ML20070N797
| ML20070N797 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/28/1994 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20070N795 | List: |
| References | |
| NUDOCS 9405090215 | |
| Download: ML20070N797 (13) | |
Text
- - - - . . . - . . - - - _ .. -- - - - - - -
l Pressurizer Power-0peraud Relief Valves (PORV) and PORV Block Valves 5.
eg- - we - we .
wa v+w.mw
&* quxequeenkx we$4pmeace sx_ a.m sun w ~ - _
-:ewewIww cued i noi6mm;p m om.e - . eShsee ~>o 0~TD0_l'Oghemaa.mede um -+>um con.mm _
iotcosyww:ionw w-ws-m niaccor.d_em.ampm.xwiw etw a,nc,mmememt m
n +u w E TfNaist I.^ni.+W.a; mss. ,e4.w.wv u.w.wv.i?3.v.E*.uw.ji.w.
swA+
S iE w 6wx+fH.w.o~u ' v.ew.+ Ri w wg TtE~w.vuw. hf.)&v.su.rWiya"hw.s(.
stWn,v.vuwwl. i' w 63 3Firf.S.FA.w 3 Rite ,1.+w.vmMu.b.E.w,y x
xc reac oracoo antasysen empera wwwwetsww.wemm**l.*mev.p :.r,mmmmdy ewwwueuet+ur+vepw mmolwd bNovemeceiuut. vwi*ne<wd3prewwwtwax^yythvv4
_ - s._-
^@@S w
_ . m
..y..r..n...;
_m _ u-_u_ ushou . 6am_a n ~a._w r
_ _ m mm sgxe_a..-mers _anm Y@C '
'A #h'M%1MN%i'tunt
, s. _ . _
elmpre ni"'m(.r..wy
-.mm uriza s sMW"W%%WOMt%.Oi's%4w.f.hWws%*O)%'.w/M%
_ me - _ m.>. _ w_.. m m-.m
'M4%
m A ."** ;
hY'M$lSYNjswWM.MINiMM
$$t#%ei y-me.mm wt# #f0onatempera nserv u, ce?P_re'd.Mlf.'W%f.4'#p/M%lt4tlN.W.Vti
. _ . u M4C0 d ., _*o]m_WMMFM"_'eMM^M J -W gf*:Mw wwwd.m W.fJ n.Wwdpi.wogas w - _
guw.me.
s re I._e._., e .a n,,g.mmmmmu-_0._l:+' ziwNOWSwid_^$yM' dVes$,_3
._ .>_&%M n.mi - M
._ x awgeyn m
.t.wwm.wrawefwa.cmdeugswam<.wwww*ded
,,e,m_p,e,r,a,u,,,re,,T,,,s,t,requ,i.,r,e, ,,,,,, niorde-onu
_ * ,O,,,n .. . . e,s,ac, o,,n?g,oi,,r,e,_s a.,k,mm.w3w.gt,,i,we*mwmewrwsw'tw_o,r,e,wwham t . nt,,e 3 no_.p,e, r_a6m1.w,.w
.wm ,,,-.wu erc.o w onen_w m3.p.ws sbt,ou_serylc_e_wt._henith_ezreq._i_
- .w:.,.___t wm.wu .l;mwa.wgw&xw.4;wx3 w.w.w u.wy,
,m...W;+..w3.;#wuu. .
rem _ent_svo -
- w. .w,sw v.w.,a+ ; + ,
5~'
_..e_c _ _cifi ._m-._..__ifiWf15NFi$fs517! I
- a. -Two PORys and their associated block valves shall be operable, j
/1.,\
g f. t. .
D A.D
. n U. 4..e. 4. m. r . a. n a m..%.h._ l. a Ana 6.a . . l. a .% nb s n y.a, i, n,
, noe
-n_. n e. .e. .a f-that
+k i r . S 1. . .n ,
- 11. mum,A .n- 4,o- .eyn a , 4. t. t. e 6 4. .. m .. n. .nm n..nonu. . k.. .% 1 1 .m km u,n mee e. .n u.nA - e. n. %n m anam.%
.y ... k l. a e n... n. .A 4 6 4. n..n. ...m..n, ulek4 n.o.n a km.a u. m. n. u. &,, k,an
,,a,.4.
.... 4...a A k. l..na, b o. 1. a., m .o k. . 1 1 km
. .e l. .a ., a .A .
M M ^YM MW y;< w%ve W.My/.Mo (1) (}'* h4'o&+wS'<pMAw%4pP A
NAYth-dg4N$:mvneg mm mm- o_t.am.0.4c.mamm.~u*-u-mm.0W"
_. .m a m. .
d a_S.emm2+n.y "'s@ tare ~ NO'
3Iid,d.isf.6f..%.<
+ wu. w6 m Etf ,i,WI,.N.w.,.w w NIDI if5 f6di d m wumuu.vm@L w.1v.lv.N.,.,.w.msswm.ssw.d.w.m.w$.M.2,..w v 5. 3Y8 w L tM u iwawwm,.7)EN ww amy wwey r
y-w.m;<hswwwmpwi
_Dne.s ~ ~ outge- _ .;.v.>e.nuwrgr wa a.s.,r .hwww thvow.wy=estw
-.a er _ .
- on>,a..nngovple abwlw.va.mlwu.tw.w eR$ a e.nL_a...u..uss.o.
m.- rv ylvermyrIbmger c.osefa es._ a+ ass 0..Clswek.+_ed.
