Letter Sequence Other |
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Results
Other: A06539, Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 170, B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement, B11827, Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity, ML20129A151, ML20133F264, ML20141F878, ML20151M062, ML20154E988, ML20195G527
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MONTHYEARB11271, Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid1985-05-28028 May 1985 Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid Project stage: Request ML20129A1511985-05-31031 May 1985 Proposed Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers Project stage: Other B11598, Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 8512261985-06-27027 June 1985 Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 851226 Project stage: Request B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement1985-07-24024 July 1985 Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement Project stage: Other ML20126M2981985-07-24024 July 1985 Application for Amend to License DPR-65,revising Tech Specs to Expand Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks.Fee Paid Project stage: Request ML20134N6051985-08-26026 August 1985 Forwards Auxiliary Sys Branch Request for Addl Info Re Util 850724 Request to Modify Tech Spec Concerning Expansion of Spent Fuel Storage Capacity.Response Requested within 15 Days Project stage: RAI ML20135G1691985-09-0505 September 1985 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion,To Complete Review of 850724 Request to Modify Tech Specs.Info Requested within 15 Days of Ltr Receipt Project stage: RAI B11712, Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity1985-09-16016 September 1985 Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity Project stage: Request ML20133F2641985-10-0101 October 1985 Proposed Rev to Tech Spec 3/4.7.10,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired Project stage: Other B11733, Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable1985-10-0101 October 1985 Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable Project stage: Request ML20133E7071985-10-0303 October 1985 Forwards Structural & Geotechnical Engineering Branch Request for Addl Info to Complete Review of 850724 Application to Modify Tech Specs Re Spent Fuel Storage Capacity Expansion Project stage: RAI B11827, Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity1985-10-28028 October 1985 Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity Project stage: Other B11889, Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons1985-11-25025 November 1985 Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons Project stage: Request B11766, Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 8601311985-11-25025 November 1985 Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 860131 Project stage: Request B11910, Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from1985-12-0303 December 1985 Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from Project stage: Request B11916, Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested1985-12-16016 December 1985 Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested Project stage: Supplement ML20141F8781986-01-0303 January 1986 Advises That Review Underway of Proposed Inservice Insp & Testing Program,Submitted on 850627.Proposal Would Increase Program Beyond Current Tech Spec Requirements.Final Approval of Submission Will Be Granted Upon Completion of Review Project stage: Other ML20214N7971987-05-27027 May 1987 Forwards Request for Addl Info for Review of 850627 Submittal Re Inservice Testing at Facility.Addl Info Should Be Submitted within 60 Days of Ltr Receipt Project stage: RAI A06539, Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 1701987-05-29029 May 1987 Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 170 Project stage: Other ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R Project stage: Other A06958, Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager1988-01-0808 January 1988 Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager Project stage: Request ML20151M0621988-04-14014 April 1988 Advises That Revised post-fire Safe Shutdown Methodology Conforms W/Requirements of Sections III.G.3. & Iii.L of App R,10CFR50 & Acceptable,Per .Technical Evaluation Rept SAIC-87/3084 Encl Project stage: Other ML20154E9881988-05-12012 May 1988 Fowards Addl Info Re Inservice Insp Program,Per 880212 Request.Attachment 1 Consists of Util Response to Questions Posed in NRC & Attachment 2 Consists of Revised Program Sections Project stage: Other ML20150C7151988-06-28028 June 1988 Forwards Request for Addl Info Re Pump & Valve Inservice Testing Program.Response Requested within 60 Days of Receipt of Ltr Project stage: RAI 1985-08-26
