ML20140H084

Forwards Project Status Rept for ACRS Subcommittee on Midland 820429 Meeting in Washington,Dc to Discuss Util Remedial Action on Soils & Structural Settlement Issues

ML20140H084
Person / Time
Site:	Midland, 05000000
Issue date:	04/21/1982
From:	Fischer D NRC
To:	Seiss C Advisory Committee on Reactor Safeguards
Shared Package
ML19255C661	List: IA-85-602, Forwards Revised Schedule for ACRS Subcommittee on Midland Plant 820429 Meeting in Washington,Dc to Discuss Util Remedial Action Re Soils & Structural Settlement Issues. Related Info Encl IR 05000330/1977002 ML19255C660 ML20133D109 ML20140B741 ML20140B746 ML20140B751 ML20140B759 ML20140G820 ML20140G826 ML20140G835 ML20140G840 ML20140G846 ML20140G850 ML20140G856 ML20140G862 ML20140G868 ML20140G873 ML20140G878 ML20140G886 ML20140G891 ML20140G901 ML20140G906 ML20140G912 ML20140G916 ML20140G928 ML20140G933 ML20140G938 ML20140G942 ML20140G947 ML20140G951 ML20140G955 ML20140G961 ML20140G968 ML20140G973 ML20140G978 ML20140G985 ML20140G990 ML20140G996 ML20140H002 ML20140H008 ML20140H013 ML20140H020 ML20140H024 ML20140H028 ML20140H035 ML20140H040 ML20140H045 ML20140H052 ML20140H057 ... further results
References
FOIA-85-602 NUDOCS 8510080438
Download: ML20140H084 (14)

Text

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f M Lwt April 21, 1982 MEMORANDlf! FOR:

C. Siess, Acting Chaiman, ACRS Subcomittee on Midland Plant Units 1 & 2 FROM:

D. Fischer, Reactor Engineer SUEJECT:

PROJECT STATUS REPORT FOR THE ACRS SUBC0tHITTEE MEETING ON MIDLAND PLANT LNITS 1 & 2 - APRIL 29,1982 -

WASHINGTON, DC Attached is a project status report for the subject meeting. The purpose of the meeting is to discuss remedial action being taken by Constners Power Company regarding the Midland soils and structural settlement issues.

The meeting will begin at 8:30 a.m. on April 29, 1982 and will be held in Room 1046 at 1717 H Street, NW, Washington, DC. Attendance by the following ACRS members and consultants is anticipated and hotel reserva-tions have been made as indicated.

If anyone is unable to make the meeting, please call us or the hotel and cancel your reservations so that were are not billed.

Park Central (202-393-4700) )

April 28 C. Siess Army-Navy Club (202-628-8400 April 28 W. Mathis J. 0sterberg None R. Scavuzzo None Z. Tudans None Attachnent:

Project Status Report cc: ACRS Members R. Fraley M. Libarkin T. McCreless J. McKinley G. Quittschreiber f4

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MIDLAND PLANT UNITS 1 & 2 OPERATING LICENSE REVIEW APRIL 29, 1982

- PROJECT STATUS REPORT -

PURPOSE:

The purpose of this meeting is to discuss remedial action being taken by Consumers Power Company regarding the Midland soils and structural settle-ment issues.

BACKGROUND:

Pertinent facts concerning the Midland Project include:

Location:

The Midland site is located partially within the city of Midland, Midland County, Michigan. The city of Midland is approximately 105 miles NNW of Detroit and about half way up Michigan's lower peninsula on the Lake Huron (east) side. The facility is located along the south shore of the Tittabawassee River and south of the city of Midland. The site is adjacent to the Dow Chemical 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.

The cooling pond receives make-up water from the Tittabawassee River. A map of the Midland plant site is included as Attachment 1.

Plant:

Unit 1 and Unit 2 each consist of a Babcock & Wilcox pressurized water reactor, a turbine generator, and associated auxiliaries.

The two units have a combined capability of approximately 1,300 MWe and 4 million Ib/hr of process steam. The process steam will be supplied to Dow and the electricity to the utility's customers. The containment for the nuclear steam supply system (NSSS) is a post-tensioned, reinforced concrete structure with a steel liner to pro-vide leak tightness. The containment which was designed and con-structed by Bechtel Power Corporation has a design pressure of 70 psig.

