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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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, ~ . o CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, C O N N E C TIC U T P o BOX 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 December 6,1985 Docket No. 50-213 B 11903 Director of Nuclear Reactor Regulation Attn: Mr. Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Haddam Neck Plant Proposed Revision to Technical Specifications Steam Generators Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby proposes to amend Operating License No. DPR-61 for the Haddam Neck Plant by incorporating the attached changes into the plant Technical Specifications. The proposed changes revise Technical Specification 4.10.1 - Inservice Inspection of Steam Generator Tubes to allow sleeving as a means to repair steam generator tubes and to include " pitting" as a mechanism causing steara generator tube degradation.
Background
By letter dated July 19, 1985(l) CYAPCO provided the NRC Staff with information concerning the activities planned for the 1986 refueling outage which will assure continued operability of the steam generators. One of the activities planned is to install sleeves inside defective tubes, thereby reducing the number of tubes which may be required to be taken out of service if the pitting corrosion identified during the last refueling outage has progressed substantially. Sleeving was successfully performed on the Millstone Unit No. 2 steam generators during the 1983 and 1985 refueling outages. The Haddam Neck Technical Specifications only allow steam generator tube plugging as a corrective measure for defective tubes. Therefore, this license amendment request to allow sleeving is necessary.
Description The repair process requires that sleeves be inserted inside defective steam generator tubes in a manner to completely span the defective tube region.
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(1) 3. F. Opeka letter to 3. A. Zwolinski, dated July 19, 1985 discussing CYAPCO's plans to sleeve and plug steam generator tubes.
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~ Plastic expansion'of the sleeve against the tube, at the top and bottom of the
- sleeve, provides a leak limiting joint which exhibits sufficient mechanical
' strength. to withstand normal operating, test and postulated accident loading conditions.. Figure I shows a typical repair configuration. The expanded sleeve forms a new section of the reactor coolant pressure boundary.
The repair process involves honing of the defective steam generator tube in the region to be sleeved and installation and mechanical expansion of the sleeve. An eddy- current test is then conducted to establish that the joint is properly expanded and accurately located. This examination also provides baseline data for future eddy current test examination.
The repair program will be conducted in accordance with ASME Section III,1980 Edition through Winter 1980 Addenda, and meet the provisions of-the original equipment specification;(2) Regulatory Guide 1.83 - Steam Generator Tubing Inspectability; and Regulatory Guide 1.121 - Steam Generator Tube Plugging Margin. This' repair program will be conducted under jurisdiction of ASME Section XI,1980 Edition through Winter 1980 Addenda.
The tube repair program planned for the Haddam Neck steam generators is essentially identical to that utilized for the Millstone Unit No. 2 steam generators during the 1983 and.1985 outages. Furthermore, sleeve installation will be conducted in accordance with Northeast Utilities Service Company (NUSCO) Specification SP-ME-518 which establishes that:
o The upper and lower mechanical joints have been qualified by design, analysis and design verification testing to ensure leak tightness, pressure retaining / load carrying ~ capability for normal and faulted design loading conditions, and adequate resistance to potential . stress-corrosion cracking and general corrosion concerns.
o All~ qualified process / installation parameters will be monitored during installation to ensure compliance with established acceptance limits and design objectives, o The tube sleeves were designed in accordance.with app!! cable ASME III fatigue requirements to ensure structural adequacy of sleeves for
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remaining service lifetime.
o - The hard rolling of the bottom tube sleeve joint will not degrade the tube-to-tube sheet weld.
o The tube sleeves were sized to minimize sleeve / tube interaction and loading on the upper joint.
(2) The original design ba3es for Connecticut Yankee (CY) steam generators include the Safety Technical Specifications; Facility Description and Safety Analysis; Combustion Engineering, Inc. Report No.1090: Analytical Report for CY Reactor Vessel, January 1965; Westinghouse' Electric Corporation Technical Manual 1440-C78 for Model 27. Steam Generator, December 1966; Westinghouse Report WNEP-8521: CY Steam Generators Stress Report,
. April I,1985; and ASME Code Case No.1270N.
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o: All sleeves are shop hydrotested in excess of 3,000 psig, in lieu of the minimum required 1,000 psig test,. to ensure structural integrity / leak tightness.
o Additional shop NDE and metallurgical inspections were implemented to ensure tube sleeve material soundness.
_o The tube sleeve extends a minimum of 1 inch above the top joint strictly to prevent a potential double-ended tube rupture.
o- The design provides for automatic and hands-on sleeve installation.
o The tube sleeve design minimizes increase to primary flow resistance.
o :The structural integrity of the existing steam generator tubes will not be degraded by the tube sleeve installation.
