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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
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N UTILITIES con.r.i oti.c. . seiden street. Bernn. connect'cui RTF RD CONNECTICUT 061414270 L t T; ;;:r.:C," =.',"~~ (2m> 6em October 26, 1988 Docket No. 50-213 B13056 Re: 10CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 205S5 Gentlemn:
Haddam Neck Plant Amendment Request for Sections 1.0, 3/4.2, 3/4.9, 3/4.10, 3/4.11, 5.0 and 6.0 of the Revised Technical Soecificatin i
! Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby proposes to amend its Operating License, DPR 61, by including the attached proposed changes as part of a new improved set of Technical l Specifications which will be forwarded for your review piecemeal.
l Discussion l The purpose of this submittal is to provide the first in a series of submittals forwarding amendment requests which will ultimately comprise an
, improved set of Technical Specifications for the Haddam Neck Plant. Along with amendment requests for Sections 1.0, 3/4.2, 3/4.9, 3/4.10, 3/4.11, 5.0 and 6.0 (the numbering and format is consistent with Westinghouse Standard Technical Specifications (STS), Rev. 5) supporting documentation has bean included. Also, included below is a discussion of CYAPCO's intended review process.
CYAPC0 acknowledges the receipt of your letter dated September 22, 1987.III We believe that the review method sugp,ested by this letter for our amendment request does not represent the optimum approach to amending our License.
(1) See the F. H. Akstulewicz letter to J. F. Opeka, dated September 22, 1987.
8811030387 881026 p\ 5' PDR ADOCK 05000213 i N t P PDC Q ( 7]
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U.S. Nuclear Regulatory Comission B13056/Page 2 October 26, 1988 As a matter of interest, we are providing a comparison gtrix which compares the amendment requests to the Westinghouse STS, Rev. 5 as well as to our current Technical Specifications.
Benefits of Amendina Technical Soecifications Revisions to the current Technical Specifications utilizing the Westinghouse STS will provide comon benefits to CYAPC0 as well as the NRC. From our perspective the revised specifications will:
o Provide a set of Technical Specifications with concise action statements and a complete set of surveillance requirements that complement the limiting conditions for operation, o Utilize a standard format that will be a benefit from a training perspective by providing a more consistent organization when considering training of operators transferring from other plants.
o Improve the development of more consistently formatted station surveillance procedures through the review and, in some cases, rewriting or originating procedures needed because of the revised surveillance requirements.
o Reduce the number of future amendment requests by making a one time improvement of Technical Specifications.
From the NRC's perspective, we believe the benefits include:
o Easter familiarization with the plant's Technical Specifications.
o More concise Technical Specifications with less ambiguities.
o A convenient mechanism for closure of all outstanding comitments associated with:
-NUREG 0737 Technical Specifications,
-Systematic Evaluation Program (SEP), and
-Various Generic letter Recomendations o Ultimate elimination of the "administrative" Technical Specifica-tions.
(2) This Revision 5 version of the Westinghouse STS was the draft version used in the development of Millstone Unit No. 3 Technical Specifications.
i U.S. Nuclear Regulatory Commission B13056/Page 3 October 26, 1988 t
To these ends, working towards the implementation of a revised set of Technical Specifications for the Haddam Neck Plant is a worthwhile ;
undertaking for both organizations. '
Review and Imolementation CYAPC0 views the proposed Technical Specifications update process as one '
which can be. reviewed in a step wise fashion and implemented at an agreed u)on time upon completion of all reviews and approvals. Overall, we expect ;
t1e entire set of specifications to be submitted over a three nonth period ,
beginning with this submittal. With this submittal, six sections are being '
forwarded. Our intent is to conduct a review process similar to the one utilized for the Cycle 15 Reload Technical Specifications. Any ['
clarification meetings needed to facilitate the NRC's evaluation tsf our amendment requests are welcome on an as needed basis. ;
i With respect to the actual review process, CYAPCO does not perceive the l process as any different than that required to approve an amendment request r i.e., staff conclusions need to be made on the adequacy of our 50.92 ,
evaluations. This process is distinctly different from that used for the i development of Technical Specifications for a near-term operating license ;
(NTOL) apolicant where significant applicant / staff interaction occurs to '
ensure standard Technical Specifications are tailored to reflect the design !
basis of a new unit. In contrast, the approval process of an amendment request for a License concentrates on verifying the changes from the '
approved Technical Specifications do not constitute a significant hazards consideration and are consistent with the plant's design basis. A NUREG is i not issued upon completion of review. Further, the Licensee is not expected ;
to sign a sworn statement that the revised Technical Specifications reflect l the plant's design basis. CYAPC0 believes such a statement would be :
redundant to the signed oath that omendment requests are forwarded under.
