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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MONTHYEARML20217K3221999-10-19019 October 1999 Amend 195 to License DPR-61,deleting Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor,Duplicate Regulatory Requirements or Duplicate Info Located in UFSAR ML20207G6321999-06-0303 June 1999 Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Replacing Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generid Titles 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 ML20207L2581999-03-0505 March 1999 Amend 104 to License DPR-21,changing TSs for Staffing & Training Requirements to Allow Use of Certified Fuel Handlers to Meet Plant Staffing Requirements ML20236K3401998-07-0101 July 1998 Amend 218 to License DPR-65,changing TS by Modifying Low Temp Overpressure Protection Requirements ML20202D1521998-06-30030 June 1998 Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant ML20217K8651998-04-0101 April 1998 Errata to Amend 103 to License DPR-21.Page Inadvertently Listed Bases Page B3/4 1-2 Instead of B 3/4 1-2a 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 ML20212G5861997-10-27027 October 1997 Amend 103 to License DPR-21,revising TSs Sections 3.1 & 4.1, RPS & Associated Bases to Remove Run Mode Intermediate Range Monitor High Flux/Inoperative W/Associated Average PRM Downscale Scram Trip Function ML20212F1301997-10-22022 October 1997 Amend 102 to License DPR-21,clarifying Requirement for Calibr of Instrument Channels That Use RTD or Thermocouples ML20211K1531997-10-0202 October 1997 Errata to Amend 122 to License NPF-49.Original TS 1-8 Replaces Revised Page That Should Not Have Been Included in Rev ML20141L8791997-05-28028 May 1997 Amend 101 to License DPR-21,revising TS on Allowed Outage Times for Protective Instrumentation & for RB Access Control 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 ML20137V5811997-04-15015 April 1997 Amend 100 to License DPR-21,deleting License Condition 2.C.(5), Integrated Implementation Schedule from Plant Unit 1 Operating License ML20137U2961997-04-10010 April 1997 Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Revising Section 6, Administrative Controls, of Plant,Units 1,2 & 3 TSs to Reflect Organizational Changes That Have Been Implemented in Nuclear Division ML20133N3311997-01-14014 January 1997 Amend 98 to License DPR-21,modifying Applicability Requirements for Certain Radiation Monitors So That Radiation Monitors Required to Be Operable Only When Secondary Containment Integrity Required ML20128L7491996-10-0404 October 1996 Amend 97 to License DPR-21,removing TS Figure 5.1 & Substitutes Defined Requirement for Max Koo for Fuel Placed in Plant Spent Fuel Pool ML20058L6881993-12-14014 December 1993 Corrected Amend 70 to License DPR-21,adding Safety Evaluation Date to License Condition 2.C(3) & Correcting Typo in License Condition 2.C(4) ML20058H7881993-12-0101 December 1993 Amend 70 to License DPR-21,modifying Operating License Condition 2.C(3), Fire Protection, by Deleting Existing Wording of License Condition & Replacing W/Standard Wording Provided in GL 86-10 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 ML20059L6921993-11-10010 November 1993 Amend 68 to License DPR-21,revises Surveillance Requirements for Local Leak Rate Testing Which Are Included in TS Section 4.7.A,to Remove 5% L Limit 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 ML20059H8311993-11-0101 November 1993 Amend 67 to License DPR-21,changing TS 4.7.A.3.d(2) 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 ML20059G0811993-10-27027 October 1993 Amend 66 to License DPR-21,increasing Max Stroke Time for RWC Sys Isolation Valves CU-2,3,5 & 28 from 18 to 20 in TS 3.7.1 ML20057F8491993-10-12012 October 1993 Amend 65 to License DPR-21,removing Fire Protection Requirements from TS 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 ML20057G3561993-09-29029 September 1993 Corrected Page 2 to Amend 64 to License DPR-21,revising Implementation Date to Occur by End of Cycle 14 Refueling Outage (Jan 94) 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 ML20057D7431993-09-29029 September 1993 Amend 64 to License DPR-21,removing Operability & Associated SR for Main Steam Line Radiation Monitor Scram & Group I Containment Isolation Functions 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 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 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 ML20128P7991993-02-19019 February 1993 Amend 