Text

Initiates & Provides Direction for NRR Review for Major Issues Raised by British in Application of PWR Technology in Sizewell B
	ML20132F393
Person / Time
Issue date:	10/25/1982
From:	Harold Denton; Office of Nuclear Reactor Regulation
To:	Eisenhut D, Hanauer S, Mattson R; Office of Nuclear Reactor Regulation
Shared Package
ML20132A685	List: IA-83-619, Forwards NUREG-0999,NRC Rept on Sizewell B Evaluation. W/O Encl; ML20132A682; ML20132A688; ML20132B510; ML20132B572; ML20132E820; ML20132E840; ML20132F098; ML20132F115; ML20132F385; ML20132F393; ML20132F410; ML20132F430; ML20132F452; ML20132F481; NUREG-0999, Minutes of 771111 Workshop on Simulation of Nuclear Fuel Rods in Loca.Viewgraphs Encl;
References
	FOIA-83-619 NUDOCS 8507180428
	Download: ML20132F393 (32)
	v • d • e

P o

9,,

October 25, 1982 '

DIST?.IBUTIO!i !

Central Files ECase BYounnblood JGlynn TSB R/F JFunches GEdison HFaulkner -

H9enton JCarter RBernero EGoodwin ,

i:E:10RASIDU 1 FOR: Darrell G. Eisenhut, Director DL Stephen H. Hanauer, Director, DST Roger J. flattson, Director, DSI Richard H. Vollmer. Director, DE Hugh L. Thompson, Jr. , Director, DHFS Paul S. Check, Program Director, CEBRPO Bernard J. Snyder, Program Director, THIPO FR0i4: Harold R. Denton, Director Office of :luclear Reactor Regulation

SUBJECT:

SIZEHELL B - A'IALYSIS OF BRITISH .'

APPLICATI0!i 0F U.S. PWR TECH!10 LOGY

'Purcose

.To initiate and provide direction for an I;RR review of the major issues raised by' the British in their application of PUR technology and of the-design changes that resulted from this application.

Bactorcund The Central Electricity Generating Board (CEGB) of Great Britain recently

.=.pplied to its Secretary of State for Energy.for approval to build a nuclear p:uer station at Sizewell in Suffolk, England. The !!uclear Installations Insp;ctcrr.tc P:II) is in the process of rcviewing this application and will begin a public inquiry early in 1983. The Sizewell "B" reactor, which will oe the first British nuclear power station to employ a PUR design, will be similar to the !!estinghouse SNUPPS reactor design. The design of the Sirewell 3" plant contains several safety related systens that differ signnicihtl)Troa S!iUPPS.'~Further,~HII'ha~s TdintiTied certain areas where they are dissatisfied with the application or where they required further information. Accordingly, it has been decided that a review of the Sizewell *

"5" design differences frca Si:UPPS and the ilII findings on the design be pcrforned by NRR so that the differences between the U.S. and Fritish FUR reactor practice end acceptance criteria are identified and the basis for -

thcir adoption understcod.

Action Enclosure 1 is a list of cpen and mjor confircatory issues raised by :II during its review of Sizewell and of najor design changes to the' S!!UPPS 6nig: nide by CEGE prior to submittal. The indicated divisions are to prepara 5 difference analysis en each issue and dssign change listed in Encicsure 1. The analysis should follow the format of Encicsure (2), should address the following:

8507180428 850606 PDR FOIA ,

SHOLLYB3-619 PDR

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(1) A detailed technical description of the design change or issue.

(2) A description of the equivalent design or position taken in the SNUPPS applications.

(3)

AdetailedtechnicaldescriptionofthebasisenwhichilRRfoundthe[F equivalent SHUPPS feature adequate. 'd (4) An enalysis of the safety benefits the CEGB change was intended to achieve or of the safety concerns underlying the NII open issue.

(5) Questions on detail or reque'tss for further information to be put to the British.

Division directors are strongly encouraged to review those portions of the British docket in their area of responsibility to identify other important arecs to be explored sinilarly. An analysis of these should be prepared on

. the. same, schedule. .

This review and analysis is a high priority effort. Given the short ischedule

%d interdisciplinary nature of m5ny of the issues the effort is likely to require senior level individuals.

Conflicts in schedule and resource comitment between this and other efforts should be brought to D/PPAS thru Ed Goodwin for resolution.

Future Effort .

When these analyses are complete, they will be reviewed by an ad hoc group consisting of S. Hanauer, R. Bernero, T. .Novak, H. Faulkner, and E. Goodwin.

This group is to identify those nost important issues deserving detailed exoloration with the British during e technical exchange visit in Decenbar and to identify the members of the !!RR exchange team.

After the exchange, a detailed report is to be prepared. ~

"anacement

The overall N'tR effort is, to be coordinated by E. roc #.<in of PPAS. The de.y-to-day management and support of the review effort is to be runaged by -

DL. The technical review, paper flow, scheduling, co..mnications, and resource management are to be handled exactly as are SER inputs. G. Edison, LB-1, is to be Project Manager. Dr. Edison is to open.a TAC number, mnitor schedule and resource expenditures for this effort, coordinate the tachnical -

re.iaws, and prepare the report.

O me a 46# *

.. p.

t Schedulino .

Reviewers identified to Pli 10/27 _

Briefing for reviewers 'and management 10/29.

Additional topics identified by divisions 10/29

- Draft analysis input to PM 11/15 Visit agenda prepared, issues identified . 11/19 l

- Exchange team identified 11/19

- Final analysis to Pit

11/22

- Tead briefed by reviewers 11/22

- Final analysis to team '

11/29 Visit to UK .

. 12/6-1p .

- Input to final report 'due* 1/14/83 -

- Report ready in draft 1/28/83

- Final report published 2/25/83

Typed input from AD to.T. Novak with copies to G. Edison and B. J. Youngblood.

References tiRR has obtained a copy of fundamentally the entire CEGB submittal. It consists of the following:

- UK Sizewell B Reference Design

- CEG3 Pre-construction Safety Report CEGS Staten:nt of Case ,

- CEGS Prob-bilistic Safety Study (h' CAP 9991) '

- UKAEA Degraded Core Analysis *

- 1111 Safety Assessment l

- Associated Documents -

Copies are held as follows:

- Each division director

- G. Edison -

E. Goodwin A. Thadeni -

LB-1 Licensing Assistant (2) 4 e =

m p at..*-

i- ,

f As further information is obtained, it will be distributed similarly.

Appended to this document as Enclosures 3 and 4 are a general description of '

Sizewell and a listing of design modifications. ,.

Drigissi%,

H.R.Duten . .

Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

As stated .

cc: E. Case '

R. Minogue J. Shea T. ifovak

SEE PREVIOUS CONCURRENCE SHEET o.9 r.t \n

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ENCLOSURE 1 APPENDIX I Major CEGB Changes to the SNUPPS Design _.

1. Use of a secondary containment (DST)

$53 Orr 2.' ECCS modifications (DSI with DST support) .

a. Two segregated steam-driven emergency charging pumps with separate

' water supply and not used for SI

b. Upgraded isolation between R,CS and RHR '

~ .

c. Four 100% HPIS pumps with larger capacity and lower shutoff head d .' Larger (50%) SI accumulators .

e. Four 100% RHR pumps, two for LPSI, two for CSS with automatic

, ,switchover Q fagotI3. Two . additional diverse 100% cooling water pumps for fan coolers to i /Huen6 improve containment reliability (DST with DSI support) hS[Ovr 4. Emergency boration system (DSI) sg / Ma6 5. Increased containment diameter and lower design pressure (DSI)

@n I 'b ad & 6. Back up reactor protection system (DSI) -

Increased equipment redundancy (DSI with DST support) ft/Leket 7.

I.

l .

. .a. Four segregated 100% AFW pumps (two electric, two steam) l b. Four 100% CCW and ESW pumps (also emergency dry cooling towers)

.. c. Four segregated 100% diesels

8. Vessel and piping manufacture and inspection (DOE) ,

Layout and ALARA chhnges (DSI) hA k k h .

10. Redesigned control room (DHFS) ,

Coen Issues in the NII Review

1. External hazards - fire, earthquake, and airplane cra'sh (00E with DST support) ,

t E p er 2. Fuel clad ballooning (DSI)

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3E$u??d 3. SG tube integrity and multiple SG tube failures (DOE with DSI support) b bs te .

3g /ggg 4. Integrated and secondary reactor protection system reliability (DSI) g/Meyer 5. Accident code validation; ATWS and severe accident analyses (DSI)

NII Confirmatory Issues

1. Human factors analysis (DHFS) -

2. QA(DOE) .

?SfEgos3. Accident fuel performance code validation (DSI)

4. RPV and RCS failure " incredibility" (DOE)

. 5.,. , Component classification and design standards (DOE) ,

(Bfd)ergst6. Extension of approval for non-remote sites (DSI) ,

as ALARA strategy, occupational exposure (DSI)

$ $ e.7.

4, G

9

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s' ENCLOSURE 2 SIZEWELL ISSUE ANALYSIS

Title:

(Should uniquely identify the issue.) -

Description:

(Describe in 50-300 words the details of the design difference or open/ confirmatory issue identified.) .

SNUPPS

Description:

(Discuss in 50-300 words the SNUPPS design or licensing position'on the issue.)

U.S. Acceptance Criteria: (Provi,dein 100-500 words the U.S. acceptance '

criteria and an analysis of how the ShuPPS plant met them. Don't just quote the SRP; explain how the design technically met them.)

Analysis: (Explain in 200-1,000 words the safety benefit the CEGB design change was intended to achieve or the risk underlying the NII concern.)

Areas for Further Exploration: (Identify further data required or questions to be asked during exchange.)

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- ENCLOSURE 3

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GE:iER AT!ON DE*lELOPME"T AllD CONSTRUCTION DIVISIO!!

SIIEWELL 'E' FWR ,

R I The PWR Reference Design (Aoril 1982) E

. i 1'

- A 'Comoarison with SNU??S and the Unadooted DesJen (Aprii , !

1981) l '. Introduction .

- i:

6

. I This paper co= pares the*NHC April 1982 Reference Design !

I with (1) the S:lU??S Design and with (ii) the Unadopted (April 1981) Design. The information is discussed in the text and also presented in tabular for (Table 1).

. It.should be noted that there are a few general itees .

id'eitir'ied in the tex (mainly associated with contamination control) which it would not be .

appecpriate to present in the table (where itemised g changes are specific). Apart from these the changes -

(

presented in the :able are slightly more extensive than ll these identified in the text. In both cases, ccly the '

j more 1:portant design differencen are identified. ;

. Clearly, it is a :stter of judge =ent as to the level of- .

de:sil down to which it is appropriate._to go. 1 The April 1932 Reference Decign was evolved by a fresh start from the 31.'U??S Design and not by =aking changes .

. . to the Unadop:+d ; April 19ei) Design. It is therefore n:: meaningful : des: ribe the Reference Design on the ,

basis of ' changes' froc :he Unadepted Design.

Differen;es be: Ween these two designs are, however, not

:c the detri=en: Of the Reference-Design.

