ML20080K646

Proposed Tech Specs Re RCS Pressure & Temp Requirements

ML20080K646
Person / Time
Site:	Farley
Issue date:	02/10/1984
From:	ALABAMA POWER CO.
To:
Shared Package
ML20080K639	List: ML20080K636 ML20080K646
References
TAC-53266, TAC-54234, NUDOCS 8402160092
Download: ML20080K646 (6)

Text

{{#Wiki_filter:. Attachment Unit 2 Page 3/4 4-28 Page 3/4 4-29 Page 3/4 4-30 Page B3/4 4-7 Page B3/4 4-8 a f 4 4 4 1 4 4 LeM 8402160092 840210 PDR ADOCK 05000364 PDR 4 P vre,--- + , - ---..s --,,na- -,,, - - -, pg -- , ~~ g -m,-, r- -~ ~, - - - ,,----,-e,-ne-g---

---

e.

--.--,,,m.-

TABLE 4.4-5 REACTOR VESSEL' MATERIAL SURVEILLANCE PROGRAM-WITHDRAWAL SCHEDULE VESSEL LEAD WITHDRAWAL CAPSULE LOCATION FACTOR TIME U 343* 3.12 Removed 1.1 EFPY W 110* 2.70 4 EFPY X 287* 3.12 6 EFPY Z 340* 2.70 12 EFPY Y 107* 3.12 18 EFPY Y 290* 2.70 Standby FARLEY - UNIT 2 3/4 4-28

1 i ,e i.:> 1 M.. -7}., : .' '.. t'; h-

I

..q i tg p.; n' p' '.. -

n

i:.-

3,:n.... _..:p.:. ". ; n.

Is3

. r. n-

p.

.l.. i.. 2 . n, n..i: .i. n..:p . r,,,

?!!j

...

'j

.st

';;j j:; g,.

,7

-I:.. "E ' :t. int . eC ...........;n-

• e s-Pressuse-Temperature 2000 MCurve AppliceWe for Hestup Rates up

[ [ H j:i ly ]l! y :;, l4 ..E 7 e to 00*f'/HR, for the Service Period up jji. jjjj Limit During Hydrostatic l J '~ '" b- - p. . Il *:. "':: TTE Testing Operetsons g 4ii: ag :'. Q ?! T to S EFPY,and Conteens Messens of " I" 8 ~i!!i 108F " as pasG far PossiWe I..c i i!Il l l M !d ill 9!! !!!! M !!N Nh l Ui! !!!! I! !!N i!N I!! !!!]lII .2., 2400

.ErwerWhnSteviaLHtrInd ocio f.3.EFPi..lM.,..b.1,..

J " iisi d j,i 1 .u id, ii?] ..f . T.i i .... ' !.i ......e m.. e uia

• t !!!!

_i m.ne :m e :urm ; 4. ;" i i! ii:t : n - i!E i 2200.,... ..!IHi!....in D,. l... liii I 'l siilliit 'iii illi ',:ii f!! .o. ii Iit wi i i iiii iE i 35 iit, i Meterisesassis: "ili ti.. ill.,i.F.id/: I.E..!,1 Ir lp. 'lu.i n..p:..,: -J9. ;ii. ..ti . ?apd l - t d> - (*i = E .u!. :.i:,J Contromine Meenrisis RV fator Shou .m i. .t t. f M a n 3 "l-p, '.' .. Copper Centent. 0.20% "4 C " m ln. . ~r;! E....1 - e . :ng nyt nu ..~ -.. I

t d

n-.- :.. ". ";,j ";:(} t;; ':"n'

d;p.

I" RT:[, RT snop -1: ;

. t

-:1 '?r NDT Orismal'-10*F n". .t

• rr Amospeshie l'p":: "::L:L!

1 1h: 1 '; :::: t-as 2;_

11t t:4: :" '. d g

u: 3 0;

m nh NOT After43 EFPY,1/4 T,%

3 1300 ~ '. ! "M - 1':"t i"' "d' " ' " - "4" it rt-3 4rt i 'M c- -I bE" i o Regionfor

• 18":

3/4T "ai g 2 i n: l tt-

1 e

n::

pu in

i.pt g.:; ;ia. -1.i,.

g.t j rjii r - jt: 5PF E

i I : -a

- p.- n -- r:a-r

n :.ty1:.