61 to License DPR-21,allowing for Temporarily Bypassing MSLRM Trip Function for Period Not to Exceed 2 Hours,In Order to Allow Condensate Demineralizers to Be Returned to Svc ML20127E3921993-01-11011 January 1993 Amend 60 to License DPR-21,providing Alternative to Increase in App J,Type a Test Frequency Incurred After Failure of Two Successive Individual Leak Rate Tests ML20058F7161990-11-0101 November 1990 Amend 47 to License DPR-21,deleting Requirement That Combined Time Interval for Any Three Consecutive Surveillance Intervals Not to Exceed 3.25 Times Specific Surveillance Interval from Tech Spec 1.0.X 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 ML20059J7651990-09-12012 September 1990 Amend 45 to License DPR-21,changing Tech Spec Section 3/4.5.C by Adding Operability & Surveillance Requirements for Mod Made to Tie Breakers 14A to 14G 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 ML20055E4551990-07-0505 July 1990 Corrected Tech Spec Page 3/4 9-1 Re Auxiliary Electrical Sys to License DPR-21 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 1999-06-03
[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 B17766, Application for Amend to License DPR-65,to Return Hydrogen Purge Sys to Former Classification of Being within Scope of Maint Rule Program,But Not as risk-significant Sys1999-09-23023 September 1999 Application for Amend to License DPR-65,to Return Hydrogen Purge Sys to Former Classification of Being within Scope of Maint Rule Program,But Not as risk-significant Sys B17832, Application for Amend to License DPR-65,removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers1999-09-0707 September 1999 Application for Amend to License DPR-65,removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers B17829, Suppl 1 to TS Change Request 1-1-99 for Amend to License DPR-21,revising Proposed Permanently Defueled TS Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-14331999-08-25025 August 1999 Suppl 1 to TS Change Request 1-1-99 for Amend to License DPR-21,revising Proposed Permanently Defueled TS Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 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 B17799, Application for Amend to License NPF-49,incorporating Editorial Revs to TS Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Sections B 3/4.3.2,B 3/4.4.11, B 3/4.6.1.2 & B 3/4.8.41999-08-0505 August 1999 Application for Amend to License NPF-49,incorporating Editorial Revs to TS Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Sections B 3/4.3.2,B 3/4.4.11, B 3/4.6.1.2 & B 3/4.8.4 B17772, Application for Amend to License DPR-65,relocating Selected TS Re Refueling Operations & Associated Bases to Plant TRM1999-07-16016 July 1999 Application for Amend to License DPR-65,relocating Selected TS Re Refueling Operations & Associated Bases to Plant TRM 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 ML20207G6321999-06-0303 June 1999 Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Replacing Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generid Titles B17764, Application for Amend to License NPF-49,deleting Reference to ASME Code Paragraph Iwv 3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger Contained in TS 4.4.6.2.2.e1999-05-17017 May 1999 Application for Amend to License NPF-49,deleting Reference to ASME Code Paragraph Iwv 3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger Contained in TS 4.4.6.2.2.e 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 B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-061999-04-19019 April 1999 Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06 B17737, Mod to 990104 Application for Amend to License DPR-65, Changing Value for Turbine Driven Auxiliary Feedwater Pump Associated with Monthly Surveillance Testing of Various ESF Pump1999-04-0707 April 1999 Mod to 990104 Application for Amend to License DPR-65, Changing Value for Turbine Driven Auxiliary Feedwater Pump Associated with Monthly Surveillance Testing of Various ESF Pump B16997, Application for Amend to License DPR-65,relocating Instrumentation TSs 3.3.3.2,3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 Trm,Per GL 95-101999-03-19019 March 1999 Application for Amend to License DPR-65,relocating Instrumentation TSs 3.3.3.2,3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 Trm,Per GL 95-10 B17343, Application for Amend to License NPF-49,revising TS to Support Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of Ol.Proprietary & non- Proprietary Licensing Repts,Encl.Proprietary Rept Withheld1999-03-19019 March 1999 Application for Amend to License NPF-49,revising TS to Support Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of Ol.Proprietary & non- Proprietary Licensing Repts,Encl.Proprietary Rept Withheld B17658, Application for Amend to License DPR-65,revising TSs 3.5.2, 3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys.Associated Bases Will Be Modified as Necessary to Address Proposed Changes1999-03-17017 March 1999 Application for Amend to License DPR-65,revising TSs 3.5.2, 3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys.Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20207L2581999-03-0505 March 1999 Amend 104 to License DPR-21,changing TSs for Staffing & Training Requirements to Allow Use of Certified Fuel Handlers to Meet Plant Staffing Requirements B17566, Application for Amend to License NPF-49,proposing Amend to TS 3/4.7.4, SW Sys, by Adding AOT for One SW Pump Using Duration More in Line with Significance Associated with Function of Pump1999-03-0202 March 1999 Application for Amend to License NPF-49,proposing Amend to TS 3/4.7.4, SW Sys, by Adding AOT for One SW Pump Using Duration More in Line with Significance Associated with Function of Pump B17669, Suppl to Application for Amend to License DPR-65,revising DG Action Statements & Surveillance Requirements1999-02-11011 February 1999 Suppl to Application for Amend to License DPR-65,revising DG Action Statements & Surveillance Requirements B17590, Application for Amend to License DPR-65,removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys, from Plant TS1999-01-18018 January 1999 Application for Amend to License DPR-65,removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys, from Plant TS B17623, Application for Amend to License DPR-65,changing TS 3.6.1.2, Containment Sys - Containment Leakage1999-01-18018 January 1999 Application for Amend to License DPR-65,changing TS 3.6.1.2, Containment Sys - Containment Leakage B17004, Application for Amend to License NPF-49,revising TS Table 3.7-6, Area Temp Monitoring & Revising FSAR to Describe Full Core off-load Condition as Normal Evolution.Proprietary Rev 2 to HI-971843,encl.Proprietary Info Withheld1999-01-18018 January 1999 Application for Amend to License NPF-49,revising TS Table 3.7-6, Area Temp Monitoring & Revising FSAR to Describe Full Core off-load Condition as Normal Evolution.Proprietary Rev 2 to HI-971843,encl.Proprietary Info Withheld ML20199L0631999-01-18018 January 1999 Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into TS 3/4.2.2, Heat Flux Hot Channel Factor-FQ(Z), 6.9.1.6.a & 6.9.1.6.b, Colr B17517, Application for Amend to License DPR-65,incorporating Changes to ESF Pump Testing Contained in TSs 3.5.2,3.6.2.1, 3.7.1.2,3.7.3.1 & 3.7.4.11999-01-0404 January 1999 Application for Amend to License DPR-65,incorporating Changes to ESF Pump Testing Contained in TSs 3.5.2,3.6.2.1, 3.7.1.2,3.7.3.1 & 3.7.4.1 B17519, Application for Amend to License DPR-65,revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1.Addl TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes,Included1998-12-28028 December 1998 Application for Amend to License DPR-65,revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1.Addl TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes,Included B17542, Application for Amend to License DPR-65,requesting Review & Approval to Plant Fsar,Per 10CFR50.90.Changes to Plant FSAR Pages,Encl1998-12-10010 December 1998 Application for Amend to License DPR-65,requesting Review & Approval to Plant Fsar,Per 10CFR50.90.Changes to Plant FSAR Pages,Encl B17546, Application for Amend to License DPR-21,requesting NRC Approval of Certified Fuel Handler Training & Retraining Program & Request for Exemption from Requirements of 10CFR50.54(m)(2)1998-12-0404 December 1998 Application for Amend to License DPR-21,requesting NRC Approval of Certified Fuel Handler Training & Retraining Program & Request for Exemption from Requirements of 10CFR50.54(m)(2) B17342, Application for Amend to License NPF-49,proposing Rev to TS 4.7.10.e to Eliminate Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred1998-12-0404 December 1998 Application for Amend to License NPF-49,proposing Rev to TS 4.7.10.e to Eliminate Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred B17498, Application for Amend to License DPR-65,revising FSAR Due to Increase in Radiological Consequences Caused by Changes in Assumptions Used in Updated Dose Consequences Analysis