[Table View] |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 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 ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F ML20154A3701998-09-28028 September 1998 Proposed Tech Specs 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,revising Info Re Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA ML20154C0491998-09-28028 September 1998 Proposed Tech Specs Revising FSAR Separation Requirement of Six Inches Which Is Applied to Redundant Vital Cables, Internal Wiring of Redundant Vital Circuits & Associated Devices ML20151V5011998-09-0909 September 1998 Proposed Tech Spec Changing TS Definitions 1.24,1.27,1.31, 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 B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified1998-08-12012 August 1998 Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified B17341, Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval1998-08-0606 August 1998 Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval ML20236Y0831998-08-0404 August 1998 Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves ML20236X2521998-07-30030 July 1998 Proposed Tech Specs Bases 3/4.9.1,3/4.1.1.3,3/4.7.1.6, 3/4.7.7,3/4.5.4 & 3/4.3.3.10,resolving Miscellaneous Condition Repts ML20236W0201998-07-30030 July 1998 Proposed Tech Specs Bases Section 3/4.6.1.1,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236T2681998-07-21021 July 1998 Proposed Tech Specs Re Reactor Protection & ESFs Trip Setpoints ML20236T5301998-07-17017 July 1998 Proposed Tech Specs Pages for TS Bases Section 3/4.4.9, Pressure/Temperature Limits ML20236T7331998-07-17017 July 1998 Proposed Tech Specs Modifying DG Testing Requirements ML20249A2811998-06-10010 June 1998 Proposed Tech Specs Re Post Accident Access to Vital Areas (Plar 3-98-6) ML20249A3121998-06-0606 June 1998 Proposed Tech Specs Re SLCRS Bypass Leakage (Plar 3-98-5) ML20249A2681998-06-0505 June 1998 Proposed Tech Specs Re Revised Steam Generator Tube Rupture Analysis (Plar 3-98-4) ML20248M2221998-06-0404 June 1998 Revised Tech Specs Pages,Changing TS Bases Section 3/4.7.1.5 to Reword Section Which Describes Limiting Temperature Case for Containment Analysis ML20247G6841998-05-14014 May 1998 Proposed Tech Specs,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 B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage1998-05-0707 May 1998 Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247B9411998-05-0101 May 1998 TS Change Pages for TS Bases Section 3/4.5.4,modifying Wording Associated W/Refueling Water Storage Tank Minimum Boron Concentration ML20217D5941998-04-30030 April 1998 Proposed Tech Specs Re Change to Basis 3/4.6.4 Which Modifies Accuracy Range Associated W/Measured Std Cubic Feet Per Minute & Corrects Listed Component Number ML20217N9441998-04-29029 April 1998 Proposed Tech Specs Replacing Two low-range Pressurizer Pressure transmitters,PT-103 & PT-103-1,which Will Identify That Two low-range Pressurizer Pressure Instrument Channels Are Independent & Redundant Only 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 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 ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
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Docket No. 50-336 Attachment Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications Fire Protection May,1985 8506040484 850528
~. PDR ADOCK 05000336 P PDR __
INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION - ,
3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.
ACTION:
With the number of OPERABLE fire detection instrument (s)less than the l
minimum number of OPERABLE requirements of Table 3.310. l
- a. Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperatures at least once per hour at the locations listed in Specification 4.6.1.5.
- b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action ;
taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status. ;
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE
_ e _ at least once per 6 months by performance of a CHANNEL
'7- FUNCTIONAL TEST. Fire detectors which are not accessible during
- plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each
. COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
f 9
MILLSTONE - UNIT 2 3/4 3-43 a
r em-,m- , -,, A -- >-- - ,.~ >,e-
- - , , w,. ---- , - --- w - ,, .>,-w-
n INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)
- 4. 3. 3. 7.2 The circuitry associated with the supervision of the above fire detection instruments and circuits, per NFPA 72-D, shall be demonstrated OPERABLE at least once per 6 months.
- 4. 3. 3.7.3 The non-supervised circuits, associated with detector alarms, between the instrument and the control room shall be demonstrated OPERABLE at least once per 31 days.
{x-8 MILLSTONE - UNIT 2 3/4 3-44
. _ - . . . - - . - - . . . . - ~ . - - - - r---
R i:
a o
R
@ TABLE 3.3-10 0 .
