ML20128C525

Proposed Tech Spec Changes,Replacing Automatic MSIV Bypass Valve Actuators W/Manual Operators

ML20128C525
Person / Time
Site:	Comanche Peak
Issue date:	05/17/1985
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20128C482	List: ML20128C525 TXX-4479, Application to Amend CPPR-126 & CPPR-127,changing Tech Specs to Replace Automatic MSIV Bypass Valve Actuators W/Manual Operators.Changes Will Be Incorporated in Future FSAR Amend
References
NUDOCS 8505280319
Download: ML20128C525 (40)

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COMANCHE PEAK - UNIT 1 3/4 6-30 q

e

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b a.-se.

b

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sf

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CONTAINMENT SYSTEMS mie m:

1. 2.hb gf, fj'ES

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s.:.~, s JQ; f

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CONTAINMENT VENTILATION SYSTEM (Continuedf".,,QQ

':Q.J,,iM i,

u.

beforegross1_eakagefailurescoulddevelop.?O:k%The 0.60 L leakage limit o m;w.w:w w.>w.s

-,a,.4w &.

?b

!. " Tf? M i.

mm -.

...~.n

~ m.w.. w.,;;.,.~.+. m..

a y

Specification 3.6.1.2b shall not be exceeded when the leakage rates determined '

by the leakage integrity tests of these valves are added to the previously 2M.

i etermined total for all valves and penetrations subject to Type B and C testsM g

, ~," J%

myWy;W w hinu%%nr.im m^-mm q _

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3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS gi;$

g.-

3/4.6.2.'1 CONTAINMENT SPRAY SYSTEM,1ff%- M

? ?.-.

9 udThe OPERABILITY of the Containment Spray System ensures that containment Y 5

t 4

(depressurization and cooling capability will be available in the event of a f~

(-

1 LOCA or steam line break. 'The pressure reduction and resultant lower contain "

i ment leakage rate are consistent with the assumptions used in the safety i d $ 5,

. $/n M, : analyses.

.?

m 7

gj.t.

3 pio The Containment Spray System, which is composed of two redundant trains, O F

provides post-accident cooling of the containment atmosphere. -However, the w-h.

QigContainment Spray System also provides a mechanism for removing iodine from m:

m g..the containment atmosphere and therefore the time requirements for restoring 9

N A ran inoperable Spray System to OPERABLE status have been maintained consistent

.Q2<;;%with that assigned other inoperable ESF equipment.

yvg,%

+

.~

'3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the Spray Additive System ensures that sufficient NaOH

.is added to the containment spray in the event of a LOCA.

The limits on Na0H volume and concentration ensure a pH value of between 8.5 and 11.0 for the

.c

' solution recirculated within containment after a LOCA.

This pH band minimizes

.s the evolution of iodine and minimizes the effect of chloride and caustic stress

..e m #v. corrosion on mechanical systems and components.

The contained solution volume

^

, limit includes an allowance for solution not usable because of tank discharge 4

line location or other physical characteristics.

These assumptions are con-sistent with the iodine removal efficiency assumed in the safety analyses.

.}

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the

)

i event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.

Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environ-i ment will be consistent with the assumptions used in the analyses for a LOCA.

l INSE R T (g) y /4.6.4 3

COMBUSTIBLE GAS CONTROL

(-

The OPERABILITY of the equipment and systems required for the detection 1'

and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable j

1 COMANCHE PEAK - UNIT 1 B 3/4 6-3

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- e ATTACHMENT 2 CHANGES 'IO FSAR SECTIONS 1.3, 3.93, 3A 6.2, 7.3, 7.4 AND 10.3 s.e*

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FSAR SECTION 1,3 CG4PARISICN Ti 3m

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, gg.rN y

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and power conversion system.

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- -d Realth Act (OSHA) to codes and @QD WfM,( W-w t u.,m...

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of the cast stage of the los pressere.cer.,

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The following have been added to the list of events that initiate

.~,

W pc.. c.? a.,.... ;*-

'r q-vg 3

a turbine trip:

.c.

r.

l ' w*

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in=.d,.c ~..

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l

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n >-

?R* actor tr%p/,.L f.,.. _.

w l.-

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s

m vs.+;muu.

M '"

Ev.

1.

WP.;%..l-UGrydir.wi M.h.. 5#)G.i..J..

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'. Steam gen. erator h.igh-bigh levei }.h'.,T 2.

M..-

N01 c.f P F-r-P 2,& m e-rn.-

.,s 2

3.

Safety injection v m.

.J

4.

Generator trip 5.

Moisture separator high.levei (each RSR) j. ;. <3..- 4' j, s -

Excessive vibration during speet 4 r4..

6.

operation from 900 rpm.astil: unit. g,.

n.w

~~

J'

'Z

^J is synchronized.