of Sgtr.Rvised FSAR Pages Encl1998-11-13013 November 1998 Application for Amend to License DPR-65,revising FSAR Due to Increase in Radiological Consequences Caused by Changes in Assumptions Used in Updated Dose Consequences Analysis of Sgtr.Rvised FSAR Pages Encl B17492, Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H, from Indefinite Period of Time1998-11-10010 November 1998 Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H, from Indefinite Period of Time B16951, Application for Amend to License DPR-65,changing TS 3.3.2.1, Instrumentation - ESFAS Intrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F1998-10-22022 October 1998 Application for Amend to License DPR-65,changing TS 3.3.2.1, Instrumentation - ESFAS Intrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F B17413, Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA1998-09-28028 September 1998 Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA B17417, Application for Amend to License DPR-65,re Separation Requirement in FSAR of Six Inches,Which Is Applied to Redundant Vital Cables,Internal Wiring of Redundant Vital Circuits & Associated Devices1998-09-28028 September 1998 Application for Amend to License DPR-65,re Separation Requirement in FSAR of Six Inches,Which Is Applied to Redundant Vital Cables,Internal Wiring of Redundant Vital Circuits & Associated Devices B17381, Application for Amend to License DPR-65,changing TS Definitions 1.24,1.27,1.31,TSs 3.0.2,4.0.5,3.2.3,3.3.2.1, 3.4.1.1,3.4.11 & Adding TS 3.0.61998-09-0909 September 1998 Application for Amend to License DPR-65,changing TS Definitions 1.24,1.27,1.31,TSs 3.0.2,4.0.5,3.2.3,3.3.2.1, 3.4.1.1,3.4.11 & Adding TS 3.0.6 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 ML20237B2691998-08-12012 August 1998 Application for Amend to License DPR-65,updating List of Documents Describing Analytical Methods Specified in TS 6.9.1.8b.Rev 1 to EMF-98-036,encl ML20236Y4951998-08-0606 August 1998 Application for Amend to License NPF-49,revising TS Surveillance 4.4.5.3.a Re SG Tube Insp Interval B16902, Application for Amend to License DPR-65,changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atomspheric Steam Dump Valves1998-08-0404 August 1998 Application for Amend to License DPR-65,changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atomspheric Steam Dump Valves B17046, Application for Amend to License NPF-49,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling1998-07-30030 July 1998 Application for Amend to License NPF-49,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling B17310, Application for Amend to License DPR-65,changing TS Bases 3/4.9.1,3/4.1.1.1,3/4.7.1.6,3/4.7.7,3/4.5.4 & 3/4.3.3.10 by Resolving Miscellaneous Condition Repts1998-07-30030 July 1998 Application for Amend to License DPR-65,changing TS Bases 3/4.9.1,3/4.1.1.1,3/4.7.1.6,3/4.7.7,3/4.5.4 & 3/4.3.3.10 by Resolving Miscellaneous Condition Repts B17190, Application for Amend to License DPR-65,changing Tech Specs 2.1.1, Safety Limits - Reactor Core, 2.2.1, Limiting Safety Sys Settings - Reactor Trip Setpoints & 3.3.1.1, Instrumentation - Reactor Protective Instrumentation1998-07-21021 July 1998 Application for Amend to License DPR-65,changing Tech Specs 2.1.1, Safety Limits - Reactor Core, 2.2.1, Limiting Safety Sys Settings - Reactor Trip Setpoints & 3.3.1.1, Instrumentation - Reactor Protective Instrumentation B16537, Application for Amend to License DPR-65,modifying DG Testing Requirements by Incorporating Recommendations Contained in GLs 84-15,93-05 & 91-041998-07-17017 July 1998 Application for Amend to License DPR-65,modifying DG Testing Requirements by Incorporating Recommendations Contained in GLs 84-15,93-05 & 91-04 B17280, Application for Amend to License DPR-65,revising Section 9.7.2, Svc Water & Section 9.4 Reactor Bldg Closed Cooling Water, Affected by Change.Attachment 1 Provides Discussion of Proposed Changes1998-07-0202 July 1998 Application for Amend to License DPR-65,revising Section 9.7.2, Svc Water & Section 9.4 Reactor Bldg Closed Cooling Water, Affected by Change.Attachment 1 Provides Discussion of Proposed Changes ML20236K3401998-07-0101 July 1998 Amend 218 to License DPR-65,changing TS by Modifying Low Temp Overpressure Protection Requirements ML20202D1521998-06-30030 June 1998 Amend 193 to License DPR-61,changing Facility Operating License & TS to Reflect Permanently Shutdown & Defueled Status of Plant B17308, Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapter 12 of Millstone Unit 3 FSAR1998-06-10010 June 1998 Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapter 12 of Millstone Unit 3 FSAR B17276, Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapters 6,9 & 15 of Millstone Unit 3 FSAR1998-06-0606 June 1998 Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapters 6,9 & 15 of Millstone Unit 3 FSAR B17288, Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapter 15 of Millstone,Unit 3 FSAR1998-06-0505 June 1998 Application for Amend to License NPF-49,by Incorporating Attached Proposed Rev Into Chapter 15 of Millstone,Unit 3 FSAR 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 1999-09-07
