ML19257D369

Revised Pages 2-1,2-4,2-5,2-6,2-7,2-7a,2-15,2-16,2-22,2-23a & 2-23b & Figures 2-1A,2-1B,2-2A,2-2B & 2-3 to Tech Specs

ML19257D369
Person / Time
Site:	Fort Calhoun
Issue date:	01/28/1980
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19257D366	List: ML19257D365 ML19257D369
References
NUDOCS 8002040222
Download: ML19257D369 (16)

Text

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e - c. w n.+u m.,4n.. m .vv yv .-s o uue. vpm.. N n_ u, 4.c . +4m . n n v. t.r r.3 4 vy 7 i.. 4. < r ' C c ". ~' # * #. -.,' " ^ -. v ug ^"*".c.+.#. ~. - a'n.' n. .c C r_1' ' va' o".- ,- i .v my-( 2' ')

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C^. "e c e v v.- m' e v m'<.v tm.- c c-.e., m-n- y. e .m.. o -_c c e. e '9 ~ ---w y injectiCr p rp An the ZutdCWU Cooling rode Shall be in Cper-m, +m o,. + n n,. n.- .... - m. .u. c. v3 e .4. c >vt,, m t. ..m, ame i ".

• M.. 'c."c n c en c e.o.'."a-c n -

.i tien of the reactor coolant when fuel is in the reactor. (o) _r.m. n,,. <.,, cm,: ,yv .v 1.,._ +n,.c gm.,. 4., e.. ,+ 4 t e. c 'v.i v, a'u c. c,. t "u e v- ..i.-4,. n m m. o 1 p 3 m*e +yn .."".c". Co -.. _1 1 ' t' i ", ^, e c v _ m..*- v'n " o ' i c", wh e.".- ".", o e r y n V v. + b.n_ -.a. w. . n c. _ o c.,. .I c p v. 4 + 4., a 2. 1 w-,+ o _.v4% i z ') r l., :..... v v.r a s. _5 cm.. - o- . _ 4 nu, o ,,t.._-. v.. m. . e i, e 2.e., ck,,, ..t-.. c .2. m_e a 2 m 3v-t u-C. L, - a..i n. +v u. l i j u o.,:. c k..n,a~.1 _-;.,.. % K i n. .'1'. t, J v u 0 4 (L) C'ne ctean reneratcr shall 'te crerable una the other steam +cr

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e + b_ v t, a.' u' 'v e9 C uD ~' l o ".# te..y oc+uw, r .4 v. p.mo .t v. n ou u. v m 1s aCove wo':. ( p- ) 1.........r n s, + c. e cc, c r.. c-~ mc e.. nv .rw ,+1c _ve ~m. mre _c c n r e s p.,1., v c ~... y be 3125 psia. A ~ u n.u~. of 10 cycles of 3125 pcia hydroctatic tests are allcwed. ( 6. ) L. r.... s n u, v.s. o,. Lu..,nm+ctle e ~c. y. m~. - c. _n,,__ h,, + -a ,,, e c,...,, . u i.. e.ceed a m. v 1250 : cia. A cininar tem.rerature cf 82e? is rea.ui ed. Oni.v 1 10 cycles are permitted. 1869 014 m m.ve m.. m..c.c. 8002040 9 7 ')

7 .r -. L, aa t t u.. m, _,.., r h u n.1,. _m_,. u,.c u'.1 r_ u' ". C' oo.' m. +. s". o '_e. " ". +~i '.n.e 4 ) 2.1.2 lie ntuu and Cco-ncwn _ute,.,ontinue a (a) The curve in Figure 2-3 shall be aed to predict the v e, as-m m3. r.,. : e m m c n .., e c - r, w-mm

v. 2 4,, e r - 3 +v -a u

.t m u u- - m e .# c.c., +. r.n... won. m TP m C7-m w.. n,, vc, r.~n, + s c,.,, +v..n_ 11*.r n a, a+v.4ca b 4 m .-w specinens indicate a deviatica frc-ti.is curve a new c u.. c. c u.. m, - w 2 ue -..e c+eu. o v (, '; '. a..n.i t.. 444 7 1 r. p ~, + k.a. c m,eeo .lgm a,n7, e.. n at -- v e u .o. J, v .-an+ A o r - ~_ u" ._ va v. ,.m 4,,. m .y c. n_..,,..,, -n.:-ca ~- .ocu,, m - + k.a. *ctol u-o m. 2 c. ~ v ,.. n -,, n + n ^." e o a + ^ '- 'v.M. _ m a_' 3" c~om" '".c- .c + n ". "v "m'p +v o +v. e k -e.-- um

