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MONTHYEARML20207G7281986-12-22022 December 1986 Proposed Tech Specs,Changing Expiration Date of OL from 101211 to 150731 Project stage: Other ML20207G6911986-12-22022 December 1986 Application for Amend to License DPR-65,changing Expiration Date of OL from 101211 to 150731 Project stage: Request B12368, Forwards Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of Ol. Fee Paid1986-12-22022 December 1986 Forwards Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of Ol. Fee Paid Project stage: Request ML20206A4141987-04-0101 April 1987 Forwards Request for Addl Info Re 861222 Application for Extension of Expiration Date for License DPR-65.Response Requested within 60 Days of Ltr Receipt Project stage: RAI B12451, Submits Addl Info Re Transportation of Nuclear Fuel & Radioactive Waste to & from Facility,Per NRC 870220 Request, Including Initial U-235 Fuel Assembly Enrichment1987-04-0303 April 1987 Submits Addl Info Re Transportation of Nuclear Fuel & Radioactive Waste to & from Facility,Per NRC 870220 Request, Including Initial U-235 Fuel Assembly Enrichment Project stage: Other ML20209H0341987-04-24024 April 1987 Forwards Request for Addl Info in Order to Continue Review of 861222 Application Re Expiration of Facility OL & 860123 Submittal Re Pressurized Thermal Shock Project stage: RAI ML20214T7491987-05-28028 May 1987 Forwards Addl Info Re Nonradiological Impacts Associated w/861222 Request to Extend Duration of License to 40 Yrs from Date of Issuance of OL Project stage: Other ML20234B4001987-06-30030 June 1987 Forwards Request for Addl Info Re 861222 Application for Extension of Expiration Date for License DPR-65.Response Requested within 60 Days of Ltr Receipt Project stage: RAI A06657, Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request1987-08-0404 August 1987 Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request Project stage: Request A06470, Forwards Addl Info,Clarifying Info Submitted in Author Re OL Extension Amend,Per NRC 870401 Request1987-10-0505 October 1987 Forwards Addl Info,Clarifying Info Submitted in Author Re OL Extension Amend,Per NRC 870401 Request Project stage: Other ML20236V6801987-12-0202 December 1987 Notification of 871210 Meeting W/Util in Bethesda,Md to Discuss Encl Questions Re Worker Radiation Exposure Project stage: Meeting B12777, Forwards Addl Info for 861222 Amend Request for 40-yr Ol,Per NRC 871210 Request.Extent & Effectiveness of Util ALARA Programs at Other Plants Evident When Reviewing Encl Chronology Program & Achievements to Date1987-12-18018 December 1987 Forwards Addl Info for 861222 Amend Request for 40-yr Ol,Per NRC 871210 Request.Extent & Effectiveness of Util ALARA Programs at Other Plants Evident When Reviewing Encl Chronology Program & Achievements to Date Project stage: Request ML20147C3461988-01-0606 January 1988 Summary of 871210 Meeting W/Util in Bethesda,Md Re Full 40-yr OL & Status of Worker ALARA Programs at Plants.List of Attendees & Viewgraphs Encl Project stage: Meeting 1987-04-24
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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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TABt2 1 MILISIUfB UNIT NO. 2 l IEgygg VA WES (%)
"I" I
"M" f=FIDENCE (Ep_1 MeV)10 I9 n/ 2 TIMF: OF CUIUtfNT O.L. PflOP. O.I..
CllENICAL CONITNr INITIAL EltROR SUCMIT. EXP. D\TE EXP. (WIF.
IDCATION Wt.% Cu Wt.% N1 Rr/ggp, TElel 7 EFPY 28 EFPY 32 EFPY ~7 EFPY 28 EFPY 32 EFPY Intermed.