.n:,m 2., :. s ,4 ---n .n: n;a a : 1 1000 a:;n : , v ,.;,g q 9.p. 3 i .t p Testins L,r1 1 e qi

p fp; a

'I ;. h:

r.:su..: ,h:. , min . x ,i g di: ::a ;,,;.--p 1 , 1 it l' t3 o,,,,,i,,,. m r n s.

a

.y. . n - m 1 8 8! - fi p"- fili H" f IlMi! 1E 2:y I:"q!!i.. 5' N H411F*[" - UnseespenWo ' 8' l 7

• tt 3-es 1400 **ta :h' p'

't 1 . f, ;l

i In 7

--t-q: is: it i i Operations l !!..I; I

is::tr

.t:j he es n-

tt' pj t

~- '- L l'" .iP I t -a 5 i 00 i', I l l g ] .i U12 n .t N.~ i gg riqI7I ..cI { t~ so

ht

4 T '4' -{j 42 P I tiF 1' t ~ 4

t. 34 I'

l u 1000 ": !

'jil

ij 4 essure - Temperatues

- t J. , Cretseelity Limit fjy j g y 1 - t 1 O H i Limit for Heat Up Retos up;-'. .,i f r Based on Inservice Hydrostatic y W ' to 00*F/HR. ] U 000 '[} i F $ h I*h,! - I i j j Test Temperatuee (2778F) for jp f' ,ii !n Wie Service Period Up to 5 EFPY."fi i {t g n: 8 ~ lli Ii }T.' .i i 1 it' N:t" I .. j};{i l ;d

+ t *i; 1

000 n'jt - t .l' 2 : I -11 i t

1.1 jf{

l 5 liii j 9j i

• j

[j h';;{ .} ,l. q. l , 7,,;

l u; Operation

. AccepteWe i d. t l t:; u u 400 8 '* Iki.. : :I a

n: :n.

.11 n, L l 4 ,,;3 f1.h.: il Ie ...i et . ::t.:;) !:j

n.

p;.: }g1,; .i.. t a t Ji,,, j . 1},.';lri. :d;. ..{

t nt

1 :t. j 4

in n'

':,:t- :t..

.t;

., M.

U: , ;r fin 1 2 4

t!1

te 1'

::!

3 .t::

.f p;.

^ 2 g II H '!n dd

ll:

i:t :[i.

n. :.. t

. 1. ! 1 -.t - nii :::p;fin: ..z;

t..

~'

. i t, '.

- n. -

t !.:I: ii;i, h .d'!!

;; :((

1 N !!i.i.!"p.i.!jli !, P, il'!.ij1' i:i.l, i'i,l i_4 : ., i :, t,. :; .:4"; .t. .t.

f.,: a i

..i .1. i .i 0 50 100 150 200 250 300 350 400 J l AVERAGE REACTOR COOLANT SYSTEM TEMPERATURE (*F) l t i r I Figure 3.4.? Reactor Coolent System, Pressure - Temperature Limits Versus SO'F/ Hour Hestup Rete Criticeiity Limit and Hydrostatic Test Limit i,

n>m r-rn WI jIi! il! l! !i!! :!! fIi !!! ili l !!l Il ![i Illl i !@ !!! !I f ji di llll Id ilIR}i" [ I i il l l! l! !!! !l!j$b !l! ii. 1!i "!: .i! 'll i l. til ! il.! !!!! ii!. tii! iiii il A !!! 6 4!i N M-I J !! ill! i i ;i i 5 2Il00 + .l Curve Applicable for the Service 9 { l i l l.l ~ (( j. " i-I .i

k...*

i j'. -.4 j-- t it N iPeriod up to 5 EFPY,and Contains [ ~ 2200 ! Margins of 10*F and 60 PSIG far _h ci L - I D--"' b -Eiit.Euerfed j ' SovictRri.d upth 9 3 EPPY, .'.l 1 l [? i (2h ' I; l i. l

i

[ } . g j 2m 4jjg,,3,_ __, y d i 1'0 1~ - - ) 1 l! [f; 'I !N'"!! l 1: ,L ~j . l !!! . !!! !! j !! ! l i.' z l 1 I ! iM' ii Tsi i i l'

i!) lii.,!!!! !lli ! il !!!!

