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| {{#Wiki_filter:~"4T Washington Public Power Supply'System A JOINT OPERATING AGENCY l/~(1 l~C-T~d~4 P.O.BOX 958 3000 GCO.WACHINCTON WAT RICHI.AND, WASHINCTON 99352~December 18, 1978 EDM-RGC-78-356 PHONC (509)375 5000 Dr.R.J.Mattson, Director Division of Systems Safety U.S.Nuclear Regulatory Commission Washington D.C.20555 | | {{#Wiki_filter:~ "4T l/ ~(1 l~ |
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| | Washington Public Power Supply'System A JOINT OPERATING AGENCY d~4 P. O. BOX 958 3000 GCO. WACHINCTON WAT RICHI.AND, WASHINCTON 99352 PHONC (509) 375 5000 |
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| | December 18, 1978 EDM-RGC-78-356 Dr. R. J. Mattson, Director Division of Systems Safety U. S. Nuclear Regulatory Commission Washington D. C. 20555 |
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| ==Subject:== | | ==Subject:== |
| ATWS COST ESTIMATES-WPPSS NUCLEAR PROJECT NO.2 | | ATWS COST ESTIMATES-WPPSS NUCLEAR PROJECT NO. 2 |
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| ==Dear Dr.Mattson:== | | ==Dear Dr. Mattson:== |
| I and members of my staff appreciated the opportunity to meet with you and your staff in conjunc'tion with other industry representatives on December 6 to discuss ATWS cost estimates.
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| We are of the opinion that the exchange was very beneficial and provided a better understanding of the impact of various ATWS fixes for all concerned.
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| As a result of our involvement in the ATWS issue over the past several months, we have developed the attached cost estimates for various levels of system modifications to accommodate an ATWS event.As we noted in our presentation to the ACRS Subcommittee on ATWS in October, we consider ATWS to be a Licensing issue and not a plant safety concern.The attached cost estimates are based on our interpretation of what may be requested by the staff.to satisfy your concerns regarding ATWS.The levels we have addressed include the 13 items contained in your November 15 letter to the Atomic Industrial Forum (Mr.John Ward, Chairman, Committee on Reactor Licensing and Safety).We have not independently addressed each item of your letter, but have instead attempted to incorporate them into systems which cover a spectrum of fixes ranging from justification of the existing design to an ultra-conservative mitigation system per NUREG-0460.
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| All assumptions, definitions and the overall bases for cost estimates are included in the attachment.
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| Should you desire further information regarding our cost estimating methods, we would be pleased to discuss the subject with you, or to cooperate with the AIF in preparing an industry presentation on cost estimating methods.7901160102
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| Dr.R.J.Mattson Page Two December 18, 1978 EDM-RGC-78-356 We trust that the attached information will be of use to you in evalu-ating the costs of ATWS.Should you have any questions regarding our transmittal, please contact me.Very truly yours, RGC:GCS:ct Attachment R.G.COCKRELL Manager, Engineering Division cc: John Ward, Chairman, AIF Committee on Reactor Licensing and Safety L.S.Sandlin, WPPSS, Manager Project Planning and Measurement ATMS COST ESTIMATE FOR MiRP-2 This document summarizes the cos imoact for five levels of fixes=or ATMS if applied to MPPSS Nuc;ear Projec Ho.2.Basic assumptions relating to the ATMS'fixes are'.dentified alorg with an out',ine of the-:ve levels wh:ch provide the basis-:or the cost estimate.The five levels outlined def":ne a spec.rum of arbitrary and possible fixes ranging from justifying exist".'rg designs to an ultra-conservative'it'.ga
| | I and members of my staff appreciated the opportunity to meet with you and your staff in conjunc'tion with other industry representatives on December 6 to discuss ATWS cost estimates. We are of the opinion that the exchange was very beneficial and provided a better understanding of the impact of various ATWS fixes for all concerned. |
| '.on sys"em design per NUREG-0460.
| | As a result of our involvement in the ATWS issue over the past several months, we have developed the attached cost estimates for various levels of system modifications to accommodate an ATWS event. As we noted in our presentation to the ACRS Subcommittee on ATWS in October, we consider ATWS to be a Licensing issue and not a plant safety concern. |
| The outl";ne':n no way'.mplies thai.what is'.nc'.ucted in each~evel provides an opt",mum level of f-;x, or that the fix is necessary, i.e., the levels are frameworks from which to illus-trate potential costs and schedule impacts ,or the Mf(P-2 plant.The costs provided are to.al costs which MPPSS estimates would incur for the various levels.The total est'.mated cost for each level is divided into two categor'"'.es
| | The attached cost estimates are based on our interpretation of what may be requested by the staff. to satisfy your concerns regarding ATWS. The levels we have addressed include the 13 items contained in your November 15 letter to the Atomic Industrial Forum (Mr. John Ward, Chairman, Committee on Reactor Licensing and Safety). We have not independently addressed each item of your letter, but have instead attempted to incorporate them into systems which cover a spectrum of fixes ranging from justification of the existing design to an ultra-conservative mitigation system per NUREG-0460. All assumptions, definitions and the overall bases for cost estimates are included in the attachment. |
| -direct cos-;s and ot;ier cost.Oirect costs include materials, insta'lation and A/E enginee.ina to ins all each fix.They are engineering estimates not detailed con truciion estimates. | | Should you desire further information regarding our cost estimating methods, we would be pleased to discuss the subject with you, or to cooperate with the AIF in preparing an industry presentation on cost estimating methods. |
| General Electr c's costs for materials and front-end engineer ng for each level of fix is included in the direct costs as materia,'s".
