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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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Northeet Nuclear Energy Company y
P.O. Ibx 128 Waterford. CT 06385-0128 (860) 447-1791
- Fax (860) 444 4277 l i The Norther v Utiltics System 3
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- Docket No. 50-336 B16344 Re 10CFR50.90 l l
U. S. Nuclear Regulatory Commission
. Attention: Document Control Desk j
, Washington, DC 20555 l
}
Millstone Nuclear Power Station, Unit No. 2 I
Proposed Revision to Technical Specifications l 4
Enclosure Buildina f
5 Pursuant to 10CFR50.90, Northeast Nuclear. Energy Company (NNECO) hereby i proposes to amend its Operating License, DPR-65, by incorporating the attached ;
i proposed changes into the Millstone Unit No.2 Technical Specifications. The proposed changes relocate the Surveillance Requirement for attaining a negative pressure in the Enclosure Building (4.6.5.1.d.3 ) from Technical Specification 3.6.5.1,
" Enclosure Building Filtration System," to Technical Specification 3.6.5.2, " Enclosure Building integrity" (4.6.5.2.2). Surveillance Requirement 4.6.5.2 is being renumbered l as 4.6.5.2.1 and is being modified to require each Enclosure Building access opening to be closed, instead of requiring each door in each Enclosure Building access opening to be closed. Technical Specification 3.6.5.2 is also being modified to include i
Enclosure Building Operability, in addition to Enclosure Building integrity. Definition i L 1.25, " Enclosure Building integrity" is being deleted and included in the Bases for j.
Section 3.6.5.2, " Enclosure Building." l Editorial changes are being made to Technical Specifications 3.6.5.1, 3.6.5.2, and 3.9.15 to standardize the terminology used. Additional information is being added, and ,
- modifications made, to the Bases of the Technical Specifications affected by this !
proposed change.
i Attachment 1 provides a discussion of the proposed changes. Attachment 2 provides ;
.the Significant Hazards Consideration. Attachment 3 provides the marked-up version .
of the_ appropriate pages of the current Technical Specifications. Attachment 4 s- provides the retyped pages of the Technical Specifications. j l
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v-U.S. Nuclear Regulatory Commission
. B16344/Page 2 Environmental Considerations NNECO has reviewed the proposed license amendment request against the criteria of 10CFR51.22 for environmental considerations. The proposed changes relocate the
, surveillance requirement for attaining a negative pressure in the Enclosure Building and moddy the requirement for Enclosure Building access openings such that each Enclosure Building access opening is required to be closed, instead of requiring each i door in each Enclosure Building access opening to be closed These changes do not significantly increase the type and amounts of emuents that may be released off site. In addition, this amendment request will not significantly increase individual or cumulative occupational radiation exposures. Therefore, NNECO has determined the proposed changes will not have a significant effect on the quality of the human environment.
1 Conclusions The proposed changes were evaluated utilizing the criteria of 10CFR50.59, and were
! determined not to involve an unreviewed safety question. Additionally, we have concluded that the proposed changes are safe.
4 The proposed changes do not involve a significant impact on public hesith and safety l (see the Safety Assessment provided in Attachment 1) and do not involve a Significant
! Hazards Consideration pursuant to the provisions of 10CFR50.92 (see the Significant Hazards Consideration provided in Attachment 2).
Plant Operations Review Committee and Nuclear Safety Assessment Board i The Plant Operations Review Committee and Nuclear S.Jety Assessment Board have
, reviewed and concurred with the determinations.
Schedule 4
We request issuance at your earliest convenience, with the amendment to be implemented within 30 days of issuance.