u FIRE DETECTION INSTRUMENTS Heat Smoke Minimum Minimum Total No. Channels Total No. Channels instrument Location (Zone) of Channels Operable of Channels . Operable
- 1. Containment East Penetration (37) -- --
7 5 i West Penetration (41) . -- --
7 5 i $. 2. Control Room Vent Duct (42) Z-2 1 1 Control Room Vent Duct (2) Z-1 1 1 y
i
$; 3. Cable Vaults & Areas Aux Bldg Cable Vault (25') (10) 5 4 16 12 Turbine Bldg Cable Vault (25') (21) : -- --
9 7 Turbine bldg Cable Vault (45') (21) -- -- 8 6 Lunch Room Cable Chase Area (36'6")(24) -- --
4 3
- 4. 4.16 & 6.9 KV Switchgear Room (54'6") (40) -- -- 4 3 4.16 KV Switchgear Room (31'6")(18) -- --
4 3 480 V Aux Bldg Switchgear Room (36'6")(28) -. --
2 1 i 480 V Turbine Bldg Switchgear' Room (36'6")(18) -- --
2 1 West DC Equipment Room (38) -- --
3 2 East DC Equipment Room (38) -- -- 4 3
- 5. Battery Rooms West Battery Room (14'6") (39) . -- --
1 1 East Battery Room (14'6") (39) -- -- 2 1 1
i
r- -
'l 5 ~
5 TABLE 3.3-10 (Continued)
FIRE DETECTION INSTRUMENTS E
4 N Heat Smoke Minimum Minimum Total No. Channels Total No. Channels Instrument Location (Zone) of Channels Operable of Channels Operable
- 6. Electrical Penetration Rooms East (14'6") (20) -- --
3 2 West (14'6") (17) -- --
2 1
- 7. Diesel Generators u Diesel 1221(30) -- --
1 1 D Diesel 1321 (32) -- --
1 1
- 8. Main Exhaust Equipment Room Room (EL 38'6")(5) -- -- 2 1
- 9. Auxiliary Building -45 (FLP-1)
General Area (48) -- --
3 2
- a. Safe Guards Room (48) -- --
2 1 ;
- b. Safe Guards Room (48) -- --
1 1
- 10. Auxiliary Building -25 (FLP-2)
General Area -25 (52) - --
9- 7 Charging Pump Rooms -25 (52) -- --
5 3
- 11. Containment Building FLP-3 RCP "A" 5 3- -- --
RCP "B" 5 3 -- --
RCP "C" 5 3 - --
RCP "D" 5 3 -- --
- q
- f. TABLE 3.3-10 (Continued)
C g FIRE DETECTION INSTRUMENTS
'M e
$ Heat Smoke H Minimum Minimum
" Total No. Channels Total No. Channels Instrument Location (Zone) of Channels Operable of Channels - Operable
- 12. Auxiliary Building (-5/14'6") FLP-4 Auxiliary Building General Area 14'6"(41) -- --
9 '7 Auxiliary Building West Piping Penetration (41)
Room -5' - --
2 1 Auxiliary Building -5' (41) , -- --
14 10 R
0
7 INSTRUMENTATION ACCIDENT MONITORING LIMITING CONDITION FOR OPERATION "
3.3.3.8: The accident monitoring instrumentation channels shown in Table 3.3.11 shall be OPERABLE.
APPLICABILITY: MODES 1,2, and 3.
ACTION:
- a. Actions per Table 3.3-11.
- b. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL -
CALIBRATION operations at the frequencies'shown in Table 4.3-7.
~
MILLSTONE - UNIT 2 3/4 3-48 L...
TABLE 3.3-11 ACCIDENT MONITORING INSTRUMENTATION o ..
Minimum
'g Total No. Channels
' of Channels Operable Action Instrument E
E 1. Pressurizer Water Level 2 1 1 9
- 2. Auxiliary Feedwater Flow Rate 2/S. G. 1/S.G. 1
- 3. RCS Subcooling Margin Monitor 1 1 2
- 4. PORV Position Indicator Acoustic Flow Monitor 1/ valve 1/ valve 3 g
- 5. PORY Block Valve Position Indicator 1/ valve 1/ valve 3
[
e
- 6. Safety Valve Position Indicator Acoustic Flow Monitor 1/ valve 1/ valve 3 l
l l
I E-____
n-TABLE 3.3-11 (Continued)
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels'less than required by Table 3.3-11, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in HOT STANDBY within~the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 - With the subcooling margin monitor INOPERABLE, determine the subcooling margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 - With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information, and monitor discharge pipe temperature once per shif t to determine valve position. This action is not required if the PORV block valve is closed with power removed in accordance with Specification 3.4.3.a or 3.4.3.b.
y MILLSTONE - UNIT 2 3/4 3-50
- r E
5; 3
x c TABLE 4.3-7
-2 U ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION
- 1. Pressurizer Water Level M R
- 2. Auxiliary Feedwater Flow Rate M R
, 3. Reactor Coolant System Subcooling Margin Monitor M R
- 4. PORY Position Indicator (Acoustic Monitor) M R
- 5. PORV Block Valve Position Indicator N.A. R i
- 6. ' Safety Valve Position Indicator (Acoustic Monitor) M R s
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.9.1.3 The fire pump diesel starting 12-volt batteries and charger shall be demonstrated OPER ABLE:
- a. At least once per 7 days by verifying that:
- l. The electrolyte level of each battery is above the plates, and
,. . 2. The individual overall battery voltages are > 12 volts.
