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May 17, 1982 MEMORANDPI FCR: D. Okrent, Chairman ACRS Subcommittee on Midland Plant Units 1 & 2 FROM: D. Fischer, Reactor Engineer
SUBJECT:
PRGIECT STA'IUS REPORT FOR 'IHE ACRS SUBCOtMITTEE MEETING ON MIDIAND P!Avr tNITS 1 & 2 - MAY 20-21, 1982, MIDIAND, MICHIGAN Attached is a project status report for the subject meeting. We purpose of the meeting is to review the application of Consumers Power Company for a license to operate the Midland Plant Units 1 & 2.
The meeting will begin at 8:30 a.m. on May 20, 1982 and will be held at the Midland Holiday Inn,1500 Wackerly Rd., Midland, Michigan.
Attendance by the following ACRS members and consultants is antici-pated and hotel reservations have been made at the Holiday Inn for the nights indicated. Box 1mches and buffet dinners will be available at nominal expense on tursday, May 20th.
D. Okrent 19th & 20th W. Mathis "
D. Moeller
- C. Siess "
P. Davis (partial) "
E. Epler
- W. Lipinski "
J. Osterberg 20th F. Parker 20th P. Pomeroy (partial) 20th R. Scavuzzo 19th & 20th M. Trifunac (partial) 20th
- 2. Zudans 19th & 20th Attachments Project Status Report ec: ACRS Members E. Epler R. Fraley W. Lipinski M. Libarkin J. McKinley F. Parker P. Pomeroy Fo/ - g g p G. Quittschreiber P. Davis R. Scavuzzo M. Trifunac gg
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'9IDIAND PLANT UNITS 1 & 2 -
OPERATING LICENSE REVIEW MAY 20-21, 1982 PROJECT STA'1US REPORT PURPOSE: g m e purpose of tnis meeting is to review the application of Consmers Power Company for a license to operate the Midland Plant Units 1 & 2.
EN:
Pertinent facts concerning the Midland Project include:
Location:
te Midland site is located partially within the city of Midland, Midland County, Michigan. Se city of Midland is approximately .
105 miles NNW of Detroit and about halfway up Michigan's lower .
peninsula on the take lluron (east) side. Se facility is located along the south shore of the Tittabawassee River and south of the city of Midland. %e site is adjacent to the Dow Oiemical Company's (Dow) main industrial complex in Midland (located on the north side of the Tittabawassee River and due north of the plant). Within 10 miles of the plant, the 1970 estimated population was 72,706, within 5 miles, there were 48,501 residents. Circulating water for the two units is obtained from a cooling pond. Se cooling pond ,
receives make-up water from the Tittabawassee River. A map of the !
Midland plant site is included as Attachment 1. p Plant Each of the two units at the Midland plant employs a Babcock and i wilcox-designed nuclear steam supply systea (4SSS) consisting of a pressurized water reactor (PWR) rated at 2468 megawstts thermal (*t),
a pressurizer, two steam generators, four reactor coolant pumps, and the associated piping required to connect these components. Attach-ment 2 shows the NSSS arrangement. h is rated power level includes 2452 Mwt generated in the core plus 16 mt added to the 76SS by the four reactor coolant peps. %e mexian core design output (excluding pump heat) is 2552 MWt. Bis power level is referred to as the stretch level and is the value used in the radiological accident an-alyses. We Midland plant is smique in that the heat generated will be used not only to produce electrical energy but also to produce steam for the Dow Chemical Company plant. S e facility's turbine generators will produce 504 megawatts ele::trical (MWe) from Unit 1 and 852 MWe from Unit 2. WeremainingheatfromUgitIwillnormally be used to produce 460 kg/s (approximately 3.6 x 10 lbyr)at1200 kPa gauge (175 psig) and 50 kg/s (approximately 0.4 x 10 lb/hr) at 4100 kPa gauge (600 poig) of process steam for use at the Dow plant.
S e process steam system is a tertiary system utilizing heat extracted 6, ;.; J. r a; a ai;^ a M " " " l il Fl i l--
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STATUS REPORT /MIDIMD We containment for the nuclear steam supply system (NSSS) is a post-tensioned, reinforced concrete structure with a steel liner to provide leak tightness. We containment idiich was ,
designed and constructed by Bechtel Power Corporation has a design pressure of 70 psig.