The requested power level per unit is 2,452

• t [NSSS output =

2452 MWt + 16 MWt (Reactor Coolant Pump heat input)]. The Unit 1 turbine generator (GE) is rated for operating at the NSSS rated output with a corresponding electrical output of 504.8 We.

Process steam is provided to Dow by using extraction steam from the high pressure turbine under normal operation, and main steam from the main steam i

header. About 4 million lb/hr of process steam can be provided to Dow at the Unit I turbine generator rated level of 504.8 We. The Unit 2 turbine generator (GE) is rated for operation at NSSS rated output with a corresponding electrical output of 852 W e.

Each unit will use two B&W once-through steam generators. The reactor cores will

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lf PROJECT STATUS REPORT MIDLAND - 4/29/82 4/20/82 i

1 1

be loaded with 177 fuel assemblies (15x15). The core will have l

an average thermal output of 5.47 kw/ft.(based on cold BOL data).

l The SSE is 0.12 g horizontal, 0.8 g vertical. The OBE is 0.06 g horizontal, 0.05 g vertical. A comparison of Midland features i

i t

I with those of similar plant designs is included as Attachment 2.

}

ADDITIONAL CONSIDERATIONS:

i Midland Units 1 & 2 have a nominal finish grade elevation of +634 ft.

i The design high water level due to probable maximum flood, including i

wave run up effects is +635.5 ft. The design water level of the 1

l Tittabawassee River, cooling pond, and ultimate heat sink are +588 ft, t

+618 ft, and +604 ft, respectively.

ACRS REVIEW:

t j

The ACRS reviewed Midland for a CP license in June 1970. A copy of the CP letter and supplement thereto is included as Attachments 3 & 4. re-i

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spectively. The ACRS Midland Plant Subcomittee plans to review the application of Consumers Power Company for an OL on May 20&21, 1982 in i

Midland, MI. The full ACRS is tentatively scheduled to review the OL j

application during its June 1982 meeting.

SOILS ISSUES:

f The April 29, 1982 ACRS Midland Plant Subcommittee meeting in Washington, DC l

i is to discuss remedial actions being taken by Consumers Power Company re-t 1

garding the Midland soils and structural settlement issues. The meeting is being conducted at the request of the NRC Staff (NRR). The NRC Staff and Consumers Power Compnay will provide information on these issues to the Sub-I comittee so that the ACRS might better coment on the merit of proposed and j

implemented fixes. A sumary of the soils-related issues at the Midland Nu-

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clear Plant is included in the attached reference material.

I encourage you to read this executive summary first (transmitted by Consumers Power Company i

i letter to H. Denton dated April 19,1982). A list of other correspondences l

j summarizing the soils-related issues at Midland is included as Attachment 5.

The documents listed on Attachment 5 are appended to this meeting status report. A chronology regarding plant fill deficiencies was compiled by the NRC Staff's Project Manager for Midland. This chronology is included as In view of the large vt,lume of material being forwarded to you by this status report, I have arranged to have extra copies available at the meeting for your use.

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s R10tJSD 1&2-F5AR TABLE 1,3-1 coppARISON OF N1DIAss FRA7URES v1?W SIW1 TAR DESIGB5" Breten mieland Reache sece Ocease 7turker Pelot toector and teacter Coolant _ wroten

[ ret Choters 4 ene 5)

Seted heet eetput (core), part 2,452 2,772 2,548 2,200 monimum everpomer. I 12 12 14 12 Reacter emeleet pressere 2,200 2,200 2,200 2.250 l'

(operating), pole 1 32 Peuer distributtee factere meet gemoreted la feel and cleedteg, X 97.3 97.3 97.3 97.4 l

F ah (secleer) 1.79 1.70 1.79 1.77 M rette et rated comeitleme 2.50 1.75(w-3) 2.0 1.01

)

SIB rette et desige everposer 2.07 1.39(w-3) 1.55 l 32 I

Coolant fler 1tstel floorste, th/hr a 19 131.3 137.8 131.3 191.5 l#

8 Bffective flow area for heet tremefer, ft' 40.9 49.17 49.19 41.0 Average velocity along feel 32 roes, ft/m 15.5 16.S 15.73 14.3 l

l cuelant temperatere m

j Beaten 1 latet (voosel)

SSS.3 SS4.5 994 S46.2 a

ponteel setiet (seeeet) 602.0 607.7 604.7 602.1 605.5 604.5 l 32 Demisel cettet (core) 605.9 i

hi-feel temperature. *F 3,900 4,400(hetepet) 4,250 4,400(overposer) i l

Smet tremefer et 2005 power i

Active heet tremeter omrface eres, ft' 49,130 49,734 49,734 42,460 Averego heet flee, Ste/hr/ft' 164,000 185,090 171,470 171,600 32 g