- b. At least once per 92 days by verifying that the specific gravity is
, appropriate for continued service of the batteries.
l
- c. At least once per 18 months by verifying that:
- 1. The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and
- 2. The terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
i 1
t i
MILLSTONE - UNIT 2 3/4 7-36 1
.e - - , ww we-,
. ... . . - ._ .. .. ~ .-.
. PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS l'
LIMITING CONDITION FOR OPERATION 3.7.9.2 The following spray and/or sprinkler systems shall be OPERABLE:
>- a.' Diesel Generator Rooms
! b. Diesel Generator Day Tank Rooms
- c. Cable Vault (Aux. Building)
- 1. Sprinkler
- 2. Deluge
- d. Cable Vault (Turbine. Building)
. e. Hydrogen Seal Oil Unit f.- Turbine Building Northeast Corner '
- _ g. Turbine Building 31'6"/l4'6"- North s
-h. Turbine Building 31'6"/14'6"- South
- i. Lube Oil Room.
- j. Aux. Building (-45'6") General Area i- k. Aux. Building (14'6") Truck Access t
- 1. Turbine Bearing f m. Steam Generator Feed Pumps e
- APPLICABILITY
- Whenever equipment in the spray / sprinkler protected areas is
. required to be OPERABLE.
ACTION:
- a. With one or more of the above required and/or systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within I hour; restore the system to OPERABLE status within 14 days or,in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability b and the plans and schedule for restoring the system to OPERABLE -
status.
- b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
4 MILLSTONE'- UNIT 2 3/4 7-37 i.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.9.2 Each of the above re' quired spray and/or sprinkler systems shall be demonstrated OPERABLE.
~
a.- At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
- b. At least once per 18 months:
1.. By performing a system functional test which includes
, simulated automatic actuation of the system; and a) Verifying that the automatic valves in the flow path actuate to their correct positions on a simulated test signal, and b) Cycling each valve in .the flow path that is not testable during plant operation through at least one complete -
cycle of full travel.
t
- 2. By inspection of the spray headers to verify their integrity, and
- 3. By inspection of each nozzle to verify no blockage.
- c. At least once per 3 years by performing an air or ' water flow test through each open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unobstructed.
m, 5
MILLSTONE - UNIT 2 3/4 7-38 ME f 4 w - , ,e - --
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v
PLANT SYSTEMS .
FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION ;
3.7.9.3 The fire hose stations shown in Table '3.7-2 shall be OPERABLE.
APPLICABILITY:' Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.*
l ACTION:
- a. ~ With one or more of the fire hose stations shown in Table 3.7-2 inoperable, route an additional equivalent capacity fire hose to'the -
unprotected area (s) from an OPERABLE hose station within I hour or.
establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s).. If the inoperable hose station (s)is not the primary means of fire suppression then route the additional fire hose (s) or establish a continuous fire watch with fire .
sur greLion equipment within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. : The provisions of Specifications 3.0.3 an'd 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS f
4.7.9.3 ' Each of the fire hose stations shown in Table 3.7-2 shall be demonstrated OPERABLE:
- a. At least once per 31 days by visual inspection of the station to assure all required equipment is at the station. The exception to the above -
will be the containment hose stations. The equipment will be located outside containment except when the unit is in cold shutdown.
- b. At least once per 18 months by:
- 1. . Removing the hose f or inspection and re-racking, and -
- 2. Replacement of all degraded gaskets in couplings.
- c. At least once' per 3 years by: -
'l.- "artially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
- 2. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the. maximum pressure available at that hose station.
- Containment hose s' tations shall be operable in MODE'S when required to support maintenance activities and MODE 6.
MILLSTONE - UNIT 2 3/4 7-39 P
t 3.
TABLE 3.7-2 FIRE HOSE SATIONS Hose Station Number Bldg / Elevation Area
-l-7~ Turbine /14'6" Turbine Building 8-14 Turbine /31'6" Turbine Building 15-21 Turbine /54'6" Turbine. Building 22 Auxiliary /-45'6" Center of Open Area 23 Auxiliary /-25'6" Near Elevator.