The April 1932 ?.eference Design is jus:ified in nuclear .

safety ter=s in the.?re-Cor.strue:icn Safety Report. It is nc: the' inten: ion of the present paper to restate or -

su==arise thi: justificatien. Rcther, the paper si: Ply indicstes brocd , easons for desi5: provisi'ons which .

differ from 3::U??S and co=ments, where approp.riate, on '

the provisions in the Unadepted Design. .

In previding the descrip; ion it is ::nvenient c, ,

lassify the'fea:Jres of the varicus designs in six separate categories, which tre discussed in Sections 2-7 below. .

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2. S .=. f.e t y features 5.ddec whien were nisc! renon: in Unaccoted Desicn -

There a're seven =ajo. safety features which bave ?

. heen added to the SNU??S design :o give ne Sizewell

'E' design, all of which were also present in the April e 1981. design. These are as follows: [:.

e (1) the four-pump High Head Safety Injection System c (HHSIS ) .

(ii) the separation of the functions of the HHSIS and charging pump system (iii) the larger accumulators ,

(iv) the forged-ring reactor pressure vessel i

(v) the Emergency Beration System .

(vi) the use of a 4-pump Essential Service Water Syste= (rather than a 2-pu:p* system)

(vii)' the provision of secondary containment ,

3. Safe:v rectures addec which were not oresent in ]

Unaccatec Desien _

r There are six majer additienci safe y features added to the SNU??S design to give the Sirewell 'B' design, which were no: present in the April 1991 design. They

he.~efore repreten: En 1:preva:ent over the.ia::er, and

2. e as fclicws: .

~

(1) the =cdifications to the upper secticr. of the !

. F.eac:cr Vqssel Cavity (allowing external in- ,;

service inspection of the r.02:le regicn) j i

.. 11) the Auxiliary Feedwater System with diversity !

cf pu=p drives (two electrically driven and two steam driven pumps) the co:puter* based Resc:or ?rotection Sy'ste:

~

(iii) wi:n a dive.se secondary protection syste: _

(iv) :he provision of a stas ' driven ene.gency enarging syste: _(' soc r.d steas driven .pucp .

inclu ded' af te. review - see Fcc ncte).

Fec; note GThe starred itc:s of the lists in 2ecti:r.s 2-5 wer,e included in the ?.eference Design as a result cf the review wr.icn fellcwee the issuing of :ne Reference Desi.gn. Report and ?re-Cens .ucti:'n Safety Report in drift fors.

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(v)s the provisivn'cf two additiendi pumps witn }

associated pipework between the containment ran ,

' coolers and the reserve ultimate heat sink to

provide increased diversity of the cooling supply to tne containment fan coolers -

g ,

i 1

10

( vi ) the extension of the high pressure piping on F the residual heat removal (RER) suction lines !

c to the outside-contain=ent isolation valves. . .

This will reduce the probability of t loss of !

coolant accident occurring outside the containment.

4. Safety features added which differ in detail from the , p Unadopted Design *

. 1 There are four =ajor additional safety features added to the S"UPPS design to give the Sizewell 'B' design, -

which are different in detail from those in the April 1981 design, but which are provided as alternative ways

, of achieving the appropriate safety standards:-

(1) the arrange =ents for actuation of the ,

recirculation phase during a LOCA (Loss of Coolant Accident)

~

(ii) the Energency Electrical Supplies (iii) the interchangeability of Residual Heat Removal and. Containment Spray pu=ps -

fiv) provision Of additional isclating valves in the feed lines and space for additicnal isclating ,

valves in the steam lines. .

j I.

5. Desi n features added to reduce radisticn ex?csure c't COeratorS

n' addition to the safety-related ch.anges the Reference Lesign incorperates a series of ceasures designed to .

reduce radiatien expocure to operations and naintenance staff. These =cssures are either the sa:e as, or

e:uivalent to, =ersures in the Ur.adepted Design. Tncy

. include:

fi: the adoption of' a narrow vessel cavity b "y Ma% % M i

(;i) the use of a culti-stud tenticner and the 1ntegrated head package to. reduce the ti:e -

requireo to re=ove the vessel nead during

.efuelling (iii) the additien of some permanint sub-charge reocs, tarriers and wash facilities 1: tne Ocntain ent

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(iv) improvements to the ventilation and cir .

filtration systems for the' contain:ent (v)- an increased contain=en di a:e': e r , cnd -

r (vi)* improvements for personnel access and ;

containment control including an extension -

building with change room facilities and additional sub-change rooms. -

[

The SNUPPS design foresees a figure of arcund 400 man-res/ year as the likely operator dose. In the UK .

Reference Design these various design changes are included to meet a target of 240 mah-rem / year. The 5 introduction cr.these changes, ghile a'dding to the .

cost, can be justified bearing in mind the guidelines - -

which require the industry to take all reasonably ,

practicable steps to reduce operator doses to "as low as is reasonably practicable". -

6. Design' chances to meet UK oractices and Sizewell Site RecuLrecents -

A number'of changes from the SNU?PS design are required to =eet UK practices and Sizewell site requirements.

Tnese same measures were included in.the unadopted -

design. They include: t 4

(1) the use of two :urbine generatcrs rather than one -

11): ne use of seawa:er ecoling fer the 'cor.densers .

rather than river water Ocelin3 er c: cling .,

o'ri t rs 1

~

(iii) :he u'se c? SOH: electrical caccines including $

reae::r ::clant pu=ps !

(iv) extention of syste=s :erved by the cc enent cooling water systen because the essential service water syste: uses seawater - -

() the use of an air-cooled heat exchanger rather

~

than a large cooling water pond for the reserve ulti nte heat sink.

. Tesi:n of Auxilisry Buildin:

The referenca design utilises -he SNU??S design of auxiliary building. The unad:pted design hac a " wrap arcund" tuniliary buildin; unich surrcunded the *

ntainmen; building entirely. This concept fa'iled to rake the best use of the Se:htel experience in ~

nstructing he SNU??S design in the United States.

. Tne S"'.'??S laycut relies less.cn p..ysi:11 tarriers te

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!;evertheless, the April 1982 Referenc*e Design achieves !!

the mere extensive physical segregation appro;iriate to !

=eet -

he CEG3 Design. Safety Guidelines, whilst still l re:Eining the benefit of the SNUPPS arrange ents. The' !

unadopted design was also built on a ccamen concrete 5 raf:. shared between the. containment and auxiliary l' buildings. This feature was considered unnecessary li following the results from the latest site j' investigations at Sizewell and analysis of differen,tial -

settlement under normal and seis=ic conditions. .

Figure I shows the general layout of the Reference Design and of the Unadopted Design. .

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., . b. - .b b .* t....h . ., . .

..h. ..e.3..-h.6- h .t. .

. .b..,. .. . . 2-6

.b

=

i.

..1.

.., .. .. . . -. ...h-..

-6 t

. .i. .. , h. .,. .,

. .w.

w i.

..I...

i. -

. b. .I .e 6- . .. .. 4

... m

b. . .

b.

i. .

wt.- ... ..

., .. -.. i l 6 .

b .. b......

4... _ .., .. . , _ ..

_. T.

w

-_e . _.. .

i 1

b .

I, '

r

. . s . . . . . 8 ab .a = .

.a.s .e. . - .e. .e. .e.s . ,

n4 . . . . . . . -

~

2 2 "X.h n

2 2 2 2 2 :

g .

, t bd

.. be.

= '.g

e e g e [

, . . ** .=, e.* e.s

. 4 . .D. .D. .D. ,

-6 . & i

== b ' M , W . M R . 6 I

. . M. . .

b b., '

8. %6eU l

. . 19.R. . . . i E .n. _a .n. .=. .n. m e. .n. .S. *. .M. .e. _ I

.* . \\ .

h t

W 8 8 *.f .h b U . . R 9 .a , . p. ,

- G A w

- .D 1 = b. k h Ub W m al n' W r. 4 .w.

6e .# g i i

h .9 -

-e q0 *. .O.,* b .g .e b. g. ey " y ., W g g&, .. !

., O ., == b 1 e. tg . g g.

E, .'l *2 8 ., .* *

8. 6' . sb ,

es t 8 .4, ' & R l . .3 g nh.6 a.s 3. 3

- R .b. fi "3

>.e i

1 4 b '3 4e

.e.dW 61

' J 4 4 .* . t, I

-3 . b4 3 ft 6 tot l "s. ,' vi r .o.f.. C e v.n

. 'bR 'l . l as . "3 4 A se . R. .wn

.'.: A= s,. l cw

., 9w 6 - ei n .a W n l'e L=

n. .

4 l

nu 4

a b

6. 1 -.9 l'. V W b - n.

9 . t 8.

't & U- 8 . . .& '432 ,8 F C. U f *

.E ."..

61. - .0. .b. 4.

h 6

6. .. . 2. .o. . .u. . .t..as. . ..

g .

g g W y i' .,

h 0

5 3, .

. *h .

.n, . 0

. 1 l' .: s. w .- n' .

, . s i- , . .

4 I & h e b .a em ==

=. ed 3 M ,

I' T .h a

d b .3 T #. W l

'u s 3-1 .

w b 4 W Wb bn j .

- 14 4 5, E AA A P G W e

8 8

-b b W .

gi l s

. D .D. M

2 b .S. AS. W i i .4 Wb ,

5. b i

b

m

g. *3 - 4 .b . .e.d.e .e 6 ,,

m I w- wa b 3W - t' W .

33 6& Tt .W. el y .e 9 - y e. .# - 6. !

61 *" M '*i .b . *% t M ' . . * . l.

I es D 4. ft b b&B 6 ., 3. '

E A 85 '

L, .. .n.4. . .i a. 85.'i . .n. ....

. .. .i . .u. .. .. . .

i

.a. .c. I. .4.. . .u. .r ..

l. Un m

+

I 1. l i h6 6 d 4 ,

, t

' I!- ____.__.-_--___ _

e e., m

--e,=

i l _ _ -. --. wsa l *.*.

4

. -%O?s r*e

,, b ** e se e

- e;pr- ;

-c

. - . asw ***

' [ g. . l o ww

l e, . . 8, .= . e f. s

.. .. 1 .; e. . ... . . .4.

w 41 '*** **

.e

..t ta . > r b 6. e.i ..e* s==.*%. se a 'J !4 . !'

! - - .4t. +n t ....e e

'6 I

.. e , se .6 .. + .

. . e. ..e:e .f.*..e .