Average therent output, tw/ft 5.47 4.10 S.SS 5.5 g

core machemical eseipi parametere g

Pool esseelles 177 177 177 157 meg Design cha cealese enA cealese cmA centese acc costose N

(shoot 11 g

newleton 32 1/01 i

l

• J MIDEAleD 1&2.FSAR Tasta 1.5-1 feestimmed) i i

grotes saidland m_-rea sece ocesse Terker Pelet God pitch, 1s.

0.544 0.548 0.940 0.S43 overall dimanelsen, in.

0.S87 og 8.S36 og 0.536 og 8.426 eq Isucher of grido per necedly 8

8 8

7 Ftsekrode m

36,016 36,016 36,814 32,020 Ostelde diameter, is.

0.438 0.430 0.430 0.422 clad thicknees, in.

0.0265 0.0265 0.0265 0.0243 clad meterial Eireeloy-4 Eircoloy-4 Eireeloy-4 Eireeloy Finet pellets i

50, sistered 00, sistered 90, sistered 50, sistered motoriet 2

2 2

2 i

Demetty. I of theoretical 95.0 92.S 93.5 94,93,92 33 Diameter, ie.

0.3606 0.370 0.370 0.3499,0.3659,0.3649 Centrol red essentlies (can)

Weetzum eheerter 93c6-19E1e-4993 SEcd-1951e-Gepe SEcd-1SI1m-deg g S1cd-1 Site-40pg Cladding material 304SS-cold worked 30455-cold worked 304SS-cold worked 304SS-cold worked clad thicknees, la.

0.021 0.021 0.021 0.019 Immeber of eseemblies 61 41 61 S3 Neher of centrol rede per eseeably 16 16 16 20 suremble potese red esemelles lerna) 64 60 64 se Wesleer Seelm Dets structeral characteristice m

Fool wetWet as 902 14 93.1 metric tone 204,020 207,406 176,000 Core diameter, in.

(egelveleet) 129.9 128.9 128.9 119.5 l

Core height. to.

l 33 (active feet) 141,3 144 144 144 Performance cherectorietice Emeding technigme 3 regles 3 reglen 3 region 3 region Peel discharge buroup, suss/stu everage first cycle 13,744 14,250 14,250 13,000 jy 24,500 i

equitsprian core everage 27.7e9 (shoot 3) 33 i

pevision 4/91

_=

IIIDIAlm IS2-FSAR thaLa 1.3-1 acontinese e

Svetes midland sancho seco oconee Turker Point Control characteristics af factive multiplication (sol) cold, sero power, clean, no burnable poison 1.24 1.252 1.248 1.100 A

not, sero power, clean, no beraable poison 1.19 1.19 1.198 1.138 Not, rated power, equili-brium Xe, with bernable poison 1.11 1.12 1.134 1.077 Baron concentrations To shutdown with rode inserted, clean, cold / hot, ppm 1,143/641 1,099/605 992/493 780/510 moron worth, hot, 1(Ak/k3 / ppa 1/96 1/100 1/100 7.3/---

Boron worth, cold, S kk/h)/psmi 1/74 1/75 1/75 5.6/---

Principal design parameters of the reactor coolant eyeten System heat output, Nut 2,460 2,772 2,584 2,200 operating pressure, peig 2,185 2,185 2,185 2,235 poactor inlet temperature,*F 555.2 556.5 554 Se6.2 seactor outlet temperature.or 602.8 607.7 604 602.1 pueber of loope 2

2 2

3 Design pressure, peig 2,500 2,500 2,500 2,485 l

Design temperature, *F 650 650 650 650 Bydro test pressere (cold), poig 3,125 3,125 3,125 3,107 Principal design parameters of reactor veseel e

meterial 34-5 33 Gr 3, SA-533, Gr B SA-533, Gr 8, SA-302 Gr 3, low alloy 18-SSS clad 18-ess clad 18-058 clad steel, internally clad with SS posiya gressure, peig 2,500 2,500 2,500 2,405 poeign temperature, *r 650 650 650 650 operating pressure, peig 2,185 2,185 2,185 2,235 Inside diameter of shell, in.

171 171 171 155.5 overall height of vessel and closere head (over CSD nossleet, ft-in.