| | 7901160102 |
| The other incremental costs include the following: | | |
| e Construction Management (unique to MHP-2)o Owner'.s Cost (startup and testing, safety and licensing, engineering, project management, quality assur ance, insurance, proper y taxes)o Contingency (on direct cost, construction management, owner's cost)o Escalation (on d:rec.cost, construction management, contingency) o Sales Tax (direct cost, escalation, contingency, cons ruction.managemen-)
| | Dr. R. J. Mattson December 18, 1978 EDM-RGC-78-356 Page Two We trust that the attached information will be of use to you in evalu-ating the costs of ATWS. Should you have any questions regarding our transmittal, please contact me. |
| s Financing and.'nterest During Construction The total estimated cost does not nclude any costs associated with fuel, delay or replacement power, operation and ma.'ntenance, or system cleanup costs due to inadvertent tr''ps of au omated s.andby liquid control systems.A cost matrix is included to show where thirteen specific NRC items related to ATMS f'.xes are included':n each level.The specified NRC items.are listed in the attachment to the november 15, 1978 letter from R.J.Hattson{NRC)to 3.Mard (ALF).KDC 12/'i2/73 Basic Assumptions for ATMS Fixes 1.No other system failure other than the one causing ATWS for levels through 4.However, the initia.ing event may be a loss of offsite power.2.A two minute opera.or act'.on t;:me is used to manually start SLC pumps for level 3.3.Metweli temperatur e limitations are not exceeded for all levels.0 4.<~ax.'mum water temperature for proven quencher operation is not exceeded, i.e., no quencher test costs or levated temperatures or all levels.6.7.Compl:ance with NUREG-0460, which assumes AT'AS is a design basis acciden , requires the m":.tigation system to be safety grade-single failure p.oof, C":as LE power for level 5b.The circuitry required for initiating ATMS fixes from Level 2 through 4, inclusive, are designed with the same reliability as the mechanical port on of the SLC system!.e., not single-fa",ure proof.: Compliance with NUREG-0460 (Level 5)requires the additional assumotions of a)failure of HPCS and b)101 of NSRV failing to close.Level 5a assumes that analyses will show the 300 gpm Automatic Boron Iniection System wil".mitigate the consequences of both of the above assumptions
| | Very truly yours, R. G. COCKRELL Manager, Engineering Division RGC:GCS:ct Attachment cc: John Ward, Chairman, AIF Committee on Reactor Licensing and Safety L. S. Sandlin, WPPSS, Manager Project Planning and Measurement |
| .~evel 5b assumes that the 300 gpm AB1 may not mitigate"he consequ nces of these two ultra-conservative assumptions. | | |
| MNP-2 LEVEL OEFINITIONS Level 1: 'a~b.C.Justify Existing gesign Tighter operational limits on the condensate storage tank to allow for more than'.35,000 gallons minimum for RCIC/HPCS usage.Some additional contro'.room information (e.g.alarms)Engineering ana',ysis Level 2: Imoroved Control-Alternate Reactor Shutdown System (ARSS)a.C.Two additional reactor low level and two additional reactor high pressure sensors o the same auality as those used for the Reactor Protection Sys".em (RPS)but independent of RPS.The additional
| | ATMS COST ESTIMATE FOR MiRP-2 This document summarizes the cos imoact for five levels of fixes |
| -:.nst: umentat-:.on vill!initiate a Recirculation Pump Trip (RPT)using a one out o", trio Niice logic.The RPT';=-equivalent to the Mon;:cello design.ALAS Rod Insertion (ARI)wi":1 be initiated by the above circuitry to vent the a.'r scram heade!using two additional solenoid valves.ARI is qualif':ed to rEEE-279, i971.Level 3: Level 2 P'.us Mitigation (Manual 86 gpm SLC)a.b.C.d.ARSS with Monticello RPT Two existing 43 gpm SLC pumps with a second suction line from the SLC tank and a second injection point (jet pump instrumen-tation 1.:ne)added.The SLG pumps will be automatically provided with power from the emergency d"diesel after a loss of offsite power.Switch will be changed to allow both pumps to start s multaneously.
| | =or ATMS if applied to MPPSS Nuc;ear Projec Ho. 2. Basic assumptions relating to the ATMS'fixes are '.dentified alorg with an out',ine of the |
| Revision of procedures and training of operators for manual initiation of SLC pumps.Feedwater pump trip initiated by ARSS.Level 4: Level 2 Plus Mit" gation (Automatic 86 gpm SLC)a 0 C.d.e.ARSS wi th Monticel'.o RPT Two existing 43 gpm SLC pumps with a second suction line from:he SLC tank and a second inject:on po nt (jet pump instru-mentation line)added.The pumos will be automatically started by ARSS circ'itry.-eedwater oump tr'.p initiated by ARSS.RCIC/HPCS initiated by ARSS.Analysis for modi f'cation o, low level and low pr essure MSIV set points.
| | -:ve levels wh:ch provide the basis -:or the cost estimate. |
| Level 5a: Mitigation System-300 gpm Automatic Boron Injection (ABI)System a.c~d.e.f.Four addit:onal reactor low level and four additional high pressure sensors to orovice two redundant trains of auto-matic',og'.c and satisfy NVREG-0460 criteria.A RPT corno'lying with crit"ria of tel R~G-0460 will require additional trip coils to trip;OC breakers, wh'.ch i(ill cut power from both normal powe.supply and the low frequency mo-or generators.
| | The five levels outlined def":ne a spec.rum of arbitrary and possible fixes ranging from justifying exist".'rg designs to an ultra-conservative'it'.ga |
| Four 150 gpm SLC pumps, 300 gpm per train, each pumo w th seoara.e suction l.ine from Si C tank.The second injection po'nt (HPCS',ine)will be as close to the reactor vessel as Oosslb~e.~eedwater pump f'p initiated by ASS circuitry. | | '.on sys"em design per NUREG-0460. The outl";ne ':n no way '.mplies thai. what is '.nc'.ucted in each ~evel provides an opt",mum level of f-;x, or that the fix is necessary, i.e., the levels are frameworks from which to illus-trate potential costs and schedule impacts ,or the Mf(P-2 plant. |
| HPCSfRCIC initiate~by A;~iS circu.ry.ARilS'Rod Inse&";on qualif',ed to IEE>>:-279, 1971 and initiated by ASS c.'rcuf try.Level 5b: Level 5a with Additional High Pressure Makeup and Heat Sink a~C.d.Level Sa Soecial ATMS Makeup (SAM)equivalent to HPCS Suppression Poo'i Interim Cooling (SPIC)equivalent to additional RHR system along with heat sink.Qiesel generators to supply emergency power for ABI, SAM, and SPIC. | | The costs provided are to .al costs which MPPSS estimates would incur for the various levels. The total est'.mated cost for each level is divided into two categor'"'.es - direct cos-;s and ot;ier cost . Oirect costs include materials, insta'lation and A/E enginee. ina to ins estimates not detailed con truciion estimates. |