. e .. . . . .e

e. q y g e. gJ ,

I

w l,

p. se s e . e t' wT=wMP r e. e s w C C et =

3. *v e* es 4 4 4' e ip**ee.e.. g ,,g. e g g, ,, w g, i

=4= 9 r. L . t? n

A= l 2 Uw=C

4 I 1

vu 6nr system ibLUb4%b 4 34=4=

CQC I wRCC3c w&Dng- '

p=c C 1 q= mW= & s t- e n b = n ed & A b u6 e w

' & = 4 bl 2 4 '. & ==C 8 TT W"b . =Eu 4 r g

- r: vt

'. =t e n = C n =1 WP , 3 t h= 9W w

Vb& 6t Ch:

=

t a = ha et 4 94345 eWO PW j Dn=. I g =gtg s 06 *Oe Wwr2wnw , &Wkw gas =Cw C Tw Cs4 42=C"C Ub= nCC=W e

==tw ==U W m = W3TW se = M WR414 b na b b4=== b2bbWO

= ' na W== i Vm CD =Lw Ud2 &= 9498 n w &b b C

't etyyg =0Wa

n 1

4**wJM WIONab DJ9m e *A&M C=w Bwb . 96Om

=

nbb &L

'M g

L3b63b == 4C=wbeef =bnm

=A & = b 4 hC=Wm2

t DO4WUD Sm n444=Gw O wwWb OCWw =uCutwD CUE LU= &W4etG b G U C- 4 bWC &n m te sWwaW43 4Aihb4 LwCO L 6=9=OGM '

=

=========-======---=abA

= b3bebbwe Hww

= = = = = = = mwag

=

CM=49"a

= =g ======= = r. b A C S S IM O u w 0 mC a 3 C C b =g n6 MTw4 n =n&

C C bWWa Cp W W W3 $3 sW $W uC "

E *

&&S

= w CabD 36 =CC n n enWwotw 3 W

&ww=

h 4 d* O C s ubw3M &== C

W W wwmem D 6 a man =

A A w*wbabW M SSh C % w&

3CCD QW e9

=

e e6.a W

MX& Q e e6 wb m.

o hm

===b 8 4 S33. w W w5 3.=nb b=v.

00=

M

=e WC P g CCC wCO Em wk Cul p 3

W =* me wasth at 90 Cn mk &

b39 94 5w C %beSW6C W = CSTC eW .

=W W m w tb b.O b 5 0 Cn=4 wg ag MT&= am 1 tw w

, bb e eD=4 *We Wnnm>w nuww a &W = w 4 3 a m e s$ s C w eSS C=Se bM %

y gm W w uw mana w ,b Wb 9 $ wCCWW4 ew>gb= Gmem =b I

e C=0Cnbee SSLaCDsSS 93engbgu n w

acon 0 mm 9a M anDw3b4b bwb

. = = = - = = = = = = = - - = = = = = = = = = = = t s == &.5. = == = = W =O w w

==-====-

an w C >

3 W 4 0 m D = h b u C b nga w N W & W

=

= w O 4 C4

& Wb W=nm # WL

= n bean C EC 4 . ObO e383n w E = Sw w

W = l bC nD31M ' C E 2 =O J =

a

,8 3 : w W=wou =&=W W = w Os -

M4

. CWbC Tn >m n= Db

e &

e 3 emW e0 eW== [

s CW3 eb bw b

3CSwwm DbSTw = CC w Mk H 4CCpw 2%*29 4 =TC Ca l= C4 4 hw=W U 4Cw=

g 3OS 3O=2 w C

M=DD C wE q

wt M

j=b 4e C CWwwg3 O= Web c = cec e

.&C t Web u wwbCO & lac = be

@ W6 S=nb D = n l4 3 a '

bbW3&= bWw79 L$

===6

&wEw Ut

b

90 789 =Meem Su UbC =b I WWwb&79 . CC&WS 93 b2WC 9C 6& =n=

- w .m .ae= = = = = = .. .n S b & b= = = = = = = = 6 =b = 4 '= " 0============....O.===n= -=====-

e l n l b .

b O

h e

W L

I

'M g 'k1wWC as e h w=n3 h

b '

t w j C w *J b4C6 Ob 3 W9 &&

C b0 **

2R MWCVO i

m b25w M = =

n = = V E u r. C RSSn.

a w

~

m * { w *=133w l e E. .A D=

== I ' n=Lh I

& l E 81 == #8 0

=

va g3 wbC 6 r. ' [ =b .' 0 4 3 & w .4 = 5 0 4Wa

g y e' mmtus=w=, abeb u

I' CD3 w u r.

b t

w a y gg ggggg pg> g .C

C. =C9g e . g .

l n

a 4 8

= st=w&

w m bwm n 2: *4 OIR w 4 Wa t C =

' 4e b=

~.

A M l"= Da b 43 3=&W

C = C4 l .

b m PJ t 7 % w m W as64 &OC=

4b g m 9 73 g I'

==3nneb w '4 R w b 3 &

=y

%wJ

' vn& ===n Cn l

m &w Em 4 r. X

a =CW bOCS& 094W C4 U.C wWC I'% l C= bw43& SE%= 33 bWWC

'e l *

>=

Mb4

b. e.-= .=..M.=&..w. r..*..A..b. .j .- =. .J. H&

3. .e ==.===============.ete=====..h..w... ==== I E n l

gC 9 e6 8

e L 3 i a . o -

e

?s e =

a n .

=

m lb l '

6 e . 3 8 4 $ , r, c . + ~ .

g l$ d . - * .

l t * ,

yg-

'I .s bh . .

[

g m..me.ema=========*.**==================l +***b n

* * * * * = = =

e '

I a

8 e e

o

e e ,.

I E

I

. I

f. .'

.--.. .- b --. ---- -

c 2 b en

e

== .d e e *: J.d 'O I C , b e .tr c

.30 ,C == E O E == @n C **

. 8 ooc =#

40b :n 3 8 CL *E '

4 3 &D I E 6 .C = 0 eb c E *: .n 1 -

fO == C i &W '

b *: "" F == w LCLb 4 .A L* 4 n = 00

' te == = is iTC L .* C C .d I : a == b O l .d : i C. O .8 C L .e .A L 1: E Cn V P. - C lc "O eh> bo e cCbc .= h c c = .i. =c c C. .# 6 8c > UL i e =.==>0 ts & to E = > L b O a- la 4 C 4 r. d .d &ChbnE: hE s c =.eO D E bL E 4.d 0=d b .3 .A R C .= C nU == C ': = 0 W b

?

P,,,; .a O8 o

b .* ec n .= to 4 0 &CCE.eb C. b n 3g = b c .= 6 .* b c L C

{1

+-

g 1 4 g 6. .d 4 C 2 == C. to JU C 6 == ed 3 .*e

= :. O Ch7C a g .e .= c 6 : E = '

sb U 3bU ME 6CU 3LUe == n = 3 ** = = .d C 0 0 == 0 C =a O O b .* C O .d bA OOe43e .* ooc 06 m0 >= c 0 9. L .*==.4= E 3 -e T d C 3 L O == 0 e

n E .0A o ne o C. .: non o o .= C ne c 0 3 > .* u o == - e

bnv n e i. u . eeoN e s a o u .* e.c u a C 3 e = .A b .d n .e t.

O 3 == 4 > t .3 O b " ed .= 0 .D C C bb o n "3 C .: b .A = 6 .D.

= = C"O O C b *

C .d Lb n> U O b == a n> 0 C b 'O 3 h t n 0 = ec ad O n 61 O b o34= 0T CE

.d = oo eOCC 0mb es e e C C == 0 0=b n C = > me c & O E C b .* C > c n ": e a n ed C. n K == c U C OOm = a C .A C. O C. 3 = C .A OM= bee b e=6e40.=CC

= COC = o b e h a n C. == L c .A gh C == c .d b .= b et n b 'C n9 0 L0 0 .* .h A C.b De C

n9 U L .d 3 3 .= f1 m L L 9 .e uC>UV O6C > =

== == U=0 0 == .A h b a .* WOW = .8 h b 3 = C.b n e ====0 3 C= CV

b O O C = =.A ec =

C. nU=eL f1 C .8 f> 4 n n se =e b n e .A G3 1.1 n 9 6 n b E G1 == eet C U.= C C C 0 to .= >, 3 .e = b L U b .d 3 >= 3 .e C .* b b .a b >= 0 to .* O .t .E C == *.

t4 .eh .eb .d 4.d 2 .= C" .* 3C>30m .e CP =e b#E E C*O

b .d &* bb To .D e En .*ed b > n ed to & C = 'O .A .8 ebb 4 0 .* O ic > == 0 C =. M D .e O C > .d W .A *3 49Cn3 GOO 3ooon: b c - == C C L C30h& C "3 A = == == b D 3 e C 'O .O A O = se L C O C 4 o h = > ** e E b UECc>CCUC s

-.n.-.

at b3L 4 .e . - =d= b U

. C "J .n..b 4.

( 3

. =4r .e..e. . 0. .Q. 4 .t.o.3 E.

O 4 *. .E .n. 41. .>. .c -C b & .C.

. -. b. A.L. .n. .U. .=. .=. .=. 0 f

0 5

.e b .C=b c C na : Onoe a I.

ta C. = n n Osb=J e =

.* E nG Q3=0 h O r =0 5 .U

E L eLeaU n =

v n 2. C. 3 b OUU U% .d e Q b C. .d C .*== C E "O C c ed N c .* C. O CN0a L 'D 5 U .d C: .d ts .a D C.M gC.O*e r. .C* O:

'C% c e ed a C .O= C0 =e et C = .a .3 m b= C U = .tr O 9> toCEOEEN 4 O e G ** z==v' b uE *

.* C n ; N b h

o .C=

.* L == n & M b == C U M C. O O O

.e U C ~ LA U C 9 L .0 ad C .*= s '3 C .

Lb =C .d 0 0CQC CC WUE e ao b= = N .a. =b>b .* O .e L "3 =# IC 4

% 'et n l v .= 0 C. > v = G L .A 0 e4 04n M .O e m C. n aO M .e et .d L ee 0 M

= t > '

C == 0 Uc4 L=4 oOEh .

C e 3

.re .e .N 6 .".3 . . .N..E .T .n. .b. .N ."3 = .T..L.: n -- .- l' a I'" *

e L '

C 8

M U C E

C e

n .d SJ U = L r! O M fd b .* .d C'%

w ed 0 C. n 3* N C. O C. .O *b C n b

=g n Em hb n URLs LNG h CC s I r. . .= = T : C. .= 3 C C = *e : n b= ,

f ! O L C. . E bL 8 s1 3 C ed G

E: s E

W : Tn

'd.: t Cl [ = > E e, c. c a: o : ob -

ou.Aoeb a

- r. E

=I P i l eo e n = 3 ed =L9UE 8 = 'O C as t '7 Ul *J .# M ed C. n p b n b E .d E8 '

aJ == 4 l We - .d b r. l a h ar c 9 h .d 3 e a c

c > i CJ C. > 6 e .d n 1C 3 nc.3 n .A L O D.

n 0' = 1 2 H O 7 n ' C *bC O 0= .= ': 1 ! C. l b C. p * *. b= C C. C. 0e9C D !

A 'e 3 C. C .

u n. : u , E: =C L 8

ovunu L b .8 o s. n l 3.

j e G C* b a b l .l*. 'C ed V to t

'et 2. .arb .,A & D Jr .8 O .1r M 4 = = 0 O b .4

' L "" O ". Nd U C 3 .* U C. .= C 0 m 4 L =i t 030Ca r. : C ULEh

!. u , = :

e -.=..= 1- m

.C/.- ..

m-

.E3.=.C===

. . --- .....r9.n.

e

- _ e t

. e c

I

., I L g *t y E t y + *

C 0N I

.== n '

r. I '

.s E

'h = " r. 10 AH ab

, in bb l E .* OE > C I h-

!3 9: 8 2 ": =3=n = '

n r.

sn 1 L LELGO I h

,4 '

.= M n l U L e d TEd b C6 l

= 4 9 = > E 3 9 j == C e en 46 nm = U "v 5 L = -

u 8 8

P.J L u .e L =6 4 P. 8 V!