+

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p

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q DECEMBER 10, 1982

& % S k Irdabn \\fc 6 [m s w) )

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W c,

9 9

e FSAR SECTION 3.9B MECIANICAL SYSTDiS AND COMPONENTS

r. w :n;. k e M.i.:q w,.

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CPSES/FSAR 1,..a e

+

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.,.., l.,.,c6,,,;nig:g

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(p&CTIVE AND INACTIVE PUMPS AND V A

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Main Steam Reheat and Steam Duro' System M Y"MWt M M,,.M.. M...,w 55'

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e O"AMNf 9.h.d.

b. Main $1 %$f*! W :M O.MSRTW =~uiA W NHSH

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steam' isolation bypass valves -W-2 I..ud; w*, 4 5

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.Feedwater system valves from containment

. isolation valves to the steam generators 2

A

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Safety In iection_ Systeg Safety injection system valves 2

A

• A = active; I = inactive b

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ACTIVE VALVES-

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val.VE IDLNTIF1 CATION VALVF TYPE' OR LOCATION AND SIZE SAFETY " OF

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.c..

, c w

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liv-23 3 38.

MS Globe [Hyd raul icj 4 2

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- IIV-2409 MS G1obe/ Air 2

2 Auto Irip'

,Open gM. -4 g.

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2 Remote Manual Closed

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Auto frip Open m

IIV-233aB MS Globe klydraul ic) il 2

(Auto Irlp)

Closed j 4 Containment isolation; 6 E -

pu d Ma It M

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a Containment"Isolationt 1.;.,p v: '

+'

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2 Auto Trip

s.,.

Remote Manual. Closed p {fContainment' Isolation g,'l e,

.y p

' Containment Isolation L;,: + g PV-2326 MS Globe / Air 8

2 4 e.-

q, IIV-2335A MS Globe flydraulic 32 2

Auto Irlp Open

en -

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(Auto Irtp3 Closed j

MV-2335B MS Globe flyd raul ic) 9a f '

Ji Ad Ma-.'

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2 Auto Trip

', Open y

49 Remote Manuel ~ Closed $xi~Conta i nment" I so l a t ion f;tY.E:i' '. ' O, PV-2327 MS Glohe/ Air 8

2 IIV-2336A MS Globo ItydraulIc 32 2

Auto Irlp, Open m Containment Isolation $pab,y *;V ',

CM J

G i.a.

W 4.vd

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ga J Ha a l Containment isolation:.

HV-2'J 12 MS Clube/ Air

'2 2

Auto Trip Open

.t s,,

[ IIV-2452-2 MS Clube/ Air 4

2 Auto Trip

Closed,

Containment Isalatlon M a A, h y h2 Q.,,

i{; PV-2328 MS Clohc/ Air 8

2 Remote Manual ^ Closed Q Containment.' isolation QJg Q j.. g 3.NConta inment i solation d >=.n% y D, 4f 'u' AM MV-2397 MS Globe / Air 3

2 Auto Trip

. Open y.Q

. p

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HV-2398 MS Globe / Air 3

2 Auto Trip,

open

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FSAR SECTION 3A NMENTAL QUALIFICATIQ1 REPORT 4

s e

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Certified 47'_

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Certified 3

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~ Certified

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ES100 (4 of 4)*

Terminal Blocks Certified I

7

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Airlock Electrical Penetration Assemblies Certified ~ 3.,

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MS7 Turbine Driven Auxiliary Feedwater Pump Certified 50 Control Panel b.:??.MS13 Medium Pump Motors Certifled mo.,.,

QM,9'pll MS15A RWM Pump Motors Certified il J. '"-. MS158 Sump Pump Motors Certified w..; ;

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MS15C Small and Medium Pump Motors - CW Certified T "

- MS20B Motor Operated Valves - Operator Certified

~

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Pneumatic Hydraulic Operator Certified MS208.1 (2 of 2)* Motor Operated Valves - Operator Certified MS208.2 Motor Operated Valves - Operator Certified MS208.1 (ES29)*

Motor Operated Valves - Limit Switches See ES29 MS34 (1 of 3)

Emergency Generator Certified MS34 (2 of 3)

Emergency Diesel Control Panel Certified MS34 (3 of 3)

Emergency Generator Control Panel Certified MS76 (1 of 3)

Deleted 52 l

MS76 (2 of 3)

MSIV's - Bypass Operator Certified j MS76 (3 of 3)

MSIV's - Rockwell Operator Certified 49 AMENDMENT 52

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switches (one per loop).

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actuated will isolate one of.nthe main steam lines.~7In additi.on, t. here

r. ~.

9;.m W/'

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. # M.,@.

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E ac.m etuation main control board mounted switches provides for actuation of m

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@the components required for reactor protection and mitigation of ig:'.