| ATv!S Cost Matrix The following table identifies where, by means of an (x), the cost of each NRC item is llsed in costing GU each cf the five levels of, ixes for ATMS.NRC Items Level 2 A&iS F',xes (2)Level 3 Level 4 Level 5 1 2 3 5 6 8 9 10 11 12 13 NA NA NA NA NA NA NA NA HA NA NA NA NA NA NA NA NA NA NA NA (1)NRC items refers to the Items in the attachment to letter from R.J.4!attson (HRC)to J.Mard (A';"-), dated November 15, 1978.(2)The five levels of ASS ixes are outlined on the attached sheets. | | all each fix. They are engineering General Electr c's costs for materials and front-end engineer ng for each level of fix is included in the direct costs as materia,'s". |
| ATWS Cost/Schedule Summar Level Oesian, Procure 5 Install Total Estimated Cost*5b 7-10 months 9-12 months 9 12 mont 18-24 months 36-42 mon hs 42-~8 months 0.5M 1.3M S 2.5M 5 4.0M S 29.4M)150M~Note e Ho delay/downtime costs included for all of the above.o"No delay/downtime costs included, however, instal'.ation costs assume installation is after lant startuo.o All assume fix is applied to an as-built (or operating) plant.e No operation/maintenance costs included for any of the above.o iso costs included.or system cleanup due to inadvert nt trips of Automatic Standby Liquid Control Systems. | | The other incremental costs include the following: |
| ASS MNP-2 Level 1 Surmarv FPC Code 10 Structures and Improvements 20 Peactor Plant Equipment 0 Turbo-Generator Units 40 Accessory Electrical Equipment 50 Misc.Power Plant Equipmen" 60 Station Equipment and Switchyard 70 Distributable Directs A/E Engineering Design Total Direct Cost Totals S-0--0--0-55,000 45,000-0--0-60,000 160,000 Construction Management A/E Portion Owner Portion Owner's Cost Contingency Escalation Sales Tax Financing and Interest During Construction Total Estimated Cost 56,000 50,000 40,000 122,300 18,800 23,200 17,400 487,700 Excludes Fuel Costs 8 Replacement Power Excludes Opera ion and Maintenance Costs ASS MNP-2 Level 2~Soaaa:r FPC Code Totals 10 Structures and Improvements 20 Reactor Plant Equipment 30:urbo-Generator L~nits~TO Accessory E',ectrica'quipment 50 Risc.Power Plant Equipment 60 Station Equipmen and Sw''tchyard 70 Oistributable Oirects A/E Engineering Design Total Direct Costs$-0-50,000-0-250,000-0-0-0-180,000 480,000 Construction management A/E Portion Owner Portion Owner's Cost Contingency Escalation Sales Tax Financ".'ng and Interest During Construction Total Est",'mated Cost 100,000 90,000 70,000.296,000 68,000 57,<00 67,100 1,228,500 Excludes Fuel Costs and Replacement Power Excludes Operation and Maintenance Costs ASS MNP-2 Level 3 SL'HOARY FPC Code Tota Is 10 Structures 5 Improvements 20 Peactor Plant Equipment 30 Turbo-Generator L~nits 40 Accessory Electrical | | e Construction Management (unique to MHP-2) o Owner'.s Cost (startup and testing, safety and licensing, engineering, project management, quality assur ance, insurance, proper y taxes) o Contingency (on direct cost, construction management, owner's cost) o Escalation (on d:rec. cost, construction management, contingency) o Sales Tax (direct cost, escalation, contingency, cons ruction. |
| ~quipment 50 Misc.Power Plan.Equipment 60 Sta+":on Lquipmen". | | managemen-) |
| Switc,",yard 70 Ois:r-butab!e 0'.rects-A 8"=.ngineer',ng Oesfcn Total 0 rect Cost S-0-350,000 250,000-0-0 360,000 960,000 Construction Management A 5 E Por+ion Owner Port-Ion Owner Cost Contingency Esca!at.'on Sa!es Tax Financing 8 Interest Ourino Construction Total Estimated Cos.200,000 180,000 135,000 590,000 150 100''~'00 14S,700 2, a<78,900 Excludes Fuel Cos s 5 Reol acement Power=xcludes Operation 5 bia'ntenance Costs ATMS MNP-2'v~4" SUf~iARY FPC Code 10 Structures | | s Financing and .'nterest During Construction The total estimated cost does not nclude any costs associated with fuel, delay or replacement power, operation and ma.'ntenance, or system cleanup costs due to inadvertent tr''ps of au omated s.andby liquid control systems. |
| &Improvements 20 Reac or Plan+Equipment 30 ,urbo-Generator Limni.s 40 Accessory E',ec+rical Equipment 50 Risc.Power Plane Equioment 60 Shat",'on Equipment&Sw tchyard 70 Ois.r." utable Oirects-A&E Engineering Tota'.Oirect Cost TOTALS$-0 400,000 600,000-0--0--0-600,000 1,600,000 Construction Management A&E Portion Owner Portion Owners Cos+'ontingency Escalation Sales Tax Financing&Interest During Construction ,otal Estimated Cost 300,000 270,000 200,000 940,000 242,400'.84,700 2<0,100 3,977,000 Excludes Fuel Costs&Replacement Power Excludes Goer ation&Maintenance Costs*Scheduled Shutdown After Fuel Loading ATMS uNP-2"Level 5a.SOY>lARY FPC Code TOTALS 10 Structures 5 Imorovements 20 Reactor Plant Equ.pment 30 Turbo-Generator Units 40 Accessory Electrica: | | A cost matrix is included to show where thirteen specific NRC items related to ATMS f'.xes are included ':n each level. The specified NRC items. |
| Eouipment 50 Misc.Power P'.ant Equipment 60 Station Equipment 5 Switchyard 70 Oistributable Oirects-A u'Eng',neering Des.'gn Total Oirec Cos S 40,000 3,000,000-0-3,400,000 60,000-0-3 000 000 9,500,000 Construction Management A 8 E Portion Owner Por;i or, Owner Cost Contingency Escalation Sales ax F',nancing 8 Interest During Construction Total Es mated Cost 2,400,000 2,160,000 1,600,000 6,265;000 4,222,000 1,357,000 1,837,000 29,34',000 Excludes Fuel Costs 5 Replacement Power Excludes Ooeration 8 iNaintenance Costs*Scheduled Snut"own after Fuel Loading ATMS'ANP-2~ove'b*SUl<l<ARY 10 Structures 8 Improvements 20 Reactor Plant Equipment 30 Turbo.-Generator L'ni ts Accessory E".ectr.'cal Equipment Misc.Powe.Plant Equipment Station Equipment A Switchyard Oistributable Oirects A 8 E Eng'neering | | are listed in the attachment to the november 15, 1978 letter from R. J. Hattson {NRC) to 3. Mard (ALF). |
| '3esign Total 0";rect Cos-TOTALS$7,345,000 30,000,000 1,423,00Q 235,000 13,100,000 52,103,000 Construction Management A~~"=Portion Owners Portion Owners Cost Contingency Escalation Sales Tax Financing 8 Interest during Construction Total Es imated Cost g,800,000 8,820,000 5,410,000 30,440,000 25,000,000 6,826,00Q'.1,75o,000 150,155,000 Excludes Fuel Costs 8 Repl acement Power Excludes Operation 5 Maintenance Costs*Scheduled Shutdown after Fuel Loading-12-KQC 12/12/78 | | KDC 12/'i2/73 |
| *U.S.GOVERNMENT PRINTING OFFICEI l97~0.978~~~R.G.Cockrell, Mgr.Engineering Division Wash.Pub.Power Supply Sys.DATE OF OOCUMENT 12/18/78 LTR MEMO: OATE RECEIVED 12/26/78 REPORT'SS:131 OTHER TO Roger J.Mattson, Director Division of Systems Safety ONRR ORIG CC: OTHER.'CTION NECESSARY (g CONCURRENCE P CATE ANSWEREO NO ACTION NFCESSARY Q COMMENT 0 SYI 1/10/79 CLASSIF OESCRIPTION, IMuu SF UnCIFHdieaI POST OFFICE REG, NO.'ILE CODE ATWS WPPSS No.2 REFERREO TO GATE RECEIVEO EY GATE ATWS Cost Estimates-WPPSS Nuc.Project No.2 ENCLOSURES'istributed to: E.Case R.Mattson D.Bunch R.Fraley, ACRS P.Boehnert, ACR T.Novak (21)V.Stello R.Tedesco REMARKS Return original yellow ticket and copy of incoming w/copy of reply to Ann Haikalis.'.
