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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217K3221999-10-19019 October 1999 Amend 195 to License DPR-61,deleting Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor,Duplicate Regulatory Requirements or Duplicate Info Located in UFSAR ML20206C8731999-04-28028 April 1999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 ML20202D1521998-06-30030 June 1998 Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant 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 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 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 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 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 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 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 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 ML20247E6501989-07-20020 July 1989 Amend 120 to License DPR-61,changing Tech Specs 3.17.1, Axial Offset & 3.17.2, LHGR, to Allow Coastline Operation of Plant at End of Cycle 15 ML20247E6781989-07-18018 July 1989 Amend 119 to License DPR-61,splitting & Revising Tech Spec Section 3.3.1.5 Re Isolated Loop ML20246L2501989-06-26026 June 1989 Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,deleting Tech Spec Figures 6.2-1 & 6.2-2 by Replacing Figures W/Narrative Description of Offsite & Onsite Organizations Functional Requirements ML20244C4411989-06-0101 June 1989 Amend 117 to License DPR-61,revising one-time Relaxation of Containment Integrity Tech Specs to Allow Cleaning or Replacement of Containment Air Reciculation Fan Motor HXs While at Power ML20248B2941989-05-31031 May 1989 Amend 116 to License DPR-16,adding New Tech Spec Section Re RCS Leakage Detection Sys ML20245J0691989-04-25025 April 1989 Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs of Four Units to Be Consistent W/Plant Restart Provision in 10CFR50.36 If Safety Limit Exceeded ML20246F8131989-04-24024 April 1989 Amend 115 to License DPR-61,changing Tech Specs Re Various Operation Conditions & Surveillance Requirements,Including post-accident Sampling,Noble Gas Effluent,Rcs Vents & Sampling & Analysis of Plant Effluents ML20245E8901989-04-21021 April 1989 Amend 113 to License DPR-61,modifying Paragraph 2.C.(5) of License to Require Compliance W/Physical Security Plan ML20235Z0861989-03-0707 March 1989 Amend 112 to License DPR-61,providing one-time Relaxation of Containment Integrity Tech Specs to Allow Svc Water Side of Four Containment Air Recirculation Fan HXs to Be Cleaned While at Power ML20196D8541988-12-0606 December 1988 Amend 109 to License DPR-61,revising Table 3.22-2 Fire Detection Instruments to Reduce Number of Smoke Detectors Available in Containment from 23 to 22 & Incorporating New Section of Sprinkler Protection Into Tech Spec 3.22G ML20205M5591988-10-26026 October 1988 Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively,modifying Tech Spec to Mofify Qualifications & Conduct of Nuclear Review Board for All Units ML20155G2791988-10-0303 October 1988 Corrected Amend 106 to License DPR-61,revising Tech Specs Re Weld Locations on Steam Supply Lines to Auxiliary Feedwater Pumps ML20155G4751988-09-28028 September 1988 Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs to Provide for Uniform Addresses for Listed Classes of Repts for Plants ML20151T7551988-08-0909 August 1988 Amend 106 to License DPR-61,revising Tech Spec 4.12, High Energy Piping Sys, Expanding Augmented Inservice Insp Program to Include Weld Locations on Steam Lines to Auxiliary Feedwater Pumps ML20150A9511988-07-0101 July 1988 Amend 105 to License DPR-61,revising Tech Specs Table 3.11-1, Containment Isolation Valves, by Adding Five New Containment Isolation Valves (CIV) & Deleting Two CIVs ML20155F9601988-06-0101 June 1988 Amend 104 to License DPR-16,increasing Required Number of Halon Storage Cylinders in Switchgear (SR) in Tech Spec 3.22.C.1 from 7 to 8 & Number of Smoke Detectors in SR from 32 to 35 in Table 3.22-2 ML20155G4971988-05-26026 May 1988 Amend 103 to License DPR-61,renumbering Manual HPSI Throttle Valves in Tech Spec 3.6.B.2 to Be Consistent W/Plant Loop Numbering Scheme ML20153G9591988-04-28028 April 1988 Corrected Amend 97 to License DPR-61 ML20151G0871988-04-0808 April 1988 Amend 102 to License DPR-61,revising Tech Spec Figures 3.17-1A & B & Section 3.17,2 to Reduce LHGR by Approx 1KW/ft W/Corresponding Reduction in Axial Offset Limits for Four Loop Operation ML20147E8591988-02-23023 February 1988 Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively,amending Tech Specs to Identify Nuclear Review Board Minutes as Acceptable Means to Forward Certain Repts & Having Max of 12 H Continuous Planned Inoperability ML20149M8841988-02-22022 February 1988 