,,.n n.gn r e.

g gadverse consequences of the postulated accident, including delayed

.w.gl.

e a ~

m$,W tc$y, m

$ deactuation of sequenced started emergency electrical loads as.well as g g &,)<

l.

M tMV; comp'onents providing switchover from the safety injection mode to the W *s

~

%:; 9..

Q' e G.~-

.m

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w.

4;n v,c/ cold leg recirculation mode following a loss of primary coolant liq.,g,c.~,ccident.. Therefore, once safety injection is initiated, those

. ga s

~

y.

e M' "

• components of the Emergency Core Cooling System (see Section 6.3) which 4;m..nq,'i

.h' are automatically realigned as part of the semiautomatic switchover go

.-?

.. o.w2 wh36 to completion on low-low refueling water storage tank (RWST) water

[

4

..n m e

.N.,t(..y/N: level without any manual action. Manual operation of other components

• *v.

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c

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'NI.,'icprocedures is not precluded nor othenvise in conflict with the above HI 96 ' [ described compliance to Section 4.17 of IEEE Standard 279-1971 of the a

semiautomatic switchover circuits.

No exception to the requirements of IEEE Standard 279-1971 has been taken in the manual initiation circuit of safety injection.

Al though Section 4.17 of IEEE Standard 279-1971 requires that a single failure within common portions of the protective system shall not defeat the protective action by manual or automatic means, the standard does not specifically preclude the sharing of initiated circuitry logic between automatic and manual functions.

It is true that the manual safety

'h AMENOMENT 36 DECEMBER 10, 1982

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> +>W.?e h :Fr,w.ui.w;.

,.n.

N w np.g - 'V

, p p.:c m

NOa.v s,

. m A.

a,

....., +.

w

..v "#N,.

2 s

. a m#,

1 q, u,n <3.

_. g& m n(E N;.,> " Manua c

. ng mam.

.~

-..y..,

Nptp;f,.d:

wgwvW whu.21;e..; e.t?.c Oy&:5 Y

W c

.%4p;w..

A.+ m> w. o....w.

~

c.,.

x,. nw.m.

e

.u.v....

s

. ~

l,J.M3. $Feedwater line ' isolation

~

".69 Q$5k%%%>bMerbNa::% tn.fli R Q Y.H & B k W W. M Gb:djN N.

..:..dln o. Jw

di W Md.?;:

.e n. A m w n w.m! 4 % :w w.:

ww

>. > ~.e.%.ws%

,s %n.M6,I.'/,pa.'M Safety injection ME.h. MSSee item 1 of Table 7.3-1 MNN$

- u-wa

~

s.,,w m.. n....,y. snsg.n w

s,.. u. f.. a e p,.r.

u. w..,so aw,s.n. t

., S &v.; -

, W.

,SB. s x,~r %e w. -

'.m s

.:.<tw u 12(3/ Steam generator) 2 in any one M.w.,jk.a.,h.n ~W..t'

+.s..b.

Steam generator d.

gg;u.rne >e..

gh-h gh.sevel Steam generator a -

w e g m N g':$N,h! $ ;- 2 2/3 on any steam

.M, rmi fM..:$.u k

~

v,e

-~

.pp e4

!! v4 7 ng'-%.~t.Jup' ',.,J,, generator w,

- M9 "f

.L;$kiMf,r,Q L j'.a m ;...

i.

e-

• 1..

Q$.lfM.4%;,.;h.FTfu

-4' Ql9D J,ff.i;y & R r.,'.'. e.c...

avg (Average See Fig. 7.2-1 See Figure 7.2-1 Low T

.....a.,w

f. u$.$Qis.f..f :.7 * / '-

Temperature)

Sh. 2, 5 & 13 Sh. 2, 5 & 13 s

W 6, ';,

Coincident with

.~m

"~

Reactor Trip

+ %. -.v...

a..\\;9.r,...

w.. w. w,. m.

q m 4fge.u.@.v :

1 y;4,.w.;

w

.. v.,...

. s., w

<..~

u.. a =.

.,;.y f.

~

". % l. +;.%

u u.,:. ~

Additionally there is a switch for each loop that will actuate the mainsteam isolation @nd bypass) valve # for its respective loop.

N AMEN 0 MENT 13 UECEMBER 15, 1980 q

f g.4 k

.l

0 y

e-FSAR SECTION 7.4 SYSTEMS REQUIRED FOR SAFE SHUIDG4N w

1

.y. ~ x ;[.:.

v-4.!;.

@.g.,.(.gw'j.

i. A ed ila.h. r

. t.

w o - m.q7. v c p f t...

- CPSES/FSAR @D

?,L

4. ' QRh,h%,."

y;? h.y

. : TABLE 7.4-l.'4.c..

[ i.n. _d,.