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| Schroeder S.Hanauer M.Ernst B.J.Youngblood U.S.NUCLEAR REGULATORY COMMISSION A.Thadani RSB File Centra Docket F NRC PDR MAIL CONTROL FORM le 79ox~6o~o2}}
| | Basic Assumptions for ATMS Fixes |
| | : 1. No other system failure other than the one causing ATWS for levels through 4. However, the initia.ing event may be a loss of offsite power. |
| | : 2. A two minute opera. or act'.on t;:me is used to manually start SLC pumps for level 3. |
| | : 3. Metweli temperatur 0 |
| | e limitations are not exceeded for all levels. |
| | : 4. <~ax.'mum water temperature for proven quencher operation is not exceeded, i.e., no quencher test costs or levated temperatures or all levels. |
| | Compl:ance with NUREG-0460, which assumes AT'AS is a design basis acciden , requires the m":.tigation system to be safety grade-single failure p. oof, C":as LE power for level 5b. |
| | : 6. The circuitry required for initiating ATMS fixes from Level 2 through 4, inclusive, are designed with the same reliability as the mechanical port on of the SLC system !.e., not single-fa",ure proof.: |
| | : 7. Compliance with NUREG-0460 (Level 5) requires the additional assumotions of a) failure of HPCS and b) 101 of NSRV failing to close. Level 5a assumes that analyses will show the 300 gpm Automatic Boron Iniection System wil". mitigate the consequences of both of the above assumptions . ~ |
| | evel 5b assumes that the 300 gpm AB1 may not mitigate "he consequ nces of these two ultra-conservative assumptions. |
| | |
| | MNP-2 LEVEL OEFINITIONS Level 1: Justify Existing gesign |
| | 'a ~ Tighter operational limits on the condensate storage tank to allow for more than '.35,000 gallons minimum for RCIC/HPCS usage. |
| | : b. Some additional contro'. room information (e.g. alarms) |
| | C. Engineering ana',ysis Level 2: Imoroved Control - Alternate Reactor Shutdown System (ARSS) |
| | : a. Two additional reactor low level and two additional reactor high pressure sensors o the same auality as those used for the Reactor Protection Sys".em (RPS) but independent of RPS. |
| | The additional -:.nst: umentat-:.on vill ! initiate a Recirculation Pump Trip (RPT) using a one out o", trio Niice logic. The RPT |
| | ';=- equivalent to the Mon ;:cello design. |
| | C. ALAS Rod Insertion (ARI) wi":1 be initiated by the above circuitry to vent the a.'r scram heade! using two additional solenoid valves. |
| | ARI is qualif':ed to rEEE-279, i971 . |
| | Level 3: Level 2 P'.us Mitigation (Manual 86 gpm SLC) |
| | : a. ARSS with Monticello RPT |
| | : b. Two existing 43 gpm SLC pumps with a second suction line from the SLC tank and a second injection point (jet pump instrumen-tation 1.:ne) added. The SLG pumps will automatically provided be with power from the emergency d"diesel after a loss of offsite power. Switch will be changed to allow both pumps to start s multaneously. |
| | C. Revision of procedures and training of operators for manual initiation of SLC pumps. |
| | : d. Feedwater pump trip initiated by ARSS. |
| | Level 4: Level 2 Plus Mit"gation (Automatic 86 gpm SLC) a 0 ARSS wi th Monticel'.o RPT Two existing 43 gpm SLC pumps with a second suction line from |
| | :he SLC tank and a second inject:on po nt (jet pump instru-mentation line) added. The pumos will be automatically started by ARSS circ 'itry. |
| | C. -eedwater oump tr'.p initiated by ARSS. |
| | : d. RCIC/HPCS initiated by ARSS. |
| | : e. Analysis for modi f'cation o, low level and low pr essure MSIV set points. |
| | |
| | Level 5a: Mitigation System - 300 gpm Automatic Boron Injection (ABI) System |
| | : a. Four addit:onal reactor low level and four additional high pressure sensors to orovice two redundant trains of auto-matic ',og'.c and satisfy NVREG-0460 criteria. |
| | A RPT corno'lying with crit"ria of tel R~G-0460 will require additional trip coils to trip;OC breakers, wh'.ch i(ill cut power from both normal powe. supply and the low frequency mo-or generators. |
| | c ~ Four 150 gpm SLC pumps, 300 gpm per train, each pumo w th seoara .e suction l.ine from Si C tank. The second injection po'nt (HPCS ',ine) will be as close to the reactor vessel as Oosslb~e. |
| | : d. ~eedwater pump f'p initiated by ASS circuitry. |
| | : e. HPCSfRCIC initiate~ by A;~iS circu. ry. |
| | : f. ARilS 'Rod Inse&";on qualif',ed to IEE>>:-279, 1971 and initiated by ASS c.'rcuf try. |
| | Level 5b: Level 5a with Additional High Pressure Makeup and Heat Sink a ~ Level Sa Soecial ATMS Makeup (SAM) equivalent to HPCS C. Suppression Poo'i Interim Cooling (SPIC) equivalent to additional RHR system along with heat sink. |
| | : d. Qiesel generators to supply emergency power for ABI, SAM, and SPIC. |
| | |
| | ATv!S Cost Matrix The following table identifies where, by means of an (x), the cost of each NRC item is llsed in costing GU each cf the five levels of, ixes for ATMS. |
| | NRC A&iS F',xes (2) |
| | Items Level 2 Level 3 Level 4 Level 5 1 |
| | 2 NA HA NA 3 |
| | 5 6 |
| | NA NA NA NA NA 8 NA NA NA NA 9 NA NA NA NA 10 NA NA NA NA 11 12 13 (1) NRC items refers to the Items in the attachment to letter from R. J. 4!attson (HRC) to J. Mard (A';"-), dated November 15, 1978. |
| | (2) The five levels of ASS ixes are outlined on the attached sheets. |
| | |
| | ATWS Cost/Schedule Summar Level Oesian, Procure 5 Install Total Estimated Cost 7-10 months 0.5M 9-12 months 1 .3M 9 12 mont S 2.5M 18-24 months 5 4.0M 36-42 mon hs S 29.4M |
| | *5b 42-~8 months )150M |
| | ~Note e Ho delay/downtime costs included for all of the above. |
| | o "No delay/downtime costs included, however, instal'.ation costs assume installation is after lant startuo. |
| | o All assume fix is applied to an as-built (or operating) plant. |