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,i tma. -,, o_,..,. c m. no m u% e m. _L 0..., 0 +otov m e rvi en v v vu ..v., o . g_ ~ n. u...,m ca,, ,,t...u.4.,,1 c.., , m c v. v~. ~u u, c e c_. c~.v t,a., n.n. +v - .j-v..e v a m. 4 c v m o -n-e a .-n + o +.w. wc + u. - ah W-u +v to ~.. w:.. e s m. y u..ou " o +v c"u u u .c~., uv. n e.t, w,. n = : e .mo "d' ) t, r ** q r v. t. e.+c 5.- 4 hf. -...e u. ,+ o n, +w-t. Crs.' n, O vo o vu_ vm un +., c,. n + n,m yo~. m e L n. s l..v.. p,-t,. a'+0 . 1" +v 1-q v stand the effects of cyclic Icais dye to reactcr coclant syster (1) + n_. e.m. r.o. m,cs.a ncc4,y a c n.r e c e,,. t, u,,, y.-o-m _ coun n_v. 1o_s u-re intr ^- v c c a ..y -s m duced by nor'al unit loua transients, reactor trips and startup anc shutdown oreration-Durinc nit startup and shutdown, the rates of tet;erature and c pressure chanres are limited. The de ci ~n n umber of cy cles for L-heatup and coolm.wn is based upm a rate of 1000F ir en"J cne hour .perloc m a.or c"clic cperatien. s The.aximun allcwable reactor coolant syster pressure at any temper-ature is baseu upcn vhe stress limitations for crittle fracture c on ci ue rat ion s. These li-;tatiens are derived by usin6 the rule s ccn alnea in,ecticn n1 b" j c 1, c. v s . h e e. c.,,.-.e..:. voce In cminc.4.r.nen dix v a 4 ', M e _%b."v.3 } e~ - u o', *.. s v.., q t, d.' <.%u..g mm vv v g M 8 u y - 3 m m'g ,.a m o'. e u. pq ,4 g p g= .,gu-ne 4 g .i e LU v4^ m'm. )- ) A4 ..p p ml u,' (', T. v. s o_ c'o,g. -k rua t, h,- Ln.,.,1' e0 v.m a +u. o mb'o-k n .A o .al u va.- 9 io '

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..ow_. ev. -.w u,,. 5. tn ~. u + e.n.a' ' c ' 2' -c.' o e~' rA ~. M o *o c"o'. %. 2 % e vt_ v 3 .. i l ' ~u +v ' i +vg" i m." c * "a "e ( '.,,1- ) c ' o n ".. '2 m' ' 'v e '* s 'v

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' e."..y .c u t _v m a 1 e o +u.co., i e wo. m t. y c na -- e.e -+ + + "ovm. C.". 'm"",v -., a 'v u o '~c h -e e 'v.m.n w..'or.med e w m., m n tc deter.ine at what temperature the plates exin alted 50 ft,lbs. a J o, r.wwv e u. o.n. e.w m u.a. v)...; i e m' o

t. _c, e.,.m r,,y -. c v.1

.co.w + k. s e v u.i.". a '. -: +n w -w v v m g u v. u.r n C +v 1 ~.,.. ...,. g. e n > m.. m s . :.,s._ yur+1C, ty '..; -- d ....c ,-nA .g e e t c.h m o.v v. c ^ lsc ame m-m.. c. e '. e.. m *m..,a_."_*"a. v. _~. -. c e _ _ c.o. (.:.%.,, m ) o ' -lco c.v. 4 ' ~ m <3. ._ o. 4.. e-c s, ,r. ..-...-....e,, c % ;c1 in +v%a-tm. _ m...n u, ca ...-m. v1 ,. a. v y m m r c c c.1 c. c. A .un n e. y c _n. o m 0.c 4 a, g. i., v_, ,.-.n..,r, , + + e3 e + 1.n.o e3 .m.t. -...-c m.m. . v %s o.v n o_.r.e,,,. 1 t.~m . o ~~ n.~. m y c.ame %.. o l -,.,. ym e. e,. <. ..~n r. + - 2 c - cw c-g... <m d a v t v y C ^.s,. a..P q *,., n. ....so. ,{ c. q, P. q,= .v.~a

• n si.,. _.,.,.

~ -o .. s rtm,., + c. c,. r s ~, s o ,,,,24 m m. .u_. --v. ma .-ca 4

u..,.ers ca-t,a t %u. co 2,e,

o m u . n u v +vm, ..o. n m. 2, 4,. . a. e.,, m -i +v >.. c o.4 a 4,3. mk.e +ve +m s. _ ~ t .. a mut ut. a r ~ e m' ru' s (; g _ c '. v..e ' r. %o v. s't *. e 5. ." _c 'v ". o u v.r "va a =o _> ' ' '=_ V ) fm' ' v.e o m e c f ti.e reactcr vessel are described in Section 3.h.6 of the FSAR, 9.m. 'v..-N e ." " +v m e~. a' 'v e m'.N.> +v '. ww e.'<.,,.o v mv..',.'.u. 7 - 1 w.' a v +v -s c v a m .v o o 10W "./cr,c, incimw tolerece over the 20.vear desirn life of + k..e . n ~e c e _7 ?) v ~ uercn. U n_ c e wa .n. c,m v.. ~.. .nn ..m' + %.m . ' _.. ~.n. w, v n..~m mv . +, c7 n v, .wv..e n n.. > 7.c. - %. d m. u i e e a v o-3 o u ."0".'.'v^" ". m o" m"#-.'