.s 6 FA

v..:a w.'yc:= /.n. (Sheet.3) Qpgr.;..

q,g5;

! L:-;i t

% :s i Q d4 z ;.. w

~-

p4.t;. ":

~:m;ic.is.;now n g w,~a, p.

%=.

-~

JhddWiT ;'31 CINSTRUENTATION AND CONTROL 9

/'

.s

~ '

LOCATED ON HOT SHUTDOWN PANEL -';;:hc,;

SN ih.^TE

[

~ ",/Mc%N.Ml/9sd9;lWDVIDEUTOR HOT STANDBY (1)

Rad?Wd 'Fm.h dN'2

Identification &Q&(.yf.pg47.;... > m.9~gf. ~ ~- ~

f

. X%5,'e

+ ::;n 3tN$

- gt g Function,%d u f;j:%]c '.g -

p t

,1/1.8801AF r.~,, e/c.g.;...#rw.. cin.:nM ww.v a m.;,;by

. - dan:p ^^ -

Q

.(A. ).. Charging pumps to Reactor Coolant System SIS

%m.g A

yv. g%e -

.,...m.'

x.

M N

w < TRANSFER hWITCHES LOC TED OiSHU

'.N' Nhf.

1 gNM Mg nfyTRANSFER PANEL (STP)

n. w Q

Function (gg;:.lyg :f.

zQ(h;,r

~45 ~w. ;g;p. :4.Le.yxh;.

n

Identification egy

g c..cy,

', m,,, 7 3.g

.y,

' 3/1-8106FT. 9,; Q.)L?? y m g;pf, waa:a. w.vi d.'M 4 *k) V F

' Q.Q l}

o

,s.

am (A) Charging pumps '.o Reactor Coolant System

@M M;>f.:

.1

?p

-" d,$ h y 2 N[ ((..,I.i,!.g' isolation valve unote local.

~ ~4. :

~.2 i

. c ;..

a w :+ ;p n p n. n v:

> o %,%'

s o

..n

,W i

443/1-8801AF W pt (A) Charging pumps to Reactor Coolant System SIS

?

$ *' t y' " # '~, g.E. q

F. M

• Wisolation valve remote local

~

M p es.Kr

. % W.... -

g43/1-8149AL h.p gp g.y.e: @ ie.iQ'&G(A).CYCS letdown orifice isolation valve rem

'id e,<

.g ww)p.m.QMEiNM,,QQW61ocal4:ai.FM. g, upe..q.7'@'.%kfMe W

'RT(h;)7"

,4

<.v r g W ;" r. w t e t h r -

. d;w,e F

g' W o w,.,

~

(A) CVCS letdown orifice isolation valve remote

'l n.et.

L 7.4%.m. +o.:n,,n+s.W43/1-81498L.

~;

+1+

<kf w..; :

q e,x g 1oca1 m;e, e.s1w y rr.

.~

g @h @':;nir;;m.g --

+

w-a m

443/1-8149CL x,

- -(A) CYCS letdown orifice isolation valve remote a;

-y

.y : v e~.F ~ -

local

~

m :.y'Y3c;.*;% %'.:!:-

.i p r

'.n

% f.

ry is :-

9[27 W b'0 Q.0;43/1-8110FT

. w y #. %.

(A) Charging pump miniflow isolation valve remote

w. '. % % g., 1' 1

local C

p.:.;. - H.y. : 43/1-APRH1F (A) RHR pump-1 remote local 5;

.n-

.'.....y

-43/1-8701AF (A) RHR loop 1 inlet isolation valve remote local

, m. ;7 -

'43/1-8701BF (A) RHR loop 2 inlet isolation valve remote local HS-2452B Turbine-driven AFWP steam supply header 31

.'S valve remote local 4,..

'43/1-TCV-129 Letdown to demineralizer or volume control tank remote local 9~'

HS-2333FT (A) Main Steam loop 1 isolation knd bypass valve j

remote local P

HS-2334FT (A) Main Steam loop 2 isolation [nd bypassjvalve[

remote local c-HS-2335FT (A) Main Steam loop 3 isolation (and bypassjvalve,s a

remote local

\\

J2 -

I o'

r

}

HS-2336FT (A) Main Steam loop 4 isolation and bypassjvalvey t

remote local 43/1-455 AFT (A)

Pressurizer power relief valve remote local 43/1-PCPRIL (A)

Pressurizer heater backup group-A remote local HS-XT (A) Water chiller ontrol remote local AMENDMENT 52 AUGUST 27, 1984

e g

FSAR SECTION 10.3 n\\1N STEAM SUPPLY SYSTEM

3 CPSES/FSAR

=

3 s.

f-g' r. ;.g: W,

Valve 4

iM.,W,5.n AT.he valves fail closed on loss of air or ele

$l, 4

,u

' N;.;.,

.,s.y;

'N4

• M Ou d, allure of the relief valves to open causes the system pressure

,,.n. e,p.