.- 6 *. 3 '

n= 8 5 C 6 n .a W 3D D *.*. Cte ': 3 b=

.. t b= .= 0C e e n ec = D l C T l t 6 6LD C C. bo '

.3 C b 6 4 E ad E C M e Lb * : !

= = k : ** 0 *= bCn>

l

ns 9 E CC a=b = =

e W* l m .A ** 5 =e E 9 L == 0 l at .# M ,

C3 :

h 2 .4* g O 0n '

M. .

.n .N. 5. .m. a 4 .n. .E. .=== .=. '

6. .N. 3..C

. -- ==

-- =

s #

- t C v l 4b W5 t

s bW l 8' 6 6 d '

3 3 kn d e. U e %% :

' en 1 CM 83 c. '

ib u9E ==

E.

';,,, L e .#

=E 5 V, . a y a qa ,

um* e ; ma un

; 4 '

Ch

8b>

.ll

OD_

a

f e *

. e

.. h.

(

t

- i

== I E e == .n= n n .a 4 C =3 e eoe c : C e c c 8* g g ,

EeACEe3 = E. L =. .C *= 0 o l T 6 g >

lC O n .* O O = W 4 C .* & CTO t* 9 *: .: 1 e .g .

l t.5 Uh n ed N L .* W3: E =aC C l

-. Cr, .# .a g> s

.C nbenn= CC nM C009 2w= Csw - 6 o C e ggg g C 9 0 9 h =* M =8 8 hC C S. L *' E .d n U

.= 0 L = g (3 .

&L n M= 2 .#.4 .e >wb .a s .a s. j.

.g lu *.a & D W n 6=2 .8 .* nS e. &ME3L ft M O O@ U = .3 l==LmE C&

g g .C. .C. g .a g,

.8 E=L 4 == 'O K DE as C g* t,: Jg n 2 '

. . C ]/

b. 4 O ed &

4 0 ZW D L == W I". C D 3 h3 8 -e .e 36AO O.a, 3

O C3n .s 14 M e e as .a *.

O = b G == n 4 8 C Og aw m heb3S=@ On abo LnOUt0s I unO:== = C=C j*

C .=EnJ3LM LCe e O ** 4 0 b a n *:f UUO n .a e ==

D M L n .* O -e E o o o a n o.o A c .* O n nT o e o q*n a LO n C .y t == *TW= & == 4 3 A em C E n C. O & -e b n> .m +

.s O h h S. A 4 0 ** D E M & == 88 C>00 eghwg ,

e "O O**LL==9 -e U M 9Aev ed 2. A ed A Te == .= A & = 2 L t O a

A C w 0 e L > C ed 3 * .= b e .e C .a C L3 ==C tLh s. .C. T 3 9 U L L == 4 * .A 80 .* T O == .* 4 ga 3 .C 6 s sie 3 .a O. p & _s e e a

.e 40 9 ti .* L 3 == c O==Ce a C- _a C en ea =.=. n C a

C. 9 88'"*O n"""n M = 4U 2>b O n .8 3 N # b M # D G .* l eL n at A S m aCM t/') 3 G b= 9 C e .=e g g W s c 3 "3 .* 3 e n .s. C.U e .e. O LJW see M .E. b s. We a. 3asL =c,Oj e. L 0.g Lg, .h. gr3 .g. .g >

C U st 6 to O G O O O ** & E L L .8 9 .* b 2 D8 *8 C ""3 b .e > C. O g e e a se {

O U O = W O n O 3 2 = O = = b = = = = O s tj ce=30 Cgg=a g ;

.C.

._-_=.w.=.a=_=_A_=_0_.*.*_ -- _ .m .=

G .E S

.c- a

_s._E _n.p.

4_ O _3.T.M _M - C.4 L _c .o _T _n .0. . .as .C .L_.3_ _>

t.

E9 l epe==

UC ** l nE. C T C at et e 9 -. M LeOCT '

ed o a E > Jr n .a o a o O

.=f n C = LC e e .s et a o ni a c. C. ! LC Cm C == c L C. D e=

c Es O t ocnn =C3cen&

c E3a L 8 .= c e W == n a a w >

ev s c. o E c. C 3 % I. .a C& R

.= c 0 L ==

& G s SD U IC% o nN me : O C .a T W E .= nb>b>

3 - GOn ..

e e L h a n ,

8 =&CCR v OUm *

. I c **n n "L L h .* *: 8 W4 .e = 3 3 4 W W 3.e L 4 ft c n nC ' == T E D a O > == C Le o 0E 'O D C n .8 n .w= & A =* &

lL b .C. .= C..C 40 & CL *

': ". == L 4 C3 b e .8

l e=. f C. c et : Oc 5 .e C == 4 9 E = ta = 0 = 4 T i.g = L=3 3 ** b > .a = == c=> ======

y anav A C C C

Ev=T=nO ;

= b m C' C 3 O LOO C O=-.d ccCD>n '

'I F

. C

._ _ .N. _=a.=_.0 _ _ _._ M- - _ __._ _= _c _ _ _ __ ___ lI .la. .C._U .C 3 - - .0. >. c L .f_t _=.=

a l n U ***** I 90 D .

C l C CT CC E I I

dE C

D C

C UC ==U !' C

.U L1 4 .4 .a L D .L. M .a *. W =

i WC n I WD l *EE 06CD

.= =!

r.

1

& : 0 h ' C *:

h C .* 3 ci n E s = r. n j s == 8 n =006 .

W 4 al ESpac =VL 4> M c == _

I CL E a nCD

. g w I 0 E g*3 = ,

E

N=

c m Tj w D '

t ==OEO n e= J .W, D .a a, ' U L, gg

.4 y 9 == . g -

.,.g; T .g.. >. = n e . n a = n u Cu at 3 l -C.L' r. n L L a 3 h O L .4 r. C 8

- =. .: C .I et cG n =E: >= L 3 m .8 GT g = :. ta)

C CWDcO l L 8'E = 0 l 1 T' I CC C3nJ j

*

tL c' = U C. C== == 8

. C. = t se e . .# = E ceO_= ; == h

=

n=>L c=

i L 3 .= a > -

3 i: r_ b n

.. = I w n .e y rt L m pt C. L UEwC u a eO .l =CC 8 == ECa C cc.

L

- - ._ a. - - - - _t .u _2 _9-------.S.O - - - - u. b -C - - - -l I >

3 e F

,_ __.I _a _s ._ _c .=. .n.

=

e

2 O tee =.

U C ha E r. T

.V= L U ft #3 .C= > n .a C a .

9h 9 .8 en Im '

re 09 *. t '.E U C.e cL C.

t'. te O ..

F3 n l 8

5A O l

F. -C=c

'la E

o G =

' = n .* C.

=CO I= L' L W E l I rt of L W C I CE E e O M nNM l & W =b c= L>

'a== h C. n L' ='

C O9=

l r, r. L h l' CC a 2 n

. M R &D n .n= 2 . g Uh c .4 *O>

2. = 2 .= W . n F. == w C.

. 1 W: C. b n C3 b -

e. !. ob = e=. p

= *l 5= == E

& 8 & c > = .

T '

L==2

EoT=

M rt M& C. Ce c .8

=*

g

L m nC cc=0 ,e f.. :g_ .N e ** W.- _--..____N_ .___=.3 _-- __>3- .. _ _ _ e .c.- ._ .=. .L .

t

= ..

. 3 T L L .J b :

e W C 4 v C .* E .

o .o .*

s l C Eo .

L ft J 1 ed 3 d 3 =3 8 r. 9a en

C 4 &

=b Ds l WW r. a>

n .uW aoE me C--u nn

'o :

C =* W

':a. O .C WE

L E. .y t ** ** + C.3.d.fe

8 3 'J ]

9 a .=. id - *7.>.# ',,,7 n

e

Ce ; =c

+ nLn :

i e s. e.

- e r. u h u_ i

: o= s ec d n P. nn ' a: r '4 r.V..E. I

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o _ __ -

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S :

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I ti : V e

= C l f* C a

.= T C

==O &C d d CD h O 3 . C n fu ! n= a v .: c== = = E o o C h av0

lC tc l tc c C C o b ., L c = :. - : o C cs eo b Cd C. = 0 C O = 0C 0C eg l C O. ,L ,=2 b = ;=; b o *g g .= C c.O, = g

!=

4 a ., c me = 0 .= 0= .3 a=

C .g=6Cn

A

.a tJ C > c .=

p 0 "O D u 'n=O == C 60 ==

nI C. O nC vnU U n .= h a EnL Q

= *= 0 0 == s o C* E D = b .a ac n as cw: 3 b Oo=b3CL

30 0 h L=0 o V OCE == lac h, O nc=0 0 3e CE = 0 0 C L L ** C E C== 4 8

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b .OaOL E Is}

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Okna >

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=,

. v => .2. t. u .= = .39nL h . C= h . ., e. .n M no A c t. v E o. o.

o l' c 6 O 6 o .a C = .D L n = .J d ** 3n C 3C ** L -e e 3 C LO C C. 3 O O -e b L e so == a L oho .a L g

-.c L UC3 C U C == .J C. b 9 .O L == b L = c

.a. ao.= C. O h

W D 0

> **L 4.e *=*==U0V .a O E e .a C *L C= n@ L C. enc 0 C C ** O M 8 .= " C .D L "3 e C .d UT C CU as EOp L33"3c30a P. L L == 0 04D C L V U n C ** =e L U = 0 C == L Uee g . n .* +8 s to =* U > 0 L .4 0 3=0 .

e =.* n O v U so L CO G U 9 L'C " C O C G E O U .e*O D C. C

, = st n == .a O c LC2 == nd = 00 0 =* b c 4CL DC= .WW G e O C =* d Q %

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8

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6

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tc ac tf e to d =* b 3 C. == *I' e == == bL C. *8 "

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=

= b b "O O

a

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I = CO M *: eO O .=

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tw 23 3 BC 8 .J C l =

4 .= ==== b : 3 ec l 0L ]

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== ~

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!= $ = co ue L M CU C I s 8 == b

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=CU == 6 C wC LC*' ss .L 3 O .* C = 0 8 D> .

1 i OEC 33 0 C D . O = Oh l DCh0 0 l CcC

.= .= = - - = .i. -.- -M- - -- .t.,. e e. .n. 2. .- ~- _=- _=. -. n. ._ _ - =a .= M- -=- c i = .C . . . t I c ?

C l C !

- C= NO n

- '= > .= ** T& _ .

th St ea C: . . .

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oL T:

L d

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'= . 3 :. L . L n :. s en _ ~. .-

en ~: -

c3= -

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= = cc La

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l CU- U . TC C ccn .

-= l = .= 0 == l tt - LLO tT l

=

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e a*

8 M i b "I e : 6 6C at : C. 8- . l l - ~

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i.