- a. s cP3obw n wenkug***
u .+
Y hmew+me,mewdxl^lmi:mm<w xmww+Ve.s.s' u eselcon S, w r--~~~~~-
ons
-cannop@svx;*u.w.mMA
.m.m.s.,bm
>+..-ax..s u.s
.tw* p.l s_.n l o.m.a a+V8.a-e me .4.w.we.e.e.cn%4huu+
.s symm ac w .h,etuni.t,-imey,r wha.nsj,N.w w a . ,$W.,
s+.s eb -uu.wu.TOO m
W...
wwwswsuv tcon
- + ..di~ w-cv4,.tion .w m
Q.yi.tw,.hw so.m m mma.m
- eEneXfi$
n a t,h.v.ecew3w. w ywl.
_ m k hex.mwg . ourst mm.m<u _ - ,
/0\
m f. t. .a M. A..D,U. 4..r. A,,n, ,r. a, n a m. .a..n ki. A n. n. e.. n.
e..k.. .s a. n. a. l.t. .. o. n. e. +. 4. . .n n. .s.1 e. n .c. +.
4,1, .u m,a, +km = mA e u 4. +. w, k n 'sis k ,1 1, km v ..iw . css e .m w - 4. u 4 w u n. A.DU nu e n w.. n. e. m.n.1 an : ow n 1. y .% ewwu nA 4%+ A
.snAm. m..
. .%. 4. n. +u- .% 4. m.. n A (e.n.k. n.
e,. i...m.
n e n. A n a e. 4 4 4. a..n. .
r.. a. .m..+ L.a.
%ee
. ..ne....n -
M .n ,e..nb o. l. u. mm ., ko .% 1 1 e
- k. .m m . . i.
, .n- n , m A u t +.. k.t... ,,,,a
- k. ..a.u.
. m.
$ u - - - -
.wyv iu
.2 ad. ,f,r.psy.W4gy sm_&_on_er OR,h.yiM.mmd.._N.m0_P.E. s A..B_ _R.. sd. L,E.A.._ueit.u.g.py.w.yypww.33,,.gmthyu,.cf g orca.u_,s_esio m mm ra.t, e hc.wu.sp.w.ymugw,<.,,i..
a m ve s.m u.c4m
- ~ - - .m m ...w nne_xc_e.s_
u 9.mmetm;nl,samekwwwemy,;me.~
ev a a..w Aw;s.#a i A ms+u e+e urr t~hwmsymw.wetrenew,:ptohmsq.-.
v.t>hcawm.weenhwwge,myu.s er s orea e: Rh o e.w.aJWo.e,.w . mytwe w.s..ge.mwi .ua.*
%v.w,.ue:.xw
.n. .;.>,m,y, .gs,p. an ,,9gr.m O P E.R.uaw.w,,..
w/aw:
AB LE.ww.+xm.o+
yy a s,tptsw a u ur.he.sh.< m.s.y,or,ma ose ,.
ecw.s.w,..n sta fm.,y,,,,;.,y,sy.,&.m. ~w ciat wwe.sgd. e .mw e
7 ..l.xu.g,,w
.u..b ocv.w
>.%s
- aaAms es4%a..vu.d n a s o.w wu.,.w.e u
removerp_owers w.:mw.wwewowmwmayf. - _roma - -es oc 1va wcy.wytvhwmh, -
vea --n Nyv ,hwe ' "" anno wekyw/+ltwggHa sMmvvmewebybw
-- .e ;
pwwu ' ww wp wer e w s wwmomq.w.9
~~~
re.wv.to m
s ne.med- nw re.uu:owvu t vpt+o
- eranwwess s opsev;>u sweAwwb,.:l.a.syx+y<wt.wmu+u,wapa*i.,+th9ixm s;ue at s.w%w us n wn rave;wn;w n hours 4 acea heaun amuu ,ns +w..w.0aa J: h T6.,TH0._TI$WTDOW~E.6Fd.it~is.n.,l_thl,~iiy.,t_hi.ag_sIWa,
- wn na, -
Fe ~ Wn.6G._MW- \
4.,., ki. n.,-k , I t o ,s r T
. t. . .D n.n n u..L1.meL ..n o. 1. o.. m 4,um m re no m..s k.1. . m , +.ns k m. . u. .,.1. o. .m k. . .,1 1 km m,+ +,. __+km
-w m,ws. _m.A
.v , , .
o m,
.y-m __
k.i w w . . . .A 4. +. 4. .u. m 4, + on k 4, ., , .m._ i.w k n..m . . m. .. .uw l
I ki. ..n
. neb o. 1. u.. m .e, k, m%.1,1, L. .. , .. .1. ,. m e, m ,A. un t. +. k. . r. n o u. n. m. m.a . . m..m.
. ., u. n
+ka A.t, m,,m,,m,, . . . .
k.l. .a.n , b u. . l. o. m,. .m..n. + k m .,n a 4. , , , + k.. .m o n. 4. +.,
. ,o k,. n.1 1 .. ka 4, , ., ko...
. + A .mu nn n n u4+k4.n n 4kn
- o. n. a
..n v e., elnv k, n, a n m.,.e..
1 9405090215 DR 940428 ADOCK 05000266 PDR <
Vnit 1 - Amendment 93 15.3.1-3 August 11, 1985 !
