic testing since no periodic testing is specified in current technical specifications. The failure mode associated with' this change is mis-calibration; however, this l failure mode.is not new because the undervoltage setpoints are I presently tested and ' calibrated. Thus, because the potential for ;
mis-calibration. already _ exists, no new failure modes are created. j No'new potential accident is created because the proposed changes l
and associated failure modes -do not modify plant response.
Therefore, the proposed technical specification changes do not create the probability of an accident or malfunction of a different type than any evaluated previously in the safety analysis report.
- 3. Involve a significant reduction in a margin of safety. The protective boundaries are'not impacted because the consequences of the DBA are not affected.- Since the protective boundaries are not affected, the- safety limits are also - not affected. The proposed change
, ' maintains the basis'. of the technical specifications in assuring r electrical power operability.
1Moreover, the Commission has provided guidance concerning the applications of standards set forth in.10CFR50.92 by providing certain examples (March 6,1986, S . F,Rf 7751) of ' amendments that are considered not likely to involve a significant hazards consideration. The changes proposed herein are most closely enveloped by example (ii) which constitutes an additional limitation or control not presently included in Jhe technical specifications. Since the proposed changes provide for more restrictive operability requirements. and provide new requirements for testin.g and calibrating the undervoltage setpoints, the proposed changes result in added assurance that the electrical power system will be available. Therefore,
' the proposed changes would not involve a significant hazards consideration.
The.Haddam Neck Plant Nuclear Review Board has reviewed and approved the ,
. attached proposed revision and concurs with the above determinations. (
l In' ;accordance with 10CFR50.91(b), CYAPCO will provide the State of ;
Connecticut with a copy of this proposed amendment. {
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U. S. Nuclear Regulatory Commission B12727/Page 5 November 17,1987 Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment
- request is the application fee of $i50.00.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY Y H l'o r 2 Y A.
E. J. Mroczka ,
Senior Vice President hhf By: W. D. Romberg Vice President cc: Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 W. T. Russell, Region I Administrator A. Wang, NRC Project Manager, Haddam Neck Plant
- 3. T. Shed!osky, Resident inspector,~ Haddam Neck Plant
. STATE OF CONNECTICUT - )
) ss. Berlin
- COUNTY OF HARTFORD )
l Then personally appeared before me W. D. Romberg, who being duly sworn, did state that he is Vice President of Connecticut Yankee Atomic Power Company, a Licensee . herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
AAvA f&h flotary Fplic My Commission Expires March 31, 1988 s
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