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Results
Other: B12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend, B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor, B12440, Startup Test Rept Cycle 8, ML20207S981, ML20209E851, ML20215K241, ML20215N827
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MONTHYEARB12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend1986-08-29029 August 1986 Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend Project stage: Other ML20209E8511986-08-31031 August 1986 Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation, Large-Break LOCA Evaluation Project stage: Other ML20203N1401986-09-18018 September 1986 Forwards Request for Addl Info to Assist in NRC Review of Util 860829 Submittal Re LOCA Calculations for Facility. Response within 30 Days of Ltr Date Requested Project stage: RAI ML20215N8271986-09-30030 September 1986 Rev 2 to Reload Safety Evaluation,Millstone Nuclear Power Station,Unit 2 Cycle 8 Project stage: Other ML20215K2411986-10-20020 October 1986 Proposed Tech Specs Revising pressure-temp Limits & Max heat-up & cool-down Rates for RCS Project stage: Other B12224, Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid1986-10-20020 October 1986 Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid Project stage: Request B12240, Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid1986-10-24024 October 1986 Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid Project stage: Request B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor1986-10-27027 October 1986 Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor Project stage: Other ML20215N8131986-10-27027 October 1986 Application for Amend to License DPR-65,allowing Reduction in RCS Flow Rate & Reducing Total Integrated Radial Peaking Factor.Forwards Westinghouse Rev 2 to Reload Safety Evaluation Millstone...Unit 2 Cycle 8. Fee Paid Project stage: Request A06096, Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves1986-12-0101 December 1986 Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves Project stage: Request ML20207S9811987-03-16016 March 1987 Forwards Millstone Nuclear Power Station Unit 2 Startup Test Rept Cycle 8. Plant Achieved Criticality on 861214 & Reached 100% Power on 870101 Project stage: Other B12473, Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions1987-03-20020 March 1987 Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions Project stage: Request B12440, Startup Test Rept Cycle 81987-03-31031 March 1987 Startup Test Rept Cycle 8 Project stage: Other 1986-08-31
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
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 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 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 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 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 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 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 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 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 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) 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 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 B17028, Application for Amend to License NPF-49,revising TS 3/4.4.3 by Replacing Pressurizer Max Water Inventory Requirements W/ Pressurizer Level Requirement1998-04-0707 April 1998 Application for Amend to License NPF-49,revising TS 3/4.4.3 by Replacing Pressurizer Max Water Inventory Requirements W/ Pressurizer Level Requirement ML20216C0401998-04-0606 April 1998 Application for Amend to License DPR-65,changing TSs 3.4.4, RCS - Pressurizer, 3.6.1.5, Containment Sys - Air Temp & 3.7.1.5, Plant Sys - Msli Valves. Info Will Be Added to Bases of Associated TSs to Address Proposed Changes B17141, Application for Amend to License NPF-49,incorporating Rev Into Chapters 2,3 & 9 of Fsar,Adding New Sump Pump Subsys to Address Groundwater Inleakage Through Containment Basemat1998-04-0101 April 1998 Application for Amend to License NPF-49,incorporating Rev Into Chapters 2,3 & 9 of Fsar,Adding New Sump Pump Subsys to Address Groundwater Inleakage Through Containment Basemat 1999-09-07
[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
[Table view] |
Text
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NORTHEAST UTILITIES o.nor.i Orrices seio n street. Beriin. connecticut 1 e NrISaNcc-s P.O. BOX 270 cos ace m**a "* HARTFORD, CONNECTICUT 06141-0270 k L J $C,'(([,'g",
, (203) 665-5000 October 24,1986 Docket No. 50-336 B12240 Office of Nuclear Reactor Regulation Attn: Mr. Ashok C. Thadani, Director PWR Project Director #8 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Surveillance Requirements - DNB Margin Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License, DPR-65, by incorporating the attached proposed change into the Technical Specifications of Millstone Unit No. 2.