Unit 2 - Amendment 97 1
.- . . . , , , ---. , v.,-.,. -, , , , , . . , - , ~
a
- e e
(3) IfiSBffilPDRVsfEi?INbPERAB.,,.L.o.E.va+>;dwu.wa+;+t3?;v.w.in,.vuudu,%wu.w
% ,:+.s. wo.w wwww.v,w ,w ;% ,;w,. .u.(~~.- - - - - - - - - E issif6theEH sii iuitosw w+ v,m..h.~y,wu v l w gowwoy< 1 RE E!S $d!A!
yumwww.m1sw l pa aggi; a.>;0mwwwI^:p:.}*wwpwewwo:afg.$>."-[s{.' w{y,q.v.owowwyhwe.we:ww.www.aj.+ { hgggg MHiEIREFMEEinBiEllif6E@!!IDHIEEEEEEHH R11MMI!!@itWOIcIfHlHIEMB]IWfIffE3M HIiEMHisiHaliliMIERIfMi1@ERM!?Ei!IDii E M IE M E E f3 1 [i! B H 1 INfREMMMEEE!MHBhEEitMaiMMMMd Nif5FsM!IBKWi1HIEeM@iEE#E111EfB MEDIfBl@EfEEEEEEEfMEEEifEEMiMisEIRIH MoNMKGMHIEMfEZEEndiTEE!SIEERM6B BRENEmil!!IBINNWi@ilMMieIMis
_,,m,,
,,iM..
W ,I.,sl,,I. .k,igget s.lsd.m., ogn _,, f.
IDEi! GEM #1EB11HBEIE6HHMMEf?HMEE1HH
$$1I N $$N1 $ $ $ $ $ d I5! N SE N !N1 N S M iN[ N 5k1 N N E IIEiliti!IEEIEEEEEIE!HlHIBIMEZKilisilEE
- 1EER13NMMEifiHEMNItE!BHEED1 MENiMMiiIEEEEEEEiHEi1RBEELEii@l MiMHillMIMfFi!EEEGIEEEEIll
- 6. The pressurizer shall be operable with at least 100 KW of pressurizer heaters available and a water level greater than 10% and less than 95%
during steady-state power operation. At least one bank of pressurizer heaters shall be supplied by an emergency bus power supply.
- 7. Reactor Coolant Gas Vent System These Specifications are not applicable during ald or refueling shut-down conditions:
- a. At least one Reactor Coolant Gas Vent System vent path to the pressurizer relief tank (PRT) or containment atmosphere shall be operable from each of the following locations:
(1) Reactor vessel head (2) Pressurizer Each vent path from these locations to the common header includes two closed valves in parallel powered from emergency buses. The common header vents to the PRT and the containment atmosphere each contain a closed valve powered from an emergency bus which provides series isolation.
Unit 1 - A1endment No.
Unit
- inendment No. 15.3.1-3a 1993
. -_ . . ~ . -
E
' provides conservative conditions should operability problems develop in the other RHR loop. Also, one residual heat removal loop may be temporarily out of service due to surveillance testing, calibration, or inspection requirements. The surveillance procedures follow administrative controls which allow for timely restoration of the residual heat removal loop to service if required.
Each of the pressurizer safety valves is designed to relieve 288,000 lbs per hour of saturated steam at setpoint. If no residual heat is removed by any of
- ? e means available, the amount of steam which could be generated at safety e alve reitef pressure would be less than half the valves' capacity. One valve, therefore, provide adequate defense against overpressurization. Below 350*F and 400 psig in the Reactor Coolant System, the residual heat removal system can remove decay heat and thereby control system temperature and pressure.
A PORY 1 defir,cd :: OPERABLE if leakage p;;t the valve 1 le:: than that allowed in Specificatica 15.3.1.0 and the PORY h:: met its most recent channe test :: Specified in Table 15.1.1 1. The PORV: Operate tc relieve, in con-trclled manner, reactor coc1:nt sy; tem prc::ure increase; belcw the Octting-of the-preswrizer cafety valves. The:c PORY: have remctcly cperated Meek valvc: to prcvide pccitive shutoff capability cheuld PORY becc=c incperabic.
K..I_PO._RH._is.*d...i(G.
. ... - .idIis7_0_PE_RA..B. _LE_?_ff 5_1.s..ik. i.ps..@, .
m _iiti..th._ sWiW._i_Hiil.w..si_ithi.n.it....
i -
hit.
NO *W a '
N + .
/ WJ W.Wa%% .? MA S .8/ gW/N#i%% .' v.g
? .N%A.
a1'1 N..q 0we+p'#
d .d,."n.'
~ .._s.. 'S. p.Wrii .',.i- c aYt. f.w.#'*?e
- g 'o.W.*$".Wd.1i c.
5.y 3'. ".1". D.n. 4a . n'4'. de/d"' h_'.W. o. /f m
- -.- - - ; m.
. , s't g_r e c las e n." s. tc,.l/(.%'.W/
o,,.c_ _%9WA%%yi,%s.
.av =ta vt"s*A*d/ -
-.;.%s. "hve isli..s. hsc.ff.i. id~lih1.Tabl.is,1.,,5,?4.,f121M..,
,=,.,,,-.p--
. - - 4y;pw g waAyy -. +
W. .y.,w.wa.sp ,ys.s . ,y . -
i._lliE_di. pfsbl ,sM__A.dd
--.sy~y,,.p.y -
l t
.gv.;.we.y v I.H., _6_hil;.x yN.n hi..!.
h-. a. .4.fV. .e- -k.~-t b..ygu.y.w w,y.v.bxe t.C a. pa i,l..'.l,Ie.:y,f,. o, .f..~s ope r.s.,el..!a ,ngTma..nual. rE n.~toi.,rel.l. eVeW.. .q wp..e.. acI..n.sy.e J'.
~~,$s Y O - y =
. v-. n .. .
