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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20207G6321999-06-0303 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 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 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 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 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 ML20059H8311993-11-0101 November 1993 Amend 67 to License DPR-21,changing TS 4.7.A.3.d(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 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) 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 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 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 ML20055E4551990-07-0505 July 1990 Corrected Tech Spec Page 3/4 9-1 Re Auxiliary Electrical Sys to License DPR-21 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 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 ML20246F3751989-05-0202 May 1989 Amend 31 to License DPR-21,revising Tech Specs by Clarifying ECCS Availability & Power Supply Requirements & by Deleting Ref to Tech Spec Sections Deleted in Previous Amend 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 ML20245L2271989-04-21021 April 1989 Amend 140 to License DPR-65,incorporating Limiting Conditions for Operation & Surveillance Requirements for Reactor Vessel Coolant Level Instrumentation in Tech Spec 3/4.3.3.8, Accident Monitoring ML20245D2941989-04-14014 April 1989 Amend 29 to License DPR-21,removing cycle-specific Parameter Limits,Decreasing Min Critical Power Ratio from 1.07 to 1.04 & Removing Previous Approval to Initiate Reactor Startup W/ Flow Indication from 1 of 20 Jet Pumps Available ML20236A8081989-03-0808 March 1989 Amend 28 to License DPR-21,revising Tech Specs to Provide Clarifying Info for Determining Required Insp Intervals & Establish Criteria for Snubbers That May Be Exempted from Being Counted as Inoperable 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 ML20207L6991988-10-11011 October 1988 Amend 24 to License DPR-21,reducing MAPLHGR by 2% to Compensate for Potentially Degraded ECCS Flow Due to debris- Induced Strainer Plugging Following LOCA 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 ML20151Y6531988-08-19019 August 1988 Amend 20 to License DPR-21,incorporating Requirements for Halon Sys in Control Room ML20151Z5541988-08-19019 August 1988 Amend 21 to License DPR-21,revising Tech Spec Section 3.7.A.3, Primary Containment by Removing Permission to Perform Open Vessel Criticality & Open Vessel Low Power Physics Testing W/O Containment Integrity ML20207H1891988-08-18018 August 1988 Amend 19 to License DPR-21,changing Expiration Date to 101006 ML20154M8851988-08-18018 August 1988 Corrected Amend 19 to License DPR-21,changing Paragraph 2.D to Paragraph 3 Re Expiration Date of License ML20150A6391988-06-27027 June 1988 Amend 18 to License DPR-21,revising Tech Spec Section 3.5.C, Core & Containment Cooling Sys - Feedwater Coolant Injection Subsys, by Increasing Min Required Condensate Storage Tank Vol to 250,000 Gallons ML20197D6981988-05-26026 May 1988 Amends 17,129 & 19 to Licenses DPR-21,DPR-65 & NPF-49, Respectively,Modifying Paragraph 2.C.(4) of Licenses DPR-21 & DPR-65 & Paragraph 2.E of License NPF-49 to Require Compliance W/Revised Plant Security Plan ML20154N2271988-05-19019 May 1988 Amend 18 to License NPF-49,revising Tech Spec Section 3.4.9.3 to Change Min RCS Vent Area Required for Cold Overpressure Protection from 7.0 to 5.4 Inches & Tech Spec Sections 3.8.1.2,3.8.2.2 & 3.8.3.1 for Consistency ML20150D6041988-03-17017 March 1988 Amend 15 to License DPR-21,deleting Tech Spec Tables 3.6.1.a & 3.6.1.b Re Listing of safety-related Hydraulic & Mechanical Snubbers,Respectively & Makes Changes to Testing & Surveillance Requirements for Snubbers 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 ML20238C8471987-12-17017 December 1987 Amend 13 to License DPR-21,revising Tech Specs to Reflect Removal of Low Reactor Pressure Switches PS-263-54 a & B from ECCS (Core Spray & Low Pressure Coolant Injection) Pump Start Logic ML20235S4291987-09-29029 September 1987 Amend 12 to License DPR-21,revising Tech Specs to Reflect Higher Set Points for Main Steam Line & Steam Tunnel Ventilation Radiation Monitors ML20235G8631987-09-0808 September 1987 Amend 11 to License DPR-21,revising Tech Spec Table 3.7.1, Primary Containment Isolation to Reflect Plant Mods & to Increase Scope of Table to Include Check Valves & Valves Opened During Operation for Testing ML20238A8541987-09-0101 September 1987 Amend 10 to License DPR-21,removing Ref to Switchyard Batteries from Tech Spec Sections 3.9.A.5,4.9.B.2 & 4.9.B 1999-06-03