Course C505-2 0.13 0.64 25 48 0.81 4.32 5.0 148.78 192.09 196.88 C505-3 0.13 0.65 0 48 0.89 3 5.24 3 6.2 3
126.18 174.18 180.04 Imer Courae C506-1 0.14 0.61 6 48 0.81 4.32 5.0 134.95 181.21 186.33 C506-3 0.13 0.70 0 48 0.81 4.32 5.0 126.36 171.14 176.10 Welds 1-203 0.22 0.99 -45 48 0.12 0.63 0.75 97.69 152.74 159.95 8-203 0.30 0.10 -60 48 0.12 0.63 0.75 72.56 120.32 126.70 9-203 0.30 0.06 -55 48 0.81 4.32 5.0 122.71 196.82 205.03 2-203 0.12 0.20 -50 48 0.01 4.32 5.0 49.77 79.35 82.62 1 Initial Rr fnin FSAR for platen (except C506-1 which is fran baseline report), adjusted for transverse orientation (pet MTEI3-5-2) .NUfor welds these are taken frun CEN-189.
2 "M" is the manjin ackled to cover uncertainties in the values of initial RT fluence arul calculational procedures. "M" = 48"F if a measured value of "I" was used, ann," coppgr
= 59 F ifand thenickel genericcontent, mean value of "I" was used.
3 Limiting caso due;,to thormal shield renoval, resulting in a drilled hole in the core barrel.
REF: NUSCO Calculation 101-200-433GP.
8701070383 861222 PDR ADOCK 05000336 p ,
PDR
TABLE 2 ANNUAL OFFSITE POPULATION DOSES FROM MILLSTONE SITE EFFLUENTS Airborne Effluents. Person-rem Liquid Effluents. Person-rem Total Units 1 & 2. Person-rem.
Yea.- Unit Whole Body Skin Thyroid Whole Body Maximum Organgal Thyroid Whole Body Sk in Maximum Oraantal Thyroid 1971 9'.4 (+1) 1 2.1(+2) 2.1(+2) 8.7 (-1) 1.0(+1) 1.0 (+1) 9.5(+1) 2.1 (+1) 1.0 (+1) 2.2 (+2) 1972 5.1 (+2) 1.2(+3) 5.5(+2) 1 1.0(+1) 1.6(+1) 1.6 (+1) 5.2 (+2) 1.2 (+3) 1.6(+1) 5.7(+2) 1973 4.6 (+1) 1 1.0(+2) 5.1 (+1) 7.6 (0) 5.2 (0) 4.8 (0) 5.< (+1) 1.0 (+2) 5.2 (0) 5.6 (+1) 1974 5.0(+2) 1 1.1(+3) 5.5(+2) 3.6(+1) 2.7(+1) 3.0 (+1) 5.4 (+2) 1.1 (+3) 2.7(+1) 5.0 (+2) 1975 1.8 (+3) 1 3.8(+3) 2.0 (+3) 2.8(+1) 2.2 (+1) 2.7 (+1) 1.8 (+3) 3.8 (+3) 2.2 (+1) 2.0 (+3) 1976 3.6(+2 8.2(+2) 1 4.2(+2) 4.4 ll-1) 9.2 (-1) 5.1(-1) 3.6(+2) 8.2 (+2) 9.6(-1) 4.2 (+2) 2 2.9(-1)) 1.0 (0) 8.6(-1) 7.1I,-3) 3.9(-2) 1.8(-2) 1977 4.2 (+2) 9.5 i;+2) 1 5.2(+2) 4.8 ll-2? 2.9 (-2) 3.1 (-2) 4.2 (+2) 9.5 (+2) 3.0 (-1) 5.2 (+2) 2 2.6(-1) 7.9I;-1) 5.3 (-1) 7.6 1,-2l 2.7(-1) 5.3 (-2) 1978 l' 2.3(+2? 