1. ". ~'.4 Ame " m' O. ' ',i s " l.'. ^ "u _l

."s. ",.oy- .' h " + #-a~AC"1, t '.. e "~. ~m ' s" 'm' ".^A-m s v. a o. u ~ u e.r.w a: +4.r cb e c o. 1. +v Cu -ay-w n ~ w,. i n w s v a ve s, n _,2 t, a +o +v..n_ .- a,j a cnn +e s Ccn v n n n n+ 4 v viva u u o.y w v au u om of the reacter vessel for later stages 1L plant life equnalent to the difference in calc ulated flux c'i~nitude The "aximum eyposure L o.e t b._ "e s o~ e.' " _11-ba

o. k '.m.m". t> u~.'."c.-

'. M. m ..o c - "_"e d ~ o m.y.'ta ."c m c v c. d mo o c e r.o c c ure b." a.".nli c a ti cn of the calibrated anzuthal ncutron flux ,..,,,44. c. 2 a v.4c.r,. ..t, r.e....,,.,.,. (' ~. _ m .n eu, o,-+ .t, = ) e Xp o- ,.,.,.12...... . Lx r ...u s av. v ) vm t. a v .u~v c .v 10$,% a .c.~.. e ca .-o..c.. ; wy.. .eos-. 4 ,,sm - ~- ~ o w .e.u .u +m,e.- a.,a 4-c...,~'ve-d 'v o b e n/cm fc2 40 years operaticn at 1500 it and 8% lead 5.5 Is.,+o.(2) m.ut,, s le eu a r.._ c. c a o-1L< i - 10 c o .. n% ee ti c,. m-v em v n e,a r,, m.a av .-e o (.s 1 c,,.e,s, ), e xp os'.re c f ). 5 lo'bc n,jc=- 13 nun, t.ne va,ue ob-o. --n, r +c4,ea c t... + %... umL a 0.,..n - %.v a 4 n. < a e ^c _ a. m n. n s,,,1

m. ot <n r

. - m. c.

r. -

w < 1., b e "o o c + ^ '.4 - 1"._ e. i c.4 i e _n ' _'s' N1 s 'ra e n +v - .",' i cn. [ ~ -ov_ m y b testirc of reactor vessel raterial sa les which are irradiated c ~_ ul " i v"1,", 'y-c o ' u ".4n ~ 'v.. -... ". e ' v M k s 'm.e '.". _" " 'l o.e + k e ."n a u^ to r v.i vessel as described in Secticn U. S. 3 and Figure h.5-1 of the PSAR. To ccrpensate for an.y increase in the T.my, cause d b.y irradiati on > linits on the pressure-temperature relaticnship are periodically chanLed to star within the stress litits durinG heatup and cool-e down. 21,. ci s o f the first removed irradiated reacuor vessel .c,.. >..,.e. l.1 ' c..a u, e - e n 1 w..~a ra u. r a. kco o u ,a, ' u v + %. -w.,, .c 1n a, m e

u. e

+. n a * +1, end or c e c v udt a. v va e c. 3 v f o fuel Lf, ele O W1J.i e 0. 04 x..:. o,w nfc on t.ne 1ns1ce currace 01, a_ c o m _1. ( ) 4 v w v..e . e d, s-v c,, n-n r. 4 - C v, r I,t, a p u u< o -). o .r..c.a0n+:u2 Vp - -, ~, - 4 .r l.'L c .a ~ u c-c v, n., o-( r. ro. v.,i e. "t<C, '1.s m tr.%- m.m..nm f~ u f. m 1 -..e. -k< o.e v 'n n p ..v, vJ + c.. nm 4 s.. iw v vvv -... a 1,,1 C4 Q}QOr. r. 3 + a v.., 4 r. p. i C.wmm. '.' ? y., w t, O._7 P mi s Go ..a u. o 1869 016 = ..t. m.'. J*

m.t3

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n.. a c.~.. w n..,

.r,.

c. a _2_m, -r vua t

mv .._e.,

.. a,. c,.