We reactor cores will be loaded with 177 fuel assemblies (15x15). W e core will have an average thermal output of 5.47 kw/ft (based on cold BOL data) . W e SSE is 0.12 g hori-zontal, 0.8 g vertical. We CBE is 0.06 g horizontal, 0.05 g vertical. A comparison of Midland features with those of simi-lar plant designs is included as Attacrvnent 3.
ADDITIONAL CONSIDERATIONS:
Midland Units 1 & 2 have a nominal finish grade elevation of +634 ft.
We design high water level due to probable maximum flood, inc1 Ming wave run up effects is +535.5 ft. he design water level of the Tittabawassee River, cooling pond, and ultimate heat sink are +588 ft,
+618 ft, and +604 ft, respectively.
ACRS REVIEW:
The ACRS reviewed Midland for a CP license in June 1970. A copy of the CP letter and supplement thereto is inc1M ed as Attachments 4 & 5, re-spectively. In response to requests for additional information from the Atomic Safety and Licensing Board (ASIR) the ACRS wrote an addi-tional Supplemental Report on Midland Plant Units 1 & 2, dated Nov.18, 1976 and provided comments to the Commission Qiairman in a letter dated March 16, 1977. Wese two letters are Attachments 6 and 7 to this status report. Supplernent No. 2 to the NRC Staff's CP SER of the Midland Plant addresses the ACRS concerns identified in the second supplemental ACRS letter report dated Nov. 18, 1976 2 1s Staff SER supplement (less the ACRS letter) is included as Attachment 8.
On April 29, 1992 an ACRS Ad Hoc Subcorsnittee met to discuss the renedial actions for soils-related structural settlement problems at the Mid-land site. We report of that Ad Hoc Subconunittee meeting is included as Attachment 9. Of particular note in this report is the Ad Hoc Sub-committee's recorvnendation (accepted by the full ACRS during the May Full Committee meeting) that the Midland Plant Subconmittee revew:
- 1. %e adequacy of the seismic input criteria and
- 2. % e seismic Site Specific Response Spectra and its relation to the proposed permanent site dewatering as a means of reducity; the probability of liquefaction due to an earthquake.
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.J STATUS REPORT /NIDIAND We full ACRS is tentatively scheduled to review the OL application during its June 1982 meeting.
OPEN ITEMS:
There are currently 16 open items. About half of these items are m-resolved due to pending NRC Staff action / evaluation and half due to the need for additional information/ evaluation from Constsners Power Company.
Disagreements between the NRC Staff and the Applicant still exist on several soils settlement issues and on the need for a reactor vessel head vent. A list of the current open items is incitried in Attachment ,
- 10. Attachment 10 also lists the license conditions to be imposed on the applicant. For a description of each of these open items and license conditions, please see the indicated section of the NRC Staff's Safety Evaluation Repart.
MEFTING TEvrATIVE SCHEDULE:
2e meeting tentative schedule was issued May 12, 1982. It incorporated topics identified in the NRC Staff's SER, past ACRS letters (Attach-ments 4,5,6, and 7), the ACRS Staff's list of suggested discussion items for OL Subcommittee meetings, and items identified in consultant reports concerning Midland. We consultant reports are incitried as Attachment 11.
Comments received from ACRS members and staff were factored into the tenta-tive schedule as were the comments received from members of the public.
SUBCOMMI'ITEE ACTIONS REQUIRED:
%e Subcomittee should decide if the full ACRS should review the appli-cation of Consumers Power Company for a license to operate Midland Plant Units 1 & 2 at the June ACRS full Committee meeting. If the Subcocmitee decides that the full Committee should review Consumers application in June, then the topics to be discussed during the Midland portion of the June full committee meeting should be identified at the close of the Sub-cocmittee meeting.
PUBLIC PARTICIPATION:
A member of the public (Mary Sinclair/Dr. 01arles Anderson hrs requested an opportmity to make an oral statement regarding the soils / foundation question. Time has been made available on the schedule for this state-ment. In addition, Mrs. Sinclair has provided a letter, Attachment 12, for ACRS consideratien.