.o..~.,.C.. s wt-o.a ol.w.,n...bsp. v.'a.v~ XS .. em.
. .m . .. . _ . . _ _ . _ . . _
p N,.p .h: d , . > - r., --
.&- f ...g,7 %y-- ..
y Af b>lf.q k.o c. s~v.~a.l ve
.~an .s. fl.fs;lld syn.), t ~ .W,f,e'y ne qd,f i+ Qp,M.d;,
- w. . r a.. sn MQ .'.%ng-y0
' E61 ' f
~~ a.n.
ith...'Q.ppgy,Q%
P.. .Ee..~a R. .A.. v~ aB"l,,v..pf,..,ys,.,jpppyy,y,./;w ei, L_.c a. n._ro p.e_r ~e._tma,n,
.y ::,,f.'.c..qqy a t,Q.y;;a u a. yya.n l,~l. 4 .ds ;~n,f.
,.,.b,,,.,..p.,d. ,
.iGi. an,c~i.id.h.tf6l.+K..did..i.i.fli.._d.T._IP6_RWii..k.k.gi_i
- . ~. a ~.n .
...n- :
WNshia.
~ - i.,P_o.~ RVN. sM.. %..N. d.PE. R.._AB._L._Eidss5ts.i.
v m x .
~ --
si...b..i,_silVeis._ m m sit,._Us..s..
ki.psN_tE._i; 610. E.k._3Vi..1Vs.~il.s
~ - _
s..h...ut.is_i,._th_5.6..W._i~F.iiris. ih.
- ~ .
_tithi_d?Wthsibl6EE.
~ m T t mV_iTVswmsE._t_ m i .
hat,im "i_%_1B
. .e ey.wy.a,. wy.:s.pw - .- v
. r .- w.ge.y w c.
.r.e. - lynadsi a v.. a...i. .
l.~a~bl.,
- . ~ - . - ~ . e..syuutyand:imay!b.yq.mu.
.n-.. .ywdsd.ee s n - n- ..
u s e .
o . o..,s.a.
,;c.~on.Iv.w.3hs ro ~l l r o.w.~,.wt; t ym.3y- a
.hm.3.f.r,,,,
-~n,e_ac. oo..
P.ORV.7d.
r wy.
.,. .ne. ..yu.
.;.w. . y.v.:c. .wnmyy.% y, v - yy - w p re ss.u - -
re m.~Eg.7,4.,.p.:xcess
.~. ~. i v. ~ye..s~pr yp.s:.p r.i.m.a. ry,,ssys.
ra.:u.~mwnt.yn wnd,.e, e.m_e.
~ ages.- -
ak.y<ove%yyi+s.t
.w. ne ~~ d_nespeci----_ot i..:.v.,~n, d.s> f,. i.w.a.ynd. .y: mwpunp.
- 1. 5_7.3M. I. D._M.TN.F,;f 6.1sEEW1.1,Viisil. y?_fsMiin.ish6.R_Wffs'6T.itiIt..hs71si,
- i .- -~ - ~- W ~ . .n - ~ -
k,fRi?. PORV.,f. fbifi
- - ~
Unit 1 - Amendment No.
Unit 2 - Amendment No. 15.3.1-3d 1993
. 1 i .
l
' 051[EdI5!51EdIII50NINE$IE3NEEd35Nk[N55$NfMOh5$MS6E$2$$MENIAEN@
7 ihih"I.REiiWisissiE.lsikisWinsT BL.Eifsiffs.is5hi 3
3~y M.3 ;~
INOP.E.~RA.y[h}powedemove;lithsR.3 3 - fillh i s gpredide sland6Myed(5_jgpp n {3.hlIE 3 7 jgsh@{j;[ ngio(ijQe HEIK311i@
- %jh]Q{p?)jylly(3((INO$RAB@@hi$ilMj@@E$R13}ipHMM]3][@ipsil EEMfilil5MEIEM MM M AM E E@3453ERIEI5E$E@ii G IINFRM
! The requirement that 100 KW of pressurizer heaters and their associated 4
controls be capable of being supplied electrical power from an emergency bus
) provides assurance that these heaters can be energized during a loss of i offsite power condition to maintain pressure control and natural circulation 1
- at hot shutdown.
4
. The requirement to have a reactor coolant system gas vent operable from the 4
reactor vessel or the pressurizer steam space assures that non-condensible j gases can be released from the Reactor Coolant System if necessary. The j Reactor Coolant Gas Vent System (RCGVS) provides an orificed vent path from i the pressurizer steam space and an orificed vent path from the reactor vessel.
i Both vent paths include two parallel solenoid-operated isolation valves which
- are powered from emergency buses and vent to a common header. From the common header, gases may be vented via separate lines, each with a single solenoid l operated isolation valve powered from the emergency bus to the pressurizer j relief tank or containment atmosphere. The orifice in these vent lines
{ restricts leakage so that, in the event of a pipe break or isolation valve failure, makeup water for the leakage can be provided by a single coolant charging pump. If a RCGVS vent path from either the pressurizer or reactor
+
vessel head is inoperable, Specification 15.3.1.A.7.c requires the remotely 4
operable valves in that inoperable path to be shut with power removed. If a
~
vent path from the common header to the pressurizer relief tank or containment ,
atmosphere is inoperable, the isolation valve in that path must be shut but I j
reactor operations may continue. If both vent paths to or both vent paths from the common header are inoperable, the RCGVS is inoperable and the steps in specification 15.3.1. A.7.d must be taken.
1 W FSAR Section 14.1.11. l
- FSAR Section 7.2.3.
Unit 1 - Amendment No.