| | e No operation/maintenance costs included for any of the above. |
| | o iso costs included .or system cleanup due to inadvert nt trips of Automatic Standby Liquid Control Systems. |
| | |
| | ASS MNP-2 Level 1 Surmarv FPC Code Totals 10 Structures and Improvements S 20 Peactor Plant Equipment 0 Turbo-Generator Units 40 Accessory Electrical Equipment 55,000 50 Misc. Power Plant Equipmen" 45,000 60 Station Equipment and Switchyard 70 Distributable Directs A/E Engineering Design 60,000 Total Direct Cost 160,000 Construction Management A/E Portion 56,000 Owner Portion 50,000 Owner's Cost 40,000 Contingency 122,300 Escalation 18,800 Sales Tax 23,200 Financing and Interest During Construction 17,400 Total Estimated Cost 487,700 Excludes Fuel Costs 8 Replacement Power Excludes Opera ion and Maintenance Costs |
| | |
| | ASS MNP-2 Level 2 |
| | ~Soaaa:r FPC Code Totals 10 Structures and Improvements $ 20 Reactor Plant Equipment 50,000 30 :urbo-Generator L~nits ~TO Accessory E',ectrica'quipment 250,000 50 Risc. Power Plant Equipment 60 Station Equipmen and Sw''tchyard 0 70 Oistributable Oirects A/E Engineering Design 180,000 Total Direct Costs 480,000 Construction management A/E Portion 100,000 Owner Portion 90,000 Owner's Cost 70,000 . |
| | Contingency 296,000 Escalation 68,000 Sales Tax 57,<00 Financ".'ng and Interest During Construction 67,100 Total Est",'mated Cost 1,228,500 Excludes Fuel Costs and Replacement Power Excludes Operation and Maintenance Costs |
| | |
| | ASS MNP-2 Level 3 SL'HOARY FPC Code Tota Is 10 Structures 5 Improvements S 20 Peactor Plant Equipment 350,000 30 Turbo-Generator L~nits 40 Accessory Electrical ~quipment 250,000 50 Misc. Power Plan . Equipment 60 Sta+":on Lquipmen". Switc,",yard 0 70 Ois:r- butab!e 0'.rects A 8 "= .ngineer',ng Oesfcn 360,000 Total 0 rect Cost 960,000 Construction Management A 5 E Por+ion 200,000 Owner Port-Ion 180,000 Owner Cost 135,000 Contingency 590,000 Esca!at.'on 150 100 Sa!es Tax ''~ '00 Financing 8 Interest Ourino Construction 14S,700 Total Estimated Cos. 2, a<78,900 Excludes Fuel Cos s 5 Reol acement Power |
| | =xcludes Operation 5 bia'ntenance Costs |
| | |
| | ATMS MNP-2 |
| | 'v ~ 4" SUf~iARY FPC Code TOTALS 10 Structures & Improvements $ -0 20 Reac or Plan+ Equipment 400,000 30 ,urbo-Generator Limni .s 40 Accessory E',ec+rical Equipment 600,000 50 Risc. Power Plane Equioment 60 Shat",'on Equipment & Sw tchyard 70 Ois.r." utable Oirects A & E Engineering 600,000 Tota'. Oirect Cost 1,600,000 Construction Management A & E Portion 300,000 Owner Portion 270,000 Owners 200,000 Cos+'ontingency 940,000 Escalation 242,400 Sales Tax '.84,700 Financing & Interest During Construction 2<0,100 |
| | ,otal Estimated Cost 3,977,000 Excludes Fuel Costs & Replacement Power Excludes Goer ation & Maintenance Costs |
| | *Scheduled Shutdown After Fuel Loading |
| | |
| | ATMS uNP-2 "Level 5a. |
| | SOY>lARY FPC Code TOTALS 10 Structures 5 Imorovements S 40,000 20 Reactor Plant Equ.pment 3,000,000 30 Turbo-Generator Units 40 Accessory Electrica: Eouipment 3,400,000 50 Misc. Power P'.ant Equipment 60,000 60 Station Equipment 5 Switchyard 70 Oistributable Oirects A u' Eng',neering Des.'gn 3 000 000 Total Oirec Cos 9,500,000 Construction Management A 8 E Portion 2,400,000 Owner Por;i or, 2,160,000 Owner Cost 1,600,000 Contingency 6,265;000 Escalation 4,222,000 Sales ax 1,357,000 F',nancing 8 Interest During Construction 1,837,000 Total Es mated Cost 29,34',000 Excludes Fuel Costs 5 Replacement Power Excludes Ooeration 8 iNaintenance Costs |
| | *Scheduled Snut"own after Fuel Loading |
| | |
| | ATMS 'ANP-2 |
| | ~ ove'b* |
| | SUl<l <ARY TOTALS 10 Structures 8 Improvements $ 7,345,000 20 Reactor Plant Equipment 30,000,000 30 Turbo.-Generator L'ni ts Accessory E".ectr.'cal Equipment 1,423,00Q Misc. Powe. Plant Equipment 235,000 Station Equipment A Switchyard Oistributable Oirects A 8 E Eng'neering '3esign 13,100,000 Total 0";rect Cos- 52,103,000 Construction Management |
| | "= Portion A ~~ |
| | g,800,000 Owners Portion 8,820,000 Owners Cost 5,410,000 Contingency 30,440,000 Escalation 25,000,000 Sales Tax 6,826,00Q Financing 8 Interest during Construction '.1,75o,000 Total Es imated Cost 150,155,000 Excludes Fuel Costs 8 Repl acement Power Excludes Operation 5 Maintenance Costs |
| | *Scheduled Shutdown after Fuel Loading KQC 12/12/78 |
| | |
| | *U. S. GOVERNMENT PRINTING OFFICEI l97~0.978 |
| | ~ ~ ~ |
| | DATE OF OOCUMENT OATE RECEIVED R.G. Cockrell, Mgr. |
| | Engineering Division 12/18/78 12/26/78REPORT'SS:131 Wash. Pub. Power Supply Sys. LTR MEMO: OTHER TO ORIG CC: |
| | Roger J. Mattson, Director OTHER.'CTION Division of Systems Safety NECESSARY (g CONCURRENCE P CATE ANSWEREO ONRR NO ACTION NFCESSARY Q COMMENT 0 SYI 1/10/79 CLASSIF REG, NO.'ILE POST OFFICE CODE ATWS WPPSS No. 2 OESCRIPTION, IMuu SF UnCIFHdieaI REFERREO TO GATE RECEIVEO EY GATE ATWS Cost Estimates- D. Bunch WPPSS Nuc. Project No. 2 ENCLOSURES'istributed to: R. Fraley, ACRS (21) |
| | E. Case P. Boehnert, ACR R. Mattson T. Novak V. Stello R. Tedesco Schroeder A. Thadani REMARKS to Ann Haikalis.'. |
| | Return original yellow ticket and copy of incoming w/copy of reply S. Hanauer M. Ernst B.J.Youngblood RSB Centra File NRC PDR Docket F le U. S. NUCLEAR REGULATORY COMMISSION MAIL CONTROL FORM 79ox ~6o ~o2}} |
|