40/8-7/8 40/8-3/4 40/8-3/4 41/6 (eheet 3)

Revision 15 11/78

gagggage ig2.ygag 1hSLE 1.3-1 (continuedl Grotes midland sancho seco oconea Turker Point Iainimos clad thicknese, in.

1/8 1/8 1/8 5/32 Friecipal doeign parameters of the stesa generatore peober 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 suoisture superheater, superheater, straight-tube sega rator straigh*-tube straight-tube Tubeelde design n

pressure, peig 2,580 2,500 2,500 2,485 Tuboeide 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 Tubeelde, peig 2,185 2,185 2,185 2,235 Shell side, peig 910 910 910 1,020 Nyorostatic test pressere, cold, tubeelde, peig 3,125 3,125 3,125 3,107 Principal design parameters of reactor coolant peeps

• of peepe 4

4 4

3 Type vertical, single vertical, single vertical, single vertical, single stage stage stage stage Design pressure, peig 2,500 2,500 2,500 2,485 Design toeperature, *F 650 650 650 650 i

Design capacity, gpa 80,000 92,400 88,000 89,500 Design total developed head, ft 327 362 396 260 3,107 Nydrostatic test pressure 3,125 (cold), poig peo+or type ac, induction, ac, induction, ac, induction, ac, induction, single speed single speed single speed sim la opted sector rating, hp 9,000 10,000 9,000 6,000 me,ector coolant piping mot leg (id.) in.

36 34 36 29 Cold leg (id.) in.

28 28 28 27-1/2 toheet 4)

Revision 15 11/71 D

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MIDIAse 162-FSAR TABLE 1.3-1 toontineedt Systegi Midla nd Sancho Seco Oconee Turkey Point h esisered Safety Features tref chapter en sefety injection eyetem pueber of high head pumpe 3

3 3

4 (shared)

Capacity each, gpen/f t 250/6,000 300/5,850 250/5,900 300/2,700 pueber of low head pumpe 2

2 2

2 l 15 Capacity each, gpsh/ft 3,000/370 3,000/350 3,000/350 3,750/240 Conta1 ament coolere Fan coolers Tan coolers Fan coolere Fan coolere Type 4

4 3

3 Number of unite Capacity, stu/hr each, at 50 10*

60x10*

80x10*

60r10*

accident Core flooding system seumber of tanks 2

2 2

3 Total water volume, each its 1,040 1,040 1,000 1,200 (total volume) 775 water vol mir.

Contalement oprey 2

2 2

2

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teumber of pumps Capacity, each, gym 1,300 1,500 1,500 1,450 l13 Spray additive for iodine NyH NaOH None None g

removal muergency power Diesel Diesel various Diesel Type Quant $ty 2/5,250ked each 2/2,600kw eacs 7 sources of signit-2/2,500kW each continuous continuous icant capacity continuous Power ceauereien Sveten erof chanter 19eE*8 Unit 2 Unit I Tortpine-generater crose generator output, set 852 504.8 850 847 720 t2p 3

k3) 595.2 cylinders, high-pressure, I hp, 2 1p 1 hp,1 1p 1 hp, 2 IF 1 hp, 3 1p 1 hp, 3 1p low-pressere (sheet 5)

Revision 15 11/76

e.

NIS M 1&2-FSAR J

vaarm 1.3-1 (continued)

Syytes Midland Rancho Seco Oconee Turkey Point Steen conditiene et throttle valve 4

Flow, les Ib/hr 9.77 9.62 10.77 11.17 8.97 Pressure, pela 900 900 900 900 745 W rature

• F 566.4 566.4 595 568.8 510 Moisture content, %

0 0

0 0

0.25 steen flow to Dow Chemical m

I 32 Preocure, poig ty/1p

-/-

632/1 #

Flow, Ib/hr lip /1p

-/-

600,000/3.65m10 "

8

-/-

t,. 84a10 5/1. 8 x 10*'"

l Turbine cycle arrangement Steen reheat stegos, no.

2 2

2 2

1 Feedseter heating stagee, 5

5 6

6 6

Bo.

Strings of feedweter 2

2 2

2 2

[

heetace, no.