C, o _,,,.. tc,.4,a) ., o- _ c _s u, mo m._ t o -.. v m 2.1. 2 Heatup and Ccoldce Rate ' Continue d) \\ 2ne lini. 11nes in r,igure 9-in, t.nrougn e .,c,_ are bacea cn the. o m cw-e .in c. : u .u. m_ - e my e,- a Co o., 3... c,, .,.e m _ p vec.2. _TT-c e . w m. /eu Co m a a. e .1 v. m m 3.ppendix G-2215 = .r .:. r t.. + .T. ,...,,s.4.,,,,,c,4., .o _rz-c._ _ ~.,. m n ne. +e,m.u.- eu.me _ - ~ ~. u,.. c n w. u., .t... .e ~ ^^ 7a 3, O,.'.9.--.- ( m* * .?....' I uT ."'4 su.e G m O.1'. .t eu O71 ) c+,..m.a- _...c,,..a.., .m, 0.,. . e... v ~ u, t o. ru' > s u"c_ i..I. c4+ o ,r,, = u.-~ --.v. . s o v. e.> ~e . q,. \\ m.1n. n c c c. e +v,,- "". c" o f' c' o n. "."e "o "u"e. rn_ "." ~o ". w " y s c. o - c 1 c. . u .u- .c t,. 3 3 +n .' n e m c ". ..,m.m.-4.- " m m i a _' + k. ~a."... l c4 ,., = e "m' m"_ e n 'v. ~. q, m m.u. t, nu e,c,.s _4 n.. 4e n,. +c + v.e. -.,. t. n -o,. m +e c..., c c e. y a 1 u _4.. e. my y _1 c_ m- .m e m e- -m. .vn.- p._,m,.,.. ,n _e.,3, %.... w. c + - m.~c 4, n c m i t,~a 1.n. e i " i gn.".m fv t "n ov-o o t h..,. - -n e e, vo c + o., e

c. n. d

m. r.m. e l. a_ v n.1' m. n. o.

• m' e

o %,. e e. +... .v. ca+e n._"m A e v. o y.-mou- .; m m m .y um o.' _' c"o 'v^*

k. i.i + o ". p. e ~o "m"a.

r ~v.- 't."._+."," 4. 4 e,

• k.. e."o. '. v' "e c c -

c m e;.. o v a _. a _4. o. n n c 4 ^ > ". ", .~u*.._"....m_ '.n. e_.0",, o" cm ,o '.1, = 0. r c,. -, n.,. g.. _.u a ~.,., +,t,., ..,,... _,_.m. t, o,._ e s. +. t o. a . au. a m m. _4..m. me m 7.,.. _rn +v '.., = ASE III, Figure G-221L-1 -:'re s c m,.u a l a t = .a. = ,-e.,, =.m 4. n ca mo _

1..

vtmot_ t = Vessel Tall Thickness - in. .. g , m- = .1. is no... .c,, .. l, .,1 cure u,, u 1*3.-2 Al r. 90 1

m., =

i. i E,a..e c.

u pos -, so.

m. t>

c,. a. m t, u,a4 e.. o 2 + -a al _, e.t %.. c,. n -om +. e w of Cocidown K17 ic therefore calculated at a ray.inum gradient and is ccn-sid : red a ecnctant = A 'or eccliown and cero for heatu.n. n.s also a c ons ant = r. v m> t,,..e.c e &s.

IP

• A" + 3 r=m-a 1869 0i7

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,-e-r + _. i ,NOrg-OPERATIONAL u_ zzzr -~ /-SYSTEM-LEAK . -._ L._ _

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zzzl CHNCKzAND HY- ~ ' ~~~

Z... _ _.

DROSTAT1CTEST -~ ^ :: ^^ ~ -^^~

~

' ^ - ' ^2: - -.. ~ LL: _- T.- 2500 ^ ^ - - ~~~~~-' _L:-.. ~:: T~r~:. .. ^ ^ ~ ~ ' ~T <5 . _ _. 11 .. __ _r. : 7: ZNONICRITICA1. w ^ ~ ^ - ^ ^ ~ ^ - ~ l~ ~ ~ ~~ ~ ^ ^- -._ - -~ - -- ~ x ( ~:~~ ~T___... w 1500 k ^. -. :: ... : T... ^zz :z ^--~ : ~~~ . -.. _ z_: ~ ^ :. z

^^

- ~~^~ ~ L- ~ ~r-~:: _ _ _z: : - -~ ^^ - - --___ : -- 1000 ~ ~ ~ ~ ~~ D TEMPERATURE /_r. {n -N 62E ~ -~~~~E .....:::. -. ::. :~ _545 / -9 7 - 7 x-7 ~ o 500 g _'_.".a._.. .: - ~ ~:~_ ::: . _ L : -~ o !1 5 O r'r.. EE 82 4- -BOLTUP T MPER$TURE:

j

. rr. _ O O 10 0 200 300 400 500 INDICATED REACTOR COOLANT INLET TEMR TC 1869 018 FORT CALHOUN REACTOR COOLANT SYSTEM PRESSURE-FIGURE TECHNICAL TEf/.PER ATURE LIMITATIONS HEATUP SP ECIFIC ATICNS 4.3 TO 5.2 EFPY OPER.- REACTOR NOT CRIT. 2-IA

I ~. f -~ N_OtEOPERATRjG CZ~i Z: SYSTEM-t-EAK- _ __._]TCHfCKZAND-Y- ~-{}::]- T 7- ~ TDROSTATIC T ST ~. - ~ ~ _ _. 2500 .lbb 55}._db ~ .{-_ gOOtDOWN-RATE U- - i rT . MAXIMUM DE- -...__x j - . - _.. _ _ _ -. -.. ~. - / ONE~740UR PERIOD 1500 W _ j_ 5 ' l_ _ i - ;_ ~ ~j- - 2 f/f} _[ a-LOWEST _~. SERVICE- - Ez J- _Jz L' N TE MPE R A..TORE. -- ~ ~ Y,. - ~~ ~ ~ g g - \\- ; __162-g /~~.20 /. -o /_- : /_100.-... D ~~__; o w / E 545 i_~Z. ' :.? l 9-i--- o 500 - r_ f, F- .___.. _ z.. _. ~ ~ - J_ _ 4 y zi.. -- -j ._zc 1: 1xz ::i-

x: 2_._.