State Notification
, i i in accordance with 10CFR50.91(b), a copy of this license amendment request is being j provided to the State of Connecticut. )
1
__ __ . _. _ I
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l U.S. Nuclear Regulatory Commission B16344/Page 3 If you should have any questions on the above, please contact Mr. Ravi Joshi at (860) 440-2080.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY MLas M. L. Bowling (/
Millstone Unit No. 2 Recovery Officer Subscribed and sworn to before me l this /d day of O, 1997
' L Q. 9 7M G Date Commission expires g l Attachments (4) W commission Expires March 31,2002 cc: H. J. Miller , Region i Administrator D. G. Mcdonald, Jr., NRC Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, PhD, Director, Special Projects W. D. Lanning, Director, Millstone Assessment Team Mr. Kevin T. A. McCarthy, Director, Monitoring and Radiation Division, Depsttment of Environmental Protection l
-, j s
i Docket No 50-336 B16344 ,
1 .
Attachment 1
- Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Enclosure Building Discussion of Proposed Changes !
i i
4 April 1997 l
l j
0
~
U.S. Nuclear Regulatory Commission 816344/ Attachment 1/Page 1 i .
I l Proposed Revision to Technical Specifications Enclosure Building Discussion of Proposed Changes introduction 4 Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License, DPR 65, by incorporating the attached i proposed changes into the Millstone Unit No.2 Technical Specifications. The proposed changes relocate the Surveillance Requirement for attaining a negative ;
pressure in the Enclosure Building (4.6.5.1.d.3 ) from Technical Specification 3.6.5.1, !
l " Enclosure Building Filtration System," to Technical Specification 3.6.5.2, " Enclosure Building integrity" (4.6.5.2.2). Surveillance Requirement 4.6.5.2 is being renumbered as 4.6.5.2.1 and is being modified to require each Enclosure Building access opening 2
to be closed, instead of requiring each door in each Enclosure Building access opening :
l j
to be closed. Technical Specification 3.6.5.2 is also being modified to include Enclosure Building Operability, in addition to Ene!osure Building Integrity. Definition 4
1.25, " Enclosure Building Integrity" is being ddeted and included in the Bases for
- Section 3.6.5.2, " Enclosure Building."
i In addition, editorial changes are being made to Technical Specifications 3.6.5.1,
. 3.6.5.2, and 3.9.15 to standardize the terminology used. ,
Backaround
- The Enclosure Building is a limited leakage steel framed structure that completely surrounds the Containment. It is designed and constructed to ensure that an i
acceptable upper limit of leakage of radioactive materials to the environment would not i be exceeded in the unlikely event of a loss of coolant accident (LOCA).
The Enclosure Building Filtration Region (EBFR) includes the region between the Containment and the Enclosure Building, the penetration rooms and the engineered safety feature equipment rooms. In the unlikely event of a LOCA, the EBFR is maintained at a slightly negative pressure by the Enclosure Building Filtration System i (EBFS). Air in the EBFR would be processed through charcoal and HEPA filters and released through the 375 foot Unit 1 stack during a LOCA.
For the EBFA to be able to maintain the EBFR at a slightly negative pressure following a LOCA, the integrity of the Enclosure Building boundary must be maintained. If the integrity of the Enclosure Building boundary, above and beyond normal everyday l personnel passage through the doorways, is not maintained, entry into the Action Statement of Limiting Condition for Operation (LCO) 3.6.5.2 is required. This Action w .~r - . . . - . . . ,
_ _ . ~ _ _ _ _ _ . . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ .
U.S. Nuclear Regulatory Commission
~
816344/ Attachment 1/Page 2 t Statement requires operability of the Enclosure Building boundary be restored within i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the plant is to be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
l NNECO has determined that if the integrity of the Enclosure Building boundary is not
- maintained, this could reduce the effectiveness of the EBFS enough, such that the
~
draw down of the Enclosure Building to a negative pressure of 0.25 inch water gauge j within 60 seconds would not be possible. The 18-month surveillance test (4.6.5.1.d.3)
! raquired for operability of the system in accordance with Technical Specification 3.6.5.1 L would probably not be successful if performed concurrent with the existence of a ;
significant deterioration in the integrity of the Enclosure Building boundary. However,
- the system would still be effective in reducing the it,veis of radionuclides released to the outside environment due to a negative pressure inside the building.