- Unit 2 - Amendment No. 15.3.1-3e 1993
15.3.15 OVERPRESSURE MITIGATING SYSTEM OPERATIONS 1
epolicability Applies to operability of the overpressure mitigating system when the reactor j 1
coolant system temperature is less than the minimum temperature for the inservice pressure test.
Ob.iective To specify functional requirements and limiting conditions for operation on the use of the pressurizer power operated relief valves when used as part of the overpressure mitigating system and to specify further limiting conditions for operation when the reactor coolant system is operated without a pressure absorbing volume in the pressurizer.
Soecification A. System Operability
- 1. Except as specified in 15.3.15.A.2 below, the overpressurization mitigating system shall be operable whenever the reactor coolant system is not open to the atmosphere and the temperature is less than the minimum pressurization temperature for the inservice pressure test, as specified in Figure 15.3.1-1. Operability requirements are:
- a. Both pressurizer power operated relief valves operable at a setpoint of <;425 psig.
- b. The upstream i clation v:lyc: to both pcwcr epcrated relief valvc; arc open.
- 2. The requirements of 15.3.15. A.1 may be modified tc allcw one of- the twc power Operated relief valve to be inopeeabic for a pef 4ed-ef nct marc than seven-dayh
- 3. If the incperable power opcrted relief valyc; connat be made operable within seven days, the reacter ccclent-system must be deprc::urized and vented to the pre :urizer relief tank within cight hours.
- b. Bbih f,powegjopera t_edgell. g~,v_a]y_el, e b. loch _yal_ves_2arejopenX
- 2.j((ffdjH@hVji6ssQD 5IA!}[@yl%IMd@@d])H)i@lf(.idl@[6E[ !
i Unit 1 - Amendment No. 125 Unit 2 - Amendment No. 129 15.3.15-1 January 10, 1990
W s l .iWV_lW6_hi_?POR_WiiiBJ_sf^i_blM.M_Ti._?H_IE_tBE_E_66l_i_d.it~i.y_sti._iii u _ m 4
.....g 4 - . .-
emmw ex.y . f/.+.em,.p.v.e.wa a.mmmtvm eo + ra uy .m.s.~r w.7.i,,.pF. w e,a:$.,.v.s wNx 200 mma. ( , s u.ys.m
,b.,.,tp m
# ~.ag me-t,h L .+L.yvo -y e s w vawv s.w<~.v.+a.v.+r mum.4pum+.%,
<w--w
.w.hs~,,n&t a,e on
.w.ouw.z.< n n.,w.iwum..w%
am w.r ressurimuss,,t< j m
+tSwe^wwwet%geme+dw mo u.+.es'+m.
s wa* u era.a.w.v.re.,an,u ws or vseqwt"n+edns
%w ns rv ceinress x*+nm+.w.*ya.ur
..wwwas+a.e.#amw%% swgewwnm.:pimecogwaxwaeNagm.n%
sw%-.
+e erarestorer e e . g:gymgi^thw^ws:.gma.m.wu^wagrthwm vs.v.-s). Swau.m%wo uuwww exsn # w
-sw.:
,- 3_, wxmwy*m.b_..l n.o.pera. e& __m- otopera e.is_ tat_mm_w_m PO_RM7.~.w3y.u.%3w.3mb_.lwwwr m mmmeveaw,lth_wiAdw.v .a.y.s:i. gor; .wjw .%waux*7x.ws yA Ms Nwws #MYN 4Y- 0%QDW.Mwv ' v
+dgp're'NWWWY@'ssut venw .uevea.e.+,.:.,+vw.9.'+A.
reg.andv' eN+Mevte actog6.w%' A r:MwwNFNN^4WpW4*0v-coo ( +%NtOV6?MW:4 s em a .E04 #.43 M:M. w&A. ks(46 % -%/ - y.4eMXhemsw 6 /v1 ef&n.M.MO ext.4 i ours ssx hNo.Mg:*.p. .v5i;.
- va ; w.w:e%w i e 6.gaggMe. .i.h%<<pu-yewsione PON
- - ~ _ _ _ _ - _
Le
>iawe+wn.uaebAle:ws.*
hve.1wganywwege,te^:g.w.wecy.l:ww+vv.noRera em
.e._ _1_e.2Le. a
%>
- w%%ND%%*
+ "*? **
W- * .
*f-.'.".%8M/M%%'pV/.NWt.%g(.%"#.,.Y.0d.%empera
> _m m_mm__. .-m a e m_ irestored*
.m__m__.__ ureheil sW2' -n pera 7 '- ' ' ' '"do_t.8 0'0'A1.eu%%t""t.%
*%%'o(8.%"%%'A%'A'A%*'6+'1'V"M o
- tr 4
ms e
~,,, ~ee xw - ry i
m.Eera o blmed. e, a
- us;-w st.etwegy.w,ith,i m.w 24
- mou_rs' m.m r ep.,r_essut.~~re
~id.. ~w
--smemmewwi. ~~<, tan e_ventmgth-,
- m-- - s a e m_.
! W 9#.9/WsM A
-*V i .lrAMMMi,m.M-?.'6gN.krf.th A m+ S. st: l .4%@c'hQ/MAf.kr.~eac.
e, ~ m >t %O.i a of" oMC_oo ot**%b'NMW W.~._m-
.an_m A 3' 2.e&~~ oym Eh^WD*4pW em.w.6Wi.'th>.i_May.4M a.4
-mm-eurs"w
, v ~~ s+aA m aaam A. . T F.-,k n
. r 6 L, a _n o a m, .a rn a m.- .a14.af. . u. .n l. u. n e- .=m..a J, a, m r m % kl .s , +..L.a. m-.