' * ~ '.4 J.

h to the set point of the first safety valve, which would then open, 4.,..

t

,...:v.w, e

- ' e W. c $

The power-operated -

reventing further pressuriiation of the system.

~.,

2,.a 9 a.m

~

/

creli,ef. valves do not provide, main steam supply system overpressure

' W N:

7,.,Q

..>. n e ylj.gl,

C protection.

• This overpressure protection is provided entirely by the' *>r,

u.... #

.t 9

Valves are designed to pass ij, Psafety valve system described previously.

y.:,.m..

u..#

D@Mygy.ma total flow of 10 percent of the plant design flow at the pressure, }.$,

?

The maximum

. r7eiponding'to steam generator no-load conditions.

Trecapacity of any one valve does not exceed the flew rate (specified by.

. u,,7 g j

4;p. -

. - ;.c3.g ;

if the steam generator manufacturer) at the design pressure of the main

WC

~.

2

.., n.

' m. ce-ham supply system in ' order to limit reactivity insertion caused by

$@@G;t.Ethe negative temperature' coefficient of the core.

)

I.1

'~

' Dhi.~'N, 'dl.The valves discharge to the atmosphere and are designed to o Each valve inlet pipe is

- -the steam pressure range of 125 to 1300 psia.

L iyv.

.v.

3.. c;R, ' '...y 1 W M(. si J;pr_ovided with one manual isolation valve for maintenance.

an o

. f l'

T_

~

.s x ;

~h; 495..iN.$ Table"10.i -3'showEt$mdpTfin. bases of the..

'~

.c-3

. Uww.i yyCp

. ;ggys;.

g$,

Main Steam Isokation Valves 10.3.2.3

. p.. 1.. m

_n

p u 10.3.2.3.1 General Each main steam line is provided with a quick-acting isolation valve.

a.

and is designed to stop flow from either direction Fithin 10 sej~ after a steam line break (five sec after receiving the closing signal) to prevent uncontrolled steam release from more than one steam generator.

The valves are installed outside the Containment, downstream of the safety valves, and are provided with an integral 4-in. bypass valve for waming the system and equalizing the pressure across the isolation i

2 The bypass valve is 21so designed to stop flow from either]

valve.

Coeked d s ool. M 3 pev.en.

10.3-7

~.

b= we

.. = _

CFSES/FSAR i r.;3., n. ~.,,

s s!!.Q:%QR

- A

-N

h. W

.., ~.

. ~

/--

...a M.n.hh f

&.-+...

u AW,i%p

,,, 9~.

w.<. M..

y

h*

y]D*T The MSIVs can be opened manually by the operator in the

1. N

~

irection).

^ '

"'ntrol Room' $thout opening the bypass ' valve. TTA j.

r

~

?.y,

f..v.:!;dNQ@.;g:$.{jl$,.{g

,m n

f

,. m

1. 1 ach MSIV is provided with a two-train module, three-position control s m..

9 The switch'has an' electrical } W::

sw tch mounted on the main control board.#

.w-

....s. n

.. w.,:.

wo-train module so that' valves can be closed "even

. J~

m-

u...

& NC.

$1he three switch positions are close, auto,' 'and open,'with spring

' 1 v,r.,.

n.9 ".

& J,M eturn to auto position. Each MSIV also' has a two-train module test

m-qy $

.i

.Or i

witch to enable a valve to be closed to a 10 percent-closed position w

.m p.w..

e...,

. +..

w

, ww,..

P en tested.'y,, addition to these control board inounted switches, v.,..,,,

In

. b.:g Ne. :.

~

m<w

' ' at,A ?:. '.. -

here is a two-train module trip switch which can be used to trip all'.-g a

w.,

y U

" j,y 9' if(ur,MSIVs, simultaneously., Trip switch positions are trip and auto, j

.m. :.

. i.,.

@y &

lM.yAithspringreturnt'oauto.

lg i

w

^

ty Spy %pif $, ' ^kSIV bypass valve also has a two-train modu hif

$f7N

~

auto $itchonthecontrol, board. The MSIV's(and bypass valvesJaro J.$M ph

~'

tautomatically closed on high-high containment pressure or steamline gt13 2.'.

1 3%reak protection logic (as/ ndicated by high steam pressure, rate o 4 9 QO32.79 i

.+;.,_..

a%%.5.:n. i./.

.High steam pressure rate is only; effective whe gn

/

v. &

%)6amline pressure).u :

.'ip3.MTT.L.

.qy.

Missteamline $1 is manually blocked during startup and cooiT. _;, d loi

., lw.u '

~

.~

~::.-.

-~ :

own; an r -i ;~ ~ -

• / W

,,,.,._1 steamline pressure is only effective when the block is renoved (see v.

4

. n.. m.s.u. E 'D Figure 7.2-1 sheet 7). The MSIV's are closed by operation of the MSIV V. :..,.