Emeters in h e necke, 2

2 0

1 2

member Beater dreia system Doeerator Demerator Cascade Pumped forward Pumped forward cycle cycle 1

Nuuher of hate pumps 2

2 3

3 2

1 Number of cohete booster pumpe 2

2 0

3 0

Number of amia feedwater pumps 2

2 2

2 2

Number of amaillary 2

2 2

1 with intertien to other 3-turbine feedwater pumpe 1-turbine 1-turbine 1-turbine 2 unito - turbine driven l

1-motor 1-motor 1-eotor

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Cepecity, each, p 885 885 840 7-1/2% full 600 feedwater capacity (eboet 4)

Revision 32 1/81 h

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n MIDLAND 1&2-FSAR

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6 That2 1.3-1 (continued)

Turkey Poldt System Midland Rancho Seco Oconee seein steam turbine bypass 154 158 158 254 404 capacity, 4 temperature *F at agt 430 430 471 460 436 Final feedwater R

Condenser Dual Single Dual pressure Single pressure Type pressure pressure 2

Condenser shelle 2

1 2

2.5 Design pressure Hg abe 4.07/2.77 2.83 2.5 average Total condeneer duty, 5.51 2.14 6.24 5.02 hp/1p Stu/hr:10*

Circulating water system Cooling Cooling Cooling tower once through once through pond pond (hyperbolic)

Lake Eeowee Biscayne Bay 2/ Unit 2 2/ Unit 1 4/ Unit 4/ Unit 2/ Unit circulating water pumpe Flow, ggun z 10*/ unit 2.64 3.90 4.47 7.08 3.12 Ultimate heat sink Cooling Cooling Spray pond Lake Reowee Biscayne Bay pond pond service water pumps, 2/ Unit 2 2/ Unit 1 2/ Unit 3 shared 3 shared (Plue one common no.

opere for Units

^

1&2)

Flow, gym /each pump 21,000 21.000 16,000 15,000 16,000 Radioactive waste stanagement systems (ret Chapter 11)

[ 32 Lipid redweste treatment Degeeified, fil-Degasified, fil-Degasified, Degasified, domineralised tered, domineral-tered, domineral-evaporated evaporated ised, evaporated ised, evaporated

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l (sheet 7)

Revision 32 1/81

• e NTDUWB 142-FSAR Tasta 1.3-1 (continued)

System flidland Rancho seco oconee Turkey Point Evaporatore, weste 30 30 10 approx 20 capacity, ga Quantity 1

1 1

1 og Domineralisers, weste 150 150 None 1,000 gal batch 9 2 gym capacity, go Quantity 2

2 1

Caseous redweste treatment Holdg tanks for Boldup tanks for Holdup tanks for decay, Holdup tanks for decay, decay, charcoal, decay, charcoal, prefilter, absolute, and monitored, released to m

and MFA filters and HEPA filters charcoal filters atmosphere Boldup Tanks guantity 6

4 2

6 Capacity, cubic ft 390 490 1,100 525 (each) solid redweste treatment costeiners 55 gallon drum 55 gallon drum 55 gallon drum 55 gallon drum Casteluseet (ref subsection 6.2.1 Type steel lined, pre-steel lined, pre-steel lined, prestressed, steel lined, prostressed, stressed, post-ten-stressed, post-ten-post-tensioned concrete post-tensioned concrete sioned concrete stoned concrete cylinder with curved cylinder with curved cylinder with cylinder with done roof done roof curved done roof curved done roof Leak rete, X/ day 0.1 0.1 0.25 0.25 Desige pressure peig 70 59 59 49.9 l 32 g

Free volume, ft x10 1.47 1.98 1.91 1.55 cylinder inner diame-ter, ft 116 130 116 116 Inside height, ft 193 185 208-1/2 169 (shoot 8)

Revision 32 1/81 i

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1 NIDE.l3D 1&2-FSAR i

TARIA 1.3-1 (continued)

I System Widland Rancho seco Oconee Turkey Point

- Structural Design Require-ments (ref section 3.8)

Operating basis

.06 0.13 0.05 0.05 earthquake (horia g) m Safe shutdown earth.