3 Thus, while the plant would have entered into the Action Statement of LCO 3.6.5.2 (i.e.,
- 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action Statement) if there was a loss of Enclosure Building boundary integrity (i.e., above and beyond the normal everyday personnel passage through doorways),
j this situation has recently been identified to create a conflict relative to meeting the
! EBFS operability requirements. Specifically,.the ability to establish and maintain a negative pressure of 0.25 inch water gauge would be reduced. Therefore, the
- requirements of the EBFS Technical Specification (LCO 3.6.5.1) may not be met. LCO 3.6.5.1, as currently written, does not address this situation (both EBFS trains inoperable). This would result in an entry into Technical Spe .ification 3.0.3, requiring a i plant shutdown for a loss of Enclosure Building boundary integrity of sufficient
! magnitude to affect the ability of the EBFS to draw down the Enclosure Building. This j situation has been recognized by the industry (i.e., cascading effect of technical specifications that requires entering additional action statements for supported systems or other systems that are also affected) and the correction to this is reflected in the i new, improved Standard Technical Specifications for Combustion Engineering plants .
! (NUREG-1432 LCOs 3.6.11 and 3.6.13). Specifically, NUREG-1432 has removed the
, draw down requirement (i.e., surveillance requirement for attaining a negative pressure
- in the Enclosure Building) from the filtration technical specification (MP2 Technical l Specification 3.6.5.1) and relocated this surveillance requirement to the building
[ technical specification (MP2 Technical Specification 3.6.5.2). This change recognizes the direct impact of boundary integrity on draw down capability. NNECO has ,
j determined that the Millstone Unit No. 2 Technical Specifications need to be modified to resolve this conflict between Specifications 3.6.5.1 and 3.6.5.2 and, therefore, .
. NNECO is proposing changes to the Millstone Unit No.2 Technical Specifications, 3.6.5.1 and 3.6.5.2, and the corresponding bases.
Also, Surveillance Requirement 4.6.5.2.1 and Bases 3/4.6.5.1 have been clarified to indicate that when double doors (two doors in series) are used in the Enclosure Building boundary, only one door is required to be closed and iatched, except for ;
normal passage. Single doors are required to be closed and latched except for normal passage. Millstone Unit No. 2 incorporates a double door design for some of the Enclosure Building access openings to minimize the pMtial for unfiltered referes.
U.S. Nucioar Regulatory Commission l B16344/ Attachment 1/Page 3 This design redundancy is not credited in the radiological dose calculations for any
- design basis accident. Therefore, it is acceptable to have only one of the double doors operable without entering the action statement. When only one door of a double door design is operable, it must be capable of automatically closing and latching to ensure
, boundary integrity at all timesM.
- Desian Basis and Licensina Basis i
The containment for Millstone Unit No. 2 consists of a primary containment structure and an Enclosure Building that encloses the primary containment. An Enclosure l Building Filtration System (EBFS) is provided for the annulus formed by these two 1 structures. The EBFS consists of two independent and redundant subsystems or trains. Each train consists of an exhaust fan, an electric heater, and a filter unit. Each filter unit contains profilters, High Efficiency Particulate Air (HEPA) filters, and charcoal filters. The EBFS will collect and filter radioactive airborne fission products that may leak from the primary containment to the annulus following the postulated loss of coolant accident (LOCA).
In the event of a LOCA, the EBFS will be actuated by an Enclosure Building Filtration Actuation Signal (EBFAS) based on high containment pressure or low pressurizer
- pressure. The EBFS will function to exhaust sufficient air from the annulus to achieve a -
! negative pressure of 0.25 inches water gauge within one minute following an EBFAS.
- . Only one EBFS train is necessary to establish this negative pressure.
The EBFS can be powered by the emergency diesel generators. If a loss of normal power occurs concurrently with the LOCA, the emergency diesel generators will supply power to EBFS equipment. To account for the time required for the emergency diesel
< generstors to start, come up to speed and voltage, and then sequence on loads, the safety analysis assumes the release of radioactivity from the primary containment structure continues for 110 seconds. After 110 seconds the uncontrolled release of radioactivity to the environment stops, because of the negative pressure established in
- the Enclosure Building by the EBFS.