6.6(+2) 3.7(+2) 8.9(-2;l 1.6I;-2) 2 4.8(-Is 1.6(-2) 1.6 (-1,l 2.8(+2) 6.6(+2) 8.3 (-1) 3.7 (+2) 1.6 (0) 9.7(-1) 7.4 (-11 1.1I;-1) 1979 1 6.3 (0) 3.0 (0) 1.4 (+1) 1.9 (-2) 5.5(-2) 1.5 (-2) 7.7 (0) 5.1 (0) 1.3 (0) 1.6(+1) 2 1.0 (0) 2.1 (0) 1.5 (0) 3.8(-1) 1.2 (0) 2.9 (-1) 1980 1 9.6 (0) 2.5(+1) 1.4(+1) 1.0 (-1) 7.7 (-2) 8.1 (-2) 1.1 (+1) 2.7(+1) 8.2 (-1) 1.6 (+1) 2 9.8 (-1) 1.5 (0) 1.4 (0) 2.2 (-1) 7.4 (-1) 1.7 (-1) 1981 1.5 (+1) 3.4(+1) 2.1 (0) 1 1.9 (-2) 6.5 (-2) 2.5 (-4) 1.6 (+1) 3.6 (+1) 4.2 (-1) 3.3 (0) 2 5.8(-1) 1.6 (0) 1.0 (0) 7.7 (-2) 3.5(-1) 1.8 (-1) 1982 1 3.4 (3) 1.2(+1) 2.1 (0;I 1.1 i;-1) 1.0I;-1) 1.1 (-1) 5.7 (0) 1.8 (+1) 8.3 (-1) 8.5 (0) 2 1.9 (0) 5.5 (0) 4.6 (0;I 3.2i,-1) 7.31,-1) 1.7 (0) 1983 1 1.8 1.0 4.7 0 5.3(-l 3.6 f-21 5.9 I;- 6.0i;-2;l 3.6 (0) 8.1 (0) 9.3 (-1) 2.4 (0) 2 3.4 0 1.2 (0 8.1ll-1? 8.7 L- ? 5.8 1,-1; 1984 9.1 (-1) 1 3.7 (0) 6.4 (-11 3.8 (-31 5.4 f-3) 3.1 (-3) 2.4 (0) 7.2 (0) 2.4 (-1) 3.2 (0) 2 1.2 (0) 3.5 (0) 2.3 (0? 2.7(-l? 2.4L-1) 2.6 (-1)
Grand Total 4.1 (+3) 8.8(+3) 8.7 (+1) 4.8 (+3)
Id)The mo lmum nrqan for liquid effluents is typicaly the liver or gastrointestinal track lower large intestine. The dose to these organs from i ' e ta.e n.- ..f f luents is insignificant compared to the liquid pathway dose.
TABLE 3 l
~.
ANNUAL MAXIMUM OFFSITE INDIVIDUAL DOSES FROM MILLSTONE SITE EFFLUENTS Airborne Effluents, mrem Liquid Effluents, mrem Total Units 1 & 2. mrem . .
Year Unit Whole Body Skin Thyroid Whole Body Maximum OrganLDJ Thyroid Whole Body Skin Maximum OrgantaJ Thyroid 1911 1 2.3 (0) 2.3 (0) 3.2 (+1) 1.0 (-1) 2.6 (0) 2.6 (0) 2.4 (0) 2.3 (0) 2.6 (0) 3.5 (+1) 1972 1 1.5 (+1) 1.5(+1) 1.2 (+1) 1.3 (0) 4.2 (0) 3.1 (0) 1.6 (+1) 1.5 (+1) 4.2 (0) 1.6 (+1)
I 1973 1 1.3 (0) 1.3 (0) 9.8 (-1) 9.5 (-1) 1.5 (0) 5.1 (-1) 2.3 (0) 1.3 (0) 1.5 (0) 1.5 (0) 1974 1 9.9 (0) 9.9 (0) 1.4 (1) 4.8 (0) 9.6 (0) 4.7 (0) 1.5 (+1) 9.9 (0) 9.6 (0) 1.9 (+1) 1975 1 3.4 (+1) 3.4(+1) 7.0 (+1) 3.8 (0) 6.7 (0) 4.5 (0) 3.8 (+1) 3.4 (+1) 6.7 (0) 7.5(+1) 2 0 0 2.6 (-5) 3.5(-4) 5.0(-3) 6.0 (-4) 1976 1 9.8 (0) 9.9 (0) 9.9 (0) 8.4 (-2;l 1.2(-1) 7.4I;-2) 1.0 (+1) 1.0(+1) 1.3(-1) 1.0 (+1) ,
2 1.1 (-1) 2.7 (-1) 1.9 (-1) 4.1 (-4;I 1.0 (-2) 2.0I;-3) l 1977 1 9.8 (0) 9.8 (0) 1.2 I;+1:1 6.0 (-3;I 7.2(-3) 1.3 (-4) 9.9 (0) 1.0(+1) 6.8 (-2) 1.2 (+1) !