The proposed change will reduce the frequency of the surveillance requirement (Technical Specification 4.2.6) for determining the reactor coolant flow rate from at least once per twelve (12) hours to at least once per thirty one (31) days.
The current surveillance requirement necessitates that the RCS flow rate be determined by using the steam generator delta P. The flow rate could be determined more accurately using a core power calorimetric calculation. How-ever, a calorimetric calculation can be reliably performed only at power levels well above the minimum power for Mode 1 because variables such as feedwater ,
flow are difficult to hold constant with minimal error at low power levels. Thus, '
there are periods of time in Mode I during which the cuorimetric cannot reliably i
be used. The proposed relaxation in the surveillance frequency will permit the 1 l use of the more accurate calorimetric flow measurement technique.
! The currently employed measurement technique uses the steam generator delta P measurement. This is calibrated once per cycle to the calorimetric flow determined at the beginning of the cycle. The uncertainty associated with the current delta P measurement is, therefore, a combination of the uncertainties I associated with the calorimetric flow determination and the steam generator delta P instrumentation. The delta P uncertainty is a significant contributor to the total.
l 8611070033 861024 01 9'6 406ih 9 ki 0 i PDR ADOCK 05000336 8 I P PDR Q0' I 1
l
There are two (2) reasons why the steam generator delta P measurement introduces a significant uncertainty into the flow measurement. They are as follows:
- 1) The wide range of the instrument. The uncertainty of instrumen-tation is usually represented as a percent of span. For this instrument, the span is about double the design flow rate, resulting in a large measurement uncertainty.
- 2) Delta P is not a direct measure of flow, rather, flow rate is inferred.
The delta P measurement can be related to flow as long as the flow geometry between the measurement taps remains unchanged. If, for example, the flow is reduced due to fouling in the steam generator tubes, then the delta P would increase. This would result in the indicated flow exceeding the actual flow.
The proposed change (Technical Specification page 3/4 2-13; see Attachment 1) would allow the calorimetric flow measurement to be made. This measurement is not affected by changes in RCS flow geometry such as crudding which is the major reason why flow would change during the course of a cycle. Therefore, the calorimetric flow measurement provides greater assurance that the actual flow is consistent with the accident analysis assumptions.
In order to obtain historical information, we monitored the delta P flow rate for the eleven (11) month period of July,1985 to June,1986. A review of the data showed there were no significant flow fluctuations during normal operation. An abnormal flow reduction would likely occur in a short time frame (less than 1 minute). If this event were not severe enough to activate the reactor protection system, the flow reduction 'is more likely to be picked up by changes in parameters other than steam generator delta P (e.g. RCS delta T). In fact, the steam generator delta P may perceive the event as an increase in RCS flow.
Thus, the decrease in RCS flow surveillance frequency will not result in an abnormal decrease in RCS . flow going undetected. In addition, a qualitative assessment of the RCS flow rate would continue to be conducted twice per day since Technical Specification Table 4.3-2 requires a channel check of RCS flow instrumentation (steam generator delta P) once per twelve hours.
NNECO has reviewed the attached proposed changes pursuant to 10CFR50.59 and has determined that they do not constitute an unreviewed safety question.
The probability of occurrence or the consequences of a previously analyzed accident have not been increased and the possibility for a new type of accident has not been created. There will not be an effect on any parameters and/or systems. The change only involves the frequency at which reactor coolant system flow rate is verified to be within the Technical Specification limit. The tests which are proposed to be used to verify RCS flow are currently being performed, so there is no additional testing required. Only the test frequency will change. NNECO has determined that the increased period between tests does not decrease assurance that any credible changes in RCS flow rate will be identified in sufficient time for appropriate corrective action.