The Enclosure Building contains numerous access openings. These access opening contain either single or dowle doors. Integrity of the Enclosure Building is maintained by ensuring that at least one door in each access openings is operable and closed, except during normal passage.
Descriotion of Proposed Chances The Enclosure Building draw down requirement is presently located in Specification 3.6.5.1 " Enclosure Buil ding Filtration System." Specifically, Surveillance Requirement (1) R. W. Reid (NRC) letter to W. G. Counsil dated December 8,1978.
4 U.S. Nuclear Regulatory Commission
+ B16344/ Attachment 1/Page 4 4.6.5.1.d.3 verifies that an EBFS train will produce a negative pressure of 0.25 inch water gauge within 60 seconds after a start signal. NNECO is proposing to relocate j this surveillance requirement to the Enclosure Building Technical Specification 3.6.5.2
- as Surveillance Requirement 4.6.5.2.2. l i .
1 Also, Surveillance Requirement 4.6.5.2.1 and Bases 3/4.6.5.1 have been clarified to j j indicate that when double doors are used in the Enclosure Building boundary, only one J door is required to be closed and latched, except for normal passage. Single doors are i required to be closed and latched except for normal passage.
1 This submittal provides the license amendment request which, if granted by the NRC, .
will recognize the direct impact of boundary integrity on the draw down capability and l will decouple Technical Specification 3.6.5.1 from Technical Specification 3.6.5.2. The i changes proposed by NNECO to modify the Millstone Unit No. 2 Technical i Specifications are described be!ow.
- 1. Enclosure Building Integrity will be deleted on Index Page ll and the word
" Integrity" will be removed from " Enclosure Building Integrity" on index Page Vll.
These changes are editorial to agree with the proposed changes described below.
- 2. Definition 1.25, " ENCLOSURE BUILDING INTEGRITY" will be deleted. The i
information related to this term will be relocated to the Bases for Technical Specification 3.6.5.2. This change decouples Technical Specification 3.6.5.2 from Technical Specification 3.6.5.1 such that a problem with the Enclosure Building Filtration System (LCO 3.6.5.1) will not require entry into the Enclosure Building Technical Specification (LCO 3.6.5.2).
- 3. The Enclosure Building Filtration System is composed of two trains. Currently,
- Technical Specification 3.6.5.1 uses " system (s)" and " train (s)" interchangeably.
! To avoid any possible confusion, " system (s)" will be replaced with " train (s),"
! where appropriate.
- 4. For consistency between the specifications contained in this submittal, the first letter of each word in either Enclosure Building Filtration System or Enclosure l Building Filtration Train (s) will be capitalized.
- 5. Surveillance Requirement 4.6.5.1.d.3 will be relocated to Technical Specification 3.6.5.2 as Surveillance Requirement 4.6.5.2.2. This change recognizes the direct impact of boundary integrity on draw down capability and decouples
, Technical Specification 3.6.5.1 from Technical Specification 3.6.5.2. Therefore,
! a loss of Enclosure Building boundary integrity (LCO 3.6.5.2) will not require entry into the Enclosure Building Filtration System Technical Specification (LCO 3 3.6.5.1 ).
1 1
U.S. Nuclear Regulatory Commission B16344/ Attachment 1/Page 5 4 ..
- 6. The word "lNTEGRITY" will be removed from the title of Technical Specification j 3.6.5.2. LCO 3.6.5.2 will be revised to address operability of the Enclosure
~ Building, instead of just integrity. These changes address the delebon of the -
Enclosure Building integrity definition and the addition of Surveillance Requirement 4.6.5.2.2.
1
- 7. Surveillance Requirement 4.6.5.2 will be renumbered as 4.6.5.2.1 and revised to l l address operability of the Enclosure Building, instead of just integrity..This j 4 change addresses the deletion of the Enclosure Building integrity definition and i
the addition of Surveillance Requirement 4.6.5.2.2.