2 5.9 (-2) 1.6(-1) 1.6I;-1) 8.9(-3;I 6.1(-2) 6.1 (-3) 1978 1 7.6 (0) 7.6 (0) 1.3(+1) 1.9 (-3) 2.7(-2) 2.2 (-3) 7.8 (0) 8.1 (0) 2.5 (-1) 1.4 (+1) j 2 1.6 (-1) 4.5(-1) 6.1(-1) 1.8(-2) 2.2(-1) 1.2 (-2) 1979 1 1.4 (-1) 1.4 (-1) 1.1 (0) 2.1 (-3) 1.2 (-2) 1.9(-3) 2.1 (-1) 2.1 (-1) 3.3 (-1) 1.4 (0) 2 2.7 (-2) 7.3 (-2) 2.2 (-1) 4.3(-2) 3.2 (-1) 3.7(-2) 1980 1 2.4 (-1) 2.4(-1) 9.2 (-1 1.2 (-2) 1.8 C-2) 1.0 3.8(-1) 4.5 (-1) 2.1 (-1) 1.6 (+0) 2 9.7(-2) 2.1 (-1) 6.1(-1) ) 2.6 (-2) 1.9I;-1) 2.1(-2)
(-2) 1981 1 2.1 (-1) 2.1 (-1) 5.1 (-1) 7.0 f 3) 1.3(-2) 4.6(-3) 3.6(-1) 5.4 (-1) 9.5 (-2) 8.5 (-1) 2 1.2 (-1) 3.3 (.O 2.7(-1) 2.4 i 8.2 (-2) 6.2 (-2) 1982 1 9.9 (-2) 1.0 (-1) 7.5 (-1) 1.4 1.4 (-2) 5.1 (-2 5.5 (-1) 1.1 (0) 2.1 (-1) 4.7 (0) 2 4.0 (-1) 1.0 (0) 3.5 (0) 4.C 2.01,-1) 4.2(-1))
1983 1 3.1 (-2) 3.1 ll-2) 1.5 (-1) 4.3 (-3) 1.4 (-2) 1.1 (-2) 4.0 (-1) 7.7 (-1) 1.8 (-1) 1.2 (0) 2 2.7 (-1) 7.1 L-1) 1.0 (0) 9.9 (-2) 1.7 (-1) 6.6 (-2) 1984 1 5.1 (-2) 5.1 (-2) 2.5 (-1) 4.4(-4) 1.0(-3) 3.6 (-4) 5.0 (-1) 5.5 (-1) 5.5 (-2) 2.9 (0) 2 4.2 (-1) 5.0 (-1) 2.6 (0) 3.2 (-2) 5 4 (-2) 2.6 (-2)
Grand Total 1.0(+2) 9.4 (+1) 2.6 (+0) 2.0 (+2)
I4)Thee numbers are the sunination of quarterly values; for airborne effluents the quarterly values can be different locations and for liquid effluents t h. qu vt. r ly values can be dif ferent organs.
Ih)ihe minimum organ for liquid effluents is typically the liver or gastrointestional tract lower large intestine. The dose to these organs from airborne ef fluents is insignif t: ant co.npared to the liquid pathway dose.
TABLE 4 ANNUAL POPULATION DOSES ALONG RADWASTE SHIPPING ROUTES FROM THE PLANT TO THE FINAL DESTINATION (a)
Millstone Site Year (Person-rem) 1968 -
1969 -
1970 -
1971 0.5 1972 0.8 1973 1.4 1974 2.0 1975 2.8 .
1976 2.9 1977 3.6 (b) 1978 3.1 (b) 1979 3.1 (b) 1980 2.9 (b)
TOTAL 23.1 (a) Distance from plant to final destination averages approximately 900 miles per shipment.
(b) Doses are from shipments from both Unit I and Unit II.