.12 0.25 0.10 0.15 quake (horis g)

Vertical seismic 67 68 66 ground motion

(% of horizontal)

Itaximm sustained wind, 85 90 95 145 300 225 Tornadoes, sph 360 inax Electrical Systems (ref Chapter

• 1*

Nusber of offsite circuits 2

5 12 (4 from 2 nuc units, 3 from fossil fuel)

Niember of auxiliary power 2-startup trans-2-startup trans-1-startup transformer 1-startup transformer sources formers (shared) formers 2-unit aux 1-unit aux 1-unit aux transformer 1-unit aux transformer transformers transformer 2

Wes6er of preferred 2

2 power to ESF buses Wusber of 4.16kV ESF 2

2 3

2 buses / unit (4kV)

Number of class 1E 2

4 2

2

'N 125Voc systems supplying buses / unit Number of Class IE 4

4 4

4 32 120Vac preferred buses / unit Sharing of starumpy none none none pone power hel Nondlim Eeuisment and Fact:A.es (re f Section 'l.1 i

Reactor building crans Type polar polar polar polar 135 main, 35 ama Capacity, toes 190 main, 25 aux 180

.i (sheet 9) 4 Revinion 32 i

1/81

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NIDEAID 1&2-FSAR TASE2 1.3-1 (continued)

System Midland Rancho Seco Oconee Turkey Point Tramofer tubee/ unit i.

Number 1

2 2

1 Capacity dual dual dual eingle I

spent fuel storage capacity (number of 1.049 242 336 217 l15 fuel assemblies)

New feel storage Type Wet or dry storage Dry Dry Wet Wet Capacity / unit 66 20 168 (new & spent) 53 l 32 Cask handling crane "ype Double girder centry crane Double girder bridge Double girder bridge and bridge trolley capacity, tone 125 main, 15 aux 185 main, 35 aux 100 105 main, 15 auxiliary cask weight = 100

"%tidland data given for Unit 2, unless Unit I 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 I 32

• production is less than 3,650.000 lb/hr.

samed om maxima calculated electrical production at 2,468MWt with a minimum corresponding steam flow to Dow.

" Represents total incoming and cutgoing circuits.

l 32 "hta on plants other than Midland not maintained current after August 1977.

I n

1 (sheet 10)

Revision 32 1/81 1

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WA.sHINGTON. D.C. s0545 June 18, 1970 i

Honorable Glenn T. Seaborg Y

Chairman U. S. Atomic Energy Commission Washington, D. C.

20545

Subject:

REPORT (E MIDIAND PIANI UNITS 1 & 2 Dear Dr.

Seaborg:

During its 122nd meeting, June 11-13, 1970, the Advisory Comunittee on Reactor Safeguards completed its review of the application by the Consumers Power Company for a permit to construct the Midland Plant Units 1 and 2.

During this review, the project also was considered at Subconsnittee meetings held on January 22, 1969, at the plant site, on April 24, 1970, at Chicago, Illinois, on February 4, 1969, March 24, 1970, and June 10, 1970, at Washington, D. C. and at the ACRS meetings of February 6,1969, April 9, and May 8,1970, in Washington, D. C.

In the course of these meetings, the

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Comunittee had the benefit of discussions with representatives and consultants of the Consumers Power Company, Babcock and Wilcox Company, Bechtel Corporation, Dow Chemical Company, and the AEC Regulatory Staff. The Ceannittee also had the benefit of the documents listed.

The Midland Plant site is on the south bank of the Tittabawassee River adjacent to the southern city limits of Midland, Michigan. The main industrial complex of the Dow Chemical Company lies within the city limits directly across the river from the site and provides an area of controlled access about two miles wide between the reactor site and the Midland busi-ness and residential districts. The exclusion area of the plant site has a radius of 0.31 miles and includes a small segment of the Dow plant; no Dow employees are permanently assigned in this segment, and the applicant has the right to remove any persons from this segment if conditions warrant.

The low population zone has a radius of 1.0 miles and contains 38 permanent residents and about 2,000 industrial workers, mainly employees of Dow Chemical Company. The number of permanent residents within five miles of the plant site was estimated to be 41,000 in 1968, mainly in the city of Midland and its environs.

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Honorable Glenn T. Seaborg June 18, 1970 The applicant has established criteria for, and has begun the formulation of a comprehensive emergency evacuation plan. This plan is being coordinated with.thewell-establishedplanoftheDowChemicalCompanyforamargency]d M

evacuation of the Midland chemical plant and portions of the City of,4if a in case of major emergencies at the chemical plant. Close coordinatio, with n

appropriate municipal and state authorities is also being established.

The Midland units will each include a two-loop pressurized water reactor designed for initial core power levels up to 2452 MWt. The nuclear steam supply systems and the emergency core cooling systems of these units are v.4 essentially identical with those for the previously reviewed Oconee Units 1, 2 and 3 and Rancho Seco Unit 1 (ACRS reports of July 11, 1967 and July 19, 1968,respectively). The combined electrical output of the two units will be 1300 MW.