NNECO has reviewed the proposed changes,in accordance with 10CFR50.92, and has concluded that they do not involve a significant hazards consideration in that these changes would not:
- 1. Involve a significant increase in the probability or consequences of an an accident previously evaluated. There are no credible RCS flow changes which could be detected by the current surveillance fre-quency and not by the proposed surveillance frequency. The proposed surveillance frequency will ensure that RCS flow is consistent with the accident analysis assumptions with no impact on protective boundaries.
- 2. Create the possibility of a new or different kind of accident from any previously analyzed. Since there are no failure modes associated with the change, there cannot be a new unanalyzed accident.
- 3. Involve a significant reduction in a margin of safety. Only the frequency of performing surveillance testing is proposed to be changed. This will allow for a more accurate flow determination.
The Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (51FR7750, March 6,1986). The changes proposed herein constitute a more accurate method of surveillance, with a decrease in test frequency and do not resemble any of the examples provided.
Using a measureme'nt technique which does not rely on the delta P instrumenta-tion would result in a substantial improvement in the accuracy of a flow measurement. The use of the calorimetric technique involves a reduction in surveillance frequency, but will provide a more accurate, reliable flow measure-ment. The resulting flow measurement has greater reliability due to elimination of sources of error associated with the current surveillance technique. The current margin of error is high due to the steam generator delta P measurement and steam generator crudding, which introduces a non-conservative error. The calorimetric method includes neither of the above mentioned errors, resulting in a more accurate, reliable calculational method. The proposed changes neither result in an increase to the probability or consequences of a previously analyzed accident nor reduce in some way a safety margin.
In summary, NNECO has concluded that the proposed changes do not constitute a l 1
significant hazards consideration for the following reasons:
- 1) Millstone Unit No. 2 has been in commercial operation for over 10 years. Data recorded and reviewed on RCS flow rate demonstrates that the flow rate does not decrease signficantly over an operating cycle. Therefore, RCS flow rate data support the conclusion that the monthly surveillance frequency is adequate. l
- 2) The secondary-side calorimetric method of calculating the RCS flow rate is a more accurate and reliable technique.
- 3) A qualitative assessment of the RCS flow rate would continue to be conducted twice per day since Technical Specification Table 4.3-2 l
l
)
Y requires a channel check once per twelve hours of RCS flow instrumentation.
- 4) Protection against dramatic changes in RCS flow rate is provided by a Reactor Protection System setpoint as listed in Technical Specifi-cation Table 3.3-2.
NNECO recognizes that the proposed change constitutes a substantial reduction in surveillance frequency. However, we believe that this change is both appropri-ate and justified for the above stated reasons.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed revisions and has concurred with above determinations.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of these proposed amendments.
Although the license amendment request proposed herein is not directly related to the refueling outage curren'tly underway, NNECO requests that if approved, the NRC Staff issue the license amendment by December 9,1986, to support startup from the refueling outage. This amendment may be required at that time to address potential steam generator tube plugging and sleeving conducted during the outage, the precise scope of which is unknown at this time.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Eth J. F. Opeka Senior Vice President
'L ByTTC W. Bishop ^
Secretary cc: Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116
STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me R. W. Bishop, who being duly sworn, did state that he is Secretary of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
Notary Publy '
MY COMMISSION EXPIRES MARCH 31,199f
i t
l Docket No. 50-336 1
B12240
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Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specification Surveillance Requirements - DNB Margin i
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s s NORTHEAST UTILITIES coner.i Ome.. . seio.n sire t. Beriin. connecticut 4 CMCW wt ama %4 cow.am-1 *nw v.amw s ucac cc-== P.O. BOX 270
.e w . ra .o.e. co***" HARTFORD. CONNECTICUT 06141-0270 k L J [.Z C."2[,*'*' (203) 66s-s000 October 24,1986 Docket No. 50-336 B12240 Office of Nuclear Reactor Regulation Attn: Mr. Ashok C. Thadani, Director PWR Project Director //8 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Surveillance Requirements - DNB Margin Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License, DPR-65, by incorporating the attached proposed change into the Technical Specifications of Millstone Unit No. 2.