REF: Low Level Radiation Health Effects Study for the Haddam Neck and Millstone Nuclear Power Facilities, July 1981.
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._, _ _ _ , . _ , . _ . . _ . _ , ~ _ . _ . , ,
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- TABLE 5 (1 of 2)
ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location.
Location Number Name Release Point ** Sample Types 1-I* Onsite - Old Millstone 0.6 Mi. - NNW TLD, Air Particulate, Iodine, Road Vegetation 2-I Onsite - Weather Shack 0.3 Mi. - SSE TLD, Air Particulate, Iodine 3-I Onsite - Bird Sanctuary 0.3 Mi. - NE TLD, Air Particulate, Iodine 4-I Onsite - Albacore Drive 1.0 Mi. - N TLD, Air Particulate, Iodine 5-I Floating Barge 0.2 tii. - SSE TLD 6-I Quarry Discharge 0.3 Mi. - SSE TLD 7-I Fox Island 0.3 Mi. - ESE TLD 8-I Environmental Lab 0.3 Mi. - SE TLD 9-I Bay Point Beach 0.4 Mi. - W TLD 10-I Peasure Beach 1.4 Mt. - E TLD, Air Particulate, Iodine 11-I New London Country Club 1.6 Mt. - ENE TLD, Air Particulate, Iodine 12-C Fisher's Island, NY 3.7 Mt. - ESE TLD 13-C Mystic, CT 12.0 Mi. - ENE TLD 14-C Ledyard, CT 12.0 Mi - NE TLD 15-C Montville, CT 14.0 Mt. - N TLD, Air Particulate, Iodine 16-C Old Lyme, CT 8.5 Mi. - W TLD 17-I Site Boundary 0.5 Mi. - NE Vegetation 18-I New London Country Club 1.6 Mi. - ENE Vegetation 19-I Cow Location #1 6.0 Mi. - N Milk 20-I Cow Location #2 9.5 Mi. - NW Milk 21-I Cow Location #3 11.5 Mi. - NE Milk 22-C Cow Location #4 16.0 Mi. - NNW Milk 23-I Goat Location #1 2.0 Mi. - ENE Milk 24-C Goat Location #2 14.0 Mt. - NE Milk 25-I Fruits & Vegetables Within 10 Miles Vegetation 26-I Fruits & Vegetables Beyond 10 Miles Vegetation 27-I Niantic 1.7 Mi. - WNW TLD, Air Particulate, Iodine 23-I Two Tree Island 0.8 Mi, - SSE Mussels 29-I Jordan Cove 0.4 Mi. - NNE Clams 30-C Golden Spur 4.7 Mi. - NNW Bottom Sediment' 31-I Niantic Shoals 1.8 Mi. - NW Bottom Sediccnt, Oysters 1.5 Mi. - NNW Mussels 32-I Vicinity of Discharge Bottom Sediment Oysters, Lobster, Fish, Seawater 33-I Seaside Point 1.8 Mi. - ESE Bottom Sediment 34-1 Thames River Yacht Club 4.0 Mi. - ENE Bottom Sediment 35-I Niantic Bay 0.3 Mi. - W Lobster, Fish 36-I Black Point 3.0 Mi. - WSW Bottom Sediment, Oysters
I TABLE 5 (2 of 2)
Location Number Name Release Point ** Sample Types 37-I Giant's Neck 3.5 Mi. - WSW Bottom Sediment, Oysters Lobster, Seawater 38-I Waterford Shellfish 1.5 Mi. - NNW Clams
- For terrestial locations, this is the MP1 stack, for aquatic it is the quarry cut.
O v--, -,- , - ,n - e -- - -- n--~s -, -- ----w,- ,- -r---rw--,- --*v --,e
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TABLE 6 (1 of 2)
MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection and/or Sample Locations Frecuency Type and Frequency of Analysis I ao- Gamma Dose - 17 Monthly Gamma Dose - Monthly Environmetal TLD 150 Gamma Dose - 22 Quarterly (a) N/A(a)
Accident TLD
- 2. Airborne 8 Continuous Gross Beta - Weekly, Particulate sampler - Gamma Spectrum - Monthly on weekly filter composite (by location), and change on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results.