S l- ~82 -BOliTUPF TEMPERAiTURE ~' 4 g O 10 0 200 300 400 500 It DICATED REACTOR COOLANT INLET TEMP TC 1869 019 FORT CALHOUN REACTOR COOLANT SYSTEM PRESSURE-FIGURE TECHNICAL TEMPERAT'JRE LIMITATIONS COOLDOWN SPECIFICATIONS 4.3 TO 5.2 EFPY OPER.- REACTOR NOT CRIT. 2-IB

p. J 4 7 ~~ ~. _-. 3000 ,7 ~~ ~ ~ ~ ~~~ ~ ~ ~~ ~~ T 2500 ^~ :: :

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az O 10 0 200 300 363 400 500 INDICATED REACTOR COOLANT INLET TEMP. T 1869 h23 FORT CALHOUN REACTOR COOLANT SYSTEM PRESSURE"' F GURC TECHNICAL TEMPER ATURE LIMITATIONS HEATUP SPECIFICATIONS 4.3 TO 5.2 EFPY OPER.- REACTOR CRITICAL 2-2A

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^:._. ~;:T_ : ~ ~[ }.-.. _.. : .. ~ _ ~ ~ ^. ~ ~ :~ ~ - -.. ~ ' ~-~~ ~ '^-~~ -- ' ~ ~ ~:2.. _ _. ~ ~~- ~ - }~~^~ . T:_ .. ~.} ^ ^ ~ _[_ 500 _==T =_ z ' L. --^ :: ~ z ::-- - - - ~ ~ - - ~ ~ ~ ~ ~ .T.~ 4 G5 ~ ~'- ~.:. . _ : -- ~ ~~ ^ ^ ~~--~^~ j o-2000 w g D ~ ~ ~ _M_T Zi_1 ~_Z. - ~ ~ _Z______T m m 1500 g x L : ^:~ - -- - ~ - ^ .. -- ~; z. ~ ^ ^ ~ ~. ~. a. g x ~ Z~~~ ZZ..Z. .. - ~ . _.. ~ --'~ T D m m i. . 1__1 _ _ - - ^ ~- r o_ o-500 ~ o ~' m_.. q g.2._ 3-g w Q !1 g 2 g ..n..., p ._. 7 _ g 6 . _..L_ _A {. _. _ p 4. z O "~H'- ~- O 10 0 200 300 363400 500 INDICATED REACTOR COOLANT INLET TEM P. T F c 1869 021 FORT CALHOUN REACTOR COOLANT SYSTEM PRESSURE - FIGURE TECHNICAL TEMPERATURE LIMITATIONS COOLDOWN 2-28 SPECIFICATIONS 4.3 TO 5.2 EFPY OPER.-REACTOR CRITICAL

500 4 I I l 400 l l l i l l l l l l 300 I l i l /l / l P -i l

1. jY m

Ea 200 l l 9 5' VESSEL ID l i s I I I i n o l 1/4t l t s E2 100 / f9 90 X i i l g I s 80 /I i j i I I d / 70 l l l l l l l l a t; 60 l l l l l i s I oa 1 i, 30 1 ~ ig 10 s 10 o 4 6 8 10 ' 2 4 6 FLUEiCE, n/cn >1 ;:EV THE FREDICTED ' DTT SHIFT OF THE QUARTER THIOK:!E3 CU3'/E ( t) IS USED TO DEIBML,s 1.u CORRE3F0::DI!G TEMPERATURE SHIFT OF FIGURES 2-1 A, 2-13, 2-2A, AliD 2-23. 1869 022 PCRT CALHOU:l FREDICTE3 ;;D T S 7 ?T ~'"^7  : -' a 2 A '"' '*'o FIGURE 'I ^ " "'~ ~ "3,_,,1 ; E3 rn e,v gm, g,g:.,y c,_1 2-3 1m.~... T,n' L "'"; a~ ~w 2' 2, u., ;, .n ,c n n., T e.r.e. T C.,- .n..