.A

?

u

.Ujc

~ ' & J ;./. !

e ' 5,f The actuator is, in effect, a hydraulic cylinder -

valve actuators.

..,3 6 The accumulator is'

.^

y coupled directly to a nitro' gen-accunulator.

f l?

designed as a chamber concentric to the hydraulic cylinder, and it

., ),

' ' " ~

stores the energy required for closing the MSIV in the fonn of s

Because the accunulator is integral part of compressed nitrogen gas.

the cylinder, the loss of any external manifolding or system elener.ts A hydraulic will not prevent the actuator from closing the valve.

20 Q212.139 control systen which maintains hydraulic fluid below the valve actuator Exter.sion of piston is utilized to regulate valve closure velocity.

the actuator to close the MSIV is accomplished by an electric signal which operates two solenoid valves in the hydraulic control system These valves pennit the hydre.ulic fluid below portion of the actuator.

1 a

e JUNE 12, 1981 10.3-8 e.

p-gn, g4,

CPSES/FSAR

. ~:

-n J.i 5. qAy.'-s.

• . 4"O.MQ -

nW:

,a

)mm.f;#.Tth'e' actuator piston to flow into a' hydraulic reservoir at a controlled

'N b 14

?

TKwrs.m sy A

d

?g j: ' y., ate as the compressed nitrogen extends the actuator to close the MSIV.

T.'"gh f

f

1. X$$...&& i~p.'

~4,.

. ':.c

, )l'.

,ygy;y:4cw:,.W. A.W,gp-

.1 g

Ea,.ch component of the hydraulic control system whose presence or

' gfd T

function is required to effect the fail-safe extension of the actuator

%, q.3d. 2

.sm.m e. ~......

-e 9

39g.+

ww.w,.

m.

.., syedundant with alsecond component capable of performing the required r.

unction regardless of the state of operation or failure of the other.

%g,;

4 u w.. --

20 g A F$'., wo hydraulic control system manifolds are provided, each of which is e

Q212.139

~li w.,

u apable of providing valve closure capability independently of the

" ~

w,. m... :. -, w., o. -... -.,.. u.:,,.

,4.

4 other.*The MSIV fails closed on a loss of hydraulic fluid.

w.. e u

)

4%A"W.Tq$WtiW 7;#);4 7 '~ 46 yf sib.

p yl

• ig}Ir.w}

-m

..g.

m 1

g '?QJ:),jThe same signal that trips closed the MSIV closes the bypass valves by i

f c$.Qp.14deenergizing redundant. solenoids on the bypass valve operator hydraulic )

re

.m ft@n. -

~

+: n

c...-

1

&!klGR? system.

QukhL -

2$1k? [$The ' initiation and control of main steam isolation is redundant and

,/.s.. %.. [N,,a I f.l electrically and' physically separated. There is no single failure in

<3.'

the initiation and control portions of the system that will prevent a 6

QO32.43 j;" main steam isolation" signal from arriving at its destination.

c-A main steam isolation signal will close the MSIVs $id the bypass) g

l

. Cva1ves 2 *--

, L:. a..

A main steam isolation signal will also isolate the flow from the drain pots upstream of the MSIVs associated with each steam line. These 4

valves have two train inputs so that valves can be closed even if one 14 train fails and also fail closed on either loss at electric signal or QO32.43 air failure.

(See Section 10.3.2.7).

QO32.74 Folicwing a main steam isolation signal, the main turbine will trip on either redundant reactor trip or turbine trip signals, and the closed turbine stop valves will serve as a backup to the MSIVs. Thus, in the

. event of a failure of a MSIV to close, main steam will still be isolated. There will be an insignificant loss of steam through the 10.3-8a JUNE 12, 1981

CPSES/FSAR y w..

~ -.,

~

,t _ _,, 7.

. -,.3.

.h...,m.N solenoid in the hydraulic circuit as well as energizing the

- };fj;.%

)4

.. w -

Mnkhhtrip-close solenoid.. An automatic MSIV trip-closi signal overrides the - ['

n(ily31{

3-

.e***

Wtest signal,and closes the valve quickly. -

.y e

n, k-h'$.'.

i::.'.Shi <.

~>L, l

/

}

?

ere is no provision for testing the bypass-valves.

' ' T -

M k.%

9 ~;

3.,'

weg f;.pM@::::i:.%W@v %plb hWi 5

{

%[k ~?

L yWr

' N; 9 Alarms are actuated when MSIVs 'have low hydraulic oil pressure or low m.

m.

%~-

.s,.w... -

-EDYW 7

actuator gas pressure. 'Each valve has position-indication lights on y

h?

-i o mn a

There are

[ $.$n monitor lights which light on valve-closed position.djthe main co U

..c-p

-, V h -

.d.:

94f%.%Q%QeW4+g.yc -3n; % M N(y; q W i +.

y;yM.~ ::

, p. g. g...