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oveten utdiend eenche s.co ormme termer Polet Beector and Beector Coolant System fref chaplere i and 5)
Roted heet output (core), Iert 2,452 2,772 2,568 2,200 Westenes overpener, I 12 12 14 12
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2,200 2,200 2,250 11 Beector ecolent pressere 2,200 (operating), pele 1 32 Feuer distrikettom factere aset generated in ftset and cladding, X 97.3 97.3 97.3 97.4 F ah taucleer) 1.7s 1.79 1.70 1,77 BNB rette et rated conditieme 2.30 1.7S(w.3) 2.0 1.01 DER retle et doelge overpower 2.07 1.39(w-3) 1.SS . l 32 i Coolent flee 7ttet fleerste, th/hr a 10 8 131.3 137.5 131.3 101.5 l16 Effective flev eroe for heet trensfor, f t' 48.9 49.17 49.19 41.0 32 AvereTo velocity along feel l! rede, ft/s 15.5 16.5 15.73 14.3 Ceolent temperatere
! Boninal inlet (voosell SSS.2 $$4.5 SS4 546.2 1
Wominal outlet (vessell 602.8 607.7 604.7 602.1 .
poalael outlet (core) 605.9 ... 405.5 604.5 l 32 j
' 4,250 4,400(overpower) h ismo feel tesseretere *F 3,900 4,400(hotspot) meet tremefor et 2005 power i
Active best tremeter surface i aree, ft' 49,130 49,734 49,734 42,440 4 Average heet fles Dte/hr/ft' 166,000 185.090 171,470 171,600 31
- g Average thernet output, kw/ft 5.47 6.10 5.SS 5.5 I
g Core mechanical emelgn parametere g Feel esse s11ee 177 177 177 157 Seeign CBA cealees CRA cealese CRA centees DCC cantose a
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System Itidlead Reacho Seco @_ Turker Point and pitch, in. 0.S60 0.548 0.S48 0.543
' overall dimenetems, in. 0.587 og 0.536 og 8.536 og e.426 og spueber of grido per essembly e 0 0 7 Ftektode number 36,016 34,016 36,816 32,020 Outside diameter, in. 0.430 0.430 0.430 0.422 clad tAlcknees, in. 0.0265 0.0265 0.0265 0.0243 Clad meteriel Sitceloy-4 Eircoloy-4 Eircoloy-4 Eireeloy Ftsel pellets letterial 90 2 , sistered UDy, statered 00 7, statared 00 2, sistered Demetty, I of theerotical 9be 92.5 93.5 94,93,92 l 33 Diameter, 1s. 0,3606 0.370 0.370 0.3659,0.3659,0.3449 I control red essemellee (cmA)
Weetree ebeerter 91cd-1SX1m-00Eng $1ce-191te-00p g $1cd-1511m-00Eng 51ce-ISX1m-40Eng 4 cladding meteriet 304ss-co14 worked 304SS-cold worked 304ss-cold oorked 304SS-cold worked Clad thicknese, in. 0.021 0.021 0.021 0.019 trueber of essenb!1ee 61 61 61 53 INeber of control rode per eseeably 16 16 16 20 surnable pelsen red esseottles (BPRA) 94 60 64 SG Wesleer Seelen Data ;
Structural charactarletics Ftsel set M ee UD 2, 1b 93.1 metric tone 204,020 207,444 176,000 core diameter, in.
i legulveleet) 128.9 120.9 128.9 119.S Core height, in.