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle ML17285B3301990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521 ML17285B3251990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 ML17285B2931990-05-29029 May 1990 Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons ML17285B2861990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 ML17285B2881990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl ML17285B2471990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS ML17285B2741990-04-26026 April 1990 Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered ML17285B2321990-04-25025 April 1990 Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17 ML17285B2121990-04-19019 April 1990 Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program ML17285B2221990-04-16016 April 1990 Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed ML17285B1881990-04-11011 April 1990 Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals ML17285B1821990-04-0505 April 1990 Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively ML17285B1741990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 ML20012F6141990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML17285B2041990-03-29029 March 1990 Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992 ML17285B1421990-03-29029 March 1990 Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312 ML17285B1381990-03-29029 March 1990 Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results ML17285B1131990-03-28028 March 1990 Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl ML17285B1331990-03-23023 March 1990 Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps ML17285B1311990-03-21021 March 1990 Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception ML17285B1291990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys ML17285B1171990-03-19019 March 1990 Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990 ML17285B1121990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement ML17285B0931990-03-0202 March 1990 Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators ML17285B0741990-03-0202 March 1990 Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide ML17285B0861990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML17285B0581990-02-26026 February 1990 Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm. 1990-08-27
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Washington Public Power Supply'System A JOINT OPERATING AGENCY d~4 P. O. BOX 958 3000 GCO. WACHINCTON WAT RICHI.AND, WASHINCTON 99352 PHONC (509) 375 5000
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December 18, 1978 EDM-RGC-78-356 Dr. R. J. Mattson, Director Division of Systems Safety U. S. Nuclear Regulatory Commission Washington D. C. 20555
Subject:
ATWS COST ESTIMATES-WPPSS NUCLEAR PROJECT NO. 2
Dear Dr. Mattson:
I and members of my staff appreciated the opportunity to meet with you and your staff in conjunc'tion with other industry representatives on December 6 to discuss ATWS cost estimates. We are of the opinion that the exchange was very beneficial and provided a better understanding of the impact of various ATWS fixes for all concerned.
As a result of our involvement in the ATWS issue over the past several months, we have developed the attached cost estimates for various levels of system modifications to accommodate an ATWS event. As we noted in our presentation to the ACRS Subcommittee on ATWS in October, we consider ATWS to be a Licensing issue and not a plant safety concern.
The attached cost estimates are based on our interpretation of what may be requested by the staff. to satisfy your concerns regarding ATWS. The levels we have addressed include the 13 items contained in your November 15 letter to the Atomic Industrial Forum (Mr. John Ward, Chairman, Committee on Reactor Licensing and Safety). We have not independently addressed each item of your letter, but have instead attempted to incorporate them into systems which cover a spectrum of fixes ranging from justification of the existing design to an ultra-conservative mitigation system per NUREG-0460. All assumptions, definitions and the overall bases for cost estimates are included in the attachment.
Should you desire further information regarding our cost estimating methods, we would be pleased to discuss the subject with you, or to cooperate with the AIF in preparing an industry presentation on cost estimating methods.
7901160102
Dr. R. J. Mattson December 18, 1978 EDM-RGC-78-356 Page Two We trust that the attached information will be of use to you in evalu-ating the costs of ATWS. Should you have any questions regarding our transmittal, please contact me.
Very truly yours, R. G. COCKRELL Manager, Engineering Division RGC:GCS:ct Attachment cc: John Ward, Chairman, AIF Committee on Reactor Licensing and Safety L. S. Sandlin, WPPSS, Manager Project Planning and Measurement
ATMS COST ESTIMATE FOR MiRP-2 This document summarizes the cos imoact for five levels of fixes
=or ATMS if applied to MPPSS Nuc;ear Projec Ho. 2. Basic assumptions relating to the ATMS'fixes are '.dentified alorg with an out',ine of the
-:ve levels wh:ch provide the basis -:or the cost estimate.
The five levels outlined def":ne a spec.rum of arbitrary and possible fixes ranging from justifying exist".'rg designs to an ultra-conservative'it'.ga
'.on sys"em design per NUREG-0460. The outl";ne ':n no way '.mplies thai. what is '.nc'.ucted in each ~evel provides an opt",mum level of f-;x, or that the fix is necessary, i.e., the levels are frameworks from which to illus-trate potential costs and schedule impacts ,or the Mf(P-2 plant.
The costs provided are to .al costs which MPPSS estimates would incur for the various levels. The total est'.mated cost for each level is divided into two categor'"'.es - direct cos-;s and ot;ier cost . Oirect costs include materials, insta'lation and A/E enginee. ina to ins estimates not detailed con truciion estimates.
all each fix. They are engineering General Electr c's costs for materials and front-end engineer ng for each level of fix is included in the direct costs as materia,'s".