The Millstone Unit No. 2 reports (3X4)in conjunction with numerous other reports available in the literature also establish that the corrosion resistance of Inconel 690 sleeves will be superior to the mill-annealed Inconel 600 tubes that
, currently exist in the Haddam Neck steam generators. .
1 . The Haddam Neck' sleeving qualification report will be submitted under separate -
cover by December 16, 1985. This report will provide _the necessary analytical and test data to verify that Inconel 690 sleeves can be used in the Haddam Neck steam generators.
. CYAPCO .has reviewed the attached proposed change pursuant to the
, < requirements of 10CFR50.59 and has determined that it does not constitute an unreviewed safety question. The basis for this determination is discussed below.
Safety Evaluation Effect of Deslan Basis Accident Analysis Steam generator tube repair, whether by plugging or sleeving, increases the flow resistance through that steam generator, decreases the available heat transfer area and reduces the volume of primary coolant. Therefore, there are limits to the number of steam generator tubes that can be repaired without affecting the assumptions made in the accident analysis. '
Calculations show that the 9% core bypass flow assumed in the original Haddam n . Neck accident analyses was excessively conservative. Recent calculations by
- the original NSSS vendor show that the bypass flow can be reduced from 9% to
- l. 4.5% and still be conservative. 'This 4.5% bypass flow reduction and a proposed i
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'(3) W. G. Counsil . letter to R. A. Clark, dated June 3, 1983 transmitting Westinghouse Report WCAP-10267, " Millstone Unit No. 2 Steam Generator i
' Sleeving Report." ' '
information was s in W. G. Counsil letter to
-(4)1. ~Suk.lemented Miller, dated November 17,198$ piled !
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change to the moderator temperature coefficient Technical Specification provide sufficient margin to allow up to 500 equivalent generator (a total of 2,000 equivalent plugged tubes) plugged without tubes requiring new per steam transient analyses. CYAPCO is currently projecting the need to sleeve 650 tubes and plug 135 tubes. This projection is based on previous eddy current test data and projected progression rates based on pitting corrosion experienced at Haddam Neck and Millstone Unit No. 2. Therefore, the present accident analyses remain bounding and there is no need to perform new accident or transient analyses.
Large break loss of coolant (LBLOCA) calculations have been performed and have included the effects of steam generator sleeving and plugging. Proposed Technical Specification changes to revise allowable peak linear heat generation rates and axial offset operating limits will be submitted based on results of the LBLOCA calculations. These proposed Technical Specification changes and a change to the reactor coolant system flow rate Technical Specification will be included in the proposed reload license amendment which will be submitted under separate cover. As stated previously,(1) the results of the evaluations and calculations will be provided with the sleeving qualification report by December 16, 1985.
Because of the above assessments, this proposed Technical Specification change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
Potential for Creation of an Unanalyzed Accident Repair of steam generator tubes by sleevmg reduces the probability of tube rupture due to wall thinning by corrosion. Regardless of this increase in safety, generic and exceptional failures can be postulated. These failures are reviewed with respect to effect, and preventative safeguards are noted.
The most serious safety implications arise from generic failures. Incorrect sleeve installation or design could result in an accident equivalent to a multiple tube rupture. For example, if the sleeve joints were partially expanded and not rolled, the potential for multiple sleeve ejection would exist. Besides the resulting loose parts, many defective tubes would then be exposed to the primary system fluid which could then leak into the secondary system. Incorrect design could lead to the same result by ignoring an important loading condition.
Because such generic failures could have severe safety consequences, a great deal of attention has been paid to design and installation aspects of the tube repair program. The design bases, compliance documents and installation procedures will be reviewed in detail to assure that no generic failures will occur. Northeast Utilities Quality Assurance plan will be used to assure that sleeves are fabricated and designed correctly. Thus, generic failures are essentially precluded.
Failures may be postulated which would not occur to all the sleeves but would be unique to a specific sleeve. This would include a single fabrication defect or incorrect installation. Single sleeve ejection with a tube rupture is the worst postulated failure.
Safeguards for exceptional failures are provided by multiple inspections for both as-fabricated and as-installed sleeves. Every sleeve is inspected after fabrication by non-destructive means - (visual, dimensional, ultrasonic, hydrostatic, and eddy _ current). Destructive examinations are performed on laboratory mock-ups on a sampling basis. Visual inspections for shipping damage are performed at the site. After installation, every sleeved tube is eddy current-tested and the results are checked by vendor and NU Quality Control. Finally, the secondary system is filled and pressurized to identify any leaking tubes.