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARB17766, 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 B16186, Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time1998-05-14014 May 1998 Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time ML20247J1131998-05-0707 May 1998 Application for Amend to License NPF-49,incorporating Attached Proposed Rev Into Chapter 15 of Unit 3 FSAR B17210, Application for Amend to License NPF-49,revising TS 3/4.5.4 Re Refueling Water Storage Tank Min Boron Concentration1998-05-0101 May 1998 Application for Amend to License NPF-49,revising TS 3/4.5.4 Re Refueling Water Storage Tank Min Boron Concentration B17112, Application for Amend to License DPR-65,replacing Two low- Range Pressurizer transmitters,PT-103 & PT-103-1 Which Will Identify That Two low-range Pressurizer Pressure Instrument Channels Are Independent & Redundant Only1998-04-29029 April 1998 Application for Amend to License DPR-65,replacing Two low- Range Pressurizer transmitters,PT-103 & PT-103-1 Which Will Identify That Two low-range Pressurizer Pressure Instrument Channels Are Independent & Redundant Only B17194, Application for Amend to License NPF-49,changing TS Bases Section 3/4.3.3.5 to Add Wording to Clarify Calibration of Intermediate Range Neutron Amps Channel Associated W/Remote Shutdown Instrumentation1998-04-23023 April 1998 Application for Amend to License NPF-49,changing TS Bases Section 3/4.3.3.5 to Add Wording to Clarify Calibration of Intermediate Range Neutron Amps Channel Associated W/Remote Shutdown Instrumentation B17144, Application for Amend to License NPF-49,assuring That PORVs Will Be Capable of Automatic Cycling as Well as Manual Cycling When in TS Action Statements That Allow Indefinite Continued Operation1998-04-14014 April 1998 Application for Amend to License NPF-49,assuring That PORVs Will Be Capable of Automatic Cycling as Well as Manual Cycling When in TS Action Statements That Allow Indefinite Continued Operation ML20216J5141998-04-13013 April 1998 Application for Amend to License DPR-65,adding TS 3.5.5, ECCS - Trisodium Phosphate 1999-09-07
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- - _ _ _ _ - _ _ . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
'o, UNITED STATES
!*- 'i NUCLEAR REGULATORY COMMISSION
- ' v, j WASHINGTON, D. C. 20555 yw .- /
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Ccmmission) has found that:
A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 18, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity 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 witn tne 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.
DI:SIO;iATED ORICINA1.
Certified Bh 1 b ot4 &~r&4 L.-
u 82dI210113 820702 DR ADOCK 05000336 PDR
- 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is ef fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Os Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 2, ]982 O
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ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. OPR-65 1
DOCKET NO. 50-336 i
4 Remove and replace the following pages of the Appendix A Technical Specifi-cations with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding over leaf pages are also provided to maintain document completeness.
Remove Replace 2-2 2-2
! 2-4 2-4 3/4 2-6 3/4 2-6.
3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 3/4 2-14 3/4 2-14 a
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and maxi-mum cold leg coolant temperature shall not exceed the limits shown on Figure 2.1-1.
APPLICABILITY: MODES 1 and 2.
ACTION:
Whenever the point defined by the combination of maximum cold leg temper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.
APPLICABILITY: MODES 1, 2, 3, 4 and 5.
ACTION:
MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
MODES 3, 4 and S Whenever the Reactor Coolant System pressure has exceeded 2750 psia, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.