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAMNECKPLANJ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 License No. DPR-61
- 1. The Nuclear Regulatory Comission (the Comission) has -found that:
A. The application- for amendment by Connecticut Yankee Atomic Power Company (thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 Comission; 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 .1111 not be inimical to. the comon 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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- 2. Accordingly, the license is amended by changes to the 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.114 , are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR GULATORY COMMISSION
~
~
oh PF. Stolz, Dir c or Pr ject Directorat I-4 vision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25, 1989 '
I
ATTACHMENT TO LICENSE AMENDMENT NO.ll4 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert '
6-13 6-13 a
e a
f '
i
l
. l, Administrative Controls 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for Reportable Events:
- a. The Commission shall be notified and/or a report submitted )
pursuant to the requirements of Section 50.73 to 10CFR Part 50 i and
^
- b. Each Reportable event shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Operations.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is '
violated.
- a. The unit shall be placed in at least HOT STANDBY within one hour. !
- b. The NRC Operations Center shall be notified by telephone as scon as l possible and in all cases within one hour. The Vice Prestdent '
Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President-Nuclear Operations within 14 days of the violation.
- e. Operation shall not be resumed until authorized by the Commission.
6.8 P_ROCEDVRES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and '
recommendations of Section 5.1 and 5.3 of ANSI N18.7-1976 and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below. I Procedures shall be established and maintained for implementation of the Facility Fire Protection Program. ?
6.8.2 Each proc 2 dure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station
(
Superintendent prior to implementation and periodically as set forth in each document. )
1
! )
l ;
6-13 Amendment No. 114 l
u____._______ _
1, o
o UNITED STATES y g
-y p, NUCLEAR REGULATORY COMMISSION 5 tj WASHINGTON, D. C. 20555
%...**/
NORTHEAST NUCLEAR ENERGY COMPANY 1
DOCKET NO. 50-245 MILLSTONE Nt! CLEAR POWER STATION, UNIT NO. 1 !
AMENDMENT TO FACILITY OPERATING LICENSE _
Amendment No. 30 License No. DPR-21
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. . The application for amendment by Northeast Nuclear inergy Company (thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), and the Comission's rules.and regulations 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 (1) 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 co m on 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.
j
_.__..m_.______.__________m______
- 2. Accredingly, the license is amended by changes to the Technical Spe'ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of. Facility. Operating License No. DPR-21-is.hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 30 , are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance, to be-implemented within 30 days of issuance.
F THE NUCLEAR RE LATORY COMMISSION .c
[
J n F. Stolz. Direc$gr roj ct Directorate E-4 sion of Reactor Projects'I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25, 1989 I
i i
___________.____.__.__________m_.__.___-
ATTACHMENT TO LICENSE AMENDMENT NO.30 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages'as indicated . The revised pages are identified by amendment number and contains a vertical line indicating the areas of. change.
Remove Insert 6-16 6-16 1
)
I 1
l
)
\
l l
I
)
q J
l,
.)