~24 Auxiliary /-5'0" Near . Elevator
-25 Auxiliary /14'6" Near Elevator 26 Auxiliary /38'6" Spent Fuel Pool-Northwest corner 27 Auxiliary /14'6" Boric Acid Datch Tank area 28 Auxiliary /14'6" Near MCC'22-lE (BSI)
E 29 Auxiliary /14'6" Railway access 30 Auxiliary /38'6" Spent Fuel Pool-South Wall 31 Auxiliary /14'6" Outside Diesel Room 34 Auxiliary /38'6" Southeast corner stairway 40 Auxiliary /5'0" Southeast corner stairway 41 Auxiliary /25'6" Cable Vault Southeast Entrance 42 Auxiliary /36'6" Control Room Ventilation Area 1
l
. MILLSTONE - UNIT 2 3/4 7-40
. l i
.l 1., n _.'- _ _
J
n I:- . ,
0 TABLE 3.7-2 FIRE HOSE S ATIONS 43 Turbine /45'0" North Entrance of
' Turbine Bldg. Cabie
- Valts 44-45 Containment /38'6" East & West Stairwells 46 . Containment /14'6" East & West Stairwells 48-49' Containment /22'0" East & West Stairwells k'
4 L '.
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I i
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' MILLSTONE UNIT 2 ~
3/4 7-41.
g.. r- ,
c PLANT SYSTEMS 3/4.7.10 PENETRATION FIRE BARRIERS LIMITING CONDITION FOR OPERATION 3.7.10 All fire barriers and fire-rated penetration seals (including cables, cable trays, conduit, pipes, fire doors and dampers) that provide physical separation between redundant safe shutdown systems / equipment shall be functional.
APPLICABILITY: At all times unless otherwise determined that the separation between redundant safe shutdown systems / equipment is not required based on the MODE of operation.
ACTION:
~
- a. W'ith one or more of the above required fire barriers / penetration
- ,eals non-functional, within I hour:
1.- determine that the fire areas / zones on both sides of the affected fire barrier / penetration seal are monitored by either an OPER ABLE fire detection or automatic suppression system and establish a fire watch patrol that inspects both areas at least once per eight (8) hours, or
- 2. establish a continuous fire watch on at least one side of the affected fire bartier/ penetration seal, or
- 3. temporarily repair the non-functional fire barrier / penetration seal and classify it as temporary.
All temporary or non-functional fire barrier / penetration seals shall be permanently repaired within thirty (30) days, or a special report to the Commissio'n pursuant to Specification 6.9.2 will be submitted within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the fire barrier / penetration seal to functional status,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.10 The above required fire barriers / penetration seals shall be verified to be functional by a visual inspection:
- a. ' At least once per 18 months for fire doors and fire dampers. l MILLSTONE . UNIT 2 3/4 7-42
LIMITING CONDITION FOR OPERATION
- b. At least once per 18 months for fire barrier penetration seals, on at least 10% of the total number of penetration seals. If any of the penetration seals in the inspection sample are found to be non-functional, then~an additional 10% sample of the total number of penetration seals shall be visually inspected. Sampling and inspection shall continue until all of the seals in a sample are found functional or 100% of the seals are inspected,
- c. Prior to returning a fire barrier / penetration seal to functional status following repairs or maintenance.
I MILLSTONE'- UNIT 2 3/4 7-43
p PLANT SYSTEMS BASES-In the event the fire suppression water system .becomes inoperable, immediate' corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-
~
four hour report to the Commission provides- for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression
, capability for the continued protection of the nuclear plant.
3/4.7.10 PENETRATION FIRE BARRIERS -
The functional integrity of fire barriers ensures that fires will be confine'd i
or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barriers are
. a pa:sive . element in the facility fire protection program and are subject to priodic inspections.
During periods of time when a barrier is not functional, alternate measures are taken to prevent the possible spread of fire. These measures include verifying the operability of fire detection or suppression systems on both sides of the affected barrier and establishing a fire watch patrol, or posting a continuous fire watch in the vicinity of the affected barrier, or installation of a temporary fire stop pending restoration of the permanent seal.
MILLSTONE - UNIT 2 B 3/4 7-7 L
i ADMINISTR ATIVE CONTROLS THIRTY-DAY WRITTEN REPORTS (Continued) form. Information provided on the licensee event report form shall' be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
- a. Reactor protection system or engineered safety features instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems,
- b. Conditions leading to operation in a degraded mode permitted by a limiting. condition for operation or plant shutdown required by a limiting condition for operation.
- c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety features systems.
- d. Abnormal degradation of systems other than those specified in 6.9.1.8.c, above, designed to contain radioactive material resulting from the fission process.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a. Inoperable Seismic Menitoring Instrumentation, Specification 3.3.3.3.
- b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
- c. Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1. -
. d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- e. Fire Detection Instrumentatloa, Specifications 3.3.3.7.
- f. Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.
- g. RCS Overpressure Mitigation, Specification 3.4.9.3.
- h. Penetration Fire Barriers, Specification 3.7.10. l MILLSTONE - UNIT 2 6-21 L _