,

D1' W T T

j3d .- 2. 3 W~

>

60ARD GMISlY 25I|)

gp'87 AUG 12 Pl2:07/0308%

listed in Table 5 2-11. The ferritic =aterial .(including veds) of the rese-ter vessel beltline vere not ordered to any additional checidEl requirements.However, the prediction of the increase in the transitien temperature of thebeltline region materials due to irradiation induced embrittlement is baaedon the ecpper and phosphorus centents of the beltline materials and on thecalculated maximum neutron fluence at any time. Topical report BAW-10056, |"Radiatica Embrittlement Sensitivity of Reactor Pressure Vessel Steels," de-scribes the basis for the increase in transition temperature prediction. -

5.2.3 2 ce=tatibility With Resetor Ceolant

All =aterial exposed to the reactor coolant exhibits corrosion resistance ferthe expected service ccnditions. The materials used (as shown in Table 5 2-11)are 30L SS, 316 SS, Incenel (Ni-Cr-Te), or veld deposits with corrosion resist-ece equivalent to or better thalt the above caterials. These materials werechosen because of their superior cc=patibility with the reactor coolant. TheRC syste: pressure boundary centains no furnace sensiti:ed vreught austeniticstainless steel. While sensitited stainless steel veld overlay (cladding) is |permitted, the cerrosien resistance of these selected veld =etals is excellentunder reacter coolant environ = ental cenditions.

The RC syste: is ,a controlled addition closed loop which, of itself, is noconducive to contaminant introducti:n. In addition, purification systems areprovided which vill maintain the contaminant levels within the limits speci-fied in Table 5.2-12. The caterials in the EC syste: vill not be adverselyaffected by expected contardnants er radiolytic products. The cenpatibilityof these aterials is further de=enstrated by the excellent cperating PWB ex-perience in the specified environment.

5.2.3.3 C =patibility With External Insulatten andEnviro . mental A :csthere ,

"ne reacter ecolant insulation is all metal reflective insulation fabricated ;,

frc= austenitic stainless steel, which is cc=patible vith the reacter coolant '.

pressure beundary caterials.;

In even. of ecolant leakage all stainless steels including ir.sulatica and In- icenel =aterials are cc:patible with the resulting enviren= ental at= sphere I

and no effective corr sion is expected. Carbon and lov alloy steels may be jsubjected to sc e general corrosion due to the boric acid content of the cool.-

|ant. H:vever, for the expected environ . ental at:0 sphere under operating c:n

,

diti:ns the c:rrosion rates are very 1:v and vill not affect the integrity of !the reactor 00:isnt pressure toundary. I

t

I5 . 2 . 3 . '. Chemist / Of Res:::r :::' ant '

||

?.e vater chemistry specift:sti:ns f:r the rea:ter coolant are given in Tab *.e5.2-12, and pr: vide a. envirenzent vnich is cc=patible with the rea: Or ::cl-ant =aterials (Table 5.2-11), and the cere esterials (7.irealey and Ine:nel). i

Tc.e pH cf the ecclant is ::ntrolled by the addition of lithiu= (711) hydroxide {to minini:e corrosien Of the syste: surfaces in' contact with the coolant solu-

tien. In turn, coolant a:tivity and radiation levels of the ::=penents are |

mininited. Hydrogen is added :: the coolan* "" ing e i fpal cperation to !f:ne:1: ally ::: tine with tne Oxygen pr:duced die LiU of the vater. During

,

('S.I-10 Am. 26 (L-1-75)0708170225 861030PDR ADOCK 05000320 pfy - t. u.f 3

: O PDR1

_ - - . _

. ,

be

,

!

i

'.i|

|

I

| \

|

1

t i

f'!

! !

1

I

,s

1

''y,

s v;

v+.: ,: 4@ y

'N:

7x,x

NTx %>,$.,@g..sx xg4

L '-

.

W /*h,

f

%k'd# , YP O

,;>Y S' ////gj f[8gIMAGE EVALUATION

///7 \''[' k ks# TEST TARGET (MT-3)

/ 4<g[ ft /g

$'

y,,, +,,,,+ s

,

1.0 it 2 Ela5 m II|p=aa tu

bdhC|,|I.8

1.25 1.4 I.6

4 150mm >

4 6" >

#% / '/4

'bh*',,

RsQ;,ifhb't/, 9

o- 2

&s# 4

I%

b h*If/%# IMAGE EVALUATION ////g'f ,f (; ,

/g/7 if. TEST TARGET (MT-3) KY 4> # ,

y,,,, + /4 t[f $4"

1

,,+ %

,. o : m m .5[ff IlllE.

! IE IllllB|-| m,,

l.25 1.4 1.6

4 150mm >

4 6" >

k +,//I*i i h'

' '

aV .,)

_

*$* gh*%$9 IO,pYbhM#

////g k // g[#@{p /g,8tIMAGE EVALUATION

//o//%"*" gI/ TEST TARGET (MT-3) NN

y,,,, 4i> /4 4 $,,

+ <,

l.O ?? M Mf|;} ||||!!l

|,i [m llilM|

1.8

1.25 l.4 1.6.

x:

4 150mm >

< 6" >

*> +zzz$s+ zzgQhekhk%f'*

5,,ffff y______ _ _--_-____--- -__--__ --_ w __ _ _ - _ _ _ _ - - _ _ - A

_ _ _ - _ _ _

& g@ee

< 96 /# h.k .$

//'//g [ \\\\ q,|g[h'"&p'([g,IIMAGE EVALUATIONo %W 44

\ ,jpp/// 'Y;[ %f// e '%TEST TARGET (MT-3)

S&f''' ^

\'

'

p'Y,+

fg,, p,,

\

I.0 ||: m tatu W |p~gb tu ' =

|,| fW h$O:_ _ _ L8

1.25 1.4 'l_1.6_[====-,

4 150mm >

4 - 6" >

*&>,,;y,%A + /,or

gb// +;p

/#3 c//yy g, #> // #<b,g

4o .