In addition, 4,050,000 lbs per hour of secondary steam will be exported to the adjacent Dow plant to supply thermal energy for chemical processing operations.

The prestressed, post-tensioned concrete reactor contairunent buildings are similar to those approved for the Oconee Units 1, 2 and 3.

'Ihe design will include penetrations, which can be pressurized, and isolation valve seal water systems to reduce leakage. Channels will be welded over the seam welds of the containment liner plates to permit leak testing of the seam welds.

Cooling water for the Midland reactors is supplied from a diked pend with a capacity of 12,600 acre-feet. Make-up water is taken from the Tittabawassee

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River. The cooling wate. supply is sufficient for 100 days of full power operation without make-up during periods of low river flow. In the unlikely event of a gross leak through the dikes of the cooling pond, a supplemental source of water will be available. The supplemental source is provided within the main pond by excavating a 24 acre area to a depth of six feet below the bottom of the main pond. This source can supply shut-down cooling capability for 30 days without make-up.

The applicant will conduct an on-site meteorological monitoring program to verify the applicability of the meteorological models used for accident evaluation and routine release limits as well as to determine any meteoro-logical effect of the cooling pond. This program should be completed during construction.

Midland is the first duel purpose reactor plant to be licensed for construc-tion. The export steam originates from the secondary side of the steam generators and may contain traces of radioactive leakage from the primary i

system. The demineralized condensate from 60 to 75 percent of the export steam is returned by Dow to the feed water supply of the reactor plant.

The condensate from the remaining steam is either chemically contaminated or cannot practically be returned to the nuclear plant. It is collected in the Dow waste treatment system for dilution and processing with other streams before eventual discharge to the river. Thus, the unreturned portion of the condensate represents an effluent from the reactor plant to which the require-ments of 10 CFR Part 20 must apply.

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Honorable Glenn T. Seaborg June 18, 1970 This matter may be considered in two parts: (1) the steps taken by the applicant to ensure that any radioactivity in the export steam is within the limits set by 10 CFR Part 20 and as low as practicable and (2) the measures taken by the Dow Chemical Company to ensure that the export steam can be used in chemical operations without product contamination and that the unreturned steam condensate is properly managed for safe disposal.

In connection with item (1), the applicant proposes to monitor and control radioactivity in the export steam. A representative, continuous sample of the export steam will be condensed for monitoring and laboratory analysis.

T The ganza activity of this flowing sample will be continuously monitored by on-line analyzers and an alarm actuated if the activity exceeds an appropriate limiting value. The alarm will serve to indicate any change in the integrity of the steam generators or fuel cladding. Samples of this condensate stream will be analyzed at appropriate intervals by sensitive low-level beta counting for determination of gross beta activity and concentration of selected radionuclides. The applicant agrees to limit, by maintaining high integrity of the steam generators and fuel cladding, the yearly average gross beta activity in the export steam to one-tenth or less of the limits specified by 10 CFR Part 20 for the selected radionuclides.

The yearly average will include any periods of short duration when the corcentrations may approach but not exceed the 10 CFR Part 20 limits. The applicant states that in his judgment it is practical to operate the plant within these limits. If these limits are exceeded, corrective measures will be taken in the plant or the delivery of export steam to Dow will be terminated. He also agrees to demonstrate the analytical equipment and

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procedures in development programs to be carried forward and completed during construction of the Midland Plant. In connection with item (2),

Dow has stated that they will apply for a 10 CFR Part 30 Materials License to receive, possess, and use the export (secondary) steam as a source of thermal and mechanical energy. No export steam or condensate will be intentionally introduced into any product. Isolation of the export steam from contact with products will be accomplished by the use of heat exchange devices which will provide suitable physical barriers. Programs will be established to provide for detection of leaks in the heat exchange devices by analyses, monitors, and other means; for repair of leaks when detected; and for appropriate administrative control of the programs.

Dow has stated that accumulation of radioactivity from the export steam and release of radioactive materials in the effluent will be in accordance with 10 CFR Part 20 The unreturned condensate will represent less than 10% of the total liquid effluent disposed of through the Dow waste treat-ment plant and the annual average concentration in the total effluent is expected to be less than 1% of the 10 CFR Part 20 limits.

The Committee believes that the criteria proposed by the applice se and Dow for the control of radioactivity in the export steam are necessary and adequate. The detailed procedures for implementation should be developed during construction in a manner satisfactory to the Rasulatory Staff. The Comunittee wishes to be kept informed.