The proposed change will reduce the frequency of the surveillance requirement (Technical Specification 4.2.6) for determining the reactor coolant flow rate from at least once per twelve (12) hours to at least once per thirty one (31) days.
The current surveillance requirement necessitates that the RCS flow rate be determined by using the steam generator delta P. The flow rate could be determined more accurately using a core power calorimetric calculation. How-ever, a calorimetric calculation can be reliably performed only at power levels well above the minimum power for Mode 1 because variables such as feedwater flow are difficult to hold constant with minimal error at low power levels. Thus, there are periods of time in Mode 1 during which the calorimetric cannot reliably be used. The proposed relaxation in the surveillance frequency will permit the use of the more accurate calorimetric flow measurement technique.
The currently employed measurement technique uses the steam generator delta P measurement. This is calibrated once per cycle to the calorimetric flow determined at the beginning of the cycle. The uncertainty associated with the current delta P measurement is, therefore, a combination of the uncertainties associated with the calorimetric flow determination and the steam generator I delta P instrumentation. The delta P uncertainty is a significant contributor to I the total. l l
1
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- There. are two (2) reasons why the steam generator delta P measurement
- introduces a significant uncertainty into the flow measurement. They are as i follows:
- 1) The wide range of the instrument. The . uncertainty of instrumen-tation is usually represented as a percent of span. For this instrument, the span is about double the design ~ flow rate, resulting in a large measurement uncertainty.
- 2) Delta P is'not a direct measure of flow, rather, flow rate is inferred.
- The delta P measurement can be related to flow as long as the flow geometry between the measurement taps remains unchanged. If, for L example, the flow is reduced due to fouling in the steam generator tubes, then the delta P would increase. This would result in the
{ indicated flow exceeding the actual flow.
- The proposed change (Technical Specification page 3/4 2-13; see Attachment 1) -
j would allow the calorimetric flow measurement to be made. This measurement l is not affected by changes in RCS flow geometry such as crudding which is the 1
' major reason why flow would change during the course of a cycle. Therefore, the calorimetric flow measurement provides greater-assurance that the actual flow is consistent with the accident analysis assumptions.
~
In order to obtain historical information, we monitored the delta P flow rate for -
the eleven (11) month period of July,1985 to June,1986. A review of the data showed there were no significant flow fluctuations during normal operation. An 1
abnormal flow reduction would likely occur in a short time frame (less than 1 minute). If this event were not severe enough to activate the reactor protection i system, the flow reduction is more -likely to' be picked up by changes in
! oarameters 'other than steam generator delta P (e.g. RCS delta T). In fact, the j
steam generator delta P may perceive the. event as an increase in RCS flow.
Ti'us, the decrease in RCS flow surveillance frequency will not result in an abrarmal decrease in RCS flow going undetected.~ In addition, a qualitative
^
asseament of the RCS flow rate would continue to be conducted twice per day since Technical Specification Table 4.3-2 requires a channel check ~ of RCS flow instrumentation (steam generator delta P) once per twelve hours.
1 NNECO has reviewed the attached proposed changes pursuant to 10CFR50.59
) and has determined that they. do not constitute an unreviewed safety question.
1 The probability-of occurrence or the consequences of a previously analyzed accident have not been increased and the possibility for a new type of accident i
has not been created. There will not be an effect on any parameters and/or systems. The change only involves the frequency at which reactor coolant
, system flow rate is verified to be within the Technical Specification limit. The j tests which are proposed to be used to verify RCS flow are currently being -
4 performed, so there is no additional testing required. Only the test frequency i will change. NNECO has determined that the increased period between tests t
- does not decrease assurance that any credible changes in RCS flow rate will be j identified in suffi ic ent time for appropriate corrective action.
l I
l l
NNECO has reviewed the proposed changes, in accordance with 10CFR50.92, and has concluded that they do not involve a significant hazards consideration in that these changes would not:
- 1. Involve a significant increase in the probability or consequences of an an accident previously evaluated. There are no credible RCS flow changes which could be detected by the current surveillance fre-quency and not by the proposed surveillance frequency. The proposed surveillance frequency wi!! ensure that RCS flow is consistent with the accident analysis assumptions with no impact on protective boundaries.