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"... e m" *., "'_"u- 'oCr..i n s 'v."u - c+ c m m m .m r ..L i. Cs v. Lw.. w .r. .". n. u t, ' v. N. 4 + 4, n.1_ u"n e,p u..acr. n - y A n.,, .r i -, w e s. n w n% a ,1r-v.-- m-vu vv-.mvaa q u. 1C 'a' "y v^ 'a.' y" k. c"c.#C o" ' t' c '. A u" s, . # ~ 'm L -M b ".. "m # o. L' " 1' 'v 1' "- " 1 e "~. ' C." "..'c~ -u m vna.. a ,+ . - m u u, g - + c - n n_ v,. S. w g n a y t u o m. w w - 4 : t. 00." l'.e 'u - n.w s c,, w g.. u,., ,m -um. 3.v. u ,ap u.w. A. cnu_Ac.- u,, w._f.c. + n.e.~+ 4,,, .?.v y e.,,. A 4.. v.en.4 wee + y a., r 7 o _-m m 3 ..c .u ..m u a s, m ...v r, _ +vo nC +e..enen+uwe,cp_ 1r n_ w g.n e g,.i n,-. n ~ n.. +,... g,r. m _, Our-, be_ m~ a. n n, .u- ..vu .y--uv a _ g h e n._ +v,a.n m.r. a c - l a n-cu..ce

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k..~m

', M_.~ 4. +.. a s 4 ' t "e -." _a * "." e, ' o S. c r,. e _"_# " e m - e --. u .c . + nt, ; o,; ,. c.z w yota ..r %.v.c e :c +ve m<ny~ 9-c o 'i r c^ 5 0 0 e .n v u _L u ~vA vm ns,a a, cesirr.cressure. m - 1 References (1) FS,B, Secticn U.2.2 (c') c .m av..r u n i..,.o..w -a n.w g s.,l.,,. O u v v 0 e, c e., coa, - ,4-n .m mem.t., T.T T w ~m . _ a. (.?.,') rca; . con 1Cr 4' o o . -z a, - s a .-.~ B69 Ood (s).=, c.n, .c _ .,..e.s [~) L'%... a i.. <c \\), O. v._?C - v ^ L3 v '.".v-+v.w l" u., r. Lun. s

c. 4,.

4 c v. v 1 .3.,,. 4. ,,v L.._. ..cv,., ^ a v. m ."..qu~..a,4 - Lw. 3. ,. 4. ee.,- , O r,, _, ' { f 7 e a s. .....-.a. ~.+v nm. ~ ^ c.

e e a..u....a 7,e-m-- L.g 3 v.,..s. u- ..1.' . L L L - < ",. C;C:: < _ n ; in u.;, ; ~__ c - v \\ n" 1 rate 'C~2+#-....- ..r.estup and Ceciden e , c c...n zb Li.2L. ' 1869 024 u t. w,-, -. 4 u....

a.v . ~..., u u

m.,

.,. c a 2.1 .u Fonctcr Cc:lant c :~.. 2.1.6 Pressariner 9.cten (Ccntinued) und Jteer. E,vstem Safe sv Valv To determine the maximus ste1m fi (Continued) en relievinc Cencervattve values far all syc.vster ascu cv, u valves. tines and ccre scderator e steam c stems parame.vstem safet.y sure protecticn 12 , coefficiente are assumed. ters, delay flev prescare drcps and elevatic.yctem which a Overprer-er ecolant prescure ecnsidering..rumn head cn heads. If nc residual heat the incunt were recavea by lift pressure would te lecc thacf ctean wnich could be gen ,21ve. at cafet) valve This crecificaticn, therefore, provides adequatn ha_ fence against overpreucurizati Perfortance cn vnen the reacter in cuberiti e de-valves requires rencval frer thof certair calib cal. en cafet3 a cafet., enance procedurec cafety '.alve er halntenance ofvalve be rencved, eithe" cp t.y Shculd atmosphere will assure that cuffi i cne nozzle open to at least of the other able. entry of foreign material into thUce of plastic cr oth ar r.ateriel to prevent the ccnst aed te violate the "cpen t e cren nozzle will not be the precence of this caterial o atsccphere" provicicn, cince the discharce cf reacter vculd not ecclant. cignificantly restrict The total re'ief capscity of th is 6.5h x 10 b e ten ctern s.yster lb/hr. At the tuted power cf lh20 !G?tsafet.v valves capacity of only L.7 x 100 and eicht valves provide relie ipressurination of th , a relief r cn locs-of-load ecnditicns ver-lb/hrm \\3) v ng capability of h.976 x 106 The power-cperated relief valv to provide cufficient margi e low n, when used in ecnjunction withcetro Technical Specification Sectic the design basis prescure t f ns 2.1.1 and 2.3, to prevent pressurinatien incident Limitaticn of this requirementransie scheduled cooldcun ensur. dictate rapid cocidown of the es that, shcula energency cenditions to cperability of the low temperatreactor coolant cynten, in-systen would not prove to be an iure overpressure protection nhibiting factor. Removal of the reactor vessel h sien volume to linit any of th ead provices sufficient expan-Thus, no additional relief capacitye design basis preccure transie t . is required. n s.