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L '

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O o

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, . = =

l:

n

3s

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10 = 6 E . ._ ._ I .:=. L-----_=._c g

. . .- l,

. I.A,i!!.51.i. (conticuad) -

~ ~ Mt eiro ~l 'r.lilli'l's TciTITa'Jir T-~ l -' 'A ri i'I' 'lill i- I- April If82. I Espinnetton or chan;;e

,_, I i .-

,1 l linailg.tcel lleni gn_l licrcrence Desl_gn l l 1 I I l .

I I

)l'esel attrage I lisent i f i ca l l een to 13ame as . 1981 Denign IUK praettee - I l

l ec:s t ri e:t elrop Iselght I i I

) I

)

1 for clask I . I

I I I l I

} - -~

~'l y,,.- ~T-~~-'--~ ~-" l l l'

) ,,,,, ,

13torage capnelly or 7 13ame as 1981 Design I3tatage caractly or ICreates opportunity for 1 3

8 l l . ft reactor cieren Ircant e,c cores leaned osal llong-term constileration nr l 8 lhasitd . cts luie elenn i t.y lleigli deenwl ty Storage l IUK polley on handling spent l 0 latocase (7. years on i

I Iruel. I

} lhants or high dennity l l l l

,0 Iracialeig avallaisle ten I l l l '

'8 loptioni l l .l l

- I -

0 1_ 1.__...-..... -_

l8tual Sterage 12 x 1005 cooling waterl81 Ititl5 cool l:8C seaterl88 x 505 cooling water lAnalysts or incidents. l 0piend egolless lpumps and 2 x 1005 l piim p a a n.I 8 x 1005 . lpumps anel 2 : 1005 linvolving loss or cooling erl

$ syntse lisent excleessgetr:s liscat .inchangers lheat e u clea nge rs Ispent ruel pond Indicates l l8 l I l Itleet the April 1987 design l l0 I I I igives adesivate ret tal'Ility. I

0. .*. . _ I...__.__...- I . . . . _ _. I,

. ,I. ,

O'.ecenda ry llin uncondary contain- 13e cennlary containment 15ccondary containment *To provide additional i Ocantairment lisent provleled over lover primary entLaln- lover primary contaln- Imargins. .

I 8 l primary cohLninoce:L Iment sinne i nc i niled lment dome included I . I 0 ldome 1 l I I i

8. . . - I __ - _ _ .l. . _ . .. . g _.,_ __ __ _ I l __..I~ l l

{'

- . . 4 g' -6 4 'e e

,1, 9 ' .

I

' e 9

e 'l 6 I

,2 a

.s ,

, s

- -- ~ -- ** - ** ~ ~ ~ ' * " ~ ~

x -- . . . . . . . . . . . . . . . . . . . .

l l 1 6 0 o

.y . _ _ _ _ - - _. ___ _ _ _ _ _ _ _ _ _ _ _ __

t .

?

.e s

Table 2 Comperison gf Sitewell S with SNUPPS ! '

J , l FEATURE SNUPP$ 1CALLAWAy) SIZEWELL S

. COMMENT Building layout 140*hemispherical with intemal diameter head containment 150'intemal diameter containment Diameter must be incremad to l

i with hemispherical head accommodate larger pump motors, accumuistors and features to reduce man rem. i.

. Auxiliary building extending Same as SNUPPS Essential feature of the SN'UPPS

slightly more than 180* around

concept for access during containment building l

[ construction .

$ Containment and auxiliary

Same as SNUPPS Emential feature of SNUPPS I building on separate foundation layout permitting buildings to

, refs , be founded et heights to suit plant layout Reactor Westinghouse 3425 MW 4-loop Some as SNUPPS Fundamental to retaining componens plant _ ,

benefit of proven design Reactor vessel fabricated fro'm Reactor vessel fabricated from Avoids vertical welds in the pe' rt plate or forging ring forgings of the reactor venel subjected to

, high neutron irradiation

Standard' reactor vessel head Head design modified to design The multistud tensioner t accommodate multi stud tensioner reduces the time required to remove and replace the venet -

. * ' head and hence reduces man.

nm dme <

Wide re' actor cavity design Narrow reactor cavity design The narrow cavity reduces adopted f f

neutron streaming and induced

activation and hence reduces man-rem dose -

60 Hz design for the reactor 50 Hz design for the reactor Requirement for UK design :

1 coolant pump (93A) coolant pump (1000) f Type 'F* steam generators Same as SNUPPS - Design chosen to improve tube . ;

__ integrity r i

Emergency core Two high head safety injection Four high head safety injection ')

Four pumps required to 8 cooling rystem pumps pumps of increased capacity improve reliability and meet l

_ _ requirements of UK single -

i

~. . . . . . . failure criterion. Increased ! I i -

- ~~

^

pump capacity reduces peak l clad temperature during small i 1 breach LOCA. .

HHSI pumps taking suction from HHSI pumps taking suction Careful pump and pipework LH51 pump outlet in recirculation direct from the containment design used to prevent need phase -

sump

+-

~

for comp!ex arrangement of i. ;

_ equipment .. i

. i Charging pumps used as part of -

Diarging pumps switched off Diarging pumps can be i' i

ECCS -

during ECCS operation omined from ECCS because

~

of in:reased capacity of high .

-~ -

head pumps. De8etion a!so

. reduces the chance of over.

~ - - ' ' - pressurisation of the prirnary ;

~ 'i circuit v&.ile it low ternperature !

~

4 x 33% accumulators 4 x 50% a:cumulators UK singfe failure criterion .

means that re:;uired operation l.

l ,

.. must be dependent upon 2 i 3

.-' ~~. . . . rather than 3 accumulate s .

working. Hence increased size 1 ,

1 Manual realignment of pumps Automatic realignment of pumps improved reliability is achieved i from injection recirculation mode from injection recirculation mode ,by automatic pump realignment .

.sv head safety injection / Four ide .tical ournes two normally The increased ca acity of the .

cua! .'est ter ovat pur .ps . aligned 'cr LMSI/KHR duty, two high head pu rps mes .s t'.at the i

...t . Et1:: rint .

Cigne:': ::ito . cnt : r:v d.:ty 'c.v ntsd laietien syns . can be

} . '. - Table 2 continued

, FEATURE $NU'PS ICALL AWAYI SIZEWELt. t COMMENT i Pressuriser system

Standard

heater system in .

pressuriser Reserve heaters available Sufficient time is available for the operator to conne:t up the reserve heaters if required

$ Chemical and 2 centrifugal pumps and 1 positive 3 volume control 2 centrifugal pumps + 2 back up The required reliability is displacement pump positive displacement diesel driven

.) system pumps achieved by using a diverse

power source for the back up 1

pumps

Auxiliary feed 2 x 100% electric motor powered .

?( water system pumps plus 2 x 100% steam driven 2 x 100% electric motor driven Seperate nozzles reduces risk j,

pumps. A!! pumps delivering into pumps delivering into separate nozzles on each steam generator.

of fatigue cracks due to low temperature feed water j . the main feedwater nozzles 2 x 100% steam turbine driven pumps delivering into main i

feedwater nozties s Y- '

Boration system Rapid bration system (within Rabid boration system deleted.

! HHS! system) included Recent analysis shows that the

! Emergency boration system added rapid boration rystem to dea!

with recriticality during steam-line break accidents is not required. The emergency boration system provides an

', attemative reactor shutdown system in the event that the main system fails to operate

~

' Component 2 train system - each train has '

2 train system - each train has For Sizewe!! *B' the component cooling water . 2 pumps and 1 heat exchanger 2 pumps and two part heat system cooling water system carries exchanger some of the load carried by the essential water system in SNUPPS This is becausa the

- EWS at Sizewell uses seawater as its coolant. This leads to a two-part heat exchanger in the CCWS

~

Essential service 2 pump system 4 pump system

, water system Reliability of the system

- ~ ~

improved by increasing the number of pumps Reserve ultimate Use of large cooling water pond Air cooled heat exchangers in heat sink ;

Air cooled heat exchanger is component cooling water system . more suitable for Sizewell site

. than a cooling pond t/.ain feedwater One norvreturn valve in each Non-return vs!ve and isolating Engineering practice in the UK feeowster line valvt in each feedwater line

.- Turbine generator Single low speed turbine generator Twin high speed turbine. generator Chesen to avoid use of a proto-type turbine generator in the first PWR plantin the UK Main heat Forced draft wet cooling tower Seawater cooling rejection system --

Dictated by choice of site

Electrical systen 60 Hz 50 Hz _ - UK practice i

~

2 x 100% diesel generators 4 x 100% diesel gener tors feeding The dive se power supplies for feeding 2 separate distribution

boards 4 separate distrib.ition boards , ? I _ certa'm vital equipment means (Note: non.e!ectric drives for that the required reliability for auxiliary feedwater and charging emerge .cy efectricat power can pumps) be provided with 4 diesel generators Reactor protection Sing'e system based on relays and Primary syitem using micro. Two systems recuired to meet solid state switches procectors. and secondary system UK safety requirements using 'l.addics' frradiated fuel Hig5 li' ort Lock gates permit flask to enter UK practice to avoid risk of

wr ding vehicie .. ...ig pond at low level dropping flask

= t, - *e r huwdw csLDRzvk raa . &n ~ o - - - ~ o ' ' ~ ~ ^

Te 'e 8 contin'wed i

~

l FEATURE $NUPPS (CALLAWAY) SCEWELL B COM M ENT T

Fuel sterage 2 x 100% cooling water pumps and '4 x 50% cooling water pumps and Analysis of incidents involving pond - cent 2 x 100% heat exchangers 2 x 100% heat exchangers ,

loss of cooling of spent fuel

. pond suggests that the Sizewell .

B' design gives~ adequate reliability Personnel change US practice t.arger main change room and CEGB practice for contamination roorns additional subchange rooms control requires additional change rooms Secendary Enclosure building is not provided Enclosure building it has not been possible to .

' for Ca!!away but is an option with provided

provide conclusive evidence that con {Dinment SNUPPS concept leakage from prestressed .

. containment structure is

= predominantly from the

. penetrated regions -

s

. S

'd

~

'E ai o

E -

S E1 x '

s{l

..r 1:

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Sis

~

ai 4j,.! :=

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4 a

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. a i.