lective feet) 141.3 144 144 144 l 33 Performance characteristice Imeding technigme 3 reglen 3 region 3 region 3 reglen Feel discharge borwup, 1 I
Ins 4/etU everage first cycle 13,744 14,250 14,250 13.000 32 1 equilabrium core everage 27,799 --- ==- 24,500 I
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oconee Turker Point Sveten Midland Sancho seco control characteristics Ef fective multiplication (BOL) cold, sero power, clean, 1.248 1.180 no burnable poison 1.24 1.252 Hot, sero power, clean, 1.198 1.138 no burnable poison 1.19 1.19 Not, rated power, equili-brium Xe, with burnable 1.134 1.077 poison 1.11 1.12 Boron concentrations To shutdown with rode inserted, clean, cold / hot, ppm 1,143/641 1,099/605 992/493 700/510 poron worth, hot, 7.3/---
1(ak/h) / ppm 1/96 1/100 1/100 Boron worth, cold, 1/74 1/75 1/75 5.6/---
5(ak/k)/ ppm Principal design parameters of the reactor coolant system 2,468 2,772 2,584 2,200 ayeten heat output, Mut 2,185 2,235 Operating pressure, peig 2,185 2,185 555.2 556.5 554 546.2 Reactor inlet temperature,er 602.1 Beactor outlet temperature,*F 602.8 607.7 604 2 2 3 teumber of loope 2 2,500 2,500 2,500 2,485 Design pressure, peig 650 650 650 Design temperature, *r 650 Mydro test pressure 3,125 3,125 3,107 (cold), peig 3,125 Principal design parameters of reactor vessel e SA-302 Gr 8, low alloy sA-533 cr n, SA-533, or 8 SA-533, or 8, Material 18-ess clad 18-8ss clad st*el, internally clad 18-853 clad with SS 2,500 2,500 2,500 2,485 Design pressure, peig 650 650 650 Design tes@erature, er 650 2,185 2,185 2,185 2,235 operating pressure, peig 171 171 171 155.5 Inside diameter of shell, in.
overall height of vessel and closure head (over 40/8-3/4 41/6 cad nossles), ft-in. 40/8-7/8 40/8-3/4 (sheet 3)
Revision 15 11/78
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TABLE 1.3-1 (continuedt .
System Midland Dancho seco Oconee Turker Point stinimum clad thicknees, in. 1/8 1/8 1/8 5/32 Principal design parameters of the steam generatore ,
seember of unite per reactor 2 2 2 3 Type Vertical, once- Vertical, once- Vertical, once-through, Vertical U-tube, through, integral through, integral integral superheater, integral noisture superheater, superheater, straight-tube separator straight-tute straight-tube Tubeelde design preneure, peig 2,500 2,500 2,500 2,e85 Tubeside design temperature, *F 650 650 650 650 Shell side design pressure, peig 1,050 1,050 1,050 1,085 Shell side design temperature. *F 600 600 600 556 Operating pressure Tubeside, peig 2,185 2,185 2,185 2,235 Sivell side, peig 910 910 910 1,020 Ilydrostatic test pres sure, cold, tubeside, peig 3,125 3,125 3,125 3,107 Principal design parameters of reactor coolant pumpe leumber of pumpe 4 e e 3 Type Vertical, single Vertical, single Vertical, single Vertical, single stage stage stage stage Design pressare, peig 2,500 2,500 2,500 2,485 Design temperature, *F 650 650 650 650 Design capacity, gym 88,003 92,400 88,000 89,500 Design total developed head, ft 327 362 396 260 Ilydrostatic test pressure 3,125 --- --- 3,107 (cold) , peig peotor type ac, induction, ac, induction, ac, induction, ac, induction, single ageed single speed single speed simla sp??d peotor rating, hp g,000 10,000 9,000 6,000 yetorcoolantpiping Isot leg (id.) in. 36 36 36 29 cold leg tid.) in. 28 28 28 27-1/2 (sheet 4)
Revision 15 11/TE s
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e MIDIAND 16 2-F5 Alt TABLE 1.3-1 fcontinuedt econee Turkey Point System Midla nd Rancho Seco Essaineered safety Features tret Chapter M i
safety injection system 3 3 e (shared) soumber of high head pumpe 3 300/5,850 250/5,900 300/2,700 Capacity each, gpm/ft 250/6,000 2 2 2 2 l 15 leusber of low head pumps 3,000/350 3,750/240 3,000/370 3,000/350 Capacity each, gpWit Containement coolers Fan coolers Fan coolers Type Fan coolers ran coolers 4 3 3 4
leumber of unite 50x10* 60x10* 80x10* 60x10*
Capacity, Stu/hr each, at accident Core flooding system 2 3 2 2 stumber of tanks Total water volume, 1,040 1,040 1,200 (total each its 1,040 volume) 775 water vol mir.