The other incremental costs include the following:
e Construction Management (unique to MHP-2) o Owner'.s Cost (startup and testing, safety and licensing, engineering, project management, quality assur ance, insurance, proper y taxes) o Contingency (on direct cost, construction management, owner's cost) o Escalation (on d:rec. cost, construction management, contingency) o Sales Tax (direct cost, escalation, contingency, cons ruction.
managemen-)
s Financing and .'nterest During Construction The total estimated cost does not nclude any costs associated with fuel, delay or replacement power, operation and ma.'ntenance, or system cleanup costs due to inadvertent trps of au omated s.andby liquid control systems.
A cost matrix is included to show where thirteen specific NRC items related to ATMS f'.xes are included ':n each level. The specified NRC items.
are listed in the attachment to the november 15, 1978 letter from R. J. Hattson {NRC) to 3. Mard (ALF).
KDC 12/'i2/73
Basic Assumptions for ATMS Fixes
- 1. No other system failure other than the one causing ATWS for levels through 4. However, the initia.ing event may be a loss of offsite power.
- 2. A two minute opera. or act'.on t;:me is used to manually start SLC pumps for level 3.
- 3. Metweli temperatur 0
e limitations are not exceeded for all levels.
- 4. <~ax.'mum water temperature for proven quencher operation is not exceeded, i.e., no quencher test costs or levated temperatures or all levels.
Compl:ance with NUREG-0460, which assumes AT'AS is a design basis acciden , requires the m":.tigation system to be safety grade-single failure p. oof, C":as LE power for level 5b.
- 6. The circuitry required for initiating ATMS fixes from Level 2 through 4, inclusive, are designed with the same reliability as the mechanical port on of the SLC system !.e., not single-fa",ure proof.:
- 7. Compliance with NUREG-0460 (Level 5) requires the additional assumotions of a) failure of HPCS and b) 101 of NSRV failing to close. Level 5a assumes that analyses will show the 300 gpm Automatic Boron Iniection System wil". mitigate the consequences of both of the above assumptions . ~
evel 5b assumes that the 300 gpm AB1 may not mitigate "he consequ nces of these two ultra-conservative assumptions.
MNP-2 LEVEL OEFINITIONS Level 1: Justify Existing gesign
'a ~ Tighter operational limits on the condensate storage tank to allow for more than '.35,000 gallons minimum for RCIC/HPCS usage.
- b. Some additional contro'. room information (e.g. alarms)
C. Engineering ana',ysis Level 2: Imoroved Control - Alternate Reactor Shutdown System (ARSS)
- a. Two additional reactor low level and two additional reactor high pressure sensors o the same auality as those used for the Reactor Protection Sys".em (RPS) but independent of RPS.
The additional -:.nst: umentat-:.on vill ! initiate a Recirculation Pump Trip (RPT) using a one out o", trio Niice logic. The RPT
';=- equivalent to the Mon ;:cello design.
C. ALAS Rod Insertion (ARI) wi":1 be initiated by the above circuitry to vent the a.'r scram heade! using two additional solenoid valves.
ARI is qualif':ed to rEEE-279, i971 .
Level 3: Level 2 P'.us Mitigation (Manual 86 gpm SLC)
- a. ARSS with Monticello RPT
- b. Two existing 43 gpm SLC pumps with a second suction line from the SLC tank and a second injection point (jet pump instrumen-tation 1.:ne) added. The SLG pumps will automatically provided be with power from the emergency d"diesel after a loss of offsite power. Switch will be changed to allow both pumps to start s multaneously.
C. Revision of procedures and training of operators for manual initiation of SLC pumps.
- d. Feedwater pump trip initiated by ARSS.
Level 4: Level 2 Plus Mit"gation (Automatic 86 gpm SLC) a 0 ARSS wi th Monticel'.o RPT Two existing 43 gpm SLC pumps with a second suction line from
- he SLC tank and a second inject:on po nt (jet pump instru-mentation line) added. The pumos will be automatically started by ARSS circ 'itry.
C. -eedwater oump tr'.p initiated by ARSS.
- d. RCIC/HPCS initiated by ARSS.
- e. Analysis for modi f'cation o, low level and low pr essure MSIV set points.
Level 5a: Mitigation System - 300 gpm Automatic Boron Injection (ABI) System
- a. Four addit:onal reactor low level and four additional high pressure sensors to orovice two redundant trains of auto-matic ',og'.c and satisfy NVREG-0460 criteria.
A RPT corno'lying with crit"ria of tel R~G-0460 will require additional trip coils to trip;OC breakers, wh'.ch i(ill cut power from both normal powe. supply and the low frequency mo-or generators.
c ~ Four 150 gpm SLC pumps, 300 gpm per train, each pumo w th seoara .e suction l.ine from Si C tank. The second injection po'nt (HPCS ',ine) will be as close to the reactor vessel as Oosslb~e.
- d. ~eedwater pump f'p initiated by ASS circuitry.
- e. HPCSfRCIC initiate~ by A;~iS circu. ry.
- f. ARilS 'Rod Inse&";on qualif',ed to IEE>>:-279, 1971 and initiated by ASS c.'rcuf try.
Level 5b: Level 5a with Additional High Pressure Makeup and Heat Sink a ~ Level Sa Soecial ATMS Makeup (SAM) equivalent to HPCS C. Suppression Poo'i Interim Cooling (SPIC) equivalent to additional RHR system along with heat sink.
- d. Qiesel generators to supply emergency power for ABI, SAM, and SPIC.
ATv!S Cost Matrix The following table identifies where, by means of an (x), the cost of each NRC item is llsed in costing GU each cf the five levels of, ixes for ATMS.
NRC A&iS F',xes (2)
Items Level 2 Level 3 Level 4 Level 5 1
2 NA HA NA 3
5 6
NA NA NA NA NA 8 NA NA NA NA 9 NA NA NA NA 10 NA NA NA NA 11 12 13 (1) NRC items refers to the Items in the attachment to letter from R. J. 4!attson (HRC) to J. Mard (A';"-), dated November 15, 1978.
(2) The five levels of ASS ixes are outlined on the attached sheets.
ATWS Cost/Schedule Summar Level Oesian, Procure 5 Install Total Estimated Cost 7-10 months 0.5M 9-12 months 1 .3M 9 12 mont S 2.5M 18-24 months 5 4.0M 36-42 mon hs S 29.4M
~Note e Ho delay/downtime costs included for all of the above.
o "No delay/downtime costs included, however, instal'.ation costs assume installation is after lant startuo.
o All assume fix is applied to an as-built (or operating) plant.
e No operation/maintenance costs included for any of the above.
o iso costs included .or system cleanup due to inadvert nt trips of Automatic Standby Liquid Control Systems.