! 8. The words "each door in" will be removed from Surveillance Requirement 4.6.5.2.1. Some Enclosure Building access openings contain a double door 1
arrangement. To satisfy this surveillance requirement, it is only necessary for one of the two doors to be closed.
- 9. Surveillance Requirement 4.6.5.2.2 will be added to Technical Specification 4 3.6.5.2 as discussed above.
1
- 10. The Enclosure Building Filtration System is composed of two trains. Currently, Technical Specification 3.9.15 uses " system" and " train" interchangeably. To avoid any possible confusion, " system" will be replaced with " train," where appropriate.
l i ,
- 11. The words " spent fuel storage pool ventilation system" in the action statement for !
Technical Specification 3.9.15 will be replaced with " Enclosure Building Filtration
. Train" since this is the correct terminology for the equipment used to satisfy LCO 3.9.15. ,
- 12. The Bases for Technical Specifications 3.6.5.1, 3.6.5.2, ard 3.9.15 have been modified to reflect the changes described above and additional information has been added to clarify the laboratory testing requirement for the charcoal sample".
The mark-up of the existing technical specifications is contained in Attachment 3. The retype of the proposed changes to the technical specifications is contained in Attachment 4 and reflect the currently issued version of the Millstone Unit 2 Technical Specifications.
1 (2) G.S. Vissing (NRC) letter to J.F. Opeka dated May 23,1994. ]
l l
U.S. Nuclear Regul tory Commission B16344/ Attachment 1/Page 6 ,
l Safety Assessment l 1
i As currently written, the Action Statement for Technical Specification 3.6.5.2 requires that in the event the Enclosure Building boundary operability is not maintained, operability must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If there was a loss of Enclosure Building l
) boundary integrity (normal everyday personnel passage through doorways does not constitute a loss of Enclosure Building boundary integrity), the plant would have ;
historically entered the Action Statement for LCO 3.6.5.2 (and not entered the Action Statement for LCO 3.6.5.1). However, with a change in the interpretation of technical specifications, the plant should enter additional Action Statements for supported systems or other systems (e.g., Enclosure Building Filtration System [EBFS)) that are j also affected. The new interpretation for the entry into the Action Statement of the EBFS Technical Specification 3.6.5.1, in conjunction with an entry in the Action Statement for LCO 3.6.5.2, would result in an entry into Technical Specification 3.0.3, requiring a plant shutdown.
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, The proposed changes to Technical Specifications 3.6.5.1 and 3.6.5.2, relocation of Surveillance Requirement 4.6.5.1.d.3 to Specification 3.6.5.2, changes to Bases i Sections 3.6.5.1 and 3.6.5.2 and deletion of Definition 1.25 will resolve this conflict
' between Specifications 3.6.5.1 and 3.6.5.2. Specifically, the requirement to establish and maintain a negative pressure of 0.25 inch water gauge in Specification 3.6.5.1 4
belongs to Specification 3.6.5.2. In the event Enclosure Building operability is not maintained in Modes 1-4, the Action Statement for LCO 3.6.5.2 requires that Enclosure
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i Building operability must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours is a reasonable completion time considering the limited leakage design of containment and the low probability of a design basis accident (DBA) occurring during this time period.
Therefore, it is considered that there exists no loss of safety function. This situation was recognized and has been rectified in the new, improved Standard Technical j Specifications for Combustion Engineering plants (NUREG-1432). The proposed changes to Specifications 3.6.5.1 and 3.6.5.2, and corresponding Bases sections do i not modify the LCO or surveillance acceptance criterion, nor do they change the j frequency of the surveillance. The proposed changes do not involve any physical changes to the plant and do not alter the way any structure, system, or component functions.
Surveillancs Requirement 4.6.5.2.1 and Bases 3.6.5.1 have been clarified to indicate that when dcuble doors are used in the Enclosure Building boundary, only one door is required to b9 closed and latched, except for normal passage. Single doors are required to be closed and latched except for normal passage. Millstone Unit No. 2 i incorporates a double door design for some of the Enclosure Building access openings to minimize the potential for unfiltered releases. This design redundancy is not credited in the radiological dose calculations for any design basis accident. Therefore, it is acceptable to have only one of the double doors operable without entering the i !