Containment spray 2 2 2 neumber of pumpe 2 1,e50 1,500 1,500 1,300 l
Capacity, each, gym NH NaOH None None l13 4
Spray additive for iodine 2 4 removal Egustgency power Diesel various Diesel I
gype Diesel 7 sources of signif- 2/2,500kW each 2/5,250kw each 2/2,600kw eaci Quant $ty continuous icant capacity continuous continuous i
Wr Conversion System tref Chapter 109E88 Unit 2 Unit 1 Turbine-generator l 847 728 ,
852 504.8,t2p 850 0 Grose generator output,per 595.2I33 1 hP, 2 1r 1 hp, 3 IP 1 hp, 3 1p i cylinders, high-pressure, 1 hp, 2 1p 1 hp, 1 1p low-pressure .
- (sheet 5)
,3 Revision 15 t 11/78 1
MIDtJUID 1&2-FSAft , ,
P TABt21.3-1 (continued)
Oconee Turkey Point Breten Midland Rancho seco Steam conditione et throttle valve 4 Flow, 10 8 lb/hr 9.77 9.62 10.77 11.17 8.97 900 900 745 Pressure, pela 900 900 510 Temperature. *F 566.4 566.4 595 568.8 poisture content, % 0 0 0 0 0.25 Steam now to Dow chemical 632/198'" - - l 37 Pressure, poig tip/1p -/-
Flow, Ib/hr hp/1p -/- 400,000/3.65x10'" - - -
-/- 6.84x105 /1.8x10'*
Tertine cycle arrangement 2 2 1 Steam reheat stages, no. 2 2 5 6 6 6 Feedwater heating stages, 5 no. 2 2 Strings of feedwater 2 2 2 heaters, no.
Beeters in W e necke, 2 2 0 1 2 atmber Beater drain system Demerator Demerator Cascade Pumped forward Pumped forward cycle cycle Igueber of condensate pumpe 2 2 3 3 2 Ifumber of condensate booster 0 3 0 pumps 2 2 Wemmber of main feedwater 2 2 pumps 2 2 2 l 3-turbine
' Ifenber of ammillary 2 2 2 1 with interties to other feedwater pumpe 1-turbine 1-turbine 1-turbine 2 unite - turbine driven 1-motor 1-motor 1-motor Capacity, each, gym 885 885 840 7-1/2% full 600 i feedwater capacity 1
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Revision 32 1/81
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MIDLAND 1&2-FSAR TAtt2 1. 3-1 (continued)
Oconee Turkey #oldt System Midland Rancho Seco 254 404 Itain steam turbine bypass 158 154 154 capacity, 4 Final feedwater 460 436 430 430 473 temperature *r at mg1 Condenser
- Single pressure Dual Single Dual pressure Type pressure pressure - 2 2 1 2 Condenser shello 2.5 average - 2.5 Design pressure Hg abe 4.07/2.77 2.83 hp/1p - 5.02 5.51 2.14 f> . 2 4 Total condenser duty, Btu /ht10* Cooling Cooling Cooling tower once through once through Circulating water system Lake Keowee Biscayne Bay pond pond (hyperbolic)
Circulating water 4/ Unit 2/ Unit pumps 2/ Unit 2 2/ Unit 1 4/ Unit 4.47 7.00 3.12 Flow, gpm x 10*/ unit 2.64 3.90 Spray pond Lake Keowee Biscayne Bay Cooling Cooling Ultimate heat sink pond pond 2/ Unit 3 shared 3 shared Service water pumps, 2/ Unit 2 2/ Unit 1 no. (Plus one common apare for Units 1&2) 16,000 15,000 16,000 Flow, gpm/each pump 21,000 21.000 1 Radioactive traste Management Systems (ref Chapter 11) l 32 Degasified, fit- Degasified, Degasified, demineralized Liquid radweste treatment Degasified, fil- evaporated tered, demineral- tered, demineral- evaporated ited, evaporated Ized, evaporated J
(sheet 7)
Revision 32 1/81 1- -- .