- 3. Airborne 8 Continuous I-131 - Weekly Iodine sampler -
weekly canister '
change
~
- c. Vegetation 5 One sample Gamma isotopic on each near middle sample and one near end of growing season
- 5. Milk 6 Monthly for Gamma isotopic,1-131, Sr-89 all animals and Sr-90 on each sample except semi- .
I monthly for goats when on pasture
- 6. Sea Water 2 Quarterly - Quarterly - Fractional Beta, Composite of Gamma Isotopic and Tritium 6 Weekly Grab on each composite samples
- 7. Bottom 7 Semiannual Gamma Isotopic on Each Sediment Sample
TABLE 6 (2 of 2)
MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and ,
Exposure Pathway Number of Collection and/or Sample Locations Frecuency Type and Frecuency of Analysis
- 8. Fin Fish-Flounder 2 Quarterly Gamma Isotopic on Each and one other type Sample of edible fin fish
- 9. Mussles 2 Quarterly Gamma Isotopic on Each Sample
- 10. Oysters 4 Quarterly Gamma Isotopic on Each Sample
- 11. Clams 2 Quarterly Gamma Isotopic on Each Sample
- 12. Lobster 3 Quarterly . Gamma Isotopic on Each Sample e - .
(a) Accident monitoring TLDs to be dedosed at least quarterly.
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Table 7 Northeast Utilities occupational Exposures Man dom Raddam Millstone Millstone Ipar Neck Unit 1 Unit 2 1968 50 1969 106 1970 689 1971 342 40 1972 325 596 1973 697 663 1974 201'"' 1430 1975 703 2022 -
1194 168 1976 449 641 392 242 1977 117 1239 1621 1978
.161 472
! 1979 ,,1793 1980 1353 :2158 636 1981 1036 1496 531 1982 126 929 1413 244 1881 1983 1384 1206 849 121 1984 1985 113 651 1728 j
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TABLE 8 (1 of 3) i MILLSTONE UNIT 2 PLANT SYSTEM ANNUAL PERSON-REM System Description 1980 1981 1982 1983 1984
. Heating Ventilation and Air Conditioning 0.050 0.050 0.050 0.035 0.120 Communications 0.215 0.055- 0.010 0.010 0.000 Fire Protection 12.777 0.320 1.305 0.880 0.045 Radioactive Monitoring 1.007 0.160 0.142 0.367 0.866 Aerated or Floor Drain Liquid
, Radioactive Waste 5.625 3.945 4.310 5.070 2.789 3 Clean Liquid Radioactive Waste 10.003 13.056 2.629 7.909 1.770 Gaseous Radioactive Waste 0.174 0.750 0.675 0.330 0.100 i
Liquid Radioactive Waste Management 0.000 0.000 0.050 0.000 0.000 Solid Radioactive Waste 11.524 6.110 3.890 8.510 23.710 Reactivity Control 50.671 1.485 5.615 3.350 0.000 Reactor Vessel Internals 4.835 0.000 2.590 31.835 0.000 Reactor Vessel & Appurtenances 65.734 14.675 39.180 43.115 0.400 Reactor Cavity 24.050 0.000 Coolant Recirculation 90.385 9.700 42.920 102.451 11.610 Feedwater 0.780 0.000 0.020 0.285 0.075 e
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+ TABLE 8'(2 of 3) .
- MILLSTONE UNIT 2 ?LANT SYSTEM ANNUAL PERSON-REM' System Description 1980 1981 1982 1983 1984 .