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uP,i wu Honorable Glenn T. Seaborg June 18, 1970 l

To =1nemise the likelihood of subsidence at the site, the applicant and Dow have agreed to prohibit future salt mining operations within one-half mile from the center of the reactor plant. No new wells will be drilled within this distance and all existing wells will be abandoned and plugged.

The Committee believes these arrangements are satisfactory.

A large volume of liquid chlorine is maintained in a refrigerated storage l

vessel about one mile from the Midland plant control room. The applicant is continuing his study of the consequences of a major accidental release of chlorine from this vessel. He has included in his criteria for the design of the control room the objective of finding a practical method of maintaining the concentration of chlorine in the control room atmosphere below the eight hour threshold limiting value (TLV) of 1 ppm for the most 1

serious conceivable chlorine accident. The Consnittee believes that adequate air purification facilities should be provided in the control room ventilation system to reduce chlorine concentration to the eight hour TLV of 1 ppm so that operators can work without respiratory equipment during an extended chlorine emergency. This matter should be resolved during construction in a manner satisfactory to the Regulatory Staff.

The reactor vessel cavity will be designed to withstand mechanical forces and pressure transients comparable to those considered in the design of i

the Zion and Indian Point-3 plants.

I The applicant has stated that he will provide additional evidence obtained i

by improved multi-node analytical techniques to assure that the emergency core cooling system is capable of limiting core temperatures to the limits established at present. He will also make appropriate plant changes if the further analysis demonstrates that such changes are required. This matter should be resolved during construction in a manner satisfactory to the Regulatory Staff. The Consnittee wishes to be kept informed.

The safety injection system for the Midland plant is actuated by either low reactor pressure or high contaimnent pressure signals. However, of these two, the reactor is trip # only by the low rasctor pressure signal.

The Committee believes that provision also should be made to trip the reactor by the high contairsnent pressure signal.

The applicant plans to develop more detailed criteria for the installation of protection and emergency power systems together with appropriate procedures to maintain the physical and electrical independence of the redundant portions of these systems. The Comunittee believes that these criteria and procedures should be reviewed and approved by the Staff prior to actual installation.

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n g gn Honorable Glenn T. Seaborg June 18, 1970 8

The 4pplican: considers the possibility of melting and subsequent disintegration of a portion of a fuel assembly because of flow starvation, gross enrichment error, or from other causes to be remote. However, the resulting effects in terms of local high temperature or pressure and possible initiation of failure in adjacent fuel elements are not well I

known. Appropriate studies should be made to show that such an incident will not lead to unacceptable conditions.

E The Consnittee believes that consideration should be given to the utili-zation of instrumentation for prompt detection of gross failure of a fuel element.

The Consnittee has commented in previous reports on the development of systems to control the buildup of hydrogen in the containment which might follow in the unlikely event of a major accident. The applicant proposes to make use of a technique of purging through filters after a suitable time delay subsequent to the accident. However, the Coasnittee reconsnends that the primary protection in this regard should utilize a hydrogen control method which keeps the hydrogen concentration within safe limits by means other than purging. The capability for purging should also be provided. The hydrogen control system and provisions for containment atmosphere mixing and sampling should have redundancy and instrumentation suitable for an engineered safety feature. The Consnittee wishes to be kept informed of the resolution of this matter.

The Consnittee reccannends that the applicant accelerate the study of means of preventing consoon failure modes from negating scram action and of design features to make tolerable the consequences of failure to scram during anticipated transients. The applicant stated that the engineering design would maintain flexibility with regard to relief capacity of the primary system and to a diverse means of reducing reactivity. This matter should be resolved in a manner satisfactory to the Regulatory Staff during construction. The Committee wishes to be kept informed.

Other problems related to large water reactors have been identified by the Regulatory Staff and the ACRS and cited in previous ACRS reports.

The Consnittee believes that resolution of these itens should apply equally to the Midland Plant Units 1 & 2.

The Consnittee believes that the above items can be resolved during con-struction and that, if due consideration is given to these items, the l

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C:U d Honorable Glenn T. Saaborg June 18, 1970

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nuclear units proposed for the Midland Plant can be constructed with reasonable assurance that they can be operated without undue risk to the health and safety of the public.

Sincerely yours, v;

/s/

Joseph H. Hendrie Chairman References

1) Amendments 1 - 12 to License Application i

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