• Pne erences (1)

Article 9 of the 1968 AC33 Boil Code, Secticn III er and Pressure Vessel ( u )'.r-n. o ~ e (} hmc((] s, 2w. .s. ;a ( 3 l' Y3.2 3 JectiCr' 1 3 iC.e n lSe n t $. 3. '., '.3 9.5 30 .o c .O-

c.0 a 3_ T, n w r.m v s r.a,a r, ~ ~ ~_m, T. r,' m' c pp r r _,x..r ~ ~ " ' wr u._ w. m. .a. m ,m. ,,,-,s..v_4.. a_3 o 2 _r...,,-.. y L, cs., u, v u~.. - - v _m.. m. (_. t

m. -

z (3) Protection acainst Iscw Terperature Overpressurinaticn The fellowin.? limiting ecnditions shall be applied during scheduled heatups and cocidcwns. Di abling cf the 4FSI p= ps need nct be required 11 the reactor vessel head, a pressuriner safet.y valve > er a FCR'S is removed. Whenever the reactor coclant syster cold ler. tenterature is belcw 320cF, at least one (1) "FSI pr.p shall be isablei. ..aenever the reacter coclant afster ccid leg temperature -m.,' v., a s c-(cj ,.-.. :, ~' r,

o.,:

_e -. ...mwwm ,c. .e.> ce_va __c ce ~ disable:. Whenever the reactor ecclant syster eclc leg temperr.ture f is below 276CF, all three (3).[FSI pr.ps shall be dis-abled. In the event that no charging pm ps are operable, a single HFSI runn tav. be made operable and utilized for boric acid in5ectie to the ecre. v Easic The ncrnal procedure for st'arting the reactor is to first heat the reacter coolant to near operatinc terperature by running the reacter ecolant pumps. The reactor is then nade critical by withdravirr CFl's and diluting boren in the reactor coolant. With this scle of start-up, the energs stored in the reactor ecclant during the a"2. rotch to criticality is substantially c equal to that during power operation and therefore all engineered safety features and auxiliary cooling systens are required to be fully c'erable. During 1cw "cwer physics tests at lcw r r temperatures, there is a negligible u.ncunt of stored energy in the reacter coclant; therefore, an accident ecmparable in severity to the design basis accident is not possible and the engineered safeguards systens are not lequired. The GIRW tank contains a minimum of 263,000 gallons of usable water containing at least 1700 pps boren.(1) This is suffi-cient boron cencentration to provide a shutdown margin of 5';, including allcwances for uncertainties, with all control rods withdrawn and a new core at a temperc.ture of 600p,(2) The limits fcr the safety injection tank pressure and volume assure the required arount of water injection during an acci-dent and are based on values used for the accident analyses. The minimum 116.2 inch level correspcnds to a volume of 825 r 3 and the,maximun 128.1 inch level correspends to a volume of 895.5 ft2 Prio: to the time the 1eactc is o r c y-'.t critieni, the valving cf the 7afe:- 1rfection ""m'e.~

st te enecked for correct c1 4 -,.

a,-+-av 4 .,,mv. t 1, < s,;, ks + b.. D, Le A a.{ -w c vm Uc., we +twg.. - 4.., m c=t ';, 'e,' '. 3 4%.=4,., V .e 6 w c r m 1869 026

s -v.7.1 ty m_p, Ci..; .t.m p--p.. n- , p er m.- ...n 9 0 m. 2.3 P.ergency Core Ccolirc Syster (Ccntinued) used fcr shut down ecoling, the valsing will be changed and rust be prcr.erly alir_ned ">rior to start-up of the reacter. The operable status of the varicus rystems and ccrpcnents is to be denenstrated by periodic tests. A large fraction of these tests will be perforced while the reactor is cperating in the power range. If a ccmr.cnent is found to be increrable, it will be nossible 2 in nest cases to effect repairs and restcre the system to full cperability within a relatively short time. For a single cct-ponent to be incperable dces not negate the abilit;.- cf the systen to perform its function, but it reduces the redundancy provided in the reacter design and thereby limits the ability to tolerate additicnal equipment failures. To provide maxi-cu~ assurance that the redr. dant ecmpcnent(s) will operate if required to do so, the redundant ec ponent(s) is to be tested prior to iritiating repair of the inoperable ccmpcnent. If it develops that the inoperable ccrponent is not repaired within the specified allowable time priod, or a seccnd ecm-pcnent in the same cr related systen is found to be inoperable, the reactor will initiall.y be rut in the het shutdown ecndi-tien to trcvide fcr reducticn of ecolinc rec.uirerents after a postulated less-of-coolant accident. This will also permit improved access for repairs in scre cases. After a limited time in hot shutdcwn, if the malfuncticn(s) is not corrected, the reactor will be placed in the cold shutdown ecnditicn utilising nornal shutdcwn and ecoldown erocedures. If the cold shutdown ecndition, release of fissicn products or da. age of the fuel eierents is not considered possible. The plant cperating prccedures will require ic~.ediate action to effect repairs cf an inoperable ccrpenent and therefore in most cases re.nairs will te ec=r.leted in less than the specified allowable repair ti.es. The limiting times to re-pair are intended to assure that cperability of the component will be restored promptly and yet allow sufficient time to effect repairs using safe and prepar precedures. The requirement for core ecoling in case of postulated loss-of-ccolant accident while in the hot shutdown ecndition is significantly reduced below the requirements for a postulated less-of-coolant accident during power operation. Puttinr; the reactor in the hot shutdown cendition reduces the consequences of a loss-of-coolant accident and also allows nere free access to some of the engineered safeguards components in crder to effect repairs. Failure to complete repairs within LS hours of going to the hot shutdown ecnditicn is considered indicative of a require-ment for majcr maintenance and, therefore, in such a case, the reactor is to be put into the ecic shatdcr conditicn. .S..e.'....'"~ .O.', 70, 0-2 m 1869 027