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pa,. w.e I L.i...n .e c-,, ,ence 8 ; gn M e n!3 4

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ndary -} *-

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ct t .t2) g 2 . ,og , , 3, C O O

CT'""T

'29.M J Q'W 33 8

. i.

jm p9 30 D D CD FfC'3 m j 11 12 W -" l 1640E Blue ime

- 8 ve* * *

\

e ,s ' /' '1673 E

/ Green bne. '

\ U /!Ieg e g g (4,

- .- I 3

{ l g Station securety fence Construction fence p'g'i 1 i

' k*t ,

iSt#'8)

(esistmg) j gg gd

l

.it

o *' -

N Meanlow water

.5 N m;.n2s$N*f !aw

- $;WM'- d4.r s- w s%._ w%wM.cnM.sw--d:.&,2 a.

v min.% w r:c h:

i::vi,,5 . -e.J,,.Y.-s - - ve,:

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N'73KgC.N,d.F,n-2,h - - - - G -4 *C* eM

S*.f.*

0 50 100 150 200 250 300 Metres Key ~

1 Rax*.or talding(corf.a;nment) 14 Dieset house - 27 400kV substation

2 AusiLary buDamg 15 Controt buildmg 28 Reserve uttanate heat sank 3 Fuelbuildmg 16 Transformers 29 Station transformers - - - -

4 Turbme house annese 17 Radweste builames 30 Site hostet 5 Turbine house - 18 Secondary diesef and ' 31 Rea'eter make-up and ~ ~~ -

6 Generator transformer controi buddin g #efuenes water tanks ___; - _ _ _

7 Water trestrnent plant buildmg 19 Workshop 32 Deminerabsed and _ . .

20 Workshop stores condensate water tanks 8 Hydrogen release tank 9 Hypochforite buildes 21 Welf are 33 Fuel oil tanks 10 C W. Pumphouse 22 Adrninistration 34 Decontam shop 11 Surge chambers 23 Fire fighteg pumphouse 35 Contractors' storage areas

'12 Mtrogen and CO, store 24 Towns water reservoir No.1 36 Construction offces - --

13 Auxihary boiler house 25 Reservoir No.2 37 M c informaton offce - _

--26132kV substation 38 Main change building - - -

Fig 2 Sizewell B Power Station - site plan _ __ _. _..

=

m, -M

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5 c

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~

==-%.

~~ "'y 32

! a3 t-f **d E'8k 3 -

~

0 10 20 30 40 50 Metrue -.-

Kay -

1 Gererator transferr>=r 13 LP. Heaters 25 sieam generstars (4) -

. 2 Pohshmg piant 14 LoaSang tasy 1 26 Pressammer --

3 C.W. Inlet .

15 Cormnessed me piant 27 Plant accesa hatch .

4 Surstchgear 16 HP. Heaters 28 Fve4 taik$ng ---

5 CW. oiret 17 Feed pumpe(6) 29 Fumi store 6 Reheaters 18 Tectuvcal support caritre 30 New fuel 7 Turtw w generator 3.1 19 Main control roorn 31 Decontam shop 8 Turtsne generstar 3.2 20 Donet house 32 EssentiaJ transformers -

9 Lutaratng o.1 ptant - 21 Assir.ary tiuDsing 33 Main change taswg - - -

-~

34 Transformers 10 Desecutor 22 Reactcr coonant gasgo -

I T1 Ausit.ary tioiler tcm.se ,23 wnv.Intng paarit 35 Staten transforwers ._

12 Steam enaire 24 Anactor pressar* wtaal 36 Enclosure t>uildeng l Fig 3 Sizewell B Power Station - plan of station .

1

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ENCLOSUP.E 4 C 4/82 .

t.

The pressurised water reactor design for .

' Sizewell B D R SMITH, MA. FIMechE National Nuclear Corporation Urnited. Whetstone, Leicester ,.

Snio? SIS The paper describes the PWR desip for Siteven 'B'; with particular emphasis on the chang:s from the US reference plast introduced to meet the UK safety and other require =ents.

s .

1 INTRODUCTION (iv) Si even B has to satisfy UK cechanical and electrical star.dards and engineeringprac-

-"d2 Frassurised Vater Eeactor (PkR), developed in tices, particularly vbere UK canufactured th2 United States and videly adopted elsewhere, equipment is to be used.

is a za =e reacter syste: for which there is a grect deal of experience of both construction (v) Siteven B desis: has to satisfy UK rather .

.a=d c;eratics. In order to take fun advantage tha: US se.fety require =ents a .d take account j cf this vealth of experience, it was decided cf charges in the US require =ents for future ;

that the PWR design for Si:even B should plants, notably require:e:ts a.risi:g tec: I rsplicate as is.r as practica.ble a reference the accident att the Three .v.ile Island plast.

pla.nt bei g built in the USA. The reactor unit golseted is a stardtri Westinghouse L-leep In addities to these, otligatcry require =ents .

d22ig: vith a hen output of .%25 W (ther:al), fer si:cvell ?,.a Ic cf ec structics, operatio-cquivilent te a set electrical output cf approx- sal s.nd tech olc6 ical experience he.s tees a:cu=-

i irately 11CC W (e). '"velve si ilar uits are ulsted since the SITJ.'.:S desig: vas ce==itted.

s . ready in c;eration e.:d a fu-ther twenty are Design charges fer thrse retsc=s have only been ~'

.: dar constructica. *:te power static: i:corpo- =ade where the tenefits are ccafidently expected l

'ratiig jhis rescier unit, is the Star.iard to be large cc:;tred with -he risks to cost asd

'uelcar Unit ?:ver Plast System (S .*Ut?S), which prograrse of introduci::g us;roven features, was desig:ed by 3e:htel fcr a group cf US u-ilities and re; resents the latest nuclear plant 2 SATITY EIQUIRIC;TS d: sip in the USA. Two 5::UFFS staticas are in -

r.h civanced stage of ec:struction, c:e at 5ecause cf the i=;ertaste rightly attached to the

C211sv2y, Misso=T and the other at Welf_ Creek, safety of nuclear pcVer static:s, it is perhaps Y. ass s.-

'a;;repriate to reviev-trief13 the i_ pact whichc .

the different approm:h to safet'y in- the UK and l

While t.he r_.R

. des:.gn for Sizewell 5 rel'1cvs USA have had on the Si:ev'en 5 desip. In the l l :lessly that of Callavay, it has bee: recessary USA, the :SC licensi:g regulations are set out i 1

.: : .he changes fer the folleving rease:s: .n g e a., deta:., . . , n , ... . - .e.

. . 10 Ci n.

In .he . b...,

4

-- eve'-

c.- . '

s cu *

-'e sea coast' vhttcas t.he NII place r nus fer proving that the desig:

as safe en the cpernce and dess.per, who have -

f a.lavay is c: a river - requiri:g- * **.:**,7 s

$a. *-es *c se:e auxi-'*ar'" cce*#--

d "* "'****' * 'de'2-*d* A.

fu.'ssental ;r: c:#le er .hese gu: del::es is the

- sters

uc - - k'ne - - **'--* vete e.:d , all rease: ably prac.:.ce.1 steps than te taken to

..s e-3 -~ , 3r......e

-*--- "ec ures* -

reduce -he exposure to radin:.en cf the Eeneral l

. public a:d the plant cpercers, both duri:g l

.ii) '"he UK g-:.d frequency as 50 Hz cc: pared to ner:a1 cperation s.nd also as the reruit of l (O E: in the USA - 50 E: rcte:ng equi;:ent accide:ts. One effe.s has been that : re is generally larger thes the 60 Hz equa- es;hasis is placed i= the UK c: the provisien of f

"1 * '" redu=da.n:y and diversity in these sys e:s l

. provided to ritigate the ec . sequences of acci- '

=s =etr:c units whereas l u:. ; '.he '.*K . .. o. . ,. ge..

4. ..5 ..,: ,. g .~..

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.. sed # .S..e ".Ia' *. '..' s .d e.g s .. , - ;, ,..-... , c... a i

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~ - - . - mu- A nnce-

1 er these g cups of syste=s t.as to be highly vessel vill be subject te ext.austive inspectic:

a

reliatie (the target is IC'1 to 10" failures du-its fabricatien, defere insta11ttion a:d per de:cd) a:1 capatie en its ov: cf preves ing , dri:g service. Tcese nessures adi es.s the .cc:-

. as u: acceptable release of. radioactivity result-

cer:s on pressure vessel integ-ity that have ing from the initiating fault. A secc:d conseq- received so much atte=tien. Similar sts:dards y ue:ce of the functicnal guidelines is reflected cf casufacture and inspection vill be a;; lied to

-?. in the CICS practices for the control of conta:- the pressure retaining. parts of the other ec=-

'. ! inatics a:d operater expcsure during ner:a1

.j b,V'Y cperatio= and sainte:asce of the ple.st, where pe=ents in the coolest circuit.

N .

4 M*F { greater prevision of charge roc =s and ventilatics The pressure vessel is supported fro = pads syste=s is required than is normaljin the USA. loested on four of the sain coclant nozzles, U *

*j 3 TEE FIACTOR MAIK COVSONELTS vhich rest on the reinforced concrete structure

' surrounding the vessel. A design with a rest-d ricted gap between the vesseland concritte shieli, Eeat is extracted frc: the fuel by water. .

I k=ovn at the 'marrov cavity' design was chosen, J pressurised at 2250 psig (about 158 atmos;beres), rather than the ' vide 'envity' of swPPS tecause which is pu= ped through the four closed loops, it reduces the irradiation exposure of operators y each of ubich contain a stram generator asd a uring refuelling.

1 pu_p.

n e coola=t circuit co:ponents are des- .

i igned to withstasd stresses resulting from Steam Generator s j' seismic disturbances, cyclic flow induced lgads g and fault tressients, as well as the normal The steam generators are of shell'emd tute ecnst-J operating conditions.

ruction with steem separators at the top. The j

j stee: Eenerator ec=sists of three sections; . a Fuel he:ispherical botte= head carrying the pri=ary ecclest inlet and cutlet nezcles, es evaporatcr 1 The fuel is of standard Westin6 house design and section enclosing the U-tube bundle, and an

{ consists of as array of fuel asse:blies with upper section enclosing the steem separators.

2 . slightly e:riched urtriu= dioxide pellets con- Access openinEs per=it inspecticn e.nd plugging

.T tii.<ed within :irconium alloy tubes which are of the tubes and water leccing of the up;er "J sealed and pressurised with helium. Each fuel surface of the tube ple ,e. '.The steam ge:eraters nsse:bly consists of 26'. fuel rods cechamically see the latest Westinghouse 'T' type which incer-Iccated in a 17 x 17 square array (269 posi- perate features to avcid the tube de: ting and I

' tiens). Le cen re position in this asse:tly is crevice a:d stress corrosien which have cce=rei

' reserved for the in-core i:strumentatic:, while with earlier desig:s. nese features i::-lude:

the re=aining 2L ;:siticas are equipped with :ir-t caley guide thi:bles available as core locatiens stainless steel tute suppert plates vi-h fer rod cluster centrol asse:blies, neutren Quatrefeil holes - avcids the prcbles of scurce asse:blies, er t r:atle ; isen rois. tube /-Itte ercsion.

Feactivity is cc rolled by i:serting er with-dravi::g the control asse:blies, and by varying ,

Pull'Iepth hydra..lic expansic: of tubes ::

I G e cencentratic: cf beric acid in the coclast tube sheet,avcids crevice cerrosien.

vater.

Modified baffling to i=;reve circulatica 5eactor *,'essel : ster:a1 Structure y

ratio - avcids sludge de;:sitic: and c:n-sequent tube dry-cut and cer ctics.

n e reac:cr vessel internal structure which are cf stazdard Westingh: se design, su;;:rt the herse.11y treated Inecnel-6CO tube :steriti t fuel asse:blies and align the red cluster - increases the resista ce to stress

"# eontrol asse:bly guide tubes with the centrol ccrresien cracking.

j red drive. They also direct the flow cf reactor j coolest, provide g- a:d neutren shielding, ~The stesi:i generater is supper:ed by fcr 9 esd provice guides for in-ccre instru entation _2 articulated 'colu:ss. U;per end IcVer lateral l between the reacter vessel botte: held e d fue1~ restraints are ;rovided to vithstssd seismic '

I assemblies. They are fat-icated er austenitic lotisi and' the Icads which vculd'cccur in the - '

i stainless' steel. -'he internals consist cf the event ci a_ pipe rupture. The reac or ccele. t .