Amend 99 to License DPR-61,revising Tech Spec 5.4, Containment, by Deleting Section 5.4.B, Penetrations, Which Refs Design Info Concerning Penetrations & Associated Bases ML20148F4461988-01-19019 January 1988 Amend 98 to License DPR-61,changing Expiration Date from 040526 to 070629 ML20236S3731987-11-12012 November 1987 Amend 97 to License DPR-61,supporting Operation of Plant for Cycle 15 & Reflecting Major Efforts in Upgrading design-basis Accident Analyses & in Reformatting Tech Specs as Part of Conversion to Westinghouse STS ML20235R9881987-09-30030 September 1987 Corrected Tech Spec Pages to Amends 93 & 94 to License DPR-61,reissued to Eliminate Inadvertent Changes in Amend 93 Caused by Amend 94 & Properly Reflect Info Approved Separately for Each Amend ML20235S5251987-09-25025 September 1987 Amend 96 to License DPR-61,revising Tech Specs to Provide long-term Acceptance Criteria for Steam Generator Tubes W/ Defects in Rolled Region & to Update Bases for Criteria ML20235R4121987-09-23023 September 1987 Amend 95 to License DPR-61,replacing Tech Specs 3.19 & 4.13 Re Snubbers W/Tech Specs Consistent W/Nrc Model STS & W/ Current Industry Guidelines Such as Generic Ltr 84-13 ML20235J0151987-09-10010 September 1987 Amend 94 to License DPR-61,revising heat-up Rate Curve & Providing Larger Interval for Low Temp Pressurization Protection Sys to Be Placed in Operation ML20235G7701987-09-0909 September 1987 Amend 93 to License DPR-61,requiring New Periodic Surveillance Requirement to Ensure Correct Valve Position & post-maint Surveillance Requirements for Throttle Valves ML20237G5421987-08-0505 August 1987 Amend 92 to License DPR-61,revising Tech Specs to Allow Possession & Use of Certain Byproduct Matl 1999-04-28
[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-97-024, 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 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 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 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 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 ML20055G5401990-07-19019 July 1990 Amend 128 to License DPR-61,revising Tech Specs to Reflect Removal of Thermal Shield & Attached Surveillance Capsules 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 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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Id p r are o# UNITED STATES s j f, NUCLEAR REGULATORY COMMISSION g g- y. WASHINGTON, D. C. 20566 Ya f.
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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213
% HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE 1 Amendment No. 95 License No. DPR-61 g
The Nuclear Regulatory Comission (the Comission) has found that:
1.
A. The. application for amendment by Connectir.ut-Yankee Atomic Power Company (the licensee), dated June 1, 1987. complies with the standards and requirements of the Atomic Energy Act of 1954, J' as amended '(the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility _will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; .
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of.this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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87100B0039 870923 PDR ADDCK 05000213
'F PDR v _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _ -
4
- 2. According$y,thelicenseisamendedbychangestothe-Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised
! through Amendment No. 95, are hereby-incorporated into the license.-
The licensee shall operate the facility in accordance with the Technical Specifications.
L 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION U$ m Cecil 0. Thomas, Director Integrated Safety Assessment Project Directorate Division of Reactor Projects III/IV/V and Special Projects
Attachment:
Changes to the Technical
- Specifications Date,of Issuance: September 23, 1987
u___e__ , _ - - -_-_x_,._w__ _
I
- . . I t, ATTACHMENT TO LICENSE AMENDMENT NO.- 95 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Revise' Appendix A. Technical Specifications by removing the pages identified' {
below and. inserting the enclosed pages. The revised pages are identified .]
by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3-38 3-38 Table 3.19-1 --
4-26, 4-26 4-27' 4-27 1
4-28 4-28 4-29 4-29 1
. . 1 i,
3.19 Snubbers Applicability: This specification applies to snubbers which are attached to the reactor coolant system and all other safety-related i y
r systems whose structural integrity is needed to be maintained during and following a seismic or other event initiating dynamic loads.
Objective: To assure reactor coolant system and other safety related system motions are adequately restricted should a design basis earthquake or other transient occur.