- 2. Create the possibility of a new or different kind of accident from any previously analyzed. Since there are no failure modes associated with the change, there cannot be a new unanalyzed accident.
- 3. Involve a significant reduction in a margin of safety. Only the frequency of performing surveillance testing is proposed to be changed. This will allow for a more accurate flow determination.
The Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (51FR7750, March 6,1986). The changes proposed herein constitute a more accurate method of surveillance, with a decrease in test frequency and do not resemble any of the examples provided.
Using a measurement technique which does not rely on the delta P instrumenta-tion would result in a substantial improvement in the accuracy of a flow measurement. The use of the calorimetric technique involves a reduction in surveillance frequency, but will provide a more accurate, reliable flow measure-ment. The resulting flow measurement has greater reliability due to elimination of sources of error associated with the current surveillance technique. The current margin of error is high due to the steam generator delta P measurement and steam generator crudding, which introduces a non-conservative error. The calorimetric method includes neither of the above mentioned errors, resulting in a more accurate, reliable calculational method. The proposed changes neither result in an increase to the probability or consequences of a previously analyzed accident nor reduce in some way a safety margin.
In summary, NNECO has concluded that the proposed changes do not constitute a j significant hazards consideration for the following reasons: l
- 1) Millstone Unit No. 2 has been in commercial operation for over 10 years. Data recorded and reviewed on RCS flow rate demonstrates that the flow rate does not decrease signficantly over an operating cycle. Therefore, RCS flow rate data support the conclusion that the monthly surveillance frequency is adequate.
1
- 2) The secondary-side calorimetric method of calculating the RCS flow rate is a more accurate and reliable technique.
- 3) A qualitative assessment of the RCS flow rate would continue to be conducted twice per day since Technical Specification Table 4.3-2
__ ~ .
requires a channel check once per twelve hours of RCS flow instrumentation.
- 4) Protection against dramatic changes in RCS flow rate is provided by a Reactor Protection System setpoint as listed in Technical Specifi-cation Table 3.3-2.
NNECO recognizes that the proposed change constitutes a substantial reduction in surveillance frequency. However, we believe that this change is both appropri-ate and justified for the above stated reasons.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed revisions and has concurred with above determinations.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of these proposed amendments.
Although the license amendment request proposed herein is not directly related to the refueling outage currently underway, NNECO requests that if approved, the NRC Staff issue the license amendment by December 9,1986, to support j startup from the refueling outage. This amendment may be required at that time to address potential steam generator tube plugging and sleeving conducted during the outage, the precise scope of which is unknown at this time.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY PcrA J. F. Opeka Senior Vice President s
W (2 By: lt. W. Bishop Secretary cc: Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116
STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me R. W. Bishop, who being duly sworn, did state that he is Secretary of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
Notary Publig MY COMMISSION EXFIRES MARCH 31,1991 l
I
NORTHEAST UTILITIES o.nero Onic.. . seio.n street. seriin. connect cut 1 .w. mi.xw s uc'ac cow. P.O. BOX 270 wo e a*sa *o.ra cev*** HARTFORD, CONNECTICUT 06141-0270 L L J [.*,,,",'s, ((.' "$' '5~, (203) 665-5000 October 24,1986 Docket No. 50-336 B12240 Office of Nuclear Reactor Regulation Attn: Mr. Ashok C. Thadani, Director PWR Project Ditector #8 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Surveillance Recuirements - DNB Margin Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License, DPR-65, by incorporating the attached proposed change into the Technical Specifications of Millstone Unit No. 2.