. a ~ a + n a.
esehnt system must be deprc: urized end "cnted tc the prc::urizer 1 m,a,s, n u. c,
+ , .a a nu+
-,,n u,, . +..u... n. o m . . .,.m.. ta_ ., .
ca ,- .ymadg.g. t th7 b..~.+t-
- um .d+.w.u *a o
- - -v v.o m.www-myrww.wwwtmuds.
ow ip.u s rro~~
% ,e..v.A. p+e.eu..v-v.ra e.gre ~ .s+~m wwwml:
.e.~d+.e.%rP. &
n era esw o.eu c.wlv.mmuM. w.msamme.e6<1ss.whwva il.w.ydy sma+msw~w.was_hsm e .- ea ve s.J$*a op..wu ' wu5mc wom
..wmm.rix~++g.wo4emlzuswta:mume Feac o qcoo_an ~ _sys..em tmweugtw=mper.mvtw.wSmdv a u_re -ss ess_ _an em n hwww;f hwe+reiw+i-^ mu ww:lwueudgp
-ws,,,-
_e' - - - - _ - . - _x._- w.,s., -r, ,m ss,,< 4 R.r_e_s s_ur_i t.i za__on.m_ d, em.p. _.r_mea t_u.ee . .f_o,r,,d_h_e ns.e.r ice,sP_r_es_su._r _vm a_ esty.t~h,e,, r.~ 4 i.'WW u.ea,.c.. WA'At%W.**Np*.W.w.4'Ml"
.orgc_oo. a..nt.. :s..y.st.
WY#AY'e'
..m m.us
; - , re..p,r_es.-~.; ... .'M*M"N.
. bM.%S;(#;dWI.s'iSWA",'.V
_e.=.v. ,n.w. s.w.e_n v .- i_wsur e . - -. n "W.".Wdyn%%'Od' '@>'s'4W 1 S.m:hyy
~ i n ourS w:<m..,.m
., 2 a
yg omtnyawe a r
- 3. eivfvt.
-.e .hwwwecowwwen;gweyelv-weg w.w+twwwgi.miv_en_t49dmwewextd_e
-_ei_re_act.ogc.~oo.._ank- s.y.s . . -emt s _e sp._er. 'exNe+{^[i*c*a_t' p_e.c _ _ ^isnhwm_on .
1 j e.. ,_.m m
.~
_._mm w._ m _._m_ __.m..IOil5?A72TiWbT6EE~FihE7iithi~ f.y_ mmeliisitlWVIFTffidfWTit?6HEii
.um,. u
,__ a m
v.wneenyfsMlfdi ever.wc y:-.u.:g;. aM .,, owewghwemst.pi:tgimgenuevyci.dsyLbr s#w enn w siprov us,n.> ,..u.av.w e -we c.w.. w s.;.gy,s.u av.s. .,w ; . .bU.,pw.a www non we*d> s olw wsds.p. e . . wsanayiom yswv.s.vua.w,s6.e.1wegeui.,t..>hwyr,ve.yweeg . s).sw.,2.> ,.a.s 6.s ha.y.pn I s Acc i c - v_a S.wAlwvw.-(-
. v_e...-_a
'Axs* o.c_e._g.
<h.g4ihswt<.ydj sea e._ g_o_q _o o3.,lw,szkmsd.w;y.tsr6w:*lsurdwee>:wwyut,hmwawi+s>we>v.w3*hs++xuwd.
._ng._eno..p_en. Msy *g.pteh au<
i zwwe.i.stximowweyut, p.os onMo erwise ve c.~ -+ mheme .m - ;0 *<.kw uws.p%y...
,rww~ i f.,y.. :.ma-sw svaman dh+e.ww.way.npath. n?ki- eev v +:.ry.
am . ..., w a wayhswa.e
.-w . 4au7h awn-a2.s u.au.s,t nu.u63wam.g r +
i B. Additional Limitations i 1. When the reactor coolant system is not open to the atmosphere and the j temperature of one or both reactor coolant system cold legs is s275 F, j no more than one high pressure safety injection pump shall be j operable. The second high pressure safety injection pump shall be demonstrated inoperable whenever the temperature of one or both
~
4 reactor coolant system cold legs is $275 F by verifying that the motor I circuit breakers have been removed from their electrical power supply circuits or by verifying that the discharge valves from the high , j pressure safety injection pumps to the reactor coolant system are shut and that power is removed from their operators. i i l Unit 1 - Amendment No. 125 i Unit 2 - Amendment No. 129 15.3.15-2 January 10, 1990 1 I, .- _ -. -
- 2. A reactor coolant pump shall not be started when the reactor coolant system temperature is less than the minimum temperature for the inservice pressure test unless:
- a. There is a pressure absorbing volume in the pressurizer or in the steam generator tubes or
- b. The secondary water temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system.