ADMINISTRATIVE CONTROLS
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB, and the Vice President Nuclear Operations within 14 days of the violation.
- e. Operation shall not be resumed until authorized by the Commission.
6.8 PROCEDURES l 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below.
- a. The applicable procedures recommended in Appendix "A" of Regulatory I Guide 1.33, February, 1978.
- b. Refueling operations. I
- c. Surveillance activities of safety related equipment.
- d. Security Plan implementation I
- e. Emergency Plan Implementation
- f. Fire Protection Program Implementation
- g. Quali+y Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974. I
- h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 00CM) implementation, except for Section I.E.,
Radiological Environmental Monitoring.
6.8.2 Each procedure and administrative policy o" 6.8.1 above, and changes thereto, shall be reviewed by che PORC/SORC, as appli- i cable, and approved by the Unit Superintendent / Station Superin- '
tendent prior to implementation and reviewed periodically as set forth in each document.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of original procedure is not altered,
- b. The change is approved by two members of the plant management i staff, at least one of whom holds a Senior Reactor Operator's j License on the unit affected. [
- c. The change is documented, reviewed by the PORC/SORC, as I applicable, and approved by the Unit Superintendent / Station Superintendent within 14 days of implementation. !
1 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 0DCM.
l Millstone Unit 1 6-16 Amendment No, 30 1
I
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'kg UNITED STATES NUCLEAR REGULATORY COMMISSION g .t WASHING TON, D. C. 20555
%...../
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY l DOCKET NO. 50-336 l MILLSTONE NUCLAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE j
. Amendment No.141 j License No. DPR-65 :
- 1. The Nuclear Regulatory Commission (the Commission) has found'that:
A. The application for amendment by Northeast Nuclear Energy Company, etal.(thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l Comission;
. C. There is reasonable assurance (1) 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
I.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.141, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This licenu amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REG LATORY COMMISSION J 'F. Stolz, Dire t r P o ect Directorate -4 ision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25, 1989 I
ATTACHMENT TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE NO. DPR 65 DOCKET NO. 50-336' Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contains a vertical line indicating the areas of change.
Remove Insert 6-16 6-16 n
l
.* j ADMINISTRATIVE CONTROLS .-. .
SAFETY LIMIT VIOLATION (Continued)
- b. The NRC Corporation Center shall se notified by telephone as soon as possible and in all cases within one hour. The Vice President Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Safety Limit Violation Report s1all be prepared. The report shall ;
be reviewed by the PORC. This report shall describe 1) applicable {
circumstances preceding the violation, (2) effects of(the violation j upon facility components, systems or structures, and (3) corrective i action taken to prevent recurrence. !
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice Presdient Nuclear Operations within 14 days of the violations.
- e. Operation shall not be resumed until authorized by the Commission. -I 6.8 PROCEDVRES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
)
- a. The applicable procedures recomm-anded in Appendix "A" of Regulatory Guide 1.33, February, 1978.
- b. Refueling operations.
- c. Surveillance activities of safety related equipment. ,
- d. Security Plan implementation.
- e. Emergency Plan implementation
- f. Fire Protection Program implement ation.
- g. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, Ane 1974.
- h. Radiological Effluent Monitoring _ and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E. Radiological Environmental Monitoring.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC/SORC, as applicable, and approved by the Unit Superintendent / Station Superintendent prior to implementation and l reviewed periodically as set forth in each document.
MILLSTONE - UNIT 2 6-16 Amendment No. 141
.s sa ato m
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g UNITED STATES y g NUCLEAR REGULATORY COMMISSION 5 :l. WASHINGTON, D. C. 20555 ;
\*...+/
NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.*
DOCKET NO. 50-423 i
MILLSTONE NUCLAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE
. Amendment No. 33 License No. NPF-49
- 1. The Nuclear Regulatory Comission (the Comission) has .found that:
A. The application for amendment by Northeast Nuclear Energy Corupany, etal.(thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity vith the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) 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 Commission'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 1 been satisfied.