The proposed change will reduce the frequency of the surveillance requirement (Technical Specification 4.2.6) for determining the reactor coolant flow rate from at least once per twelve (12) hours to at least once per thirty one (31) days.
The current surveillance requirement necessitates that the RCS flow rate be determined by using the steam generator delta P. The flow rate could be determined more accurately using a core power calorimetric calculation. How-ever, a calorimetric calculation can be reliably performed only at power levels well above the minimum power for Mode 1 because variables such as feedwater flow are difficult to hold constant with minimal error at low power levels. Thus, there are periods of time in Mode 1 during which the calorimetric cannot reliably be used. The proposed relaxation in the surveillance frequency will permit the use of the more accurate calorimetric flow measurement technique.
The currently employed measurement technique uses the steam generator delta P measurement. This is calibrated once per cycle to the calorimetric flow determined at the beginning of the cycle. The uncertainty associated with the current delta P measurernent is, therefore, a combination of the uncertainties associated with the calorimetric flow determination and the steam generator delta P instrumentation. The delta P uncertainty is a significant contributor to the total, y g # /W //2o
- mv / v7 ,v
2
? -
1
]
j There, are two (2) reasons why the steam generator delta P measurement introduces a significant uncertainty into the flow measurement. They are as follows:
- 1) The wide range of the instrument. The uncertainty of instrumen- '
tation is usually represented as a percent of span. For this -
2 instrument, the span is about double the design flow rate, resulting in a large measurement uncertainty.
4
- 2) Delta P is not a direct measure of flow, rather, flow rate is inferred.
1 The delta P measurement can be related to flow as long as the flow geometry between. the measurement taps remains unchanged. If, for j example, the flow is reduced due to fouling in the steam generator j tubes, then the delta P would increase. This would result in the indicated flow exceeding the actual flow.
The proposed change (Technical Specification page 3/4 2-13; see Attachment 1) would allow the calorimetric flow measurement to be made. This measurement
- is not affected by changes in RCS flow geometry such as crudding which is the
, major reason why flow would change during the course of a cycle. Therefore, i the calorimetric flow measurement provides greater assurance that the actual
- flow is consistent with the accident analysis assumptions.
In order to obtain historical information, we monitored the delta P flow rate for f
the eleven (11) month period of July,1985 to June,1986. A review of the data showed there were no significant flow fluctuations during normal operation. An
- abnormal flow reduction would likely occur in a short time frame (less than 1
- minute). If this event were not severe enough to activate the reactor protection system, the flow reduction is more likely to be picked up by changes in parameters other than steam generator delta P (e.g. RCS delta T). In fact, the i
steam generator delta P may perceive the event as an increase in RCS flow.
l Thus, the decrease in RCS flow surveillance. frequency will not result in an abnormal decrease in RCS flow going undetected. In addition, a qualitative assessment of the RCS flow rate would continue to be conducted twice per day i~ since Technical Specification Table 4.3-2 requires a channel check of RCS flow instrumentation (steam generator delta P) once per twelve hours.
- NNECO has reviewed the attached proposed changes pursuant to 10CFR50.59 i and has determined that they do not constitute an unreviewed safety question.
l The probability of occurrence or the consequences of a previously analyzed' i accident have not been increased and the possibility for a new type of accident j has not been created. There will not be an effect on any parameters and/or-
- systems. The change only involves the frequency at which reactor coolant i
system flow rate is verified to be within the Technical Specification limit. The tests which are proposed to be used to verify RCS flow are currently being performed, so there is no additional testing required. Only the test frequency will change. NNECO has determined that the increased period between tests j does not decrease assurance that any credible changes in RCS flow rate will be 1 identified in sufficient time for appropriate corre ctive action.