Basis The Overpressurization Mitigating System consists of a diverse means of relieving pressure during periods of water solid operation and when the system temperature is below the value permitted to perform the primary system leak test. This method of water relief utilizes the pressurizer power operated relief valves (PORV's). The PORV's are made operational for low pressure relief by utilizing a dual set-point where the low pressure circuit is energized and de-energized by the operator with a keylock switch depending on plant conditions. The logic required for the low pressure setpoint is in addition to the existing PORV actuation logic and will not interfere with existing automatic or manual actuation of the PORV's. Th$10lPERAB;}UTQShelRORVsils?#s{sfijiliisdibjQtE53}jjiijddhs fDelny))ijiiiiTsl6f aWassiW11FMTili!MhBMiMBn4MieYsEEMBRDMis#35Wf3IHi5fWni During plant cooldown prior to reducing reactor coolant system temperature below the minimum temperature allowable for the inservice pressure test, the operator under administrative procedures shall place the keylock switch in the " Low Pressure" position. This action enables the Overpressure Mitigating System. The redundant PORV chanr.els shall remain enabled and operable wM4e the reaeter eeclant system i; ret open to the atmosphere and-the-temperakee-4: les; t4 tan-the sh4eum prc;;uriza'A n temperature-for the insrcrvice pressure test, except that one PORV may be cut of service for a pericd-of up to seven days. [hQyErps;ssBFs MN35}Ei oE55. jf5iUM5fE5}NdithilIEM5NENfIU}i2 1 Unit 1 - Amendment No. 45 I Unit 2 - Amendment No. 50 15.3.15-3 May 20, 1980 l l J
1 l ThKFiacf6Essbll; anti;jiitemRiid' E fiiisdiasWentiddfjihifi[iMih@pjn]Minitiji
-.,...f...v . . v ..x .f- .; - - yc . . - ,9.A..v f <<.---m e . - . . u.. . -
s.s e ...f y f.y,v. A.- ., s .f c. . o_olan tisys t.e..- re a c t..oric emjpres.sure,.oun ry; .oia vw-+.-.v b- em v.-*<da..- . pt .emo s phe.we
., .tc.w - re:;ori.v t.v 7.vp;. t ,xp..
- h. ^. 3..e;pr.e_ssurizergelj.: ..+.ef
$nRihitihis? Mis @yiljsnil@Mfim!)f;isi6fsMelihy@{sipM;ilHylei!EPORQ !%5iiis
.y - C. d..M..
5samp.,li. s"6n.<,::i...n. 6 . y ps, d. .is:giU..i. h: E..1.6d.
- c. a . v x o e.. t.a. .n.:.s.y _ pe., n.:.f.or/.rs..s.
.. - . - ~ - - y -.c-
; :.5.., .7...s...d..
st I)0RV})T6. .p.i, d..f.a x..i. ini.>l.; i. .d u 6$ppeis;UpjlssmaiipiisgaIFim6VidlpfisidFlMjjfstyHilysyiddMMitsp16Rth's FesEtbFWsisil $hsh{ thsyss;c;tiFysissliheid [hisibishidii661 tid [biRein6Vid.1 The mass input transient used to determine the PORV setpoint assumed a worse case transient of a single high pressure safety injection pump discharging to the reactor coolant system while the system is solid. Therefore, when the reactor coolant system is less than 275 F, only one high pressure safety injection pump shall be operable at any time except when the reactor coolant system is open to the atmosphere. 1 The heat input transient used to determine the PORV setpoint assumes a temperature difference between the reactor coolant system and the steam generator of 50 F. Therefore, before starting a reactor coolant pump when the reactor coolant system is solid, the operator shall insure that the secondary temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system unless a pressure absorbing volume has been verified to exist in the pressurizer or steam generator tubes. 1 Unit 1 - Amendment No. 45 Unit 2 - Amendment No. 50 15.3.15-4 May 20, 1980
TABLE 15.4.1-1 (3 ,of 4) -
. t No. Channel Description Check Calibration Test Remarks
- 24. Containment Pressure S R M** Narrow range containment pressure I
(-3.0, +3 psig excluded) +
- 25. Steam Generator Pressure S*** R M**
- 26. Turbine First Stage Pressure S** R M**
- 27. Emergency Plan Radiation Survey Q R Q Instruments
- 28. Environmental Monitors M N.A. N.A.
- 29. Overpressure Mitigating S R C6dERIFEijuWsdI6ii WDRaisths i hp pfe#
ppgra, {@ippj (j$jp apijp{yy @ ))))jj
- 30. PORV Position Indicator S R R
- 31. PORV Block Valve Position Q- R N.A. [
Indicator
- 32. Safety Valve Position M R N.A.
Indicator
- 33. PORV Operability N.A. R M Performance of a channel functional test but excluding valve operation
- 34. Subcooling Margin Monitor M .R N.A. ;
- 35. Undervoltage on 4 KV Bus N.A. R M** For Auxiliary Feedwater Pump Initiation
- 36. Auxiliary Feedwater Flow Rate See R N.A. Flow Rate indication will be checked at i Remarks. each unit startup and shutdown
- 37. Degraded 4.16 KV. Voltage S R- M**
- 38. a. Loss.of Voltage (4.16 KV) S R M** i
- b. Loss of Voltage (480 V) S R M**
. F
- 39. 4160 V Frequency N.A. R N.A.
i , Unit 1 - Amendment No. 113 April 14, 1988 Unit 2 - Amend:at No.116
TABLE 15.4.1-1 (Page 4 of 4) , i Channel No. Description Check Calibrate Test Remarks t
- 40. Containment High Range Radiation S ** R M ** Calibration to be verification of response to a source.
- 41. Containment Hydrogen Monitor D R/Q N.A. Gas Calibration - Q, Electronic Calibration R Sample gas for calibration at 2% and 6% hydrogen.
- 42. Reactor Vessel Fluid Level System M R N.A.
- 43. In-Core Thermocouple M R N.A. Calibration to be verification of response to a source.