ASS MNP-2 Level 1 Surmarv FPC Code Totals 10 Structures and Improvements S 20 Peactor Plant Equipment 0 Turbo-Generator Units 40 Accessory Electrical Equipment 55,000 50 Misc. Power Plant Equipmen" 45,000 60 Station Equipment and Switchyard 70 Distributable Directs A/E Engineering Design 60,000 Total Direct Cost 160,000 Construction Management A/E Portion 56,000 Owner Portion 50,000 Owner's Cost 40,000 Contingency 122,300 Escalation 18,800 Sales Tax 23,200 Financing and Interest During Construction 17,400 Total Estimated Cost 487,700 Excludes Fuel Costs 8 Replacement Power Excludes Opera ion and Maintenance Costs
ASS MNP-2 Level 2
~Soaaa:r FPC Code Totals 10 Structures and Improvements $ 20 Reactor Plant Equipment 50,000 30 :urbo-Generator L~nits ~TO Accessory E',ectrica'quipment 250,000 50 Risc. Power Plant Equipment 60 Station Equipmen and Swtchyard 0 70 Oistributable Oirects A/E Engineering Design 180,000 Total Direct Costs 480,000 Construction management A/E Portion 100,000 Owner Portion 90,000 Owner's Cost 70,000 .
Contingency 296,000 Escalation 68,000 Sales Tax 57,<00 Financ".'ng and Interest During Construction 67,100 Total Est",'mated Cost 1,228,500 Excludes Fuel Costs and Replacement Power Excludes Operation and Maintenance Costs
ASS MNP-2 Level 3 SL'HOARY FPC Code Tota Is 10 Structures 5 Improvements S 20 Peactor Plant Equipment 350,000 30 Turbo-Generator L~nits 40 Accessory Electrical ~quipment 250,000 50 Misc. Power Plan . Equipment 60 Sta+":on Lquipmen". Switc,",yard 0 70 Ois:r- butab!e 0'.rects A 8 "= .ngineer',ng Oesfcn 360,000 Total 0 rect Cost 960,000 Construction Management A 5 E Por+ion 200,000 Owner Port-Ion 180,000 Owner Cost 135,000 Contingency 590,000 Esca!at.'on 150 100 Sa!es Tax ~ '00 Financing 8 Interest Ourino Construction 14S,700 Total Estimated Cos. 2, a<78,900 Excludes Fuel Cos s 5 Reol acement Power
=xcludes Operation 5 bia'ntenance Costs
ATMS MNP-2
'v ~ 4" SUf~iARY FPC Code TOTALS 10 Structures & Improvements $ -0 20 Reac or Plan+ Equipment 400,000 30 ,urbo-Generator Limni .s 40 Accessory E',ec+rical Equipment 600,000 50 Risc. Power Plane Equioment 60 Shat",'on Equipment & Sw tchyard 70 Ois.r." utable Oirects A & E Engineering 600,000 Tota'. Oirect Cost 1,600,000 Construction Management A & E Portion 300,000 Owner Portion 270,000 Owners 200,000 Cos+'ontingency 940,000 Escalation 242,400 Sales Tax '.84,700 Financing & Interest During Construction 2<0,100
,otal Estimated Cost 3,977,000 Excludes Fuel Costs & Replacement Power Excludes Goer ation & Maintenance Costs
- Scheduled Shutdown After Fuel Loading
ATMS uNP-2 "Level 5a.
SOY>lARY FPC Code TOTALS 10 Structures 5 Imorovements S 40,000 20 Reactor Plant Equ.pment 3,000,000 30 Turbo-Generator Units 40 Accessory Electrica: Eouipment 3,400,000 50 Misc. Power P'.ant Equipment 60,000 60 Station Equipment 5 Switchyard 70 Oistributable Oirects A u' Eng',neering Des.'gn 3 000 000 Total Oirec Cos 9,500,000 Construction Management A 8 E Portion 2,400,000 Owner Por;i or, 2,160,000 Owner Cost 1,600,000 Contingency 6,265;000 Escalation 4,222,000 Sales ax 1,357,000 F',nancing 8 Interest During Construction 1,837,000 Total Es mated Cost 29,34',000 Excludes Fuel Costs 5 Replacement Power Excludes Ooeration 8 iNaintenance Costs
- Scheduled Snut"own after Fuel Loading
ATMS 'ANP-2
~ ove'b*
SUl<l <ARY TOTALS 10 Structures 8 Improvements $ 7,345,000 20 Reactor Plant Equipment 30,000,000 30 Turbo.-Generator L'ni ts Accessory E".ectr.'cal Equipment 1,423,00Q Misc. Powe. Plant Equipment 235,000 Station Equipment A Switchyard Oistributable Oirects A 8 E Eng'neering '3esign 13,100,000 Total 0";rect Cos- 52,103,000 Construction Management
"= Portion A ~~
g,800,000 Owners Portion 8,820,000 Owners Cost 5,410,000 Contingency 30,440,000 Escalation 25,000,000 Sales Tax 6,826,00Q Financing 8 Interest during Construction '.1,75o,000 Total Es imated Cost 150,155,000 Excludes Fuel Costs 8 Repl acement Power Excludes Operation 5 Maintenance Costs
- Scheduled Shutdown after Fuel Loading KQC 12/12/78
- U. S. GOVERNMENT PRINTING OFFICEI l97~0.978
~ ~ ~
DATE OF OOCUMENT OATE RECEIVED R.G. Cockrell, Mgr.
Engineering Division 12/18/78 12/26/78REPORT'SS:131 Wash. Pub. Power Supply Sys. LTR MEMO: OTHER TO ORIG CC:
Roger J. Mattson, Director OTHER.'CTION Division of Systems Safety NECESSARY (g CONCURRENCE P CATE ANSWEREO ONRR NO ACTION NFCESSARY Q COMMENT 0 SYI 1/10/79 CLASSIF REG, NO.'ILE POST OFFICE CODE ATWS WPPSS No. 2 OESCRIPTION, IMuu SF UnCIFHdieaI REFERREO TO GATE RECEIVEO EY GATE ATWS Cost Estimates- D. Bunch WPPSS Nuc. Project No. 2 ENCLOSURES'istributed to: R. Fraley, ACRS (21)
E. Case P. Boehnert, ACR R. Mattson T. Novak V. Stello R. Tedesco Schroeder A. Thadani REMARKS to Ann Haikalis.'.
Return original yellow ticket and copy of incoming w/copy of reply S. Hanauer M. Ernst B.J.Youngblood RSB Centra File NRC PDR Docket F le U. S. NUCLEAR REGULATORY COMMISSION MAIL CONTROL FORM 79ox ~6o ~o2