ii: lili !!fi !!! :ll W

1e00 ^ 'r 1 ! il i !I li! Unacceptable!!!. iii: !!!! / li /i isi li!! E h L,i,i ! i E! F F "4"" li i i, lii F, iii; ! ll N !im! n h. II 'l 'I.' I 'l m.. o. M liH Illi l H

. o p.

w 1e00 ...I I.miiiI ti Operation iil e i[!i i~!~ ,l i II! I li 'i il i !! f !il t!!I i '!l T f' 'I t i ' 'l l !! 1 '!i t !" iiij i it !!' i i "i!!!:ii lli lii' " j* ' /'ij iii: 'i liij ${ - 'fi'}' i

i!I i'i i'

i'k lE H

i ii 4']'*S'. P}?j i"* ~ ill'1 f. 4 11 }. p"jd

l. ' i..ii.'i!'i.i.

,i. f :. :. ? .'1 r ji. { ' '!,.'5 0 W 1400 f f j j t I F i!

8 i.

i t I t-1 i-g.3 Il n.. t i. + p.- 6 + -y.~ ,/) i- .,s. ....:2-:..q j4r.} 4 -t y' u g,6 lS. g,..

1 :

.'j j:: ;;;. i... m. i 2.

f-(4 y

l. J.

.l

p!, '.,

~ N ,,3 1200 3 E' i 'l fir Acceptable p. d .:li hl I ,,I } I l i i 2 t i a. p { Operation jl i Pressure - Ter'nperaturel M ~ ] 2 L {j t.a a 4 l -tj t .. l } r + 1000 p I i I I k}; i Limits g o i , M E i -f -p l 'i ]I - -{ C i ll )I!l l' I l ! ! ! I IN k il lil! l lll u + ' F l - II

i 1111 !

i k.i :! !![ t a. liiitit&% I i; i i I i i - [1. z a /;I I t!,:,: u. __.m_. _4 "n.Materials Basis: E '!!i h !'!i I. '!! }3 ;h I T ..Cooldown Rate (*F/HR) l lii.!. "j' '8

yg

_7. i j l,;; {,;. ;{;i ;g

q 600

1. g,,tg 4,,,,,p

. 4,j, 9;.. . ;,11 ;;;;ipm!,,, Controlling Material - RV Inter Shell lj E I 1 l -t = I o i , 0 em O! !* i i'!l l Copper Content,0.20% "Pii: 8'. 20asf" : m,,,M gT 11!! l.;! ljjj i ; b;; ;;;: j[;i i j:,i l l ll l j ,Pi 60 4 s' -*T '!. ! ;j-l'.::i

!!. !l!!

.ii: ;, RTNDT Original,-100F

• i!:: p.!

400 Iji' !! l jji 5 i~ t MTIE i dM "t '! n l " 1RT Or - l- . "F '100**... ' ' F tiu

iti jj;-' !!!!

.!l NDT After 43 EFPY,1/47, ~ p f,0 ~ ":i:: a 3/4T TIE l i: j ;;6

n.

~:! i i.: al,1 i,, ,j 200 f

!}!.

.pp .t ., : h j ti

i : tm.4.,.

11[f, il h,,. . M:-

n

~I II N: "l k..'~I

ti-m d.i, i

~:

n H~ i' '" iP: ' :,i - "l : :i..i. ':al.i.i."l :in 14 ? '. "I'1T -

l. 'I

l!]!i Fi !m TP c.

a ::n i i iriT

b

~. il el i I O 50 100 150 200 250 300 350 400 AVER AGE REACTOR COOLANT SYSTEM TEMPERATURE (OF) Figure 3.4,3 Reactor Coolant System Pressure - Temperature Limits Versus Cooldown Rates

..j. REACTOR COOLANT SYSTEM BASES.