S - Each Shift M - Monthly i D - Daily P - Prior to each startup if not done previous week. , W - Weekly R - Each Refueling interval (But not to exceed 18 months). B/W - Biweekly N.A. - Not applicable. Q - Quarterly
**Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
***During cold or refueling shutdown, a check of one pressure channel per steam generator is required when the steam generator could be pressurized.
****When used for the overpressure mitigating system each PORV shall be demonstrated operable by:
- a. Performance of a channel functional test on the PORV actuation channel, but excluding valve
, operation, within 31 days prior to entering a condition in which the PORV is required operable 1 and at least once per 31 days thereafter when the PORV is required operable.
- b. Tc; ting vclve operctica in cccordcnce with the inservice test rcquire ent cf the ASME Sciler cnd Prc;sure Vc :cl Code, Section XI.
J ! Unit 1 - Amendment No. 113 April 14, 1988 Unit 2 - Amendment No. 116 -
l TABLE 15.4.1-2 (Continued) 1 Test Freauency i
- 8. Secondary Coolant Gross Beta-gamma Weekly")
Activity or gamma isotopic analysis Iodine concentration Weekly when gross Beta-gamma activity equals or exceeds 1.2 pCi/cc (*)
- 9. Control Rods Rod drop times of all Each refueling or full length rods ") after maintenance that could affect proper functioning ")
- 10. Control Rod Partial movement of Every 2 weeks ")
all rods
- 11. Pressurizer ja \ Valves Set point Every five years ""
rm '%
- 12. Main steam Saf' Valves Set Point Every five years (")
- 13. Containment Isolation Trip Functioning Each refueling shutdown
- 14. Refueling System Interlocks Functioning Each refueling shutdown
- 15. Service Water System Functioning Each refueling shutdown
- 16. Primary System Leakage Evaluate Monthly ")
- 17. Diesel Fuel Supply Fuel inventory Daily
- 18. Turbine Stop and Governor Functioning Annually ")
Valves
- 19. Low Pressure Turbine Visual and magnetic Every five years Rotor Inspection ") particle or liquid penetrant
- 20. Boric Acid System Storage Tank Daily Temperature l
- 21. Boric Acid System Visual observation Daily '
of piping temperatures (all > 145 F)
- 22. Boric Acid Piping Heat Electrical circuit Monthly Tracing operability
- 23. PORV Block Valves si Complete Valve Cycle Quarterly ") M hMO@ @posM ijnijheski jEyiffM 72 460 $ M Unit 1 - Amendment No. 129 Page 2 of 4 October 16, 1991 I Unit 2 - Amendment No. 133
l I 1
. 1 l
TABLE 15.4.1-2 (Continued) l Imt Freauency
- 24. Integrity of Post Accident Evaluate Each refueling Recovery Systems Outside cycle Containment
- 25. Containment Purge Supply Verify valves are Monthly ")
and Exhaust Isolation Valves locked closed
- 26. Reactor Trip Breakers a. Verify independent Monthly ")
operability of automatic shunt and undervoltage trip functions.
- b. Verify independent Each refueling operability of man- shutdown ual trip to shunt and undervoltage trip functions.
l
- 27. Reactor Trip Bypass Breakers a. Verify operability Prior to of the undervoltage breaker use I trip function.
- b. Verify operability Each refueling of the shunt trip shutdown functions.
- c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip functions.
28FlPdssRO@ifedlReliiffVilyss Opsfits"" EsdiMliUfd6ssf" (PORVs), PORV4Solsii6fd7AMC6RfF61 i yalvissandJAMS.ste@lissh i 1 (1) Required only during periods of power operation. (2) E determination will be started when the gross activity analysis of a l filtered sample indicates 210pCi/cc and will be redetermined if the ' primary coolant gross radioactivity of a filtered sample increases by more than 10gCi/cc. (3) Drop test shall be conducted at rated reactor coolant f1cw. Reds shall be dropped under both cold and hot condition, but cold drop tests need not be timed. (4) Drop tests will be conducted in the hot condition for rods on which maintanance was performed. (5) As accessible without disassembly of rotor. (6) Not required during periods of refueling shutdown. (7) At least once per week during periods of refueling shutdown. Unit 1 - Amendment No. 129 Page 3 of 4 October 16, 1991 Unit 2 - Amendment No. 133
I 1 1 (8) At least three times per week (with maximum time of 72 hours between samples) during periods of refueling shutdown. (9) Not required during periods of cold or refueling shutdown. (10) Sample to be taken after a minimum of 2 EFPD and 20 days power operation since the reactor was last subcritical for 48 hours or longer. (11) An approximately equal number of valves shall be tested each refueling outage such that all valves will be tested within a five year period. If any valve fails its tests, an additional number of valves equal to the number originally tested shall be tested. If any of the additional tested valves fail, all remaining valves shall be tested. (12)'Not' Fell uir~edif th'e' bibck'valife is"' shut"t'o'isbl'ites^PORV 'that?is, in6psrabls for reasons other than excessive seat leakage; (13) Only applicable when the overpressure mitigation"syst'em'is"in ie^rvi'ce? (14) Required to be performed only if conditions will'be establish'ed';' as defin'ed'iri Specification 15.3.15, where the'PORVs'are used for low temperature overpressure protection. The test,,must be performed prior,to establish'iiii these conditionse (15)' Test valve operation' Irs'aEc' o rdan'c^e'sith'theinseiirice' t'esf riiquife'm'enti of the~' '
' ASME , Boiler and, Pressure' Vessel Code, Sectjon XIi Unit 1 - Amendment No. 129 Page 4 of 4 October 16, 1991 Unit 2 - Amendment No. 133
. .. - - .... . ..- _ - . - - -.}}