'.,. --__.,---..._---_..---_..-----__._-m-_._. -
- - - - ~ . _ . .
iI l
! NNECO has reviewed the proposed changes,in accordance with 10CFR50.92,tand ,
, has concluded that they do not involve a significant hazards consideration in that
, these changes would not:
+
1 l 1. Involve a significant increase in the probability or consequences of an -
an accident previously evaluated. There are no credible RCS flow 3
changes which could be detected by the current surveillance fre-l quency and not by the proposed surveillance frequency. The proposed ,
j surveillance frequency will ensure that RCS flow is consistent with the. accident analysis assumptions with no impact on protective i boundaries.
j 2. Create the possibility of a new or different kind of accident from any j previously analyzed. Since there are no failure modes associated i with the change, there cannot be a new unanalyzed accident.
- 3. Involve a significant reduction in a margin of safety. Only the 2
frequency of performing surveillance testing .is proposed to be '
changed. This will allow for a more accurate flow determination.
- The Commission has provided' guidance concerning the application of standards in 10CFR50.92 by providing certain examples (51FR7750, March 6,1986). The i changes proposed herein constitute a more accurate method of surveillance, with l a decrease in test frequency and do not resemble any of the examples provided.
!- Using a measurement technique which does not rely on the delta P instrumenta-j tion would result in' a substantial improvement in the accuracy of a flow _
- measurement. The use of the calorimetric technique involves a reduction in i surveillance frequency, but will provide a more accurate, reliable flow measure-
! ment. The resulting flow measurement has greater reliability due to elimination of sources of error associated with the current surveillance technique. The~ ;
current margin of error is high due to the steam generator delta P measurement
- and steam generator crudding, which introduces a non-conservative error. The i calorimetric method includes neither of the above mentioned errors, resulting in ,
- a more accurate, reliable calculational method. The proposed changes neither l l . result in an increase to the probability or consequences of .a previously analyzed !
l accident nor reduce in some way a safety margin. .
l j In summary, NNECO has concluded that the proposed changes do not constitute a !!
4 significant hazards consideration for the following reasons: \
- 1) Millstone Unit No. 2 has been in commercial operation for over 10 i years. Data recorded and reviewed on RCS flow rate demonstrates i that the flow rate does not decrease signficantly over an operating i cycle. Therefore, RCS flow rate data support the conclusion that the i
- monthly surveillance frequency is adequate.
t
- 2) The secondary-side calorimetric method of calculating the RCS flow rate is a'more accurate and reliable technique. ,
! 3) ' A qualitative assessment of the RCS flow rate would continue to be l
) conducted twice per' day since Technical Specification Table 4.3-2 1
i I
i- i f
requires a channel check once per twelve hours of RCS flow instrumentation.
- 4) Protection against dramatic changes in RCS flow rate is provided by
} a Reactor Protection System setpoint as listed in Technical Specifi-cation Table 3.3-2.
NNECO recognizes that the proposed change constitutes a substantial reduction in surveillance frequency. However, we believe that this change is both appropri-ate and justified for the above stated reasons.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed revisions and has concurred with above determinations.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of these proposed amendments.
Although the license amendment request proposed herein is not directly related to the refueling outage curren'tly underway, NNECO requests that if approved, the NRC Staff issue the license amendment by December 9,1986, to support startup from the refueling outage. This amendment may be required at that time to address potential steam generator tube plugging and sleeving conducted during the outage, the precise scope of which is unknown at this time.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY bEAA J. F. Opeka Senior Vice President l
l By: R. W. Bishop Secretary I cc: Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116
= . . .
v STATE OF CONNECTICUT )
. ) ss. Berlin
! COUNTY OF HARTFORD )
~
Then personally appeared before me R. W. Bishop, who being duly sworn, did state that he is Secretary of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the
- name and on behalf of the Licensees herein and that the statements contained in
] said information are true and correct to the best of his knowledge and belief.
j -
Notary Pubig '
i MY COMMISSION EXPIRES MARCH 31,1991 1
i i
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