J
- Northeast Nuclear Energy Company is authorized to act as agent and represent -
ative for the following Owners: Central Maine Power Company, Central Vemont j Public Service Corporation, Chicopee Municipal Lighting Plant, City of ;
Burlington, Vermont, Connecticut Municipal Electric Light Company, l Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, l New England Power Company, The Village of Lyndonville Electric Department, j
( Western Massachusetts Electric Company, and Vemont Electric Generation and "
1 Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
4
- 2. Accordingly, the license is amended by changer to the Technical 1 Specifications as. indicated in the attachment ta this license amendment, and paragraph 2.0.(2) of Facility Operating License'No. NPF-49 is hereby j amended to read as follows. 3 (2) Technical Specifications i The Technical Specifications contained in Appendix A, as revised !
through Amendment No. 33 , are hereby incorporated in the license.
The licensee shall operate the facility' in accordance with the Technical Specifications.
]
- 3. This license amendment is effective as of the date of issuance, to be 1 implemented wit'iin 30 days of issuance.
F R THE NUCLEAR R GULATORY COMMISSION r
~
1 i Jh F. Stolz, Direp:or ro ect Directorate)I-4 ision of Reactor Projects I/II Office of Nuclear Reactor Regulation ]
Attachment:
Changes to the Technical -l Specifications Dcte of Issuance: April 25, 1989 1
j
)
4 ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. NPF-49 I l
DOCKET NO. 50-423 i Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by )
amendment number and contains a vertical line indicating the areas of change. j Remove Insert 6-12 6-12 6-16 6-16 b
i i
i i
i 1
I i1
@MINISTRATIVE CONTR0l.S REVIEW 6.5.3.6 The NRB shall function as an independent review body and shall review:
- a. The safety evaluations for: (1) changes to procedures, equipment, or systems; and (2) tests or experiments completed under the i provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;
- b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; I
- d. Proposed changes in Sections 1.0-5.0 of these Technical Specifications or this Operating License; '
l
- e. Violations of Codes, regulations, orders, Technical ,
Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; l i
- f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety;
- g. All REPORTABLE EVENTS;
- h. Indications of a significant unanticipated deficiency, affecting nuclear safety, in some aspect of design or operation of structures, systems, or components; and
- 1. Reports and meeting minutes of the PORC.
AUDITS 6.5.3.7 Audits of unit activities shall be performed under the cognizance
{
of the NRB. These audits shall encompass:
l i
- a. The conformance of unit operation to provisions contained within i the Technical Specifications and applicable license conditions at l least once per 12 months;
- b. The performance, training, and qualifications of the unit staff at least once per 12 months; .
I
- c. The results of actions taken to correct deficiencies occurring in l unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; and
- d. Any other area of unit operation considered appropriate by the NRB or the Senior Vice President-Nuclear Engineering and Operations.
I MILLSTONE - UNIT 3 6-12 Amendment No. 33
ADMINISTRATIVE CONTROLS i
SAFETY LIMIT VIOLATION (Continuec)
- d. The Safety Limit Violation ' Report shall be. submitted to the Commission, the Chairman of the NRB, .and the. Vice i President-Nuclear Operations within 14 days of the violation;'and '
- e. Operation shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
- a. The applicable procedures recommended in Appendix A' of Regulatory
, Guide 1.33, Revision 2, February 1978;
- b. The applicable procedures required to implement the require-ments of NUREG-0737 and supplements thereto;
- c. Refueling operations;
- d. Surveillance activities of safety related equipment;
- e. Security Plan implementation; l
- f. Emergency Plan implementation; J
- g. Fire Protection Program implementation;
- h. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974; and
- 1. Radiological Effluent Monitoring and. Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E, Radiological- Environmental' Monitoring.
6.8.2 Each procedure of Specification 6.8.1, and changes. thereto, shall be reviewed by the PORC/SORC, as appropriate, and shall be approved by the Unit Superintendent / Station Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro--
vided:
- a. The intent of the original procedure is not altered;. >
- b. The change is approved by two . members of the plant management !
staff, at least one of whom holds a Senior Operator license on. the !
unit affected; and j MILLSTONE - UNIT 3 6-16 Amendment No. 33 .;
4