4) The pressurizer heatup and cooldown rates shall.not exceed 100"F/hr and 200*F/hr respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 320*F.

5) ' System preservice'hydrotests and in-service leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel Code, Section XI.

g I' The fracture toughness properties of the ferritic materials in the reactor vessel are determined in accordance with ASTM E185-82 and in I accordance with additional. reactor vessel requirements. These properties are then evaluated in accordance with Appendix G of the 1976 Summer hidenda to Section III of the ASME Boiler and Pressure Vessel Code and the calculation methods described in WCAP-7924-A, " Basis for i Heatup and Cooldown Limit Curves, April 1975." Heatup and cooldown limit curves are calculated using the most limiting value of the nil-ductility reference temperature, RTndt, 'at the end of 5 effective full power years of service life. The 5 EFPY service life period is chosen such that the limiting RTndt at the 1/4T ' location in the core region is greater than the RTo t of the limiting unirradiated material. The selection of'such a limiting R ndt assures that all components in the Reactor Coolant System will be operated conservatively in accordance with applicable Code requirements.. The-reactor vessel materials have been tested to determine their initial RTndt; the 'results of these tests are shown in Table B 3/4.4-1. Reactor t operation' and resultant fast neutron (E greater. than 1 MEV) irradiation can cause an increase in the RTndt. Therefore, an adjusted reference temperature, based upon the fluence and copper content of the material in question, can be predicted using Fipre B 3/4.4-1 and the recommendations of Regulatory Guide 1.99, Revision 1, Effects of Residual Elements on 4 Predicated Radiation Damage to Reactor Vessel Materials." The heatup and cooldown limit curves of Figures 3.4-2 and 3.4-3 include predicted adjustments for this shift in RTndt at the end of 4.3 EFPY (as well as adjustments for possible errors in the pressure and temperature sensing -instruments).. i 2 -FARLEY - UNIT 2 B 3/4 4-7 . ~

t J REACTOR COOLANT SYSTEM 1 BASES Values ofdkRTndt determined in this manner may tut used until the results from the material surveillance program, evaluated according to ASTM E185-82, are available. Capsules will be removed in accordance with the rquirements of ASTM E185-82 and 10CFR50, Appendix H..The I surveillance specimen withdrawal schedule is shown in Table 4.4-5. The heatup and cooldown curves must be recalculated when thetLRTndt determined from the surveillance capsule exceeds the calculateddiRTndt for the equivalent capsule radiation exposure. Allowable pressure-temperature relationships for various heatup and -cooldown rates are calculated using methods derived from Appendix G in Section III of the ASME Boiler and Pressure Vessel Code as required by Appendix G to 10CFR Part 50 and these methods are discussed in detail 'in WCAP-7924-A. -The. general method for calculating heatup and cooldown limit curves is -based upon the principles of the linear elastic fracture mechanics (LEFM) technology. In the calculation procedures a semi-elliptical surface defect witn a depth of one-quarter of the wall thickness, T, and a length of 3/2T is assumed to exist at the inside of the vessel wall 'as well as at the outside of the vessel wall. The dimensions of this postulated crack, referred to in Appendix G of ASME Section III as the reference flaw, amply exceed the current capabilities of inservice inspection techniques. Therefore, the reactor operation limit curyc1 developed for this reference crack are conservative and provide sufficient safety margins for protection against non-ductile failure. To assure that the radiation embrittlement effects are accounted for in the calculation of the limit curves, the most limiting value of the nil ductility reference temperature, RTndt, is used and this includes the radiation induced shift.dkRTndt, corresponding to the end of the period for.which heatup and cooldown curves are generated. k + FARLEY - 0 NIT 2-B 3/4 4-8 e . _. -,..... _ _. _. -. _. -. _ _ _, _ -,, - -. _ _.. _ _ _ _ _}}