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l U.S. Nuclear Regulatory Commission B16344/ Attachment 1/Page 7 action statement. When only one door of a dual door design is operable, it must be capable of automatically closing and latching to ensure boundary integrity at all times".
The proposed changes do not have any adverse impact on the design basis accidents previously . analyzed. The proposed changes resolve conflicts between two specifications,, namely 3.6.5.1 and 3.6.5.2. Therefore, the proposed changes do not -
pose a condition adverse to safety.
W (3) R. W. Reid (WRC) letter to W. G. Counsil dated December 8,1978.
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Docket No. 50-336 B16344 Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Spacifications Enclosure Building Significant Hazards Consideration l
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1 April 1997
4 U.S. Nuclear Regulatory Commission 816344/ Attachment 2/Page 1 l- .
t Proposed Revision to Technical Specifications Enclosure Building
! Significant Hazards Consideration Sionificant Hazards Canaldatation Pursuant to 10CFR50.92, Northeast Nuclear Energy Company (NNECO) has reviewed ,
i the proposed changes. NNECO concludes that these changes do not involve a significant hazards consideration (SHC) since the proposed changes satisfy the criteria i in 10CFR59.92(c). That is, the proposed changes do not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
l The proposed changes to Technical Specifications 3.6.5.1 and 3.6.5.2, i relocation of Surveillance Requirement 4.6.5.1.d.3 to Specification 3.6.5.2, .
changes to Bases Sections 3.6.5.1 and 3.6.5.2, and deletion of Definition 1.25 i- will resolve the conflict that currently exists between Specifications 3.6.5.1 and
- 3.6.5.2. Specifically, the requirement to establish and maintain a negative l pressure in the Enclosure Building boundary included in Specification 3.6.5.1 belongs in Specification 3.6.5.2. In the event Enclosure Building operability. is not maintained in Modes 1-4, the Action Statement for LCO 3.6.5.2 requires that Enclosure Building operability must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four j hours is a reasonable completion time considering the limited leakage design of containment and the low probability of a DBA occurring during this time period.
- Therefore, it is considered that there exists no loss of safety function. The proposed changes do not modify the LCO or surveillance acceptance criterion, nor do they change the frequency of the surveillances. The proposed changes
- i. do not involve any physical changes to the plant, do not alter the way any
. structure, system, or component functions. Therefore, the structures, systems, I or components will perform their intended function when called upon. (The redundancy of the double doors has not been credited in the radiological dose calculations for any Design Basis Accident.) The proposed changes do not affect
- the probability of any previously evaluated accident. Additionally, the proposed changes are consistent with the new, improved Standard Technical Specifications for Combustion Engineering plants (NUREG-1432).
l The editorial changes to Technical Specifications 3.6.5.1, 3.6.5.2, and 3.9.15 do not change any technical aspect of these specifications. Therefore the proposed changes do not affect the probability of any previously evaluated accident.
Based on the above, the proposed changes do not involve a significant increase
! in the probability or consequences of an accident previously evaluated.
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U.S. Nuclear Regulatory Commission 816344/ Attachment 2/Page 2
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes do not make any physical or operational changes to existing plant structures, systems, or components. The proposed changes do not introduce any new failure modes. The proposed changes simply resolve a conflict which currently exists between Specifications 3.6.5.1 and 3.6.5.2. Thus,
- the proposed changes do not create the possibility of a new or different kind of .
accident from any accident previously evaluated.
- 3. Involve a significant reduction in a margin of safety.
The proposed changes do not have any adverse impact on the accident analyses. Also, the proposed changes resolve a conflict which currently exists between Specifications 3.6.5.1 and 3.6.5.2. The structures, systems, or components covered under Specifications 3.6.5.1 and 3.6.5.2 will perform their intended safety function when called upon.
Based on the above, there is no significant reduction in the margin of safety.
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