MILLSTONE - UNIT 2 2-1
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F 1 o 3 - aunivuaanal os, a,oa nonixvn MILLSTONE - UNIT 2 2-2 Amendment No. 7, R,B ,79 m + . == w . e,
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SETPOINTS 2.2.1 The reactor protective instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY: AS SHOWN FOR EACH CHANNEL IN TABLE 3.3-1.
ACTION:
With a reactor protective instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint .
value.
MILLSTONE - UNIT 2 2-3
TABLE 2.2-1 3
E~ REACTOR PROTECTIVE INSTRUMENTATION TRIP SETP0lN1 LIMITS y FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VAI.UES
[ 1. Manual Reactor Trip Not Applicable Not Applicable
- s G 2. Power Level-liigh ru four Reactor Coolant Pumps < 9.6% above TilERMAL POWER, < 9.7% above TilERMAL POWER, with Operating with a minimum setpoint of a minimum of < 14.7% of RATED
< 14.6% of RATED TilERMAL TilERMAL POWER, and a maximum of POWER, and a maximum of 3,106.7% of RATED TilERMAL POWER.
< 106.6% of RATED TilERMAL POWER.
- 3. Reactor Coolant Flow - Low (1) m four Reactor Coolant Po ?s > 91.7% of reactor coolant > 90.1% of reactor coolant flow E Operating flow with 4 pumps operating *. with 4 pumps operating *.
- 4. Reactor Coolant Pump > 830 rpm
> 823 rpm S*_ed - Low
. Pressurizer Pressure - liigh ,
3.2400 psia 3,2408 psia
. 5. C- .ainment Pressure - High 5,4.75 psig 5,5.23 psig R /. Staam Generator Pressure - ~> 500 psia -> 492 psia 2 Low (2) (5)
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= 8. Steam Generator Water > 36.0% Water Level - each > 35.2% Water Level - each steam Level - Low (5) steam generator genera tor h' 9. Local Power Density - liigh (3) Trip setpoint adjusted to not Trip setpoint adjusted to not
- s. exceed the limit lines of exceed the limit lines of
!* Figures 2.2-1 and 2.2-2-(4). Figures 2.2-1 and 2.2-2 (4).
R M
Design Reactor Coolant flow with 4 pumps operating is 362,600 gpm. ~
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- - - a - - a SUO13Vd NOl1V1N3WDnv MILLSTONE - UNIT 2 3/4 2-5 Amendment No. 38. 52, 61 1
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1 POWER DISTRIBUTION LIMITS TOTAL PLANAR RADIAL PEAKING FACTOR - F LIMITING CONDITION FOR OPERATION 3.2.2 The calculated value of F ,definedasFfy=F (1+Tq ), shall be limited to < l.583.
l APPLICABILITY: MODE 1*.
ACTION:
4 WithFfy>l.583,within6hourseither: l
- a. Reduce THERMAL POWER to bring the combination of THERMAL POWER l
andF[j to within the limits of Figure 3.2-3 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6; or I, b. Be in at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4 2.2.2 Ffy shall be calculated by the expression F =F (1+Tq ) and F shall be determined to be within its limit at the follcaing intervals:
xy r
- a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading,
- b. At least once per 31 days of accumulated operation in MODE 1, and
- c. Within four hours if the AZIMUTHAL POWER TILT (T q ) is > 0.02.
See Special Test Exception 3.10.2.
3/4 2-6 Amendment No. 38,42,79 MILLSTONE - UNIT 2
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POWER DISTRIBUTION LIMITS SURVEILLANCE RE0UIREMENTS (Continued) 4.2.2.3 F xy shallbedeterminedeachtjmeacalculationofFfy is required i by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This detenninatica shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.
4.2.2.4 Tq shallbedeterminedeachtimeacalculationofFfy is required i
and the value of Tqused to determine F xy shall be measured value of Tq .
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l MILLSTONE - UNIT 2 3/4 2-7 Amendment No. 38
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. FIGURE 3.2-3 Total Radial Peaking Factor Versus Allowable Fraction of RATED THERMAL POWER rn N
e 4
6 9
POWER DISTRIBUTION LIMITS T
TOTAL INTEGRATED RADI AL PEAKING FACTOR - F, LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of FT , defined as FT y
, pr (1+Tq ), shall be 7
limited to < l.597. l APPLICABILITY: MODE 1*.