Etgg d Rules Because of the intended scope of this Technical Specification improvement project and the fact that Revision 5 to the Westinghouse STS is being used !
cxtensively as a guide to model the new specifications, it is important to :
reiterate some important ground rules that have always been our !
understanding. CYAPC0 believes that the Westinghouse STS should be adopted !
except when: l (1) Plant-specific design considerations would dictate othenvise, or l (2) Hardware, structural, or organization changes from previously approved [
conditions would be required to conform to the Westinghouse STS, or l
(3) Based on past operating experience, the existing plant-specific L requirement can be shown to provide an equivalent degree of protection to that provided by the Westingheuse STS.
U.S. Nuclear Regulatory Commission B13056/Page 4 October 26, 1988 It is important that implementation take place during a mutually agreed upon time frame with careful consideration given to the implementation of new '
surveillance requirements.
A logistical detail which we believe needs to be agreed upon by both the NRC i and CYAPC0 is as follows: ,
o For those sections which have been approved but not yet implemented, a mechanism should be established to make revisions.
CYAPC0 believes this can be accomplished through the normal amendment process whereby your review would concentrate on any ;
proposed revisions to a section without the need to reopen the '
review of an entire section that has already been approved but not yet implemented.
Eggoortina Documentation In support of tile amendment requests for Sections 1.0,3/4.2,3/4.9,3/4.10, 3/4.11, 5.0 and 6.0 four attachments are being provided as described below:
o Attachment I forwards the revised Technical Specification pages, o Attachment 2 provides a description of the changes from the ,
existing Technical Specifications. CYAPC0 has reviewed the prososed revised Technical Specification changes in accordance witi 10CFR50.92 and has determined that they do not involve a significant hazards consideration. The basis of this !
determination is discussed in Attachment 2. !
o Attachment 3 provides a comparison matrix as described in the i preface to that attachment. [
o Attachment 4 provides a commitment summary of outstanding open issues intended to be resolved through the implementation of the revised Technical Specifications. This listing is cross referenced to the revised Technical Specifications.
Moreover, the Commission has provided guidance concerning the application of the standards in 10CFR50.97. by providing certain examples (March 6,1986, FR7751) of amendments that are considered not likely to involve a significant hazards consideration. The changes proposed herein are enveloped by example (ii), a change that constitutes an additional limitation, restriction or control not previously included in the Technical Specifications. These proposed changes would add Limiting Conditions for Operation and Surveillance Requirements for the systems covered under the proposed revised Technical Specification sections. This will help ensure the operability and reliability of the systems covered under the proposed revised Technical Specification sections. Therefore, the proposed changes do not impact the consequences of any design basis accident.
i l
i U.S. Nucioar Regulatory Commission B13056/Page 5 October 26, 1988 Based upon the information in this submittal, there are no significant radiological or nonradiological impacts associated with the proposed changes, and the proposed license amendment will not have a significant effect on the quality of the human environment. The Haddam Neck Nuclear Review Board has reviewed and approved the proposed changes and has c concurred with the above determination.
In accordance with 10CFR50.91(b), CYAPC0 is providing the State of Connecticut with a copy of this proposed amendment.
Pursuint to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.00.
Should you have any questions on the attached amendment request and/or feel a meeting would help clarify the attached material please contact our licensing representative directly.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY ti. S .%h E. J. Mroczka "
Senior Vice President By: C. F. Sears Vice President ec: Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, CT 06116 W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shediosky, Senior Resident Inspector, Haddam Neck Plant
U.S. Nuclear Regulatory Commission
~B13056/Page 6 October 26, 1988 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me C. F. Sears, 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, i saUu%. (%el
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