'f.

.. c.

}

$..J @.

l f

9E n y. m:3.2.Jhe automatically operated MSIVs serve on y a sa ety function and are~ 'x we.m ry e

They are required to limit J Jf,-l+

$fd5 J.bg."c.M.~.g:not required for power operation.

/

.c @$..,.

Em %

=

/

4d; TJa-@c.2..M.-_!un.'c~ontrolled flow of steam from the steam generators in the event. of a

... w; y...

M w%@gp;g.cQbreak in the piping system. These valves operate under the following M

yn M,6 69f'i.P. situations:

M. b@y.:

.s

",, {..

m M.

~2 n;..oa,,

./

r l.[f"N, ~y y '

~

c: e.::

t F

~

i' 1.

Break in the Steam Line'from One Steam Generator Inside the.

f]

- h

{7 Containment Building 4'

$?:~$.

ik. 1.%.

b$d.?.:i;?,:b:dk.

Nl-l.

.s

...e-..

. -If,the break.is within the Containment, steam is disctfatged into M f_

".. m

-r.m t. w.u. r..

- -m the Containment. The other steam generators act to feed steam through the interconnecting header into the broken line and then

~

into. the Containment. A steam line break results in a l

significant pressure rise in the Containment so that reverse flow

/

protection is necessary to prevent discharge of more than one steam generator. According to calculations, reverse flow must be

- interrupted $Tthin 10 seNo limit the Containment pressure rise to an amount below design pressure. To achieve this, the automatic isolating valves close within five sec from receipt of the initiating signal. Closure of these valv::s allows for a single failure of an active component.

10.3-9

/

J

,J ) -

CPSES/FSAR

. '... y.:c

.....y*

vs

.;w

.o r

)?

~

~

.,. 6,.. 9, $.' S'h ) t.,e 2. ?N.. sreak in the Steam Line outside containment s

.y._.

'm$.h 4

, i%r+L..$

J.

k5hihm.om the Isolation Valve d ff fr e

y y e.

m:

. "g M g~ M ;3 ' a -

t$

..u..c._

j f'r.:

u b

4.;

l In this case, Containment Building pressurization is not.a i

h~g 1

yx, ~ sn' However, the uncontrolled blowdown of more than one

~s.

^

concern. <

rbtq'r must be prevented. 'Thehs c valve ckosure time s

established previously satisfies the requirements for this

. ?.'

" *j

.d

.=

L

~,., & Xtsituation.,97+0

..e - X -

a, 4

~'

. %u % t M t: -.

s :,

.k a sp,;gy.

1

+

n.d:n

?

R-@, ' -

I4. 9.:M Break in the Steam Line or Header Downstream of the Isolation

'y

~

m pM&

. n s> p..

. n..

u.,

al ve"FM N ' / f W,s...Xtw W ~. - -

w c.

W n

,d 4 f,...c. : ' r..;; *

~

c1';, uv;4!df$* <W~ %+:' k;!,h*rK h %. P11 v-3fh3; I:55%

' U.S A.-

1. ~

, lh@ )

~

f

.ON?St dys@klyb kf5&jgThe im J-'~~

e-}]Ki@yf 0 se closure time established previously meets the

.Q.ls%g,jsR 'W$.

w u,

requirements "for this situation.

y.

d W. nk.w.w W P, li?

d53N.d%NN%

$?NNy.xa.N$c., ~,.

:. A.

t

..sh E.

4 7 5 team Generator Tube Rupture m

1 n%.w,w..%,f.m=.

. X

... ~

,^

up.ptrat; 2M + >.

u..

. ei.. ~ +

M 4R. M,..V. V.- " yin this case, a fast-acting valve closure is not required..The i

s.w w

.

. w/ w/

3 A 4/

isolation valves limite pr'imary coolant. leakage during shutdown by s:

t

/

nn];J..

~

7 after.the primary system,

• 3. '.iCf,h.M. C..,i.solating the d.amaged steam, generato p

n'

. a..

.'-"*.ML.OM&f ressure is Yeduced beiow the~ steam generator shell-si4 design pressure.

. ~@ :..

0. :

10.3.2.3.2 MSIV, Design Requirements I

/

1.

Analysis of Accident Conditions The MSIVs are designed to withstand the conditions created by a large steam line break on either side of them. The valves are designed to withstand the effects of high mass flow rate, moisture carryover, and high fluid velocity. These valves have a controlled speed of closure. The surge pressure caused by the dynamic effect of valve closure does not affect the pressure boundary, in accordance with the calculation of ASME 8&PV Code, 10.3-10 f

.-----,,n.,

..n p - -,

?

x..

CPSES/FSAP,

..v...?

=

. T;..

...a

. b. j y e

.. o.,.E g.