,

_ - _ _ - _ _ _ _ _ _ = . _ _ - _ _ - _ _ _ _ - _ . _ _ _ _ _ _ _ _

._ - _ - _ _ _ _ _ _. . _ _ _ . _ _ _ - -

1 *

f .

!-V

'

,

L

g' \\~_e

non-eritical operation celow 200F, hydrs:ine is added to chenically rea:t vitnany oxygen that may be present. The additi:ns of hydr: gen at hydra:.ne v; '.d

minimi:e the effect of oxygen on the corrosion of the system surfe:e at tneexpected service c nditiory.

5.2.L FRACT"RE TOUGP. NESS.

5.2.L.1 Comr11ance witn code Feautrement_s

The pressure-retaining Terr tic materials, not including piping, of the rea:-ter coolant pressure beundary were ordered and tested in accordance with therequirements of the 1965 Edition of Section III of the ASME Code includingall Addenda through Summer 1967 (see Table 5.2-1). All the piping was orderedand tested in accordance with requirements of ASAS (now ANSI) Standard 331.7,dated February 1968, including the Errata dated June 1968. Neither the 1965Idition of the ASMI Code nor the ASAS Standard B31.7 require the determinationof the nil-ductility temperature (NDT) as obtained by dropveight test, or theCharpy V-notch 50 ft-lb/35 mils of lateral expansion transition temperaturefor specimens oriented in the "venk" direction, as it is required by the Sun-mer 1972 Addenda of the ASMI Code.

Charpy V-notch tests were used to meet the fracture toughness requirements ofthe 1965 Edition of the ASMI Code and of the ASAS Standard B31.7. The number,

,g direction, and location of the Charpy specimens were in accordan:e with the{ referenced specifications. All the ferritic materials (including velds) of\~- the pressure boundary met the energy requirements at a temperature of +LCT er

lover vith the exception of the core beltline region ferritic materials ofthe reacter vessel which met the requirements at a temperature of +307 er lever.Ter the veld deposits the transition temperature was obtained by performingCharpy V-netch impact tests during procedure qualificatier. On veld dep sitsusing the skme flux and filler vire ecmbinations as the production velds.

As an estimate, the reference temperature (P.T,2.) of al; the ferriti: mater-ials of the reactor coolant pressure boundary" 1 predicted to te equal : :rless than 607. ~he referende temperature is defined in t'.e Summer 1972 Ad--

denda of Section II! of the ASMI Code, and is determined by the drepveigntnil-ductility transitien temperature and by the Charpy V-notch 50 f t-1ts/ 25mils of lateral expansi:n transition temperature.

In addition to Charpy impact tests required by ASME Code, the nil-:uctil:t,temperature was obtained for two of the four plates that :omprise the ::reregien of the reactor vessel. The p; ate material is SA-533, Grade B, Class :-The dropveight tests were taken at 1/L of the plate thickr.ess , the same 1:ca-tion as the ASMI tests. Specimens were oriented in the leng:tudiral direet;:n.The veld depcsits of the core region vere impact tested at +10F using :narpyV-notch specimens oriented p, perpendicular to the directi:n of velding with tr.enotch ncrtal to the surface. No upper shelf fractare energy levels were de-termined.

. ''N,,

>iV

380 229 |. ,

i'5.2 11 mTM $pedegr

e. ,e.

~

-__ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.

.

/

(N

Table 5 2-12.REACTOR COOLANT SYSTEM WATER QUALITY

Nermal Steam Generator Feedvater Quality,

Total dissolved and suspersied solids (max), ppb 50

. Cat Icn conductivity (max), umho/cm 0.5Dissolved cxygen (max), ppb 7

Total silica u SiO2 (max), ppb 20

Total !ren as Te (max), ppb 10,

Total cepper as Cu (max), ppb 2

pH at 77T (adjusted with a monia) 9 3 to 9.5

Peacter Ceeln.nt Quality

Total solids (max), " ppm 1.0,

Beren, ppm See Figure L.3-2L

Li, ppm (when required for pH 0.2 - 2.0(b)lithiu= as 7o adj us t=ent )

k. pH at 77F L.6 - 8.5Dissolved oxygen as 02 (max), ppm 0.1Chierides as Cl- (max), ppm 0.1

'

Hydregen as H , std ce/Kg H:0 15 LO2

T1uerides as F' (max), pp= 0.1Total dissolved gas (=ax), std cc/Kg H O 1002

I"IIncluding dissolved ecd undissolved but excluding H E03 and LiCH.3

(b) Equivalent range as 7LiCH is 0.666 to 6.66 p;r(* E:;uivalent pH at 600T is 6.h to 7.8.

165-

9' 0O" {

''

mm 1|

. 5 2 L5 m.,mg, ng u - . m

.- .x' '' j

_ _ _ _ _ _ - _