Specification: A. During Modes 1, 2, 3, and 4 (Modes 3 and 6 for '
snubbers located on systems required operable in those Modes) all safety-related snubbers shall be maintained in an operable condition except as noted in 3.19.B below. Snubbers on nonsafety-related systems shall be operable if their failure or failure of the system on which they are installed would have an adverse effect on any safety-related system.
B. With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to operable status and perform an engineering evaluation per Specification 4.13.c on the supported component or declare the supported system inoperable and follow the appropriate specification for that system.
Bases All snubbers are required to be operable to ensure that the structural integrity c.
the reactor coolant system and all other safety-related systems are maintainn during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those insta!!ed on nonsafety-related systems and then only if their failure, or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
When a snubber is found inoperable, an engineering evaluation is performed, in cddition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
Amendment No. 9, M , 95 3-38 P'
4.13 Snubbers I
1 Applicability: This specification applies to the snubbers required to be ;
operable in accordance with Specification 3.19. I Objective: To provide assurance of snubber operability over the plant service lifetime.
Specification: Each snubber shall be demonstrated operable by performance of the following augmented inservice inspection program.
A. Visual Inspection Schedule All snubbers shall be visually inspected in accordance with the following schedule:
Number of Snubbers Found Inoperable During Inspection Next Required Or During Inspection Interval Inspection Interval *# l 0 18 months + 25 %
1 12 months ! 25%
2 6 months ! 25%
3, 4 124 days E 25%
5,6,7 62 days 1 25 %
8 or more 31 days 1 25 % l The snubbers may be categorized into two groups: those accessible, and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time, i
- The provisions of Specification 4.0.2 are not applicable.
B. Visual Inspection Acceptance Criteria Visual inspection shall verify (1) that there are no visible indications of damage or impaired operability, and (2) attachments to the foundation or supporting structure are secure. The inspection will also identify indications of excessive leakage from hydraulic snubber reservoirs or connections. Snubbers which appear inoperable as a result of visual inspections may be determined operable for the purpose l of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected ,
snubber is functionally tested in the as-found condition and l determined operable per Specifications 4.13.D or 4.13.E, as i applicable.
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C. - ~ Functional Tests j {
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l- At least 'once per 18 months during shutdown, a 5 y representative sample of at least 10% of the total of each !
r type of snubber in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.13.D or 4.13.E, an additional 5% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of j snubbers. At least one (1) snubber shall be selected from j each piping system containing snubbers. At least one (1) snubber shall be tested from the full range of snubber manufacturers and snubber sizes used. In the selection of .
the representative sample, consideration shall be given to i other effects on snubbers such as vibration in the vicinity of equipment such as pumps, motors, turbines, valves, etc.
or fluid forces from a relief valve discharge.
Functional test samples shall be rotated such that different snubbers are tested at each test interval.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these i snubbers may not be included for the re-sampling. { i If any snubber selected for functional testing either fails f to lockup or fails to move, i.e., frozen in place, the cause l will be evaluated and if caused by manufacturer or design )
deficiency, all snubbers of the same design subject to the i same defect shall be functionally tested. This testing requirement shall be independent of the requirements {
stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this l engineering evaluation sha!! be to determine if the '
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components supported by the snubber (s) were adversely I
affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of
,: meeting the designed service requirement.
D. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
- 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 2. Snubber bleed, or release rate, where required, is !
within the specified range in compression or tension. 1 For snubbers specifically required not to displace "
under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
E. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
- 1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
- 2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under
, continuous load, the ability of the snubber to withstand load without displacement shall be verified.
F. Snubby S_ervice Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.h.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each safety-related snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next i
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i scheduled snubber service life review, the snubber service
. life shall be reevaluated or the snubber shall be replaced 5 or reconditioned so as to extend its service life beyond l the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
I Bases The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before '
the original required time interval has elapsed (nominal less than 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and vibration.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. These tests will include stroking of snubbers to verify freedom of movement over the full stroke, restraining characteristics, and drag force (if applicable). Ten percent (10%) of the total of each type of snubber represents an adequate sampling for these tests. Observed failures on these samples require testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance program.
The service life is evaluated via manufacturer input and information with consideration of snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, high temperature areas, location of potential fluid transient loading, etc.) The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of age and operating conditions. (Due to implementation of the snubber service life monitoring program af ter several years of plant operation, the historical records to date may be incomplete.) Snubber service life records will provide a statistical basis for future consideration of snubber service life.
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