6 1 0 u _ m... ~..

7. s,. t. r <.. _ m.,

n n. .m -.0 . 1,. r... n.,;

w,. n_., c.. ^ _,. o_

t v 2,.,4._ c,. e., n_,- t C m~.. _'.. m A ) m.. ._.t ..y t. -c ._ 1 '.'ith respect to the core cooling function, there is functional I redundancy over test of the range of break sizes. 3 . ' -.^ " ' b.e b.e e n.. .u..m .r c m.4,,m_,, e.4 e c m, L.4 aacm+e ^ ~.e com'i"..u ^. o -.. -. o .o m r . u..e -_ i ,1.

a. -"m>e l e -e. ~d e d bee

• e.. -.

u ,ap., .a.a L., _,,m, a 4,, _ ,. m e,_, +v,,. t.. 3 oy assuming the safet-in iect i cn cr.pabilit.i-which cost adversel.v 0 affects accident consequences and are defined as follows. The entire contents of all fcur safety infection tanks are ascused e..e ce". ~g e " " e ^ ~.'. ' ". m, k"+., + k. ~o c e.". +v e ". '.c u - 1, k' a 4 'vc M-o tv. .m m. ~ of cne of the tanks is ass = ed te te lest throu g'r the reactor ecclant cycter. In additien, of the three high-pressure safety e.. ".l e ^ '- 4 c.n. 44 n,a .ne...-,e.. .recc.. n -.o "e " ~.. e -, "c

2. y e,,.. 3.

o, .e u.. .y ~ m w v - m4 4.. i.e _n e m...n a. .b..at +w"~ o k i c-h. .c. _,, ac..m.. -,. c- --:-_c "v " e "~c "a " e u and cne 1cv pressure cperate while cniv cne of each tyne is accrea to cperate in the c:all treak an11ysis(5), and also that 257 cf their ec: tined uiccharge rate ic lcat frcr the

n...e. 'v "m". c i e n +. h n'.

.re v~ - c~.'c-e -. e.. tv - c" 4.e '" "_... +- o m .a. spct fuel clat terperatures fcr the break sizes considered are chewn cn FSAR Figures 1-9 (Arend ent :,'o. 3b). Inadvertent actuaticn of three (3) EPSI pumps and three (3) charging pumps, coincident with the crening of cne cf the two FCEV's, would result in a peak prirary system pressure of 1190 psia. 1190 reic ^crreepends with a minimum per-issible + e... e., -,,. e o. ~.. , -. e, u-. t.,. c e,. c. c,.e. w. a o. u o ,a ew

1.. a -

e _. c. gm, pr.p is cicabled at 3200F Inadvertent actuation of two (2) HFSI pumps and three (3) charrinr r.umrs, coincident with the o.reninO~ of cne of the m two FORV's, would result in a peak prirary syster pressure of ICLO psia. 10LO psia ecrresp nds with a nininun permissible terperature of 310CF cn Figare 2-13. Thui, at least two HFSI p=ps vil_. te disabled at 3100F. Inadvertent actuaticn of cne (1) 1FSI and three (3) charging p=p s, coincident with cpening of e.e of the two POEV's, would result in a peak primary cyster pressure of 6ES psia. 685 psia corresponds with a mininun allowable terperature of 276CF cn Figure 2-13. Thus, all three HFSI pu.ps will be disabled at 2 # 6cv.. Inadvertent actuation of th"ee ( 3) charging p=ps, coincident with cpening of cne of the two PORV'c, would result in a peak primary systen prescure of 160 psia. It'0 psia correspcnds with a nini2:un allowable temperature of 760F (approxi~ately the boltup tez.perature cf 820F) cn Figure 2-13. Thus, dis-abling of the charging p=ps is not required. Removal of the reactor vescel head, cne preccuriner safety valve, or cne FCE'; prendes cufficient expansion vel =e to

m. w,,

am e.4 -.. w, _4e. r n .c,, m + ,._4.e _ L.. 4 t cm ro .w m.o .m o g -o m.- .-..o ..o. c ~_o m no additicnal relief capc. city is re quired. .. n. r .. n,... ,a, n;, ,s m. 1869 028

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