} upper core suppert structure which is re cyable flovs into the channel _ head at the bette: cf_the . .

. fer refuelling, and the lever ecre su;;cr stens gener,ater, thr:rgh Incenel T-tutes and trek' stru tre vhich also has to be re oved fcr -

cut cf the chtnrel head to' reten to ne'reac cr

. interr.a1 vessel ins;ee-icn. vessel. Feedvater enters near the tcp.cf the ,'

stet: Eenerater, where it =ixes with the re-ci cr e Pressure vessel "~~

ulation flev -frc: the centrifugal stet = se; ara-e scrs and passes devn the as:ulus tetveen the tube The pressure vessel is' essentially the same bu .ile and the shell. It then ri'ses between the 4 design as' that for S:."J!?S, except that it vil.l' U-tubes to the steam sept aters frec'where the .

$ be fabrica ed frc: ring f,crgings. This avoids separated stes: is piped to the turbine gere-5 the lengitudinal velds (which are =cre highly raters, q stres ter' thes' ** 3 el M e::ial velds) in the '

part of the ve se. 1.rNr e :; erie:ces the highest

~

Feacter Ccolant P.' ps l ne;;r:: irradiatica. Se verrel is fabricated j

- - ~ . - -

4

'y i **

, vster lubricated bearing in th2 pu=p casi:g. 3 RIACIDE AUXILIARY SYSTEMS (Rcr:any

! . Operati:g)

be pu=;s are drives by 6 HV cc: stas. *

' sp'eed, air cceled, vertical squirrel cage The Che:ical asd Yolu:e Ccatrol Syste= (CVCS) induction cotors with oil lubricated thrust a:d !

Q radial bearings. Fu=ps and motore are of e' stab- ne chemical and volu=e control eystem (CVCS)

'i lished desig:s shich have been tested at over- has the following functions:

? speeds of up to 125 per cent of no=inal speed.

l The pu:ps are su; ported cs articulated colu=ns Regulation of the beric acid concentratics ase restrained laterany by seismic dampers and 1 in the reactor coola:t to ec:pe: sate for J pipe whip restraints. .

reactivity cha:ges during start-up and 3 shutdown, and due to fuel burn-up.

j Pressuriser g Regulation of the reactor coolant inventory g, The reactor coolant pressure is controned by a to maintain pressuriser level within the j single pressuriser connected to the hot leg of angvable range.

fa one of the loops. The pressuriser is a vertical',

cylindrical pressure vessel with benispherical I

Treatment of the reactor coolant by con-l( top asa bottom closures. It is fabricated in tinuous removal of corrosion and fission carbon stell with austenitic stainless steel products and maintenance of the correct 3 cladding on an surfaces exposed to the reactor

hydrogen concentration.

j coolast. During operation a water level is main- '

{ tained in the pressuriser,by adding or r'enovitg A saan quantity of reactor coolant is contin-A water from the coolant circuit to ecupensate for uously discharged through regenerative and non-3 the expansion and contraction of the coolmat regenerative heat exchangers and pressure

$ during operation. reducing crifices. Purificatics is affected by

. a system of de: ineralisers and filters. Regul-To reduce the coolast pressure cool vater is ation of boren is achieved by the boron ther .a1 .

. j sprayed i=to the pressuriser.

This condenses regenerative fystem (BTP.S), which adds or re= oves i sc=e of the steam and reduces the water terper- boron according to the te=perature of the ica I

ature, Electrical i=mersion heaters in the exchamge resins. Two centrifugal charging pu=ps, pressuriser raise the saturation temperature asd one is sufficient for the duty, return the C7CS

.' pressure to inerense the coolast circuit flov to the reactor coolast circuit. Part of

ressure. Increases in pressure beyond the cap- this flow is directed to the reactor coolest

, stility of the spray syste= cause power oper- pu"p seals.

I ated relief valves to cpen to relieve the -.

i pressure by dischargi g fluid into the pressu- The Cc= pose: t Cooli:g Wo.ter Syste= (CCWS) a:d

, riser relief task in the co: tai = ment building. Essential Sea Water System (ESWS)

. At pressure setti:gs below the design limits of 1 the syste=, additic:a1 spri:g-loaded safety The ec: pone =t cooli:g water syste= is provided valves aute:aticany cpen to prevent over- to cool the main reactor ec=p :e:ts asd auxiliary -

, pressurising the cocle.st circuit, systems. The cain heat loads are:

3 E

~ ~

Contai::est The reacter coclast pr. p ther=al barriers

. .I. The reactor and coolast loops are housed within The che:ical a=d volu:e cei: trol system *

. a cyli:drical steel-line? prestressed concrete heat exchassers cc tai =:e:: building with a he ispherical roof,

. see yigure 1. It is designed to contain releases The residual heat re=cval heat exchargers from accidents in which coolest escapes from th 2 pri ary system. A spray system is provided to The centain=ent fas.--~

coolers ,

I cesdesse stem: is the eve =t of such as accident j'

and so reduce pressure, and to vash out iodine _ The spent fuel pond _cooli=g system..

asd particulate fissica pioducts. - yas coolers ~ ~"

~ J ~~

' ~ " --

~

4 j

are provided to centrol the te:Peratre within The system is arranged in two halves, each -

- ,j l -

! the contaitre=t during normal operation, and - equipped with two pu_ps, a main and subsidia.y i they also serve to Yeduce te:perature asd pres- heat exchasser and a surge tank. The syste: is;-- j; ~

i sure withis the ecstai =est fenoving a loss of 2

e closed loep and uses de:i:eralised, rater,-

~

d I ccolast accident. Massive -reinforced cel : rete

! : i:ter:a1 structres suppert the pri:ary coolast _ _ter: dose ally _drejects with a heti cerrosic~ inhibiter,vater tp the esse:tial and it ; [ j'

1ast within the ce: tai::est. "hese structures cocling syste=. It can also reject heat to the J #

1 are designed te withsta':d the loads 'frem plast reserve ulti:ste heat sich which -is a'ferced 7-

, restrai:ts is the eve:: cf as earthquake er a draught water to tir heat; exchanger. - '-i ~ ~

. . rup.ure of a high pressure pipe. The , *- --

l 8

centai::e=t is partiaMy e=c1csed by the auxi- L SWTDOW COOLIEG SYSTEM .

4 liary buildi:g which houses the reactor cocla:t '

~

auxiliary syste=s. This building encloses the systers -desig=ed~to safeguard _-

-~

i i ;enetrated rerio= of the ecstait=e:t Milding, .There the reactor 'are several,t when a as shut down ner: ally, or l ssd niovides a "secc dary" ' fonovi:g a fault cr as accidest:

a:y leakage which might occ . cc:tain-

. :e tuilding e : ugh these penetrat cas,'t d AMXili"*7 I"O EY 8t'"

.* ..., n. w r... .. ,, -

.e , .

. . , er sfatdev: hsat, which am:: ts to sc:e 100 MW(th)

- cc tai =ing borated water sad vben this is e=; tied five zi:utes after shutdevn. 5:::e.11y this heat they re-circulate water fic: the sur;s in the ec tinues to be re::ved thrcugh the steam ge=e- ecstai::en tuildi:g, rejecti:t heat tc the FS.!

rn:rs , vis'. s ea: ty;tssed direct to the tuti:e hea) excha:gers. Alter:atively, the required cc:de:sers. When the ecndenser or the main feed flov of water ca: be provided by three of the syste: is unavailable, the steam generators are four high head injection pu=ps.

i cooled by either of the two auxiliary feed sys- .

?

te:s. One of the auxiliary feed. systems has two 5 RENELLING pur;s driven by electric noters, asd the other .

( has tvc pu=ps drives by s:an steam turbines Approximately one third of the fuel in the core

supplied from the steam generators. These pumps I is replaced each year. The op'eration is carried are supplied from two separate condensate water out with the reactor shut-down, and cooled to f storage tasks. Should neither main condenser lov temperature and atmospheric pressure. A y be available, steam is discharged to atmosphere multi-stud tensioner and. integrated head package through relief valves. is provided to reduce the time required *for

) - ~

removing the eessel head and internals prior to Residual Eest Removal System (RERS)

j -

'refuening, and hence to reduce the irradiation exposure cf the operators. The cavity above the i Uben the reactgr coolamt te=perature and pressure reactor is flooded to form a pool through which i

have fanen sufficiestly, the shutdown reactor the reactor vessel head and upper internal -

cam be cooled by the residual heat removal sys- structure are removed, and the fuel lifted fro-te= (EDLS). This has two paranel loops, es,ch the vessel and transferred from the primary con-E with a heat exchanger and two pumps; one loop

tainment building to a storage pond in the I

vith o:e pump is sufficient for the duty. The adjacent fuel building. After a period to allow

} system is con =ected to the reactor coolant cir- auch of the radioactivity to decay, the fuel is

cuit through valves which are nor: ally closed. put into a flask for tress,crt to the re;rocess-6 'It e: ables the reacter coelast to be reduced to "

ing plant at Sellafield. The fuel stcrage pcmd stecspheric pressure, and if desired the circuit win acco=modate up to 18 years' output cf .

h _ cpe:ed fcr refuelling during which it continues irradiated fuel giving a high degree of indep-

}'

to re:ove the reacter shutdown heat. The RER endence of off-site stcrate and eeprocessing .

. .sy'ste= ' alto fer:s part of the Emergency Core facilities.

Cooling Syste=, cperating in a low pressure

, injectics cr re-circulati:g mode (see below). 6 COXTROL AND PROTECMON SYSTEMS Tce systes is also designed to per=it the pu-ps to be alignedte supply the centain:ent spray The contrcl and ;rctection syste=s serve two syste=. Eeneral p'urposes: -'

e Z:ergen:y Core Cooli=g Syste= (ECCS) to regulate the reacter heat output to a In the

iikely event cf a 1 css of coolant acci ' match the turb:ne Ee:erater load .

~

de t (LCCA), it is =ecessary to inject water in- te magiter plant operati g ec:ditio:s, l . to the ::clast cir: i to prevent the core being and in the event cf pote:tially unsafe N f' unceverei and the fuel cverheati g. This is done conditions, au c=stically, to trip the '

i by the I:erge:cy Ccre C: cling Syste= (ECCS). reacter asd ac uate the necessar-/ safe-

, Tnis syste: is designed to ;revide core cooling guards syste=. __j fer accide:ts up to sad including the hype-

. -~

y t

the*ical ir.stastereous double-e:ded rupture of ~

The reacter pcver is regulated by actuati:g the a reac or coclas ;ipe. ccatrol rod drive ze:haris:s which are :::sted en *be reactor vessel head. The drive =echasis=

..- The ICCS is auto:ttically actuated by signals is a standard.Westi:ghouse electrc-mecha:ical

- indicating:

~ ~

jacking device, which c:ves the cluster up or devn in*a series of s:an s eps. ' The drive =echanis:

housing for=s part of the coolast circuit bouzi- _

~

low pressuraser pressure ._. ;. .'