9 Main Steam 1.370 2.511 1.010 0.948 0.550 Residual Heat Removal 0.040 2.370 0.465 2.865 0.035 4
i CVCS 50.112 11.480 51.369 25.506 8.250 Process Sampling 0.190 2.922 5.930 0.480 0.130 Other Auxiliary Sampling 0.425 9.525 0.735 1.915 0.100 l
Cooling Water; Reactor Auxiliary 2.865 7.602 4.465 3.045 1.870 l
Other Auxiliary Water 0.135 0.005 0.240 0.380 0.020 l
j- All Electric Power System 0.705 0.005 0.020 0.405 0.000 Containment Auxiliary 0.030 0.060 0.250 0.215 0.000 4
CTMT Heat Removal 2.256 3.860 25.625 3.260 0.595 ;
I Emergency Core Cooling 18.355 39.596 37.529 27.481 5.675 Reactor Containment 29.109 8.325 10.895 32.584- 0.735 Auxiliary Building 1.450 0.055 0.060 0.253 0.000 Fuel Handling 9.447 3.310 4.575 6.603 0.010 New Fuel Storage 0.477 0.160 0.000 0.160 0.060 Spent Fuel Pool Cooling 0.390 0.140 0.135 0.640' O.080 Spent Fuel Storage 0.613 0,095 0.220 'O.000 0.940 3
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9-TABLE 8 (3 of 3) ,
MILLSTONE UNIT 2 PLANT SYSTEM ANNUAL PERSON-REM System Description 1980 1981 1982 1983 1984
. Reactor Trip 0.000 14.275 1.560 27.185 0.185 Safety Related Display Instrumentation 23.695 4.015 25.149 8.545 0.175 Steam Generator 64.039 187.204 166.505 258.139 0.075 Pressurizer 10.185 14.102 25.773 23.205 0.040 Plant Personnel Blanket 70.592 62.147 106.541 233.190 15.812 Contractor Blanket 11.517 25.698 735.018 1170.326 24.817 System Code N/A 60.976 57.024 113.040 14.349 12.194 Extraction & Auxiliary Steam 0.040 0.035 0.000 0.310 0.000 Main Condenser 0.000 0.000 0.000 9.230 0.000 i
l S.G. Blowdown 0.110 0.035 3.460 7.846 7.720 1
Turbine Generator 0.181 0.050 0.005 0.270 0.000
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TABLE 9 PRINCIPAL COMPONENTS OF MILLSTONE UNIT NO. 2 LICENSE EXTENSION ECONOMIC ANALYSIS (MILLIONS OF DOLLARS)
Cumulative Cumulative (l)
Nominal Present Worth Dollars Dollars A. Cost of Millstone Unit No. 2 Extension o Carrying Charges for Capital Additions 609 36.4 o O&M Expense 1,501 76.9 o Property Tax (incremental) 13 0.6 o Fuel 500 25.6 Subtotal 2,623 139.5 B. Cost of Deferral Base Load Replacement o Carrying Charges (2) 2,818 144.2 o O&M Expense 856 43.8 o Property Tax 187 9.6 o Fuel 2,044 104.6 Subtotal 5,905 302.2 C. Differences (A-B) for Millstone Unit No. 2 (3,282) (162.7)
Sponsors' Consumers Notes
- 1. Present worth to January,1987 using a 11.74 percent discount rate.
- 2. Estimate uses " economic carrying charges", which correctly capture the long-term cnsts of deferrals.
The specific results displayed above depend upon numerous estimates with respect to future costs, fuel prices, tax laws, etc. Principal assumptions used in this analysis are shown in Table 10.
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0 TABLE 10 PRINCIPAL ECONOMIC ASSUMPTIONS Deferred Base Load Capacity Millstone Unit No. 2 Composite Cost of Capital (pct.) 11.74 11.74 AFUDC (pct.) 9.00 9.00 Discount Rate (pct.) 11.74 11.74 Fixed O&M Expense ($/kW-yr in 2010) 111.9 317.4 Variable O&M Expense'(Mills /kWh in 2010) 11.26 -
Cost of Fuel (Mills /kWh in 2010) 70.1 17.5 Annual Capacity Factor (pct.) 70.0 70.0 Installed Capital Cost ($/kW in 2010) 7990* -
Capital Additions ($/kW) 2010 -
4 9. '#
42.1*
2012 -
33.6*
2013 --
23.9*
2014 -
12.7*
2015 --
4.4
- Property Tax Note 1 Note 2
Note 1 - 1% of the installed cost, unescalated Note 2 - A 2010-2015 extension is estimated to result in increased property taxes of about $12.7 million for Millstone Unit No. 2.