ACTION:
With FT7 > l .597, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either: l
- a. Reduce THERMAL POWER to bring the combination of THERMAL POWER and FT7 to within the limits of Figure 3.2-3 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or
- b. Be in at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
T 4.2.3.2 FfshallbecalculatedbytheexpressionFf=F(1+T)andF r q y shall be detennined to be within its limit at the-following intervals:
- a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading , -
- b. At least once per 31 days of accumulated operation in MODE 1, and
- c. Within four hours if the AZIMUTH L POWER TILT (T q
) is > 0.020, T
4.2.3.3 F shall be determined each time a calculation of F is required r 7 by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State I,nsertion Limit for the existing Reactor Coolant Pump Combination.
T 4.2.3.4 T shall be determined each time a calculation of F is required q
and the value of Tq used to detennine Frshall be the measured value of 2-
- See Special Test Exception 3.10.2.
MILLSTONE - UNIT 2 3/4 2-9 .....ent No. 18, ,
3
~. . .- . . . . . . - . - . ., . . . . . . . __ - .-
POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - T q LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL POWER TILTq (T ) shall not exceed 0.02.
APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER *. l ACTION:
- a. With the indicated AZIMUTHAL POWER TILT determined to be > 0.02 but < 0.10, either correct the power tilt within two hours or determine within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per sub-sequent 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, that the TOTAL PLANAR RADIAL PEAKING FACTOR.(F,T y )
and the TOTAL INTEGRATED RADIAL PEAKING FACTORr (F ) are within the limits of Specifications 3.2.2 and 3.2.3.
- b. With the indicated AZIMUTHAL POWER TILT determined to be > 0.10, operation may proceed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the TOTAL T
INTEGRATED RADIAL PEAKING FACTOR (F7 ) and TOTAL PLANAR RADIAL PEAKING FACTOR (Ffy) are within the limits of Specifications 3.2.2 and 3.2.3. Subsequent operation for'the purpose of measurement and to identify the.cause of the tilt is allowable provided the THERMAL POWER level is restricted to < 20% of the
' maximum allowable THERMAL POWER level for the exisBng Reactor Coolant Pump combination.
! SURVEILLANCE REQUIREMENT -
l~
4.2.4.1 The provisions of Specification 4.0.4 are not applicable.
4.2.4.2 The AZIMUTHAL POWER TILT shall be determined to be within the
!- limit by:
- a. Calculating the tilt at least once per 7 days when the Channel High Deviation Alarm is OPERABLE, -
l' l
- See Specia! Test Exception 3.10.2.
l MILLSTONE - UNIT 2 3/4 2-10 Amendment No. g ,52 l-
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l l
l POWER DISTRIBUTION LIMITS DNB MARGIN LIMITING CONDITION FOR OPERATION 3.2.6 The DNB margin shall be preserved by maintaining the cold leg I temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the limits specified in Table 3.2-1 and Figure 3.2-4 APPLICABILITY: MODE 1.
ACTION:
With any of the above parameters exceeding its specified limits, restore the parameter to within its above specified limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to < 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.6 The cold leg temperature, pressurizer pressure, reactor coolant I flow rate, and AXIAL SHAPE INDEX shall be determined to be within the limits of Table 3.2-1 and Figure 3.2-4 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
IIILLSTONE - UNIT 2 3/4 2-13 Amendment tio. 38 i
e TABLE 3.2-1 DNB MARGIN d
LIMITS
/
Four Reactor Coolant Pumps Operating /
Parameter Cold Leg Temperature < 549'F Pressurizer Pressure t 2225 psia
l AXIAL SHAPE INDEX Figure 3.2-4
- Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER j step increase of greater than 10% of RATED THERMAL POWER.
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.4 MILLSTONE - UNIT 2 3/4 2-14 Amendment No. -)$, ji/,79 i .
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