~

ary, so that no seals,are required en the centrol Eigh pressure in the ec taissent*bdilding . rod. . ' l.

~

_- drive shafts.

Lev stems li e pressee.

Most plant instru:ents verk through contin ~uous. -

~

, ,i readings on c e of three para eters; te:;erature,__

The systes cc:tains~f:ur high presse e injectics ~ pressee cr neutre: flux. ' Auto:stic cc: trol 7,'.-"

u: ;s, ;revided to deal with s:an LCCA in which syst'e:s are provided o si:plify the ce:;1ex . ~ .-

.ne ::c.as prers=e re: tins high for a ec. sider- sc-ivities er.:si'ed in str t-up and shutievn c'_ .

LCe -ize. In -he case cf a'large LOCA (e.g. ---~'ihe pla. a d in chtsgi:s cut;ut~._ The tin-~ r' ._

=ajer ;i;e rupture) the cccla:t pressure fans centrol re:: which is adjacent to the reseter ~ -

very ra; idly, and a rapid injectica of water is auxiliary building, vill be a UK desig: e= ploying required to replace that los.t thrcugh the breach. -the latest erge:c=ie principles and taki:g ~

Tnis is achieved by for accu =ulators, storage . account of the lessons of the Ttree rile,Isla:d ,

vessels containi:g bcrated water and press e ised - accident, and provided with vestilatics ~

ty titregen gas, one cf which is cenr.ected to arr's.:ge=ents which prevent ing: ess of ecsta=irated .

each .m c si cop S accu =ulaters have b- ='. ra zi:ed s: that tvc vin provide *he required cuta . .' '

. . . . .. .. s.. . e-,. : e d . vat e c c -

6.e a. .._... 3 ater s .....e .. .

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.u.,, .. v .nz _ os..~~_ w a w n.am --r g-*,,n..... - - - - - - - ' - - - - -

syste is based en cierc;resser techselogy, a:d Diesel buildi:g the seec dary eysten also e:plcys solid state , Auxiliary bciler house

. ele:e:ts, na:ely the 'Laidic' ele:e: s developed

Teti e house i=cluding =echa ical annexe

.' fer the UY. gas cceled reacters. The ner=al i =eth:d of trippics the reacter is by interruptir; I nese buildings are provided with ve:tilatics and the electrical supplies to the ec: trol red mech- filtratic: syste:s to li=it the release of radio-

) asis:s. This allows the ecstrol rod asse:blies activity to the e: viro::e=t in the event of an 3 to drop into the core. A: e:erseccy boration accident. The arrangement of the buildings is

, i syste: provides a diverse method of shut-down in chosen to provide direct access to the , reactor ll the very re:ete possibility of sufficie:t co= trol contai==est duri=g ec=structics, thus giving s rods failing to enter the core. Automatic good access for the installatics of major pla:t.

reactor protection and safeguards systems actuaticn

, a d centrol are provided so that the safety of Important buildings which are separate' from the the public does not depend on actions by the main block are the cooling water purphouse, the g cperator for half-an-hour. This gives the radioactive vaste processing and storage build-3 operator time to deter =ine the nature of the ings, the secondary diesel house *and emergency

( fault asd appraise the plant state from the data control building, together with workshops, d dispisy systems before taking action. offices, storage tanks and towns water reservoirs.

) . A service tu=nel for pipe, cable and personnel T TURBIKE-GEKERATOR PIMT ~

access joins the radioactive vaste processing

[ The turbine generaters are arranged sid,e by side building to the auxiliary building.

s 1

d in the turbine house with a central maintesahce The secondary diesel and emergency, control j a d leading bay between them. They are 3000 rpm

=achines with a normal full load gross electric-building, and its associated essential auxiliary trassformers and fuel tasks, are located on the 2

l al output of 600 MW. Each turbine has a double c;posite side of the reactor centain=ent build-l flev high pressure cylinder and three double ing frem the =ain control roo= and diesel house.

t flev low pressure cylinders. The turbine This is to avoid the possibility of losing both

'- ge:eraters and the conde= sing' sea-vater cooling, primary and secondary ecstrol systems or power feed heating and feed pu=p syste=s are all based supplies as a result of a cajcr fire, or

! cn vell established practice. your cain steam cissiles resulting frc= the disruptive failure 2 pipes, provided with relief valves and quick of rciating plast. Ter the sa:e reason, the l clcsi:g isolati:ig valves to deal with faults station, unit and auxiliary tra:sformers are take stes= frc: the stes: generators to the separated in g oups c= either side of the turbine i turbines. Tita.=iu: ccede=ser tubes with double house. Similarly, water stcrage tanks are peup-j tube plates are used to reduce the risk of sea ed cn c;posite sides of the main buildings -and uter impess. To protect the sten: generators re=ote frc: tovss va .er reservcirs. Cable

- frc: cerrosics, the ec=densate is treated in as routes frc= the = tin co: trol ree: and diesel i ics exchange deri:eraliser, which also precludes house to essential reacter equipment are sepe-j conta:isatics fro: sea vater. gated frc: the cable rcutes associated with the seccadary diesel s.nd emergency centrcl building.

- 8 ELECTRICAL SYSTEM -

. Pla . layout within tuildings is the most i The turbine generaters feed the LLO kV grid line i pertant = tans cf prctecticE sr.fety related

=: via two generator transformers. They also supply equi;:ent frem fires. -The auxiliary buildinE, y- the statien auxiliaries through two unit trans- see Figure k, which houses the auxiliary feed 4* fer:ers feeding the i ternal distributics systen system, the residual her.t re= oval sys e=, the - -

at 11 kV. 3rea.kers ene.tle the generators to be reat cr cha:E ing pu=ps and the e:erge:cy ccre

coupled or u= coupled frc= the grid er statien cooling system is divided into two broadly inter: a1 syste=, An alternative source of power sy :etrical areas, each area ec:taining

' $' for the statics auxiliaries is provided by two sufficient plast to perfer= the _ required safety. .

! station tra.nsfer:ers which are connected to the function. -The .tvo diesel generaters in the _

!. 132 kV grid line. The statien main distribution adjacent diesel house are si ilarly sep'eEated, __

j voltages' are 11 kV, 3.3 kV and kl5 kV. In the with each. supplying.the. plant in one half cf' the .

case of loss of electrical supplies from the grid, - auxiliary building through sepegated cable i fcur diesel ge=eraters are provided, any cne of routes. Centrol cables a.-e also se pegated

( vhich is adequate to su;;1y essential leads in strcugh cable spreading roc: e.b:ve a:d belev ,

cst circu=sta ces. the :ti: cc: trol rec =, *:ithin the ec:tainze:t, _.

-cables are sepeEated =ainly by distance.,

't 9 STATION 1.ATC"? -

Persca:el access _to pctentially ecst't':isate'd ~ _ 7

'.S.e static laycut, see yigure 2, has tees des- areas is via the _:ain change rc::s located in __

ig:ed to be adaptatie to a vide range of site the ccatrol building._ A :::ber cf sub-chsmge cc:diticus. '"he power tieck arrange:ent ;rovides rec:s are located in the auxilia.ry and fuel good access to the building fcr ec:structics asd _,tuildings to ccafire the s;reti of ec:ta. izatic:i,.

j cperatics, and =icitises the 1e:gths of i:ter- _ _;articularly.during raintenance,jVentilatien" f i ectnecting service pipeverk a:d elec rice.1 power .flevs are centrolled to ensure that the direct-I and centrel cables. The follevi:g buildi:gs its of flov is always frc: the less to the ::re I cc , rise the pover hioih, see TiE tre 3: ' e'.nti=i:ated zenes, frc= where it is dir

e.,.ec...

. ... .. c...a:.

. e . bul'ld: a..-

' t FCuEh filters to the ventilatics stack.

br.ilit-v bud ding -

. .- . . . .. .. ...r....... . . . _ .

,a a. -

9 CC1KLUSIDES .

accou:t of techno1cgical and safety develepsents The 7d?. design for Si:evell 2 is based on the verld-vide, ine.lutits the lessoas from the star.f 3d Jestir.ghouse feu- Icep reacter cf which acciden at the Three .v.ile Isla=d ;1ast in the L*SA. A thirty-tvo u:its are is c;eratics or,usder con- Table 2,gu==ary of the changes is set out in.

struction. The station desig= is based on .frca which it can be deduced that they Sechtel's SETPPS designs now in as advanced stage have tir.inus impact on the reactor itself, and .

af ce=struction at Callavey in MissourJL and Wolf that the general arrangement of auxiliary plant Crsak in Kansas. Design chamges have been sade follows closely that of SIMPPS. Thus the -

. whsrs necessary to meet IJK safety and other benefits of replicating existi=g *pla:t, in terns asssstial requirements. The design also takes of cc:fidence of meeting construction progra=me and ecst targets have been retained.

Table 1 Plant data <s e -

I Station thermal power of reactor :

3411 MW '

. Station g-oss electrical output 1182 MW Station internal power consumption * ..

72 MW Station net electrical output 1110 MW '

Fuel assembly array

17 x 17 .

Number of fuel rods . 264 Number of guide tubes: ',

for absorber 24 for in. core instrumentation 1 i Mass of UO in fuel assembly 523.4 kg 3

. Fuel rod: length i

, . , , 3851 mm ?

.* outside diameter .

9.5 mm cladding thickness '

0.57 mm Number of fuel assemblies 193 Number of control assemblies 53 Linear heat rating: average 17.8 kW/m maximum 41.3 kW/m .

Coolant pressure at vessel inlet 158.3 bar a Coolant pressure at vessel outlet - 155.1 bar a .

Coolant temperature:. vesselinlet - 293.4* C

~ ,

{

vessel outlet 324.9*C . j Coolant flowrate . . ~ 18740 kg/s

~ ~~ ~

Reactor vessel overall height with'the head without the head 13.55 m 10.08 m

--,j -

~~

- ~- '

Reactor vesselinside diameter ~ 4.39 m -

Total vessel thickness (opposite the core) 215 mm I Minimum stainless ciadding thickness 3.m m 1 Reactor vessel weight (including head) 385t - - - ~ -

.~

~

j

'~ .~ - .

Steam generator onrall height 20.63 m " --

3

~ - -

-* =

~- . . ' . ' _ _ ..-i_ ,

Steam generator upper part diameter - -

4.468 m -

Steam generator lower part diameter -

{ ;

_- 3.434 m . . . - '. drg _ ;

Steam generator U tubes: number -

- 5626 - ' -

- - ~

outside diameter ~ 22.22 mm -

= - -

thickness 1.02 mm _. _ _ - - . _

Steam generator (weight) empty 306t * .

Reactor coolant characteristics: -

~~~~*-~~~

-- feedwater temperature

. ::.~. .

" 227'C , _ L--

-' . steam temperature . -

- /~285'C

.,_ --..- ; ._~

steam pressure . 69 bar a J- "'

- ~

-- steam flow rate 477 kg/s ,..

I -

. _ _ _ .- -

ML20132F393

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