..:..,0.,

m, a%E.*y. s A.';,y.,n

.. w..m._gM d. -

~

,u

.%4;%

-g Closing Rate Test 3'

. ;w;g t.;.

r w p

n. % % m% M M w q a u p:. '

. g

-M

.c

,' h Y)'

h ~J$nk h&f

.,-}e : (~.% M,4,'hf'i*4

?"

?Y b ' ?The conplete valve.?,., ssenbly is tested to ensure thal the I

? " w3 a

%' ~ w-JL

= y..

4 h CM W W 51osing' time is le'ss than five sec.

M.n T@J %@

2 y;q$gr %.=u ~7. n %>,,;?/f H n '.' q:. W~.g y.

m.

..,W y

J.

j r^k

%NM y

ggg. v g y.

m

.Q 4m a.,

@N3 -

n.~d W;.g,widu. h.w$.. y[gleakage 5f.'

m.

u.

2..e 1 4

T r a ts.fJ >

> '.NU.

a.

.u-g.'@W&e 9

+

c..~..

.m.

1

,t

• i E I.'y f

L

[

f%pg - h '

Y*~ O #C.I + ' ~ % ".

s,.

• vc.%,#.cP:1.The valve disc and seat materials are such that valve wear does

'.7,,fh h/

sC o

c-

~

'c.! M g v T

.WMM/.Nu,.mdYnot increase the leakage rate after a minimtsn of 500 cycles onder, ' 3,43*w?,;

fl.;

%$hIonnal iipeNting condition's.

~ j@5y.

O

'[j k.,M Q

hhh~ w.+.-N U M f'A.

a m...

s

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7

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dlN

-f& d,?p, p -

~ fn 2.2T%,; s....,&.%w. ;. ~

.W aqj-0 n.m#.m o tW 10.3.2'.4 : Main Steam Isolation Bypass Valves

.~. v'y

,3

~

grn:.

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25 w

. The MSIVs are provided with 4-ir!. bypass valves which are normally

~'

cl osed.

If the bypass valves were open they would tend to negate the

~

' protection provided by the MSIVs. Therefore, the valves (close within]

five sec of receipt of the closure signal.hTable 10.3-5 shows the design bases for the main steam isolation bypass valves, b

f cw. keltuL GAcAnd-10.3.2.5 Flow Restrictors i(hnd powa cbAAtle"-)

o Each stema generator is provided with flow restrictors which are located inside the steam generator outlet nozzle.

These restrictors (several venturis arranged in a bundle) limit the stean fluw rate in the event of a steam line rupture.

These restrictors also miniuize the thrust force effects on the steam generator and piping system.

The design basis, description, and test and inspections are included in Section 5.4.4.

13

(-

AMENDMENT 13 10.3-15 DECEMBER 15, 1980

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(

Table 14.2-2 (Sheet 50 of 60)

MAIN STEAM AND FEEDWATER ISOLATION VALVES TEST

SUMMARY

OBJECTIVE

, To demonstrate the operability of the main steam and feedwater l isolation valves including their capability to close automatically as required.

PREREQUISITES 1.

Plant conditions are established as necessary for test perfomance.

~

2.

Equipment is available to measure the closure time of the

.(

isolation valves.

TEST METHOD 1.

Demonstrate local an o eration of the main steam isolation valves

' bypass valves nd the feedwater isolation I#di valves.

P 2.

Verify that the isolation valves hypassvalve will close upon receipt of an isolation signal.

c/e/e/<

ypas54/-t[b

~

3.

Measure the closure time of the isolation valves nd

'fQ to ensure they close within the maximum and minimum time Q 23.12 section 23 required.

deld<

Verifythattheisolationvalveshbypassvalvhwillclose 4 '.

6 upon receipt of an isolation signal foi a minimum of 30 minutes Q423.12 section 18

{

while isolated from the Instrument Air System.

AMENDMENT 6 MAY 31, 1979

p

CPSES/FSAR 4-Table 14.2-2 (Sheet 50A of 60)

ACCEPTANCE CRITERIA de/<h i

The main ' steam and feedwater isolation valves (hss val respond 6

properly to remote and local operation and close upon receipt of an Q423.11 isolation signal. Valve closure times meet Technical Specification requirements.

i a

i-t' l'

AMENDMENT 6 MAY 31, 1979

(_

N Y

k) r'.

TABLE 15.1-2 (Sheet 3 of 4)

Short Term (Required for Mitigation of Accident) llot Standby Required for Cooldown Circuits and/or equipment required to trip the main feedwater pumps.

Main feedwater isolation valves (trip closed 3

m feature).

R Y

Main steam line stop valves (trip closed feature).

Main steam line stop valve bypass valves (trip closed g/e[c[-c feature).

Steam generator blowdown isolation valves (automatic closure feature).

.