, ,a E'1DtAIS 1&2-PSAR , ,
TAsta 1.3-1 (contineed)
Systen 9tidland Rancho Seco Oconee Turkey Point Evaporotors, weste 30 30 10 approx 20 ,,
capacity, gym quantity 1 1 1 1 8e Domineralisers, weste 150 150 None 1,000 gal, batch 9 2 gym capacity, gym Quantity 2 2 - 1 Caseous redweste treatment Holdup tanks for flo1 dup tanks for Holdup tanks for decay, Holdup tanks for decay, decay, charcoal, decay, charcoal, prefilter, absolute, and monitored, released to and PEPA filters and IEPA filters charcoal filters atmosphere Isoldup Tanks Quantity 6 4 2 6 capacity, cubic ft 390 490 1,100 525 (each) solid redwoots treatment Containers 55 gallon drum 55 gallon drum 55 gallon drum 55 gallon drum containment (ret subsecties 1 6.2.1 Type steel lined, pre- steel lined, pre- steel lined, prestressed, steel lined, prestressed, stressed, post-ten- stressed, post-ten- post-tensioned concrete post-tensioned concrete sioned concrete sioned concrete cylinder with curved cylinder with curved cylinder with cylinder with done roof done roof curved done roof curved done roof taak rate, X/ day 0.1 0.1 0.25 0.25 70 59 59 49.9 l 32 Design pressure,alopeig Free voltme, ft- 1.67 1.98 1.91 1.55 Cylinder inner diame-ter, it 116 130 116 116 Inside height, ft 193 185 208-1/2 169 l
l teheet el Revision 32 i 1/01 l
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e MIDtJWID 1&2-FSAR TABt2 1.3-1 (continued) s system Midland Rancho Seco Oconee Turkey Point structural Desten Require-ments (ref Section 3.8)
Operating basis .06 0.13 0.05 0.05 earthquake (horis g) safe shutdown earth- .12 0.25 0.10 0.15 quake (horis g)
Vertical seismic 67 68 - 66 ground motion
(% of horizontal)
Haminum sustained wind, 85 90 95 145 mph Tornadoes, uph 360 max - 300 225 Electrical systems (ref Chapter a,y*
Number of offsite circuits 2 5 12 (4 from 2 nuc units, 3 from fossil fuel)
Number of auxiliary pouer 2-startup trans- 2-startup trans- 1-startup transformer 1-startup transformer sources formers (shared) formers 2-unit aus 1-knit aux 1-unit aux transformer 1-unit aux transformer transformers trans former musber of preferred 2 2 -
2 power to ESF buses Ihamber of 4.16kV ESF 2 2 3 2 buses / unit (4kV)
Number of Class IE 2 4 2 2 125Vdc systems supplying buses / unit Bhamber of Class IE 4 4 4 4 32 120Vac preferred buses / unit sharing of staney none none none none power Fuel Bandline Equipment and Facilisties (ref Section 9.1)
Reactor building crane Type polar polar polar polar capacity, tons 190 main, 25 aux 160 - 135 main, 35 aux (sheet 9)
Revision 32 1/81
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NTDUGO 1&2-FSAR , ,
TABER 1.3-1 (continued)
Systess Midland Rancho seco Oconee Turkey Point Transfor tubee/ unit .-
Number 1 2 2 1 Capacity dual dual dual single 10 spent fuel storage Capacity (number of 1,049 242 336 217 fuel assemblies) l15 3Bev fuel storage Type wet or dry storage Dry Dry Wet %*et Capacity / unit 66 20 168 (new & spent) 53 l 32 Cask handling crane Type Double girder Centry crane Double girder bridge Double girder bridge and bridge trolley i
Capacity, toes 125 main, 15 aux 185 main, 35 aux 100 105 main, 15 auxiliary cask weight = 100 "4tidland data given for Unit 2, unless 17 nit 1 data given in addition.
All data for other plants given on per unit basis.
- Design steam flow to Dow at rated reactor power. High-pressure process steam flow may exceed 400,000 lb/hr, up to a maximum of 800,000 lb/hr, when low-pressure process steam 1 32 production is less than 3,650,000 lb/hr.
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- sased on maximum calculated electrical production at 2,468Mwt with a minimum corresponding steam flow to Dow.
" Represents total incoming and outgoing circuits. lyy
- Data on plants other than Midland not maintained current after August 1977. l 4
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