Because of the extensive qualification process, sleeve specification, inspection and : testing, and controls on sleeve installation, these failure modes are
- considered to be improbable.
- As a result,-this proposed Technical Specification change does not create the possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report.
Effect on the Marain of Safety The design specification for the sleeves, the sleeve inspection,-sleeve testing, and installation procedures will result in a repaireJ steam generator tube which is structurally sound. The repaired tube will provide a pressure boundary function which meets all necessary requirements. Therefore, repairing steam generator tubes by sleeving will not be detrimental to public health and safety.
Therefore this proposed Technical Specification change does not reduce the margin of safety as specified in the basis of any technical specification.
Summary and Conclusion Because of the above assessments, the changes implemented by this proposed Technical Specification change are considered to be safe and do not constitute an unreviewed safety' question, as defined in 10CFR50.59 since it does not:
- 1. Increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report,
- 2. Create the possibility for an accident or malfunction of a different type
..than that previously analyzed in the safety analysis report, or
- 3. : Rt. duce the margin of safety as defined in the technical specifications.
~ ALARA Considerations The CYAPCO has taken into account ALARA considerations for each of the activities required in the steam generator sleeving and plugging program at Haddam Neck. ALARA activities specifically directed to reduction of
-occupational radiation doses include decontamination of steam generator channel heads, special shielding to reduce exposure to personnel during channel head and tube sheet operations, a control ventilation system for the channel heads' and
-other surrounding work areas, special tools designed for high radiation areas, TV and audio surveillance of all platform and channel head operations, and personnel
r training in full-size mock-ups. CYAPCO has verified the training program is in accordance with Regulatory Guides 8.27, 8.29 and 8.13 or equivalent. In addition, CYAPCO and its sleeving contractor, Westinghouse, make extensive use of classroom and mock-up training for individuals who perform sleeving operations.
CYAPCO estimates the total collective dose will be 518 person-rems for the Haddam Neck steam generator inspection and repair activities. This collective dose will include all occupational doses resulting from the sleeving operation incluo.ng all site and contractor support personnel. CYAPCO estimates that 90% of the dose will be received by technicians (platform and channel head workers).
A breakdown of each task by estimated dose is provided as follows:
Tube Plugging 64 person-rems Tube Sleeving 300 person-rems Eddy Current Testing 47 person-rems Decontamination 60 person-rems Other Activities
- 47 person-rems Total 518 person-rems
- Other activitim 1,clude man-way removal and installation, nozzle dam installation and remcval, tube pulling, and platform preparation.
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 consideration. The basis for this conclusion is that the three criteria of 50.92(c) are not compromised, a conclusion which is supported by our determination made pursuant to 10CFR50.59. The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (April 6,1983, 48 FR 14870) of amendments that are considered not likely to involve significant hazards considerations. Example (i) relates purely to a administrative change to the Technical Specification. For example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature. Example (vi) relates to 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 with respect to the system or component specified in the Standard Review Plan. For example, a change resulting from the application of a small refinement of a previously used calculational model or design method. The changes discussed above are similar to examples (i) and (vi) of 48 FR 14870 and thus do not involve a significant hazards consideration. The following is a detailed description of how each of the changes discussed above are similar to the examples of 48FR14870.
The change to the definition of degradation in Technical Specification 4.10.1.D.I.b recognizes the phenomena of pitting as a mechanism causing steam generator tube degradation and is similar to example (i). The change to Technical Specification 4.10.1.D.2 will allow sleeving as a means to repair steam generator tubes and is similar to example (vi). The change to
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Technical Specification 4.10.1 Sections D.I.3, D.I.f, E, the bases, and Table 4.10.1-2 provide consistency throughout the Technical Specification and is similar to example (1). Based on the above considerations, CYAPCO has determined that these changes do not involve a significant hazards consideration.
In accordance with 10CFR50.91(b), CYAPCO is providing the State of Connecticut with a copy of this proposed amendment.
The Haddam Neck Nuclear Review Board has reviewed and approved' this proposed amendment and has concurred with the above determinations.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.00 Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY AE Cd
- 3. F. OpeWa O Senior Vice President cc: Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06116 Dr. Thomas E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me 3. F. Opeka, who being duly sworn, did state that he is Senior Vice President of Connecticut Yankee Atomic Power Company, Licensees herein, that he is ~ authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
A A Abrt .
IVotary Publiff My CommissioHxpires March 31,1988 i
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